ML050890323

From kanterella
Jump to navigation Jump to search
License Amendment Request Applicable to Technical Specifications 5.6.1, Occupational Radiation Exposure Report; and 5.6.4, Monthly Operating Reports, Using the Consolidated Line Item Improvement Process
ML050890323
Person / Time
Site: Oconee, Mcguire, McGuire  Duke Energy icon.png
Issue date: 03/14/2005
From: Barron H
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050890323 (12)
v • d • e


Text

L Duke HENRYB.BARRON LFPowere Group VP, Nuclear Generation and Chief Nuclear Officer A Duke Energy Company Duke Power EC07H /526 South Church Street Charlotte, NC 28202-1802 Mailing Address:

P. 0. Box 1006- EC07H March 14, 2005 Charlotte, NC 28201-1006 704 382 2200 U. S. Nuclear Regulatory Commission 704 382 6056 fax Washington, DC 20555-0001 hbarron@duke-energy.cor ATTENTION: Document Control Desk

SUBJECT:

Duke Energy Corporation Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, and 50-287 McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 License Amendment Request Applicable to Technical Specifications 5.6.1, Occupational Radiation Exposure Report; and 5.6.4, Monthly Operating Reports, Using the Consolidated Line Item Improvement Process (CLIIP)

In a letter dated September 28, 2004, Duke Energy Corporation (Duke) submitted a license amendment request (LAR) for the Oconee, McGuire, and Catawba Nuclear Stations Facility Operating Licenses and Technical Specifications (TS). This LAR applied to TS 5.6.1, Occupational Radiation Exposure Report; and TS 5.6.4, Monthly Operating Reports, and it implemented the NRC CLIIP TS improvement item published in the Federal Register on June 23, 2004 (69 FR 35067). This letter provides new reprinted TS pages for the NRC's use in issuing this.LAR, which has now been approved. Attachment 1 provides new reprinted pages for Oconee and Attachment 2 provides new reprinted pages for McGuire. Due to interference with other LARs which are currently in the NRC's issuance process, the new reprinted pages for Catawba will be provided at-a later date.

Inquiries on this matter should be directed to J. S. Warren at 704-875-5171.

Very truly yours, Henry B. Barron o9( 1-200 Heritage

  • Service
  • Vision www. dukepower.com 0n 0

U. S. Nuclear Regulatory Commission March 14, 2005 Page 2 xc w/Attachments:

W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 L. N. Olshan (Addressee Only)

NRC Senior Project Manager (ONS)

U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 J. J. Shea (Addressee Only)

NRC Senior Project Manager (MNS)

U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 M. C. Shannon Senior Resident Inspector (ONS)

U. S. Nuclear Regulatory Commission Oconee Nuclear Site J. B. Brady Senior Resident Inspector (MNS)

U. S. Nuclear Regulatory Commission McGuire Nuclear Site

U. S. Nuclear Regulatory Commission March 14, 2005 Page 3 Henry B. Barron affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.

/1 Henry B. Barron Subscribed and sworn to me, / "gOS Date Notary Public My cii/ expir My commission expires: AX-s - f.,epe '5 Dater

/

SEAL A-

Attachment 1 Oconee Units 1, 2, and 3 Revised (Clean) Technical Specifications Pages Remove Insert 5.0-34 5.0-34 5.0-35 5.0-35

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted 5.6.2 Annual Radiological Environmental Operating Report

NOTE---------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year.

The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

OCONEE UNITS 1, 2, & 3 5.0-34 Amendment Nos. I

Reporting Requirements 5.6 5.6 Reporting Requirements: (continued) 5.6.3 Radioactive Effluent Release Report

NOTE---------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR part 50, Appendix I,Section IV.B.1.

