Text

Tech Spec Pages for Amendments 291 and 229 Regarding Administrative Changes to Technical Specifications
	ML060760208
Person / Time
Site:	Millstone
Issue date:	03/16/2006
From:	; Plant Licensing Branch III-2
To:	;
References
	TAC MC6315, TAC MC6316
	Download: ML060760208 (79)
	v • d • e

INDEX LIMITING CONI)ITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLTCABILITY...............

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 REACTIVITY CONTROL.3/4 1-1 Shutdown Margin (SDM).

3/4 1-1 DELETED.3/4 1-2 Reactivity Balance.3/4 1-3 Boron Dilution.3/4 1-4 Moderator Temperature Coefficient (MTC).3/4 1-5 Minimum Temperature for Criticality.3/4 1-7 3/4.1.2 BORATION SYSTEMS...........................

3/4 1-8 DELETED.3/4 1-8 DELETED.3/4 1-9 DELETED.................................................................................................... 3/4 1-11 DELETED.3/4 1-13 DELETED.................................................................................................... 3/4 1-14 DELETED.................................................................................................... 3/4 1-15 DELE TED.................................................................................................... 3/4 1-16 DELETED.................................................................................................... 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.3/4 1-20 CEA Group Position.3/4 1-20 Position Indicator Channels.3/4 1-24 CEA Drop Time.3/4 1-26 Shutdown CEA Insertion Limit.3/4 1-27 Regulating CEA Insertion Limits.3/4 1-28 Control Rod Drive Mechanisms.3/4 1-31 MILLSTONE - UNIT 2 IV Amendment No. 3, 4-04, 4-16, 4-5, 291'

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE..............................................

3/4 2-1 3/4.2.2 Deleted T

3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Fr 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT..........................................

3/4 2-10 3/4.2.5 Deleted 3/4.2.6 DNB MARGIN...................................

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 INSTRUMENTATION............................................... 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION...............................................

3/4 3-24 Radiation Monitoring...............................................

3/4 3-24 Remote Shutdown Instrumentation...............................................

3/4 3-28 Accident Monitoring............................................... 3/4 3-31 3/4.3.4 CONTAINMENT PURGE VALVE ISOLATION SIGNAL....................... 3/4 3-36 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 HOT STANDBY..............................................

3/4 4-1 a HOT SHUTDOWN...............................................

3/4 4-lb COLD SHUTDOWN - Reactor Coolant System Loops Filled................... 3/4 4-Id 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-,3, 66, 69, 99, 404,439, 4-3, 4-,

49+, 23,724249, 31O, 2, 291

INDEX BASES SECTION 3/4.0 APPLICABILITY.....................................................................................................

PAGE B 3/4 0-1 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 T

3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F B 3/4 2-1 3/4.2.4 AZIMUTHAL POWER TILT

.B3/42-1 3/4.2.5 Deleted 3/4.2.6 DNB M ARGIN.......................................................................................... 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 CONTAINMENT PURGE VALVE ISOLATION SIGNAL..................... B 3/4 3-6 MILLSTONE - UNIT 2 XI Amendment No. 3, 49,4-G4,4-39,-18, 245, 28a, 291

INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.......................... B 3/4 4-1 3/4.4.2 SAFETY VALVES.......................................

B 3/4 4-id 3/4.4.3 RELIEF VALVES.......................................

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

B 3/4 4-2a 3/4.4.5 STEAM GENERATORS.......................................

B 3/4 4-2a 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE....................................... B 3/4 4-3 3/4.4.7 DELETED.......................................

B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY............................................................................... B 3/4 4-4 3/4.4.9 PRESSURE/TEMPERATURE LIMITS.................................................... B 3/4 4-5 3/4.4.10 DELETED........................................

B 3/4 4-7 3/4.4.11 DELETED.......................................

B 3/4 4-8 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS.....

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS......

B 3/4 5-2 3/4.5.4 REFUELING WATER STORAGE TANK (RWST).....

B 3/4 5-2d 3/4.5.5 TRISODIUM PHOSPHATE (TSP).....

B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.....................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.............................. B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES..................................... B 3/4 6-3a 3/4.6.4 COMBUSTIBLE GAS CONTROL........................................................... B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT...........

.......................... B 3/4 6-5 MILLSTONE - UNIT 2 XII Amendment No. 66, 69,

, 44-04, 4-,

i-8, 204, 264, 266, 291

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE............................................... B 3/4 7-1 3/4.7.2 DELETED..............................................

B 3/4 7-3 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM........

B 3/4 7-3a 3/4.7.4 SERVICE WATER SYSTEM.................

............................. B 3/4 7-3c 3/4.7.5 DELETED..............................................

B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM............. B 3/4 7-4 3/4.7.7 DELETED...............................................

B 3/4 7-5 3/4.7.8 SNUBBERS..............................................

B 3/4 7-5 3/4.7.9 DELETED..............................................

B 3/4 7-6 3/4.7.10 DELETED..............................................

B 3/4 7-7 3/4.7.11 ULTIMATE HEAT SINK.............

.................................. B 3/4 7-7 3/4.8 ELECTRICAL. POWER SYSTEMS....

B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.B 3/4 9-1 3/4.9.2 INSTRUMENTATION.B 3/4 9-1 3/4.9.3 DECAY TIM E.......................................................................................... B 3/4 9-la 3/4.9.4 CONTAINMENT PENETRATIONS.B 3/4 9-la 3/4.9.5 DELETED.B 3/4 9-la 3/4.9.6 DELETED.B 3/4 9-2 3/4.9.7 DELETED.

B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLING RECIRCULATION............

B 3/4 9-2 MILLSTONE - UNIT 2 XI[I Amendment No. i3, 4, 69,96,404,

44i, 4-91, 240, 22, 291

INDEX BASES SECTION PAGE 3/4.9.9 and 3/4.9.10 DELETED...............................................

B 3/4 9-2 3/4.9.11 and 3/4.9.12 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL WATER LEVEL...............................................

B 3/4 9-2b 3/4.9.13 DELETED.B 3/4 9-3 3/4.9.14 DELETED......

B 3/4 9-3 3/4.9.15 STORAGE POOL AREA VENTILATION SYSTEM.B 3/4 9-3 3/4.9.16 SHIELDED CASK................................................................................... B 3/4 9-3b 3/4.9.17 SPENT FUEL POOL BORON CONCENTRATION.B 3/4 9-3b 3/4.9.18 SPENT FUEL POOL - STORAGE.B 3/4 9-4 3/4.9.19 SPENT FUEL POOL - STORAGE PATTERN.B 3/4 9-4 3/4.9.20 SPENT FUEL POOL - CONSOLIDATION.B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................................................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS.B 3/4 10-1 3/4.10.3 DELETED......

B 3/4 10-1 3/4.10.4 DELETED.B 3/4 10-1 3/4.10.5 DELETED.B 3/4 10-1 3/4.11 DELETED 3/4.11.1 DELETED.................

B 3/4 11-1 3/4.11.2 DELETED.................

B 3/4 11-1 3/4.11.3 DELETED.................

B 3/4 11-1 MILLSTONE - UNIT 2 X1V Amendment No. 69, 404, 409, 44-7, 453, 45i, 4-8i, 245, 2i, 274, H0, 291

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION.........................

5-1 5.2 DELETED 5.3 REACTOR CORE Fuel Assemblies.........................

5-4 Control Element Assemblies.........................

5-4 5.4 DELETED 5.5 DELETED 5.6 FUEL STORAGE Criticality.........................

5-5 Drainage.........................

5-5a Capacity..........................................................................................................................

5-Sa 5.7 DELETED 5.8 DELETED 5.9 DELETED MILLSTONE - UNIT 2 XV Amendment No. 4-0-4, 9, 270, 291

INDEX 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........................................................... 6-18a 6.9.2 SPECIAL REPORTS.........................................................

6-19 6.10 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 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) 3ASES CONTROL PROGRAM................... 6-28 6.24 DIESEL FUEL OIL TEST PROGRAM..........................................................

6-29 MILLSTONE - UNIT 2 XVII Amendment No. -79, 6, 63, 66, 4-03, 4-04,444-, 44&, 4,,-,6,469,239, 250, 262,264, 270, 276, 2i, 26, 291

DEFINITIONS VENTING 1.35 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING Vent, used in system names, does not imply a VENTING process.

MEMBER(S) OF THE PUBLIC 1.36 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

The term "REAL MEMBER OF THE PUBLIC" means an individual who is exposed to existing dose pathways at one particular location.

SITE BOUNDARY 1.37 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.

UNRESTRICTED AREA 1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial institutional and/or recreational purposes.

