ML021420155

Technical Specifications, Amendment Relocating Designated Technical Specifications to the Licensing Requirements Manual and the Offsite Dose Calculation Manual

ML021420155
Person / Time
Site:	Beaver Valley
Issue date:	05/21/2002
From:	NRC/NRR/DLPM
To:
Collins D, NRR/DLPM, 415-1427
Shared Package
ML020530416	List: ML020530410 ML021420155
References
TAC MB2048, TAC MB2049
Download: ML021420155 (24)

Text

DPR-66 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.1.3.4 3/4.1.3.5 3/4.1.3.6 Rod Drop Time.............................

Shutdown Rod Insertion Limit..............

Control Rod Insertion Limits..............

PAGE 3/4 1-22 3/4 1-23 3/4 1-23a 3/4. 2 POWER 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.4 3/4.2.5 DISTRIBUTION LIMITS AXIAL FLUX DIFFERENCE HEAT FLUX HOT CHANNEL FACTOR..............

NUCLEAR ENTHALPY HOT CHANNEL FACTOR.......

QUADRANT POWER TILT RATIO.................

DNB PARAMETERS 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4 3/4 3/4 3/4 3/4 3/4 3-1 3/4 3-14 3/4.3.3.1 3/4.3.3.5 3/4.3.3.8 Radiation Monitoring......................

Remote Shutdown Instrumentation...........

Accident Monitoring Instrumentation.......

BEAVER VALLEY -

UNIT 1 2-1 2-5 2-8 2-10 2-12 3/4 3/4 3/4 3-33 3-44 3-50 Amendment No.250 IV

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.......................

3/4 10-2 3/4.10.3 PRESSURE/TEMPERATURE LIMITATION REACTOR CRITICALITY.......................

3/4 10-4 3/4.10.4 PHYSICS TEST..............................

3/4 10-6 3/4.10.5 NO FLOW TESTS.............................

3/4 10-7 BASES SECTION PAGE 3/4.0 APPLICABILITY....................................

B 3/4 0-i 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL..........................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS..........................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES....................

B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE B 3/4 2-1 BEAVER VALLEY -

UNIT 1 Amendment No.

250 IX

DPR-66 INDEX BASES SECTION PAGE 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS........................

B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO......................

B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 AND 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-2 3/4.3.3.1 Radiation Monitoring Instrumentation.........

B 3/4 3-2 3/4.3.3.5 Remote Shutdown Instrumentation...............

B 3/4 3-3 3/4.3.3.8 Accident Monitoring Instrumentation..........

B 3/4 3-3 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS......................

B 3/4 4-1 3/4.4.3 SAFETY VALVES..............................

B 3/4 4-ig 3/4.4.4 PRESSURIZER B 3/4 4-2 3/4.4.5 STEAM GENERATORS...........................

B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE................

B 3/4 4-3 3/4.4.6.1 Leakage Detection Instrumentation............

B 3/4 4-3 3/4.4.6.2 Operational Leakage........................

B 3/4 4-3d 3/4.4.6.3 Pressure Isolation Valve Leakage.............

B 3/4 4-3j BEAVER VALLEY -

UNIT 1 Amendment No. 250 X

DPR-66 BASES SECTION 3/4.9.3 3/4.9.4 3/4.9.8 3/4.9.9 3/4.9.10 AND 3/4.9.12 3/4.9.14 INDEX DECAY TIME................................

CONTAINMENT BUILDING PENETRATIONS.........

RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...............................

CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM....................................

3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL..............................

FUEL BUILDING VENTILATION SYSTEM..........

FUEL STORAGE -

SPENT FUEL STORAGE POOL....

PAGE B 3/4 B 3/4 9-1 9-1 B 3/4 9-3 B 3/4 9-3 B

B B

3/4 3/4 3/4 9-4 9-4 9-5 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.......................

3/4.10.3 PRESSURE/TEMPERATURE LIMITATIONS-REACTOR CRITICALITY...............................

3/4.10.4 PHYSICS TESTS.............................

3/4.10.5 NO FLOW TESTS.............................

