ML042300425

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Supplement to Oyster Creek Technical Specification Change Request No. 323 - Relocation of Stability Protection Settings to the Core Operating Limits Report
ML042300425
Person / Time
Site: Oyster Creek
Issue date: 08/11/2004
From: Gallagher M
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-04-20195, TAC MC2217
Download: ML042300425 (19)
v • d • e


Text

ArnerGen Energy Company, LLC www.exeloncorp.com AmerGen An Exelon Company SM 200 Exelon Way Kennett Square. PA 19348 10 CFR 50.90 2130-04-20195 August 11, 2004 U.S. Nuclear Regulatory Commission ATTN: Dccument Control Desk Washington, DC 20555-0001 Oyster Creek Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219

Subject:

Supplement to Oyster Creek Technical Specification Change Request No. 323 -

Relocation of Stability Protection Settings to the Core Operating Limits Report

.TAC NO. MC2217).

Peferences: '1. AmerGen Let'er No. 2130-04-20011, dated February 27, 2004, Technical Specification Change Request No. 323 - Relocation of Stability Protection Settings to the Core Operating Limits Report (TAC NC). MC2217).

2. Letter from NRC to C. M. Crane dated July 15, 2004.

This letter is being sent to supplement Technical Specification Change Request (TSCR)

No. 323 to modify Technical Specification (TS) by relocating the Average Power Range Monitor (APRM) based stability protection settings for the Option II stability solution to the Core Operating Limits Report (COLR) (Reference 1). This supplemental letter provides information in response to NRC request for additional information (RAI) as discussed in a conference call on June 22, 2004, and documented in a letter from NRC to C. M. Crane (Reference 2) regarding the above mentioned TSCR. The additional information is provided in Enclosure 1. Enclosure 2 contains the sample COLR, as requested in the RAI.

There are no additional regulatory commitments contained in this letter.

We are notifying the State of New Jersey of this supplement to the application for changes to the Technical Specifications by transmitting a copy of this letter and its attachment to the designated State Official.

If any additional information is needed, please contact Dave Robillard at (610) 765-5952.

i US Nuclear Regulatory Commission August 11, 2004 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Sincerely, Executed On Michael P. Gallagher Director, Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Enclosures:

(1) Response to Request for Additional Information (2) Sample COLR with APRM Stability Settings cc: S. J. Collins, Administrator, USNRC Region 1 P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 04028

ENCLOSURE 1 OYSTER CREEK RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATION CHANGE REQUEST No. 323 RELOCATION OF STABILITY PROTECTION SETTINGS TO THE CORE OPERATING LIMITS REPORT 2130-04-20195 Page 1 of 3

1. NRC Question Please justify that the proposed relocation of the average power range monitor-based stability setting to the COLR meets the guidar;ne of Generic Letter 88-16.

Also, describe all the steps involved in the process used to calculate the COLR stability safety limits on a cycle-specific basis. For each relevant step, provide a reference to the approved methodology that it is based on (for example, if using cycle-specific DIVOM, provide a reference to the new DIVOM methodology).

Response

The BWR Owners' Group (BWROG) defined stability long-term solution Option II was approved for implementation at Oyster Creek in October 2002 (Reference 1

- TAC NO. MB4960). NEDC-33065P, "Application of Stability Long-Term Solution Option II to Oyster Creek" (Reference 2) provides a demonstration of the application of the Option II methodology at Oyster Creek for Cycle 19.

The Oyster Creek Cycle 19 analysis established Average Power Range Monitor (APRM) flow biased neutron flux scram and rod block settings for stability protection. These settings were implemented directly into the plant Technical Specifications (TS). The settings for protection against reactor instability are cycle-specific (Reference 2). However, Oyster Creek is a low power density plant and projections of future cycle operating parameters (e.g., reload batch sizes) performed at the time of the analysis were consistent with the Cycle 19 operating parameters. Therefore, it was anticipated that the Cycle 19 analysis would continue to be bounding for future operating cycles and the established APRM flow biased neutron flux scram and rod block settings would remain unchanged.

At the time the Oyster Creek Cycle 19 analysis was performed, a 10 CFR Part 21 Notification (Reference 3) had been issued against the BWROG stability long-term solution. Specifically, the generic DIVOM (Delta CPR/lnitial CPR vs.

Oscillation Magnitude) curve was identified to be potentially non-conservative.

