ML17292A311

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Rev 0 to WNP-2 Cycle 12 COLR, for May 1996
ML17292A311
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/31/1996
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17292A309 List:
References
NUDOCS 9606110341
Download: ML17292A311 (81)


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'F606'L 10341 960605 PDR ADGCK 05000397 P

PDR'OLE 96-12, Revision 0 Controlled Copy No.

WNP-2 Cycle 12 Core Operating Limits Report 7

Washington Public Poorer Supply System

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9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 WNP-2 Cycle 12 Core Operating Limits Report LI T FEFFE TIVE PA E

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WNP-2 Cycle 12 Core Operating Limits Report TAB E F

NTENT 1.0 IN D

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P IFI ATI 24 Washington inuclear - Unit 2 COLR 96-I2, Revision 0

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1.0 INT TI N AND i

Y This report provides the Average Planar Linear Heat Generation Rate (APLHGR) limits, the Minimum Critical Power Ratio (MCPR) limits, and the Linear Heat Generation Rate (LHGR) limits for WNP-2, Cycle 12 as required by Technical Specification 6.9.3.1.

As required by Technical Specifications 6.9.3.2 and 6.9.3.3, these limits were determined using NRC-approved methodology and are established so that all applicable limits of the plant safety analysis are met.

References 5.1, 5.2, 5.3, and 5.7 describe the LOCA analysis for rated power.

The analysis was performed with a methodology that results in Single Loop Operation being adequately covered by Two Loop Operation.

The thermal limits for all fuel types for Single Loop Operation are the same as Two Loop Operation.

The thermal limits for fuel given in this report-are documented in the "WNP-2 Cycle 12 Reload Report" (Reference 5.3), the "WNP-2 Cycle 12 Transient Analysis Report" (Reference 5.4), and Reference 5.5.

The MCPR limitis the maximum of (a) the applicable exposure dependent, full power and full flow MCPR limit, (b) the applicable exposure and power dependent MCPR limit, and (c) the applicable Qow dependent MCPR limit specified in'this report. This stipulation assures that the safety limitMCPR will not be violated throughout the WNP-2 operating regime.

Full power MCPR limits are specified to define operating limits at, rated power and flow.

Power dependent MCPR limits are specified to define operating limits at other than rated power conditions.

A flow dependent MCPR is specified to define operating limits at other than rated Qow conditions. The reduced flow MCPR limit, set by the limitingRecirculation Flow Increase event, provides bounding protection for all events at reduced flow.

The reload licensing analyses for this cycle provide operating limits for Extended Load Line Limit Analysis (ELLLA)operation which extends the power and flow operating regime for WNP-2 up to the 108% rod line which at fullpower corresponds to 88% ofrated Qow. The MCPR limits defined in this report are applicable up to 100% ofrated thermal power along and below the 108% rod line.

The minimum Qow for operation at rated power is 88% of rated Qow; the maximum is 106%.

The references in Section 5.0 document the analyses in support ofELLLAoperation.

Preparation, review, and approval of this report were performed in accordance with applicable Supply System procedures.

The specific topical e ort revisions and supplements which describe the methodology utilized in 9

this cycle specific analysis are referenced in Technical Specification 6.9.3..

Washington Nuclear - Unit 2 COLR 96-12, Revision 0

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.2.1 The APLHGRs for use in Technical Specification 3.2.1, as a function of Average Planar Exposure, shall not exceed the limits shown in the following figures when in two loop or single loop operation:

a. Figure 2.1 - SPC 8x8-2 reload fuel
b. Figure 2.2 - SPC 9x9-9X reload fuel
c. Figure 2.3 - ABB SVEA-96 reload fuel washington Nuclear - Unit 2 2.

COLR 96-12, Revision 0

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Two Loop and Single Loop Operation

-'1 3.5 13 12.5 cr 11 10.5 10 9.5 8.5 7.5 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWd/MTU)

Average Planar Exposure (MWcUMTU) 15500 45000 55000 MAPLHGR(kW/ft) 12.5 12.5 9.3 7.9 Maximum Average Planar Linear Heat Generation Rate (siPLHGR)

Versus Average Planar Exposure SPC 9x9-9X Figure 2.2 Washington ivuclear - Unit 2 COLR 96-12, Revision 0

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3.0 MINIM M ITI A P

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The MCPR limitfor use in Technical Speci6cation 3.2.3 shall be greater than or equal to the bounding limits determined from Table 3.1a, Table 3.1b, Figures 3.1 through 3.3, and Figures 3.4a through 3.18b.

Washington iNuclear - Unit 2 COLR 96-12, Revision 0

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Table 3.1a WNP-2 Cycle 12 MCPR Oyerating Limits Two Loop and Single Loop Oyeration Cycle Exposure g 5000 1VDVd/MTU SLMCPR = 1.07<'>

Condition NSS <>>

Limit Full Power Flow Dependent<'>

Power Dependent<6>

SPC 8x8-2 1.28<3>

Fig. 3.1 Fig. 3.4a SPC 9x9-9X 1.28<3>

Fig. 3.2 Fig. 3.5a ABB SVEA-96 1.26'>

Fig. 3.3 Fig. 3.6a TSSS

Full Power Flow Dependent<>>

Power Dependent<6>

1.32 Fig. 3.1 Fig. 3.7a 1.28 Fig. 3.2 Fig. 3.8a 1.32 Fig. 3.3 Fig. 3.9a NSS <>>

RPT Inop.