B 3/4 10-1 B 3/4 10-1 B

B B

3/4 3/4 3/4 10-1 10-1 10-1 BEAVER VALLEY -

UNIT 1 Amendment No.

250 XlIl

DPR-66 INDEX DESIGN FEATURES SECTION 5.1 SITE LOCATION....................................

5.2 REACTOR CORE.....................................

5.3 FUEL STORAGE.....................................

ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY...................................

6.2 ORGANIZATION 6.2.1 6.2.2 Onsite and Offsite Organizations........

Unit Staff..............................

6.3 FACILITY STAFF QUALIFICATIONS....................

6.4 TRAINING,.......................................

6.5 DELETED 6.6 REPORTABLE EVENT ACTION..........................

6.7 SAFETY LIMIT VIOLATION...........................

BEAVER VALLEY -

UNIT 1 PAGE 5-1 5-1 5-1 PAGE 6-1 6-1 6-2 6-5 6-5 6-5 6-5 XIV Amendment No-250

DPR-66 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.8 PROCEDURES...................................................

6-6 6.9 REPORTING REQUIREMENTS...........................

6-17 6.9.1 Occupational Radiation Exposure Report..

6-17 6.9.2 Annual Radiological Environmental Operating Report........................

6-17 6.9.3 Annual Radioactive Effluent Release Report..................................

6-18 6.9.4 Monthly Operating Report...................

6-18 6.9.5 Core Operating Limits Report (COLR).....

6-18 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM....................

...... 6-20 6.12 HIGH RADIATION AREA.............................

6-23 6.13 PROCESS CONTROL PROGRAM (PCP)...........................

6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)..........

6-24 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS...............................

6-25 6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM........

6-25 6.18 TECHNICAL SPECIFICATIONS (TS)

BASES CONTROL PROGRAM 6-26 BEAVER VALLEY -

UNIT I Amendment No.250 XV

DPR-66 Table Index (cont.)

TABLE 3.3-11 4.3-7 4.4-1 4.4-2 4.4-3 4.4-12 3.7-1 3.7-2 4.7-2 3.8-1 3.9-1 Accident Monitoring Instrumentation Accident Monitoring Instrumentation Surveillance Requirements Minimum Number of Steam Generators to be Inspected During Inservice Inspection Steam Generator Tube Inspection Reactor Coolant System Pressure Isolation Valves Primary Coolant Specific Activity Sample and Analysis Program OPERABLE Main Steam Safety Valves versus Maximum Allowable Power Steam Line Safety Valves Per Loop Secondary Coolant System Specific Activity Sample and Analysis Program Battery Surveillance Requirements Beaver Valley Fuel Assembly Minimum Burnup vs.

Initial U235 Enrichment For Storage in Region 2 Spent Fuel Racks BEAVER VALLEY -

UNIT 1 TITLE PAGE 3/4 3-51 3/4 3-52 3/4 4-10g 3/4 4-10h 3/4 4-14b 3/4 4-20 3/4 7-2 3/4 7-4 3/4 7-9 3/4 8-9a 3/4 9-15 Amendment No.

250 XVI I

DPR-66 ADMINISTRATIVE CONTROLS

3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

c.

Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Holdup System, the quantity of radioactivity contained in Waste Gas Decay

Tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP)

ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure".

The liquid radwaste quantities shall be determined in accordance with Standard Review

Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures".

The program shall include:

1.

The limits for concentrations of hydrogen and oxygen in the Waste Gas Holdup System and a surveillance program to ensure the limits are maintained.

Such limits shall ensure that the concentration of hydrogen and oxygen is maintained below the flammability limits.

2.

A surveillance program to ensure that the quantity of radioactivity contained in each Waste Gas Decay Tank is less than the amount that would result in a whole body exposure of

> 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and

3.

A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners,

dikes, or

walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations greater than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

BEAVER VALLEY -

UNIT 1 Amendment No. 250 6-16

DPR-66 ADMINISTRATIVE CONTROLS The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

6.9 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

6.9.1 Occupational Radiation Exposure 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.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions (e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling).

This tabulation supplements the requirements of 10 CFR 20.2206.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD),

or film badge measurements.

Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

The report shall be submitted by April 30 of each year.

6.9.2 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 before 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 Part 50 Appendix I Sections IV.B.2, IV.B.3, and IV.C.

BEAVER VALLEY -

UNIT 1 Amendment No. 250 6-17

DPR-66 ADMINISTRATIVE CONTROLS 6.9.3 ANNUAL -RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for a multi-unit station.

The submittal should combine those sections that are 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 Annual Radioactive Effluent Release Report covering the operation of the unit during 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 (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I

Section IV.B.I.

6.9.4 MONTHLY OPERATING REPORT 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.

6.9.5 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:

2.1.1 Reactor Core Safety Limits 3.1.3.5 Shutdown Rod Insertion Limits 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference-Constant Axial Offset Control 3.2.2 Heat Flux Hot Channel Factor-FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor-F N 3.2.5 DNB Parameters 3.3.1.1 Reactor Trip System Instrumentation Overtemperature and Overpower AT Setpoint Parameter Values BEAVER VALLEY -

UNIT 1 Amendment No.

250 6-18

DPR-66 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (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:

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

July 1985 (Westinghouse Proprietary).

WCAP-8745-P-A, Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT trip functions, September 1986.

WCAP-10266-P-A Rev.

2/WCAP-11524-NP-A Rev.

2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"

Kabadi, J.

N.,

March 1987; including Addendum 1-A "Power Shape Sensitivity Studies" 12/87 and Addendum 2-A "BASH Methodology Improvements and Reliability Enhancements" 5/88.

WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT."

September 1974 (Westinghouse Proprietary).

T.

M.

Anderson to K.

Kniel (Chief of Core Performance

Branch, NRC)

January 31, 1980

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

NUREG-0800, Standard Review Plan, U.S.

Nuclear Regulatory Commission, Section 4.3, Nuclear

Design, July 1981.

Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),

Rev.

2, July 1981.

WCAP-12610-P-A, "VANTAGE+

Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).

As described in reference documents listed

above, when an initial assumed power level of 102% of rated thermal power is specified in a previously approved method, 100.6% of rated thermal power may be used when input for reactor thermal power measurement of feedwater flow is by the leading edge flow meter (LEFM).

Caldon, Inc.

Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFMWTM System,"

Revision 0,

March 1997.

BEAVER VALLEY -

UNIT 1 6-19 Amendment No. 250

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

Caldon, Inc.

Engineering Report-160P, "Supplement to Topical Report ER-80P:

Basis for a Power Uprate With the LEFMITM System" Revision 0, May 2000.

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 shutdown margin, 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.

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.

BEAVER VALLEY -

UNIT 1 6-20 (next page is 6-23)

Amendment No. 250

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.3.3.5 3/4.3.3.8 Remote Shutdown Instrumentation..............

Accident Monitoring Instrumentation..........

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 3/4.4.1.1 3/4.4.1.2 3/4.4.1.3 3/4.4.1.4 3/4.4.1.5 3/4.4.1.6 3/4.4.3 3/4.4.4 3/4.4.5 3/4.4.6 3/4.4.6.1 3/4.4.6.2 3/4.4.6.3 3/4.4.8 3/4.4.9 3/4.4.9.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Normal Operation.............................

Hot Standby..................................

Shutdown.....................................

.1 Loop Isolation Valves - Operating............

Isolated Loop Startup........................

Reactor Coolant Pump-Startup.................

SAFETY VALVES................................

PRESSURIZER..................................

STEAM GENERATORS.............................

REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Instrumentation............

Operational Leakage..........................

Pressure Isolation Valves....................

SPECIFIC ACTIVITY............................

PRESSURE/TEMPERATURE LIMITS Reactor Coolant System.......................

BEAVER VALLEY -

UNIT 2 PAGE 3/4 3-52 3/4 3-57 3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-5 3/4 4-6 3/4 4-7 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-17 3/4 4-19 3/4 4-21 3/4 4-27 3/4 4-30 Amendment No. 130 V

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM -

3/4.9.14 3/4.9.15 FUEL MOVEMENT...............................

