ML20141F386
| ML20141F386 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-043, NPF-10-A-43, NPF-15-A-032, NPF-15-A-32) |
| Issue date: | 03/27/1986 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141F391 | List: |
| References | |
| TAC-59883, TAC-59884, NUDOCS 8604230008 | |
| Download: ML20141F386 (36) | |
Text
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UNITED STATES y
NUCLEAR REGULATORY COMMISSION
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated October 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and se.curity or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.43, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This amendment is effective immediately and is to be fully implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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M c h"~ cf L
George W Knighton,' Director PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27, 1986
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O March 27, 1986 3-ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 1
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contains vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page 3/4 1-6 3/4 1-5 3/4 1-7 3/4 1-8 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-14a 3/4 5-1 3/4 5-2 3/4 5-8 3/4 5-7 B 3/4 1-2 B 3/4 1-1 4
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e REACTIVITY CONTE 0L SYSTEMS MIN!%M TEMPERAT:.1E FOR CRITICALIT(
LIMIil!.C-CCNDITI^N FCR CPERATION 3.1.1.4 The Reacter Ccolant System icwest cperating icco tem erature (T "C) shall be greater than er equal to 520 F.
A?PLICAEILITY:
MCDES I and 2#.
ACTION:
With a Reactor Ccolant System operating loop temperature (T,'9e) less than to within its.i it within 15 minutes o'?
in NOT STANDEY 520 F, restcre T n
witnin the next iE9 minutes'.
SURVEILLANCE RECUIREMENTS 4.1.1.4 The Reactor Coolant Svstem temperature (T^*9) shall be determined to be greater than or equal to 52'O F:
i a.
Within 15 minutes prior to achieving, reactor criticality, and b.
At least once per 20 minutes when the reactor is critical and the Reacter Ccolant System T is less than 535*F.
asg HWith Kgff greater than or equal to 1.0.
SAN ONOFRE-UtJIT 2 1/4 1-5 AMENDMENT NO.
16
e REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.
a.
A flow path from either bori~c acid makeup tank via either one of the boric acid makeup pumps, the blending tee or the gravity feed connection and any charging pump to the Reactor Coolant System if the boric acid makeup tank in Specification 3.1.2.7.a is OPERABLE, or b.
The flow path from the refueling water tank via either a charging pump or a high pressure safety injection pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.7.b is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
Intentionally deleted, b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
SAN ONOFRE-UNIT 2 3/4 1-6 AMENDMENT N0. 43
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REACTIVITY. CONTROL SYSTEMS FLOW PATHS - OPERATING i
LIMITING CONDITION FOR~0PERATION 3.1.2.2 The following boron injection flow paths to the RCS via the charging pumps (s) shall be OPERABLE:
a.
At least one of the following combinations:
1)
One boric acid makeup tank, with the tank contents in accordance with Figure 3.1-1, its associated gravity feed valve, and boric 1
acid makeup pump.
2)
Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, their associated gravity feed valves, and boric acid makeup pumps, 3)
Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at least one boric acid makeup pump, and b.
The flow path from the refueling water storage tank.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With fewer than the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore the required boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTOOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the required flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:
a.
. Intentionally deleted.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
At least once per 18 months during shutdown by verifying that each c.
automatic valve in the flow path actuates to its correct position on a SIAS test signal.
SAN ON0FRE-UNIT 2 3/4 1-7 AMENDMEN1 NO.43 1
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REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or one high pressure safety injection pump in the. boron injection flow path required GPERABLE pursuant to Specifica-tion 3.1.2.1 shall be OPERABLE and capab1.e of being powered from an OPERABLE emergency power source.
l APPLICABILITY: MODES 5 and 6.
ACTION:
l With no charging pump or high pressure saf.ety injection pump OPERABLE or capable of being powered from an OPERABLE hmergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
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SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
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SAN ONOFRE-UNIT 2 3/4 1-8 l
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t REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION TOR OPERATION 3.1.2.6 The boric acid makeup pump (s) in the boron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the boric acid makeup pump (s) required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup pump (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F; restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0.5.
4 SAN ONOFRE-UNIT 2 3/4 1-11 AMENDMENT NO. 43
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
a.
One boric acid makeup tank with a minimum boron concentration of 1720 ppm and a minimum borated water volume of 5150 gallons, or b.
