Text

Amends 28 & 17 to Licenses NPF-10 & NPF-15,respectively, Providing Consistency W/Revised Plant Design for ECCS Subsystems,Adding Emergency Chilled Water Subsystem & Changing Boric Acid Storage Tank Vol/Concentration
	ML20106G353
Person / Time
Site:	San Onofre
Issue date:	12/19/1984
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20106G356	List: ML20106G353; ML20106G380;
References
	TAC-54872, TAC-54873, TAC-55999, TAC-56000, TAC-56001, TAC-56215, TAC-56220, NUDOCS 8502140352
	Download: ML20106G353 (39)
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UNITED STATES o,'n NUCLEAR REGULATORY COMMISSION E

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

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DOCKET NO.'50-361 SAN ONOFRE NUCLEAR GENERATINh2 STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE

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Amendment No. 28 License N'o. NPF-10 1.

The Nuclear Regulatory Comission (the Comission) has found that:

The applications for amendment to the license for San Onofre Nuclear A.

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 April 24, April. 27, July 9, August 7 August 21, August 27 and September 12,1984, comply with the standards and requirements of the Atomic Ener.gy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter li B.

The facility will operate in confomity with the applications, as l

amended, the provisions of the Act, and the regulations of the Comission; l

C. ' There is reasonable assurance:.(i)thattheactivitiesauthorized 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 common defense-and security or to the health and safety of the public; l

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The issuance of this amendment is.in accordance with 10.CFR Part 51 i

i of.the Coninission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is' amended by changes to the Technical -Specifica-J tions as indicated.in the attachment to this license-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 Environ'-

mental Protection Plan contained-in Appendix B, as revised through Amendment No. 28, are hereby incorporated in the license. SCE shall operate.the facility in accordance with the Technical Specifications and the Environmental Protection Plan..

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This amendment is. effective-as of the date of issuance.

FOR THE-NUCLEAR REGULATORY COMMISSION Dr? girl s@5d by:

Georga W. Knightca.

.i George W. Knighton, Chief.

Licensing Branch No. 3 s

Division of Licensing

Attachment:

Changes to the Techn' Specifications Date of Issuance: December 19, 1984 Y

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ATTACHMENT 'TO LICENSE AMENDMENT ' NO. '28 1 >

,a L-FACILITY OPERATING LICENSE NO.' NPF-101

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1 DOCKET NO. 50-361

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q l Replace ~the'following pages of-the Appendix A Technical = Specifications with.,

the enclosed pages.- The revised pages are identified by Amendment number. and

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i contain vertical ?1ines indicating the area of. change. Also to,befreplaced are 7the following overleaf pages to the amended pages.

' Amendment Pages Overleaf Pages

-3/4 1-3:

3/4'1-4 3/4.1-7 3/4 1-8 3/4 1-9

-3/4 1-10' 3/4 1 -

3/4 1-126 3/4-l-13:

3/4 1-14

'3/4 5-4 3/4 5 -3/4 7-36

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B 3/41-1

- B 3/4 1-2 B.3/4 7-8 B 3/4 7-7

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REACTIVITY CONTROL SYSTEMS

. SHUTDOWN MARGIN - T,y LESS THAN'OR EQUAL T0'200'F

' LIMITING CONDITION FOR OPERATION-

. 3.1.1.2' The SHUTDOWN MARGIN shall' be greater than or equal to 3.0% delta k/k.

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. APPLICABILITY: MODE 5.

ACTION:

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With the-SHUTDOWN MARGIN 'less than 3.0% delta k/k', immediately initiate and -

l-i continue boration at greater than or equal to 40 gpa of a solution containing greater than or equal to 1720 ppm boron or_ equivalent until the required-SHUTDOWN MARGIN is. restored.

1 SURVEILLANCE REQUIREMENTS 1

I 4.1.1.2 The ' SHUTDOWN MARGIN shall be determined to be greater than or equal to 3.0% delta k/k:

a.~

Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s) is inoperable.

If the. inoperable CEA is immovable or untrippable, the above.

required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn wcrth of the immovable er untrippable CEA(s).-

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following -

i factors:

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Reactor coolant system' boron concentration, 1

2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal, energy generation,-

5.

Xenon concentration,and-6.

,Samaritmi concentration.

7.

Whenever the~ reactor coolant ' level is below the hot leg.

i centerline, one and only one charging pump shall be operable; by verifying that power is removed from the remaining charging pumps.

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' SAN ONOFRE-UNIT-2 3/4 1-3

-AMENDMENT NO..28 l

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REACTIVITY CONTROL SYSTEMS I

MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3.The moderator temperature coefficient (MTC) shall be:

-4 a.

Less positive than 0.13 x 10 delta k/k/*F, and'

-4 b.

Less negative than -2.5 x 10 delta k/k/*F at RATED THERMAL P,0WER.

APPLICABILITY: MODES 1 and 2*#

ACTION:

With the moderator temperature coefficient outside any one of the-above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS S 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.

4.1.1.3.2 The MTC shall be determined at the following frequencies snd THERMAL POWER conditions during each fuel cycle:

a.

Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.

b.

At any THERMAL POWER, within 7 EFPD of reaching 40 EFPD core burnup.

