RNP-RA/13-0110, Transmittal of Core Operating Limits Report, Cycle 29

Transmittal of Core Operating Limits Report, Cycle 29

ML13353A044
Person / Time
Site:	Robinson
Issue date:	11/21/2013
From:	Wheeler-Peavyhouse S Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/13-0110 FMP-001, Rev 30
Download: ML13353A044 (27)

Text

ShamnA. V.9NaW*%$aW*taU H.a Roblnaon Steam (1SDUKE Etecdt Plant Unt 2 UanagW- Suppwt Saemb iV0 ENERGYo 3661 West Enbunce ROMd hwt~a*, SC 29550 F. iUS 867 1319 ARAML*Ue3Iu TS 5.6.5.d

• ., :..

Serial: RNP-RA113.0110 .. .

NOV 2 12013 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 TRANSMITTAL OF CORE OPERATING LIMITS REPORT Ladies and Gentlemen:

In accordance with Technical Specifications 5.6.5.d, Duke Energy Progress, Inc., formerly known as Carolina Power and Light Company, Is transmitting Revision 0 to the H. B. Robinson Steam Electric Plant, Unit No. 2, Core Operating Limits Report (COLR) for Cycle 29. A summary of the changes Is provided on Page 2 of the attached revision to FMP-001, "Core Operating Limits Report (COLR)." The COLR Is Attachment 10.1 to FMP-001.

There are no commitments associated with this letter.

Ifyou have any questions concerning this matter, please contact Richard Hightower at (843) 857-1329.

Sincerely, Sharon A.*r-Peavyhouse Manager - Support Services SWP/msc Attachment c: V. McCree, NRC, Region II NRC Resident Inspector, HBRSEP S. Lingam, NRR KITJCý

United States Nuclear Regulatory Commission Attachment to Serial: RNP.RA/1 3-0110 26 pages Including cover page H. S. ROBINSON STEAM ELECTRIC PLANT (HSRSEP), UNIT NO. 2 CYCL 22 cGJM OEIRATIN UITSI REPO=T *lEMMIO 0 Note: This report Is Attachment 10.1 to HBRSEP, Unit No. 2, Fuel Management Procedure (FMP) - 001 x' ;

( DUKE KENERGY, ... Information

... N.-., *.u:,

H. B. ROBINSON NUCLEAR PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 6 PART S FUIL MANAGEMENT PROCEDURE,,

, ft CORE OPERA 1ING LIMITS REPORT (COLR)

REVISION 30 FMP-001 Rev. 30 Page 1 of 25

SUMMARY

OF CHANGES PRR 686169 EC 87447 FMP401 Revision 30 SectIonStep REVISION COMMENTS Cover Replaced Proress Enery logo with Duke Energy logo (Editoriall Throughout Replaced Nuclear Fuels Management & Safety Analysis Section

_(NFM&$A) with Nuclear Fuel Engineering (NFE). (Editriat) 2.5 ,,.Changed reference to Cycle 29 Reload Design and Safety Analysis EC

_ _ _ _ 87447. EdWr) 2.11 Changqd to Cycle 29COLR calculation per EC 8747 (PRR 585169) 8.5.1 -ChangeO,"memo recmmending the revision of the COLR" to "Design

......... ___ Calculation." per EC 87447 PRR 685109)

PRR 585169 Attachment 10.1 Changed the following per EC 87447

1) Section 1:

a. 590 EFPD (20,614 MWDIMTU) changed to 545 EFPD (18,978 MWD/MTU)

b. Replaced EC 77261 with EC 87447.

c. Removed mention of Methodology 2 from Table.

2) Section 2,1.2: 300pp,-Sufveilllnce Lim.it char"gedirom -39.70 pcmJ0F to -39.57 pcm-PF. . . ' -. , .- .

3) Section 211.3: 60ppm'Surveillance Limit changed from -43.90 pcm/OF to -43.81 pcmPF

4) Section 2.4.1: Reference to batch R092-26 removed and reference to batch R082-29 added.

5) Section 2.5.2: Reference to batch R082-26 removed and reference to batch R002-29 added.

6) Section 3.0:

a. Reference 2: Changed to "Not Used for Cycle 29".

