ML17346A671
| ML17346A671 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/13/1984 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17346A672 | List: |
| References | |
| NUDOCS 8412260303 | |
| Download: ML17346A671 (14) | |
Text
AMENDMENT CORRECTIONS FACILITY ND DPR-41 Revise Appendix A as follows:
Remove Pa es i Amendment Nos.
110 and 104 iv Amendment Nos.
111 and 105 1-9 Amendment Nos.
108 and 102
- 3. 1-4 Amendment Nos.
110 and 104 Table 4.1-1 Sh 3 5 Sh 4
Amendment Nos.
110 and 104 Insert Pa es i Amendment Nos.
110 and 104 iv Amendment Nos.
111 and 105 1-9 Amendment Nos.
108 and 102
- 3. 1-4 Amendment Nos.
110 and 104 Table 4.1-1 Sh 3
& Sh 4
Amendment Nos.
110 and 104 B 2.3-3 Amendment Nos.
106 and 100 B 2.3-3 Amendment Nos.
106 and 100 8412250303 841213 PDR *DOCK 05000250 PDR
I
TABLEOF CONTENTS Section Title TECHNICAL SPECIFICATIONS
~Pa e
1.0 1.1 1.2 1.3 1.0 1.5 1.6 1.7 1.8 1.9 1.10 1.11 1.12 1.13 1.10 1.15 1.16 1.17 1.18 1.19 1.20 1.21 1.22 1.23 1.20 1.25 1.26 1.27 1.28 1.29
~+1.30 1~31 1.32 1.33 1.30 1.35 2.0 2.1 2.2 2.3 3.0 3.1 DEFINITIONS Safety Limits Limiting Safety System Settings Limiting Conditions for Operation Operable Containment Integrity Protective Instrumentation Logic Instrumentation Surveillance Shutdown Power Operation Refueling Operation Rated Power Thermal Power Design Power Dose Equivalent I-131 Power Tilt Interim Limits Low Power Physics Tests Engineered Safety Features Reactor Protection System Safety Related Systems and Components Per Annum Reactor Coolant System Pressure Boundary Integrity Coolant Loop E-Average Disintegration Energy Gas Decay Tank System Ventilation Exhaust Treatment System Process Control Program (PCP)
Offsite Dose Calculation Manual (ODCM)
Dose Equivalent I-131 Purge-Purging Venting Site Boundary Unrestricted Area Member(s) of the Public Heavy Loads SAFETY LIMITSAND LIMITINGSAFETY SYSTEM SETTINGS Safety Limit, Reactor Core Safety Limit, Reactor Coolant System Pressure Limiting Safety System Setting, Protective Instrumentation LIMITINGCONDITIONS FOR OPERATION Reactor Coolant System Operational Components Pressure-Temperature Limits Leakage Maximum Reactor Coolant Activity Reactor Coolant Chemistry DNB Parameters l-l l-l l-l 1-1 1-1 1-2 1-2 1-3 1-3 1-4 1-4 1-0 1-0 1-0 1-5 1-5 1-6 1-6 1-6 1-6 1-6 1-6 1-6 1-7 1-7 1-8 1-8 1-8 1-8 1-8 1-9 1-9 1-9 1-9 1-9 1-9 2.1-1 2.1-1 2.2-1 2.3-1 3.0-1 3.1-1 3.1-1 3.1-2 3.1-3 3.1-0 3.1-6 3.1-7 Amendment Nos.
~~~ and
~~<
t1
Section TABLEOF CONTENTS (Continued)
Title
~Pa e B3.5 B3. 6 B3.7 B3.8 B3.9 B3.10 B3.11 B3.12 B3.13 B3.14 B3.15 B3.17 B0.1 B0.2 B0.3 B0.0 B0.5 B0.6 B0.7 B0.8 B0.9 B0.10 B0.11 B0.12 B0.13 B0.10 B0.15 B0.18 B0.19 Bases for Limiting Conditions for Operation, Instrumentation Bases for LimitingConditions for Operation, Chemical and Volume Control System Bases for LimitingConditions for Operation, Electrical Systems Bases for LimitingConditions for Operation, Steam and Power Conversion Systems Bases for LimitingConditions for Operation, Radioactive Vaterials Release Bases for Limiting Conditions for Operation, Refueling Bases for Limiting Conditions for Operation, Miscellaneous Radioactive Material Sources Bases for Limiting Conditions for Operation, Cask Handling Bases for Limiting Conditions for Operation, Snubbers Bases for Fire Protection System Bases for LimitingConditions of Operation, Overpressure
%titigating System Bases for LimitingConditions for Operation, Spent Fuel Storage Bases for Operational Safety Review ~
Bases for Reactor Coolant System In-Service Inspection Bases for Reactor Coolant System Integrity Bases for Containment Tests Bases for Safety Injection Tests Bases for Emergency Containment Cooling System Tests Bases for Emergency Containment Filtering and
'ost Accident Containment Venting Systems Tests Bases for Emergency Power System Periodic Tests Bases for Main Steam Isolation Valve Tests Bases for AuxiliaryFeedwater System Tests Bases for Reactivity Anomalies Bases for Environmental Radiation Survey Bases for Fire Protection Systems Bases for Snubbers Bases for Surveillance Requirements, Overpressure
%litigating System Bases for System Flow Path Verifications Bases for Reactor Coolant Vent System B3.5-1 B3.6-1 B3.7-1 B3.8-1 B3.9-1 B3.10-1 B3.11-1 B3.12-1 B3.13-1 B3.10-1 B3.15-1 B3.17-1 B0.1-1 B0.2-1 B0.3-1 B0.0-1 B0.5-1 B0.6-1 B0.7-1 B0.8-4.