- c.

At any THERMAL POWER, within 7 EFPD of reaching 2/3 of expected core burnup.

"With K,ff greater than or equal to 1.0.

See Special Test Exception 3.10.2.

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REACTIVITY CONTROL SYSTEMS f

FLOW PATHS'- 0PERATING

. LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following boron injection flow paths and one associated heat tracing circuit shall be OPERABLE:

a.

Flow paths from one or both boric acid makeup tanks via 1.

The associated gravity feed connection (s) and/or 2.

The associated boric acid makeup pump (s) via charging pump (s) to the RCS and/or b.

The flow path from the refueling water storage tank via charging pump (s) to the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the 4

Reactor Coolant System to OPERABLE. status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN. equivalent to'at least 3.0% delta k/k at l

200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least~two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

i a.

At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path from the boric acid makeup tanks is above the temperature limit line shown on Figure 3.1-1.

b.

At least once per 31 days by verifying that each valve (inanual, 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.

d.

At least once per 13 months by verifying that the flow path required by Specification 3.1.2.2.a delivers at least 40 gpm to the Reactor Coolant System.

SAN ONOFRE-UNIT 2 3/4 1-7 AMENDMENT NO.' 28 i

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ftEACTIVITY~CONTROLSYSTEMS t

' CHARGING PUMP'- SHUTOOWN I --

LIMITING CONDITION FOR OPERATION 3

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--

i tion 3.1.2.1 shall be 0PERABLE and capable of being powered from an OPERABLE emergency power. source.

t APPLICA8ILITY: MODES 5 and 6.

i ACTION:

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i 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.

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i SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by i

Specification 4.0.5.

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SAN ONOFRE-UNIT 2 3/4 1-8

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-REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING' LIMITING CONDITION FOR OPERATION' l

1 3.1.2.4 At 'least two charging pumps si.all be OPERABLE.

l APPLICABILITY: MODES 1, 2, 3 and 4.

. ACTION:

With only one charging pump OPERABLE, restore at'least two charging puinp's to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDB7 and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F within the next l.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD _ SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

s SURVEILLANCE REQUIREMENTS 4.1.2.4 No additional Surveillance Requirements ~other than those required by Specification 4.0.5.

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SAN ON0FRE-UNIT 2 3/4 1-9l AMENDMENT NO.28

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t REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP ' 11P - SHUTDOWN.

LIMITING CONDITION FOR OPERATION 3.1.2.5 ' At le'ast one boric acid makeup pump shall be OPERABLE and capable. of being powered from an OPERABLE emergency bus if only the flow path.through the boric acid pump.in Specification 3.1.2.1.a is OPERABLE.

APPLICABILITY: MODES 5 and 6.

ACTION:

4 With no boric acid makeup pump OPERABLE as required to complete the flow path of Specification 3.1.2.1.a. suspend all operations' involving CORE ALTERATIONS.

or positive reactivity changes.

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, SURVEILLANCE REQUIREMENTS f

4.1.2.5 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 Atl1'easttheboricacidmakeuppump(s).intheboroninjectionflow path (s) required OPERABLE pursuant to Specification 3.1.2.2a 'shall be OPcRABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump (s) in-Specification 3.1.2.2a is OPERABLE.

l APPLICABILITY: - MODES 1, 2, 3 and 4.

ACTION:

With one boric acid makeup pump required for the boron injection flow path (s).

pursuant to Specification 3.1.2.2a_ inoperable, restore the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 l

OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE-REQUIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0.5.

SAN ONOFRE-UNIT 2 3/4 1-11 AMENDMENT NO.28 4

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< t REACTIVITY CONTROL SYSTEMS B0 RATED 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 and at least one associated heat tracing circuit with the tank contents in accordance with Figure 3.1-1.

b.

The refueling water. storage tanks with:

1.f' A minimum. borated water volume of 997'O gt'lons above the ECCS l

suction connection,

' 2.

A minimum boron concentration of 1720 p., and 3.

A solution temperature between 40*F and 100*F.

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APPLICABILITY: MODES 5 and 6.

ACTION:

With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE0VIREMENTS 4.1.2.7 The above required borated water source shall be' demonstrated OPERABLE:

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At least ccce per 7 days by:

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Verifying the boron concentration of the water, 2.

Verifying the contained borated water volume of the tank, and 3.

Verifying the boric acid makeup tank solution temperature when it is the source of borated water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

N SAN ONOFRE-UNIT 2 3/4 1-12' AMENDMENT NO.28

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REACTIVITY CONTROL' SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:

- a.

At least one boric acid makeup tank and at least one associated heat -

tracing circuit with the contents of the tanks in accordance with Figure 3.1-1, and b.

The refueling water storage tank wit:c

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A' minimum contained borated water volume of 362,800 gallons above the ECCS suction connection, 2.

Between 1720 and 2300 ppm of boron, and 3.

A solution temperature between 40 F and 100*F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the above required boric acid makeup tank inoperable, restore the tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHU100WN MARGIN equivalent to at least 3.0% delta k/k at 200'F; restore the above l

required boric acid makeup tank to OPERABLE status within the next 7 days or be in COLD 3HUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water sources 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, and 3.