Full Power Flow Dependent<>>

Power Dependent<<>

1.30 Fig. 3.1 Fig. 3.16a 1.28<:>>

Fig. 3.2 Fig. 3.17a 1.30 Fig. 3.3 Fig. 3.18a Washington Nuc)ear - Unit 2 COLR 96-12, Revision 0

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Notes for Tables 3. la and 3.lb Note 1:

The scram insertion times must meet the requirements of Technical Specification 3.1.3.4. The NSS MCPR values are based on the ABB transient analysis performed using the control rod insertion times shown below (defined as normal scram speed:

NSS). In the event that Surveillance 4.1.3.2 shows these scram insertion times have been exceeded, the MCPR limit shall be determined from the applicable Technical Specification Scram Speed (TSSS) MCPR limitsin Tables 3.1a and b.

Position Inserted From Full Withdrawn Slowest measured average control rod insertion times to specified notches for all operable control rods for each group offour control rods arranged in a two-b -two arra (seconds)

Notch 45 Notch 39 Notch 25 Notch 5 0.430 0.720 1.600 2.950 Note 2:

Note 3:

Note 4:

For Single Loop Operation (SLO), the SLMCPR increases by 0.01.

The increase is included in the MCPR operating limits.

For the noted fullpower MCPR limits, the Rod Withdrawal Error (RWE) event is limiting.

The Generator Load Rejection No Bypass (GLRNB) event is limiting for the remaining full power limits. The RWE analysis was performed with a noniinal Rod Block Monitor (RBM) setpoint of 1.06.

For the noted full power MCPR limits, the Misoriented Bundle

, event is limiting.

The Generator Load Rejection No Bypass (GLRNB) event is limitingfor the remaining full power limits.

Note 5:

Flow dependent MCPRs are not applicable for single loop operation.

Note 6:

Power dependent MCPR limits are provided for core thermal powers greater than or equal to 25 % of rated power at, all core Qows. The power dependent MCPR limits for core thermal powers less than or equal to 30% of rated power are subdivided by core Qow. Limits are provided for core Qows greater than 50% ofrated Qow and less than or equal to 50% of rated flow, respectively.

A step change in the power dependent MCPR limits occurs at 30% of rated power because direct scram on turbine throttle valve closure is automatically bypassed per Technical Specification 3.3.1.

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Operating LimitMCPR 1.31 1.56 2.10 2.20 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power NSS, RPT Operable, SPC 8x8-2 Cycle Exposures >5000 MVd/MTU Figure 3.4b Washington nuclear - Unit 2 COM 96-12, Revision 0

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Operating LimitMCPR 1.28 1.52 2.10 2.20 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, SPC 9x9-9X Cycle Exposures <5000 MVd&iTU Figure 3.8a Washington Nuclear - Unit 2 9]

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Operating LimitMCPR 1.36 1.63 2.10 2.20 2.40 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, SPC Bx8-2 FFTR Operation Figure 3.13 Washington Nuclear - Unit 2 CQLR 96-12, Revision 0

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Operating LimitMCPR 1.32 1.56 2.10 2.20 2.40 2.50 Reduced Power MCPR Operating LimitVersus Percent ofRated Power TSSS, RPT Operable, SPC 9x9-9X FFTR Operation Figure 3.14 Washington ifuclear - Unit 2 COLR 96-12, Revision 0

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The LHGRs for use in Technical Specification 3.2.4, as a function ofAverage Planar Exposure, shall not exceed the limits shown in the followingGgures:

a. Figure 4.1 - SPC 8x8-2 reload fuel
b. Figure 4.2 - SPC 9x9-9X reload fuel
c. Figure 4.3 - ABB SVEA-96 reload fuel Washington Nuclear - Unit 2 COLR 96-3.2, Revision 0

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Average Planar Exposure (MWd/MTU) 25400 43200 48100 LHGR (kW/ft) 16.0 9.0 Linear Heat Generation Rate (LHGR) Versus Average Planar Exposure SPC 8x8-2 Figure 4.1 Washington Nuclear - Unit 2 COLR 96-12, Revision 0

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5.0 5.1 NEDO-33269, "Washington Public Power Supply System Nuclear Project 2, Supplement to SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis," GE Nuclear Energy, September, 1993.

5.2 Letter, Karch Taghavi (GE) to J. D. Fisher (WPPSS), "Extended MAPLHGRCurve for SNP 9x9-9x," October 4, 1995.

5.3 CE NPSD-803-P, "WNP-2 Cycle 12 Reload Report," ABB Combustion Engineering Nuclear Operations, i%lay 1996.

5.4 CE NPSD-802-P, "WNP-2 Cycle 12 Transient Analysis Report,"

ABB Combustion Engineering Nuclear Operations, May 1996.

5.5 Letter KVW-95:050, K. V. Walters (Siemens Power Corporation) 70 R. A. Vopalensky (WPPSS), 'WNP-2 Fuel Misorientation Error Analysis," October 16, 1995.

5.6 NEDC-32141 P, "Power Uprate with Extended Load Line Limit Safety Analysis for WNP-2," GE Nuclear Energy, June, 1993.

5.7 CE NPSD-801-P, "WNP-2 LOCA Analysis Report," ABB Combustion Engineering Nuclear Operations, May 1996.

Washington Nuclear - Unit 2 COLR 96-l~ Revision 0

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