ML16294A253
| ML16294A253 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/12/2016 |
| From: | Duke Energy Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16294A253 (6) | |
Text
l Duke Energy Date: 1Qll2l2Q1§ Distribution:
Document Transmittal #: TR-NUC-MC-0043Q3
- 1. Boyer, Robert P DOCUMENT TRANSMITTAL FORM
Purpose:
~
- 2. Carroll, Michael E
- 3. Gardner, Troy R Released By:
- 4. Mc Ginnis, Vickie L Facility: MC~!.!IRI: N!.!CLliAR SIAIIQN Dukg i;mu:gy SUBJECT 13225 Hi9gCi Fem RQid
- 5. OPS HUMAN PERFORMANCE -
- 6. OPS TRNG MGR.
Issue MNS TS 5.6 Rev. 2 Amend. 288£267 Document Management
- 7. QATS-M§Q2DM
- 8. RESIDENT NRC INSPECT Hunm!'.l!villg. Nt 28Q78 I
- 9. SERV BLDG FILE ROOM -
MNSDCRM@duke-energy.com
- 10. U S NUC REG WASHINGTON, DC
- 11. USNRC
- 12. WESTINGHOUSE ELECTRIC CO LLC Page 1of1
- .+.. ' '*
- +~.1*\\T*;;**\\\\,...* *00c:u"°'ellt1[).* +*<***,*
- (!,;;'.
- <~~:~-:~Jr! ~ *. :\\;:,'.:
1 2
3 4
s 6
7 8
9 10 11 12 LicNlt.1c"Ts-s:6;~002PI5suE6' :F;f'.f'.ch::::: :::'F..,...*..*..*. FYIIE FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE Remarks: 8gmQllglR!i:Rlicg IS 5,§-l tb[y 5,§-5
~\\
- .. 0~
- ~.
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 5.6.3
N 0 TE--------------------------,-------------------
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 1 O CFR 50, Appendix I, Sections IV.8.2, IV.8.3, 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 Tectmical 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.
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 1 O CFR 50.36a and 1 O CFR Part 50, Appendix I,Section IV.B.1.
(continued)
McGuire Units 1 and 2 5.6-1 Amendment Nos. 226 / 208
__J
/
Reporting Requirements 5.6 i 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.
Moderator Temperature Coefficient BOL and EOL limits and 60 ppm and 300 ppm surveillance limits for Specification 3.1.3,
- 2.
3,
- 4.
- 5.
6.
- 7.
- 8.
- 9.
Shutdown Bank Insertion Limit for Specification 3.1.5, Control Bank Insertion Limits for Specification 3.1.6, Axial Flux Difference limits for Specification 3.2.3, Heat Flux Hot Channel Factor for Specification 3.2.1, Nuclear Enthalpy Rise Hot Channel Factor limits for Specification 3.2.2, Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,.
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. 226 / 208 I
5.6 Reporting Requirements Reporting Requirements 5.6 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," M[Proprietary).
- 2.
WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," Ml Proprietary).
- 3.
BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B& W Proprietary).
- 4.
DPC-NE-2011 PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
- 5.
DPC-NE-3001PA, "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-3002A1 "FSAR Chapter 15 System Transient Analysis 1 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 ".
McGuire Units 1 and 2
- 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 TAC03," (DPC Proprietary).
- 13.
WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," Ml Proprietary)
(continued) 5.6-3 Amendment Nos. 226 I 208 J
5.6 Reporting Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- c.
- 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," ('f:J_ Proprietary).
- 16.
DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASM0-4/SIMULATE-3 MOX," (DPC Proprietary).
- 17.
DPC-NE-1007-PA, "Conditional Exemption of the EOC MTC Measurement Methodology" (Duke and Westinghouse Proprietary).
- 18.
- WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995. (Westinghouse Proprietary).
- 19.
WCAP-12610-P-A & CENPD-404-P-A, Addendum 1-A, "Optimized ZIRLO',"July 2006. (Westinghouse 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).
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 SOM, 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. 288/267
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.8 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.9, Steam Generator (SG) Program. The report shall include:
- a.
- b.
- c.
- d.
- e.
- f.
- g.
McGuire Units 1 and 2 The scope of inspections performed on each SG, Degradation mechanisms found, Nondestructive examination techniques utilized for each degradation mechanism, Location, orientation (if linear), and measured sizes (if available) of service induced indications, Number of tubes plugged during the inspection outage for each degradation mechanism, The number and percentage of tubes plugged to date, and the
- 1 effective plugging percentage in each steam generator, and The results of condition monitoring, including the results of tube pulls and in-situ testing. *
(continued) 5.6-5 Amendment Nos. 284/263