STORAGE PATTERN 1.39 The Region B spent fuel racks contain a cell blocking device in every 4th rack location for

.administrative control. This 4th location will be referred to as the blocked location. A STORAGE PATTERN refers to a blocked location and all adjacent and diagonal cell locations surrounding the blocked location within the respective region.

MILLSTONE - UNIT 2 I -81 Amendment No. 404, 4417, 445,1 4, 291

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING CONDITION FOR OPERATION 3.1.3.1 All CEAs shall be OPERABLE with each CEA of a given group positioned within 10 steps (indicated position) of all other CEAs in its group, and the CEA Motion Inhibit and the CEA Deviation Circuit shall be OPERABLE.

APPLICABILITY:

MODES 1(1) and 2(1).

ACTION:

INOPERABLE EQUIPMENT REQUIRED ACTION A. One or more CEAs trippable A. I Reduce THERMAL POWER to < 70% of the and misaligned from all other maximum allowable THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CEAs in its group by > 10 steps and restore CEA(s) misalignment within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or and < 20 steps.

otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OR One CEA trippable and misaligned from all other CEAs in its group by 2 20 steps.

B. CEA Motion Inhibit inoperable. B.l Verify the indicated position of each CEA to be within 10 steps of all other CEAs in its group within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter, and restore CEA Motion Inhibit to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

OR B.2(2) Place and maintain the CEA drive system mode switch in either the "off' or "manual" position, and withdraw all CEAs in group 7 to 2 172 steps within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or otherwise be in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

(I) See Special Test Exception 3.10.2 (2) Performance of ACTION B.2 is allowed only when not in conflict with either Required Action I

A.1 orC.l.

MILLSTONE - UNIT 2 3/4 1-20 Amendment No. -3, i80, 291

REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE MECHANISMS LIMITING CONDITION FOR OPERATION 3.1.3.7 The control rod drive mechanisms shall be de-energized.

APPLICABILITY:

MODES 3*, 4, 5 and 6, whenever the RCS boron concentration is less than refueling concentration of Specification 3.9.1.

ACTION:

With any of the control rod drive mechanisms energized, restore the mechanisms to their de-energized state within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or immediately open the reactor trip circuit breakers:

SURVEILLANCE REQUIREMENTS 4.1.3.7 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The control rod drive mechanisms shall be verified to be de-energized at least once per

The control rod drive mechanisms may be energized for MODE 3 as long as 4 reactor coolant pumps are OPERATING, the reactor coolant system temperature is greater than 5000 F, the pressurizer pressure is greater than 2000 psia and the high power trip is OPERABLE.

I MILLSTONE - UNIT 2 3/4T 1-31 Amendment No. 44-6,291

POWER DISTRIBUTION LIMITS TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR - FTr LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of FTr shall be within the 100% power limit specified in the CORE OPERATING LIMITS REPORT. The FTr value shall include the effect of AZIMUTHAL POWER TILT.

APPLICABILITY:

MODE I with THERMAL POWER >20% RTP*.

ACTION:

With FTr exceeding the 100% power limit within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Reduce THERMAL POWER to bring the combination of THERMAL POWER and FTr to within the power dependent limit specified in the CORE OPERATING LIMITS REPORT and withdraw the CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or

b.

Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 FTr shall be determined to be within the 100% power limit at the following intervals:

a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading,

b.

At least once per 31 days of accumulated operation in MODE 1, and

c.

Within four hours if the AZIMUTHAL POWER TILT (Tq) is> 0.020.

4.2.3.3 FTr shall be determined by using the incore detectors to obtain a power distribution map with all CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump Combination.

I

See Special Test Exception 3.10.2.

MILLSTONE - UNIT 2 3/4 2-9 Amendment No. 3-,

9,, 90, 99, 444, 4-9,449, 4455,464,201, M&0, 291

POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - TQ LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL POWER TILT (Tq) shall be < 0.02.

APPLICABILITY:

MODE 1 with THERMAL POWER > 50% of RATED THERMAL POWER(I).

ACTION:

a.

With the indicated Tq > 0.02 but < 0. 10, either restore Tq to < 0.02 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or verify the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR (FTr) is within the limit of Specification 3.2.3 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Or otherwise, reduce THERMAL POWER to < 50% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

With the indicated Tq >0.10, perfonr the following actions: (2)

1.

Verify the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR (FTr) is within the limit of Specification 3.2.3 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and

2.

Reduce THERMAL POWER to < 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and

3.

Restore Tq < 0.02 prior to increasing THERMAL POWER. Correct the cause of the out of limit condition prior to increasing THERMAL POWER.

Subsequent power operation above 50% of RATED THERMAL POWER may proceed provided that the measured Tq is verified < 0.02 at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or until verified at 95% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.2.4.1 Verify T is within limit at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The provisions of Specification 4.0.4 are not applicable for entering into MODE I with THERMAL POWER > 50% of RATED THERMAL POWER from MODE 1.

(l) See Special Test Exception 3.10.2.

(2) All subsequent Required ACTIONS must be completed if power reduction commences prior to restoring Tq < 0. 10.

MILLSTONE - UNIT 2 3/4 2-10 Amendment No. 38, 52, 90, 19,44, 280, 291

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective 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 4.3-1.

4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

MILLSTONE - UNIT 2 3/4 3-1 Amendment No.

, 1492, 291

TABLE 3.3-1 (Continued)

TABLE NOTATION With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(a) Trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is Ž 5% of RATED THERMAL POWER.

(b) Trip may be manually bypassed when steam generator pressure is < 800 psia and all CEAs are fully inserted; bypass shall be automatically removed when steam generator pressure is 2 800 psia.

(c) Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is 2 15% of RATED THERMAL POWER.

(d) Trip does not need to be OPERABLE if all the control rod drive mechanisms are de-energized or if the RCS boron concentration is greater than or equal to the refueling concentration of Specification 3.9. 1.

(e) DELETED (f) AT Power input to trip may be bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is 2 5% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and/or open the protective system trip breakers.

ACTION 2 -

With the number of OPERA13LE channels one less than the Total Number of Channels, operation may continue provided the following conditions are satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition within I hour. The inoperable channel shall either be restored to OPERABLE status, or placed in the tripped condition, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , all functional units receiving an input from the inoperable channel are also declared inoperable, and the appropriate actions are taken for the affected functional units.

b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be removed from service for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , provided one of the inoperable channels is placed in the tripped condition.

MILLSTONE - UNIT 2 3/4 3-4 Amendment No. 9, &, X, 1-6, 443, i2, 2 6, i, 291

TABLE 3.3-1 (Continued)

ACTION STATEMENTS ACTION 3 - NOT USED ACTION 4 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, immediately verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1, and at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter.

ACTION 5 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 6 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MILLSTONE - UNIT 2 3/4 3-5 Amendment No. 224, 82, 291

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The engineered safety feature actuation system instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY:

As shown in Table 3.3-3.

ACTION:

a.

With an engineered safety feature actuation system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, either adjust the trip setpoint to be consistent with the value specified in the Trip Setpoint column of Table 3.3-4 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or declare the channel inoperable and take the ACTION shown in Table 3.3-3.

b.

With an engineered safety feature actuation system instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each engineered safety feature acutation system 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 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

MILLSTONE - UNIT 2 31'4 3-9 Amendment No. 419, I, 291

INSTRUMENTATION ENGINEERED SAFETY FEATURE ACTIJATION SYSTEM SENSOR CABINET POWER SUPPLY DRAWERS LIMITING CONDITION FOR OPERATION 3.3.2.2 The engineered safety feature actuation system Sensor Cabinets (RC02AI, RC02B2, RC02C3 & RC02D4) Power Supply Drawers shall be OPERABLE and energized from the normal power source with the backup power source available. The normal and backup power sources for each sensor cabinet is detailed in Table 3.3-5a:

CABINET NORMAL POWER BACKUP POWER RC02AI VA-10 VA-40 RC02B2 VA-20 VA-30 RC02C3 VA-30 VA-20 RC02D4 VA-40 VA-10 Table 3.3-5a APPLICABILITY:

MODES 1, 2,3 and 4 ACTION:

With any of the Sensor Cabinet Power Supply Drawers inoperable, or either the normal or backup power source not available as delineated in Table 3.3-5a, restore the inoperable Sensor Cabinet Power Supply Drawer to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE REQUIREMENTS 4.3.2.2.1 The engineered safety feature actuation system Sensor Cabinet Power Supply Drawers shall be determined OPERABLE once per shift by visual inspection of the power supply drawer indicating lamps.

4.3.2.2.2 Verify the OPERABILITY of the Sensor Cabinet Power Supply auctioneering circuit at least once per 18 months.

MILLSTONE - UNIT 2 3/4 3-23 Amendment No. 449, 282, 291

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, 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. 41-5, 245, I82, 284, 291

INSTRUMENTATION ACCIDENT MONITORING LIMITING CONDITION FOR OPERATION I

3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

ACTIONS per Table 3.3-1.

