ML20055G315

Amends 89 & 79 to Licenses NPF-10 & NPF-15,respectively, Establishing New Tech Spec 3/4.7.1.6 Re Atmospheric Dump Valves

ML20055G315
Person / Time
Site:	San Onofre
Issue date:	07/10/1990
From:	Larkins J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055G316	List: ML20055G315 ML20055G317
References
NUDOCS 9007230038
Download: ML20055G315 (31)

Text

...__ _. _. _ _ __

l

[ * * **'aa g,%,,

I UNITED STATES J

NUCLEAR REGULATORY COMMISSION.

o l

w AsHlWGTON, D. C. 2065h r

1

• .. 4 l

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 1

SAN ONOFRE NUCLEAR GENERATING STATION UNIT NO. 2 I

AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 89 License No. NPF-10 1.

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

,l A.

The applications for amendment to the license.for San Onofre NuclearGeneratingStation, Unit 2(thefacility)filedby j

Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside, y

California and the City of Anaheim, California (licensees) dated August 18, 1989 and supplemented May 31, 1990 complies with the standards and req)uirements of the Atomic Energy Act of 1954, as amended (the Act, and the Comission's regulations l

set forth in 10 CFR Chapter I;

]

B.

The facility will o>erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of tie Comission; i

C.

Thereisreasonableassurance(1)thattheactivitiesauthor-ized 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; q

D.

The issuance of:this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require-ments have been satisfied.

f@g72gggg {Q@

1 P

~

2 AccordinglyIndicated in the attachment to this license amendment, andthe lic 2.

cations as

+

paragraph 2.C(2) of Facility Operating License No. NPF.10 is hereby 1

amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, and i

the Environmental Protection Plan contained in Appendix B.

as revised through Amendment No. 89. are hereby incorporated i

in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and t

must be fully implemented no later than 30 days from the date of issuance.

i FOR THE NUCLEAR REGULATORY COMMISSION W {fh V

J f ohn T. Larkins Acting Director P Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications t

L Date of Issuance: July 10, 1990 L

L o

b L

,4 ATTACHMENT TO LICENSE AMENDMENT NO.89 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and Inserting the enclosed pages.

The revised pages are identified by amendment iumber and contain marginal lines indicating the area of change, Also enclosed are the following overleaf pages to the amended pages.

AMENDMENT PAGE OVERLEAFPAg VII VIII X111 XIV 3/4 7-9e 3/4 7-10 B 3/4 7-3 B 3/4 7-3a B 3/4 7-3b B 3/4 7-4 l

2

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES........................................

3/4 7-1 AUXILIARY FEEDWATER SYSTEM...........................

3/4 7-4 CONDENSATE STORAGE TANK..............................

3/4 7-6 ACTIVITY.............................................

3/4 7-7 MAIN STEAM LINE ISOLATION VALVES.....................

3/4 7-9 ATMOSPHERIC DUMP VALVES..............................

3/4 7-Sa l

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM..........................

3/4 7-11 3/4.7.4 SALT WATER COOLING SYSTEM...............................

3/4 7-12 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM...............

3/4 7-13 3/4.7.6 SNU8BERS......................,.........................

3/4 7-16 3/4.7.7 SEALED SOURCE CONTAMINATION.............................

3/4 7-24 i

3/4.7.8 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM........................

3/4 7-26 SPRAY AND/0R SPRINKLER SYSTEMS.......................

3/4 7-29 FIRE HOSE STATIONS...................................

3/4 7-32 3/4.7.9 FIRE RATED ASSEMBLIES...................................

3/4 7-34 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0PERATING............................................

3/4 8-1 SHUTD0WN.............................................

3/4 8-8 3/4.8.1 b.C. SOURCES OPERATING............................................

3/4 8-9 SHUTD0WN.............................................

3/4 8-12 SAN ONOFRE-UNIT 2 VII AMENDMENT NO. 89

-. _... -, - +

-~'#*

~-'

l a

g LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE i

3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS

)

'0PERATING............................................

3/4 8-13 1

1 SHUTD0WN.............................................

3/4 8-15 3/4.8.4 ELECTRICALEQUIPMENTPROTECTIONDEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT.

PROTECTIVE DEVICES.................................

3/4 8-16 MOTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION 8YPASS.............................................

3/4 8-31 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4 9-4

.3/4.9.5 COMMUNICATIONS...........................................

3/4 9-5 3/4.9.6 REFUELING MACNINE.......................................

3/4 9-6 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING 3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL.....................................

3/4 9-8 LOW WATER LEVEL......................................

3/4 9-9 L

3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM......................

3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................

3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE P00L..............................

3/4 9-12 3/4.9.12 FUEL HANDLING BUILOING POST-ACCIDENT CLEANUP FILTER SYSTEM...............................................

3/4 9 13 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION.....................

3/4 9-16 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.........................................

3/4 10-1

.3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS............................

3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS...................................

3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT AND REGULATING CEA INSERTION LIMITS................................................

3/4 10-4 3/4.10.5 RADIATION MONITORING / SAMPLING -- DELETED SAN ONOFRE-UNIT 2 VIII AMENDMENT NO. 87

- -,. -.,,. -. ~.. - -. -.,,, -

-,....,nn,.._

.._-,-,,,,,..,_-.n-,

.,.,,,,a

INDEX t

BASES 4

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINECYCLE.......................l.................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......