SPENT FUEL POOL STORAGE.....................

FUEL STORAGE POOL BORON CONCENTRATION.......

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.............................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.........................

3/4.10.3 PHYSICS TESTS...............................

3/4.10.4 REACTOR COOLANT LOOPS.......................

3/4 3/4 3/4 9-13 9-15 9-17 3/4 10-1 3/4 3/4 3/4 10-2 10-3 10-4 APPLICABILITY......................................

REACTIVITY CONTROL SYSTEMS

.1 BORATION CONTROL............................

.2 BORATION SYSTEMS............................

.3 MOVABLE CONTROL ASSEMBLIES..................

PAGE B 3/4 0-1 B 3/4 1-1 B 3/4 1-2 B 3/4 1-4 BEAVER VALLEY -

UNIT 2 BASES SECTI(

3/4.0 3/4.1 3/4.1 3/4.1 3/4.1 ON Amendment No. 130 IX

NPF-73 INDEX BASES SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS FQ(Z)

AND FRH............

3/4.2.4 3/4.2.5 QUADRANT POWER TILT RATIO....................

DNB PARAMETERS...............................

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..........

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......................

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation.........

3/4.3.3.5 Remote Shutdown Instrumentation..............

3/4.3.3.8 Accident Monitoring Instrumentation..........

PAGE B 3/4 2-1 B

B B

3/4 3/4 3/4 2-2 2-5 2-5 B 3/4 3-1 B 3/4 3-1 B

B B

3/4 3/4 3/4 3-10 3-11 3-11 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION..................................

B 3/4 4-1 3/4.4.3 SAFETY VALVES................................

B 3/4 4-2 3/4.4.4 PRESSURIZER..................................

B 3/4 4-2 BEAVER VALLEY -

UNIT 2 X

Amendment No. 130

NPF-73 INDEX BASES SECTION 3/4.9.12 3/4.9.14 3/4.9.15 FUEL BUILDING VENTILATION SYSTEM..........

SPENT FUEL POOL STORAGE...................

FUEL STORAGE POOL BORON CONCENTRATION.....

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.......................

3/4.10.3 PHYSICS TESTS.............................

3/4.10.4 REACTOR COOLANT LOOPS.....................

PAGE B 3/4 9-8 B 3/4 9-9 B 3/4 9-10 B 3/4 10-1 B

B B

3/4 3/4 3/4 10-1 10-1 10-1 DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION......................................

5-1 5.2 REACTOR CORE.......................................

5.3 FUEL STORAGE.......................................

5-1 5-1 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.....................................

6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS..........

BEAVER VALLEY -

UNIT 2 6-1 Amendment No. 130 XIII

NPF-73 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.2.2 UNIT STAFF..............................

6-2 6.3 FACILITY STAFF QUALIFICATIONS....................

6-6 6.4 TRAINING.........................................

6-6 6.5 DELETED 6.6 REPORTABLE EVENT ACTION..........................

6-6 6.7 SAFETY LIMIT VIOLATION...........................

6-6 6.8 PROCEDURES.......................................

6-7 6.9 REPORTING REQUIREMENTS 6.9.1 Occupational Radiation Exposure Report..

6-17 6.9.2 Annual Radiological Environmental Operating Report........................

6-18 6.9.3 "nnual Radioactive Effluent Release Report..................................

6-18 6.9.4 Monthly Operating Report......................

6-19 6.9.5 Core Operating Limits Report...............

6-19 6.10 DELETED 6.11 RADIATION PROTECTION PROGRAM...........................

6-21 BEAVER VALLEY -

UNIT 2 Amendment No.130 XIV

NPF-73 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.12 HIGH RADIATION AREA.............................

6-21 6.13 PROCESS CONTROL PROGRAM (PCP).......................

6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM).............

6-25 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid).................

6-25 6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM........

6-25 6.18 TECHNICAL SPECIFICATIONS (TS)

BASES CONTROL PROGRAM.........................................

6-26 BEAVER VALLEY -

UNIT 2 Amendment No. 130 XV

NPF-73 ADMINISTRATIVE CONTROLS PROCEDURES (Continued)

10)

Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

b.

Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring,

sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the

ODCM,

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

c.

Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Waste Gas Holdup System, the quantity of radioactivity contained in Gaseous Waste Storage Tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP)

ETSB 11-5, "Postulated Radioactive Release due to Waste Gas System Leak or Failure".

The liquid radwaste quantities shall be determined in accordance with Standard Review

Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures".

BEAVER VALLEY -

UNIT 2 Amendment No.130 6-16

NPF-73 ADMINISTRATIVE CONTROLS PROCEDURES (Continued)

The program shall include:

1.

The limits for concentrations of hydrogen and oxygen in the Waste Gas Holdup System and a surveillance program to ensure the limits are maintained.

Such limits shall ensure that the concentration of hydrogen and oxygen is maintained below the flammability limits.

2.

A surveillance program to ensure that the quantity of radioactivity contained in each connected group of Gaseous Waste Storage Tanks is less than the amount that would result in a whole body exposure of > 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents, and

3.

A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners,

dikes, or

walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations greater than the limits of 10 CFR 20, Appendix B, Table 2,

Column 2,

at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

6.9 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

6.9.1 Occupational Radiation Exposure 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.

BEAVER VALLEY UNIT 2 6-17 Amendment No.130

NPF-73 ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposure greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions (e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling).

This tabulation supplements the requirements of 10 CFR 20.2206.

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

The report shall be submitted by April 30 of each year.

6.9.2 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 before 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 Part 50, Appendix I Sections IV.B.2, IV.B.3, and IV.C.

6.9.3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A

single submittal may be made for a

multi-unit station.

The submittal should combine those sections that are 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.

Amendment No.130 BEAVER VALLEY UNIT 2 6-18

NPF-73 ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

The Annual Radioactive Effluent Release Report covering the operation of the unit during 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 (PCP) and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I

Section IV.B.l.

6.9.4 MONTHLY OPERATING REPORT 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.

6.9.5 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:

2.1.1 Reactor Core Safety Limits 3.1.3.5 Shutdown Rod Insertion Limits 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference-Constant Axial Offset Control 3.2.2 Heat Flux Hot Channel Factor-FQ(Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor-F NAH 3.2.5 DNB Parameter 3.3.1.1 Reactor Trip System Instrumentation Overtemperature and Overpower AT setpoint parameter values

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:

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

July 1985 (Westinghouse Proprietary).

BEAVER VALLEY -

UNIT 2 Amendment No.130 6-19

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

WCAP-8745-P-A, "Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT Trip Functions," September 1986.

WCAP-10266-P-A Rev.

2/WCAP-11524-NP-A Rev.

2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"

Kabadi, J.

N.,

March 1987; including Addendum I-A "Power Shape Sensitivity Studies" 12/87 and Addendum 2-A "BASH Methodology Improvements and Reliability Enhancements" 5/88.

WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT."

September 1974 (Westinghouse Proprietary).

T.

M.

Anderson to K.

Kniel (Chief of Core Performance

Branch, NRC)

January 31, 1980

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

NUREG-0800, Standard Review Plan, U.S.

Nuclear Regulatory Commission, Section 4.3, Nuclear

Design, July 1981.

Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),

Rev.

2, July 1981.

WCAP-12610-P-A, "VANTAGE+

Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).

As described in reference documents listed

above, when an initial assumed power level of 102% of rated thermal power is specified in a previously approved method, 100.6% of rated thermal power may be used when input for reactor thermal power measurement of feedwater flow is by the leading edge flow meter (LEFM).

Caldon, Inc.

Engineering Report-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM4 TM System,"

Revision 0,

March 1997.

Caldon, Inc.

Engineering Report-160P, "Supplement to Topical Report ER-80P:

Basis for a Power Uprate With the LEFM4Tm System,"

Revision 0, May 2000.

BEAVER VALLEY -

UNIT 2 Amendment No.

130 6-20

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

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 shutdown margin, 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.

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.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.1601 of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring BEAVER VALLEY -

UNIT 2 Amendment No. 130 6-21