Verifying the boric acid makeup tank solution temperature.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is less than 40'F or greater than 100*F.

SAN ON0FRE-UNIT 2 3/4 1-14 AMENDMENT NO. 28 a

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3/4.7.10 EmergencyLChilled Water System

.The OPERABILITY of the emergency chilled water system ensures that space.

l cooling capacity is available for.continuec operation of safety-related

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' equipment during accident conditions. The redundant cooling capacity of these systems.is consistent =with single failure criteria and the assumptions used in the' accident analyses.'

A=7. day. ACTION requirement is~specified in the event i

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ofJamergency chilled water system inoperability, based on the high reliability-of offsite power _and availability of the normalgHVAC' system. Further Actions g

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-(b.1.,1b.2 and b.3) are-specified regarding i.he status of systems and equipment which are unit specific and common. These Actions are.not intended _to apply.

- to the status of. systems and equipment specific to the other Unit. When one emergency chilled water system is inoperable, there:is an ACTION requirement to verify within.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months that the normal ~HVAC system'is providing space cooling Lto the vital power distribution rooms that are served by the inoperable F

emergency. chilled water _ system. Availability of the normal HVAC system j

permits the vital' bus inverters and emergency battery chargers to continue to be considered OPERABLE by ensuring that environmental qualification limits are not exceeded (the-loss of space cooling to tLe vital power distribution rooms.

will not result.i_n_ loss of vital bus inverter lor emergency battery charger function in less than 75 minutes). The requirement to. establish ~0PERABILITY of all required systems,. subsystems, trains, components and. devices, that depend on the remaining emergency chilled water. system for space cooling, is intended to provide assurance that an OPERASLE train _of safety-related-i equipment is available to meet the requirements 'of the range of design basis events. The requirement to; establish OPERABILITY of-the minimum safe shutdown systems ensures that at least one train of safety systems is available to place the plant in a safe, stable condition in the event of transients such as loss of offsite power, a safe shutdown earthquake, or design. basis fire prior e

to establishment of OPERABILITY of the remaining required safety systems. ~The term verify as used in this context means to administrative 1y check by examining logs or'other information to determine if certain components are out-of-service f>r maintenance or other reasons.. It does not mean to perform the surveillance requirements needed to demonstrate OPERABILITY.of the-L component. Tc establish OPERABILITY as used in this context means to either verify OPERABILITY as above or to return the required equipment to OPERABLE.

status and perform the associated surveillance requirements as required..

Surveillances are specified to verify correct positioning of emergency chilled water system valves servicing equipment.which is unit specific and common.

It i

is not intended that surveillance of valves servicing equipment = specific to the other Unit be required to establish ECWS.0PERABILITY under this Technical Specification. The safety systems served by the emergency chilled water system cannot be considered OPERABLE in the absence of all (both nornal and

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emergency) space cooling. The definition of OPERABILITY-(TS 1.17) is to be

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used.in conjunction with-the Technical Specifications governing'the u fected j

systems, to determineithe appropriate action requirement in the event of loss L

of all. space cooling.

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PLANT SYSTEMS BASES FIRE SUPPRESSION SYSTEMS (Continued)

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the

major fire suppression sapability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

The San Onofre Unit 2&3 fire' pumps and water supplies, supply water"to the San Onofre Unit 1 fire system.

3/4.7.9 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility' of a single fire involving more than one fire area prior to detection ar.d extinguishment. The fire barriers, fire barrier penetrations for conduits, cable trays and piping, fire windows, fire dampers, and fire doors are periodically inspected to verify their OPERABILITY.

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SAN ONOFRE-UNIT 2 8 3/4 7-7 Amendment No. 4 b

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. 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 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, 5) associated heat tracing systems, and 6) 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 frec; 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 l

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 or 81,970 gallons of 1720 ppm borated water from the refueling water tank. 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.

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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 ALTERATIONS and positive reactivity changes'in the event' prohibiting CORE the single injection system becomes inoperable.

.j 1

The boron capability required below 200*F is based upon providing a j

3% delta' k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 14U*F. -This condition requires either 9,970 gallons of 1720 ppe borated water from the refueling water tank or boric acid solution from the boric acid makeup tanks in accordance with the requirements of Specification 3.1.2.7.

)

SAN ONOFRE-UNIT 2 B 3/4 1-2

~.

-m

. m.

,_m.,.

L L. -

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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 t

A sufficient SHUTDOWN MARGIN ensures.that 1) the reactor can be made' subcritical from'all operating conditions,'2) the reactivity transients:

3 associated with' postulated accident conditions-.are controllable within

- acceptable -limits, and 3) the reactor will be maintained aufficiently subcritical to preclude inadvertent criticality in the_, shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of

-fueidepletion,RCSboronconcentration,~andRCST,yg.:Themostrestrictive 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-l trolled RCS cooldown. In the analysis of-this accident, a minimum SHUTDOWN j

MARGIN of-5.15% oelta k/k is-required to control the reactivity transient.