I SURVEILLANCE REQUIREMENTS I

4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

MILLSTONE - UNIT 2 3/4T 3-31l Amendment No. 66, 44-, 8, 291

0z t.M TABLE 3.3-11 ACCIDENT MONITORING INSTRUMENTATION Instrument

1.

Pressurizer Water Level

2.

Auxiliary Feedwater Flow Rate

3.

RCS Subcooled/Superheat Monitor

4.

PORV Position Indicator Acoustic Monitor m

5.

PORV Block Valve Position Indicator

6.

Safety Valve Position Indicator Acoustic Monitor

7.

Containment Pressure (Wide Range)

8.

Containment Water Level (Narrow Range)

9.

Containment Water Level (Wide Range) l

10.

Core Exit Thermocouples Be

11.

Main Steam Line Radiation Monitor Z

12.

Reactor Vessel Coolant Level Total No.

of Channels 2

2/S.G 2

1/valve 1/valve 1/valve 2

1 2

4 CETs/core quadrant 3

2*

Minimum Channels OPERABLE 1

l/S.G 1

1/valve 1/valve 1/valve 1

1 1

2 CETs in any of 2 core quadrants 3

1*

ACTION I

I 1

2 3

3 3

.4 4

5 6

8

A channel is eight (8) sensors in a probe. A channel is OPERABLE if four (4) or more sensors, two (2) or more in the upper four and two (2) or more in the lower four, are OPERABLE.

I

1. Refer to ACTION statement in Technical Specification 3.4.6.1.

TABLE 3.3-11 (Continued)

ACTION STATEMENTS ACTION I -

ACTION 2 -

ACTION 3 -

ACTION 4 -

With the number of OPERABLE channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-11, either restore the inoperable channel(s) to OPERABLE status within 30 days or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the number of channels OPERABLE less than the MINIMUM CHANNELS OPERABLE, determine the subcooling margin once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information, and monitor discharge pipe temperature once per shift to determine valve position. This ACTION is not required if the PORV block valve is closed with power removed in accordance with Specification 3.4.3.a or 3.4.3.b.

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the total number of channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or submit a special report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction, the plans for restoring the channel(s) to OPERABLE status, and any alternate methods in affect for estimating the applicable parameter during the interim.

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or submit a special report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction, the plans for restoring the channel(s) to OPERABLE status, and any alternate methods in affect for estimating the applicable parameter during the interim.

I MILLSTONE - UNIT 2 314. 3-33 Amendment No. 420, 2, 291

REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.4.1 Two reactor coolant loops shall be OPERABLE and in operation.

APPLICABILITY:

MODES I and 2.

ACTION:

With the requirements of the above specification not met, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

MILLSTONE - UNIT 2 3/4 4-1 Amendment No. 50, 69, 2O,249,291

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.5 Reports

a.

Following each inservice inspection of steam generator tubes, the number of tubes plugged and sleeved in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed. This report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration for each indication of an imperfection.

3.

Identification of tubes plugged or sleeved.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported pursuant to 10 CFR 50.72. A Special Report pursuant to Specification 6.9.2 shall be submitted prior to resumption of plant operation and shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

MILLSTONE - UNIT 2 3/4 4-7b Amendment No. X, A, 9, 89, 41-, 291

0z M~

H t'W TABLE 4.4-6 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result ACTION Required Result ACTION Required Result ACTION Required A minimum of C-I None N/A N/A N/A N/A S tubes per C-2 Repair defective C-1 None N/A N/A SQ tubes and inspect C-2 Repair defective tubes and C-1 None additional 25 tubes in inspect additional 45 tubes in C-2 Repair defective this S.G.*

this S.G*

tubes*

C-3 Perform ACTION for C-3 result of first sample C-3 Perform ACTION for C-3 N/A N/A result of first sample C-3 Inspection all tubes All other None N/A N/A in this S.G, repair S.Gs are C-defective tubes and I

inspect 25 tubes in Some S.Gs Perform ACTION for C-2 N/A N/A each other S.Ct*

C-2 but no result of second sample additional Prompt notification S.G are C-3 to NRC pursuant to 10 CFR 50 72 Additional Inspect all tubes in each S.G.

N/A N/A S.G is C-3 and repair defective tubes.*

Prompt notification to NRC pursuant to 10 CFR 50.72 z

0 ED G3 io S

3N% Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection n

Repair of defective tubes shall be limited to plugging with the exception of those tubes which may be sleeved. Tubes with defective

-S sleeves shall be plugged.

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11.

" 20 30' 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0 g Ci/gram DOSE EQUIVALENT I-131 1 MILLSTONE - UNIT 2 3/4 4-16 Amendment No. 291

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRTMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2,3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations0l) not capable of being closed by OPERABLE containment automatic isolation valves(2) and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions,(3) except for valves that are open under administrative control as permitted by Specification 3.6.3.1.

b.

At least once per 31 days by verifying the equipment hatch is closed and sealed.

c.

By verifying the containment air lock is in compliance with the requirements of Specification 3.6.1.3.

d.

After each closing of a penetration subject to type B testing (except the containment air lock), if opened following a Type A or B test, by leak rate testing in accordance with the Containment Leakage Rate Testing Program.

e.

By verifying Containment structural integrity in accordance with the Containment Tendon Surveillance Program.

(1)

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.

These penetrations shall be verified closed prior to entering MODE 4 from MODE 5, if not performed within the previous 92 days.

(2)

In MODE 4, the requirement for an OPERABLE containment automatic isolation valve system is satisfied by use of the containment isolation trip pushbuttons (3)

Isolation devices in high radiation areas may be verified by use of administrative means.

MILLSTONE - UNIT 2 3/4 6-1 Amendment No. A, 9, IO2, 2410, 24, 2I74, 291

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY AND COOLING SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.2.1 Two containment spray trains and two containment cooling trains, with each cooling train consisting of two containment air recirculation and cooling units, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2 and 3*.

ACTION:

I Inoperable Equipment Required ACTION

a.

Onecontainment a.1 Restore the inoperable containment spray train to spray train OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1750 psia within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

One containment b. 1 Restore the inoperable containment cooling train to cooling train OPERABLE status within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

One containment

c. 1 Restore the inoperable containment spray train or the spray train inoperable containment cooling train to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

One containment cooling train

d.

Two

d. 1 Restore at least one inoperable containment cooling train to containment OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT cooling trains SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e.

All other e.lI Enter LCO 3.0.3 immediately.

combinations SURVEILLANCE REQUIREMENTS I

4.6.2.1.1 Each containment spray train shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying each containment spray manual, power operated, and automatic valve in the spray train flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

The Containment Spray System is not required to be OPERABLE in MODE 3 if pressurizer pressure is < 1750 psia.

MILLSTONE - UNIT 2 3/4t 6-12 Amendment No. 21-5,

, 236, 283, 291

PLANT SYSTEMS MAIN FEEDWATER ISOLATION COMPONENTS (MFICs)

LIMITING CONDITION FOR OPERATION (Continued)

a.

With two or more of the feedwater isolation components inoperable in the same flow path, either:

I.

Restore the inoperable component(s) to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months until ACTION 'a' applies, or

2.

Isolate the affected flow path within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and verify that the inoperable feedwater isolation components are closed or isolated/secured once per 7 days, or

3.

Be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.6 Each feedwater isolation valve/feedwater pump trip circuitry shall be demonstrated OPERABLE at least once per 18 months by:

a.

Verifying that on 'A' main steam isolation test signal, each isolation valve actuates to its isolation position, and

b.

Verifying that on 'B' main steam isolation test signal, each isolation valve actuates to its isolation position, and

c.

Verifying that on 'A' main steam isolation test signal, each feedwater pump trip circuit actuates, and

d.

Verifying that on 'B' main steam isolation test signal, each feedwater pump trip circuit actuates.

MILLSTONE - UNIT 2 3/4 7-9b Amendment No. 4489, 291

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, and

b.

Two separate and independent diesel generators each with a separate fuel oil supply tank containing a minimum of 12,000 gallons of fuel.

APPLICABILITY:

MODES 1, 2,3 and 4.

ACTION:

Inoperable Equipment Required ACTION I

a.

One offsite circuit

a. I Perform Surveillance Requirement 4.8.1.1.1 for remaining offisite circuit within I hour prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND a.2 Restore the inoperable offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MILLSTONE - UNIT 2 3/4 8-1 Amendment No. 4-, 4-7, 4A9, A34-,

291+,261, 291

ELECTRICAL POWER SYSTEMS ACTION (Continued)

Inoperable Equipment Required ACTION

b.

