Text

Amends 87 & 77 to Licenses NPF-10 & NPF-15,respectively, Revising Tech Specs Re Spent Fuel Pool Reracking
	ML20042G264
Person / Time
Site:	San Onofre
Issue date:	05/01/1990
From:	Larkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20042G265	List: ML20042G264; ML20042G266; ML20042G290; ML20043A381;
References
	NUDOCS 9005140021
	Download: ML20042G264 (44)
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[ISOCas UNITED STATES T

.g NUCLEAR REGULATORY COMMISSION

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t wAsMiwoToN, D. C. 20666 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY-THE CITY OF RIVERSIDE CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l

t Amendment No. 87 License No. NPF-10 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 2 (the facility) filed 1

by Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside,) California and the City of Anaheim, California (licensees dated March 10, April 19, May 4, May 19. June 1 June 2 September 22, November 2, November 9, 1989 January 18, February 9, February 16. and March 20, 1990, complIeswith 1

the standards and requirements of the Atomic Energy Act of l

1954, as amended (the Act), and the Commission's regulations L

set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applica-tion, the provisions of the Act, and the regulations of the 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 Commission'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 l-GROS 140021 9005o3 p

ADOCK 05000361 PDC l

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E.

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

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and pararwA 2.C(2) of Facility Operating License No. NPF-10 is hereby amenc y ;o read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 87, 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 must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John T.-Larkins, Acting Director Project Directorate V-Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 1, 1990 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361

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Revise Appendix A Technical Specifications by removing the pages identified-below and inserting the enclosed pages. The revised pages are identified by amendment'nur6er and contain marginal lines indicating the-area of change.

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

AMENDMENT PAGE OVERLEAF PAGE 3/4 9-7 3/4 9-13 3/4 9-13a 3/4 9-14 3/4 9-16 3/4 9-15 B 3/4 9-2 B 3/4 9-1

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B 3/4 9-2a l

B 3/4 9-3 B 3/4 9-4' 5-7 5-7a 5-8 5-12 Figure 5.6-1 5-11(Table 5.7-1) 5-13 Figure 5.6-2 5-14 Figure 5.6-3 5-15 Figure 5.6-4 i

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RErVELING OPERATIONS 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool except for the following four cases:

a.

Spent fuel pool gates shall not be carried at a height greater than 30 inches (elevation 36' 4") over the fuel racks.

b.

Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39' 10") over rack cells which' contain Unit 2 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit-1 fuel assemblies.

I Installation or removal of the cask pool cover over the cask pool c.

with fuel in the cask pool.

The cover, fuel, and racks will be removed from the cask pool on completion of the reracking process.

d.

The lift of construction loads, including the temporary gantry crane and the old and the new fuel storage racks (including lifting equipment and rigging), above the cask pool with the cask pool cover in place and fuel in the cask pool.

This includes temporary storage of these construction loads on the cask pool cover during construction.

These lifts are prohibited prior to a minimum fuel decay time of 88 days for all stored spent fuel assemblies.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

With the requirements of the above specification not satisfied, place the fuel handling machine in a safe condition.

l SURVEILLANCE REQUIREMENTS 4.9.7 Fuel handling machine interlocks and physical stops which prevent fuel handling machine travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to fuel handling

--machine use and at least once per 7 days thereafter during fuel handling i

machine operation.

SAN ONOFRE-UNIT 2 3/4 9-7 AMENDMENT NO. 87

6

.RFFUELING OPERATIONS R'EFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter systems shal1~be OPERABLE.

.^

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

ACTION:

With one fuel handling building post-accident cleanup filter system a.

inoperable, fuel movement within the storage pool or operation of H

fuel handling machine over the storage pool may proceed provided the l

OPERABLE fuel handling building post-accident cleanup filter system is capable for being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.

i b.

With no fuel handling building post-accident cleanup filter system OPERABLE, suspend all operations involving movement of fuel within the storage pool or operation of fuel handling machine over the storage pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERABLE status.

The provisions of Specification 3.0.4 are not applicable, c.

d.

Temporary exception to item (a) and (b) above, applicable only L

during spent fuel pool reracking construction activities:

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With no fuel handling butiding post-accident cleanup filter system OPERABLE, all-spent fpei pool raracking construction activities including continued operation of the fuel handling machine without fuel, cask handling crane or the temporary gantry crane are permitted provided that the irradiated fuel in the storage pools has-decayed for.a minimum of 88 days and that no more than 480 irradiated fuel assemblies are stored in the pools.

Fuel assemblies will only be moved with the post accident cleanup-filter system OPERABLE per a and b above.

