ML20076G841
| ML20076G841 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/09/1983 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20076G814 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM NUDOCS 8306160266 | |
| Download: ML20076G841 (11) | |
Text
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.2 SAFETY VALVES - SHUTDOWN................................
3/4 4-6 3/4.4.3 SAFETY VALVES - OPERATING............................... 3/4 4-7 SAFETY and RELIEF VALVES - OPERATING Safety Valves........................................... 3/4 4-7 Relief Valves........................................... 3/4 4-7a 3/4.4.4 PRESSURIZER............................................. 3/4 4-8 3/4.4.5 STEAM GENERATORS........................................ 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................... 3/4 4-16 Operational Leakage..................................... 3/4 4-17 3 /4. 4. '7 CHEMISTRY............................................... 3/4 4-19 3/4.4.8 SPECIFIC ACTIVITY....................................... 3/4 4-22 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.................................. 3/4 4-29 Pressuri:er.............................................
3/4 4-30 Overpressure Protection Systems.........................
3/4 4,-31 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components...................
3/4 4-33 Steam Generator Supports................................
3/4 4-35 3/4.4.11 REACTOR VESSEL iiEAD VENT.................................
3/4 4-36 l
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i 3/4.5.1 ACCUMULATORS............................................ 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T, g 350*F.......................... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T, g 350*F.......................... 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank....................................
3/4 5-7 Heat Tracing............................................ 3/4 5-8 3/4.5.5 REFUELING WATER STORAGE TANK............................ 3/4 5-9 r
8306160266 830609 PDR ADOCK 05000338 P
pm NORTH ANNA - UNIT 1 V
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INDEX BASES SECTION PAGE 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 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS.................................... B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES................................. B 3/4 4-2 3/4.4.4 PRESSURIZER.............................................. B 3/4 4-2 3/4.4.5 STEAM GENERATORS......................................... B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE........................... B 3/4 4-4 3/4.4.7 CH EMI S T RY................................................ B 3 /4 4 -5 3/4.4.8 SPECIFIC ACTIVITY........................................ B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS.............................. B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY..................................... B 3/4 4-11 3/4.4.11 REACTOR VESSEL HEAD VENT.................................. B 3 /4 4-13 NORTH ANNA - UNIT 1 XII J
REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENT LIMITING CONDITION FOR OPERATION 3.4.11.1 At least two Reactor Vessel Head Vent (RVHV) paths consisting of two isolation valves powered from emergency buses shall be OPERABLE and closed.
Applicability: Modes 1, 2 and 3.
ACTION:
a.
With one of the above RVHV paths inoperable, startup and/or power operation may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of both isolation valves in the inoperable vent path, b.
With two RVHV paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all the isolation valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 30 days or be in HOT STANDBY within 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 />, c.
If any RVHV isolation valve cannot be verified to be closed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in HOT STANDBY within 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 />.
SURVEILLANCE REQUIREMENTS 4.4.11.1 Each RVHV path isolation valve not required to be closed above shall be demonstrated OPERABLE by:
a.
Exercising each remotely controlled valve through one cycle from the control room pursuant to Specification 4.0.5.
4.4.11.2 Each RVHV path shall be demonstrated OPERABLE following each refueling by:
a.
Verifying that the upstream manual isolation valve is locked in the opened position.
b.
Verifying flow thcough the RVHV paths during system venting.
l NORTH ANNA - UNIT 1 3/4 4-36
REACTOR COOLANT SYSTEM BASES 3/4.4.11 REACTOR VESSEL HEAD VENT The accumulation of non-condensable gases in the Reactor Coolant System may result from sudden system depressurization, accumulator discharges and/or inadequate core cooling conditions.
The function of the Reactor Vessel Head Vent (RVHV) is to remove non-condensable gases from the reactor vessel head.
The RVHV is designed with redundant safety grade vent paths.
Venting of non-condensable gases from the pressurizer steam space is provided primarily through the Pressurizer PORV's.
The pressurizer is,
- however, equipped with a steam space vent designed wit: redundant safety grade vent paths.
NORTH ANNA - UNIT 1 B 3/4 4-13
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTICN PAGE 3/4.4.2 SAFETY VALVES - SHUTDOWN................................ 3/4 4-6
.3/4.4.3 SAFETY VALVES - OPERATING............................... 3/4 4-7 SAFETY and RELIEF VALVES - OPERATING Safety Valves........................................... 3/4 4-7 Relief Valves........................................... 3/4 4-7a 3/4.4.4 PRESSURIZER............................................. 3/4 4-8 3/4.4.5 STEAM GENERATORS........................................ 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................... 3/4 4-16 Operational Leakage..................................... 3/4 4-17 3/4.4.7 CHEMISTRY............................................... 3/4 4-19 3/4.4.8 SPECIFIC ACTIVITY....................................... 3/4 4-22 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.................................. 3/4 4-29 Pressurizer............................................. 3/4 4-30 Overpressure Protection Systems......................... 3/4 4-31 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components................... 3/4 4-32 Steam Generator Supports................................ 3/4 4-33 3/4.4.11 REACTOR VESSEL HEAD VENT................................ 3/4 4-34 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS............................................ 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T, 350*F.......................... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg 350*F.......................... 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM Boron Inj e c tion Tank.................................... 3/4 5-8 l
Heat Tracing............................................ 3/4 5-9 3/4.5.5 REFUELING WATER STORAGE TANK............................ 3/4 5-10 i
NORTH ANNA - UNIT 2 V
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INDEX BASES SECTION PAGE
~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 3-1 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS.................................... B 3 /4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES................................. B 3/4 4-2 3 /4. 4.4 PRESSURIZER.............................................. B 3/4 4-2 3/4.4.5 STEAM GENERATORS......................................... B 3/4 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAY.CE........................... B 3/4 4-4 3/4.4.7 CH EM I STRY............................................... B 3 / 4 4 -5 3/4.4.8 SPECIFIC ACTIVITY........................................ B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS.............................. B 3/4 4-6 3 /4.4.10 STRUCTURAL INTEGRITY..................................... B 3 /4 4-16 3/4.4.11 REACTOR VESSEL HEAD VENT.................................. B 3/4 4-17 l NORTH ANNA - UNIT 2 XI j
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REACTOR COOLANT SYSTEM 3/4.4.11 REACTOR VESSEL HEAD VENT LIMITING CONDITION FOR OPERATION 3.4.11.1 At least two Reactor Vessel Head Vent (RVHV) paths consisting of two isolation valves powered from emergency buses shall be OPERABLE and closed.
