ML032751202
| ML032751202 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/01/2003 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB6615 | |
| Download: ML032751202 (12) | |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS............................... 3/4 9-4 3/4.9.5 (THIS SPECIFICATION NUMBER IS NOT USED).......................... 3/4 9-5 3/4.9.6 THIS SPECIFICATION NUMBER IS NOT USED).......................... 3/4 9-6 3/4.9.7 THIS SPECIFICATION NUMBER IS NOT USED).......................... 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High W ater Level ...................................................................... 3/4 9-8 Low W ater Level ...................................................................... 3/4 9-9 3/4 9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM 3/4 9-10 3/4 9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-11 3/4 9.11 WATER LEVEL - STORAGE POOL 3/4 9-12 3/4 9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM 3/4 9-13 3/4 9.13 SPENT FUEL ASSEMBLY STORAGE 3/4 9-16 FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS. INITIAL ENRICHMENT FOR SPENT FUEL ASSEMBLY STORAGE ........................... 3/4 9-17 3/4.9.14 NEW FUEL ASSEMBLY STORAGE ............................................. 3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS 3/4 10-2 3/4.10.3 PHYSICS TESTS 314 10-3 3/4.10.4 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 10-4 I 3/4.10.5 POSITION INDICATION SYSTEM- SHUTDOWN 3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS (THIS SPECIFICATION NUMBER IS NOT USED) ......................... 3/4 11-1 (THIS SPECIFICATION NUMBER IS NOT USED) ......................... 3/4 11-2 (THIS SPECIFICATION NUMBER IS NOT USED) ......................... 3/4 11-3 Liquid Holdup Tanks ................................................................ 3/4 11-4 3/4.11.2 GASEOUS EFFLUENTS (THIS SPECIFICATION NUMBER IS NOT USED) .......................... 3/4 11-5 (THIS SPECIFICATION NUMBER IS NOT USED) ................... 3/4 11-6 (THIS SPECIFICATION NUMBER IS NOT USED) .......................... 3/4 11-7 (THIS SPECIFICATION NUMBER IS NOT USED) .......................... 3/4 11-8 Explosive Gas Mixture - System .............................................. 3/4 11-9 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED)........................ 3/4 11-10 314.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) ........................ 3/4 11-12 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED)........................... 3/4 12-1 SEABROOK - UNIT I ix Amendment No. 6,34,66,72 91
INDEX BASES SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ................... B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM................ B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL.......................................................................................... B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM ...... B 3/4 9-2 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE.......................................................... B 3/4 9-3 314.9.14 NEW FUEL ASSEMBLY STORAGE.............................................................. B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN................................................................................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS...... B 3/4 10-1 3/4.10.3 PHYSICS TESTS ........................................................................................... B 3/4 10-1 3/4.10.4 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 10-1 I 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN........................................ B 3/4 10-1 3/4.10.6 REACTOR COOLANT LOOPS...................................................................... B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 (THIS SPECIFICATION NUMBER IS NOT USED) .................................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS................................................................................ B 3/4 11-2 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 11-5 3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 12-1 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 12-1 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) ....................................... B 3/4 12-2 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.............................................................................................. 5-1 5.1.2 LOW POPULATION ZONE .................................................................................. 5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS......................................
FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY ........................................... 5-3 FIGURE 5.1-2 LOW POPULATION ZONE....................................................................... 5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION......................................... 5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION............................................................................................... 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE...................................................... 5-9 SEABROOK - UNIT I Aii SEABROOK Amendment
-UNIT I xiiNo. 14W, 91
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) Z (SL TRIP SETPOINT ALLOWABLE VALUE
- 1. Manual Reactor Trip N.A. N.A. N.A. N.A. N.A.