B 3/4 7-3b

^

3/4.7.3 COMPONENT COOLING WATER SYSTEM........................

B 3/4 7-3b i

3/4.7.4 SALT WATER COOLING SYSTEM.............................

B 3/4 7-3b 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM............. B 3/4 7-4 3/4.7.6 SNUBBERS..............................................

B 3/4 7-5 3/4.7.7 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-6 3/4.7.8 FIRE SUPPRESSION SYSTEMS..............................

B 3/4 7-6 3/4.7.9 FIRE RATED ASSEMBLIES.................................

B 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and DNSITE POWER DISTRIBUTION SYSTEMS................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...............

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................

B 3/4 9-1 i

3/4.9.2 INSTRUMENTATION.......................................

B 3/4 9-1 3/4.9.3 DECAY TIME............................................

B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS..............................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................

B 3/4 9-1 SAN ONOFRE-UNIT 2 XIII AMENDMENT NO. 89

192 j

8ASES SECTION g

3/4.9.6 REFUELING MCNINE.....................................

8 3/4 9-2 P

3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING...

8 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION..............

8 3/4 9-2 3/4.9.9 CONTAIMENT PURGE VALVE ISOLATION SYSTEN..............B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER IEVEL - REACTOR VESSEL and STORAGE P00L........................................

8 3/4 9-3 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM..............................................

B 3/4 9-3 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION...................

8 3/4 9-4 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................

B 3/4 10-1

)

3/4.10.2 GROUP HEIGNT, INSERTION AND L

POWER DISTRIBUTION LIMITS...........................

B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................

8 3/4 10-1 l

3/4.10.4 CENTER CEA MISALIGNMENT AND REGULATING CEA INSERTION LIMITS....................................

B 3/4 10-1

-3/4.10.5 RADIATION MONITORING / SAMPLING -- DELETED 3/4.11 RADI0 ACTIVE EFFLUENTS V

3/4.11.1 LIQUIDEFFLUENTS......................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.....................................

B 3/4 11-1 3/4.11.3 SOLID RADIDACTIVE WASTE -- DELETED 3/4.11.4 TOTAL DOSE -- DELETED 3/4.12 RADIO ENVIRONMENTAL MONITORING -- DELETED 3/4.12.1 MONITORING PROGRAM -- DELETED 4

3/4.12.2 LAND USE CENSUS -- DELETED 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM -- DELETED SAN ONOFRE-UNIT 2 XIV AMENDMENT NO. 87

t i

f.

INDEX i

LIST OF FIGURES FIGURES PAGE 3.1 1 MINIMUM 80RIC ACID STORAGE TANK VOLUME AND TEMPERATURES AS A FUNCTION OF STORED BORIC ACID CONCENTRATION.........

3/4 1-13 3.1-2 CEA INSERTION LIMITS.....................................

3/4 1-24 3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS...............

3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSSOUTOFSERVICE).......................

3/4 2-8 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING........................

3/4 3-40 4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA...................

3/4 4-15a 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT...........................................

3/4 4-26 3.4-2 RCS HEATUP PRESSURE / TEMPERATURE LIMITATIONS FOR 4-8 EFPY.............................................

3/4 4-29 3.4-3 RCSC00LDOWNPRESSURE/TEMPERATUkELIMITATIONSFOR 4-8 EFPY.................................................

3/4 4-30 3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE............

3/4 7-6A 5.1-1 EXCLUSION AREA...........................................

5-2 5.1-2

. LOW POPULATION 20NE......................................

.5-3 5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS......................

5-4 5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS.......................

5-5 5.6-1 UNITS 2 & 3 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS......................................

5-12 5.6-2 UNIT 1 FUEL MINIMUM BURNUP VS, INITIAL ENRICHMENT FOR REGION II RACKS......................................

5-13 5.6-3 FUEL STORAGE PATTERNS FOR REGION II RACKS................

5-14 5.6-4.

FUEL STORAGE PATTERNS FOR REGION II RACKS 1

RECONSTITUTION STATI0N...................................

5-15 6.2-1 0FFSITE ORGANIZATION.....................................

6-2 6.2-2 UNIT ORGANIZATION........................................

6-3 6.2-3 CONTROL ROOM AREA........................................

6-4a SAN ON0FRE-UNIT 2 XXI AMENDMENT NO. 87

~

. ~.

PLANT SYSTEMS ATMOSPHERIC DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.6 The atmospheric dump valves shall be OPERABLE.

}

APPLICABILITY:

MODES 1, 2, 3, and 4*.

ACTION:

a.

With an atmospheric dump valve inoperable, restore the valve 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 STAND 8Y within 4

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 and on shutdown cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With both atmospheric dump valves inoperable, be in at least l

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 and on shutdown cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With the backup nitrogen gas system capacity less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, c.

restore the backup nitrogen gas system capacity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the ADV inoperable.

d.

The provisions of Specification 3.0.4 are not applicable for MODES 2, 3 and 4* with only one atmospheric dump valve inoperable.

SURVEILLANCE REQUIREMENTS 4.7.1.6.1 Each atmospheric dump valve shall be determined OPERABLE at least once per REFUELING INTERVAL by:

a.