Starting with Cycle 29, Boron dilution analyses are performed per Methodology Reference 25.

b. Reference 9: Changed Cycle 28 to Cycle 29

c. Reference 18: Changed "and correspondence" to "Revision 0".

d. Reference 22: Changed "Volume 1, Volume 2 and Attachment" to "Volumes I and 2" iaw the SAR.

7) Figure 1.0: The note was updated to reflect the new cycle breakpoint of 273 EFPD (9,500 MWD/MTU)

8) Figure 3.1: Note was updated to reflect the Cycle 29 End of Licensed Life of 18,976 MWD/MTU.

9) Figure 3.2: Cycle 28 changed to Cycle 29. 0.2 Replaced GP-006-2 with AOP-038 which supersedes GP-006-2.

FMP-001 Rev. 30 - Page2 of25

TABLE OF CONTENTS SECTION PAGE 1.0 PURPO SE ......................................................................................................... 4

2.0 REFERENCES

...................................... ..................... 4..

4 3.0 RESPONSIBILITIES.................................................... ................................ 5 4.0 PREREQUISITES .... '.

5.0 PRECAUTIONS and LITATIONS ................................................................ 5 6.0 SPECIAL TOOLS and EQUPMENT ...................  : ............ .......6 7.0 ACCEPTANCE CRITERIA ................................................................................... 6 8.0 PROCEDURE .................................................................................................. 7 9.0 R EC ORDS .......................................................................................................... 11 10.0 ATTACHMENTS ............................................................................................ 11 10.1 HBRSEP UNIT NO, 2, CYCLE 29 CORE OPERATING LIMITS REPORT,.:'12 10.2 PROCEDURES POTENTIALLY AFFECTED BY COLR REVISIONS ..... 25 I FMP-001 Rev. 30 Page 3 of 25 1

1.0 PURPOSE 1.1 To present the cycle-specific Core Operating Limits Report (COLR) for HBRSEP Unit No. 2 1.2 To provide a means of incorporating the COLR into the Plant.Operating Manual (POM). The COLR is placed in the POM to ensure that it resides in a controlled location, and that references are provided that ensure that the requirements specified in NRC Generic Letter 88-16 and Improved Technical Specification 5.6.5 are met.

2.0 REFERENCES

2.1 Improved Technical Specifications 1.1, 3.1.1, 3.1.3, 3.1.5, 3.1.6, 3.2.1, 3.2.2, 3.2.3, 3.4.5, 3.4.6, 3.9.1, and 5.6.5 2.2 PLP-100, Technical Requirements Manual (TRM) 2.3 NRC Genetic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 4, 1988.

2.4 Ucense Amendment No. 141 - Regarding Removal of Cycle-Specifi Parameter Limits to Core Operating Liffits Report 2.5 EC 87447, RNP Cycle:29 Reload Core Design and Safety Analysis 2.6 PRO-NGGC,0204, Procedure Review and Approval 2.7 PLP-001, Plant Nuclear Safety Committee (PNSC) 2.8 REG-NGGC-0010, 10 CFR 50.59 and Selected Regulatory Reviews 2.9 Self Assessment # 108207, Technical Specifications 5.0, Administrative Controls 2.10 UFSAR Section 17.3, RNP Quality Assurance Program Description 2.11 Calculation RNP-F/NFSA-0224, RNP Cycle 29 COLR Update 2.12 NFP-NGGC-0018, Core Operating Limits Report Generation for HNP, RNP, and CR3 IFMP-001 I Rev. 30 1 Page 4 of 25 1

3.0 RESPONSIBILITIES 3.1 RES Reactor Systems and/or Nuclear Fuel Engineering (NFE) is responsible for revising this procedure as changes to the COLR are required. At a minimum, revisions are required once per cycle, at Beginning of Cycle, to make the COLR cycle-specific.

3.2 The Plant Nuclear Safety Committee (PNSC) is responsible for reviewing revisions to the COLR and providing concurrence prior to implementation of COLR revisions (UFSAR Section 17.3, RNP Quality Assurance Program Description, Appendix A Item A. 1.6.8j).

3.3 RES Reactor Systems and Operations are responsiblis for monitoring plant conditions to ensure the Core Operating Limits specified In this procedure are met.

3.4 Licensing/Regulatory Programs is responsible for providing prompt notification of COLR revisions to the NRC in accordance with ITS 5.6.5.d within 30 days upon procedure approval.