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SAN ON0FRE-UNIT 2 3/4 9-13 AMENDMENT NU. 87

REFUELING OPERATIONS

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-SURVEILLANCE REQUIREMENTS (Continued) 1.

Verify that with the system operating at a flow rate of 12925 cfm i 10% and recirculating through the HEPA filters and charcoal adsorbers, the total bypass flow of the system through-the system diverting valves, to the facility vent is less than or equal to 1% when the system is tested by. admitting cold 00P.

at the system intake.

2.

- Verifying that the cleanup filter system satisfies the in place testing acceptance criteria and uses the test procedures of

' Regulatory Positions C.5.a. C.S.c and C.S.d of Regulatory Guide 1.52 Revision 2, March 1978, and the system flow rate is 12925 cfm i 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of-a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1979, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

4.

Verifying a system flow rate of 12925 cfm i 10% during system operation when. tested in accordance with ANSI N510-1975.

I c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal-adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of' Regulatory Guide 1.52, Revision 2, March 1978, meets-the laboratory testing criteria of Regulatory position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d.

At least once per 18 months by:

s 1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less that 7.3 inches i

Water Gauge while operating the system at a flow rate of 12925 cfm i 10%.

2.

Verifying that on a Fuel Handling Isolation (FHIS) test signal, the' system automatically isolates normal ventilation and starts recirculation through the HEPA filters and charcoal adsorber banks.

3.

Verifying that the heaters dissipate 28.7

1.5 kw for E464, 32.3

1.7 kw for E465, and 3.8

0.2 kw for E652 when tested in accordance with ANSI N510-1975 with the measured heater dissipation corrected to correspond to nominal voltage.

SAN ONOFRE-UNIT 2 3/4 9-14 AMENDMENT NO. 26

4 SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling building post-accident cleanup filter systems shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter er charcoal adsorber housings. or (2) following i

painting, fire, or chemical release in any ventilation zone comniunicating with the system by:

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SAN ON0FRE-UNIT 2 3/4 9-13a AMENDMENT NO. 87

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r RE. FUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) i After each' complete or partial replacement of a HEPA filter bank by e.

verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 12925 cfm i 10%.

f.

After each complete or partial replacement of a charcoal adsorber l

bank by verifying that the charcoal adsorbers remove greater than or i

equal to 99.95% of a halogenated hydrocarbon refrigerant test gas l

when they are tested in place in accordance witn ANSI N510-1975 while operating the system at a flow rate of 12925 cfm i 10%.

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4 SAN ONOFRE-UNIT 2 3/4 9-15

3/4.9 REFUELING OPERATIONS 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION l~

3.9.13 The boron concentration in the spent fuel pool shall be maintained at

'a level greater than or equal to 1850 ppm.

Applicability:

With fuel assemblies in the spent fuel pool.

Action:- With the requirenent of the above specification not satisfied:-

Immediately suspend all additions or movement of fuel in the spent fuel pool and take action to restore the boron concentration to a value equal to or greater than 1850 ppm.

1 SURVEILLANCE REQUIREMENTS 4.9.13 A sample of spent fuel pool-water shall be collected and analyzed for boron concentration at least:

l-a.

Once per month and l

b.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to any fuel movement.

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SAN ONOFRE-UNIT 2 3/4 9-16 AMENDMENT NO.87

REFUELING OPERATIONS BkSES 3/4'9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that:

(1) the refueling machine will be used for movement of all fuel assemblies including those with a CEA inserted,-(2) each machine has sufficient load capacity to lift a fuel assembly including those with a CEA, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle utilizing the refueling machine or can be removed without'the associated fuel bundle utilizing the refueling machine auxiliary hoist.

The four finger CEAs are inserted through the upper guide structure with two fingers in each of the two adjacent fuel bundles in the periphery of the core.

The four finger CEAs are either removed with the upper guide structure and lift rig or can be-removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or the refueling machine auxiliary hoist.

Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is accomplished using one of the gripper operating tools.

The coupling and l

uncoupling is verified by weighing the drive shaft extensions.

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

Refueling Operations The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in six L

fuel assemblies, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. - This assumption is based on the calculated results which demonstrate that, with credit taken for the fuel handling building filters, the offsite doses would be well within (less than 25%) the 10 CFR 100 limits.

B.

Spent Fuel Pool Reracking Construction Activities The restriction on movement of heavy loads over spent fuel ensures that in the event a heavy load is dropped:

. SAN ONONFRE - UNIT 2 B 3/4 9-2 AMENDMENT NO. 87 1

3/4.9 REFUELING OPERATIONS BASES ~

l 3 /4. 9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will remain tuberitical during CORE ALTERATIONS, and 2) a uni-form boron concentration it s intained for reactivity control in the water volume having direct access to the reactor vessel.