One diesel b.1 Perform Surveillance Requirement 4.8.1.1.1 for the generator offsite circuit within I hour prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND b.2 Demonstrate OPERABLE diesel generator is not inoperable due to common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or perform Surveillance Requirement 4.8.1.1.2.a.2 for the OPERABLE diesel generator within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

AND b.3 Verify the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If this condition is not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AND b.4 (Applicable only if the.14 day allowed outage time specified in ACTION Statement b.5 is to be used.)

Verify the required Millstone Unit No. 3 diesel generator(s) is/are OPERABLE and the Millstone Unit No. 3 SBO diesel generator is available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. Restore any inoperable required Millstone Unit No. 3 diesel generator to OPERABLE status and/or Millstone Unit No. 3 SBO diesel generator to available status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND b.5 Restore the inoperable diesel generator to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (within 14 days if ACTION Statement b.4 is met) or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MILLSTONE - UNIT 2 3/4 8-la Amendment No. 4-, 7,492, 234-,

2$-I, 2641, 291

ELECTRICAL POWER SYSTEMS ACTION (Continued)

Inoperable Equipment Required ACTION

c.

One offsite circuit AND One diesel generator c.l Perform Surveillance Requirement 4.8.1.1.1 for remaining offsite circuit within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND c.2 Demonstrate OPERABLE diesel generator is not inoperable due to common cause failure within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or perform Surveillance Requirement 4.8.1.1.2.a.2 for the OPERABLE diesel generator within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

AND c.3 Verify the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If this condition is not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AND c.4 Restore one inoperable A.C. source to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND c.5 Restore remaining inoperable A.C. source to OPERABLE status following the time requirements of ACTION Statements a or b above based on the initial loss of the remaining inoperable A.C. source.

4 d.

Two offsite circuits

d. I Restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AND d.2 Following restoration of one offsite source restore remaining inoperable offsite source to OPERABLE status following the time requirements of ACTION Statement a above based on the initial loss of the remaining inoperable offsite source.

MILLSTONE - UNIT 2 3/4 8-2 Amendment No. 4-6I, 477, A3-, I6-, 291

ELECTRICAL POWER SYSTEMS ACTION (Continued)

Inoperable Equipment Required ACTION I

e.

Two diesel generators e.I Perform Surveillance Requirement 4.8.1.1.1 for the offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND e.2 Restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND e.3 Following restoration of one diesel generator restore remaining inoperable diesel generator to OPERABLE status following the time requirements of ACTION Statement b above based on the initial loss of the remaining inoperable diesel generator.

11 I SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Verify correct breaker alignment and indicated power available for each required offsite circuit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

MILLSTONE - UNIT 2 3/4 8-2a, Amendment No. 431,-231, 277, 291

5.0 DESIGN FEATURES 5.1 SITE LOCATION The Unit 2 Containment Building is located on the site at Millstone Point in Waterford, Connecticut. The nearest SITE BOUNDARY on land is 2034 feet northeast of the containment building wall (1627 feet northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3. No part of the site that is closer than these distances shall be sold or leased except to Dominion Nuclear Connecticut, Inc. or its corporate affiliates for use in conjunction with normal utility operations.

5.2 DELETED MILLSTONE - UNIT 2 5-1 Amendment No. 24-6,470, 291

TABLE 6.2-1(3)

MINIMUM SHIFT-CREW COMPOSITION(2)

APPLICABLE MODES LICENSE CATEGORY 1, 2,3 & 4 5&6 Senior Reactor Operator 2

1(1)

Reactor Operator 2

1 Non-Licensed Operator 2

1 Shift Technical Advisor 1(4)

None Required (1)

Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling individual supervising CORE ALTERATIONS after the initial fuel loading.

(2)

The above shift crew composition and the qualified radiation protection technician of Section 6.2.2 may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence provided expeditious actions are taken to fill the required position.

(3)

Requirements for minimum number of licensed operators on shift during operation in MODES other than COLD SHUTDOWN or REFUELING are contained in 1 OCFR50.54(m).

(4)

The Shift Technical Advisor position can be filled by either of the two Senior Reactor Operators (a dual-role individual), if he meets the Shift Technical Advisor qualifications of the Commission Policy Statement on Engineering Expertise on Shift.

I MILLSTONE - UNIT 2 6-4 Amendment No. 66, 4, 92, 436, 463, 49-, 2-40, 288, 291

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (CONT.!

8.

XN-NF-62 I (P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear 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 Burnups of 62 GWdIMTU," 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.

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.

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 MILLSTONE - UNIT 2 6-19 Amendment No. 448, 463, 2I, 250 260,28+,

291

ADMINISTRATIVE CONTROLS 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the primary containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Performance-Based Option of 10 CFR Part 50, Appendix J": The first Type A test performed after the June 10, 1995 Type A test shall be performed no later than June 10, 2010.

The peak calculated primary Containment internal pressure for the design basis loss of coolant accident is Pa.

The maximum allowable primary containment leakage rate, La, at Pas is 0.5% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and < 0.75 La for Type A tests;

b.

Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is < 0.05 La when tested at 2 Pa.

2. For each door, pressure decay is < 0.1 psig when pressurized to 2 25 psig for at least 15 minutes.

The provisions of SR 4.0.2 do not apply for test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

6.20 RADIOACTIVE EFFLUENT CONTROLS PROGRAM This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the REMODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402; MILLSTONE - UNIT 2 6-26 Amendment No. 203, 250, 26, 28, 291

ADMINISTRATIVE CONTROLS 6.20 RADIOACTIVE EFFLUENT CONTROLS PROGRAM

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the REMODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the REMODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the REMODCM at least every 31 days;

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be in accordance with the following:

1.

For noble gases: a dose rate

500 mrem/yr to the whole body and a dose rate < 3000 mrem/yr to the skin, and

2.

For iodine-131, iodine 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate < 1500 mrem/yr to any organ;

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR 50, Appendix I;

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR 50, Appendix I; and

j.

Limitations on the annual dose or dose commitment to any member of the public, beyond the SITE BOUNDARY, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of Specification 4.0.2 and Specification 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

MILLSTONE - UNIT 2 6-27 Amendment No. Q50, 276, 291

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY.........................................................

3/40-1 3/4.1 REACTIVl1Y CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - MODES 1 AND 2.............................................. 3/4 1-1 SHUTDOWN MARGIN - MODES 3,4, AND 5 LOOPS FILLED............. 3/4 1-3 FIGURE3.1-1 DELETED.........................................................

3/4 1-4 FIGURE 3.1-2 DELETED.........................

3/4 1-5 FIGURE 3.1-3 DELETED.....................

3/4 1-6 FIGURE 3.1-4 DELETED.....................

3/4 1-7 SHUTDOWN MARGIN - COLD SHUTDOWN -

Loops Not Filled.....................

3/4 1-8 FIGURE 3.1-5 DELETED.....................

3/4 1-9 Moderator Temperature Coefficient........................

3/4 1-10 Minimum Temperature for Criticality........................

3/4 1-12 3/4.1.2 BORATION SYSTEMS DELETED.....

3/41-13 DELETED.....

3/4 1-14 DELETED.....

3/4 1-15 DELETED.....

3/4 1-16 DELETED.....

3/4 1-17 DELETED.....

3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.......

3/4 1-20 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD...................... 3/4 1-22 Position Indication Systems - Operating.......................

................. 3/4 1-23 MILLSTONE - UNIT 3 iv Amendment No. -0, 60,99, I9-97,',

2-1&, 229

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.3-13 DELETED TABLE 4.3-9 DELETED 3/4.3.4 DELETED 3/4.3.5 SHUTDOWN MARGIN MONITOR...................................

3/4 3-82 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1.

REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation...........................

3/4 4-1 HOT STANDBY...........................

3/4 4-2 HOT SHUTDOWN...........................

3/4 4-3 COLD SHUTDOWN - Loops Filled...........................

3/4 4-5 COLD SHUTDOWN - Loops Not Filled...........................

3/4 4-6 Loop Stop Valves...........................

3/4 4-7 Isolated Loop Startup...........................

3/4 4-8 3/4.4.2 SAFETY VALVES.3/4 4-9 DELETED.3/4 4-10 3/4.4.3 PRESSURIZER Startup and Power Operation.....................................

3/4 4-11 FIGURE 3.4-5 PRESSURIZER LEVEL CONTROL.....................................

3/4 4-1 la Hot Standby........................

3/4 4-11 b 3/4.4.4 RELIEF VALVES........................

3/4 4-12 3/4.4.5 STEAM GENERATORS........................

3/4 4-14 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION............................... 3/4 4-19 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION.......................................... 3/4 4-20 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................................................

