ML071560535

Tech Spec Pages for Amendment 298 Regarding Alternate Source Term

ML071560535
Person / Time
Site:	Millstone
Issue date:	05/31/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Hughey J, NRR/DORL, 301-415-3204
Shared Package
ML0715605280	List: ML071450053 ML071560535
References
TAC MD2346
Download: ML071560535 (11)

Text

Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix, as revised through Amendment No. 298 , are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications.

Renewed License No. DPR-65 Amendment No. 298

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEA R HEAT RATE ................................................................................... 3/4 2-1 3/4.2.2 Deleted 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F .................. 3/4 2-9 3/4.2.4 AZIM UTHAL POW ER TILT ...................................................................... 3/4 2-10 3/4.2.5 Deleted 3/4.2.6 D NB M AR G IN ............................................................................................ 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION ..................................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IN STRUM ENTATION .................................................................................. 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION ............................ 3/4 3-24 Radiation Monitoring ................................... 3/4 3-24 Rem ote Shutdown Instrumentation .............................................................. 3/4 3-28 Accident M onitoring .................................................................................... 3/4 3-31 3/4.3.4 Deleted 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION .............................. 3/4 4-1 Startup and Power Operation ............................... 3/4 4-1 H O T STAN D B Y ......................................................................................... 3/4 4-la HO T SH U TD O WN ..................................................................................... 3/4 4-lb COLD SHUTDOWN - Reactor Coolant System Loops Filled ................... 3/4 4-ld COLD SHUTDOWN - Reactor Coolant System Loops Not Filled ............. 3/4 4-If Reactor Coolant Pumps - COLD SHUTDOWN ......................................... 3/4 4-1h MILLSTONE - UNIT 2 V Amendment No. 3-5, 3*-, 66, 69, 99, 4-04,449,183,4-8-5, 4-, 2-3-7, 5,249, 2-50, 2892, 29, 298

INDEX BASES" SECTION PAGE 3/4.0 A PPLIC A B ILITY ..................................................................................................... B X/4 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL ........................................................ .................... B 3/4 1-1 3/4.1.2 Deleted 3/4.1.3 MOVABLE CONTROL ASSEMBLIES ................................................... B 3/4 1-2 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE ............................................................................. B 3/4 2-1 3/4.2.2 Deleted 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Fr .............. B 3/4 2-1 3/4.2.4 AZIMUTHAL POWER TILT ................................................................... B 3/4 2-1 3/4.2.5 Deleted 3/4.2.6 DN B M AR GIN .......................................................................................... B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION .................................................... B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION ................. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION ................................. ................. B 3/4 3-2a 3/4.3.4 Deleted I MILLSTONE - UNIT 2 XI Amendment No. 33, 49, 404, 4-39, 8-5, 24-5, 2*-3, 9-1, 298

DEFINITIONS AZIMUTHAL POWER TILT - Tq 1.18 AZIMUTHAL POWER TILT shall be the difference between the maximum power generated in any core quadrant (upper or lower) and the average power of all quadrants in that half (upper or lower) of the core divided by the average power of all quadrants in that half (upper or lower) of the core.

AZIMUTHALPOWERTILT [Maximum power in any core quadrant (upper or lower)l L Average power of all quadrants (upper or lower) j DOSE EQUIVALENT 1-131 1.19 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (micro-curie/gram) which alone would produce the same CEDE-thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed under inhalation in Federal Guidance Report No. 11 (FGR1 1), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion."

E-AVERAGE DISINTEGRATION ENERGY 1.20 E shall be the average sum of the beta and gamma energies per disintegration (in MEV) f6r isotopes, other than iodines, with half lives greater than 15 minutes, making up,at least 95% of the total noniodine activity in the coolant.

STAGGERED TEST BASIS 1.21 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subinterval, and

b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

FREQUENCY NOTATION 1.22 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

MILLSTONE - UNIT 2 .1-4 Amendment No. 4-04, 6, 298

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or declare the channel inoperable.

b. With the number of OPERABLE channels less than the number of MINIMUM CHANNELS OPERABLE in Table 3.3-6, take the ACTION shown in Table 3.3-6.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-3.

4.3.3.1.2 DELETED 4.3.3.1.3 Verify the response time of the control room isolation channel at least once per 18 months.

MILLSTONE - UNIT 2 3/4 3-24 Amendment No. 4--5+, 24-, 282, 284, 29-4, 298

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 2 3/4 3-36 Amendment No. 245,-2-M, 284,298

THIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 2 3/4 3-37 Amendment No. 24-5, 280, 298

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be imirted to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE,

c. 75 GPD primary-to-secondary leakage through any one steam generator, and I

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.

APPLICABILITY: MODES 1, 2,3 and 4.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.,

b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System IDENTIFIED LEAKAGE and UNIDENTIFIED LEAKAGE shall be demonstrated to be within limits by performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation except when operating in the shutdown cooling mode.

4.4.6.2.2 Primary to secondary leakage shall be demonstrated to be within the above limits by performance of a primary to secondary leak rate determination at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The provisions of Specification 4.0.4 are not applicable for entry into MODE 4.

MILLSTONE - UNIT 2 3/4 4-9 Amendment No. 2-, 3-7, 82, 8-5, +O4-,

+--2-,-1-44, 24-5, 2-2g, 298

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment l*akage rates shall be limiteL:

a. An overall integrated leakage rate of< La, 0.50 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 54 psig.

b. A combined leakage rate of< 0.60 La for all penetrations and valves subject to Type B and C tests when pressurized to Pa-

c. A combined leakage rate of< 0.014 La for all penetrations that are secondary containment bypass leakage paths when pressurized to Pa-APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, or (c) with the combined bypass leakage rate exceeding 0.014 La, restore I

the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200"F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated in accordance with the Containment Leakage Rate Testing Program.

MILLSTONE - UNIT 2 3/4 6-2 Amendment No. 4-24, 56, 4--87, 2-0-3, 2-3.4,298

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION ACTION (continuedl MODES 5 and 6, or during irradiated fuel movement within containment or the spent fuel pool:**

d. With one Control Room Emergency Ventilation Train inoperable, restore the inoperable train to OPERABLE status within 7 days. After 7 days, either initiate and maintain operation of the remaining OPERABLE Control Room Emergency Ventilation Train in the recirculation mode of operation, or immediately suspend CORE ALTERATIONS, and the movement of irradiated fuel assemblies.

e. With both Control Room Emergency Ventilation Trains inoperable, or with the OPERABLE Control Room Emergency Ventilation Train required to be in the recirculation mode by ACTION d. not capable of being powered by an OPERABLE normal and emergency power source, immediately suspend CORE ALTERATIONS, and the movement of irradiated fuel assemblies.

• • In MODES 5 and 6, when a Control Room Emergency Ventilation Train is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of 3.7.6.1 Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and device(s) are OPERABLE, or likewise satisfy the requirements of the specification. Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then ACTION 3.7.6. .d or 3.7.6.L.e shall be invoked as applicable.

MILLSTONE - UNIT 2 3/4 7-16a Amendment No. 24-5, 24, 2-54, 284, 298

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

3. Verifying that control room air in-leakage is less than 200 SCFM with the Control Room Emergency Ventilation System operating in the recirculatiornfiltration modc.

f, After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 2500 cfm +/- 10%.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 2500 cfm +/- 10%.

MILLSTONE - UNIT 2 3/47-18 MAmendment No. 72, 4-00, 449, 228, 298