ML18066A416

From kanterella
Jump to navigation Jump to search
Rev 4 to COLR, for Palisades Nuclear Plant
ML18066A416
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/01/1999
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18066A415 List:
References
NUDOCS 9903250351
Download: ML18066A416 (11)
v • d • e


Text

Palisades COLR Revision 4 Date 4-1-99 PALISADES NUCLEAR PLANT TITLE: CORE OPERATING LIMITS REPORT Preparef I( Date Technical Reviewer bate rl(L /~

PRCl Reviewed Date Reference #

I Nuclear Engineering Supervisor Approval Date 9903250351 990318,...,

PDR ADOCK 05000255

-~ __ _ _ _ __ _ _ .. PD~ _ __ ____ _

Palisades COLR Revision 4 Page 1 of 10 Consumers Power Company Docket No. 50-255 License No. DPR-20 Core Operating Limits Report 1 .0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Palisades has been prepared in accordance with the requirements of Technical Specification 6.6.5. The Technical Specifications affected by this report are listed below:

Se~tiQD TIM .crs. .{lifil 2.1 ASI Limits for Tinlet Function 3.1.1 3.2.4 2.2 Regulating Group Insertion Limits 3.10.5 3.1.6 2.3 Linear Heat Rate (LHR) Limits 3.23.1 3;2.1 2.4 Radial Peaking Factor Limits 3.23.2 3.2.2 NOTE:

Any procedure or document previously referencing the Technical Specifications for any operating limit that has been moved to the COLA should be viewed as referencing the COLA until the applicable procedures or documents are revised.

Palisades COLR Revision 4 Page 2 of 10 2.0 OPERATING LIMITS

  • 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 NRC-approved methodologies specified in Section 3.0.

2.1 ASI Limits for Tintet Function CTS - 3.1.1 {ITS -3.2.4}

The ASI limit for the Tintet function is shown in Figure 2.1.

1.2 1.1

.. 1.0 Unacceptable GI

~

0 0.9 Operation i a.

'O 0.8 Ill Acceptable Operation I a: 0.7 0 0.6 r c

0. 0.5 I

I

~ I u

I! 0.4 I u.

0.3 0.2

--0.600 --0.400 --0.200 0.000 0.200 0.400 Axial Shape Index Figure 2.1 - ASI Limit for Tinlet Function

  • Break Points:

-0.550, 0.250

-0.300, 0.700

-0.080, 1.000

-0.080, 1.080

+0.400, 1.080

+0.400, 0.250

Palisades COLR Revision 4 Page 3 of 10 2.2 Regulating Group Insertion Limits CTS - 3.10.5 {ITS -3.1.6}

a. To implement the limits on shutdown margin, individual rod worth and hot channel factors, the limits on control rod regulating group insertion shall be established as shown on Figure 2.2.
b. The sequence of withdrawal of the regulating groups shall be 1, 2, 3, 4.
c. An overlap of control banks in excess of 40% shall not be permitted.
d. 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 ..

Palisades COLR Revision 4 Page 4 of 10 MAJl..iN POWEi LEVEL

~ qo1--~~..,___---___;:~~~-+~~--r-~~--r-~~-+~~--1~~--1

-: ~1~------i------+--~-----'~~--+------+------+------+---~

i201---_._~-+-~~~~~.._~~--+~-+-~-+-~

! 101---~~~,~~-+~~-+~~-+~~~~~,......~-+-~~-+-~~~

~ O'--~~~i~~-'-~~-'-~~-'-~~-'-~~--"""~~--'~~~

.. o 20 llO Fu'\ eo ao 100 o 20 aROy qo

&ROUP \31 g...---;i----J,1----6b,____Jo.,.._-ffi-...,do

~IHROL ROD IMSERTIOle, PERCEMT GROUP @

~Ult PUN, OP£1tATIOle 901---~~1-+~~t--~---ii--~~t--~~t--~~t-~~-t--~~-1--1 i aoi--~--1-........~-1-----1-------t~---t------t-----1----~~

~ 701--~~1--~~+--:a..o:--ir--~~+--~~1--~~+-~~+-~~~

N ..................

. &01---~~1--~~t--~---ii--~~"'-t-~~-t-~~-t-~~-+~~--+-t i :~~+-~-+-~-+-~--+-""-....-+-~--+~~~~.-..!

.. "- 11 j

~ 301--~~1--~~1--~--1r--~~+--~~f"'olll::--~t-~~t-~~~

i 201--~~l--~~1--~--1r--~~+--~~1--............... ~.....;;:i~~~+-~~+-!

101--~~l--~--1--~--11--~~1--~~l--~~+-~~~r-~+4

~

~.._

20 ~ ~ ~ 100 ~ 20 GROUP IM)

Gi!OU, @ 1 I I I I @,

0 20 ~ GROUP 60 80 100 COMTIIOL llOO INSERTION. PEi!CEllT (!>

Figure 2.2 Power Dependent Control Rod Insertion Limits

Palisades COLR Revision 4 -

Page 5 of 10 2.3 Linear Heat Rate (LHR) Limits CTS - 3.23.1 {ITS -3.2.1}

The LHR in the peak powered fuel rod shall not exceed the following:

Where:

LHRTs = Maximum allowable LHR shown in Table 2.1.