Accordingly, the-SHUTDOWN MARGIN requirement is based upon this limiting I

condition and is consistent with FSAR safety analysis assumptions. With1T,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 t

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 t

[

the measured MTC value is within its limit provides assurances that the coef-'

ficient will be maintained within acceptable values throughout each fuel 4-cycle.

i.

1 SAN ONOFRE-UNIT'2 B 3/4 1-1 AMENW4ENT'NO. 28

-,, +. +.,,s.. a p

p

,,,.9

,,v.

..s e

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EMERGENCY CHILLED WATER 'YSTEM-S SURV'EILLANCE REQUIREMENTS (Continued) l b.

. At least once per.18 months by verifying that: each power-operated or: automatic valve servicing safety-related equipment actuates to its -

-correct position and each chilled water pump starts automatically on a

,TGIS, CRIS, SIAS and,'with' irradiated fuel in the storage pool, FHIS.

s f

4 4

1 9

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JSAN ONOFRE-UNIT 2-

' - 3/4 7-37

' AMENDMENT N0.'28 i.

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-PLANT SYSTEMS' 3/4.7.10 EMERGENCY CHILLED WATER SYSTEM LIMITING CONDITION FOR OPERATION

3.7.10 -Two independent emergency chilled water systems shall be OPERABLE.

i~

APPLICABILITY: -MODES 1, 2, 3 and 4.

I ACTION:

a.

With only one'energency chilled water system OPERABLE,~ restore the

' inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~

i b.

.With only one emergency chilled water system OPERABLE:

i 1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that the normal HVAC system is providing i

space cooling to the vital power distribution rooms containing i

emergency battery chargers and inverters that depend on the inoperable emergency chilled water system for space cooling, and.

2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months establish OPERABILITY of the safe shutdown systems which do not depend on the inoperable emergency chilled water system (one train each of boration and' auxiliary feedwater per Sections 3/4.1.2.2 and 3/4.7.1.2, respectively, and one. bank of pressurizer heaters per. Section 3/4.4.3) and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish OPERABILITY of all required systems,.

subsystems, trains, components and devices that depend on the remaining OPERABLE emergency chilled water system for ' space :

l cooling.

t If these conditions are not satisfied within the specified time, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.10 Each of the above-required. emergency chilled water-systems'shall be demonstrated OPERABLE:

~

a.

At.least once per 31 days by verifying that each manual valve

. servicing safety-related equipment that is.not locked, sealed,--or otherwise secured in position, isiin its correct position and, j

l SAN ONOFRE-UNIT 2 3/4 7-36 AMENDMENT-NO.'28L n,e.

' 9 n.

4

.2 zu.

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' EMERGENCY CORE COOLING SYSTEMS

--SURVEILLANCE REQUIREMENTS 4.5.2' Each ECCS subsystem shall'be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves ~are in:the indicated positions with power to the valve operators removed:

Valve Number LValve Function Valve Position a.

HV9353 SDC Warmup CLOSED b.

HV9359-SDC Warmup

-CLOSED

.c.

HV815c SDC(HX) Isolation CLOSED d.

HV8151 SDC(HX) Isolation CLOSED e.

HV8152 SDC(HX) Isolation CLOSED f.

HV8153 SDC(HX) Isolation CLOSED g.

HV0396 SDC Bypass Flow. Control CLOSED h.

HV8161 SDC(HX) Bypass Flow OPEN Isolation 1.

HV9420 Hot Leg Injection CLOSED Isolation j.

HV9434 Hot Leg Injection CLOSED Isolation k.

HV8160 SDC Bypass Flow Control OPEN 1.10-068 RWST Isolation LOCKED OPEN (MANUAL) m.

HV8162 LPSI Miniflow Isolation OPEN n.

HV8163 LPSI Miniflow Isolation OPEN b.

At least once per 31 days by:

1.

Verifying that' the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and-2.

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 the correct position.

I By a visual inspection which verifies that no loose debris (rags, c.

trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the 1

pump suctions during LOCA conditions. This visual inspection shall i

be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

Of.the areas affected within containment at the completion of-containment entry when C0hTAINMENT. INTEGRITY is established.

d.

' At least once per 18 months by:

l 1.

Verifying automatic isolation of the shutdown cooling system

~

from the Reactor Coolant' System when RCS' pressure is simulated j

- greater than or equal to 715 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves

[

when simulated RCS pressure is. greater.than or equal to-376 psia.

SAN ONOFRE-UNIT 2 3/4 5-4~

AMENDMENT N0. 28 l-

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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 'ECCS SUBSYSTEMS --T,y GREATER THAN OR EQUAL TO 350*F

.L1HITING CONDITION FOR OPERATION 3.5.2,Two independent Emergency ' Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

One OPERABLE high pressure-safety injection, pump,

-a.

b.

One OPERABLE low pressure. safety injection pump, and One OPERABLE charging pump capable'of taking suctio.n from either the c.

boric acid makeup tank or the-refueling water storage tank.

d.

An independent OPERABLE flow path capable lof taking suction from the' refueling water tank on a Safety Injection Actuation Signal and automatically tr'ansferring suction to the containment sump on a Recirculation Actuation Signal..

APPLICABILITI: MODES 1, 2 and 3".

ACTION:

With one ECCS subsystem inoperable, restore the inoperable subsystem a.