4.0 PREREQUISITES 4.1 None.

5.0 PRECAUTIONS and LIMITATIONS 5.1 Requirements for Revision of the COLR 5.1.1 The COLR is cycle-specific, this procedure will be revised at least once per cycle, that is, at the beginning of the cycle.

5.1.2 The methods and requirements established by this procedure for revision of the COLR supplement those of PRO-NGGC-0204.

5.1.3 Changes to the COLR will require a 10CFR 50.59 Evaluation as well as PNSC concurrence and notification of the NRC per TS 5.6.5.d as part of the revision process.

5.2 Core Operating Limits Report (COLR) 5.2.1 The current cycle-specific Core Operating Limits Report is provided in ATTACHMENT 10.1.

5.2.2 The titles for the Methodology references in attachments 10.1.3 have been altered to match what is currently listed in the RNP Technical Specifications. These report titles may differ slightly from current report titles.

FMP-001 Rev. 30 Page 5 of 25

6.0 SPECIAL TOOLS and EQUIPMENT 6.1 None.

7.0 ACCEPTANCE CRITERIA 7.1 None.

%; :, C IFMP-001 Rev. 30 Page6of251

8.0 PROCEDURE 8.1 Definitions 8.1.1 F0V(Z) - the Heat Flux Hot Channel Factor Is the maximum local heat flux on the surface of a fuel rod divided by the average fuel rod heat flux and including the V (z) penalty and measurement uncertainties.

8.1.2 CFQ = FQRTP - the cycle-specifc Fo limit at Rated Thermal Power (RTP).

8.1.3 K(Z) - the normalized axial dependence factor for F0 versus core elevation.

8.1.4 FmfuN - the Nuclear Enthalpy Rise Hot Channel Factor Is the integral of linear power along the rod with the highest Integrated power divided by the average rod power.

8.1.5 FAH~ fy- the cycle-specific Fm Limit .at Rated Th~aivia Power' '(RTP).,

8.1.6 PFm - the Power Factor Multlplierfor FA.

8.1.7 AFDO:,the Axial Flux.Difference Is the difference in normalized flux signals between the top -andbottom halves of a two-section excore neidron detector.

8.1.8 V(Z).-the ratio of the maximum Fo(Z) produced during and following transient maneuvers to the equilibrium Fa(Z) value at target axial offset conditions.

8.1.9 P - the fraction of rated power (2339 MWt) at which the core Is operating.

8.1.10 RTP - Rated Thermal Power is a total reactor core heat transfer rate to the reactor coolant of 2339 MWt.

8.2 Abbreviations 8.2.1 POM - Plant Operating Manual 8.2.2 PNSC - Plant Nuclear Safety Committee 8.2.3 COLR - Core Operating Limits Report 8.2.4 MTC - Moderator Temperature Coefficient I FMP-001 I Rev. 30 1 Page 7 of 251

8.2.5 ITS - Improved Technical Specifications 8.2.6 RIL - Rod Insertion Limits 8.2.7 EFPD - Effective Full Power Day 8.2.8 HBRSEP - H.B. Robinson Steam Electric Olant 8.2.9 NRC - Nuclear Regulatory Commission 8.2.10 RES - Rpblnson Engineering Sea*',.

8.2.11 ARO-A*IlRods Out 8.2.12 SDM - Shutdown Margin 8.3 Background Information 8.3.1 HBRSEP Unit No. 2, like afl other commercial nuclear power plants, is required to operate within the specific core operatinglimits and restrictions as specified in the Technical Specifications. Examples of these limits/restrictions include power dependent rod insertion limits, and limits of FP(Z) and Fm, among others. Technical Specification changes and NRC approval were required as specific numerical values for these timits/restrictions were revised. If these changes were frequent, e.g. on a cycle-specific basis, or if they were needed on accelerated schedules, considerable administrative burdens were placed on both the NRC and on utility, personnel.

8.3.2 To reduce this burden, the COLR concept was developed in which specific numerical values for certain core operating limits and/or restrictions would be removed from the Technical Specifications and relocated to a COLR document, Using NRC approved methodologies, numerical values for these operating limits and/or restrictions can be updated on an as-needed basis (e.g. each cycle) by simply revising the COLR withappropriate review and notification to the NRC. Hence, revisions to the Technical Specifications are not required.