Allowable LHR as a function of peak power location shown in Figure 2.3.

Table 2.1 - Linear Heat Rate Limit

-l~l=========Pe=a=k=R=od====================1=5=.2=8=(=kW==/f=t)======::::::!Jll 1,2 . - - - - - - - - - - - - - - - - - - - - - - - ,

Unacceptable

-~

u Operation

c

..J (0,60, 1,00) a: E 3 e 1-0 . . - - - - - - - - - - - - - -

~i

~ 0 0,9 (1-00, 0,93)

~

n a Acceptable Operation I!

!!:. 0,8 0,7 '---'--~~....___ _ _ _.....___~----~....___--___,

0,0 0,2 0-4 Q_6 0,8 1-0 Fraction of Active Fuel Height Figure 2.3 - Allowable LHR as a Function of Peak Power Location

Palisades COLR Revision 4 Page 6 of 10 2.4 Radial Peaking Factor Limits CTS - 3.23.2 {ITS -3.2.2}

The radial peaking factor shall not exceed the following:

for P 2.. 0.5 TS F,=F, x[1.0 +0.3x(1 -P)]

and for P < 0.5, TS F,=F, x1.15 Where:

A T F, = Measured F, or F, ,

. FA FT

= Maximum allowable r or r (Table 2.2),

p = Fraction of rated power.

TS Table 2.2 - Peaking Factor Limits, F, Peaking Factor Reload M Reload N Reload 0 & Later A

Assembly F, 1.57 1.66 1.76 T

Peak Rod F, 1.92 1.92 2.04

Palisades COLR Revision 4 Page 7 of 10 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 XN-75-27(A) and Supplements 1 through 5, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Report and Suppl~ment 1 dated April 1977, Supplement 2 dated December 1980, Supplement 3 dated September 1981 (P), Supplement 4 dated December 1986 (P), and Supplement 5 dated February 1987(P).

3.2 ANF-84-73 Revision 5 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events,"

Advanced Nuclear Fuels, July 1990.

3.3 XN-NF-82-21 (P)(A) Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.

3.4 ANF-84-93(P)(A) and Supplement 1, "Steamline Break Methodology for PWRs,"

Advanced Nuclear Fuels Corporation, March 1989.

3.5 XN-75-32(P)(A) Supplements 1 through 4 of "Computational Procedure for

!:valuating Fuel Rod Bowing," Exxon Nuclear Company, October 1983. (Base document not approved.)

  • Palisades COLR Revision 4 Page 8 of 10 3.6 EXEM PWR Large Break LOCA Evaluation Model as defined by:

XN-NF-82-20(P)(A) Revision 1 Supplement 2, "Exxon Nuclear Company Evaluation Model EXEM/PWR ECCS Model Updates," Exxon Nuclear Company, February 1985.

XN-NF-82-20(P)(A) Revision 1 and Supplements 1, 3 and 4, "Exxon Nuclear 11 Company Evaluation Model EXEM/PWR ECCS Model Updates, Advanced Nuclear Fuels Co_rpora~i_~n _ January 1 990.

XN-NF-82-07(P)(A) Revision 1, "Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, November 1982.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.

ANF-81-58(P)(A) Revision 2 Supplements 3 and 4 "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," Advanced Nuclear Fuels Corporation, June 1990.

I- XN-NF-85-16(P)(A) Volume 1 and Supplements 1, 2 and 3; Volume 2, Revision 11 1 and Supplement 1, "PWR 17x17 Fuel Cooling Test Program, Advanced Nuclear Fuels Corporation, February 1990.

XN-NF-85-105(P)(A) and Supplem~nt 1, "Scaling of FCTF Based Reflood Heat Transfer Correlation for Other Bundle Designs," Advanced Nuclear Fuels Corporation, January 1990.

  • Palisades COLR Revision 4 Page 9 of 10
3. 7 XN-NF- 78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1 983.

3.8 ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report:

Analysis of Chapter 1 5 Events," Advanced Nuclear Fuels Corporation, June 1988.

3.9 ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:

Ar:ialysis of Non-LO CA Chapter 1 5 Events," Advanced Nuclear Fuels Corporation, May 1992.

3.10 EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, March 1994 .

.3.11 XN-NF-621 (P)(A) Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.

3.12 XN-NF-82-06(P)(A) Revision 1 and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.

3.13 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels'

  • PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1 991 .
  • Palisades COLR Revision 4 Page 10 of 10 3.14 XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1 986.

Specific application of these methodologies to Palisades is described in the cycle's most current safety analysis reports.

Retrieved from "https://kanterella.com/w/index.php?title=ML18066A416&oldid=2413378"