ML20211P701

Rev 5 to PDB-F0001, COLR for Perry Nuclear Power Plant,Unit 1,Cycle 7 (Reload 6)

ML20211P701
Person / Time
Site:	Perry
Issue date:	09/10/1997
From:	Rinckel J CENTERIOR ENERGY
To:
Shared Package
ML20211P698	List: ML20211P701 ML20211P708 PY-CEI-NRR-2229, Forwards Rev 5 to PDB-F0001, COLR for Perry Nuclear Power Plant,Unit 1,Cycle 7 (Reload 6) & Rev 0 to J11-03060SRLR, Suppl Reload Licensing Rept for Perry Npp,Unit 1,Reload 6, Cycle 7
References
PDB-F0001, PDB-F0001-R05, PDB-F1, PDB-F1-R5, NUDOCS 9710210118
Download: ML20211P701 (22)

Text

.

FDB-F0001 Pages i

Rev.:

5 PERRY OPERATIONS MANUAL Plant Data Book Entry TITLE: CORE OPERATING LIMITS REPOP_T FOR THE PERRY NUCLEAR POWER PLANT UNIT 1 CYCLE 7 (RELOAD 6)

PDB - F0001 /Rev. 5 HPL J11 EFFECTIVE DATE:

/O-/g,.cf 7

SUMMARY

OF LAST CHANGE: Periodic Review - Not Required Incorporated the Cycle 7 fuel design and licensing parameters for plant ope rrit ions.

Replaced fuel type-specific MCPRp and MCPRf curves with the limiting fuel type MCPRp and MCPRf curves.

AETERENCES: PY-CEI-NRR-1104 L; PY-CEI-NRR-1157 L; PY-NRR-CEI-0529 L COMMITMENTS: LO1462, LO1960 s

s PREPARED BY J. M Rinckel 9-10-97 Date EFFECTIVE PIC's PICl Type of Effective No.

Change Date 9710210118 971017 PDR ADOCK 05000440-P pop

,- ~ _... _,-... -

PDB-r0001 Page 1

Rev.:

5 UNIT 1 CORE OPERATING LIMIT 8 REPORT INDEX Specificatioq Page INTRODUCTION AND REFEREllCES 3

i AVERAGE PLANAR LINEAR HEAT GENERATION RATE 5

(CORRESPONDS 70 TS 3.2.1) rigure 3.2.1-1 riow Dependent MAPLHGR ractor (MAPTACg)

Puel Types GE10 6

Figure 3.2.1-2 riow Dependent MAPLHGR ractor (MAPTACg)

Fuel Type Gell & GE12 7

i Figure 3.2.1-3 Power Dependent MAPLHGR ractor (MAPFAC )

p ruel Types GE10 8

rigure 3.2.1-4 Power Dependent MAPLHGR ractor (MAPTAC )

p ruel Type Gell & GE12 9

i rigure 3.2.1-5 MAPLHGR Versus Average Planar Exposure, ruel Type GL 1-P10SSB369-14GZ-120T-150-T 10 4

}

rigure 3.2.1-6 MAPLHGR Versus Average Planar Exposure, ruel Type GE12-P10SSB369-12GZ-120T-150-T 11 i

^

rigure 3.2.1-7 MAPLHGR Versus Average Planar Exposure, ruel Type GE10-P8SXB306-10GZ2-120M-150-T 12 rigure 3.2.1-8 MAPLHGR Versus Average Planar Exposure, Fuel Type GE10-P8SXB306-11GZ3-120M-150-T 13 Figure 3.2.1-9 MAPLHGR Versus Average Planar Exposure, Fuel Type GE11-P9SUB330-10GZ-120T-146-T 14 Figure 3.2.1-10 MAPLHGR Versus Average Planar E,cposure, ruel Type GE11-P9SUB330-12GZ-1207-146-T 15 i

i i

i PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT n....