8.3.3 The NRC endorsed the COLR concept by encouraging licensees to develop such a document in Generic Letter 88-16 which provided guidance for relocation of specific numerical values for various core operating limits and/or restrictions to a COLR and indicated that these values could be changed without prior NRC approval so long as an NRC-approved methodology is followed. Future changes and updates would be allowable provided an Evaluation is performed in accordance with the provisions of 1OCR 50.59, the COLR is suitably revised, and the NRC is promptly informed of the revision.

FMP-001I Rev. 30 1Page 8 of 25

8.3.4 The use of a COLR at H. 8. Robinson was accepted by the NRC per License Amendment 141. The amendment established requirements for a cycle-specific COLR and for notificationlof the NRC (ITS 5.6.5.d) when any revisions or supplements (beginning of cycle or midcycle) are made.

Since the COLR is cycle-specific, the COLR will be revised at least once per cycle, that is, at the beginning of the cycle.

8.4 Contents of the H.B. Robinson:Unit 2 COLR 8.4.1 Technical Specification ITS 5.6.5.a requires the following cycle-specific core operating limits be established and documented in the Core Operlng Limits Reports I. Moderator.TemperatufeCoefficlent (MTC) Limits mb

2. Shutdown Ba.* hmet"o Limits

3. Control Bank Insertion.Limits .--

4. Heat Flux Hot Channel Factor (Fo(i)) Limit, CFQ S. K(Z) Curve

6. Nuclear Enthalpy Rise Hot Channel Factor (Fm N) Limit, Fa RTP

7. FAH Power Factor M"ltiplier (PFm)

8. Axial Flux Difference (AFD) Limits

9. V(Z) Curve(s)

10. Shutdown Margin

11. Refueling Boron Concentration 8.4.2 The COLR will also contain a listing of the specific methodologies used to support the core operating limits per TS 5.8.5.b.

8.4.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met (TS 5.6.5.c).

I FMP-001 Rev. 30 1 Page 9 of 25 1

8.5 Revisions to The COLR 8.5.1 Nuclear Fuel Engineering (NFE) shall review and recommend for implementation any changes to the COLR. The review is normally documented in an EC including any required Owner's Reviews, calculations and other reviews. The use of NRC approved methodologies is also confirmed Inthe EC. Changes recommended by NFE are normally transmitted to the plant via a Design Calculation.

8.5.2 Once NFE recommends a revision to the COLR, a Reactor Engineer shall prepare a revision to FMP-001 in accordance with the requirements of PRO-NGGC-0204.

8.5.3 Other plant procedures shall be reviewed to determine if they require revision in order to implement the revised COLR. At a minimum, the procedures listed in ATTACHMENT 10.2 shall be reviewed.

8.5.4 Any required procedure revisions or new procedures necessary to incorporate the change to the COLR shall be completed by the effective date of the COLR change.

8.5.5 The proposed revision of the COLR shall be submitted to the PNSC for review.

8.5.6 The PNSC shall review the proposed revision to the COLR and concur with the changes prior to their implementation in accordance with UFSAR Section 17.3 Appendix A Item A. 1.6.6.j.

8.5.7 Upon approval of the COLR revision, Licensing/Regulatory Programs shall notify the NRC per ITS 5.6.5.d within 30 days.

I FMP-001 I Rev. 30 Page 10 of 251

9.0 RECORDS 9.1 This procedure does not generate any records.

10.0 ATTACHMENTS 10.1 HBRSEP Unit No. 2 Cycle 29 Core Operating Limits Report, Revision 0 10.2 Procedures Potentially Affected By COLR Revisions I.

ol, .

IFMP-001 Rev. 30 1Page 11 of 25

ATTACHMENT 10.1 Page 1 of 13 HBRSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 1.0 OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for HBRSEP Unit No. 2, Cycle 29 has been prepared per EC 87447 in accordance with the requirements of ITS 5.6.5-and is applicable to 545 EFPD (18,976 MWDIMTU).

The Improved Technical Specifications affected by this report and the methodologies used for the various parameters are listed below.

