ML091350181

Supplement to License Amendment Request: Changes to Technical Specification Administrative Controls Section

ML091350181
Person / Time
Site:	Palisades
Issue date:	05/14/2009
From:	Schwarz C Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML091350181 (10)

Text

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 Christopher J. Schwarz Site Vice President May 14,2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Supplement to License Amendment Request: Changes to Technical Specification Administrative Controls Section Palisades Nuclear Plant Docket 50-255 License No. DPR-20

References:

1. Entergy Nuclear Operations, Inc. letter to NRC, dated August 28,2008, License Amendment Request: Changes to Technical Specification Administrative Controls Section

2. NRC electronic mail to Entergy Nuclear Operations, Inc., dated March 18, 2009, Palisades LAR - Administrative Changes - MD9560

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. submitted, in Reference 1, a Palisades Nuclear Plant license amendment request (LAR) for Nuclear Regulatory Commission review and approval pursuant to 10 CFR 50.90. The LAR proposed, in part, to implement Technical Specifications Task Force (TSTF) Improved Technical Specifications Change Traveler TSTF-363-A. TSTF-363-A would allow references to approved topical reports in the Technical Specifications (TS) to be cited using the report number and title and eliminate revision numbers and dates from the topical report list. The COLR would include complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

Reference 2 identified that a statement, on the contents of the COLR, required to fully implement TSTF-363-A was omitted in the submitted LAR (Reference 1). , to this letter, provides revised TS Section 5.6.5 pages incorporating the omitted statement concerning COLR content. Additionally, the dates and revisions of the topical reports listed in TS Sections 5.6.5b.6., 5.6.5b.17., and 5.6.5b.18 have been removed in accordance with TSTF-363-A. Attachment 2 provides the annotated pages for TS 5.6.5 showing the proposed changes.

The proposed changes to TS Section 5.3.1 (TS page 5.0-4) cited in Reference 1 are

Document Control Desk Page 2 not affected by this supplement. This supplement does not alter the significant hazards consideration or the environmental considerations previously provided in Reference 1.

A copy of this request has been provided to the designated representative of the State of Michigan.

Summarv of Commitments This letter identifies no new commitments and no revisions to existing commitments.

I declare under penalty of perjury that the forgoing is true and correct. Executed on May 14,2009.

Attachments: 1. License Amendment Request: Changes to Technical Specifications Administrative Controls Section: Revised Technical Specifications Pages

2. License Amendment Request: Changes to Technical Specifications Administrative Controls Section: Mark-up of Technical Specifications Pages cc: Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ATTACHMENT I LICENSE AMENDMENT REQUEST: CHANGES TO TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS SECTION REVISED TECHNICAL SPECIFICATIONS PAGES 5.0-25, 5.0-26, AND 5.0-27 3 Pages Follow

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 (Deleted)

CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

3.1. I Shutdown Margin 3.1.6 Regulating Rod Group Position Limits 3.2.1 Linear Heat Rate Limits 3.2.2 Radial Peaking Factor Limits 3.2.4 AS1 Limits 3.4.1 DNB Limits

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: I

1. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs," Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. . ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company.

(LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs, "Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-25 Amendment No. W ,24-7, m,

Reporting Requirements 5.6 5.6 Reporting Requirements COLR (continued)

6. EMF-2310 (P)(A), Framatome ANP, Inc., "SRP Chapter 15 Non- 1 LOCA Methodology for Pressurized Water Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

7. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)

8. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

9. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Power Corporation. (LCOs 3.2.1 , 3.2.2, & 3.2.4)

10. XN-NF-621(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

11. XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company. (LCOs3.1.6, 3.2.1, 3.2.2, &3.2.4)

12. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWDIMTU," Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

13. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium DioxideIGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-26 Amendment No. W ,N ,

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

14. EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), "SEMIPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

16. ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 19881 (LCOs 3.1.6, 3.2.1, 3.2.2, &3.4.1)

17. EMF-1961(P)(A), Siemens Power Corporation, "Statistical I Setpoint/Transient Methodology for Combustion Engineering Type Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, & 3.4.1)

18. EMF-2328 (P)(A), Framatome ANP, Inc., "PWR Small Break 1 LOCA Evaluation Model, S-RELAP5 Based." (LCOs 3.1.6, 3.2.1,

& 3.2.2)

19. BAW-2489P, "Revised Fuel Assembly Growth Correlation for Palisades." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

20. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors." (LCOs 3.1.6, 3.2.1, & 3.2.2)

21. BAW-10240(P)-A, "lncorporation of M5 Properties in Framatome ANP Approved Methods." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, & 3.4.1)

The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

c. 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 limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

Palisades Nuclear Plant 5.0-27 Amendment No. ~ , .217,222,

~ , ~ ,

a, w,

ATTACHMENT 2 LICENSE AMENDMENT REQUEST: CHANGES TO TECHNICAL SPECIFICATIONS ADMINISTRATIVE CONTROLS SECTION MARK-UP OF TECHNICAL SPECIFICATIONS PAGES 5.0-25, 5.0-26, AND 5.0-27 (showing proposed changes)

(additions are highlighted and deletions are strikethrough) 3 Pages Follow

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 (Deleted)

I CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

3.1.1 Shutdown Margin 3.1.6 Regulating Rod Group Position Limits 3.2.1 Linear Heat Rate Limits 3.2.2 Radial Peaking Factor Limits 3.2.4 AS1 Limits 3.4.1 DNB Limits

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs," Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company.

(LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs, "Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-25 Amendment No. 4433,247,220

Reporting Requirements 5.6 5.6 Reportins Requirements COLR (continued)

6. EMF-2310 (P)(A), Re&bw& Framatome ANP, Inc., !&y-XK&

"SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

7. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)

8. ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

9. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from I

Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Power Corporation. (LCOs 3.2.1, 3.2.2, & 3.2.4)

10. XN-NF-621(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

11. XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

12. ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWDIMTU," Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

13. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium DioxideIGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-26 Amendment No. a, 209

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

14. EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), "SEMIPWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 83.2.2)

16. ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 19881 (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.4.1)

17. EMF-1961(P)(A), FkwMw-&Siemens Power Corporation, &&

2 W & "Statistical Setpointrrransient Methodology for Combustion Engineering Type Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

18. EMF-2328 (P)(A), ~ F r a m a t o m ANP, e Inc., !vhdG%&

"PWR Small Break LOCA Evaluation Model, S-RELAP5 Based."

(LCOs 3.1.6, 3.2.1, & 3.2.2)

19. BAW-2489P, "Revised Fuel Assembly Growth Correlation for Palisades." (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

20. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors." (LCOs 3.1.6, 3.2.1, & 3.2.2)

21. BAW-10240(P)-A, "Incorporation of M5 Properties in Framatome ANP Approved Methods." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

The COLR hill contain the complete identificationfor each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e.. report number, title, revision, date. and any supplements).

c. 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 limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

Palisades Nuclear Plant 5.0-27 Amendment No. %#,W,i?88,212; 22-2, 229,234