These limitations are con-sistent with the initial conditions assumed for the boron dilution incident the accident analyses.

K/K conservative allowance for uncertainties.The value o includes a 1% delta Similar1 the baron concentra-tion value of 2350 ppm or greater also includes a conservative uncertainty l

allowance of 50 ppm boron.-

3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures tnat condition of the core. redundant monitoring capability is available to detect changes in 3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior'to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that suffi-cient time has elapsed to allow the radioactive decay;of the short lived fis-sion products.

This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

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L SAN ONONFRE - UNIT 2 B 3/4 9-1 AMENDMENT NO. 61 h i..

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I REFUELING OPERATIONS j

BASES 3/4.9.7= FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING (Continued) 1.

The radiological consequences due to complete rupture of all spent fuel assemblies in the spent fuel pool and the cask pool (480 i

maximum), will remain below (less than 25% of) the exposure limits l

of 10 CFR a minimum.100 for offsite doses as long as spent fuel has received of 88 days decay time.

This analysis takes no credit for-fuel handling building filters (i.e., the fuel handling building hatches are open).

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2.

Any possible distortion of all fuel assemblies and racks'will not result in a critical' array and K will remain less than 0.95, as i

longasfuelisstoredperTechnTN1 Specifications 5.6," Fuel l

i Storage," and 3.9.13, " Spent Fuel Pool Boron Concentration."

l 3/4.9.8 SHUT 00WN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operat'.on ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilutior.-incident and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there is less

'than 23 feet of water above the reactor pressure vessel flange, ensures that a

~

single failure of the operating shutdown cooling loop will not rer, ult in a com-plete loss of decay heat removal capacity.

With the reactor vessel head re-moved and 23 feet of water above the reactor-pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating-shutdown cooling train, adequate time is provided to initiate emer-gency-procedures to cool the core.

SAN ONONFRE - UNIT 2 B 3/4 9-2a AMENDMENT NO. 87

3/4.9 REFUELING OPERATIONS BASES 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION The minimum requirement of 1850 ppm boron ensures that k,ff 5 0.0" in the Region II racks in the event of fuel assembly misloading with an enrichinent/

burnup combination ~not meeting the criterion for storage in Region II.

Calculations show that with 1800 ppm boron the Region II racks can be completely filled with misloaded fresh unshimmed fuel with an assembly average enrichment of up to 4.1 w/o and maintain k,ff 1 0.95, including all uncertainties.

Therefore, 1850 ppm of boron is specified to allow for measurement uncertainty.

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SAN ONONFRE - UNIT 2 B 3/4 9-4 AMENDMENT NO. 87 l

REFUE'ING OFERATIONS L

BASES-j 3/4.9.9' CONTAINMENT PURGE ISOLATION SYSTEM i

l The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the-i containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the-i environment.

3/4.9.10 AND 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STCRAGE POO The restrictions on minimum water level ensure that sufficient water depth is available-to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM The limitations on the fuel handling building post-accident cleanup filter system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERABILITY of-this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

[

An exception to these limitations, the fuel handling building post-accident 1-

' cleanup filter system can be taken out of service during teracking construction activities based on the new limitation of 88 days minimum decay time and limiting the number of spent fuel assemblies to a maximum of 480.

These added limitations ensure that all potential radioactive releases are enveloped by existing accident analysis without regard to the OPERABILITY of this system.

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

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SAN ONONFRE - UNIT 2 B 3/4 9-3 AMENDMENT NO. 87 1

DESIGN FEATURES VOLUME' 5.4.2 The total water and steam volume of the reactor coolant system is 11,800 + 600/-0-cubic feet at a nominal T,yg of 582.1*F.

5. 5 METEOROLOGICAL TOWER 1.0 CATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a.

AK equivalent to less than or equal to 0.95 when flooded with unbN$tedwaterandwhenfullyloadedwithfuelwhichmeetsthe burnup requirement of Technical Specification 5.6.2.

This includes a conservative allowance for uncertainties as described in the UFSAR.

b.

A nominal 10.40 inch center-to-center. distance between fuel assemblies placed in the Region I storage racks and a nominal 8.85 inch center-to-center distance between fuel assemblies placed in the Region II storage racks.

5. 6. 2 The enrichment-fuel assembly discharge burnup shall be above (greater than) the curves shown on Figure 5.6-1, for Unit 2 fuel assemblies, or Figure 5.6-2 for Unit 1 fuel assemblies for unrestricted storage.

