ML022750119
| ML022750119 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/01/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| Martin R, NRR/DLPM, 415-1493 | |
| Shared Package | |
| ML022750477 | List: |
| References | |
| TAC MB3222, TAC MB3223 | |
| Download: ML022750119 (4) | |
Text
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2
'Annual Radioloqical Environmental Operating Report (continued)
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 I 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.
5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
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.
Moderator Temperature Coefficient BOL and EOL limits and 60 ppm and 300 ppm surveillance limits for Specification 3.1.3, (continued)
Amendment Nos. 208 & 189 McGuire Units 1 and 2 5.6.2
5.6 Reporting Requirements "5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 2.
Shutdown Bank Insertion Limit for Specification 3.1.5,
- 3.
Control Bank Insertion Limits for Specification 3.1.6,
- 4.
Axial Flux Difference limits for Specification 3.2.3,
- 5.
Heat Flux Hot Channel Factor for Specification 3.2.1,
- 6.
Nuclear Enthalpy Rise Hot Channel Factor limits for Specification 3.2.2,
- 7.
Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,
- 8.
Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4,
- 9.
Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1,
- 10.
Spent fuel pool boron concentration limits for Specification 3.7.14,
- 11.
SHUTDOWN MARGIN for Specification 3.1.1, and
- 12.
31 EFPD Surveillance Penalty Factors for Specifications 3.2.1 and 3.2.2.
- 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," & Proprietary).
- 2.
WCAP-1 0266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," (W Proprietary).
- 3.
BAW-10168P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," (B&W Proprietary).
(continued)
Amendment Nos. 208 & 189 McGuire Units 1 and 2 5.6-3
FQ(X,Y,Z)
B 3.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the FQ(X,Y,Z) limit with the last FMQ(X,Y,Z) increased by the appropriate factor specified in the COLR or to evaluate FQ(X,Y,Z) prior to the projected point in time when the extrapolated values are expected to exceed the extrapolated limits.
These alternative requirements attempt to prevent FQ(X,Y,Z) from exceeding its limit for any significant period of time without detection using the best available data. FM0(X,Y,Z) is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending. Also, extrapolation of FMo(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within +/-2% of the core height about the demand position of the rod tip.
FQ(X,Y,Z) is verified at power levels > 10% RTP above the THERMAL POWER of its last verification, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions to ensure that F0(X,Y,Z) is within its limit at higher power levels.
The Surveillance Frequency of 31 EFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of FQ(X,Y,Z) evaluations.
The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.
REFERENCES
- 1.
- 2.
UFSAR Section 15.4.8.
- 3.
10 CFR 50, Appendix A, GDC 26.
- 4.
10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 5.
DPC-NE-201 1 PA "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors".
McGuire Units 1 and 2 Revision No. 34 B 3.2.1-11
AFD B 3.2.3 BASES SURVEILLANCE REQUIREMENTS (continued)
This Surveillance verifies that the AFD, as indicated by the NIS excore channel, is within its specified limits and is consistent with the status of the AFD monitor alarm. With the AFD monitor alarm inoperable, the AFD is monitored every hour to detect operation outside its limit. The Frequency of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on operating experience regarding the amount of time required to vary the AFD, and the fact that the AFD is closely monitored. With the AFD monitor alarm OPERABLE, the Surveillance Frequency of 7 days is adequate considering that the AFD is monitored by a computer and any deviation from requirements is alarmed.
REFERENCES
- 1.
DPC-NE-201 1 PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors".
- 2.
10 CFR 50.36, Technical Specifications, (c)(2)(ii).
- 3.
UFSAR, Chapter 7.
Revision No. 34 McGuire Units 1 and 2 B 3.2.3-4