The refueling water storage tanks with:
1.
A minimum borated water volume of 5150 gallons above the ECCS suction connection, 2.
A minimum boron concentration of 1720 ppm, and 3.
A solution temperature between 40 F and 100 F.
' APPLICABILITY:
MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration of the water, and 2.
Verifying the contained borated water volume of the tank.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water when the outside air temperature is less than 40 F or greater than 100 F.
SAN ON0FRE-UNIT 2 3/4 1-12 AMENDMENT N0. 43
t Figure 3.l-l REQUIRED STORED BORIC ACID VOLUME A8 A FUNCTION OF CONCENTRATION 14000 13000- -
REGION OF ACCEPTABLE OPERATION
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12000-11000-b RWST at 1720 ppm-o RWST at 2000 ppm o 10000-RWCT at 2300 ppm i
9000-N< N'N N a
RWST at 2500 ppm s
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8000-7000- -
i-REGION OF UNACCEPTABLE -
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OPERATION l
l a000 2.28 2.80 2.78 3
3.28 3.80 (3. es4)
(4, 377)
(4.s07)
(s. 248)
(s, esa)
(s. tie)
BORIC ACID CONCENTRATION, WT % (ppm)
SAN ON0FRE-UNIT 2 3/4 1-13 AMENDMENT NO. 43
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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 The following borated water sources shall be OPERA 8LE:
At least one of the following combinations:
a.
1)
One boric acid makeup tank, with the tank contents in accor-dance with Figure 3.1-1, its associated gravity feed valve, 4
and boric acid makeup pump, 2)
Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, their associated gravity feed valves, and boric acid makeup pumps, 3)
Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at 4
least one boric acid makeup pump and, b.
The refueling water storage tank with:
1.
A minimum contained borated water volume of 362,800 gallons above the ECCS suction connection, 2.
Between 1720 and 2500 ppm of boron, and 3.
A solution temperature between 40 F and 100 F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the above required boric acid makeup tank (s) inoperable, restore a.
the tank (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within thi next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTOOWN MARGIN equivalent to at least 3.0% delta k/k at 200 C; restore the above required boric acid makeup tank (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the refueling water tank inoperable, restore the tank to OPERABLE status within one hour 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 SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water sources shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
SAN ONOFRE-UNIT 2 3/4 1-14 AMENDMENT N0. 43
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying the baron concentration in the water, and 2.
Verifying the contained borated water volume of the water source.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40 F or greater than 100 F.
SAN ONOFRE-UNIT 2 3/4 1-14a AMENDMENT NO. 43
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3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
a.
The isolation valve open and power to the valve removed, b.
A contained borated water volume of between 1680 and 1807 cubic
- feet, c.
Between 1720 and 2500 ppm of boron, and d.
A nitrogen cover pressure of between 600 and 625 psig.
APPLICABILITY:
MODES 1, 2 and 3.*
ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying that the contained borated water-volume and nitrogen cover pressure in the tanks is within the above limits, and 2.
Verifying that each safety injection tank isolation valve is open.
With pressurizer pressure greater than or equal to 715 psia.
SAN ON0FRE-UNIT 2 3/4 5-1 AMENDMENT NO. 43
EMERGENCY CORE COOLING SYSTEMS t
SURVEILLANCE REQUIREMENTS (Continued) 1 b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injectior, tank solution.
c.
At least once per 31 days by verifying the fuses removed from each safety injection tank vent valve.
d.
At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position, At least once per 18 months by verifying that each safety injection e.
tank isolation valve opens automatically under each of the following conditions:
1.
Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.
Upon receipt of an SIAS test signal.
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t SAN ONOFRE-UNIT 2 3/4 5-2
i EMkRGENCYCORECOOLINGSYSTEMS
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3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350*F avg LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
One OPERABLE high pressure safety injection pump, and a.
b.
An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
j APPLICABILITY:
MODES 3* and 4.
ACTION:
With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem a.
to OPERABLE status 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 COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
I b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days l
describing the circumstances of the actuation and the total
(
accumulated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
SURVEILLANCE REQUIREMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
With pressurizer pressure less than 400 psia.
e SAN ONOFRE-UNIT 2 3/4 5-7
f EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank shall be OPERABLE with:
a.