Verifying that each atmospheric dump valve will open in modulate mode using the backup nitrogen system, b.

Verifying that each atmospheric dump valve will close to its isolation position upon a MSIS test signal, c.

Verifying that each atmospheric dump valve will open in modulate / override mode with a MSIS test signal present, and d.

Verifying that local manual operation will fully open and close each atmospheric dump valve.

4.7.1.6.2 Verify at least once per 7 days that the backup nitrogen gas system capacity will provide a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of pneumatic operation for each atmospheric dump valve.

4.7.1.6.3 The atmospheric dump valves shall be determined OPERABLE as required per Specification 4.0.5.

l

• When steam generators are being used for decay heat removal.

SAN ONOFRE-UNIT 2 3/4 7-9a AMENDMENT NO. 89

l r,

. PLANT SY$fEMS 3/4.7.2 STEAM CEN[RATOR PRES $URE/TEMPlu TURE LIMITATION LIMIT MG CONDITION FOR OPf M TION 3.7.2 The tempratures of both the primar steam generaters shall be greater than 70'y and secondary coolants in the F when the ptessure of either cool-ant in the steam generator is greater than 200 psig.

APPLICAB!t!TY:

At all times.

d ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam onerator pressur*e of the applicable side to less than or equal to 00 psig within 30 minutes, and b.

Perform an engineering evaluation to detemine the effect of the overpressurization on the structural integrity of the steam generator.

Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200'F.

SURVE!LLANCE REQUIREM[NTS t

4.7.2 The pressure in each side of the steam generators shall be detemined to be less than 200 psig at least once~ per hour when the temperature of either the primary or secondary coolant is less than 70'F.

O O

e i

e' e

SAN ONOFRE-UNTT 2 3/4 7-10

PLANT SYSTEMS

\\

BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in j

1 the steam generator of the affected steam line and a concurrent loss of offsite electrical power.

These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 MAIN STEAM LINE !$0LATION VALVE The OPERABILITY of the main steam line isolation valver ensures that no more than one steam generator will blowdown in the event of a steam line rupture.

This restriction is required to 1) minimize the positive reactivit effects of the Reactor Coolant System cooldown associated with the blowdown,y and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.

The OPERABILITY of the main steam isolation i

valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident. analyses.

3/4.7.1.6 ATMOSPHERIC DUMP VALVES i

The Atmospheric Dump Valves (ADVs) provide a safety grade method for cooling the plant to the shutdown cooling entry conditions should the l

preferred heat sink via the Steam Bypass System to the condenser not be available.

This is done in conjunction with the Auxilidry Feedwater System providing a safety grade source of cooling water frer the condensate storage tanks.

The ADVs are equipped with pneumatic contro11erc to permit control of the cooldown rate.

The controllers provide both automaue and manual ADV 1

operating modes.

The ADVs are used during normal plant startups and cooldowns when either a vacuum in the condenser or the Steam Bypass Control System is not available.

The ADVs are capable of being o Control Room or the Remote Shutdown Panel (perated remotely from either the L-042), and locally with manual handwheels.

However, controlling the ADVs from the Remote Shutdown Panel is not credited in the Safety Analyses.

Operating the ADVs during design bases

)

events from the Remote Shutdown Panel is not a criteria for determining ADV operability.

Two ADVs are provided to meet single failure assumptions followin rendering one steam generator unavailable for Reactor Coolant System (g an event RCS) heat removal.

In the accident analysis, the ADVs are not assumed to be used until the operator takes action to cool down the plant.

This is typically 30 minutes following initiation of an event.

The limiting events are those which render one steam generator unavailable for RCS heat removal, with a coincident loss of offsite power.

Typical initiating events falling into this category are a main steam line break (MSLB) upstream of the main steani isolation valves, a feedwater i

line break (FWLB), and a steam generator tube rupture (SGTR) event.

SAN ONOFRE-UNIT 2 B 3/4 7-3 AMENDMENT NO. 89

PLANT SYSTEMS BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued)

At least one ADV is required to conduct a plant cooldown following an event in which one steam generator and the condenser become unavailable.

Failure to meet the LCO can result in the inability to cool the plant to shutdown cooling entry conditions following an* event in which the condenser is unavailable for use with the Steam Bypass system. The ADVs are required to be OPERABLE whenever the steam generators are being used for RCS heat removal.

In these MODES they provide the safety grade path for cooling the RCS to shutdown cooling entry conditions.

The ADVs are normally operated from the plant non-safety instrument air supply.

A Seismic Category I Pressurized Gas Supply, which consists of bottled nitrogen, is provided to the ADvs on loss of instrument air.

The bottled nitrogen pressure is read locally, and it is nct.larmed in the control room.

The backup nitrogen capacit minimum accumulator pressure of 1050 psig.y surveillance 4.7.1.6.2 requires a This pressure includes allowances for seven days worth of leakage and uncertainty in the nitrogen consupation rates.

The value represents enough backu at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of pneumatic operation. p nitrogen gas for each ADV to have SDC) conditions d This is based on the time needed to reach shutdown cooling (istent and conservative relative to the Units 2 and 3 uring a small break loss-of-coolant accident.