3/4 4-21 Operational Leakage.........................................................................................3/4 4-22 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..3/4 4-24 3/4.4.7 DELETED............................................................

3/4 4-25 TABLE 3.4-2 DELETED............................................................

3/4 4-26 TABLE 4.4-3 DELETED............................................................

3/4 4-27 3/4.4.8 SPECIFIC ACTIVITY............................................................

3/4 4-28 MILLSTONE - UNIT 3 vii Amendment No. 4-60,4-64,498, 4-93, 229

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY >IlpCi/gram DOSE EQUIVALENT 1-131....................

3/4 4-30 TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.3/4 4-31 3/4.4.9 PRESSURE/TEMPERATURE LIMITS............................. 3/4 4-33 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS -

APPLICABLE UP TO 10 EFPY..............................................................

3/4 4-34 FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS -

APPLICABLE UP TO 10 EFPY...........................

3/4 4-35 TABLE 4.4-5 DELETED..................................................

3/4 4-36 DELETED.3/4 4-37 Overpressure Protection Systems.3/4 4-38 FIGURE 3.4-4a High Setpoint PORV Curve For the Cold Overpressure Protection System.3/4 4-40 FIGURE 3.4-4b Low Setpoint PORV Curve For the Cold Overpressure Protection System.

314 4-41 3/4.4.10 DELETED.3/4 4-42 3/4.4.11 DELETED...................................

3/4 4-43 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS............

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg GREATER THAN OR EQUAL TO 3500 F......................................

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg LESS THAN 3500F.................................... 3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK......................................

3/4 5-9 3/4.5.5 pH TRISODIUM PHOSPHATE STORAGE BASKETS........................ 3/4 5-10 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.,

3/4 6-1 Containment Leakage.3/4 6-2 Containment Air Locks.3/4 6-5 Containment Pressure.

3/4 6-7 MILLSTONE - UNIT 3 viii Amendment No. 9,

, &9, 91-5, 204,

242, 229

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.8 PROCEDURES AND PROGRAMS.......................................................

6-14 6.9 REPORTING REOUIREMENTS.......................................................

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 PROGRAM................. 6-26 6.19 COMPONENT CYCLIC OR TRANSIENT LIMIT.................................................... 6-27 MILLSTONE -UNIT 3 xix Amendment No. 56, 69, 6, 4A, 48,

-24, 24-, 245, 2-23, 229

3/4.1 REACTIVITY CONTROL SYSTE MS 3/4.1.1.1 BORATIONCONTROL SHUTDOWN MARGIN - MODES I AND 2 LIMITING CONDITION FOR OPERATION 3.1.1.1.1 The SHUTDOWN MARGIN shall be within the limits specified in the CORE OPERATING LIMITS REPORT (COLR).

APPLICABILITY:

MODES 1 and 2*.

ACTION:

With the SHUTDOWN MARGIN not within the limits specified in the COLR, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:

a.

Within I hour after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s);

b.

When in MODE I or MODE 2 with Keff greater than or equal to I at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6;

c.

When in MODE 2 with Keff less than 1, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6;

d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4.1.1.1.2, with the control banks at the maximum insertion limit of Specification 3.1.3.6; and See Special Test Exceptions Specification 3.10.1.

MILLSTONE - UNIT 3 3/4 1-1 Amendment No. 60.44, 2-14, 24-1, 229

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - MODES 3.4 AND 5 LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.1.1.1.2 The SHUTDOWN MARGIN shall be within the limits specified in the CORE OPERATING LIMITS REPORT (COLR).*

APPLICABILITY:

MODES 3,4 and 5 ACTION:

With the SHUTDOWN MARGIN less than the required value, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6600 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be within the limits specified in the COLR:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s); and

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor Coolant System boron concentration,

2.

Control rod position,

3.

Reactor Coolant System average temperature,

4.

Fuel burnup based on gross thermal energy generation,

5.

Xenon concentration, and

6.

Samarium concentration.

4.1.1.1.2.2 Valve 3CHS*V305 shall be verified closed and locked at least once per 31 days.

Additional SHUTDOWN MARGIN requirements, if required, are given in Specification 3.3.5.

MILLSTONE - UNIT 3 3/4 1-3 Amendment No. 60, 4-1, 464, 44, 2-18,229

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control rod positions within 12 steps.

APPLICABILITY:

MODES I and 2.

ACTION:

a.

With a maximum of one digital rod position indicator per bank inoperable:

1.

Determine the position of the nonindicating rod(s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With a maximum of one demand position indicator per bank inoperable:

1.

Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is inoperable, then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.2.2 Each of the above required digital rod position indicator(s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full-range of rod travel at least once per 24 months.

MILLSTONE - UNIT 3 3/4 1-23 Amendment No. 6O2I, 6

417, l

22'

REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be limited in physical insertion as specified in the CORE OPERATING LIMITS REPORT (COLR).

APPLICABILITY:

MODES 1* and 2* **.

ACTION:

With a maximum of one shutdown rod inserted beyond the insertion limits specified in the COLR except for surveillance testing pursuant to Specification 4.1.3.1.2, within I hour either:

a.

Restore the rod to within the limit specified in the COLR, or

b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limits specified in the COLR:

a.

Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an approach to reactor criticality, and

b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

- With Keff greater than or equal to 1.

MILLSTONE - UNIT 3 3/4 1-26 Amendment No. 60, 229

REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the CORE OPERATING LIMITS REPORT (COLR).

APPLICABILITY:

MODES I* and 2***.

ACTION:

With the control banks inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a.

Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b.

Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank position using the insertion limits specified in the COLR, or

c.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS I

4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod insertion limit monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

- With Keff greater than or equal to 1.

MILLSTONE - UNIT 3 3/4L1-27 Amendment No. -5, 60, 229

POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - FQfZ)

LIMITING CONDITION FOR OPERATION 3.2.2.1 FQ(Z) shall be limited by the following relationships:

F RTP FQ(Z)

Y K(Z) for P > 0.5 RTP F (Z) <

Y K(Z) for P *0.5 Q

0.5 FQRTP = the FQ limit at RATED THERMAL POWER (RTP) provided in the CORE OPERATING LIMITS REPORT (COLR).

I Wher-P=

THERMAL POWER

_n RATED THERMAL POWER'and K(Z) = the normalized FQ(Z) as a function of core height specified in the COLR.

APPLICABILITY:

MODE 1.

ACTION:

With FQ(Z) exceeding its limit:

a.

For RAOC operation with Specification 4.2.2.1.2.b not being satisfied or for base load operation with Specification 4.2.2.1.4.b not being satisfied:

(1)

Reduce THERMAL POWER at least 1% for each 1% FQ(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip setpoints have been reduced at least 1% for each 1% FQ(Z) exceeds the limit, and MILLSTONE - UNIT 3 3/4 2-5 Amendment No. 0, 60, 99, 420, 4.-0, 24-I, 229

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued)

(2)

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by item (1) above; THERMAL POWER may then be increased provided FQ(Z) is demonstrated through incore mapping to be within its limits.

b.

For RAOC operation with Specification 4.2.2.1.2.c not being satisfied, one of the following ACTIONS shall be taken:

(1)

Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits specified in the CORE OPERATING LIMITS REPORT by at least 1% AFD for each percent FQ(Z) exceeds its limits. Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints to these modified limits, or (2)

Verify that the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load operation.

Where it is necessary to calculate the percent that FQ(Z) exceeds the limits for item (1) above, it shall be calculated as the maximum percent over the core height (Z),

consistent with Specification 4.2.2.l.2.f, that FQ(Z) exceeds its limit by the following expression:

(pQM(Z XW(Z) 1 Ml FQ (Z) X W(Z)

RTP

-1 x 100 for P > 0.5 FQ x K(Z)

c.

For base load operation with Specification 4.2.2.1.4.c not being satisfied, one of the following ACTIONS shall be taken:

(1)

Place the core in an equilibrium condition where the limit in 4.2.2.1.4.c is satisfied, and remeasure FQM(Z), or MILLSTONE - UNIT 3 3/4 2-6 Amendment No. 99, 4O, 4-70, 229

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

c.

Satisfying the following relationship:

RTP M

FQ xK(Z)

Q (Z)

Px W(Z) for P>0.5 RTP M F x K(Z)

FQ (Z) 5< for P < 0.5 where FQM(Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FQRTP is the FQ limit, K(Z) is the normalized FQ(Z) as a function of core height, P is the relative THERMAL POWER, and W(Z) is the cycle-dependent function that accounts for power distribution transients encountered during normal operation. FQRTPI K(Z),

and W(Z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.6.

d.

Measuring FQM(Z) according to the following schedule:

(1)

Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which FQ(Z) was last determined,*** or (2)

At least once per 31 Effective Full Power Days, whichever occurs first.

e.