.,.,n.,

PDB-r0001 Psge:

2 kev.:

5 Ut11T 1 CORE OPERATING LIMITS REPORT INDEX (Continued)

Specification Page MINIMUM CRITICAL POWER RATIO (CORRESPONDS TO TS 3.2.2) 16 Pigure 3.2.2-1 Power Dependent MCPR Limit.(MCPR )

p Limiting fuel Type 17 Figure 3.2.2-2 riow Dependent MCPR Limit (MCPRg)

Limiting ruel Type 18 LINEAR HEAT GENERATION RATE (CORRESPONDS TO TS 3.2.3)

Linear Heat Generation Rate of each ruel Type 19 REACTOR PROTECTION SYSTEM INSTRUMENTATION (CORRESPONDS TO TS 3.3.1.1)

Simulated Thermal Power Time Constant 20 ATTACHMENTS Attachment la Cycle 7 MCPR Limits Per Transient 21 s

s PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

I PDB-P0001 Pages 3

Rev.:

5 INTRODUCTION AND REFERENCES INTRODUCTION This Core Operating Limits Report for PHPP Unit 1 Cycle 7 is prepared in i

f accordance with the requirements of PHPP Technical Specification Administrative Controls 5.6.5.

The core operating limits presented were developed using NRC-approved methods (Reference 2)., Results from the reload analyses for the General Electric fuel in PNPP Unit 1 for Cycle 7 are documented in References 3, 4, 5, and 6.

The cycle-specific coto operating limits for the following PHPP Unit 1 Technical Specifications are included in this reports 1.-

Average Planar Linear Heat Generation Rate (APLHGR) Limits for each f

fuel / lattice type, including the power and flow dependent MAPPAC curves with the single loop HAPLHGR reduction factor.

(Technical Specification 3.2.1) 2.

Minimum Critical Power Ratio Operating Limit including the power and flow dependent MCPR curves.

(Technical Specification 3.2.2)

No changes aro required to MCPR operating limits during Sir.gle Loop Operation.

3.

Linear Heat Generation Rate (LHGR) Limit for eac, fuel type.

(Technical Specification 3.2.3) 4.

The simulated thermal power time constant.

(Technical Specification 3.3.1.1, SR 3.3.1.1.14)

REFERENCES 1.

Perry Nuclear Power Plant Updated Safety Analysis Report, Unit 1, Appendix 15B-Reloed Safety Analysis.

2.

" General Electric Standard Application for Reactor Puel-GESTAR II,"

NEDE-24011-P-A-13 and NEDE-24011-P-A-13-US (US Supplement),

August 20, 1996, i

3.

" Supplemental Reload Licensing Report for the Perry Nuclear Power Plant Unit 1, Reload 6, Cycic 7,"

GE Document J11-03060SRLR Rev. 0

-i (August 1997).

4.'

" Lattice Dependent MAPLHGR Report for the Perry Nuclear Power Plant

. Unit 1, Reload 5, Cycle 6," GE Document J11-02581 MAP Rev. 0 (January 1996).

5.

" Lattice Dependent MAPLHGR Report for the Perry Nuclear Power Plant Unit 1, Reload 6, Cycle 7," GE Document J11-03060 MAP Rev. 0 (August 1997).

LPERRY. UNIT 1 CYCLE 7 CORE OPERATINfi LIMITS REPORT g.

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t PDB-r0001 Paget 4

Rev.:

5 6.

" Supplement i to the Supplemental Reload Licensing Submittal for the Perry Nuc1 car Power Plant Unit 1, Reload 3, Cycle 4," GE Document 23A7147AA, Rev. 0 (January 1992).

7.

J. B. Hopkins (USNRC) to R. A. Stratman (Centerior), Amendment No. 61 to Facility Operating License NPr - 50, June 2, 1994.

HRRCE10719L <LO1960>

8.

H. D. Lyster (CEI) to USNRC, Core Operating Limits Report Submittal (Cycle 4), May 22, 1992. CEINRR'.4 95L <LO1462>

9.

Technical Specification 3.2.1, Average Planar Linear Heat Generation Rate 10.

Technical Specification 3.2.2, Minimum Critical Power Ratic 11.

Technical Specification 3.2.3, Linear Heat Generation Rate 12.

