U-603845, Issuance of the Core Operating Limits Report Cycle 12

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Issuance of the Core Operating Limits Report Cycle 12
ML080420219
Person / Time
Site: Clinton Constellation icon.png
Issue date: 01/30/2008
From: Bryan Hanson
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
U-603845
Download: ML080420219 (17)
v • d • e


Text

AmerGen ,

An Exelon Company Clinton Power Station R. R. 3, Box 228 Clinton, IL 61727 10CFR50.36 U-603845 January 30, 2008 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Issuance of the Core Operating Limits Report for Clinton Power Station, Unit 1, Cycle 12 In accordance with Technical Specification 5.6.5, "Core Operating Limits Report (COLR),"

Item d., AmerGen Energy Company, LLC (AmerGen) is submitting the COLR for Clinton Power Station, Unit 1, for Cycle 12.

Should you have any questions concerning this report, please contact Mr. Steve Gackstetter, Regulatory Assurance Manager, at (217) 937-2800.

Respectfully,

  1. Fa~~nson Site Vice President Clinton Power Station JLP/blf Attachment cc: Regional Administrator, NRC Region III NRC Senior Resident Inspector, Clinton Power Station MLW4

OOLf ciwm 1 CLIiRV.OagUpI at S CORE OPERATING UMITS REPORT FOR CLINTON POWER STATION UNIT I CYCLE 12 Prepared By* Z,Ncw. Date:

9G" W.Bcm Rovlmed BY.

R*eviwed By.

Approved By:

PlwmizzI-s Datc: o Reviewer S.. Date:

Popel IGOI 4

Exelon Nuclear - Nuclear Fuels DOC ID: COLR Clinton I CLLC12 Core Operating Limits Report Rev. 3 Tablm of Contents Page 1.0 Terms and Definitions 4 2.0 General Information 5 3.0 MAPLHGR Limits 6 4.0 MCPR Limits 7 5.01 Unear Heat Generation Rate Limits 11 6.0 Reactor Protection System (RPS) Instrumentation 14 7.0 Stability Protection Setpoints 14 8.0 Modes of Operation 15 9.0 Methodology 15 10.0 References 16 Page 2 ot 16

Exelon Nuclear

  • Nuclear Fuels ;DOC Mr., CVi'ton 1 CLIC12 Core Operating Limits Report Rev. 3

- Page Table 3-1 MAPLHGR:for a*M,214C Fuel -

Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 6 Table Operating Limit MinimUm Critical Power Ratio 9 4- Oprtn Limi Mii u "- '.,. 9:*:

Table'4-2 Power Dependent MCPR Limits (MCPR(P)) and Multipliers K(P) 9 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 10 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits MCPR(F) 10 Table 5-1 Linear Heat Generation Rate Limits for U0 2 Rods 11 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods 12 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 12 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 12 Table 5-5 LHGR Singie Loop Operaticn (SLO) Reductiorn Factoi'. 13 Table 5-6 Power Dependent LICR Muitipir LHGRFAC'P)

(Loss of 'FULL' Feedwater Heating) 13 Table 5-7 Flow Dependent LHGR Multiplier LHGRFAC(F)

(Loss of 'FULL' Feedwater Heating)

Table 7-1 OP*I.M PBDA Trip Setpoirts Table 8-1 Modes of Operation Parf' 3 of 16

.EkelongNUcWlr -Nuclear Fuels DOC ID: COLR Clinton 1 CLIC12 Core Operating Limits Report Rev. 3 1.0 Terms and Definitions Base Case A case analyzed with two (2) Safety-Relief Valves Out-of-Service (OOS), one (1)-ADS valve'OOS, and up to a 50°F feedwater temperature reduction (FWTR includes feedwater heater OOS or final feedViatertemperature reduction) at any point in the cycle operation in Dual Loop mode (Reference 3).

Coastdown The reactor condition where thermal power gradually decreases due to fuel depletion while the following conditions are met: 1) alloperable control rods are fully withdrawn and 2) all cycle extension techniques have been exhausted including'FFWTR and ICF.

