ML032970550
ML032970550 | |
Person / Time | |
---|---|
Site: | Turkey Point ![]() |
Issue date: | 10/21/2003 |
From: | NRC/NRR/DLPM |
To: | |
References | |
TAC MB7148, TAC MB7149 | |
Download: ML032970550 (22) | |
Text
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE 5.41.1 SITE LOCATION......................................................5-I 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 FUEL STORAGE 5.5.1 CRITICALITY........................................................
5.5.2 DRAINAGE.........................................................
5.5.3 CAPACITY...........................................................
5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT..............................
TABLE 5.6-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.....................
TURKEY POINT - UNITS 3 & 4 AiV AMENDMENT N(
5-1 5-1 5-4 5-4 5-4 5-4 5-5 5-6 5-6 5-6 5-7
.I DS. 224 AND 219
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly containing 204 fuel rods clad with Zircaloy-4 or ZIRLO", except that replacement of fuel rods by filler rods consisting of stainless steel, or by vacant rod positions, may be made In fuel assemblies if justified by cycle-specific reload analysis using NRC-approved methodology. The reactor core contains approximately 71 metric tons of uranium In the form of natural or slightly enriched uranium dioxide pellets. Each fuel rod shall have a nominal active fuel length of 144 Inches. Should more than 30 Individual rods In the core, or 10 fuel rods in any fuel assembly, be replaced per refueling, a Special Report discussing the rod replacements shall be submitted to the Commission within 30 days after cycle startup.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 45 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The absorber material shall be silver, indium, and cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System Is designed and shall be maintained:
- a.
In accordance with the Code requirements specified In Section 4.1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,
- b.
For a pressure of 2485 psig + 1%, and
- c.
For a temperature of 650°F, except for the pressurizer which is 6800F.
VOLUME 5.4.2 The nominal water and steam volume of the Reactor Coolant System is 9343 cubic feet at a nominal Toy of 574.2°F.
TURKEYPOINT -U-NITS-3 & 4 -
AMENDMENT HOS-224 AND 219
DESIGN FEATURES 5.5 FUEL STORAGE 5.5.1 CRITICALITY 5.5.1.1 The spent fuel storage racks are designed to provide safe subcritical storage of fuel assemblies by providing sufficient center-to-center spacing or a combination of spacing and poison and shall be maintained with:
- a.
kff equivalent to less than 1.0 when flooded with unborated water, which Includes a conservative allowance for uncertainties as described In WCAP-1 4416-P.
- b.
A kff equivalent to less than or equal to 0.95 when flooded with borated to 650 ppmn water, which includes a conservative allowance for uncertainties as described in WCAP-14416-P.
C.
A nominal 10.6 Inch center-to-center distance for Region I arid 9.0 inch center-to-center distance for Region II for two region fuel storage racks.
- d.
The maximum enrichment loading for fuel assemblies Is 4.5 w~eight percent of U-235.
5.5.1.2 The racks for new fuel storage are designed to store fuel In a sate subcritical array and shall be maintained with:
- a.
A nominal 21 inch center-to-center spacing to assure kef equal to or less than 0.98 for optimum moderation conditions and equal to or less than 0.95 for fully flooded conditions.
- b.
Fuel assemblies placed In the New Fuel Storage Area shall contain no more than 4.5 weight percent of U-235.
TURKEY POINT - UNITS 3 & 4 5-5 AMENDMENT NOS. 224 AND 219
DE$IGN FEATURES 5.5.1.3 Credit for bumup is taken in determining placement locations for spent fuel In the two-region spent fuel racks. Administrative controls are employed to evaluate the burnup of each spent fuel assembly stored in areas where credit for burnup Is taken. The bumup of spent fuel is ascertained by careful analysis of bumup history, prior to placement Into the storage locations. Procedures shall require an independent check of the analysis of suitability for storage. A complete record of such analysis is kept for the time period that the spent fuel assembly rpmains In storage onsite.
DRAINAGE 5.5.2 The spent fuel storage pit is designed and shall be maintained to prevent Inadvertent draining of the pool below a level of 6 feet above the fuel assemblies in the storage racks.
CAPACITY 5.5.3 The spent fuel storage pool Is designed and shall be maintained with a storage capacity limited to no more than 1404 In two region storage racks 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.6.1 The components identified in Table 5.6-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6-1.