The Oyster Creek analysis was performed utilizing the generic DIVOM curve, which was demonstrated to be bounding for Cycle 19.

The resolution of the Part 21 issue is documented in Reference 4. The resolution requires the application of plant-specific DIVOM curves in place of the original generic DIVOM curve. In addition, current evaluations of the Cycle 20 operating parameters differ significantly from the previous projection. Based on the above, it has been determined that the Cycle 19 analysis will not be bounding for Cycle 20 and a change to the APRM flow biased neutron flux scram and rod block 2130-04-20195 Page 2 of 3 settings is required. Furthermore, changes to future operating cycle parameters, such as a changes in cycle energy, the introduction of a new fuel design or a change to the licensed operating domain, may require a change to the APRM flow biased neutron flux scram and rod block stability protection settings.

NRC Generic Letter 88-16 provides guidance to Licensees for the preparation of license amendment requests to modify TS that have cycle-specific parameter limits. The guidance provides for the relocation of cycle-specific parameter limits to a named formal report that includes the values of cycle-specific parameter limits that have been established using NRC-approved methodology and consistent with all applicable limits in the safety analysis. As described above, the APRM flow biased neutron flux scram and rod block stability protection settings are cycle-specific because key input parameters to the calculation of the stability protection settings are cycle-specific.

The application of the BWROG Stability Analysis Solution Option II methodology for establishing the APRM flow biased neutron flux scram and rod block stability protection settings is described in Reference 2. This application is based on the NRC approved methodology described in Reference 5. The step-by-step process for calculating the stability protection settings is described in Section 6 of Reference 2. For plant/cycle-specific application, this methodology/process remains unchanged with the exception of utilizing a plant/cycle-specific DIVOM curve slope in place of the generic DIVOM curve slope for the calculation of the fractional Critical Power Ratio change (Section 6.4 of Reference 2). The methodology for developing the DIVOM curve is described in Section 4.4 of Reference 5. For plant/cycle-specific application, the methodology for developing the DIVOM curve is consistent with the methodology described in Reference 5, except that plant and cycle-specific parameters (e.g., core power and flow, core loading, cycle energy, fuel types, etc.) are utilized in place of the generic fleet parameters.

2. NRC Question Please provide an example of the new COLR format for a simulated COLR using the old values for the last cycle (Cycle 19).

Response

An example of the proposed COLR format that will include the APRM stability protection settings, using the actual values for Cycle 19, is included as Enclosure 2.

2130-04-20195 Page 3 of 3

References:

1. NRC SER - Oyster Creek Nuclear Generating Station - Issuance of Amendment Re: Use of Option II Solution for Reactor Instability Problem (TAC NO. MB4960), October 18, 2002
2. NEDC-33065P, "Application of Stability Long-Term Solution Option II to Oyster Creek", April 2002
3. GENE 10 CFR Part 21 Notification, "Stability Reload Licensing Calculations Using Generic DIVOM Curve", MFN-01-046, August 31, 2001
4. BWROG-03048, "Utility Commitment to NRC for OPRM Operability at Option IlIl Plants", September 30, 2003
5. NEDO-32465-A, "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," August 1996

ENCLOSURE 2 OYSTER CREEK RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TECHNICAL SPECIFICATION CHANGE REQUEST No. 323 RELOCATION OF STABILITY PROTECTION SETTINGS TO THE CORE OPERATING LIMITS REPORT 2130-04-20195 Page 1 of 12 AmerGen SAMPLE ONLY - NOT FOR USE Oyster Creek Cycle 19 Core Operating Limits Report Topical Report - 066 Rev. 17 BA Number 335400 May 2004 Author: M. P. Hynes Approved:

Manager Date Nuclear Design - BWR Branch Reviewed:

SQR Date Reactor Engineering PORC Chairman Date TR-066 Rev. 17 2130-04-20195 Page 2 of 12 Page 2 of 12 TABLE OF CONTENTS Page Introduction.......................................................................................................3 References........................................................................................................4 TABLE 1 Option II Stability Protection Settings ................ ................... 5 FIGURE 1 GE9B-348 Fuel MAPLHGR Limits .................................. 6 FIGURE 2 GE9B-338 Fuel MAPLHGR Limits .................................. 7 FIGURE 3 GE1 1B-374 Fuel MAPLHGR Limits ............... .................... 8 FIGURE 4 GE1 1B-369 Fuel MAPLHGR Limits ............. ..................... 9 FIGURE 5 MCPR Limits................................... 10 FIGURE 6 Kf Flow Factor .................................. 11 FIGURE 7 LLHGR Limits .................................. 12 SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 3 of 12 Page 3 of 12 INTRODUCTION Generic Letter 88-16 provides guidance for Technical Specification Changes concerning cycle-specific limits. The generic letter provides a vehicle for the removal of cycle