This is cons Emergency Operating Instructions.

The ADVs are one of the systems required to meet Branch Technical Position (BTP) RSB 5-2, Design Requirements of the Residual Heat Removal System conditIonstocoldshutdown.and 10 CFR 50, Appendix R for taking the plant from normal operating Units 2 and 3 have both met the requirements for Class 2 plants under BTP RSB 5-1 usinbV in sufficient for cooling down to $DC two ADVs.

For the RSB 5-1 scenario 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of backup nitrogen for each A conditions without a 4-hour hold.

For either longer term cooldowns or for shutdownfromoutsidetheControlRoomwheretheADVswouldberequIred,the local manual op'erating capability can be used.

The February 24 1988 NRC letter on the Safet EvaluationoftheNaturalCirculationCooldowntestsat SONGS Units 2 and 3,y' acknowledges in Paragraph g:

"That the atmospheric dump valves could be manually operated in the event the nitrogen supply to these valves should become depleted."

Surveillance of the ADVs using the nitrogen backup capability and the 7-day minimum backup nitrogen pressure surveillance requirement provides adequate assurance that the ADys and the nitrogen backup system remain operable.

In addition, handwheels are provided for local manual operation for each ADV.

This redundancy ensures that the Reactor Coolant System can be cooled down such that the Sht.tdown Ccoling System can be placed in service.

To perform a controlled cooldown of the RCS, the ADVs must be able to be opened and throttled through their full opening range from either the Control Room or the local handwheel. The surveillt.nce requirements ensure that the ADVs are tested through a full control cycle at least once per fuel cycle.

As the ADVs are subject to inservice testing per Surveillance 4.7.1.6.3, the frequency of Surveillance 4.7.1.6.1 is based on the length of a fuel cycle.

SAN ONOFRE-UNIT 2 B 3/4 7-3a AMENDMENT NO.89

PL' ANT SYSTEMS kSES 3/4.7.1.6 ATNOSPNERICDUMPVALVES(Continued)

The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not apply when only one ADV is inoperable, and the ADV can be made OPERABLE yithin the allowed action times.

However, with two inoperable ADys the plant must be placed on shutdown cooling.

Therefore, the provisions of Specification 3.0.4 i

do apply with two inoperable ADVS, 3/a.7.2 STEAM GENERATOR PRES $URE/ TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maxieum allowable fracture toughness stress limits.

The limitations of 70'F and 200 psig are based on a steam generator RTMT of 30'F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT C0OLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that suf-ficient cooling cenacity is available for continued operation of safety related equipment during n " mal and accident conditions. The redundant cooling capacity of this syntes se sing a sin

?/t analyses.gle failure, is consistent with the assumptions used in the att 3/4.7.4 SALT WATER COOLING SYSTEM The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is available for continued operation of equipment during nor -

mal and accident conditions.

The redundant cooling capacity of this system, assuming a sin dent analyses.gle failure, is consistent with the assumptions used in the acci-SAN ONOFRE-UNIT 2 B 3/4 7-3b AMENDMENT NO. 89

.. 's

1 PLANT SYSTEMS BASES 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures i

that 1) the ambient air temperature does not exceed the allowable temperature for continuous dut this system and 2)y rating for the equipment ahd instrumentation cooled by the control room will remain habitable for operations personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix A, 10 CFR 50.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters, f

if 4

SAN ONOFRE-UNIT 2 B 3/4 7-4

F

' g NUCLEAR REGULATORY COMMISSION t

wAsMiwotoN,0, C. 20666 f

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVER $1DE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 79 License No. NPF-15 1.

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

A.

The applications for amendment to the license for San Onofre NuclearGeneratingStation, Unit 3'(thefacility)filedby SouthernCaliforniaEdisonCompany(SCE)onbehalfofitself andSanDiegoGasandElectricCompanylifornia(licensees) the City of Riverside, California and the City of Anaheim, Ca dated August.18, 1989 and supplemented May 31, 1990 complies with the standards and req)uirements of the Atomic Energy Act of 1

1954, as amended (the Act, and the Comission's regulations i

set forth in 10 CFR Chapter I; B.

The facility will o)erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of tie Comission; C.

Thereisreasonableassurance(i)thattheactivitiesauthor-ized 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require-ments have been satisfied, u

s

,y- -

'r---e

- * + -

,s.*4+

w.i

.. =

~

_. =

.?,

2 2.

Accordingly, the license is amended by changes to the Technical Specifi-i cations as indicated in the attachment to this license amendment, and j

paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby i

amended to read as follows:

1 1

(2) Technical Specifications The Technical Specifications contained in Appendix A, and i

the Environmental Protection Plan contained in Appendix B.

as revised through Amendment No. 79. are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and I

must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h

lY

(,4ohn T. Larkins, Acting Director i

'TV Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications i

Date of Issuance: July 10, 1990 4

l L

r

,4

-~

ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 i

Revise Appendix A Technical Specifications by removing the pages identified i

below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Also enclosed are the following overleaf pages to the amended pages.

AMENDMENT PAGE OVERLEAF PAGE VI V

XI XII 3/4 7-10a B 3/4 7-3 B 3/4 7-3a B 3/4 7-3b B 3/4 7-4

+

,3

~

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REOUIREMENTS l

SECTION PAGE HOT SHUTD0WN............................................