DLO Dual Reactor Recirculation Loop Operation FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service ICF Increased Core Flow LHGR Linear Heat Generation Rate LHGRFAC(F) LHGR thermal limit flow dependent:adjystments and multipliers LHGRFAC(P) LHGR thermal limit power depeWent adjustments and multipliers MAPLHGR Maximum Average Planar Linear Heat Generation Rate MIVPR Minimum Critical Power Ratio MtPR(P) MCPR thermal limit power dependent adjustmenis and multipliers MCPR(F) MCPR thermal limit flow dependent adjustments and multipliers OLMCPR Operating Limit Minimum Critical Power Ratio SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Reactor Recirculation Loop Operation Page 4 of 16

Exelon Nuclear - Nuclear Fuels MlQC P; COLR Clinton 1

  • CL1C12 Core Operating Llmite Report Rev. 3 2.0 General Information This report is prepared in accordance with Technical Specification 5.6,5 of Retprence 1. Power and flow dependent limits are listed for various power and flow levels. Linear interpolation is to be used to find intermediate values.

The data presented in this report is valid for all licensed operating domains on the operating map, including:

  • Maximum: Extende- *Load Line Limit down.to 99% of rateo core flow during full power operation
  • Increased-Core Flow (ICF) up to 107% of rated core flow
  • Final Feedwater iTemperature Reduction (FFWTR) up to 500F during cycle extension operation
  • Feedwater Heater Out of Service' (FWHOOS)u~p toý 50°F teedwater temperature reduction at any time during the cycle prior to cycle extension.

Page .5 of 16

Exelon Nuclear-Nliiclear Fuels DOC ID: CULFR Clinton 1

  • CLIC12 Core Operating Limits Report Rev. 3 3.0 MAPLHGR Limits 3.1 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.

32

Description:

Table 3-1 is used to determine the maximum average planar linear heat generation rate

-(MAPLHGR) limit for each Nel type. Limits listed in Table 3-1 are for dual reactor recirculation loop operation (DLO).

For single reactor recirculation loopoperation (SLO), the MALIHGR limrnits given in Table 3-1 must be multiplied by a SLO MAPLHGR multiplier provided in Tabl] 3-2. The SLO MAPLHGR multiplier for GEl 4 fuel is 0.76 (Reference 3).

Table 3-1 MAPLHGR for all GE14C Fuel1 (Reference 3, 13 and 15)

Avg. Planar MAPLHGR Exposure Limit (GWdIST) (kW/ft) 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 3)

Fuel MAPLHGR Type SLO GE14C 0.76 Linear interpolation should be used for points not listed in Table 3-1.

Page 6 of 16

Exelon Nuclear - Nuclear Fuels DOCV!D: COLR ClInton 1

.CL1C12 Core Operating Limits Report Rev. 3 4.0. MCPR Umits 4Al tTech,'_..

3pecification

Reference:

Sections 3.2.2 and 3.4.1

4.2 DescIpIYon

D The various MCPR limits are described below.

4.2.1 Manua Flow Control MCPH Limits The Operating Limit MCPR (OLMCPR) is determired from either section 4.2.1.1 or 4.2.1.2, whichever is reaer at any givdn power aii; flow condition.

S 4.2.1.1 Powpr-Dependant MCPR For operation less than or equal to 33.3% core thermal power, the MCPR(P) as a functiori'of ore thte'rmal p6wer Is shown in Table 4-2. FOr operation at greater than 33.3% c6re theimal power, ths OLMCPR as a function of-core thermal power is determintcd by thiultiplying'the' applicable rated condition 0LMCPR limit shown in Table 4-1 by the applicable MCPR multiplier K(P) given in Table 4-2.

4.2.1.2 Flow-Depend.prtt MCPR Tables 4-3 and 4-4 give the MCPR(F) as a function of flow based on the applicable plant condition. The limits for dual loop operation are listed in Tables 4-3. The limits for single loop operation are listed in Tables 4-4. The MCPR(F) determined from these tables il the flow dependent OLMCPR.

4.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.

. pe 7 of 16

Exelon Nuclear4. Nuclear Fuels DOC; 10: COLRClinton 1 CLLC12 Core Operating Limits Report Rev. 3 4.2.3 Opti~n A and Option B Option A and Option B refer to use of -scramn speeids:for ,*rblishing MCPR operating limits.

Option A scram speed is the BWR/6 Technical Specification scram speed. The Technical Specification scram speeds must. be met to utilize. the Option A MCPR limits.

Reload analyses performed by GNF for Cycle 12 Option A MCPR limits utilized a 20%

core average insertion time of 0.516 seconds ,(Reference 17).