TURKEY POINT -UNITS 3 & 4 5-6 AMENDMENT NOS. 224 AND 219
-4 C
0 z-1 C=
z CD, P-J Tnl 0en COMPONENT ii I
- I ii I I I
I I
I TABLE 5.6-1 I
COMPONENT CYCLIC OR TRANSIENT LIMITS CYCLIC OR TRANSIENT LIMIT 200 heatup cycles at < 1000 F/h and 200 cooldown cycles at
- I00°F/h.
200 pressurizer cooldown cycles at* 200OF/h.
80 loss of load cycles, without immediate Turbine or Reactor trip.
40 cycles of loss-of-offsite A.C. electrical power.
80 cycles of loss of flow in one reactor coolant loop.
400 Reactor trip cycles.
150 leak tests.
5 hydrostatic pressure tests.
6 loss of secondary pressure 50 leak tests 35 hydrostatic pressure tests.
DESIGN CYCLE OR TRANSIENT Heatup cycle - TV,, from
- 200'F to 2 5500F.
Cooldown cycle - T., from 2 5500F to
- 2000F.
Pressurizer cooldown cycle temperatures from > 6500F to
- 2000F.
215% of RATED THERMAL POWER to 0% of RATED THERMAL POWER.
Loss-of-offsite A.C. electrical ESF Electrical System.
Loss of only one reactor coolant pump.
100% to 0% of RATED THERMAL POWER.
Pressurized to 2 2435 psig.
PressurIzed to 23100 psig.
Loss of Secondary pressure Pressurized to 2 1085 psig Pressurized to 2 1356 psig.
ry Coolant System Seconda' I
i I
I i
INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS............
1.0 1.1 ACTION.1-1 1.2 ACTUATION LOGIC TEST.1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST.1-1 1.4 AXIAL FLUX DIFFERENCE.1-1 1.5 CHANNEL CALIBRATION.1-1 1.6 CHANNEL CHECK..................................
1-1 1.7 CONTAINMENT INTEGRITY.1-2 1.8 CONTROLLED LEAKAGE.1-2 1.9 CORE ALTERATION.1-2 1.10 CORE OPERATING LIMITS REPORT.1-2 1.11 DIGITAL CHANNEL OPERATIONAL TEST...............................
1-2 1.12 DOSE EQUIVALENT 1-131.1-3 1.13 E AVERAGE DISINTEGRATION ENERGY.1-3 1.14 FREQUENCY NOTATION.1-3 1.15 GAS DECAYTANK SYSTEM.1-3 1.16 IDENTIFIED LEAKAGE.1-3 1.17 OPERABLE - OPERABILITY.
1-4 1.18 OPERATIONAL MODE - MODE.1-4 1.19 PHYSICS TESTS.1-4 1.20 PRESSURE BOUNDARY LEAKAGE.1-4 1.21 PURGE-PURGING.1-4 1.22 QUADRANT POWER TILT RATIO.1-5 1.23 RATED THERMAL POWER.1-5 1.24 REPORTABLE EVENT.1-5 1.25 SHUTDOWN MARGIN.1-5 1.26 SITE BOUNDARY.1-5
- -TURKEYPOINT-1.UNITS3&,4.,-i
_ AMENDMENT NOS. 224 AND 219
INDEX DEFINITIONS SECTION PAGE 1.27 SO LIDIFICATION........................................................................................................
1.28 SOURCE CHECK.......................................................................................................
1.29 STAGGERED TEST BASIS........................................................................................
1.30 THERMAL POWER..................
1.31 TRIP ACTUATING DEVICE OPERATIONAL TEST....................................................
1.32. UNIDENTIFIED LEAKAGE.
1.33 UNRESTRICTED AREA.............................................................................................
1.34 VENTILATION EXHAUST TREATMENT SYSTEM.....................................................
1.35 VENTING....................................................................................................................
TABLE 1.1 FREQUENCY NOTATION..................................................................................
TABLE 1.2 OPERATIONAL MODES....................................................................................
1-5 1-5 1-5 1-6 1-6 1-6 1-6 1-6 1-6 1-7 1-8 I
......I.
TURKEY-POINT - UNITS 3 & 4 ii AMENDMENT NOS. 224 AND 219
DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
- a.
All penetrations required to be closed during accident conditions are either:
- 1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or
- 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured In their closed positions, except as provided in Specification 3.6.4.
- b.
The equipment hatch is closed and sealed,
- c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3,
- d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and
- e.
The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rIngs) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATIONS 1.9 CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT 1.10 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with NRC approved methodology. Unit operation within these operating limits is addressed in individual specifications. The COLR is submitted to the NRC in accordance with the requirements of 6.9.1.7.