A minimum borated water volume of 362,800 gallons above the ECCS suction connection, b.
Between 1720 and 2500 ppm of boron, and c.
A solution temperature between 40*F and 100 F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the refueling water storage tank inoperable, restore the tank to OPERABLE status 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 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 REfy IREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the contained borated water volume in the tank, and 2.
Verifying the boron concentration of the water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40 F or greater than 100*F.
SAN ONOFRE-UNIT 2 3/4 5-8 AMENDMENT NO. 43
e 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN I
A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made l
I subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident ;onditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently l
subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout Core life as a function of j
fuel depletion, RCS boron concentration, and RCS T,yg.
The most restrictive condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 5.15% delta k/k is required to control the reactivity transient.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T,yg less than or equal to 200*F, the reactivity transients resulting from any l
postulated accident are minimal and a 3.0% delta k/k shutdown margin provides adequate protection.
l 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coef-ficient will be maintained within acceptable values throughout each fuel cycle.
SAN ONOFRE-UNIT 2 8 3/4 1-1 AMENDMENT NO. 28
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 520*F.
This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT temperature.
NDT 3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include 1) borated water sources, 2) charging pumps,
- 3) separate flow paths, 4) boric acid makeup pumps, and 5) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable.
Allowable out-of service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 3.0% delta k/k after xenon decay and cooldown to 200 F.
The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and volumes of Specification 3.1.2.8 plus approximately 13,000 gal-lons of 1720 ppm borated water from the refueling water tank or approximately 45,000 gallons of 1720 ppm borated water from the refueling water tank alone.
However, for the purpose of consistency the minimum required volume of 362,800 gallons above ECCS suction connection in Specification 3.1.2.8 is identical to the more restrictive value of Specification 3.5.4.
With the RCS temperature below 200 F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.
The boron capability required below 200 F is based upon providing a 1
3% delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200 F to 140 F.
This condition requires 5150 gallons of 1720 ppm borated water from either the refueling water tank or boric acid solution from a boric acid makeup tank.
SAN ONOFRE-UNIT 2 8 3/4 1-2 AMEN 0 MENT N0. 43 l
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'o UNITED STATES
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WASHINGTON, D. C. 20555
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees) dated October 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted witbout endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 32, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective on initial entry into the applicable MODE of I
Cycle 3 with the following exception:
Page 3/4 5-1 is effective immediately and is to be fully implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION z/(f L F
\\
/
Georg
- Knighton, irector
{
PWR Project Direct' orate No. 7
{
Division of PWR Licensing-B
Attachment:
Changes to the fachnical Specifications Date of Issuance:
March 27, 1986 l
l
March 27, 1986
' i ATTACHMENT TO LICENSE AMENDMENT N0. 32 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced is the following overleaf page to the amended page.
Amendment Page Overleaf Page 3/4 1-6 3/4 1-5 3/4 1-7 3/4 1-8 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-14a 3/4 1-15 3/4 1-16 3/4 5-1 3/4 5-2 3/4 5-8 3/4 5-7 8 3/4 1-2 B 3/4 1-1
REACTIVITY CONTROL SYSTEMS
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MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (Tavg) shall be greater than or equal to 520 F.
APPLICABILITY:
MODES 1 and 2#.
ACTION:
With a Reactor Coolant System operating loop temperature (T 520*F, restore T to within its limit within 15 minutes o@V8e) less than in HOT STANDBY within the next 759 minutes.
SURVEILLANCE REQUIREMENTS 4.1.1.4 The Reactor Coolant System temperature (Tavg) shall be determined to i
be greater than or equal to 520 F:
Within 15 minutes prior to achieving reactor criticality, and a.
b.
At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T is less than 535 F.
avg
- With Kef f greater than or equal to 1.0.
SAN ON0FRE-UNIT 3 3/4 1-5
REACTIVITY CONTROL SYSTEMS 3/4.1.2 80 RATION SYSTEMS FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the foll,owing boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.
A flow path from either boric acid makeup tank via either one of the a.
boric acid makeup pumps, the blending tee or the gravity feed connection and any charging pump to the Reactor Coolant System if the boric acid makeup tank in Specification 3.1.2.7.a is OPERABLE, or b.
The flow path from the refueling water tank via either a charging pump or a high pressure safety injection pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.7.b is OPERABLE.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
Intentionally deleted b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct-position.