- 2. Power Range, Neutron Flux
- a. High Setpoint 7.5 4.56 1.42 <109% of RTP* 5111.1% of RTP*
- b. Low Setpoint 8.3 4.56 1.42 <25% of RTP* *27.1% of RTP*
- 3. Power Range, Neutron Flux, 1.6 0.5 0 S5% of RTP* with *6.3% of RTP* with High Positive Rate a time constant a time constant 22 seconds 22 seconds
- 4. NOT USED I
- 5. Intermediate Range, 17.0 8.41 0 *25% of RTP* 531.1% of RTP*
Neutron Flux
- 6. Source Range, Neutron Flux 17.0 10.01 0 *1 05 cps *1.6 x 105 cps
- 7. Overtemperature AT N.A. N.A. N.A. See Note I See Note 2
- 8. Overpower AT N.A. N.A. N.A. See Note 3 See Note 4
- 9. Pressurizer Pressure - Low N.A. N.A. N.A. 21945 psig 21,933 psig
- 10. Pressurizer Pressure - High N.A. N.A. N.A. s2385 psig 72,397 psig
- RTP = RATED THERMAL POWER SEABROOK - UNIT I 2-4 Amendment No. 42, a, 91
TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 1. Manual Reactor Trip 2 1 2 1,2 1 2 1 2 3*, 4*, 5* 10
- 2. Power Range, Neutron Flux
- a. High Setpoint 4 2 3 2 1#t, 2 2
- b. Low Setpoint 4 2 3 1,2
- 3. Power Range, Neutron Flux 4 2 3 1,2 2 High Positive Rate
- 4. NOT USED I
- 5. Intermediate Range, Neutron Flux 2 I 2 3
- 6. Source Range, Neutron Flux
- a. Startup 2 I 2 4
- b. Shutdown 2 0 1 3,4,5 5
- c. Shutdown 2 1 2 3*, 4*, 5* 10
- 7. Overtemperature AT 4 2 3 1,2 6
- 8. Overpower AT 4 2 3 1,2 6
- 9. Pressurizer Pressure-Low 4 2 3 1** 6
- 10. Pressurizer Pressure-High 4 2 3 1, 2 6
- 11. Pressurizer Water Level-High 3 2 2 1** 6#
SEABROOK - UNIT 1 3/4 3-2 Amendment No. 36, 01
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHEQK_ CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
- 1. Manual Reactor Trip N.A. N.A. N.A. R(13) N.A. 1,2,3',4*,5*
- 2. Power Range, Neutron Flux
- a. High Setpoint S D(2, 4), Q N.A. N.A. 1,2 M(3, 4),
Q(4. 6),
R(4, 5)
- b. Low Setpoint S R(4) SIU(1) N.A. N.A. 1***, 2
- 3. Power Range, Neutron Flux, N.A. R(4) Q N.A. N.A. 1,2 High Positive Rate
- 4. NOT USED I
- 5. Intermediate Range, S R(4, 5) SIU(1) N.A. N.A. 1***, 2 Neutron Flux
- 6. Source Range, Neutron Flux S R(4. 5) S/U(8),Q(9) N.A. N.A. 2*,,3,4,5 I
- 7. Overtemperature AT S R Q N.A. N.A. 1,2
- 8. Overpower AT S R Q N.A. N.A. 1,2
- 9. Pressurizer Pressure-Low S R Q N.A. N.A. 1
- 10. Pressurizer Pressure-High S R Q NA N.A. 1,2
- 11. Pressurizer Water Level-Hlgh S R N.A. N.A.
Q I
- 12. Reactor Coolant Flow-Low S R Q N.A. N.A. I SEABROOK - UNIT 1 3/4 3-9 Amendment No. 36, 91
TABLE 4.31 (Contnu REACTO TRIP SYSTM INSTRUMENTATION SURVILLaNjCE REQUIREMENS.
TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT gi8ECK CALiBRATiON TEST TIES LQ ISREQUIJRED
- 13. Steam Generator 'AFater Level S R Q NA NJ 1,2 LoW-Low
- 14. Undervoltage - Reactor Coolant NA R NA Q NJL I Pumps
- 15. Underfrequency - R eactor NA R NA. Q NJ I Coolant Pumps
- 16. Turbine Trip
- a. Low Fluid Oll Pressure NA R NA S/U(8, 10) NA I
- b. Turbine Stop Valve NA R N.A S/N(8, 10) NA. I
- 17. Safety Injection Input from NA NA NA. R NA. 1.2 ESF
- 18. Reactor Trip System Interlocks
- a. Intermediate Range Neutron Flux, P-6 N.A. R(4) R NA NA. 2**
- b. Low Power Reactor Trips Block, P-7 NA R(4) R NA NA I
- c. Power Range Neutron Flux, P-B NA R(4) R NA NA I
- d. Power Range Neutron Flux, P-9 NA R(4) R NA NA I SEABROOK-UNIT I 314 3-10 Amendment No. M, 9i
TABLE 4.3-1 (Continued)
TABLE NOTATIONS
- Only If the Reactor Trip System breakers happen to be closed and the Control Rod Drive System Iscapable of rod withdrawal.
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-1 0 (Low Setpolnt Power Range Neutron Flux Interlock) Setpolnt.
(1) If not performed In previous 92 days.
(2) Comparison of calorimetric to excore power Indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power If absolute difference Is greater than 2%. The provisions of Specification 4.OA are not applicable to entry Into MODE 2 or 1.
(3) Single point comparison of Incore to excore AXIAL FLUX DIFFERENCE above 50%
of RATED THERMAL POWER. Recalibrate If the absolute difference Isgreater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry Into MODE 2 or 1. For the purposes of this surveillance requirement, monthly shagl mean at least once per 31 EFPD.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) Initial plateau curves shall be measured for each detector. Subsequent plateau curves shall be obtained, evaluated and compared to the Initial curves. For the Intermediate Range and Power Range Neutron Flux channels the provIsIons of Specification 4.0.4 are not applicable for entry Into MODE 2 or 1.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0A are not applicable for entry Into MODE 2 or 1. For the purposes of this surveillance requirement, quarterly shall mean at least once per 92 EFPD.