'specific parameters from the Technical Specifications and the maintenance of these values within a Core Operating Limits Report (COLR). The Technical Specification modification also establishes reporting requirements and includes definitions supporting the proposed changes. The COLR, including mid-cycle revisions, will be provided for

-each reload cycle.

This COLR has been prepared in accordance with the requirements of OC Technical Specification 6.9.1.f. The Cycle 19 fuel/core operating limits were generated using the NRC-approved codes and methodologies identified in Reference 9. The information in this report is taken from References 10 through 16.

For each GE fuel design, the APLHGR limits provided in the COLR for operation with less than five loops are calculated to be the same as the five-loop limits at all exposure levels provided a non-operating loop is not an ISOLATED RECIRCULATION LOOP. If a non-operating loop is ISOLATED (both the suction and discharge valves are in the closed position as defined in References 6 and 14), then a 0.98 MAPHLGR multiplier must be applied at all exposure levels. Only one ISOLATED non-operating loop is

-permitted. Requirements for operation with recirculation loops out-of-service are provided in Technical Specification 3.3.F.2.

The LLHGR limits are implemented on a fuel rod exposure dependent basis. Figure 7 shows the maximum value of the LLHGR limit. The exposure dependent LLHGR values are contained Reference 13 for the GE9B fuel, and in Reference 12 for the GE1 1 fuel.

The CPR limits in Figure 5 are differentiated based on the number of recirculation loops in service; one set of limits applies to the condition of five or four loops in service, while the other set applies to the condition of three loops in service. Cycle exposure dependent limits are provided for each condition. The limits cover operation at any point in the cycle with increased core flow up to 67.5 Mlb/hr, feedwater temperature reduction of up to 105 OF, and operation in the extended load line limit analysis (ELLLA) region.

The Stability Long-Term Solution Option II Stability Protection Settings in Table 1 are documented in Reference 16. These settings ensure that, in the event of a postulated reactor instability event, the quadrant-based Average Power Range Monitor (APRM) system will initiate a reactor scram to prevent fuel cladding damage.

During power operation thermal margins should be maintained within the specified limits. If at any time during power operation it is determined by normal surveillance that the limiting value for APLHGR (Figures 1, 2, 3 and 4), LLHGR (Figure 7) or CPR (Figure

5) is being exceeded, action shall be initiated to restore operation to within the prescribed limits as specified in Technical Specification Section 3.10.

SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 4 of 12 Page 4 of 12 REFERENCES

1. Deleted
2. Deleted
3. Deleted
4. Deleted
5. Deleted
6. "Oyster Creek NGS SAFER/CORECOOUGESTR-LOCA Loss-of-Coolant Accident-Analysis," NEDE-31462P August 1987
7. Deleted
8. Deleted
9. "General Electric Standard Application for Reload Fuel," NEDE-24011 -P-A-1 4 June 2000 and U.S. Supplement, NEDE-2401 1-P-A-1 4-US, June 2000.
10. "Oyster Creek C19 New Option A Limits," GE-NE-0000-0026-6850-R0, March 2004. (DRF Number: 0000-0025-2677).
11. 000000055032-SRLR, "Supplemental Reload Licensing Report for Oyster Creek Reload 18 Cycle 19", Revision 2, May 2003.
12. 000000055032-FBIR, "Fuel Bundle Information Report for Oyster Creek Reload 18 Cycle 19", Revision 0, September 2002.
13. GNF-eOOOO-0007-5877, "Improved LHGR Limits for GE9B Fuel in Oyster Creek",

September 2002.