DIGITAL CHANNEL OPERATIONAL TEST 1.11 A DIGITAL CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the
channel as close to thesensor. as practicable to yerify OPERABILITY of alarm, interlock, and/or trip functions.
TURKEYPOINT_-UN1TS._344 1-2 AMENDMENT NOS. 224 AND 219
DEFINITIONS DOSE EQUIVALENT 1-131 1.12 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.
E-AVERAGE DISINTEGRATION ENERGY 1.13 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample isotopes, other than iodines, with half lives greater than 30 minutes, making up at least 95 percent of the total non-iodine activity in the coolant.
FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the Intervals defined in Table 1.1.
GAS DECAY TANK SYSTEM 1.15 A GAS DECAY TANK SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
- a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
- b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c.
Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.
TURKEY POINT - UNITS 3 & 4 1 -3 AMENDMENT NOS. 2-24 AND 219
DEFINITIONS OPERABLE - OPERABILITY 1.17 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).
OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation: (1) described in Chapter 13.5 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.20 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
PURGE - PURGING 1.21 PURGE or PURGING shall be any 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 required to purify the confinement.
TURKEY POINT - UNITS 3 & 4 1-4 AMENDMENT NOS.224 AND 219
DEFINITIONS QUADRANT POWER TILT RATIO 1.22 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be usdd for computing the average.
RATED THERMAL POWER
.. 1.23.RATED THERMAL POWER shall be atotal reactor core heat transfer rate to the reactor coolant of 2300 MWt.
REPORTABLE EVENT 1.24 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
SHUTDOWN MARGIN 1.25 SHUTDOWN MARG IN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully Inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully Withdrawn.
SITE BOUNDARY 1.26 The SITE BOUNDARY shall mean that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.
SOLI DIFICATION 1.27 SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK 1.28 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
STAGGERED TEST BASIS 1.29 A STAGGERED TEST BASIS shall consist of:
- a.
-A-tcst-hedule-for n systems,,subsystems-- tralns,-or-other--designated components
.- obtained-by-dividing the specified test interval into n equal subintervals, and
- b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
TURKEY POINT - UNITS 3 & 4 15AMENDMENT NOS. 224 AND 219
DEFINITIONS THERMAL POWER 1.30 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.31 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.32 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.33 An UNRESTRICTED AREA shall mean an area, access to which is neither limited nor controlled by the licensee.
VENTILATION EXHAUST TREATMENT SYSTEM 1.34 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.35 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain l 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.
TURKEY POINT-- UNITS-3 & 4.---
16 AMENDMENT NOS, 224 AND 219
I 011 kr3 TABLE 2.2-1 (Continued)
TABLE NOTATIONS NOTE 1:
rE EMPERATURE AT (1+r~S)
(
ir(+T4S)1
(+T2S)
(1 +r3S)
(I+T S) T(1+ T6S) -T+K 5(P-P')-fdAI)j Whbre:
AT
=
Measured AT by RTD Instrumentation 1 :
=
Lead/Lag compensator on measured AT; sr = Os, T2 Os
-1~~~~~1
~
=
Lag compensator on measured AT; T3 = Os AT6 j
Indicated AT at RATED THERMAL POWER K,'
1.24; KlI 0.017PF; 4
=
The function generated by the lead-lag compensator for T,, dynamic compensation; S4 f Tr5 Time constants utilized In the lead-lag compensator for T., T4 = 25s, '5 = 3s; T
I
=
Average temperature, °F;
=
Lag compensator on measured T..; T = Os 6
r.
s 577.2 'F (Nominal T,, at RATED THERMAL POWER);
K3'
=
0.001/psig; P
=
Pressurizer pressure, psig;
I.
P.0 I
l TABLE 2.2-1 (Conlinued)
TABLE NOTATIONS (Continued)
NOTE 3:
1O\\ERPOWERAT
'6T S ~~ATo {K sTS(T f-a 2
T(o AI)
I+T2)
('1+ S
{
4 K1+ 7S 1+ T6S) T
+Tra)
Whbre:l AT As defined in Note 1, j
1+ I1S
=
As defined In Note 1, A1
=
As defined In Note 1, j
+.r3S lATO
=
As definedIn Note 1, I
II i
i I
K4 K5 I+r 7S T7, 1 +T6 s
1.10, 0.021°F for Increasing average temperature and 0 for decreasing average temperature,
=
The function generated by the lead-lag compensator for T. dynamic compensation;
= Time constants utilized In the lead-lag compensator for Tn, Tr7 t 10 S.
