ML042310488

Tech Spec Pages for Amendment No. 116, Steam Generator Water Level Instrumentation

ML042310488
Person / Time
Site:	Harris
Issue date:	08/16/2004
From:	NRC/NRR/DLPM
To:
Patel C P, NRR/DLPM, 415-3025
References
TAC MC1942
Download: ML042310488 (9)

Text

INDEX 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE...........................

2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..................

2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMITS - THREE LOOPS IN OPERATION.

2-2 WITH MEASURED RCS FLOW > [293,540 GPM x (1.0 + C1)]

2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS........... 2-1 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS..... 2-4 BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE.......................... B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS.......... B 2-2 SHEARON HARRIS - UNIT 1 iii Amendment No.

116

INDEX 3.0/4.0 BASES SECTION 3/4.0 APPLICABILITY PAGE B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL...............

3/4.1.2 BORATION SYSTEMS...............

3/4.1.3 MOVABLE CONTROL ASSEMBLIES..........

3/4.2 POWER DISTRIBUTION LIMITS.............

3/4.2.1 AXIAL FLUX DIFFERENCE.............

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR FIGURE B 3/4.2-1 (DELETED) 3/4.2.4 QUADRANT POWER TILT RATIO...........

3/4.2.5 DNB PARAMETERS................

3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM INSTRUMENTATION AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION................

3/4.3.3 MONITORING INSTRUMENTATION..........

3/4.3.4 (DELETED)...................

B 3/4 1-1 B 3/4 1-2 B 3/4 1-3 B 3/4 2-1 B 3/4 2-1 B 3/4 2-2a B 3/4 2-3 B 3/4 2-6 B 3/4 2-6 B 3/4 3-1 B 3/4 3-3 B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 3/4.4.2 3/4.4.3 3/4.4.4 3/4.4.5 3/4.4.6 3/4.4.7 3/4.4.8 3/4.4.9 REACTOR COOLANT LOOPS AND COOLANT SAFETY VALVES..........

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

RELIEF VALVES..........

STEAM GENERATORS........

REACTOR COOLANT SYSTEM LEAKAGE CHEMISTRY............

SPECIFIC ACTIVITY........

PRESSURE/TEMPERATURE LIMITS...

CIRCULATION..... B 3/4 4-1

........... B 3/4 4-1

........... B 3/4 4-2

........... B 3/4 4-2

........... B 3/4 4-2b

........... B 3/4 4-3

. B 3/4 4-4

........... B 3/4 4-5

........... B 3/4 4-6 SHEARON HARRIS - UNIT 1 xiii Amendment No. 11 6

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION.........

B 3/4 7-2 3/4.7.3 COMPONENT COOLING WATER SYSTEM..........................

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

B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK......................................

B 3/4 7-3 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM................

B 3/4 7-3 3/4.7.7 REACTOR AUXILIARY BUILDING EMERGENCY EXHAUST SYSTEM.....

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

B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-5 3/4.7.10 (DELETED).B 3/4 7-5 3/4.7.11 (DELETED).B 3/4 7-5 3/4.7.12 (DELETED).B 3/4 7-5 3/4 7.13 ESSENTIAL SERVICES CHILLED WATER SYSTEM.B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 3/4 8 2 AND 3/4.8.3 A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION...................................

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.................

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4.9.2 INSTRUMENTATION.........................................

3/4.9.3 (DELETED)...............................................

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4.9.5 (DELETED)...............................................

3/4.9.6 (DELETED)...............................................

3/4.9.7 (DELETED)...............................................

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........

3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND NEW AND SPENT FUEL POOLS..............

3/4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM........

B 3/4 8-1 B 3/4 8-3 B

B B

B B

B B

B B

3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 9-1 9-1 9-1 9-1 9-2 9-2 9-2 9-2 9-2 I

I B 3/4 9-3 B 3/4 9-4 SHEARON HARRIS - UNIT 1 xv Amendment No. 116

INDEX BASES SECTION 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN................

3/4.10.2 GROUP HEIGHT. INSERTION. AND POWER DISTRIBUTION 3/4.10.3 PHYSICS TESTS.................

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

3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN.....

PAGE

.... B 3/4 10-1 LIMITS B 3/4 10-1

....B 3/4 10-1

.... B 3/4 10-1

.... B 3/4 10-1 3/4.11 3/4.11.1 3/4.11.2 3/4.11.3 3/4.11.4 RAnlTnArTIVF FFFI IJFNTS

. I -

I. I LIQUID EFFLUENTS.

GASEOUS EFFLUENTS.

(DELETED).....

(DELETED).....