5.6.4 Deleted 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

Core operating limits shall be established, determined and issued in accordance with the following:

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:
1. Shutdown Margin limit for Specification 3.1.1;
2. Moderator Temperature Coefficient limit for Specification 3.1.3;
3. Physical Position, Sequence and Overlap limits for Specification 3.2.1 Rod Insertion Limits;
4. AXIAL POWER IMBALANCE operating limits for Specification 3.2.2;
5. QUADRANT POWER TILT (QPT) limits for Specification 3.2.3; OCONEE UNITS 1, 2, & 3 5.0-35 Amendment Nos. I

Attachment 2 McGuire Units 1 and 2 Revised (Clean) Technical Specifications Pages Remove Insert 5.6-1 thru 5.6-5 5.6-1 thru 5.6-5

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted 5.6.2 Annual Radiological Environmental Operating Report

----- NOTE--- -----

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in Chapter 16 of the UFSAR and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of the analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

---- NOTE-- ----

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in Chapter 16 of the UFSAR and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

(continued)

McGuire Units 1 and 2 5.6-1 Amendment Nos.

5.6 Reporting Requirements 5.6.4 Deleted 5.6.5 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:
1. Illustration of Reactor Core Safety Limits for Specification 2.1.1.
2. Moderator Temperature Coefficient BOL and EOL limits and 60 ppm and 300 ppm surveillance limits for Specification 3.1.3,
3. Shutdown Bank Insertion Limit for Specification 3.1.5,
4. Control Bank Insertion Limits for Specification 3.1.6,
5. Axial Flux Difference limits for Specification 3.2.3,
6. Heat Flux Hot Channel Factor for Specification 3.2.1,
7. Nuclear Enthalpy Rise Hot Channel Factor limits for Specification 3.2.2,
8. Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,
9. Reactor Coolant System pressure, temperature, and flow departure from Nucleate Boiling (DNB) limits for Specification 3.4.1,
10. Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4,
11. Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1,
12. Spent fuel pool boron concentration limits for Specification 3.7.14,
13. SHUTDOWN MARGIN for Specification 3.1.1, and.
14. 31 EFPD Surveillance Penalty Factors for Specifications 3.2.1 and 3.2.2.

(continued)

McGuire Units 1 and 2 5.6-2 Amendment Nos.

5.6 Reportinq Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

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. WCAP-9272-P-A, 'WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," &MProprietary).
2. WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE,"' Proprietary).
3. BAW-1 01 68P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B&W Proprietary).
4. DPC-NE-201 1PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
5. DPC-NE-3001 PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
6. DPC-NF-201 OA, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design
7. DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology".
8. DPC-NE-3000PA, 'Thermal-Hydraulic Transient Analysis Methodology ," (DPC Proprietary).
9. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO -

3/SIMULATE-3 P ".

10. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).
11. DPC-NE-2005P-A, 'Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
12. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
13. WCAP-10054-P-A, 'Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," LW Proprietary).

(continued)

McGuire Units 1 and 2 5.6-3 Amendment Nos.

- 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

14. DPC-NE-2009-P-A, 'Westinghouse Fuel Transition Report," (DPC Proprietary).
15. WCAP-12945-P-A, Volume 1 and Volumes 2-5, " Code Qualification Document for Best-Estimate Loss of Coolant Analysis," Q(LA Proprietary).

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 number, report date or NRC SER 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 (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Ventilation Systems Heater Failure Report When a report is required by LCOs 3.6.10, "Annulus Ventilation System (AVS),"

or LCO 3.7.9, 'Control Room Area Ventilation System (CRAVS)," a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.

5.6.7 PAM Report When a report is required by LCO 3.3.3, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

McGuire Units 1 and 2 5.6-4 Amendment Nos.

- 5.6 Reporting Requirements 5.6.8 Steam Generator Tube Inspection Report

a. The number of tubes plugged in each steam generator shall be reported to the NRC within 15 days following completion of the program;
b. The complete results of the Steam Generator Tube Surveillance Program shall be reported to the NRC within 12 months following the completion of the program and shall include:
1. Number and extent of tubes inspected,
2. Location and percent of wall-thickness penetration for each indication of an imperfection, and
3. Identification of tubes plugged.

(continued)

McGuire Units 1 and 2 5.6-5 Amendment Nos.

Retrieved from "https://kanterella.com/w/index.php?title=ML050890323&oldid=2289634"