As defined In Note 1.
I
'.I-
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...................................................................
3/4 0-1 314.1 REACTIVITY CONTROL SYSTEMS 314.1.1 FIGURE 3.1-1 3/4.1.2 FIGURE 3.1-2 BORATION CONTROL Shutdown Margin - Tevg Greater Than 2000F................................................
REQUIRED SHUTDOWN MARGIN VERSUS REACTOR COOLANT BORON CONCENTRATION..............................................
Shutdown Margin - T.v, Less Than or Equal to 200OF...................................
Moderator Temperature Coefficient..............................................................
Minimum Temperature for Criticality.............................................................
BORATION SYSTEMS Flow Path - Shutdown................
Flow Paths - Operating.................................................................................
Charging Pumps - Operating........................................................................
Borated Water Source - Shutdown................................................................
Borated Water Sources - Operating..............................................................
BORIC ACID TANK MINIMUM VOLUME.............................................
3/4 1-1 3/4 1-3 314 14 314 1-5 3/4 1-7 3/4 1-8 3/4 1-9 3/4 1-11 314 1-12 3/4 1-14 3/4 1-14a I
3/4.1.3 TABLE 3.1-1 TABLE 4.1-1 MOVABLE CONTROL ASSEMBLIES Group Height................................................................................................
ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD............................
Position Indication Systems - Operating.......................................................
ROD POSITION INDICATOR SURVEILLANCE REQUIREMENTS.................
Position Indication System - Shutdown.........................................................
Rod Drop Time.............................................................................................
Shutdown Rod Insertion Limit.......................................................................
Control Rod Insertion Limits..........................................................................
3/41-17 3/4 1-19 314 1-20 3/4 1-22 3/4 1-23 3/4 1-24 3/4 1-25 3/4 1-26 TURKEY-POINT--UNITS 3&4.
_iv AMENDMENTNOS. 224 AND 219
This page Is Intentionally blank.
TURKEY-POINT-- UNITS3&4 314 1-16 AMENDMENT NOS. 224_ANID 219
MATERIAL PROPERTY BASIS LIMITING MATERIAL:
Intermediate/Lower Shell Circumferential Weld Seams (Ht. #71249)
LIMITING ART VALUES AT 32 EFPY:
114 T, 2620F 3/4 T, 2180F FPL 32 EFPY COOLDOWN CURVES I
7,4.
I 2m 175 6
a.
10 sm la)pm eQ Qm Ffrr 40 Da Ffrr 120 on F;RT-0 D% Fftr I.
7SE SW2 0
50 150IO 0 ~
2 A
tsdicated RCSTempetaftrt (De% F)
FIGURE 3.4-3 Turkey Point Units 3 and 4 Reactor Coolant System Cooldown Limitations (Cooldown Rate of 0, 20, 40, 60 and 1 00°Fthr) Applicable for 32 EFPY (Without Margins for Instrumentation Errors)
~~~~~~~~~.._,......
TURKEY POINT - UNITS 3A 4 314 4-32 AMENDMENT NOS. 224 AND 219
REACTOR COOLANT SYSTEM OVERPRESSURE MITIGATING SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 The high pressure safety injection flow paths to the Reactor Coolant System (RCS) shall be isolated, and al least one of the following Overpressure Mitigating Systems shall be OPERABLE:
- a.
Two power-operated relief valves (PORVs) with a lift setting of < 468 psig, or
- b.
The RCS depressurized with a RCS vent of greater than or equal to 2.20 square Inches.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~..............
APPLICABILITY MODES 4 (when the temperature of any RCS cold leg is less than or equal to 2750F);,5, and 6 with the reactor vessel head on.
ACTION:
- a.
With the high pressure safety injection flow paths to the RCS unisolated, restore isolation of these flow paths within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b.
With one PORV Inoperable in MODE 4 (when the temperature of any RCS cold leg Is less than or equal to 2750F), restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 2.20 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- c.
With one PORV inoperable In Modes 5 or 6 with the reactor vessel head on, either (1) restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and venting of the RCS through at least a 2.20 square Inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />, or (3) complete depressurization and venting of the RCS through at least one open PORV and associated block valve within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
- d.
With both PORVs inoperable, either restore one PORV to OPERABLE status or complete depressurization and venting of the RCS through at least a 2.20 square inch vent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- e.
In the event either the PORVs or a 2.20 square inch vent is used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances Initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence. A Special Report is not required when such a transient Is the result of water Injection into the RCS for test purposes with an open vent path.