-to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at _least. HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 circumstahces of the actuation and the total accumu-lated 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.'

~

s With pressurizer pressur,e greater than tr equal to.400 psia.

e C~t l

SAN ONOFRE-UNIT 2 3/4 5 AMENDMENT NO. 16 i-

1 g new 9,,

UNITED STATES

+

'I NUCLEAR REGULATORY COMMISSION o

s j

WASMNGTON, D. C. 20565 4.,...../

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 ONOFRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No. 17 License do. NPF-15 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Com California (pany, The City of Riverside and The City of Anaheim, licensees) dated A and September 12, 1984, comply with the standards and requirements of -

the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Commissiion; j

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 common defense and security or to the health and.. safety of the public; I

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w-.

s 2[-

~

'E. ' ;The issuance of this amendment is in-'accordance with.10.CFR Part 51 of the Commission's: regulations and a11' applicable requirements have.

been satisfie'd..

2; Accordingly, the" license is amended by changes to'the1 Technical Specifica--

tions as indicated:in the attachment to this license amendment,'and.>

paragraph 2.C(2) of Facility 0perating License No. NPF-15 is/hereby amended to read as follows::

(2). Technical Specifications 3 -

TheTechnical-SpecificationscontainedinApp$ndixAandtheEnviron-menta1' Protection-Plan coritained in Appendix B, as revised through ~

Amendment No.17..'are herebyiincorporated in the license. - :SCE 'shall-

~

operate'the facility in accordance with the Technical: Specifications

.and the-Environmental. Protection Plan.

3.-

The following Technical Specification pages for this amendment are

. effective as of the date of issuance:

3/4 7-37 3/4 7-38

+

B 3/4 7-8 The following Technical Specification pages for this amendment are effective prior to initial entry into Mode 5 following first refueling:

~

3/4 1 3/4 7-37 3/4 1-7 3/4 7-38 j'

3/4 1-9 B 3/4 1-1 m

3/4 1-11 B 3/4 1-2 L

3/4 1-14 l

FOR THE NUCLEAR REGULATORY COMMISSION i

l

[-

Or!Einalsig:15:1 by:

l Georgo W. KnigMon George W. Knighton, Chief Licensing. Branch No.13

' Division of Licensing i

L Attachmer.t:

Changes-to the-Technical Specifications

' December 19 h g Date of Issuance:

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3 HRood/yt.

LChandler n ghton 12/g /84.

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... December 19, 1984:

ATTACHMENT TO LICENSE AMENDMENT N0; 17 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 are

- the following overleaf pages to the amended pages.

Amendment Pages Overle'af Pages' 3/4 1-3 3/4 1-4

-3/4 1-7 3/4 1-8 3/4 1-9

'3/4 1-10

3/4 1-11 3/4 1-12 3/4 1-14 3/4 1-13 3/4 7-37.

3/4 7-38 B 3/4 1-1 B 3/4 1-2 B 3/4 7-8 B 3/4 7-7 4

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REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T LESS THAN OR EQUAL TO 200*F LIMITING CONDITION FOR OPERATION l

3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 3.0% delta k/k. l APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 3.0% delta k/k, immediately initiate and l

continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 1720 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

E SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 3.0% delta k/k:

l a.

Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s) is inoperable.

If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s).

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, S.

Xenon concentration,and 6.

Samarium concentration.

7.

Whenever the reactor coolant level is below the hot leg center-line, one and only one charging pump shall be operable; by veri-fying that power is removed from the remaining charging pumps.

SAN ONOFRE-UNIT 3 3/4 1-3 AMENDMENT NO. 17

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. MODERATOR TEMPERATURE COEFFICIENT; LIMITING CONDITION-FOR OPERATION t

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'3.1.1.3 The moderator temperature. coefficient (MTC) shall be:

~4 a.

-Less positive than 0.13_x 10 de'Ita k/k/?F, and

~4 b.

Less negative than '-2.5 x 10 delta k/k/?F at RATED THERMAL-POWER.

I APPLICABILITY: MODES 1-and'2*#~

ACTION:

With~the~ moderator temperature coefficient outside any one of the above

i limits,be in'at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i-SURVEILLANCE REQUIREMENTS I

(

4.1.1.3.1 The MTC shall be determined to be within itsilimits;by confirmatory

~

l measurements. MTC measured values.shall be extrapolated-and/or compensated.to permit direct comparison with the above limits.

4.1.1.3.'2'.The MTC shall be determined at the following frequencies and-L THERMAL POWER conditions during each. fuel cycle:

a.

Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading, b.

At any THERMAL POWER, within 7 EFPD.of reaching 4'O EFPD core burnup.

c.

At any THERMAL POWER, within 7 EFPD of reaching 2/3 of expected core burnup.

With K,gg greater-than or equal to 1.0.,

See:Special Test' Exception 3.10.2.-

SAN ONOFRE-UNIT 3

- 3/4 1-4' 4..

3 4

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- FLOW PATHS - OPERATING LINITING CONDITION FOR OPERATION 4

3.1.2.2.. At least-two. of the f. howing boron injection flow paths and one associated heat tracing circuit. hall be OPERABLE:

a.