3/4 4 3 COLD SHUTDOWN - LOOPS FI LLED.........'...................

3/4 4-5

[

COLD SHUTDOWN - LOOPS NOT FILLED........................

3/4 4-6 3/4.4.2 S AFETY VALVES - 0PERATING...............................

3/4 4-7 3/4.4.3 PRESSURIZER.............................................

3/4 4 8 3/4.4.4 STEAM GENERATORS........................................

3/4 4 9 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS.................

3/4 4-17 OPERATIONAL LEAKAGE..........r............

3/4 4-18 3/4.4.6 CHEMISTRY...............................................

3/4 4 21 3/4.4.7 SPECIFIC ACTIVITY.......................................

3/4 4 24 i

3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR'C00LANT SYSTEM...............................

3/4 4-28 PRESSURIZER - HEATUP/C00LDOWN........................

3/4 4-32 OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE < 302'F......................

3/4 4-33 RCS TEMPERATURE F 302'F......................

3/4 4 35 1

3/4.4.9 STRUCTURAL INTEGRITY....................................

3/4 4-36 3/4.4.10 REACTOR COOLANT GAS VENT SYSTEM.........................

3/4 4-37 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS..................................

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg,>,350'F..........................

3/4 5 3 3/4.5.3 ECCS SUBSYSTEMS - T3y,<350*F..........................

3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK............................

3/4 5-8

-i SAN'ONOFRE - UNIT 3 V

AMEN 0 MENT NO. ?! DEC 141989

t INDEX i

LIMITINF CONDITIONS FOR OPEPATION AND SURVEILLANCE REQUIREMENTS l

1.

l l

SECTION PAGE 3/4.6 CONTAIRMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY................................

3/4 6-1 I

CONTAINMENT LEAKAGE..................................

3/4 6-2 CONTAINMENT AIR L0CKS................................

3/4 6-5 INTERNAL PRESSURE....................................

3/4 6-7 AIR TEMPERATURE......................................

3/4 6-8

{

CONTAINMENT. STRUCTURAL INTEGRITY.....................3/4 6-9 CONTAINMENT VENTILATION SYSTEM.......................

3/4 6-14 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM.............................

3/4 6-15 10 DINE REMOVAL SYbTEM................................

3/4 6-17 CONTAINMENT COOLING SYSTEM...........................

3/4 6-18 3/4.6.3 CONTAINMENT ISOLATION VALVES............................

3/4 6-19 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN M0NITORS....................................

3/4 6-27 ELECTRIC HYDROGEN REC 0MBINERS........................

3/4 6-28 CONTAINMENT DOME AIR CIRCULAT0RS.....................

3/4 6-29 i

3/4.7 PLANT-SYSTEMS 3/4.7.1 TURBINE CYCLE i

SAFETY VALVES........................................

3/4 7-1 AUXILIARY FEEDWATER SYSTEM...........................

3/4 7-4 CONDENSATE STORAGE TANKS.............................

3/4 7-6 i

ACTIVITY.............................................

3/4 7-8 MAIN STEAM LINE ISOLATION VALVES.....................

3/4 7-10 ATMOSPHERIC DUMP VALVES..............................

3/4 7-10a-SAN ONOFRE - UNIT 3 VI AMENDMENT NO. 79

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM..........................

3/4 7-12 3/4.7.4 SALT WATER COOLI NG SYSTEM...............................

3/4 7-13 3/4.7.5 CONTROL 900M EMERGENCY AIR CLEANUP SYSTEM...............

3/4 7-14 3/4.7.6

$NU8BERS................................................

3/4 7-17 3/4.7.7 SEALED SOURCE CONTAMINATION.............................

3/4 7-25 3/4.7.8 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM........................

3/4 7-27 SPRAY AND/0R SPRINKLER SYSTEMS.......................

3/4 7-30 FIRE HOSE STATIONS...................................

3/4 7 33 3/4.7.9 FIRE RATFD ASSEMBLIES.....,.............................

3/4 7-35 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING............................................

3/4 8-1 SHUTD0WN.............................................

3/4 8-8 4

3/4.8.2 0.C. SOURCES OPERATING............................................

3/4 8-9 SHUTD0WN.............................................

3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OPERATING............................................

3/4 8-13 SHUTD0WN.............................................

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.................................

3/4 8-16 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS.............................................

3/4 8-31 i

i SAN ONOFRE-UNIT 3 VII

INDEX LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING _0PERATIONS 3/4.9.1 80RON CONCENTRATION.....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 i

3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4 9-4 3/4.9.5 COMMUNICATIONS..........................................

3/4 9-5 3/4.9.6 REFUELING MACHINE.......................................

3/4 9-6 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING 3/4 9-7 3/4.9.8 SHUT 00WN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL...........

3/4 9-8 LOW WATER LEVEL......................................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM...................... 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................

3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE P00L..............................3/4 9-12 s

3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM...............................................

3/4 9-13 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION....................

3/4 9-16 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOWN MARGIN.........................................

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS............................

3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS..............................-....

3/4 10-3 3/4.10.4 CENTER'CEA MISALIGNMENT AND REGULATING CEA INSERTION LIMITS................................................