To utilize the MCPR limits for the Optiobn Bscram.speed;,the cycle average scram insertion time for 20% insertion must satisfy equation 2 in Reference 5 Section 4. If the cycle average scram insertion.time does not meet the Option B criteria, the appropriate MCPR value may be det~rr.in*dlfrom a linear interpolation between the Option A and B limits as specified by equation 4 in Reference 5 Section 4.

4.2.4 Recirculation Flow Cantrol Valve Sýetting*

- Cycle 12 was analyzed-with a maximum core flow runqut of 109%; therefore the 4- recirculation flow control valve must be set to maintain core flow less than 109%

S(92.05 MIb/hr)for all runout events (Reference 16), -

Page 8 of 16

Exelon Nuclear -W uclear Fuels DOC *Q: PCCLR t;,:Rton 1

  • :*,....Rev. 3 CL1C12 Core Operating Limits Report rTable 4-1 Li-n"t M iit C 'icai Power Ratio (R.$ertnce 3)

-F B4L2 Option A I EOOS Combination A Ali exaosures I All exDosures Base; Case 1.29 1.37 Base Case F 1.30 2 1.40 Notes for Table 4-1:

1. Analyzed Option B OLM',PR is 1.27 per Reference 3, value is adjusted to obtain an OPRM
2. SLO Option B OLMCPR is the analyzed Option B OLMCPR plus 0.03.

-Table 4-2 1 2 Power Depend..;. .,!CPP,, Llrr*t, Adjustmenit, and Multipliers MCPR(P)

(Reference ,7 and 11)

Core%Flow I Core Thermal Power (%)

Combination (% of 0E1 >33.3 _<43 >43 k'70 >70 100 Rated) MCPR(P) K(P3 BaseBae as Case .550 2.20

.022 2.20 1.97

.7 1.351 1.347 1.313 1.212 1.15 1.00

>50 2.46 2.46 2.17

  • 50 2.23 2.23 2.00 Base Case SLO 1.351 1.347 1.313 1.212 1.15 1.00

>50 2.49 =

2.49 2.20 pp =,,, , ,, =,=

Notes for Table 4-2:

1. Values are interpolated between relevant power levels.
2. Allowable EOOS conditions are listed In Section 8.
3. Based on 0.500 second turbine trip time deMay with OLMCPR a 1.27.

P-a--.V of 16

Euelon Nucl&`r- Nuclear Fuels ,.DOC ID-COLR Clinton 1 CLLC12 Core Operating Limits Report S.Rev. 3 J- Table 4-3 Flow D6 ndent.MCPgt. I e.imLt-to;(F) 1 (Refevence 7 and 11)

C%atedf MCPR(F)

(% rated),-

0 1.8755 25 ,.6954 93.78 109 i - *.

'Table 4-C-_...

Single Loop Operation (SLO) Flow Dependent MCPIHthks MCPR(F)f

(

Reference:

  • -land 1 :1)

Core Flow MCPR(F)

(% rated) 0.. 1.9055 25 1.7254 93.78 1.23 1

109 . -1.23 Linear interpolation should be used for points not listed in Table 4-3.

2 inear interpolation should be used for points not listed in Table 4-4.

Page 10 of 16

Exelor Nucleor - Nuclear Fuels .,DOC P*I.COLR Clinton 1-CLIC12 Core Operating Limits Report , - Rev. 3 5.0 Unear Heat Generation Rate LUmiis 5.1 Tnrhnioal Sp~rificatinn RArefmrn '-

Section 3.2.3 and 3.4.1. . - .

5.2 Aq..r.p. ;n.

The linear heat generation rate (LHGR) !imit is the product of the exposure dependent LHGR limit (from Table 5-1 for UQI2 fuel rods andTable 5-2 for Gadolinia fuel rods) and the minimum of: the power dependent LHGR Factor, LHGRFAC(P), the flow dependent LHGR Factor, LHGRFAC(F), or the' 'singikA .lp operatic-kni (.SLQ) multiplication factor ifapplicable. The LHGRFAC(P) is determined from Table 5-3. The LHGRFAC(F) is determined from Table 5-4.

The SLO multiplication factor can be found in Table 5-5. Tables 5-1 and 5-2 are the LHGR limit as a function of peak pellet exposure.

The Gadoliri'i fu;fj.6Jlimi;s in Tatl) 3;-2.ar,.,hewmost limiting Gadolinia fuel rods. The most limiting values are provided here as a convenience and do not imply that all the Gadolinia fuel rods must satisfy the listed values..