Flow paths from one'or both boric acid makeup tanks via

~

1.

.The associated gravity' feed connection (s) and/or

~

2.

The' associated boric acid makeup pump (s) via charging pump (s) to the RCS

.and/or l

b.

The flow path from the refueling water storage' tank via charging i

i pump (s) to the Reactor Coolant System.

I APPLICABILITY: MODES 1, 2, 3 and 4.

p.

ACTION:

With only' one of the above required boron injection flow paths to the Reactor.

I Coolant System OPERABLE, restore at least two boron. injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .or be in at'least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k-'

l1 at 200'F within.the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two-flow' paths to OPERABLE status within the 'next 7 days.or be in. COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow path's shall.be' demonstrated OPERABLE:

At least once per 7 days'by verifying that the temperature of 'he

~

t a.

heat traced portion of the flow path.from the boric acid makeup-l tanks is above the temperature limit line shown on Figure 3.1-1.

~

b.

At least once per'31 days by verifying that each vcive (manual, power operated or automatic).in the flow path that tis 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.

d.

At least once per 18 months by verifying that the flow path required

.by Specification 3.1.2.2.a delivers at least'40 gpm to the Reactor Coolant System.'

SAN ONOFRE-UNIT 3'

'3/4 1-7

. AMENDMENT NO.17 l

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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 OPERABLE pursuant to Specifica-tion 3.1.2.1 shall be 0PERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: H0 DES 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.

u I '

SAN ON0FRE-UNIT 3 3/4 1-8 l

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING

- LIMITING CONDITION FOR OPERATION 3.1.2.4 -At least two charging pumps shall be OPERABLE.

- APPLICABILITY: MODES 1, 2, 3 and 4.

- ACTION:

With only one charging pump OPERABLE,. restore at least two charging pumps "to -

OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least NOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F within the next-l 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4 No additional Surveillance Requirements other than those required by Specification 4.0.5.

t s

SAN ONOFRE-UNIT 3.

3/4 1-9 AMENDMENT NO. 17 n

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+

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4 i.

4 REACTIVITY C04 TROL' SYSTEMS

- BORIC ACID MAKEUP PUMP - SHUTDOWN--

LIMITING CONDITION FOR OPERATION 3.1;2.5.' At least one boric acid makeup pump shall be OPERA 8LE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid pump-in Specification 3.1.2.1.a is OPERABLE.

APPLICA8ILITY: MODES-5 and 6.

- ACTION:

J With no' boric acid makeup pump OPERABLE as required to complete the flow path of Specification 3.1.2.1.a. suspend all operations involving CORE ALTERATIONS or-positive reactivity changes.

4 i

i SURVEILLANCE REQUIREMENTS

(

i 4.1.2.5 No additional Surveillance Requirements other than those required by-l Specification 4.0.5.

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, SAN ONOFRE-UNIT 3 3/4 1-10 g

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REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - OPERATING 4 -

' LIMITING CONDITION FOR OPERATION 3.1.2.6 1At least th'e boric acid makeup pump (s) in.he-boron injection flow

path (s)Lrequired OPERABLE pursuant to Specification 3.1.2.2a shall be -

OPERABLE'and capable of being powered from an OPERA 8LE emergency bus if the flow path through the boric acid pump (s) in Specification 3.1.2.2aris c

OPERABLE.

i APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one boric acid makeup pumn-required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a inoperable, restore.the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least.H01 STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least 3.0%' delta k/k at 200*F; restore the above required boric acid'eakeup pump (s) to l

{

OPERABLE status within the'next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4 i

SURVEILLANCE REQUIREMENTS 4.1.2.6. No additional Surveillance Requirements other +.han those required by Specification 4.0.5.

1 4

1.

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I' SAN ONOFRE-UNITf3 3/4 1-11 AMENDMENT NO. 17:

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$ ~ + ~

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REACTIVITY CONTROL SYSTEMS i

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i BORATED WATER' SOURCE -:SHUTOOWN g

LIMITING CONDITION TOR OPERATION 3.1.2.7 As a' minimum,ione of the'following borated water sources shall be

- '0PERA8LE:

One boric acid makeup tank'and'at least one associated heat tracing

'~

a.

. circuit with the tank contents in accordance.with Figure 3.1-1.~

b.

The refueling water storage tanks with:

1.

A minimum borated' water volume of 5465 gallons above the ECCS suction connection,

'2.

A minimum boron. concentration of 1720 ppe, and 3.

A solution' temperature between 40*F and 100*F.

4 r

APPLICA8ILITY:. MODES 5 and 6.

i l

ACTION:

With no borated water sources OPERABLE, suspend all operations involving CORE I

ALTERATIONS or positive reactivity changes.

l l

SURVEILLANCE REQUIREMENTS i

4.1.2.7 The above required borated water source shall be demonstrated

~

OPERA 8LE:

l a.

At'least once per 7 days by:

1.

Verifying the boron concentration of the water,

, ' 2.

Verifying the contained borated water volume of the tank, and -

I Verifying the boric acid makeup-tank solution temperature when 3.