ITS Applicable Methodology Parameter Reference . (Secton 3.0 Numberd MTC 3.1.3 8,19, 22, 23, 25 Shutdown Bank RILs .3.1.5 8 18, 19, 22, 23, 25 Control Bank RILe .3.1.6 8, 18, 19,22, 23,12 FaV(Z) 3.2.1, 3.2.3 5, 811,1,7,18, 19,21, 22, 23, 24, 25, 26, 27 Fm 3.2.2, 3.2.3 3, 6, 11,17, 18,19,20,21,

___ 22, 23, 24,25, 26, 27 AFD 3.2.1, 3.2.3 16, 18, 19, 21, 22, 23, 24, 25, 27 Shdlw Margin Requirements 3.1.1, 3.4.5, 3.4.6 8, 18, 19, 22,13, 25 Refueling Boron Requirements 3.9.1. . . 8, 19,22,23 COLR 5.6.8 .. .None...

FMP-001 Rev. 30 Page 12 of 2

ATTACHMENT 10.1 Page 2 of 13 HBRSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 2.0 OPERATING LIMItTI *-

The cycle-specific parameter limits for the specifications listed In Section 1.0 are presented Inthe following subsections. These limits have been developed using the NRC-approved methodologies specified in ITS 5.6.5 and the COLR Section 3.0.

2.1 Moderator Temperature Coefficlent (ITS &1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

a) The Positive MTC (ARO) shall be less than or equal to +5.0 pcm/0F for power levels less than 50% RTP, and b) The Positive MTC (ARO) shall be less than or equal to 0.0 pcm/0 F at 50%

RTP and above.

c) The Negative MTC (ARO/RTP) shall be less negative than -45.0 pcm/PF.

21.2 The,300 ppm Surveillance limit Is:

At an equilibrium RTP.ARO boron concentration of 300 ppm the MTC shall b less negative than or equal to -39.57 pcm/nF.

2.1.3 The 60 ppm Surveillance limit is:

At an equilibrium RTP-ARO boron concentration of 60 ppm the MTC shall be less negative than or equal to -43.81 pcmPF.

2.2 Shutdown Banks Insertion Limits (ITS 3.1.5) 2.2.1 The shutdown banks shall be withdrawn to at least 225 steps.

2.3 Control Bank Insertion Limits (ITS 3.1.6)

.2.3.1 The control banks shall be limited in physical insertion as shown in Figure 1.0 FMP-001 Rev. 30 Page 13 of 25

ATTACHMENT 10.1 Page 3 of 13 HBRSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 2.4 Heat Flux Hot Channel Factor" fe (Z) (ITS 3.2.1, 3.2.3)

FQV(Z) < (CFQ/P) x K(Z) for P > 0.5 FV(Z) < (CFQ/0.S) x K(Z) for P < 0.5 Where: P = (Thermal Power / Rated Thermal Power) 2.4.1 CFQ = 2.46 for R062-25, RO82-27", ROB2-28, -and R082.29 reload batches , -

2.4.2 K(Z) Is specified In Figure 2.0 2.5 Nuclear Enthalpy Rise Hot Chmmel Factor - Fm,(TS 3.2.2, 3.2.3)

F&4 < F MRTP (1 + PFAH(1-P)) *  :

Where.: P = (Thermal Power i Rated Thermal Power) 2.5.1 FAm is the measured FAHN multiplied by the measurement uncertainty (1.04) 2.5.2 F r =1.80 1- for ROB2-25, R082-27, R0B2-28, and ROB2-29 reload batches 2.5.3 PFA = 01 2.6 Axial Flux Difference (ITS 3.2.1, 3.2.3) 2.6.1 The axial flux difference target bands are +/-3% and +/-5% about the target AFD.

2.6.2 V(Z) values for the +/-3% and +/-5% target bands are specified in Figures 3.1 and 3.2 2.6.3 The AFD Acceptable Operation Limits are specified in Figure 4.0 I FMP-001 Rev. 30 Page 14 of 25 1

ATTACHMENT 10.1 Page 4 of 13 IHBRSEP UNIT NO. 2, CYCLE 29 CORE OPERAT1NG LIMITS REPORT REVISION 0 2.7 Shutdown Margin Requirements (8DM) (ITS 3.1, 3,1.4,341.5,3.1.6, 3.1.8, 3.4.5,3.4.6, 3.9.1) 2.7.1 The Mode I and Mode 2 required 8DM versus RCS boron concentration Is presented in Figure 5.0.

2.7.2 The Mode 3 8DM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the SOM shall be greater than or equal to that specified in Figure 5.0.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 6% Ak/k. This shutdown margin requirement shall be met with a minimum boron concentration of 1950 ppm.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to that specified In Figure 5.0.