3/4 10-4 SAN ONOFRE - UNIT 3 VIII AMENDMENT NO. 77

i INDEX BASES-SECTION PAGE i

3/4.4.4 STEAM GENERATORS......................................

B 3/4 4-2 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE........................

B 3/4 4-4 3/4.4.6 CHEMISTRY.............................................

B 3/4 4-4 3/4.4.7 SPECIFt.C ACTIVITY.....................................

B 3/4 4-5 3/4.4.8 PRESSURE / TEMPERATURE LIMITS...........................

B 3/4 4-6 3/4.4.9 STRUCTURAL INTEGRITY.................................

B 3/4 4-10 3/4.4.10 REACTOR COOLANT GAS VENT SYSTEM.......................

B 3/4 4-10 3/4.5 EMERGENCY CORE COOLING SYSTEMS i

3/4.5.1 SAFETY INJECTION TANKS................................

B 3/4 5-1 i

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.....,......................

B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK.........................

B 3/4 5-2 3/4.6 CONTAININMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT....................

B 3/4 6-1 l

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS..................

B 3/4 6 3 3/4.6.3 CONTAINMENT ISOLATION VALVES..........................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...............................

B 3/4 6-5 3/4.7 PLANT SYSTEMS j

i 3/4.7.1 TURBINE CYCLE.........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE /TEarERATURE LIMITATION.......

B 3/4 7-3b

'3/4.7.3-COMPONENT COOLING WATER SYSTEM........................

B 3/4 7-3b 3/4.7.4 SALT WATER COOLING SYSTEM.............................

B 3/4 7-3b 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM.............

B 3/4 7-4 3/4.7.6 SNUBBERS.............:................................

B 3/4 7-5 3/4.7.7 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-6 3/4.7.8 FIRE SUPPRESSION SYSTEMS..............................

B 3/4 7-6 3/4.7.9 FIRE RATED ASSEMBLIES.................................

B 3/4 7 SAN ONOFRE - UNIT 3 XI AMEN 0 MENT NO. 79

y INDEX

/

tBASES SECTION PAGE

~3/4.8' ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTERS................

B 3/4 8-1 i

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...............

B 3/4 8-3 c

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORONCONC;":iMTION...................................

B 3/4 9-l' 3/4,9.2-INSTRUMENTATION.......................................

B 3/4 9-1 3/4.9.3 DECAY TIME............................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.....................

B 3/4 9-1 3/4.9.5' COMMUNICATIONS.................(......................-

B 3/4 9-1 4

3/4.9.6:

REFUELING MACHINE.....................................

B 3/4 9-2 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING...

B 3/4 9-2

'3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION..............

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM....................

B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL.........................................

B 3/4 9-3 1

3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM..............................................

B 3/4 9-3 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION...................

B 3/4 9,

. 3/4.10 SPECIAL. TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................-

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.

B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................

B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT AND REGULATING CEA INSERTION LIMITS..............................................

B 3/4 10-1 S.jNONOFRE-UNIT 3 XII AMENDMENT NO 77 1

INDEX LIST OF FIGURES

' FIGURE PAGE 3.1-1

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

3/4 1-13 i

3.1-2 CEA INSERTION LIMITS VS FRAC P0WER....................... TION OF 6LLOWABLE THERMAL 3/4 1-24 L

3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS..............

3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)......................

3/4 2-8 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING.......................3/4 3-40 4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA..................

3/4 4-16 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE o

EQt:IVALENT I-131...............'........................

3/4 4-27 3.4-2 HEATUP RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS...............................................

3/4 4-30 3.4-3 000LDOWN RCS PRESSURE / TEMPERATURE LIMITATION 0-5 YEARS...................................S FOR 3/4 4-30a 3.4-4 RCS PRECSUt m EMPERATURE LIMITATIONS FOR 4-8 EFPY.......

3/4 4-31 3.4-5 RCS PRl!S. 4/ TEMPERATURE LIMITS MAXIMUM ALLOWABLE C00LD0'l M" !S (4-8 EFPY)...............................

3/4 4-31a 3.7-1 MINDi M MQUIPb iLOWATER INVENTORY FOR TANK T-121 FOR MAXIM e " 'F R ' Mu TO D ATE..........................

3/4 7-7 5.1 EXCL(.,u: 4EA.

5-2 5.1-2 LOW PLH W 104 rdE.....................................

5-3 5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS.....................

5-4 5.1_4 SITE BOUNDARY FOR LIQUID EFFLUENTS......................

5-5 5.6-1 UNITS 2 AND 3 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS..........................

5-12 5.6-2 UNIT 1 FUEL MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION II RACKS..........................

5-13 5.6-3 FUEL STORAGE PATTERNS FOR REGION II RACKS...............

5-14 SAN ONOFRE - UNIT 3 XVII AMENDMENT NO. 77

T.:.,

j INDEX LIST OF TABLES

.1 TABLE MEl 1.1 OPERATIONAL M0 DES..........................................

1-7

1. 2 FREQUENCY N0TATION.....................'.....................

18 2.2-1 REACTOR PRDTDfG INSTRUMENTATION TRIP SETPOINT LIMITS....

2-3 2.2-2 CORE PRCTECT!ON CALCULATOR ASSPESSABLE CONSTANTS...........