-it is the source of borated water.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by' verifying the RWST : temperature when it b

.b.

is the source of borated water when the outside air temperature is

'less than 40*F.or greater than 100*F..

~

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-SAN ON0FRE-UNIT 3-

'3/4 1-12 I

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4

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160 9,500 2

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STORED BORIC ACID CONCENTRATION -WT %,(ppm B)

Figure 3.1 1 -

MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION k

SAN ONOFRE-UNIT 3 3/4 1-13 f

4

~

3EACTIVITY CONTROL SYSTEMS

.BORATFD WATER SOURCES - OPERATING LIMITING CONDITION FOR'0PERATION

~ ~

3.1.2.8 Each of the following borated water sources shall be~ 0PERABLE:

1.

a.

At least one boric acid makeup tank and at least one associated heat tracing circuit with the contents of the tanks in accordance with Figure 3.1-1, 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 2300 ppm of boroa, and 3.

A solution temperature between 40*F and 100*F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the above required boric acid makeup tank inoperable, restore the tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200'F; restore the above l

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 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l b.

With the refueling water tank inoperable, restore the tank to OPERABLE status within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPEkABLE:

a.

At least once per 7 days by:

l 1.

Verifying the boron concentration in the water, 2.

Verifying the contained borated water volume of the water source, and 3.

Verifying the boric acid makeup tank solution temperatur2.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is less than 40*F or greater than 100*F.

1

(

SAN ONOFRE-UNIT 3 3/4 1-14 AMENDMENT NO. 17

.. ~

PLANT SYSTEMS ~

- 3/4.7.10 ' EMERGENCY CHILLED WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10 Two independent emergency chilled water systems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

' With only one emergency chilled water system OPERA 8LE, restore the?

inoperable system to OPERABLE status within 7 days or be in at least.

t NOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the fo110 wing'30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With only one emergency chilled water system OPERABLE:

1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify.that the normal HVAC system is providing

[

space cooling to the vital power distribution rooms containing emergency battery chargers and inverters that depend on the j

inoperable emergency chilled water system for space cooling,'and i

2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months establish OPERABILI1Y of the safe shutdown systems which do not depends on the inoperable emergency chilled water system (one train each of boration and auxiliary feedwater i

per Sections 3/4.1.2.2 and 3/4.7.1.2, respectively. and.one bank of pressurizer heaters per Section 3/4.4.3) and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months establish OPERABILITY of all required systems, I

subsysteas, trains, components and devices that depend on the remaining OPERABLE emergency chilled water system for space cooling.

If these conditions are not satisfied within the specified time, be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.10 Each of the above required emergency chilled water systems shall-be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each manual va1've servicing safety-related equipment that is not~ locked, sealed, or otherwise secured in position,'is in its correct position and, 1

SAN ON0FRE-UNIT 3 3/4 7 AMENDMENT NO. 17 h

Jp.. -

v- +

-EMERGENCY CHILLED WATER SYSTEM-

SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per.18 months by. verifying that: 'each power-operated or automatic valve servicing safety-related equipment actuates to its correct position and each chilled wter pump starts automatically on a TGIS, CRIS, SIAS ~and,:with irradiated fuel.in the storage pool, FHIS.

~

l SAN ON0FRE-UNIT 3 3/4 7-38 AMENDMENT NO.(17--

=

I 3/4.1 REACTIVITY CONTROL SYST' EMS

- 8ASES

'3/4.1.1 BORATION' CONTROL 4

3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient 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.

' acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent riticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg..The most restrictive l

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 wit'h FSAR safety analysis assumptions. With T,yg less than or equal to 200*F, tne reactivity transients'resulting from any postulated accident are-minimal and a 3.0% delta k/k shutdown margin provides adequete 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

~

f REACTIVITY CONTROL SYSTEMS' l

BASES-

^

3/4.1~.1.4 MINIMUM TEMPERATURE FOR' CRITICALITY This specification ensures that the. reactor will not be made critical 4

with the Reactor Coolant System average temperature less than-520*F. - This -

1-limitation is required to ensure (1) the moderator temperature coefficient is4 i

within its-analyzed temperature range, (2) the protective instrumentation is' within'its normal operating range, (3) the pressurizer is capable of being in

[

an OPERA 8LE status with a steam bubble, and (4) the reactor pressure vessel is above its minimum RTNDT temperature.

I, -

3/4.1.2 BORATION' SYSTEMS i

i The boron injection system ensures that negative reactivity control is I

available during each mode of. facility operation. The components required to perform this function include (1) borated water sources, (2) charging pumps, i

(3) separate flow paths, (4) boric acid makeup pumps, (5) associated heat' l

tracing systems, and (6) an emergency power supply from OPERABLE diesel j

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 j

inoperable. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall i

}'

facility safety from injection system failures during_the repair period.

i The boration capability of either. system is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions'of 3.0% dalta k/k after xenon decay and cooldown to 200'F. The maximum expected boration~ capability i

reo"irament 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 or 53,500 gallons of i

1720 ppm borated water from the refueling water tank. However, for-the-i purpose of consistency the minimum required volume of 362,800 gallons above ECCS-i suction connection in Specification 3.1.2.8 is identical to the more restrictive value of Specification 3.5.4.

l With the RCS temperature below 200*F one. injection system is' acceptable without single failure consideration on the basis of the stable reactivity i

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 l

3.05 delta k/k SHUTDOWN MARGIN after xenon decay and cooldown~ from 200*F to i

140*F. This condition requires either 5465 gallons of 1720 ppe borated l

water from the refueling water tank or boric acid solution from the boric acid makup tanks in accordance with the requirements of Specification 3.1.2.7.

