ML070250018

Technical Specification Updated List of Documents Describing Approved Analytical Methods Used to Determine Core Operating Limits

ML070250018
Person / Time
Site:	Millstone
Issue date:	01/23/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
nerses V, NRR//DORL, 415-1484
Shared Package
ML063480533	List: ML063480536 ML070250018
References
TAC MC0706
Download: ML070250018 (5)

Text

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1 R O U TIN E REPO RT S............................................................................................... 6-16 STA RTU P REPO RTS ............................................................................................... 6-16 ANNUAL REPORTS ......................................... 6-17 ANNUAL RADIOLOGICAL REPORT .................................................................... 6-18 CORE OPERATING LIMITS REPORT ............................................................... 6-18a 6.9.2 SPE C IA L REPO RT S ................................................................................................ 6-20 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM ............................ 6-20 6.12 HIG H RA D IATION AREA ......................................................................................... 6-20a 6.13 SYSTEMS INTEGRITY ........................................ 6-23 6.14 IO D INE M O N ITO RIN G ............................................................................................. 6-23 6.15 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)... ............................................. 6-24 6.16 RADIOACTIVE WASTE TREATMENT .................................................................... 6-24 6.17 SECONDARY WATER CHEMISTRY ....................................................................... 6-25 6.18 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 (TS) BASES CONTROL PROGRAM ................... 6-28 6.24 DIESEL FUEL OIL TEST PROGRAM ....................................................................... 6-29 MILLSTONE - UNIT 2 XVII Amendment No. -79,46,63,66,403, 4704, 4-44, 449, 4-5-, 4-6,4-69, 2-39, -MO, 2-6-2, 64, 270, 2,-6,27-7, 2-96, ,

295

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing 176 rods. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal average enrichment of 4.85 weight percent ofU-235. A fuel rod shall have a maximum enrichment of 5.0 weight percent of U-235.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 control element assemblies. The control element assemblies shall be designed and maintained in accordance with the design provisions contained in Section 3.0 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.4 DELETED MILLSTONE - UNIT 2 5-4 Amendment No. 3,8, 4-39, 446, 204, 216, 27, 2-4, 280, 295

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (CONT.)

8) XN-NF-62 1(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nu'clear Company.

9) XN-NF-82-06(P)(A), and Supplements 2, 4 and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company.

10) ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Bumups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation.

11) XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company.

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

13) EMF-1961 (P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation.

14) EMF-2130(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP.

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

16) EMF 116(P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.

c. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

MILLSTONE - UNIT 2 6-19 Amendment No. 4-49, +63, 2-2-28, 2-59 60, 2 -1+,21-,

295

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy to the Regional Administrator, Region I, and one copy to the NRC Resident Inspector within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Deleted

b. Deleted

c. Deleted

d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e. Deleted

f. Deleted

g. RCS Overpressure Mitigation, Specification 3.4.9.3.

h. Deleted

i. Tendon Surveillance Report, Specification 6.25

j. Steam Generator Tube Inspection, Specification 4.4.5.1.5.

k. Accident Monitoring Instrumentation, Specification 3.3.3.8.

1. Radiation Monitoring Instrumentation, Specification 3.3.3.1.

m. Deleted 6.10 Deleted.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving

_personnel radiation exposure.

MILLSTONE - UNIT 2 6-20 Amendment No. 9, -,6, 4-04, 444-, +-48, 4-62,4-63,494,239,24-0,266, 2-7-6, 49, 295

ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and ( b ) of 10 CFR Part 20:

6.12.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area, Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of a Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

MILLSTONE - UNIT 2A 6-20a Amendment No.2951