14. GE-NE-0000-0001 -7486-01 P, "Oyster Creek Generating Station Loss of Coolant Accident Evaluation for GE1 1", July 2002.
15. 10 CFR 50.46 Notification Letter, GE to Exelon, 2003-05, May 13, 2004
16. NEDC-33065P, "Application of Stability Long-Term Solution Option II to Oyster Creek", April 2002 SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 5 of 12 Page 5 of 12 TABLE 1 OPTION II STABILITY PROTECTION SETTINGS Technical Specification 2.3.A.1 Neutron Flux, Scram - APRM For W *27.5 x 106 lb / hr:

S * (0.98 x 10-6) W + 41.4 where:

S = setting in percent of rated power W = recirculation flow (Ib/hr)

Technical Specification 2.3.B Neutron Flux, Control Rod Block For W *27.5 x 16lb / hr:

S * (0.98 x 106) W + 34.1 where:

S = setting in percent of rated power W = recirculation flow (Ib/hr)

SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 6 of 12 Page 6 of 12 FIGURE 1 GE9B-P8DWB348-1 2GZ-80M-1 45-T MAPLHGR LIMITS MAPLHGR Limits for 3, 4, and 5 Loop Operation Technical Specfication 3.10.A DATA POINTS 12.00 -

ALL LATTICES Exposure 11.00; -- - ------- -------

GWD/IMT KW/FT 0.00 10.88 10.00 2.00 4.

0.20 10.88 1.10 10.98 E 9.00 - - - -- -L - - - -- -L - - - -- -L - - - -

5.50 11.30 8.80 11.28 X .0 ------- r------- r------- t--------

11.00 11.19 13.80 11.11 16.50 10.79 < 7.00 ------ _____________

19.30 9.76 22.00 9.66 6.00 ---------r------- ------- -------

27.60 9.61 38.60 9.39 49.60 9.45 60.60 9.35 4.00 71.70 9.37 0.00 20.00 40.00 60.00 80.00 Average Planar Exposure (GWDIMT)

I All Lattices I SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 7 of 12 Page 7 of 12 FIGURE 2 GE9B-P8DWB338-1 1GZ-80M-1 45-T MAPLHGR LIMITS Technical Specfication 3.10.A MAPLHGR Limits for 3,4, and 5 Loop Operation DATA POINTS 12.00 ALL LATTICES Exposure 11.00 ------ -------- __a -- _ -- -

GWDIMT KW/FT 0.00 10.93 10.00 ------- -------- --------

0.20 10.93 1.10 11.03 9.00X-- - - - - - - - - - - - - - - - - -

5.50 11.37 I I 8.80 11.29 11.00 11.11 7 .00 --------- -------- --------- --------

I ,I 13.80 11.11 16.50 10.68 19.30 9.72 , .00 - -- - - - -- I- -- -- -- -4 - - -- - --

22.00 9.61 27.60 9.60 38.60 9.39 4.00 49.60 9.43 0.00 20.00 40.00 60.00 80.00 60.60 9.36 Average Planar Exposure (GWDIMT) 71.70 9.44 l - -A l Lattices l SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 8 of 12 Page 8 of 12 FIGUFIE3 GEl1 B-P9HUB374-13( 3Z-1 00T-1 45-T6-2559 MAPLHGFI LIMITS Technical Specfication 3.10.A MAPLHGR Limits for 3,4, and 5 Loop Operation DATA POINTS LATTICES _

Exposure PSZ DOM SDZ NATU GWD/MT KW/FT KWIFT KW/FT KW/FT 11.00 ---- -- - ---- -

0.00 9.83 9.78 9.83 9.83 0.20 9.83 9.78 9.83 9.83 7 .00 --_- _----__1-_____--

1.10 9.81 9.73 9.81 9.81 5.50 9.65 9.62 9.65 9.65

-_ I I 11.00 9.52 9.52 9.52 9.52 5s0 ----- l-\------ ------- --------

16.50 9.46 9.45 9.46 9.46 22.00 9.23 9.22 9.23 9.23 27.60 8.28 8.24 8.28 8.28 4 .00-._ _ __.

38.60 7.99 7.98 7.99 7.99 49.60 8.01 8.04 8.01 8.01 60.60 8.02 8.02 8.02 8.02 71.70 7.54 7.54 7.54 7.54 0.00 20.00 40.00 60.00 80.00 Average Planar Exposure (GWDIMT) 1+-PSZ -- *DOM A SDZ --- NATUl SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 9 of 12 Page 9 of 12 FIGURE 4 GE1 1B-P9HUB369-12GZ-10T-145-T6-2560 MAPLHGR LIMITS Technical Specfication 3.10.A MAPLHGR Limits for 3,4,and 5 Loop Operation DATA POINTS LATTICES 11.w Exposure PSZ DOM SDZ NATU GWD/lT KW/FT KW/FT KW/FT KW/FT 0.00 10.10 10.11 10.10 10.10 900 0.20 10.10 10.11 10.10 10.10 1.10 10.05 10.04 10.05 10.05 8 5.50 9.96 9.88 9.96 9.96 11.00 9.76 9.72 9.76 9.76 7 I 16.50 9.64 9.64 9.64 9.64 C 22.00 9.27 9.25 9.27 9.27 I I 27.60 8.39 8.35 8.39 8.39 .