2.7.3 The Mode 4 SDM requirements are as follows:

a) With at least 2 reactor coolant pumps in operation, the 8DM shall be greater than or equal to 2,6% Ak/k.

b) With less than 2 reactor coolant pumps in operation and the rod control system capable of rod withdrawal, the SDM shall be greater than or equal to 6% Ak/k. This shutdown margin requirement shall be met with a minimum boron concentration of 1950 ppm.

c) With less than 2 reactor coolant pumps in operation and with the rod control system not capable of rod withdrawal, the SDM shall be greater than or equal to 2.6% Ak/k.

2.7.4 The minimum required SDM for Mode 5 is 2.6% Ak/k.

2.7.5 The minimum required SDM for Mode 6 is 6% Ak/k.

2.8 Refueling Boron Concentration (ITS 3.9.1) 2.8.1 In Mode 6 the minimum boron concentration shall be 1950 ppm.

FMP-001 Rev. 30 Page 15 of 25]

ATTACHMENT 10.1 Page 5 of 13 HBRSEP UNIT NO. 2t CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 3.0 METHODOLOGY REFERENCES

1) Deleted

2) Not Used for Cycle 29

3) XN-NF482-21(A), Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.

4) Deleted

5) XN-75-32(A) Supplements 1, 2, 3, and 4, "Computational Procedure for Evaluating Rod Bow," Exxon Nuclear Company, October 1983.

6) Deleted

7) Deleted,

8) XN-NF-78-44(A)," Generic Control Rod Ejection Analysis," Exxon Nuclear Company,'-ctober 1983

9) Not Used For Cycle 29

10) Deleted

11) XN-NF-82-06(A), Revision I and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Bumup," Exxon Nuclear Company, October 1986.

12) Deleted FMP-001 Rev. 30 Page 16 of 25

ATTACHMENT 10.1 Page 6 of 13 HBRSEP UNIT NO. 2. CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0

13) Deleted

14) Deleted

15) Deleted

18) ANF-88-054(P), "POC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H.B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, October 1990.

17) ANF-88.133(P) (A), and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Bumups of 62 GWd/MTU,"

Advanced Nuclear Fuels Corporation, December 1991.

18) ANF-89-1 51(A), Revision 0, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.

19) EMF-92-081(A), Revision 1, "Statistical SetpointlTransient Methodology for Westinghouse Type Reactors," Siemens Power Corporation, February 2000.

20) EMF-92-153(P) (A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005.

21) XN-NF-85-92(P) (A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.

22) EMF-9W-029(P) (A), Volumes 1 and 2, "Reactor Analysis System for PWRs,"

Siemens Power Corporation, January 1997.

23) EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs,"

Siemens Power Corporation, February 1999.

24) EMF-2103(P) (A), Revision 0, Realistic Large Break LOCA Methodology for Pressurized Water Reactors, Framatome ANP, April 2003.

I FMP-001 I Rev. 30 1 Page 17 of25

ATTACHMENT 10.1 Page 7 of 13 HBRSEP UNIT NO. 2, CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 0

25) EMF-2310(P) (A) Revision 1, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, May 2004.

26) BAW-10240(P) (A), "Incorporation of M6 Properties In Framatome ANP Approved Methods," Framatome ANP, May 2004.

27) EMF-2328(P) (A), -PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," March 2001.

IFMP-001 I Rev. 30 Page 18 of:25

ATTACHMENT 10.1 Page 8 of 13 HBRSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LuMTS REPORT REVMS1ON 0 Figure 1.0, Control Group insertion Limits for Three Loop Operation 261 o00 176 II. 160 -- (*,P7 X1):I II 101

.... -...

. ...----------------------

(3*,00 J---...-.

s8 25 1 a -4 4 4~4 - 4 4-0 10 20 s0 40 60 t0 o0 t0 I**

coawi Aa 44 NOTE: The brekpolnt between BOL and EOL RIL occurs at 50% of the cycle as defined by bumup. For Cycle 29, this bumup occurs at 273 EFPPS (9,500 MWD/MTU).

Control rod banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Control "A", Control "B", Control "C",

and Control "D". The insertion sequence is the reverse of the withdrawal sequence.

Overlap of consecutive control banks shall not exceed the prescribed setpoint for automatic overlap. The setpoint is 97 steps.