B0.9-1 B0.10-1 B0.11-1 B0.12-1 B0.13-1 B0.10-1 B0.15-1 B0.18-1 B0.19-1 iv 111 105 Amendment Nos.
and
0 E
1.30 PURGE - PURGING PURGE or PURGING 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 required to purify the confinement.
1.31 VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain tern perature,
- pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. V'ent, used in system names, does not imply a VENTING process.
1.32 SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither
- owned, leased nor otherwise controlled by the licensee.
1.33 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation from radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional and/or recreational purposes.
1.3'EMBER(Q OF THE PUBLIC 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 licensee, its contractors, vendors or members of the Armed Forces using property located within the SITE BOUNDARY.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This ategory does include persons who use portions of the site for recreational, occupational or other purposes, not associated with the plant.
1.35 HEAVYLOADS Any load in excess of the nominal weight of a fuel and control rod assembly and associated handling tool.
For the purpose of this specification, HEAVY LOADS will be defined as loads in excess of 2000 pounds.
1-9 Amendment Nos 108and 102
e.
After shutdown, corrective action shall be taken before operation is resumed.
f.
hbove 2X of rated pover, tvo leak detection systems of different principles shall be operable, one of vhicb is sensitive to radioactivity.
The latter aay be out of service for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided l)
Tvo other systems are operable and 2) containment purge valves are maintained closed.
g.
Reactor Coolant System leakage shall be limited to 1 gpm total primary-to-secondary leakage through all steam generators not isolated from the Reactor Coolant System and 500 gallons per day through any one steam generator not isolated from the Reactor Coolant System.
0.
MAXIMUMREACTOR COOLANT ACTIVITY The specific activity of the primary coolant shall be limited to:
~
Less than or equal to I.b microcurie per gram DOSE EQUIVALENT1-131, and b.
Less than or equal to 100/E microcuries per gram.
With the above limits being exceeded, the following actions shall he taken:
1.
When the reactor is critical or average reactor coolant temperature is reater than 500 F:
a.
With the specific activity of the primary coolant greater than 1.0 microcurie per gram DOSE EQUIVALENTI-131 but within the allowable Bmit (below and to the left of the line) shown on Figure 3.1-1, operation may continue for up to 08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />'rovided that the cumulative operating time under these circumstances does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 month period.
With the total cumulative operating time at a primary coolant specific activity greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 exceeding 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in 3.1-0 Amendment Nos.. )10 and 104
23.
Logic Channels 24.
Emer. Portable Survey instruments 25.
Seismograph Cbeck N.h.
N.h.
~Caiibra a N.A.
~T Mt
~Rm~+
Make trace.
Test battery (change semiannually) 26.
Auxiliary Feedwater Plow Rate 27.
RCS Subcooling Margin Monitor 2L PORV Position indicator (Prifnary Detector) 29.
PORV Block Valve Position indicator 30.
Safety Valve Position indicator 3l.
a.
Loss of Voltage (both 4kv bussess) b.
Undervoltage (both 4KV busses and 480 volt Load Centers)>>
Mt Mt Mt Mt N.h.
St N.A.
N.h.
Mt Check consists of monitoring indicated position and verifying by observation of related parameters.
For hFW actuation at power only 32.
Trip of both h4in Feedwater Pump Breakers N.A.
N.A.
For AFW actuation at power only 33.
Turbine Trip (huto-Stop Oil Pressure Switches)
N.h.
R.
N.h.
~
This itefn docs not apply on Unit 3 until atter implementation of PC/M 79-I lb and on Unit 4 until after implementation of PC/M 80-44.
TlSA Amendment Nos 110 qd 104
TABLEO.l-l SHEET 0 Charnel Descri tion Calibrate Remarks 34.
Containment Water Level (Narrow Range)
Containment Water Level (Wide Range)
Containment High Range Area Radiation 37.
Containment Hydrogen Monitors 38.
High Range Noble Gas Effluent Monitors a.
Plant Vent Exhaust
- b. Unit 3 Spent Fuel Pit Exhaust c.
Condenser Air Ejectors d.
Main Steam Lines Sf R(Note 1)
N.A.
(1) Channel calibration using sample gas containing:
a.
One volume percent hydrogen, balance nitrogen.
b.
Four volume percent hydrogen, balance nitrogen.
39.
Incore Thermocouples
N.A.(See Note 2)
Amendment Nos 1 1 0 ad 1 04
Reactor Tri Interlocks Spec1fied reactor trips are by passed at low power where they are not required for protection and would otherwise interfere with normal.opera-tion.
The prescr1bed set points above which these trips are made func-tional assures the1r availability in the power range where needed.
An automatic reactor tr1p will occur if any pump is lost above 55% power which will prevent the minimum value of the DHBR from going below the applicable design limit dur1ng normal and anticipated trans1ent operat1ons when only two loops are 1n serv1ce, and the (9) overtemperature hT tr1p setpoint is adjusted to the value specified for three loop operation.
A turbine trip initiates a reactor trip.
On decreasing
- power, the turbine trip is automatically blocked by P-7; and on increasing poMer reinstared automatically by P-7.
Reset of reactor trip interlocks will be done under strict administra-tive control.
References (1)
FSAR 14.1.1 (2)
FSAR 14.1.2 (3)
FSAR 14.1 (4)
FSAR 7.2, 7.3 (5)
FSAR 3.2.1 (6)
FSAR 14.3.1 (7)
FSAR 14 (page 14"3 and 14.1.9)
(8)
FSAR 14.1.11 (9)
FSAR 14.1.9 (10) %CAP-8074 B2. 3-3 Amendment Nos.
106 and 100
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I e