1 New cr burned fuel which does not meet the enrichment versus discharge burnup criteria of Figures 5.6-1/5.6-2 may be stored in Region I.

It may also be stored in Region II if all the following conditions are met.

I Fuel Type.1 new or burned fuel which does not meet the

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L criteria of Figures 5.6-1/5.6-2.

'uel Type 2 fuel which does meet the criteria of Figures

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5.6-1/5.6-2.

a.

Fuel Type 1 shall have initial enrichment < 4.1 w/o U-235.

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k SAN ONOFRE-UNIT 2 5-7 AMENDMENT NO. 87

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DESIGN FEATURES 5 6.2 (Continued) b.

Fuel Type I shall be stored in Region II in either (not both simultaneously) a checkerboard pattern or an alternating row pattern per Figure 5.6-3.

Fuel Type 1 shall be separated from Fuel Type 2 by at least one (1) c.

completely empty row of storage cells.

d.

Fuel Type 1 shall not be stored in the same row as Fuel Type 2.

One (1) completely empty row of Region II storage cells shall e.

separate Fuel Type I stored in Region II from fuel storage Region I.

f.

Except for the purposes of a fuel reconstitution station described 1

below (g), Fuel Type 1 and Fuel Type 2 storage arrays shall not l

alternate in Region II.

1 g.

For purposes of fuel reconstitution / inspection work, it is permissible to have the three (3) row (empty every other Fuel Type 1

empty) arrangement of Figure 5.6-4 any where in the Fuel Type 2 storage array.

Additional empty rows are allowed.

This three (3) row pattern may be repeated in the Fuel Type 2 storage array if at least eight (8) rows separate repetitions.

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DRAINAGE I

5.6.3 The spent fuel storage pool is designed and shall be maintained to-prevent inadvertent draining of the pool below the Technical Specification L

3.9.11 value (23 feet above the top of irradiated fuel assemblies seated in p

the storage racks).

-CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.

1 5,7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

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. SAN ONOFRE-UNIT 2 5-7a AMENDMENT NO. 87

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TABLE 5.7-1

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2:

COMPONENT CYCLIC OR TRANSIENT LIMITS 3

og DESIGN CYCLE A

CYCLIC OR OR TRANSIENT a

COMPONENT TRANSIENT LIMIT Reactor Coolant System 500 system heatup and cooldown Heatupcgcle-T from < 200*F i

cycles at rates < 100*F/hr.

to > 545 F; coo 183Sn cycle -

N T,,9 from > 545'F to < 200*F.

500 pressurizer heatup and Heatup cycle -. Pressurizer temperature-cooldown cycles at rates from < 200*F to > 653*F; cooldown

_ 653'F to _< 200'F i

_ 200*F/hr.

i 10 hydrostatic testing cycles.

RCS pressurized to 3125 psia with RCS temperature in accordance with

-l Specification 3.4.8.

T 200 leak testing cycles.

RCS pressured to 2250 psia with RCS temperature greater than minimum for i

m hydrostatic testing, but less than i

minimum RCS temperature.fer critically.

l 200 seismic stress cycles.

Subjection to a seismic event equal to one half the design basis earthquake (DBE).

480 cycles (in any combination)

Trip from 100% of RATED THERMAL 3

t of reactor trip, turbine trip power; turbine trip (total with delayed reactor.~ trip, load rejection) from 100% of or complete loss of forced RATED THERMAL POWER followed 8

-reactor coolant' flow.

by resulting reactor trip; simultaneous loss of all Reactor-Coolant Pumps at 100% of RATED THERMAL POWER.

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COMPONENT CYCLIC-OR TRANSIENT LIMITS i

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CYCLIC OR DESIGN CYCLE L

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COMPONENT TRANSIENT LIMIT OR TRANSIENT.

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P Pressurizer Spray System Calculational Method:

l 1.

The spray cycle is defined as any initiation and termination of main.or auxiliary spray flow through the pressurizer spray nozzle.

I 2.

If the maximum temperature difference between the pressurizer and the pressurizer spray during the spray cycle exeeds 200*F, each spray cycle and w

g the corresponding temperature difference is logged.

'3.

The spray system tisage factor is calculated as follows:

A.

Fill in Column "N" above.

8.

Calculate "N/N " (Divide N and N ).

g g

C.

Add Column "N/N " to find IN/N.

This total is the cumulative

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g usage factor.

4.

A.

If the cumulative usage factor is equal to or less than 0.65 no further action is required..

m5 B.

If the cumulative usage factor exceeds 0.65, subsequent pressurizer spray 4

operation shall continue to be monitored and an engineering evaluation'of spray system fatigue shall be performed within 90 days.