2-5 3.3-1 RE!,tTOR. PROTECTIVE INSTRUMENTATION.........................

3/4 3-3 3.3*2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES..........

3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURV REQUI REMENTS............................EI LLANCE 3/4 3 10 3.3-3 ENGINEERED SAFETY FEATURES ACTUATI INSTRUMENTATION....................ON SYSTEM

(........................

3/4 3-14 v>

r

'3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES........................'........

3/4 3-22 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES..................

3/4 3-27 e

4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................. 3/4 3-31 3.3-6 RADIATION MONITORING ALARM INSTRUMENTATION.................

3/4 3-35

+

t 4.3-3 RADIATION MONITORING INSTRUMENTATION SURV REQUIREMENTS.............................EILLANCE 3/4 3-38 3.3-7 SEISMIC MONITORING INSTRUMENTATION.........................

3/4 3-43 i

4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................

3/4 3-44 3.3-8 METEOROLOGICAL' MONITORING INSTRUMENTATION..................

3/4 3-46 4.3-5 METEOROLOGICAL MONITORING INSTAUMENTATION SURVEILLANCE REQUIREMENTS...............................................

3/4 3-47 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION.................

3/4 3-49 4.3-6 REMOTE SHUTDOWN MONI'LRING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................................'..............

3/4 3-E0 3.3-10 ACCIDENT MONITORING INSTRUMENTATION........................

3/4 3-5 SAN ONCFRE-UNIT 3 XVIII

21j j

i INDEX LIST OF FIGURES l

a FIGURE-PAGE 1

L 5.6 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION..................................

5-15 l-L 6.2-1 0FFSITE ORGANIZATION....................................

'6-3

)

L

=6.2-2 UNIT ORGANIZATION.......................................

6-4 F

6.2-3 CONTROL ROOM AREA.......................................

6-6

.1 L

,l v

3_-

Y i

i

>Fii

-p SAN.ONOFRE - UNIT XVIIa AMENDMENT NO.- 77 1

1:

l,

.~. _,-.

L....

}.,

PLANT SYSTEMS ll ATMOSPHERIC DUMP VALVES

[

LIMITING CON 0! TION FOR OPERATION l

3.7.1.6 The atmospheric dump valves shall be OPERABLE.

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

ACTION:

a.

With an atmospheric dump valve inoperable, restore the valve 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 in HOT SHUTDOWN and on shutdown cooling,

+

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With both atmospheric dump valves inoperable, 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 and on shutdown u

cooling within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, With the backup nitro 0en gas system capacity less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, c.

restore the backup nitrogen gas. system capacity within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the ADV inoperable.

d.'

The provisions of Specification 3.0.4 are not applicable for MODES 2,.3, and 4* with only one atmospheric dump valve inoperable.-

SURVEILLANCE REQUIREMENTS 4.7.1.6.1 Each atmospheric dump valve shall be determined OPERABLE at least

't once per REFUELING INTERVAL by:

i a.

' Verifying that each atmospheric dump valve will open in modulate i

mode using the backup nitrogen system, b.

Verifying that each atmospheric dump valve will close to its isolation position upon a MSIS test signal, c.

Verifying that each atmospheric dump valve will open in modulate / override mode with a MSIS test signal present, and d.

Verifying that local manual operation wil1 ~ fully open and close each atmospheric dump valve.

4.7.1.6.2 Verify at least once per 7 days:that the backup nitrogen gas system capacity will provide a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of pneumatic operation for each atmospheric dump valve.

4.7.1.6.3 The atmospheric' dump valves shall be determined OPERABLE as required per Specification 4.0.5.

• When steam generators are being used for decay heat removal.

SAN ONOFRE-UNIT.3 3/4 7-10a AMENDMENT NO. 79

g..,..-

• y' PLANT SYSTEMS-r l

-BASES' J

I 3/4.7.1.4 ACTIVITY-l The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube laak in the steam g m rator of the affected steam line and a concurrent loss of offsite electrical power.

These values are consistent with the assumptions used in the accident _ analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVE The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blow down in the event of a steam line rupture.

This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements is consistent with the assumptions used in the accident analyses.

3/4.7.1.6 ATMOSPHERIC DUMP VALVES The Atmospheric Dump Valves (ADVs) provide a safety grade method for cooling:the plant to the shutdown cooling entry conditions should the preferred heat sink via the Steam Bypass System to the condenser not be available. This is done in conjunction with the Auxiliary Feedwater System providing a safety grade source of cooling water from the condensate storage tanks.

The ADVs are equipped with pneumatic controllers to permit control of the cooldown rate. 'The controllers provide both automatic and manual ADV operating modes, i

The ADVs are used during normal plant startups and cooldowns when either a' vacuum in the condenser or the Steam Bypass Control System is not available. The ADVs are capable of being operated remotely from either the Control Room or the Remote Shutdown Panel (L-042), and locally with manual handwheels.

However, controlling the ADVs from the Remote Shutdown Panel is not credited in the Safety Analyses. Operating the ADVs during design bases events from the Remote Shutdown Panel is not a criteria for determining ADV operability.

Two ADVs are provided to meet single failure assumptions followin rendering one steam generator unavailable for Reactor Coolant System (g an event RCS) heat removal.