38.60 8.07 8.06 8.07 8.07 49.60 8.15 8.15 8.15 8.15 60.60 7.99 7.98 7.99 7.99 _ _ _ _ _ _ _

71.70 7.51 7.51 7.51 7.51 U.W eU.W 4UAAJ bU.W tU.W Average Planar Exposure (GWDlMT)

-- PSZ -- DOM A-SDZ - NATUl SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 10 of 12 Page 10 of 12 FIGURE 5 MINIMUM CRITICAL POWER RATIO (MCPR) - Tech Spec 3.10.C MCPR Limits for Five or Four Recirculation Loops in Service APRM STATUS BOC to EOR-2205 EOR-2205 MWD/MT ' MWD/MT to EEOCt 2 ;

1. If any two (2) LPRM assemblies which are input to the APRM system and are separated in distance by less than three (3) times the control rod pitch contain a combination of 1.47 three (3) out of four (4) detectors located in 1.45 either the A and B or C and D levels which are failed or bypassed (i.e., APRM channel or LPRM input bypassed or inoperable)
2. If any LPRM input to the APRM system at the B, C,or D level is failed or bypassed or if any 1.45 1.47 APRM channel is inoperable (or bypassed).
3. All B, C, and D LPRM inputs to the APRMIl system are operating and no APRM channels 1.45 1.47 are inoperable or bypassed.

MCPR Limits for Three Recirculation Loops in Service APRM STATUS BOC to EOR-2205 EOR-2205 MWD/MT ( MWD/MT to EEOC(2

1. If any two (2) LPRM assemblies which are input to the APRM system and are separated in distance by less than three (3) times the control rod pitch contain a combination of 1.48 three (3) out of four (4) detectors located in 1.46 either the A and B or C and D levels which are failed or bypassed (i.e., APRM channel or LPRM input bypassed or inoperable)
2. If any LPRM input to the APRM system at the B, C, or D level is failed or bypassed or if any 1.46 1.48 APRM channel is inoperable (or bypassed).
3. All B, C, and D LPRM inputs to the APRM system are operating and no APRM channels 1.46 1.48 are inoperable or bypassed.

Notes:

(1) Limit applies in the cycle exposure range from beginning of cycle (BOC) until 2205 MWD/MT prior to end of rated (EOR). EOR is defined as the cycle exposure point where all rods out at rated power and flow occurs with all feedwater heaters in service.

(2) Limit applies in the cycle exposure range from 2205 MWD/MT prior to EOR to extended end of cycle (EEOC). EEOC includes cycle extension options used beyond EOR (increased core flow, feedwater temperature reduction, and coastdown).

SAMIPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 11 of 12 Page 11 of 12 FIGURE 6 Technical Specification 3.10.C Kf Curve 1.40 DATA POINTS FLOW Kf 1.30 -

0.3 1.28 1.20 0.4 1.22 0.5 1.17 0.6 1.13 iz 1.10 0.7 1.09 0.8 1.05 0.9 1.00 1.00 -

1 1.00 1.2 1.00 0.90 Flowmax =117%

0.80 - I 0 0.2 0.4 0.6 0.8 1 1.2 1.4 Fraction of Core Flow NOTE: For Fraction of Core Flow (FCF) less than 0.40 the following adjustment factor must be applied to the curve: 1.0 + (0.32)(1.22)(0.40-FCF)

SAMPLE ONLY - NOT FOR USE TR-066 Rev. 17 2130-04-20195 Page 12 of 12 Page 12 of 12 FIGURE 7 LOCAL LINEAR HEAT GENERATION RATE (LLHGR) - Tech Spec 3.1 0.B FUEL TYPE LLHGR Limit GE8x8NB < 13.4 kw/ft GE1 1 < 11.0 kw/ft SAMPLE ONLY - NOT FOR USE

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