SAN ON0FRE-UNIT 3 3/4 1-6 AMENDMENT N0, 32
REACTIVITY CONTROL SYSTEMS
_ FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 The following boron injection flowpaths to the RCS via the charging pump (s) shall be OPERABLE:
a.
At least one of the following combinations:
1)
One boric acid makeup tank, with the tank contents in accordance with Figure 3.1-1, its associated gravity feed valve, and boric acid makeup pump.
2)
Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, their associated gravity feed valves, and boric acid makeup pumps, 3)
Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at least one boric acid makeup pump, and b.
The ficw path from the refueling water storage tank.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With fewer than the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore the required boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the required flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:
a.
Intentionally deleted.
b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a SIAS test signal.
SAN ON0FRE-UNIT 3 3/4 1-7 AMENDMENT NO. 32
REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDI110N FOR OPERATION 3.1.2.3 At least one charging pump or one high pressure safety injection pump in the boron injection flow path required OPERABLE pursuant to Specifica-tion 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no charging pump or high pressure safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.
SAN ONOFRE-UNIT 3 3/4 1-8
REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING COND: TION FOR OPERATION 3.1.2.6 The boric acid makeup pump (s) in the baron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the boric acid makeup pump (s) required for the boron injection flow path (s) l pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup pump (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within l
the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F; restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0.5.
SAN ONOFRE-UNIT 3 3/4 1-11 AMENDMENT N0. 32
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
One boric acid makeup tank with a minimum boron concentration of 1720 a.
ppm and a minimum borated water volume of 5150 gallons, or b.
The refueling water storage tanks with:
1.
A minimum borated water volume of 5150 gallons above the ECCS l
suction connection, 2.
A minimum boron concentration of 1720 ppm, and l
3.
A solution temperature between 40 F and 100 F.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration of the water, and 2.
Verifying the contained borated water volume of the tank.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water when the outside air temperature is less than 40 F or greater than 100 F.
SAN ON0FRE-UNIT 3 3/4 1-12 AMENDMENT N0. 32
Figure 3. l-I i
REQUIRED STORED BORIC ACID VOLUME AS 'A FUNCTION OF CONCENTRATION 14000 l
13000-
+
REGION OF ACCEPTABLE OPERATION
..i..
. j..
12000-
_ 11o oo -
RWST at 1720 ppm-Q RWST at 2000 ppm o
e toooo-RWST at 2300 ppm RWST at 2500 ppm g
O soo0-b" CD 8000-
.i.
.. i...
..i..
7aoo-REGION OF UNACCEPTABLE OPERATION s
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5000 2.25 2.50 2.IS 3
3.55 3.80 (a,ss4)
(4, 377)
(4 so7)
(s. 24s)
(s, set)
(s.11s)
BORIC ACID CONCENTRATION, WT % (ppm)
SAN ONCFRE-UNIT 3 3/4 1-13 AMENDMENT NO. 32
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 The following borated water sources shall be OPERABLE:
At least one of the following combinations:
{
a.
1)
One boric acid makeup tank, with the tank contents in accordance with Figure 3.1-1, its associated gravity feed valve, and boric acid makeup pump, 2)
Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, their associated gravity feed valves, and boric acid makeup pumps, 3)
Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at least one.
boric acid makeup pump and, b.
The refueling water storage tank with:
1.
A minimum contained borated water volume of 362,800 gallons above the ECCS suction connection, 2.
Between 1720 and 2500 ppm of boron, and 3.
A solution temperature between 40 F and 100 F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
~
ACTION:
With the above required boric acid makeup tank inoperable, restore a.
the tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least H0T 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 borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F; restore the above required boric acid makeup tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the refueling water tank inoperable, restore the tank to OPERABLE status 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 />.
SURVEILLANCE REQUIREMENTS 4.1. 2. 8; Each borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration in the water, 2.
Verifying the contained borated water volume of the water
- source, SAN ONOFRE-UNIT 3 3/4 1-14 AMENDMENT NO. 32
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING SURVEILLANCE REQUIREMENTS (continued) b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40 F or greater than 100 F.
SAN ON0FRE-UNIT 3 3/4 1-14a AMENDMENT NO. 32
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
a.