,.or Loss o 'FIJLL' Fe(idwater Heating (:10 °F of design NORMA. ,pati.4 LHGRFAC(P) is dettrmn.iedfJrf!rnTable 5-6 and LHGRFAC(F) is determined from Table 5-7. Concurrent operation'with SLO and 4e6uced ik'edwater'heating has not 15een evaluated and thus is not a valid Operating mode.ý (Referehce 3, 7, 8,- and-1 0)

Linear Heat Generation Rate Limits for U02 Rods, 412 and 14) 4ht.d~c

.Pea* IPellet LHGR Expinure 'Limit dIGWST)ý _____f

. *0. _.. " 1.."

3.40

[14.,c1 13.40

i i:,:57.61 ': .8.00 r,,63.50 5.00 Unear interpolation should be used for points not listed in Table 5-1. The values listed inTable 5-1 are limiting for all bundle types.

Pag* 11 of 16

Exelonn NucelaiNuclear Fuels CDC ID: COLR Clinton I CLIC12 Core Operating Limits Report Rev. 3 Table 5-2 Linear Heat Generation Rate Limits for Gad Rods' (Reference 4; 12 and 14)

Peak Pellet LHGR Exposure Limit (GWd/ST) (kW/tt) 0.00 11.76 12.08 11.76 54.21', '7.02 59.98. -.4.39 Table 5-3 Power DependentLHGR Multiplier LHGRFACIP)2 (Reference 3,r7.and 11).

EO OS C om b lna t,on C r . " 0 '.; Core 3 3 (%

21:;Thermal Power  ! *Ratedi

  • ,00 1'*

Core

-O ..o .... Flow (%)LHGRFAC(P

<5 _ 0.63*" ... 4 0.68V Base Case > 50 0.512' "b.5-72 '*'"0.600 .I ý 0.689 1.000 Base Case SLO -* 0.634 0.634 0.689 0.689 1.000

........._, > 50

______ , 572 0.572 0.6600

. .. .TAb1e,5-Flow Dependent LHGR Multiplier LHGRFAC(F)3 (Reference-y and 11)

  • .ore Fow., *l R

-'(%Crated)

.FAC(F) 0.00 , 0.443 25.00  ; 0.612 30.00 0.646

- 828 00 107.00 1.00 Linear interpolation should be used for points not listed in Table 5-2. The values listed in Table 5-2 are limiting for all bundle types.

2 Linear interpolation should be used fo" points not listed in Table 5-3.

Linear Interpolation should be used for points not listed in Table 5-4.

Page 12 of 16

Exelon N'uclear;- Mluclear Fuels DDG;010 -2ýLR Clinton 1 CLLC12 Core Operating Limits Report I, Rev. 3 Tabi1 5-5 LHGR Single Loop Operrtkin, (fLO) Reduction Fartor (Reierence3).

Fuel LHGR Type SLO Multiolier I3 GE14C. I 0.76 ....

Table 5-6.. .

Power Dependent LHGR Multiplier LHGRFAC(P)'

.(Loe.. of 'FUL! Fcuedw.ter Heatiný,

' Reference 7,j3,10 and11)

........ *. Ogr Thermal 'Poý!Mef-%.R_ . .

OOS; Combination

.. Core Fiow.r o F , 1 0.. *._2i.6.15 .>...3-*,:***.*.

LHGRFAC(,P 100 Base Case

<~ Ro O~27 I 0627 II.7 fl~R2 II n~ r,97- 1 1 A 0.682 0.99 Base Case SLO S....Tb!e E-7 Flow Dependent LHGR Multiplier LHGRFAC(F) 2 (Loss of 'FULL' Feedwater Heating)

(Reference 7, 8, 9 and 10)

Core oraed Flow FlowLHGRFAC(F)

(%_rated) ______

0.00 0.438

  • 25.00 0.605 30.00 0.639 82.18 0,99 107.00 0.99 1Unear Interpolation should be used for points not listed in Table 5-6.

2Unear interpolation should be used for points not listed in Table 5-7.

P gG 13 of 16

Exelon IC. l-Nuclear Fuels OOC ID: COLR Clinton 1 CLIC12 Core Operating Limits Report Rev. 3 6.0 Reactor Protection System (RPS) Instrumentation 6.1 Technical !n'PenficAtidn RefriThl. ,

Section 3.3.1.1 6.2 De.s* pf..n.

The Average Power Range Monitor (APRM) simulated thermal power time constant, shall be between 5.4 seconds and 6.6 seconds (Reference 17).