Technical Specification 3.3.1.1, Reactor Protection System Instrumentation 13.

Technical Specification 5.6.5, Core Operating Limits Report PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

. ~. _ - - -

l PDB-r0001 Page:

5 Rev.:

5 AVERAGE PIANAR LINEAR HEAT GENERATION RATE (TS 3.2.1)

All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR

-values

• by the smaller of. either the flow dependent MAPLHGR factor j

(MAPFACg) rigures 3.2.1-1 and 3.2.1-2, or the power dependent MAPLHGR l

factor (MAPTAC ) rigures 3.2.1-3 and 3.2.1-4.

p l

'i e

These applicable MAPLHGR values ares 1.

Those for the respective fuel and lattice, type as a function of the average planar exposure (as described by the NRC approved methodology described in GESTAR-II) or, 2.

When hand calculations are required, the MAPLHGR as a function of the average planar exposure for_the most limiting lattice shown-in Figures 3.2.1-5 through Figure 3.2.1-10 for the applicable type of fuel.

PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

.. ~.... -

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PDB-F0001 Page:

6 Rev.

5 Flow Dependent MAPIJICR Factor (MAPPAcc), Puol Types CE10 s

PNPP No. 8787 Rw, WM 3,, _

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O 20 40 60 80 100 120 CORE FLOW (% RATED), F FLOW DEPENDENT MAPLHGR FACTOR (MAPFACv)

FUELTYPE: GE10 Figure 3.2.1-1 PERRY UNIT 1 CYCLE 7 CORE OPEPATING LIMITS REPORT

PDB-F0001 Page:

7

)

Rev.:

5 Flow Dependent MAPLHCR Factor (MAPFACp), Fuel Type CE11 & CE12 PNPP h. 9003 Rev. W2747 PDorooot 1.0 -

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FUEL TYPES: GE11 and GE12 Figure 3.2.1-2 PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

PDB-F0001 Page:

8 Rev.:

5 Power Dependent HAPLHCR Factor (MAPFAc ), ruel Types GE10 m

PNPP No. 0764 Rev. S/2747 PDB F0001 l

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FUELTYPE:GE10 Figure 3.2.1-3 PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

PDB F0001 i

Page 9

Rev.:

5 Power Dependent MAPLHCR Factor (MAPTACm), Fuel hT>e CE11 & CE12 PNPP No. 9004 Nov. 67M7 g

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FUELTYPE: GE11 and GE12 Figure 3.2.1-4 PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT y,-

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P09-TV001 Pages 13 Rev.:

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-Pages-16 Rev.:

5 l

MINIMt24 CRITICAL POWER RATIO (Ts 3.2.2)

The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the higher of the MCPRg and MCPRp limits at the indicated core flow, THERMAL POWER, delta T and core average exposure compared.to the End of Cycle Exposure (EOCE)** as specified in Figuren 3.2.2-1 and 3.2.2-2.

i NOTE la For Cycle 7, no change to MCPR limits is required for planned reduction of feedwater temperature to es low as 320*F.

Final feedwater temperature may be reduced to 250'r after all control rods are withdrawn at the end of cycle.

NOTE 2:

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.

NOTE 3:

Figures 3.2.2-1 and 3.2.2-2 depict the limiting fuel type.

For

-fuel type specific values, consult Reference 3. illustrates the limiting transients for each fuel type. MCPRg is limited by the fuel loading errors-(FLE).

MCPRp represents the remainder of the transients.

The thermal limits calculation uses whichever is highest (MCPRg or MCPR )

for the given power and flow condition.

p NOTE 4:

There are a total cf 19 safety / relief valves, the two lowest

~

setpoint valves-are assumed to be out-of-service in the transient analyses.

s s

This delta T refers to the planned reduction of rated feedwater temperature from nominal rated feedwater temperature (420*F), such as prolonged removal of feedwater heater (s) from service.

End of Cycle Exposure (EOCE) is defined as 1) the core average exposures at which there is no longer sufficient reactivity to achieve RATED THERMAL POWER with rated core flow, all control rods withdrawn, all feedwater heaters in service and equilibrium Xenon, or 2) as specified by the fuel vendor.