The isolation valve open and power to the valve removed, b.
A contained borated water volume of between 1680 and 1807 cubic
- feet, c.
Between 1720 (1420 for Cycle 2) and 2500 ppm of boron, and d.
A nitrogen cover pressure of between 600 and 625 psig.
APPLICABILITY:
MODES 1, 2 and 3.*
ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour 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 H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying that the contained borated water volume and nitrogen cover pressure in the tanks is within the above limits, and 2.
Verifying that each safety ~ injection tank isolation valve is open.
- With pressurizer pressure greater than or equal to 715 psia.
SAN ON0FRE - UNIT 3 3/4 5-1 AMENDMENT N0. 32
EMERGENCY CORE COOLING SYSTEMS
(
SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 31 days and withia 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution.
volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injection tank solution.
c.
At least once per 31 days by verifying the fuses removed from each safety injection tank vent valve.
d.
At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position.
At least once per 18 months by verifying that each safety injection e.
tank isolation val've opens automatically under each of the following conditions:
1.
Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.
Upon receipt of an SIAS test signal.
(
l.
SAN ON0FRE-UNIT 3 3/4 5-2
ENERGENC CORE COOLING SYSTEMS
(
3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350 F avg LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
One OPERABLE high pressure safety injection pump, and b.
An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.
APPLICABILITY:
MODES 3* and 4.
ACTION:
With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem a.
to OPERABLE status 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 COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor
(
Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
SURVEILLANCE REQUIREMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
With pressurizer pressure less than 400 psia.
I SAN ONOFRE-UNIT 3 3/4 5-7
EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank shall be OPERABLE with:
a.
A minimum borated water volume of 362,'800 gallons above the ECCS suction connection, b.
Between 1720 and 2500 ppm of boron, and c.
A solution temperature between 40*F and 100 F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the refueling water storage tank inoperable, restore the tank to OPERABLE statur 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 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTD')WN 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 4.5.4 The RWST shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the contained borated water volume in the tank, and 2.
Verifying the boron concentration of the water.
i b.
At least once ner 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air uemperature is less than 40*F or greater than 100 F.
1 l
~
i i
SAN ON0FRE - UNIT 3 3/4 5-8 AMENDMENT NO. 32
d
(
3/4.1 REACTIVITY CONT 20L SYSTEMS B/SES 3/4.1.1 80 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A suf ficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptaole limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary.t,hroughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg.
The most restrictive condition occurs at E0L, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN
['
MARGIN of 5.15% delta k/k is required to control the reactivity transient.
Accordingly, the SHUTOOWN MARGIN requirement -is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T,yg less than or equal to 200*F, the reactivity transients resulting from any postulated accident are minimal and a 3.0% delta k/k shutdown margin provides l
adequate protection.
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coef-
~
ficient will be maintained within acceptable values throughout each fuel cycle.
SAN ONOFRE-UNIT 3 8 3/4 1-1
REACTIVITY CONTROL SYSTE!iS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 520 F.
This limitation is required to ensure (1) the moderator temperatura coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor pressure vessel is above its minimum RT temperature.
NDT 3/4.1.2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid makeup pumps, and (5) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capa-bility in the event an assumed failure renders one of the systems inoperable.
Allowable out-of-service periods ensure that minor component repair or correc-tive action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 3.0% delta k/k after xenon decay and cooldown to 200 F.
The maximum expected boration capability requirement occurs at E0L from full power eqailibrium xenon conditions and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and volumes of Specification 3.1.2.8 plus approximately 13,000 gallons of 1720 ppm borated water from the refueling water tank or approximately 45,000 gallons of 1720 ppm borated water from the refueling water tank alone.
However, for the purpose of consistency the minimum required volume oi 362,800 gallons above ECCS suction connection in Specification 3.1.2.8 is identical to more restrictive value of Specification 3.5.4.
With the RCS temperature below 200 F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.
The boron capability required below 200 F is based upon providing a 3.0% delta k/k SHUTOOWN MARGIN af ter xenon decay and cooldown from 200 F to 140 F.
This condition requires 5150 gallons of 1720 ppm borated water from either the refueling water tank or boric acid solutie from the boric acid makeup rank.
SAN OP'FRE-UNIT 3 B 3/4 1-2 AMENDMENT N0. 32
_ _ _