With the maximum value of FQM(Z)

K(Z) over the core height (Z) increasing since the previous determination of FQM(Z),

either of the following ACTIONS shall be taken:

(1)

Increase FQM(Z) by an appropriate factor specified in the COLR and verify that this value satisfies the relationship in Specification 4.2.2.1.2.c, or

- - During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and power distribution map outlined.

MILLSTONE - UNIT 3 3/4 2-8 Amendment No. &O, 60, 99, 20, 0, 229

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

b.

During base load operation, if the THERMAL POWER is decreased below APLND then the conditions of 4.2.2.1.3.a shall be satisfied before reentering base load operation.

4.2.2.1.4 During base load operation FQ(7Z) shall be evaluated to determine if FQ(Z) is within its limit by:

a.

Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER above APLND.

b.

Evaluate the computed heat flux hot channel factor by performing both of the following:

(1)

Determine the computed heat flux hot channel factor, FQM(Z), by increasing the measured FQM(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increase the value by 5% to account for measurement uncertainties, and (2)

Verify that FQM(Z) satisfies the requirements of Specification 3.2.2.1 for all core plane regions, i.e., 0 - 100% inclusive.

c.

Satisfying the following relationship:

RTP FQ x K(Z)

ND FM(Z)* Q for P > APL Q

PxW(Z)BL where: FQM(Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FQRTP is the FQ limit, K(Z) is the normalized FQ(Z) as a function of core height, P is the relative THERMAL POWER, and W(Z)BL is the cycle-dependent function that accounts for limited power distribution transients encountered during base load operation.

FQRTP K(Z), and W(Z)BL are specified in the COLR as per Specification 6.9.1.6.

d.

Measuring FQM(Z) in conjunction with target flux difference determination according to the following schedule:

(1)

Prior to entering base load operation after satisfying Section 4.2.2.1.3 unless a full core flux map has been taken in the previous 31 EFPD with the relative THERMAL POWER having been maintained above APLND for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to mapping, and (2)

At least once per 31 Effective Full Power Days.

MILLSTONE - UNIT 3 3/4 2-10 Amendment No. -O, 60, 99, 4-G, 229

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

e.

With the maximum value of M

F (Z)

K(Z) over the core height (Z) increasing since the previous determination of FQM(Z),

either of the following ACTIONS shall be taken:

1)

Increase FQM(Z) by appropriate factor specified in the COLR and verify that this value satisfies the relationship in Specification 4.2.2.1.4.c, or I

2)

FQM(Z) shall be measured at least once per 7 Effective Full Power Days until 2 successive maps indicate that the maximum value of F '1(Z)

K(Z) over the core height (Z) is not increasing.

f.

The limits specified in 4.2.2.1.4.c and 4.2.2.1.4.e are not applicable in the following core plane regions:

1)

Lower core region 0% to 15%, inclusive.

2)

Upper core region 85% to 100%, inclusive.

4.2.2.1.5 When FQ(Z) is measured for reasons other than meeting the requirements of Specifications 4.2.2.1.2 or 4.2.2.1.4, an overall measured FQ(Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

MILLSTONE - UNIT 3 3/4 2-11 Amendment No. M, 60,99,4-20, 4-0, 229

t4 cj 0z hi TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE 2

1 2

FUNCTIONAL UNIT

1. Manual Reactor Trip APPLICABLE MODES 1,2 3*, 4*, 5*

ACTION 1

11 2

1 2

2. Power Range, Neutron Flux

a. High Setpoint

b. Low Setpoint w

3. Power Range, Neutron Flux High Positive Rate

4. Deleted

5. Intermediate Range, Neutron Flux

6. Source Range, Neutron Flux

a. STARTUP 2

3 1,2 2

2 3

2 2

3 1,2 2

1 2

3 1

2 Cb B

z qa ED 0

so

b. Shutdown

7. Overtemperature AT

8. Overpower AT

9. Pressurizer Pressure--Low

10. Pressurizer Pressure-High

11. Pressurizer Water Level--High 1

2 2

3 3

2 2fl 3*, 4*, 5*

1,2 1,2 1**

1,2 1**

4 I

11 6

6 6 (1) 6 (1) 6

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 9-(Not used)

ACTION 10-ACTION 11-ACTION 12-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1. 1, provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

b.

When the Minimum Channels OPERABLE requirement is met, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of the Turbine Control Valves.

ACTION 13-ACTION 13A-With one of the diverse trip features (undervoltage or shunt trip attachments) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 10. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable Channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

I MILLSTONE - UNIT 3 3/4 3-7 Amendment No. 40, 89, 229

TABLE 4.3-2 (Continued)

TABLE NOTATION

1.

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

2.

This surveillance may be performed continuously by the emergency generator load sequencer auto test system as long as the EGLS auto test system is demonstrated OPERABLE by the performance of an ACTUATION LOGIC TEST at least once per 92 days.

3.

On a monthly basis, a loss of voltage condition will be initiated at each undervoltage monitoring relay to verify individual relay operation. Setpoint verification and actuation of the associated logic and alarm relays will be performed as part of the CHANNEL CALIBRATION required once per 18 months.

4.

For Engineered Safety Features Actuation System functional units with only Potter &

Brumfield MDR series relays used in a clean, environmentally controlled cabinet, as discussed in Westinghouse Owners Group Report WCAP-13900, the surveillance interval for slave relay testing is R.

MODES 1, 2, 3, 4, 5 and 6.

During fuel movement within containment or the spent fuel pool.

I I

MILLSTONE - UNIT 3 3/4 3-41 Amendment No. 4-, 44, 9, 100, 429, 49, 2209 2 19, 229

TABLE 3.3-6 (Continued)

TABLE NOTATIONS With fuel in the fuel storage pool areas.

ACTION STATEMENTS I

ACTION 28 - With less than the Minimum Channels OPERABLE requirement, fuel movement may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel storage pool area.

Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel storage pool areas.

ACTION 29 - With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

MILLSTONE - UNIT 3 3/4 3-44 Amendment No. 46, 4-9, 229

cj H-0-z TABLE 3.3-10 (Continued)'

ACCIDENT MONITORING INSTRUMENTATTON TOTAL NO. OF CHANNELS INSTRUTvMENT MINIMUM CHANNELS OPERABLE 1

I 16.

Containment Area - High Range Radiation Monitor

17.

Reactor Vessel Water Level

18.

Deleted w

19.

Neutron Flux 2

2*

1*

2 1

w LA)

A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sensors, half or more in the upper head region and half or more in the upper plenum region, are OPERABLE.

I 0U 0.y z

Po

INSTRUMENTATION 3/4.3.5 SHUTDOWN MARGIN MONITOR LIMITING CONDITION FOR OPERATION 3.3.5 Two channels of Shutdown Margin Monitors shall be OPERABLE

a.

With a minimum count rate as designated in the CORE OPERATING LIMITS REPORT (COLR), or

b.

If the minimum count rate in Specification 3.3.5.a cannot be met, then the Shutdown Margin Monitors may be made OPERABLE with a lower minimum count rate, as specified in the COLR, by borating the Reactor Coolant System above the requirements of Specification 3.1.1.1.2 or 3.1.1.2. The additional boration shall be:

1.

A minimum of 150 ppm above the SHUTDOWN MARGIN requirements specified in the COLR for MODE 3, or

2.

A minimum of 350 ppm above the SHUTDOWN MARGIN requirements specified in the COLR for MODE 4, MODE 5 with RCS loops filled, and MODE 5 with RCS loops not filled.

APPLICABILITY:

MODES 3*, 4, and 5.

ACTION:

a.

With one Shutdown Margin Monitor inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With both Shutdown Margin Monitors inoperable or one Shutdown Margin Monitor inoperable for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , immediately suspend all operations involving positive reactivity changes via dilution and rod withdrawal.

Verify the valves listed in Specification 4.1.1.2.2 are closed and secured in position within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and at least once per 14 days thereafter.**

Verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1.2 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

The shutdown margin monitors may be blocked during reactor startup in accordance with approved plant procedures.

- The valves may be opened on an intermittent basis under administrative controls as noted in Surveillance 4.1.1.2.2.

MILLSTONE - UNIT 3 3/4 3-82 Amendment No. 4764, 21-7, 2-8,229

INSTRUMENTATION 3/4.3.5 SHUTDOWN MARGIN MONITOR (continued)

SURVEILLANCE REQUIREMENTS 4.3.5

a.

Each of the above required shutdown margin monitoring instruments shall be demonstrated OPERABLE by an ANALOG CHANNEL OPERATIONAL TEST at least once per 92 days that shall include verification that the Shutdown Margin Monitor is set per the CORE OPERATING LIMITS REPORT (COLR).

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months VERIFY the minimum count rate (counts/sec) as defined within the COLR.