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(8) If not performed in previous 31 days.
(9) Surveillance InMODES 3*, 4*, and 5* shan also Include verification that permissives P6 and P-10 are Intheir required state for existing plant conditions by observation of the permissive annunciator window.
(10) Setpoint verification Is not applicable.
(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall Independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
SEABROOK - UNIT I 3/4 3-12 Amendment No. 33, 91
_ REACTOR COOLANT SYSTEM _ ___ __
3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 All reactor coolant loops shall be in operation.
APPLICABILITY: MODES 1 and 2. I ACTION:
With less than the above required reactor coolant loops in operation, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified 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 />.
I SEABROOK - UNIT I 3/4 4-1 Amendment No. 91
-SPECIAL TEST EXCEPTIIONS ___ ___ __
314.10.3 PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.3 The limitations of Specifications 3.1.1.3, 3.1.1.4, 3.1.3.1, 3.1.3.5, and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS provided:
- a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER,
- b. The Reactor Trip Setpoints on the OPERABLE Intermediate Range and Power Range* channels are set at less than or equal to 25% of RATED THERMAL POWER, and
- c. The Reactor Coolant System lowest operating loop temperature (Tan) is greater than or equal to 541 "F.
APPLICABILITY: MODE 2.
ACTION:
- a. With the THERMAL POWER greater than 5%of RATED THERMAL POWER, Immediately open the Reactor trip breakers.
- b. With a Reactor Coolant System operating loop temperature (Tavg) less than 541 OF, restore Tavg to within Its limit within 15 minutes or be in at least HOT STANDBY within the next 15 minutes.
SURVEILLANCE REQUIREMENTS 4.10.3.1 The THERMAL POWER shall be determined to be less than or equal to 5%of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
4.10.3.2 Verify each OPERABLE Intermediate Range and Power Range* channel has been subjected to an ANALOG CHANNEL OPERATIONAL TEST per Specification Table 4.3-1 prior to initiating PHYSICS TESTS.
4.10.3.3 The Reactor Coolant System temperature (Tavg) shall be determined to be greater than or equal to 541 "F at least once per 30 minutes during PHYSICS TESTS.
- Power Range Low Setpoint only.
SEABROOK - UNIT I 3/4 10-3 Amendment No. 9i
SPECIAL TEST EXCEPTIONS ___ ___ _ _
3/4.10.4 (THIS SPECIFICATION NUMBER IS NOT USED) I SEABROOK - UNIT 1 3/4 10-4 Amendment No. 91
LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS (Continued)
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level. In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity. The functional capability at the specified trip setting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip Is Initiated. This prevents the reactivity Insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
Manual Reactor Trim The Reactor Trip System includes manual Reactor trip capability.
Power Range. Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip setting. The Low Setpolnt trip provides protection during subcritical and low power operations to mitigate the consequences of a power excursion beginning from low power, and the High Setpoint trip provides protection during power operations to mitigate the consequences of a reactivity excursion from all power levels.
The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Range. Neutron Flux. High Positive Rate The Power Range High Positive Rate trip provides protection against rapid flux Increases which are characteristic of a rupture of a control rod drive housing. Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid-power.
SEABROOK- UNIT 1 B 2-4 Amendment No. 91
-314i& SPECIALTESTIEXCEPTIONS_ ____ __ __ __
BASES 3/4.10.1 SHUTDOWN MARGIN This special test exception provides that a minimum amount of control rod worth is immediately available for reactivity control when tests are performed for control rod worth measurement. This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel bumup or fuel cycling operations.
3/4.10.2 GROUP HEIGHT. INSERTION, AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be positioned outside of their normal group heights and insertion limits during the performance of such PHYSICS TESTS as those required to: (1) measure control rod worth and (2) determine the reactor stability index and damping factor under xenon oscillation conditions.
3/4.10.3 PHYSICS TESTS This special test exception permits PHYSICS TESTS to be performed at less than or equal to 5% of RATED THERMAL POWER with the RCS Tvg slightly lower than normally allowed so that the fundamental nuclear characteristics of the core and related instrumentation can be verified. In order for various characteristics to be accurately measured, it is at times necessary to operate outside the normal restrictions of these Technical Specifications. For instance, to measure the moderator temperature coefficient at BOL, it is necessary to position the various control rods at heights which may not normally be allowed by Specification 3.1.3.6 and the RCS Tavg may be below the minimum temperature of Specification 3.1.1.4 during the measurement.
3/4.10.4 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN This special test exception permits the Position Indication Systems to be inoperable during rod drop time measurements. The exception is required since the data necessary to determine the rod drop time are derived from the induced voltage in the position indicator coils as the rod is dropped. This induced voltage is small compared to the normal voltage and, therefore, cannot be observed If the Position Indication Systems remain OPERABLE.
SEABROOK - UNIT 1 B 314 10-1 Amendment No. 34, 91