In the accident analysis, the ADVs are not assumed to be used until the operator takes action to cool down the plant.

This is typically 30 minutes following initiation of an event.

The limiting events are those which render one steam generator unavailable for RCS heat removal, with a coincident loss of offsite power.

Typical initiating events. falling into this category are a main steam line break (MSLB) upstream of the main steam isolation valves, a feedwater line break (FWLB), and a steam generator tube rupture (SGTR) event.

SAN ON0FRE-UNIT 3 8 3/4 7-3 AMENDMENT NO. 79

PLANT SYSTEMS i.

BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued)

L At least one ADV is required to conduct a. plant cooldown following an event in which one steam generator and the condenser become unavailable.

Failure to meet the LCO can result in the inability to cool the plant to shutdown cooling entry conditions following an event in which the condenser is unavailable for use with the Steam Bypass System.- The ADVs are required to be p

OPERABLE whenever the steam generators are being used for RCS heat removal..

L In these MODES they provide the safety grade path for cooling the RCS to-shutdown cooling entry conditions.

The ADVs are normally operated from the plant non-safety instrument air i

supply. A Seismic Category I Pressurized Gas Supply, which consists of l

bottled nitrogen, is provided to the ADVs on loss of instrument air.

The bottled nitrogen pressure is read locally, and it is not alarmed in the control room.

The backup nitrogen capacity surveillance 4.7.1.6.2 requires a minimum accumulator pressure of 1050 psig.. This pressure includes allowances

-for seven days worth of leakage and uncertainty in the nitrogen consupation rates.

The value represents-enough backup nitrogen gas for each ADV to have l

at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of pneumatic operation.

This is based on the time needed to l

reach shutdown cooling (SDC) conditions during a small break loss-of-coolant I

' accident.

This is consistent and conservative relative to the Units 2 and 3 L

Emergency Operating-Instructions.

-The~ADVs are one of the systems required to meet Branch Technical Position (BTP) RSB 5-1, Design Requirements of the~ Residual Heat Removal i

. System, and 10 CFR 50, Appendix R for taking the plant from normal operating-condit1ons to cold shutdown.

Units 2 and 3 have both met the requirements for Class 2 plants under BTP RSB 5-1 using two ADVs.

For the RSB 5-1 scenario, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of backup' nitrogen for each ADV is sufficient for cooling down to SDC

. conditions'without a 4-hour hold.

For either longer term cooldowns or for shutdown from outside the Control Room where> the ADVs would be required, the t

local manual op'Safeterating capability can be used.

The February 24, 1988, NRC letter on the Evaluation of the Natural Circulation Cooldown Tests at SONGS Units 2 and 3,y' acknowledges in Paragraph g:

i "That the atmospheric dump valves could be manually operated in the event the nitrogen supply to these valves should become depleted."-

Surveillance of the ADVs using the nitrogen backup capability and the

l 7-day minimum backup nitrogen pressure surveillance requirement provides I

adequate assurance that the ADVs and the nitrogen backup system remain operable.

In addition, handwheels are provided for local manual operation for each ADV.

This redundancy ensures that the Reactor Coolant System can be cooled down such that the Shutdown Cooling System can be placed in service.

To perform a controlled cooldown of the RCS, the ADVs must be able to be opened and throttled through their full opening range from either the Control Room or the local handwheel.

The surveillance requirements ensure that the ADVs are tested through a full control cycle at least once per fuel cycle.

As SAN ONOFRE-UNIT 3 B 3/4 7-3a AMENDMENT NO. 79

- 1 o

.c

]

+. PLANT SYSTEMS.

i BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued) the ADVs are subject to inservice testing per Surveillance 4.7.1.6.3, the frequency of Surveillance 4.7.1.6.1 is based on the length of a fuel cycle.

The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not apply

,l

.when only.one ADV is inoperable, and the ADV can be made OPERABLE within the allowed action times.

However, with two inoperable ADVs the plant must be placed on shutdown cooling.

Therefore, the provisions of Specification 3.0.4-4 do apply with two inoperable ADVS,

'3/4.7.2' STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The' limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the l

maximum allowable fracture toughness stress limits.

The limitations of 70*F and 200 psig are based on a steam generator RT of 30'F and are sufficient to prevent brittle fracture, HDT 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the com onent coolin water system ensures that suffi-cient cooling capacity is available for cont nued operation of safety related I

equipment during normal and accident conditions.

The redundant cooling capacity of-this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

~3/4.7.4 SALT WATER COOLING SYSTEM The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions.

The redundant cooling capacity of this system, assuming.

a. single failure, is consistent with the assumptions used in the accident analyses.

l SAN ONOFRE-UNIT 3 B 3/4 7-3b AMENDMENT NO. D

• .- (

PLANT SYSTEMS

'l BASES 3/4.7.5 CONTROL ROOM EMERGENCY AIR CLEANVP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and-instrumentation cooled by this_ system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rom or less whole body, or its equivalent.

This limitation is

consistent with the requirements of General Design Criterion 19 of_ Appendix A, 10 CFR 50.

Cumulative operation of the system with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

I SAN ONOFRE-UNIT 3 8 3/4 7-4 l

.