- f.
The provisions of Specification 3.0.4 are not applicable.
TURKEY POINT - UNITS 3 & 4 3/4 4-36 AMENDMENT NOS. 224 AND 219
314.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be In at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and In COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANC;E REQUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:
- a.
At least once per 31 days by verifying that all penetrations' not capable of being closed by OPERABLE containment automatic Isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their closed positions; I
- b.
By verifying that each containment air lock Is in compliance with the requirements of Specification 3.6.1.3.
Exception may be taken under Administrative Controls for opening of valves and airlocks necessary to perform surveillance, testing requirements and/or corrective maintenance. In addition, Specification 3.6.4 shall be complied with.
Except valves' blind flanges, and deactivaied omtic-Valves-which-are-locatedinside the containment and are locked, sealed or-otherwise-secured in-the-closed-position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed moreoftietn oafince per 92 days.
TURKEY-POIN-UNITS 3&4 -.-
314 6-1 AMENDMENT NOS. 224 AND 219
PLANT SYSTEMS STANDBY FEEDWATER SYSTEM LIMIITING CONDITION FOR OPERATION 3.7.1.6 Two Standby Steam Generator Feedwater Pumps shall be OPERABLE* and at least 135,000 gallons of water (indicated volume), shall be In the Demineralized Water Storage Tank."
APPLICABILITY:
MODES 1, 2 and 3 ACTION:
- a.
With one Standby Steam Generator Feedwater Pump lnoperabler restore the inoperable pump -to available status within 30 days or submit a SPECIAL REPORT per 3.7.1.6d.
- b.
With both Standby Steam Generator Feedwater Pumps inoperable, restore at least one pump to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or:
- 1.
Notify the NRC within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and provide cause for the inoperability and plans to restore pump(s) to OPERABLE status and,
- 2.
Submit a SPECIAL REPORT per 3.7.1.6d.
- c.
With less than 135,000 gallons of water Indicated in the Demineralized Water Storage Tank restore the available volume to at least 135,000 gallons Indicated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or submit a SPECIAL REPORT per 3.7.1.6d.
- d.
If a SPECIAL REPORT is required per the above specifications submit a report describing the cause of the Inoperability, action taken and a schedule for restoration within 30 days In accordance with 6.9.2.
SURVEILLANCE BEQUIREMENTS 4.7.1.6.1 The Demineralized Water Storage tank water volume shall be determined to be within limits at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.7.1.6.2 At least monthly verify the standby feedwater pumps are OPERABLE by testing in recirculation on a STAGGERED TEST BASIS.
4.7.1.6.3 At least once per 18 months, verify operability of the respective standby steam generator feedwater pump by starting each pump and providing feedwater to the steam generators.
- These pumps do not require plant safety related emergency power sources for operability and the flowpath is normally isolated.
"The Demineralized Water Storage Tank Is non-safety grade.
TURKEY POINT - UNITS 3 & 4 3/4 7-1 1 AMENDMENT NOS. 224 AND 219
REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS LIMITING CONDITION FOR OPERATION 3.9.7 Loads In excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.
APPLICABILITY:
With fuel assemblies in the storage pool.
ACTION:
- a.
With the requirements of the above specification not satisfied, place the crane load in a safe condition.
- b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.7 Prior to crane operation over fuel assemblies in the spent fuel storage pool, verify that each load Is 2000 pounds or less.
.... -....1...
I TURKEY-POINT-UNITS-3 & 4 3
- 39.
.3-AMENDMENT NOS. 224 AND 21S
REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.11 The water level shall be maintained greater than or equal to elevation 56' - 10' the spent fuel storage pool.*
APPLICABILITY:
Whenever irradiated fuel assemblies are in the storage pool.
ACTION:
- a.
With the requirements of the above specification not satisfied, suspend all movement of fuel..
assemblies and crane operations with loads In the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b.
The provisions of Specification 3.0.3 are not applicable.
5URVELLAtCE REQUIREMENTS 4.9.11 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when Irradiated fuel assemblies are in the fuel storage pool.
- The requirements of this specification may be suspended for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hours to perform maintenance provided a 10 CFR 50.59 evaluation is prepared prior to suspension of the above requirement and all movement of fuel assemblies and crane operation with loads In the fuel storage areas are suspended. If the level is not restored within 7 days, the NRC shall be notified within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I
- -TURKEY POINT-UNITS 3 & 4-- ---*---
3/4 9-12_-_---.-.
-AMENDMENT NOS. 224 AND 219