ML051660081
| ML051660081 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/03/2005 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Christian D Dominion Nuclear Connecticut |
| References | |
| TAC MC5430, TAC MC5431, TAC MC5456 | |
| Download: ML051660081 (9) | |
Text
Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements The following reports shall be submitted in accordance with 10CFR50.4.
5.7.1 Deleted (continued)
Millstone - Unit I 5.0-1 5 Amendment No. 406, 442.
114
ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS .................................... 6-16 STARTUP REPORTS ................................... 6-16 ANNUAL REPORTS ................................... 6-17 ANNUAL RADIOLOGICAL REPORT ................................... 6-18 CORE OPERATING LIMITS REPORT ................................... ; 6-18 6.9.2 SPECIAL REPORTS ................................... 6-19 6.1 0 DELETED 6.11 RADIATION-PROTECTION PROGRAM ................................... 6-20 6.12 HIGH RADIATION AREA .................................... 6-20 6.13 SYSTEMS INTEGRITY ................................... 6-23 6.14 IODINE MONITORING ................................... 6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFST DOSE CALCULATION MANUAL (REMODCM ................................... 6-24 6.16 RADIOACTIVE WASTE TREATMENT ................................... 6-24 6.17 SECONDARY WATER CHEMISTRY ............... .. ..................... 6-25 6.1-8 DELETED 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM . ...........................6-26 6.20 RADIOACTIVE EFFULENT CONTROLS PROGRAM ............................................... 6-26 6.21 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............. ............ 6-28 6.22 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM ........... ......... 6-28 6.23 TECHNICAL SPECIFICATION aTS) BASES CONTROL PROGRAM .......... ............ 6-28 6.24 DIESEL FUEL OIL TEST PROGRAM .......................... ............................. 6-29 MILLSTONE - UNIT 2 XVII Amendment No. -9, -X, 63,66,403, 404,444,44,,4B4,463,469,239,260,
- 6, 264, -2 , 26, 2,4, 286
ADMINISTRATIVE CONTROLS ANNUAL REPORTS' 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4 6.9.1 .5a.DELETED I 6.9.1.5b The complete results of steam generator tube inservice inspections performed during the report period (reference Specification 4.4.5.1.5.b). The report covering the previous calendar year shall be submitted prior to March 1 of each year.
6.9.1 .5c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1)
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3)
Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-13 1 concentration and one other radioiodine isotope concentration in microcuries per gram as a fuiction of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit. The report covering the previous calendar year shall be submitted prior to March 1 of each year.
I A single submittal may-be made fora multiple unit station. The submittal should combine those sections that are common to all units at the station.
MILLSTONE - UNIT 2 6-17 Amendment No. 36, 114, 4-5, 46, q 0, o6, 286
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL REPORTS 6.9.1 .6a -ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- -- NOTE -----------------
A single submittal may be made for a multiple unit station. The submittal shall 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 I 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 Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the REMODCM, as well as summarized and tabulated results of these analyses and measurements. 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 the next annual report.
6.9.1 .6b RADIOACTIVE EFFLUENT RELEASE REPORT
- ---------- NOTE ----
A single submittal may be made for a multiple unit station. The submittal shall 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 50.3 6a.
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 REMODCM and in confornmance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.I.
6.9.1.7 Deleted MILLSTONE - UNIT 2 6-18 Amendment Nos. 3X, 96, 444, 44, 445, 449, 420, 434,44&, 4,46, 2H-, 4 p46, I, A, 286
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.8 a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.
3/4.1.1.1 SHUTDOWN MARGIN (SDM) 3/4.1.1.4 Moderator Temperature Coefficient 3/4.1.3.6 Regulating CEA Insertion Limits 3/4.2.1 Linear Heat Rate 3/4.2.3 Total Integrated Radial Peaking Factor - FTr 3/4.2.6 DNB Margin
- 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 I and 2, "Reactor Analysis System for PWRs Volume 1 - Methodology Description, Volume 2 -Benchmarking Results,"
Siemens Power Corporation.
- 2) ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events,"
Advanced Nuclear Fuels.
- 3) XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company.
- 4) XN-75-32(P)(A) Supplements I through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company.
- 6) EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.
- 7) XN-NF-44(NP)(A), "A Generic Analysis of the Control rod Ejection
-Transient for Pressurized water reactors;" Exxon Nuclear Company. -
MILLSTONE - UNIT 2 6-18a Amendment No. 6,9-, .4-04,4-,4-5, 449, 440,44-2, 44&, 464,469, 249, 286 2 v s EVA, 24VA 286
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.8 PROCEDURES AND PROGRAMS ....................................................... 6-14 6.9 REPORTING REQUIREMENTS ........................ ............................... 6-17 6.9.1 ROUTINE REPORTS .6-17 Startup Report .6-17 Annual Reports .6-18 Annual Radiological Environmental Operating Report .6-19 Annual Radioactive Effluent Release Report .6-19 Core Operating Limits Report .6-19a 6.9.2 SPECIAL REPORTS .. 6-21 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM ....................................................... 6-21 6.12 HIGH RADIATION AREA ....................................................... 6-21 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM' ....................................................... 6-24 6.14 RADIOACTIVE WASTE TREATMENT ........................... ............................ 6-24 6.15 RADIOACTIVE EFFLUENT CONTROLS PROGRAM ................................................ 6-25 6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ......................... 6-26 6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM .................... 6-26 6.18 TECHNICAL SPECIFICATIONS (TS) BASES CONTROL PROGRAM1 ..................... 6-26 6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT ....................................................... 6-27 MILLSTONE - UNIT 3 xix Amendment No. i6,69,86, 47-, 1, 244,.4-, 4-5, 223
ADMINISTRATIVE CONTROLS Startup Reports shall be submitted within: (l) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS*
6.9.1.2 Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted in accordance with 10 CFR 50.4.
6.9.1.2a. Deleted 6.9.1.2b.The results of specific activity analyses in which the reactor coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (I) Reactorpower history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (pCi/gm) and one other radioiodine isotope concentration (pCi/gm) as a function of time for the
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
MILLSTONE - UNIT 3 6-18 Amendment No. 69, 245, 223
ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the reactor coolant exceeded the radioiodine limit. The report covering the previous calendar year shall be submitted prior to March 1 of each year.
6.9.1.3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
NOTE ----------------
A single submittal may be made for a multiple unit station. The submittal shall 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 1 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 Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), and in 10 CFR Part 50, Appendix I, Sections IV.B.2, IV.B.3, and 1V.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the REMODCM, as well as summarized and tabulated results of these analyses and measurements. 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 the next annual report.
6.9.1.4 RADIOACTIVE EFFLUENT RELEASE REPORT
NOTE ---------- --
A single submittal may be made for a multiple unit station. The submittal shall 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 REMODCM and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section W.B.I.
MILLSTONE - UNIT 3 6-19 Amendment No. 24, 3-, 69, 86, 4-S, 223 A4
ADMINISTRATIVE CONTROLS 6.9.1.5 Deleted I CORE OPERATING LIMITS REPORT 6.9.1.6 a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
- 1. Overtemperature AT and Overpower AT setpoint parameters for Specification 2.2.1,
- 2. Shutdown Margin for Specifications 3/4.1.1.1.1, 3/4.1.1.1.2, and 3/4.1.1.2,
- 3. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.13.
MILLSTONE - UNIT 3 6-19a Amendment No. 24, 3, 69, 6, 4I, 223 4,