Applicability: Modes 1, 2 and 3.
ACTION:
a.
With one of the above RVHV paths inoperable, startup and/or power operation may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of both isolation valves in the inoperable vent path.
b.
With two RVHV paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all the isolation valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 30 days or be in HOT STANDBY within 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 />.
c.
If any RVHV isolation valve cannot be verified to be closed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in HOT STANDBY within 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 />.
SURVEILLANCE REQUIREMENTS 4.4.11.1 Each RVHV path isolation valve not required to be closed above shall be demonstrated OPERABLE by:
a.
Exercising each remotely controlled valve through one cycle from the control room pursuant to Specification 4.0.5.
4.4.11.2 Each RVHV path shall be demonstrated OPERABLE following each refueling by:
a.
Verifying that the upstream manual isolation valve is locked in the opened position.
b.
Verifying flow through the RVHV paths during system venting.
NORTH ANNA - UNIT 2 3/4 4-34 J
REACTOR COOLANT SYSTEM BASES 3/4.10.2 STEAM CENERATOR SUPPORTS For the A572 material, operation above 225' provides a conservative temperature limit and thus toughness level in the steel.
This assures the safety of the A572 material even under the worst postulated accident conditions.
The points to be monitored were determined during hot functional testing, which indicated the top level corner lags the middle level corner during heatup; however, once the material achieved 225'F the top level corner exceeded the temperature of the middle level corner.
The latter thus becomes the controlling zone during operation.
For the monitored top level corner of the steam generator supports, operation below 355'F provides assurance that no other region of the supports will exceed this temperature.
The monitored top _ level corner is the highest temperature region in the supports. With the temperature of the supports less than 355*F all materials will be within allowable stress limits even, under the worst postulated accident condition.
3/4.4.11 REACTOR VESSEL HEAD VENT The accumulation of non-condensable gases in the Reactor Coolant System may result from sudden system depressurization, accumulator discharges and/or inadequate core cooling conditions.
The function of the Reactor Vessel Head Vent (RVHV) is to remove non-condensable gases from the reactor vessel head.
The RVHV is designed with redundant safety grade vent paths.
Venting of non-condensable gases from the pressurizer steam space is provided primarily through the Pressurizer PORV's.
The pressurizer is,
- however, equipped with a steam space vent designed with redundant safety grade vent paths.
NORTH ANNA - UNIT 2 B 3/4 4-17
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ATTACINENT 2 i
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DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE NUREG-0737, Item II.B.1, required the installation of the Reactor Vessel Head Vent (RVHV) whose function is to remove non-condensable gases from the reactor vessel head.
The Reactor Vessel Head Vent is designed with redundant safety grade vent paths.
'The_ Reactor Vessel Head Vent System will extend the reactor coolant pressure boundary to and including the 3/8 in, orifices in the Reactor Vessel Head Vent.
The system is designed, fabricated, and installed in accordance with the requirements of FSAR Section 5, and all applicable codes, as part of the Reactor Coolant System.
Loss of reactor coolant resulting from vent failure is categorized as being a loss of coolant accident which is fully bounded by previous evaluations, while a failure downstream of the 3/8 in. orifices is within the capacity of the normal reactor coolant makeup system.
System design provides for manual initiation or termination of venting effective with the single failure criteria.
This proposed change does not involve a significant hazards consideration.
This system does not increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety and previously evaluated in the Safety' Analysis Report, nor does it create the possibility of an accident or malfunction of a different type than any previously evaluated in the Safety Analysis Report.
The margin of safety as defined in the basis for any technical specification is not reduced, and this system does not lessen any other system's ability to perform its design function.
M7/006
COMMONWEALTH OF VIRGINIA )
)
CITY OF RICHMOND
)
The foregoing document was acknowledged before me, in and for the City and Consnonwealth aforesaid, today by W.
R.
Cartwright who is Manager-Nuclear Operations Support, of the Virginia Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
7/.,
Acknowledged before me this 9
day of th
,1923 f
My Commission expires:
A-A4
, 19 &[
l us 0. W 'b Notary Public l
(SEAL)
S/001
.