L1 SAN ONOFRE-UNIT 3 B 3/4 1-2 l

9 g

6 D-er e

+

9~

-M-eist

A

'*3 *ba yr. M ^ 'P8& e 9 #

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l

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. ~

. - nm.

1 l

)

-PLANT SYSTEMS 3

BASES

> FIRE SUPPRESSION SYSTEMS (Continued)

In the event the fire suppression water system becomes inoperable,

'immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirescnt for a

.24-hour report.to'the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability:for the continued protection of the nuclear plant.

The San Onofre Unit 2 and 3 fire pumps and water supplies supply water to the San Onofre Unit 1 fire system.

3/4.7.9 FIRE RATED ASSEMBLIES

.The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize'the possibility of a single fire involving more than one fire area prior to detection and extinguishment. The fire barriers, fire barrier penetrations for conduits,-

cable trays and piping, fire windows, fire dampers, and fire doors are periodically inspected to verify their OPERABILITY.

r t

?

4 i

(

SAN ONOFRE-UNIT 3 B 3/4 7-7 4

win

, 1 L

1

PLANT-yYSTEMS

~ BASES l3/4.7.'10 Emergency Chilled Water Sys$em

~

The OPERABILITY of the, emergency chilled water system ensures that. space cooling capGty.is available for continued operation of safety-related

. equipment-during accident conditions. The redundant cooling capacity of these

= systemsLis consistent with single failure criteria _and the: assumptions used in the accident' analyses. A 7 day ACTION requirement-is specified in the event-of emergency chilled water system inoperability, based on the high' reliability

-of offsite power and availability of the normal HVAC system. Further Actions (b.1., b.2 and b.3) are specified regarding the' status of systems and equipment

' which are unit specific and common. These Actions are not intended to apply-p

' to'the status of. systems and equipment-specific to the other Unit. When one

~

emergency chilled water system is inoperable, there is an ACTION _ requirement to verify within-1 hour that the' normal HVAC system-is<providing_ space cooling to the_ vital power distribution rooms that are served by the inoperable emergency chilled water system. Availability of the normal HVAC system

. permits the vital bus inverters and emergency battery chargers to continue to-be considered OPERABLE by ensuring that environmental qualification limits'are.

not exceeded (the loss of space cooling to the vital. power distribution rooms will not result in loss 'of vital bus inverter or emergency battery charger function in less than 75 minutes). The requirement to establish OPERABILITY 3

of all' required systems, subsystems,-trains, components and devices, that depend on the' remaining emergency chilled water system for space cooling, is intended to~ provide assurance that an OPERABLE train of safety-related equipment is available to meet the requirements of the range of. design basis events. The requirement to establish OPERABILITY of the minimum ~ safe shutdown systems ensures that at least one train of safety systems is available to place the plant in a_ safe, stable condition in the event of transients such as loss of offsite power, a safe shutdown earthquake, or design basis fire prior to establishment of OPERABILITY of the' remaining required safety systems. The i

term verify as.used in this context means to administratively check by examining logs or other information to determine if certain components 'are out-of-service for maintenance or ~other reasons.

It does~not mean to perform j

the surveillance requirements needed to demonstrate OPERA 8ILITYLof;the component.- To establish OPERABILITY as used in this context means to:either

. verify OPERABILITY as above or to return the required equipment to OPERABLE status-and perform the associated surveillance requirements as required.

Surveillances are.specified to verify correct positioning'of emergency chilled l

water system valves' servicing equipment which is unit specific and common.

It is not intended that surveillance of valves servicing equipment specific to l'

the other Unit be required to establish ECWS~0PERABILITY under this Technical Specification.' ~ The safety systems served by the emergency chilled water.-

!L system cannot be considered OPERABLE in the absence of all-(both normaland i

emergency)l space' cooling.' ' The definition of OPERA 8II.ITY.(TS 1.17) is to be used in conjunction with the Technical Specifications governing the affected systems, tc-determine the appropriate action requirement in the event of loss of allfspace cooling.

(.

SAN ONOFRE-UNIT 3 B 3/4 7-8 AMENDMENT N0. 17 f

.m..

e s

j y

re a %r l'

~..

~

-

v t e Letter Sequence Other
TAC:54872, (Approved, Closed) TAC:54873, () TAC:55999, (Approved, Closed) TAC:56000, (Approved, Closed) TAC:56001, (Open) TAC:56215, (Approved, Closed) TAC:56220, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Approval, Approval, Approval, Approval, Approval Other: ML13303A845, ML20084D509, ML20084D523, ML20101S552, ML20106G353, ML20148L065, ML20206Q756, ML20214Q868, ML20245D589
MONTHYEAR1985-01-09 [Table View]

ML20106G353

Text

Attachment:

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