Control bank A must be withdrawn from the core prior to power operation.

At BOL and 0% core power, Control bank B will be at or above step 224.

FMP-001 Rev. 30 Page 19 of 25

ATTACHMENT 10.1 Page 9 of 13 HSRSIP UNIT NO. 2, CYCLE 29 CORE OPERATING LMITS REPORT REVISION 0 FIgure 2.0, Nomnl;zd Axial Dependence Factor K(z) for Fq emus Elevatlon 1.2 1.1 1.o I.~ I 0.9 0.7 O.8 0.5 0.4 03 0.2 . ý..-, -4.

0.1 0,0 0.0 1.0 2.0 3.0 4.0 5.0 6,0 7.0 so0 9.0 10.0 11.0 12.0 I NOTE: For all power levels the K(z) at all axial levels Is 1.0.

IFMP-001 Rev. 30 Page 20 of 25

ATTACHMENT 10.1 Page 10 of 13 HBRSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 Figure 3.1 V(z) as a Functllo of Core Height At". *4% +ý.^

.A1. V.0 VIA Cmo 1.73 1.12 *3412 1M aaa a i i i i i i i i i I i - ,-

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fj44 42 VA71 I:W6 am I:WS120 us. IoZeP 0M e .6 .9 2.9 s.0 10 4. &14

5. 60 7.0 10.9 11.0 Ceft No** ft

.5 '3971 I=S 362 X4 1:417 23 '69" 1%1.^

14 '0=1 1 =7 S! ow'6 117(r4 3: 0'621 1".3; NOTE: V(z) data applicable for 0 < bumup, < 18,976 MWD/MTU. .3 a0m6 1 ME

,Va. 'tri 1=175

I: am I =60 For power levels below 50% RTP, the V(z) data at all axial IG am 1ME 1C9 levels is 1.0. It is conservative to apply the above figure to .1' om 120ME power levels below 50% RTP. 1' 300m 1200:

I FMP-001 Rev. 30 Page 21 of 25]

ATTACHMENT 10.1 Page 11 of 13 HURSEP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 Figure 32 V(x). a Functon of Core Hstht Figure 3.2 is not required for Cycle 29 FMP-001 Rev. 30 Page 22 of 25

ATTACHMENT 10.1 Page 12 of 13 HBRS6P UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 Figur 4.0, Alowable Deviation from Target Fkx Diftrnce 100 I I 90.

8o - - - - - - - -

70 xI 60 ILE OPUMATbON s0

---

40. .~ -----

.-----

---

-- ------ ......

---

---

30 20 10 0

-40 -30 .20 -10 0 10 20 30 40 MWAflWHFOM TAWW!PLK W"MW~E(%)

NOTE: For power levels above 90%, power operation is allowed within the target bands L+3% and +5%).

I FMP-001 Rev. 30 1 Page 23 of 25 1

ATTACHMENT 10.1 Page 13 of 13 HRP UNIT NO. 2, CYCLE 29 CORE OPERATING LIMITS REPORT REVISION 0 Figure 8.0, Shutdown Margin Versus Boron Concentration 1~n

~o~1 Li~)

t.

is.

I Mod. 4 b I mod"s I 4 u~ ii I

0 n8 4W so 0w noW tm 14 lOW Is* AIM SOWNM CoScEW1mTmIK ~HFWp" IFMP-001 I Rev. 30 Page 24 of 251

ATTACHMENT 10.2 Page 1 of I PROCEDURES POTENTIALLY AFFECTED BY COLR REVISIONS Revisions to the COLR may require that revisions be made to other plant procedures. At a minimum the following procedures should be reviewed to determine Ifthey must be revised:

APP-006 GP-002 CP-010 GP-003 EST-002 GP-006-1 EST-003 AOP-038 EST-028 GP-009-1 EST-048 GP-009-2 EST-049 GP-009-3 EST-050 GP-009-4 EST-105 GP-009-6 EST-146 GP-010 FMP-009 LP-551 FMP-012 LP-552 FMP-014 OP-003 FMP-019 OP-910 FHP-003 OMP-003 Station Curve Book PLP-100 ERFIS CAOC Software NFP-NGGC-0018 The procedures listed above are those that are typically affected by COLR revisions; however, other procedures may also be affected.

I FMP-001 I Rev. 30 - Page 25 of 25