MILLSTONE - UNIT 3 3/4 3-83 Amendment No. 4164,229

REACTOR COOLANT SYSTEM LOOP STOP VALVES LIMITING CONDITION FOR OPERATION 3.4.1.5 operator.

Each RCS loop stop valve shall be open and the power removed from the valve APPLICABILITY:

MODES 1, 2,3 and 4.

ACTION:

a.

With power available to one or more loop stop valve operators, remove power from the loop stop valve operators within 30 minutes or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.(0)

With one or more RCS loop stop valves closed, maintain the valve(s) closed and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.1.5 Verify each RCS loop stop valve is open and the power removed from the valve operator at least once per 31 days.

(l) All required ACTIONS of ACTION Statement 3.4.1.5.b shall be completed whenever this action is entered.

I MILLSTONE - UNIT 3 3/4 4-7 Amendment No. 21-7, 229

REACTOR COOLANT SYSTEM ISOLATED LOOP STARTUP LIMITING CONDITION FOR OPERATION 3.4.1.6 A reactor coolant loop shall remain isolated with power removed from the associated RCS loop stop valve operators until:

a.

The temperature at the cold leg of the isolated loop is within 201F of the highest cold leg temperature of the operating loops, and

b.

The boron concentration of the isolated loop is greater than or equal to the boron concentration required by Specifications 3.1.1.1.2 or 3.1.1.2 for MODE 5 or Specification 3.9.1.1 for MODE 6.

APPLICABILITY:

MODES 5 and 6.

ACTION:

a.

With the requirements of the above specification not satisfied, do not open the isolated loop stop valves.

SURVEILLANCE REQUIREMENTS 4.4.1.6.1 The isolated loop cold leg temperature shall be determined to be within 200F of the highest cold leg temperature of the operating loops within 30 minutes prior to opening the cold leg stop valve.

4.4.1.6.2 The isolated loop boron concentration shall be determined to be greater than or equal to the boron concentration required by Specifications 3.1.1.1.2 or 3.1.1.2 for MODE 5 or Specification 3.9.1.1 for MODE 6 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to opening the hot or cold leg stop valve.

MILLSTONE - UNIT 3 3/4 4-8 Amendment No. X-, 6, 60, 4-4, 02, 229

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4.

Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one or both PORV(s) inoperable because of excessive seat leakage, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the block valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one or both block valve(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve(s) to OPERABLE status, or place its associated PORV(s) control switch to "CLOSE." Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

Entry into an OPERATIONAL MODE is permitted while subject to these ACTION requirements.

MILLSTONE - UNIT 3 3/4 4-12 Amendment No. -

S8, 1.864, 229

M-I U3 tw TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result ACTION Required Result ACTION Required Result ACTION Required A minimum of C-1 None N.A.

N.A.

S Tubes per C-l None N.A.

S.G C-2 Plug defective tubes C-2 Plug defective tubes C-1 None and inspect additional and inspect additional C-2 Plug defective tubes 2S tubes in this S.Cx 4S tubes in this S.G Perform ACTION-for C-3 result of first sample Perform ACTION for N.A.

N.A.

C-3 C-3 result of first sample C-3 Inspect all tubes in All other None N.A N.A this S.G, plug de-S.Gs are fective tubes and C-I inspect 2S tubes in Some S.Gs Perform ACTION for N.A.

N.A.

each other S.G.

C-2 but no C-2 result of second additional sample Notification to NRC S.G are pursuant to §50.72 C-3 (b)(2) of 10 CFR Additional Inspect all tubes in each N.A.

N.A Part 50 S.G is C-3 S.G and plug defective tubes. Notification to NRC pursuant to

§50.72 (b)(2) of 10 l

CFR Part 50 S = 3 N %Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an CD n

n minspection to 0

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

a.

Either the Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System, and

b.

The Containment Drain Sump Level or Pumped Capacity Monitoring System APPLICABILITY:

MODES I,2,3, and 4.

ACTION:

a.

With both the Containment Atmosphere Gaseous and Particulate Radioactivity Monitors inoperable, operation may continue for up to 30 days provided the Containment Drain Sump Level or Pumped Capacity Monitoring System is OPERABLE and gaseous grab samples of the containment atmosphere are obtained at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for gross noble gas activity within the subsequent 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the Containment Drain Sump Level or Pumped Capacity Monitoring System inoperable, operation may continue for up to 30 days provided either the Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System is OPERABLE; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.6.1 The Leakage Detection Systems shall be demonstrated OPERABLE by:

a.

Containment Atmosphere Gaseous and Particulate Radioactivity Monitoring Systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies specified in Table 4.3-3, and

b.

Containment Drain Sump Level and Pumped Capacity Monitoring System-performance of CHANNEL CALIBRATION at least once per 24 months.

MILLSTONE - UNIT 3 3/4 4-21 Amendment No..14, 49, 4-00, 43 06, 229

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class IE Distribution System, and

b.

Two separate and independent diesel generators, each with:

1)

A separate day tank containing a minimum volume of 278 gallons of fuel,

2)

A separate Fuel Storage System containing a minimum volume of 32,760 gallons of fuel,

3)

A separate fuel transfer pump,

4)

Lubricating oil storage containing a minimum total volume of 280 gallons of lubricating oil, and

5)

Capability to transfer lubricating oil from storage to the diesel generator unit.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

Inoperable Equipment Required ACTION

a.

One offsite circuit

a. I Perform Surveillance Requirement 4.8.1.1..a for remaining offsite circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND a.2 Restore the inoperable offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

One diesel generator

b. 1 Perform Surveillance Requirement 4.8.1.1.1.a for the offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND b.2 Demonstrate OPERABLE diesel generator is not inoperable due to common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or perform Surveillance Requirement 4.8.1.1.2.a.5 for the OPERABLE diesel generator within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

AND I

MILLSTONE - UNIT 3 3/4 8-1 Amendment No. 64, 97, 44A, 4,

229

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (continued)

Inoperable Equipment I

Required ACTION

b.

One diesel generator b.3 Verify all required systems, subsystems, trains, components, and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are OPERABLE, and the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND b.4 (Applicable only if the 14 day allowed outage time specified in ACTION Statement b.5 is to be used).

Verify the required Millstone Unit No. 2 diesel generator(s) is/are OPERABLE and the Millstone Unit No. 3 SBO diesel generator is available within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. Restore any inoperable required Millstone Unit No. 2 diesel generator to OPERABLE status and/or Millstone Unit No. 3 SBO diesel generator to available status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND b.5 Restore the inoperable diesel generator to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (within 14 days if ACTION Statement b.4 is met) or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

One offsite circuit c.1 Perform Surveillance Requirement 4.8.1.1..a for remaining offsite circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least AND once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND One diesel generator c.2 Demonstrate OPERABLE diesel enerator is not inoperable due to common cause failure within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or perform Surveillance Requirement 4.8.1.1.2.a.5 for the OPERABLE diesel generator within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

AND MILLSTONE - UNIT 3 3/4 8-2 MNAmendment No. 240, 229

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (continued)

Inoperable Equipment Required ACTION

c.

One offsite circuit c.3 Verify all required systems, subsystems, trains, AND components, and devices that depend on the e dremaining OPERABLE diesel generator as a source l One diesel generator of emergency power are OPERABLE, and the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND c.4 Restore one inoperable A.C. source to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND c.5 Restore remaining inoperable A.C. source to OPERABLE status following the time requirements of ACTION Statements a. or b. above based on the initial loss of the remaining inoperable A.C. source.

d.

Two offsite circuits

d. I Restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

AND d.2 Following restoration of one offsite source, restore remaining inoperable offsite source to OPERABLE status following the time requirements of ACTION Statement a. above based on the initial loss of the remaining inoperable offsite source.

e.

Two diesel generators e.1 Perform Surveillance Requirement 4.8.1.11.La for the offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

AND MILLSTONE - UNTIT 3 3/4 8-3 Amendment No. A24-0, 229

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (continued)

Inoperable Equipment Required ACTION

e.

Two diesel generators e.2 Restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

AND e.3 Following restoration of one diesel generator, restore remaining inoperable diesel generator to OPERABLE status following the time requirements of ACTION Statement b. above based on the initial loss of the remaining inoperable diesel generator.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and

b.

Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:*

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1)

Verifying the fuel level in the day tank,

2)

Verifying the fuel level in the fuel storage tank,

3)

Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank,

4)

Verifying the lubricating oil inventory in storage,

5)

Verifying the diesel starts from standby conditions and achieves generator voltage and frequency at 4160 - 420 volts and 60 t 0.8 Hz. The diesel generator shall be started for this test by using one of the following signals:

a)

Manual, or

All planned starts for the purpose of these surveillances may be preceded by an engine prelube period.