7.0 Stability Protection Setpoints, The Clinton 1 Cycle 12 OF4P, 0Period Based Detection Algorithm (PBDA) Trip Setpoints for the OPRM System for use in Technical Specification 3.3.1.3 are found in Table 7-1. These values are based on the cycle specific analysis documented in Reference 3.

Any change td6-th0 LMCPR value and/or ARTS-based power depen dent MCPR limits, should be

. evaluated *ir potentia[ irripact on the0OPRM PBDA Trip Set0points,.

OPFIO PBDA TrIp Sc;points (FHeference 3)"! .

ST PBDA Trip ACorresponding Amplitude CountMaximum Confirmation Trip Setting I 1.10 13 Page 14 of 16

Exelon; Nuclear - Nuclear Fuels 1700Q .OLRCVinton1 CLIC12 Core Operating Limits Report Rev. 3 8.0 Modes Of Operation The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EQOS) are as described below:

Table 8-1 Modes of Operation (Reference 3)

Operatng Regi .......

EOOS OptloIi-c ' -LA ICF FFWTR Coastdown Base Case. Option A I - -.:-Yes Yes - Yes Yes Base Case SLO., Option A Yes No No No Yes ase Case, Option B . Yes " Yes Yes Yes Yes Base Case SLO 1 , Otion B Yes No No NO Yes Notes:

1. Concurrent operation with SLO and Loss of 'FULL' Feedwater Heating (+/-1°O*F of design NORMAL temperature) or FFWTR has not been evaluated and thus not a valid operating mode. (Refernce 3,.7,8,9 and 10) 9.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by th, ,. pecfc*.lv those described in .the following doc.ment:
1. "Genarai Electric-Standard iAppila- rir Reactr Fuel", ;NEDE-2401 -T.P,.A.5,September 2005 and U.S. Supplement NEDE-2401 1-P-A-I5-US, September 2005.

.Page ;5 of 16

Exelon Nuc .ar- Nuclesr Fuels -DOC ID: CULR Clinton 1 CL1C12 Core Operating Limits Report Rev. 3 10.0 References

1. Technical Specifications for Clinton Power Station Unit 1, Docket No. 50-461, License No. NPF-62.
2. General Electric Standard Application for Reactor Fuel (GESTAR II) and US supplement, NEDE-2401 1-P-A-15, September 2005.
3. Document 0000-0067-2201-SRLR Revision 0, "Supplemental Reload Licensing Report

ýIfor Clinton Power Station Unit 1 Reload 11ý Cycle 12".', December 2007,.

4. Document 0000--0067-2201-FBIR Revisiohn0, "Fuel Bundle finformation -Rport for Clinton Power Station Unit 1 Reload 1.1 Cycle 12", December 2007.

.5 Document GE-NE-0600-0000-7456-'01 P, "Option B Scram Times For Clinton Power Station", February 2002

6. NEDC-32694P-A, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations,"

August 1999. ..

7. GE-NE-0000-0042-4570-RO, "Clinton Off rated Analyses Below the iPLU Power Level,"

September 2005.

8. Calculation GENE-0000-0030-8309, "Clinton Assessment of Feedwater Riser Flow Deviation," Rev. 0, March 2005.
9. 1`-`EC 355034.RO, "Fe4dwater Riser Flow Deviatioh Assssm~t. -
10. ,EC 354185 RO, "Uncertainty in Feedwater Tumptlitudl fTwo , Loop and Sing{b Loop'...

Operation" ,

11. GE-NE-0000-0026-1857-R1," Evaluation of Operation With Equipment Out-Of-Service for the Clinton Power Station", June 28, 2004
12. Document 0000-0016-5277FBIR Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 9 Cycle 10", December 2003
13. Document 000-001 6-5277SRLR Revision 1, 'Supplemental Reload Licensing Report For Clinton Power Station Unit 1 Reload 9 Cycle 10", August 2005
14. Document 0000-0038-3490FBIR Revision 0, "Fuel Bundle Information Report for Clinton Power Station Unit 1 Reload 10 Cycle 11", December 2005
15. Document 0000-0038-3490SRLR Revision 1, "Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 10 Cycle 11", January 2006
16. TODI NF0700232 Revision 0, "Clinton Unit 1 Cycle 12 Final FRED Form Revision 1'
17. TODI NF0700130 Revision 1, "Clinton Unit 1 Cycle 12 Customer Proposed OPL-3 Values" Page 16 of 16
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