.... B 3/4 11-1

.... B 3/4 11-1 I

.... B 3/4 11-2

.... B 3/4 11-2 3/4.12 3/4.12.1 3/4.12.2 3/4.12.3 RADIOLOGICAL (DELETED)

(DELETED)

(DELETED)

ENVIRONMENTAL MONITORING

................. B 3/4 12-1

................. B 3/4 12-1

................. B 3/4 12-1 SHEARON HARRIS - UNIT 1 xvi Amendment No. 11 6

INDEX 5.0 DESIGN FEATURES SECTION 5.1 SITE 5.1.1 EXCLUSION AREA........................

5.1.2 LOW POPULATION ZONE......................

5.1.3 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS........

FIGURE 5.1-1 EXCLUSION AREA..................

FIGURE 5.1-2 LOW POPULATION ZONE................

FIGURE 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.

FIGURE 5.1-4 ROUTINE GASEOUS RADIOACTIVE EFFLUENT RELEASE POINTS PAGE 5-1 5-1 5-1 5-2 5-3 5-4 5-5 5-1 5-6 5-6 5-6 5-6 5-6 5.2 CONTAINMENT 5.2.1 CONFIGURATION...........................

5.2.2 DESIGN PRESSURE AND TEMPERATURE..................

5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES..........................

5.3.2 CONTROL ROD ASSEMBLIES......................

5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE..................

5.4.2 VOLUME..............................

5.5 METEOROLOGICAL TOWER LOCATION................... 5-6a I 5.6 FUEL STORAGE 5.6.1 CRITICALITY............................ 5-7 5.6.2 DRAINAGE

............................. 5-7 5.6.3 CAPACITY

............................. 5-7 FIGURE 5.6-1 BURNUP VERSUS ENRICHMENT FOR PWR FUEL......... 5-7b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT................ 5-7a TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS............ 5-8 SHEARON HARRIS - UNIT 1 xvi i Amendment No. II 6

INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION P

PAGE 6.1 RESPONSIBILITY........................... 6-1 6.2 ORGANIZATION..........

6.2.1 ONSITE AND OFFSITE ORGANIZATION 6.2.2 UNIT STAFF..........

FIGURE 6.2-1 DELETED........

FIGURE 6.2-2 DELETED........

TABLE 6.2-1 MINIMUM SHIFT CREW COMPO 6.2.3 DELETED............

6.2.4 SHIFT TECHNICAL ADVISOR....

.................. 6-1

............... 6-1 1

.................. 6-la I

............... 6-3

.................. 6-4 ITION

.............. 6-5

.................. 6-6

.................. 6-6 IS 6.3 DELETED........

.. 6-6 6.4 TRAINING.............................. 6-7 6.5 DELETED........

... 6-7 SHEARON HARRIS - UNIT 1 xviii Amendment No. 116

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6-16 6.6 REPORTABLE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION.

6.8 PROCEDURES AND PROGRAMS 6-16 6-16 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS..............

Startup Report Annual Reports Annual Radiological Environmental Operating Annual Radioactive Effluent Release Report Monthly Operating Reports.........

Core Operating Limits Report.......

6.9.2 SPECIAL REPORTS..............

6.10 DELETED..................

Report

.. 6-20

.. 6-20

.. 6-20

.. 6-21

.. 6-22

.. 6-23

.. 6-24

.. 6-24c I

........... 6-24c I 6.11 RADIATION PROTECTION PROGRAM 6.12 HIGH RADIATION AREA.....

6.13 PROCESS CONTROL PROGRAM (PCP)

............. 6-26

............. 6-26

............. 6-27 SHEARON HARRIS - UNIT 1 xix Amendment No. 11 6

REACTOR COOLANT SYSTEM HOT SHUTDOWN SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required reactor coolant pump(s). if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying wide range (WR) secondary side water level is greater than 74% or narrow range (NR) secondary side water level is greater than 30% at least onceI per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.3 operation At least one reactor coolant or RHR loop shall be verified in and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SHEARON HARRIS - UNIT 1 3/4 4-5 Amendment No. 116

REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one residual heat removal (RHR) loop shall be OPERABLE and in operation'. and either:

a.

One additional RHR loop shall be OPERABLE". or

b.

The secondary side water level of at least two steam generators shall be greater than 74% wide range (WR) or greater than 30%

narrow range (NR).

APPLICABILITY:

MODE 5 with reactor coolant loops filled ACTION:

a.

With one of the RHR loops inoperable and with less than the required steam generator water level. immediately initiate corrective action to return the inoperable RHR loop to OPERABLE status or restore the required steam generator water level as soon as possible.

b.

With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'The RHR pump may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration. and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

One RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.

A reactor coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 3250F unless the secondary water temperature of each steam generator is less than 50'F above each of the Reactor Coolant System cold leg temperatures.

SHEARON HARRIS - UNIT 1 3/4 4-6 Amendment No.116