PERRY UNIT 1 CYCLE 7 i

CORE OPERATING LIMITS REPORT

..____m l

PDB-F0001 Page:

17 I

Rev.

5 Power Dependent MCPR Limit (MCPRn)-

Limiting Fuel Type e

1 l

2.3 PNPP No. 9979 Rev. IV24/97 PO3.F0001 1 a a i If I i 1 1

,Eii1 1 1

1 1 65

' !11.L ILLL11 1111!!I!

IlI 2*2 MCPg [2.1 + 0.002(40. P)]

ac FOR 25% $ Py.40%; Core now > $0%

,y "4

1 1

E I

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, MCP% = [1.88

• 0.0133 (40. P)]

m FOR 25%5P140%;Com news 550%

i il i

6 i

in h

1.9 L

PERMISSIBLE 3

REGION OF 1.8 OPERATION 1

iLiiiiiiiii MCPR, = 1.30 (1.21 + 0.004 (70. P)]

q'7 4

FOR 40% < P570%; AI core Rows 7

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1.2 MCPR, = 1.30(1.0 + 0.005 (100. P)]

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FOR 70% < P5100%;AI core Rows 1.1 I

IIII Ii!

III'!

i 1.0 0

20 40 60 80 100 120 CORE THERMAL POWER (% RATED), P POWER DEPENDENT MCPR LIMIT (MCPRe)

LIMITING FUELTYPE

• Refer to NOTE 3 on Page 16.

Figure 3.2.2-1 PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

PDB-F0001 Page 18 Rev.:

5 Flow Dependent MCPR Limit (MCP*tQ Limiting Puel Type

• g,g PNPP No. 9600.Rev. 9/27/97 PDB-F000t ai hl 1

J

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OPERATION

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MCPR, = max (t.30, [1.81x. 0.006H8F) *

. g M

lt.0sts.071)for oett and ostr A

MCm = uAx (1.a tt.atu.0.00ewaF1-C 1.5 I

,u-_-

[1st.07D P

i ear T~~

F > 40%

g j_..

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• ]ri

s 11 L 1.4

~

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.__g._g~

3> RATED OPERATING

[

C-s K

g UMITMCPR = 1.30 7

t 1.3

\\-~

1.2 i

1.15 O

20 40 60 80 100 120 CORE FLOW (% RATED), F FLOW DEPENDENT MCPR LIMIT (MCPRr)

LIMITING FUELTYPE

• Refer to NOTE 3 on Pane 16.

Figure 3.2.2-2 PERhY UNIT 1 CYCLE 7 CORE OPERATING LIMIT.S REPORT

PDB-F0001 Page 19 Rev.:

5 LINEAR HEAT GENERATION RATE (TB 3.2.3)

The LINEAR HEAT GEllERATION RATE (LHGR) shall not exceeds 14.4 kw/f t, for the following fuel types:

a.

1.

GE10-PBSXB306-10GZ2-120H-150-T (GE8X8NB-1) 2.

GE10-P8SXB306-11GZ3-120M-150-T (GE8X8HB-1) 3.

GE11-P9SUB338-10GZ-1207-146-7 (Gell) 4.

GE11-P9SU3330-12GZ-1207-14 6-T (Gell) b.

11.8 kw/ft. for the following fuel types 1.

GE12-P10SSB369-14GZ-120T-150-T (GE12) 2.

GE12-P10SSB369-12GZ-1207-150-T (GE12) s s

e PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

PDB-r0001 Page 20 Rev.:

REACTOR PROTECTION SYSTEM INSTRUMENTATION (TS 3,3,1,1)

The simulated thermal power time constant shall be 610.6 seconds.

l s

-s PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT

1 PDB-r0001 Page 21 - LAST j

Rev.:

5 Cycle 7 HCPR Limits i

I Cycle 7 McPR Values i

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i PERRY UNIT 1 CYCLE 7 CORE OPERATING LIMITS REPORT i