MILLSTONE - UNIT 3 3/4 8-3a Amendment No. 40, 64, 44-, 4-94,2-0, 229

5.0 DESIGN FEATURES 5.1 SITE LOCATION The Unit 3 Containment Building is located on the site at Millstone Point in Waterford, Connecticut. The nearest SITE BOUNDARY on land is 1719 feet northeast of the containment building wall (1627 feet northeast of the elevated stack), which is the minimum distance to the boundary of the exclusion area as described in 10 CFR 100.3. No part of the site that is closer than these distances shall be sold or leased except to Dominion Nuclear Connecticut, Inc. or its corporate affiliates for use in conjunction with normal utility operations.

5.2 DELETED MILLSTONE - UNIT 3 5-1 Amendment S.-2 229

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9.1.5 Deleted 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. Overtemperaturd 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 3/4.1.1.3.

I MILLSTONE - UNIT 3 6-19a Amendment No. 24, t 69, E6, 4°8, 24-8,22;,

229

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)

4. Shutdown Rod Insertion Limit for Specification 3/4.1.3.5,

5. Control Rod Insertion Limits for Specification 3/4.1.3.6,

6. AXIAL FLUX DIFFERENCE Limits, target band, and APLND for Specification 3/4.2.1.1,

7. Heat Flux Hot Channel Factor, K(z), W(z), APLND, and W(Z)BL for Specification 3/4.2.2.1.

8. Nuclear Enthalpy Rise Hot Chanmel Factor, Power Factor Multiplier for Specification 3/4.2.3.

9. DNB Parameters for Specification 3/4.2.5.

10. Shutdown Margin Monitor minimum count rate for Specification 3/4.3.5.

11. Boron Concentration for Specification 3/4.9.1.1.

6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," (W Proprietary). (Methodology for Specifications 3.1.1.3--Moderator Temperature Coefficient, 3.1.3.5--Shutdown Bank Insertion Limit, 3.1.3.6--Control Bank Insertion Limits, 3.2.1 --AXIAL FLUX DIFFERENCE, 3.2.2--Heat Flux Hot Channel Factor, 3.2.3--Nuclear Enthalpy Rise Hot Channel Factor,3.1.1.1.1, 3.1.1.1.2,3.1.1.2 -- SHUTDOWN MARGIN, 3.9.1.1 --

Boron Concentration.)

2. 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.

3. NUREG-800, 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 Oliset Control (CAOC), Revision 2, July 1981.

4. WCAP-10216-P-A-RIA, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION,"

(W Proprietaiv). (Methodology for Specifications 3.2.1--AXIAL FLUX DIFFERENCE [Relaxed Axial Offset Control] and 3.2.2--Heat Flux Hot Channel Factor [W(z) surveillance requirements for FQ Methodology].)

5. WCAP-9561-P-A, ADD. 3, "BART A-1: A COMPUTER CODE FOR THE BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS--SPECIAL REPORT:

THIMBLE MODELING W ECCS EVALUATION MODEL,"

QY Proprietary). (Methodology for Specification 3.2.2--Heat Flux Hot Channel Factor.)

6. WCAP-10266-P-A, Addendum 1, "THE 1981 VERSION OF THE WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE,"

(W Proprietary). (Methodology for Specification 3.2.2-Heat Flux Hot Channel Factor.)

MILLSTONE - UNIT 3 6-20 Amendment No. 24,7, 6, 69, 894, 422, 440, -24, 229

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Cont.)

7.

WCAP-11946, "Safety Evaluation Supporting a More Negative EOL Moderator Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3," (W Proprietary).

8.

WCAP-10054-P-A, "WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL. 17 USING THE NOTRUMP CODE," (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

9.

WCAP-10079-P-A, "NOTRUMP - A NODAL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," (W Proprietary). (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

10.

WCAP-12610, "VANTAGE+ Fuel Assembly Report," (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

11.

Letter from V. L. Rooney (USNRC) to J. F. Opeka, "Safety Evaluation for Topical Report, NUSCO-152, Addendum 4, 'Physics Methodology for PWR Reload Design,' TAC No. M91815," July 18, 1995.

12.

Letter from E. J. Mroczka to the USNRC, "Proposed Changes to Technical Specifications, Cycle 4 Reload Submittal - Boron Dilution Analysis," B13678, December4, 1990.

13.

Letter from D. H. Jaffe (USNRC) to E. J. Mroczka, "Issuance of Amendment (TAC No. 77924)," March 11, 1991.

14.

Letter from M.; H. Brothers to the USNRC, "Proposed Revision to Technical Specification, SHUTDOWN MARGIN Requirements and Shutdown Margin Monitor OPERABILITY forMODES 3,4, and 5 (PTSCR 3-16-97), B16447, May 9, 1997.

15.

Letter from J. W. Anderson (UJSNRC) to M. L. Bowling (NNECO), "Issuance of Amendment - Millstone Nuclear Power Station, Unit No. 3 (TAC No. M98699),"

October 21, 1998.

16.

WCAP-8301, "LOCTA-IV Program: Loss-of-Coolant Transient Analysis."

I

17.

WCAP-10054-P-A, Addendum 2, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model."

18.

WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," (Westinghouse Proprietary Class 2).

(Methodology for Specification 2.2.1.)

MILLSTONE - UNIT 3 6-20a Amendment No. 8-, 40, 2-1°, 229

ADMINISTRATIVE CONTROLS 6.9.1.6.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.

6.9.1.6.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.

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.

6.10 Deleted.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 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 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 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.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area, or MILLSTONE - UNIT 3 6-21 Amendment No. 24, 40, 6, 69, 404, 229

ADMINISTRATIVE CONTROLS 6.15 RADIOACTIVE EFFLUENT CONTROLS PROGRAM This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the REMODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the REMODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the REMODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the REMODCM at least every 31 days;

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be in accordance with the following:

1.

For noble gases: a dose rate

500 mrem/yr to the whole body and a dose rate

3000 mrem/yr to the skin, and

2.

For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate < 1500 mrem/yr to any organ;

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR 50, Appendix I;

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY, conforming to 10 CFR 50, Appendix I; and MILLSTONE - UNIT 3 6-25 Amendment No. 4188,24, 229

ADMINISTRATIVE CONTROLS

j.

Limitations on the annual dose or dose commitment to any member of the public, beyond the SITE BOUNDARY, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of Specification 4.0.2 and Specification 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

6.16 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 REMODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

a.

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

b.

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

c.

Participation in a 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.

6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels at least once every 10 years.

6.18 TECHNICAL SPECIFICATIONS TS)1 BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications:

a.

Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following: i

1.

A change in the TS incorporated in the license or

2.

A change to updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

MILLSTONE - UNIT 3 6-26 Amendment No. 4IS, 204, 212, 2-,

229

APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-49 MILLSTONE POWER STATION, UNIT 3 DOMINION NUCLEAR CONNECTICUT, INC.

DOCKET NO. 50-423 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

Amendment No. 229

MILLSTONE POWER STATION, UNIT NO. 3 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

TABLE OF CONTENTS Section Page 1.0 Objectives of the Environmental Protection Plan.................................................... 1-1 2.0 Environmental Protection Issues...............

..................................... 2-1 3.0 Consistency Requirements....................................................

3-1 3.1 Plant Design and Operation.................................................... 3-2 3.2 Reporting Related to the NPDES Permit and State Certifications...............

............ 3-3 3.3 Changes Required for Compliance with Other Environmental Regulations............

3-3 4.0 Environmental Conditions.................................................... 4-1 4.1 Unusual or Important Environmental Events....................................................

4-1 4.2 Environmental Monitoring.................

4-1 5.0 Administrative Procedures.................

5-1 5.1 Review.................

5-1 5.2 Records Retention.................

5-1 5.3 Changes in Environmental Protection Plan.............................

5-2 5.4 Plant Reporting Requirements.............................

5-2 MILLSTONE - UNIT 3 Amendment No. 229

2.0 Environmental Protection Issues In the FES-OL dated December, 1984, the staff considered the environmental impacts associated with the operation of Millstone Power Station, Unit No. 3. No environmental issues were I

identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of the environment.

MILLSTONE - UNIT 3 2-1 Amendment No. 229

written evaluation of such activity and obtain prior NRC approval. When such activity involves a change in the EPP, such activity and change to the EPP may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3 of this EPP.

A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns: (I) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level; or (3) a matter, not previously reviewed and evaluated in the documents specified in (I) of this Subsection, which may have a significant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of the Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests and experiments.

MILLSTONE - UNIT 3 3-2 Amendment No. 229

v t e Letter Sequence Other
TAC:MC6315, (Open) TAC:MC6316, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML051660042, ML060760208
MONTHYEAR2006-03-16 [Table View]

ML060760208

Text

Attachment:

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