The evaluation P

shall determine that the spray system remains acceptable for additional 2

service beyond the 90 day period or subsequent spray operation shall be' restricted so that the maximum temperature difference between pressurizer and pressurizer spray during the spray cycle 5, hall be limited to less than or equal to 200*F.

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U-236 ENRICalENT '(t/0) l.

SAN ONOFRE NUCLEAR GENERATING STATION Units 2 & 3 UNITS 2 & 3 FUEL I

MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 11 RACKS FIGURE 5.61 SAN ON0FRE-UNIT 2 5-12 AMENDMENT NO. 87

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SAN ONOFRE NUCLEAR GENERATING STATION ~

L Uniu 2 & 3 UNIT 1 FUEL MINIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 11 RACKS FIGURE 5.6 2 L

SAfl Ofl0FRE.UfJIT 2 5-13 AMEllDMEf4T f40. 87

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_O Type 1 Fuel SAN ONOFRE NUCLEAR GENERATING STATION Units 2 & 3 Empty Storage Location FUEL STORAGE PATTERNS FOR REGION 11 RACKS FIGURE 5.6-3 SAf1 Of40FRE-UfJIT 2 5-14 AMEf10MEfJT fJ0. 87

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UNITED STATES E

g NUCLEAR REGULATORY COMMISSION q

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WASHING TON, D. C. 20666

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1 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 NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 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 Nuclear Generating Station, Unit 2 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Com)any, the City of Riverside,) California and the City of Analeim.-California (licensees dated March 10, April 19, May 4 June-2, September 22, November 2, November $,May19. June 1, 1989, and January 18 -February 9, February 16, and March'20, 1990, complies with the standards and requirements of the~ Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; 3

.B.

The facility will operate-in conformity with the applica-tion, the provisions of the Act, and.the regulations of the Commission; 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; 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 i

L -

l

2 E.

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

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2)ofFacilityOperatingLicenseNo.NPF-15ishereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

77, are hereby incorporated in the license.

SCE shall operate the facility in accordance with the Technical Specifications and the Envia:imental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION fb John T. Larkins, Acting Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 1, 1990

1 ATTACHMENT TO LICENSE AMENDMENT NO. 77 FACILITY OPERATING LICENSE NO. NPT-1,5 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified b amendm' int number and contain marginal lines indicating the area of change. y Also enclosed are the following overleaf pages to the amended pages.

AMENDMENT PAGE OVERLEAF PAGE 3/4 9-7 3/4 9-13 3/4 9-13a 3/4 9-14 3/4 9-16 3/4 9-15 i

B 3/4 9-2 B 3/4 9-1 B 3/4 9-2a B 3/4 9-3 B 3/4 9-4 5-7 5-7a 58 5-12 Figure 5.6-1 5-11 (Table 5.7-1) 5-13 Figure 5.6-2 5-14 Figure 5.6-3 5-15 Figure 5.6-4 t

y

l REFUELING OPERATIONS 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool except for the following four cases:

Spent fuel pool gates shall not be carried at a height greater than a.

30 inches (elevation 36' 4") over the fuel racks.

b.

Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39' 10") over rack cells which contain Unit 3 fuel assemblies or greater than 30 feet 8 inches (elevation 64' 6") over rack cells which contain Unit 1 fuel assemblies.

Installation or removal of the cask pool cover over the cask pool c.

with fuel in the cask pool.

The cover, fuel, and racks will be removed from the cask pool on completion of the reracking process.

The lift of construction loads, including the temporary gantry crane d.

and the old and the new fuel storage racks (including lifting equipment and rigging), above the cask pool with the cask pool cover in place and fuel in the cask pool.

This includes temporary storage of these construction loads on the cask pool cover during construction.

These lifts are prohibited prior to a minimum decay time of 88 days for all stored fuel assemblies.

APPLICABILITY: With fuel assemblies in the storage poel.

ACTION:

With the requirements of the above specification not satisfied, place the fuel handling machine in a safe condition.

l SURVEILLANCE REQUIREMENTS l

4.9.7 Fuel handling machine interlocks and physical stops which prevent fuel handling machine travel with loads in excess of 2000 pounds over fuel assem-blies shall be demonstrated OPERABLE within 7 days prior to fuel handling machine use and at least once per 7 days thereafter during fuel handling machine operation.

SAN ONOFRE - UNIT 3 3/4 9-7 AMEN 0 MENT NO. 77

REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter s" stems shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

With one fuel handling building post-accident cleanup filter system a.

inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the OPERABLE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filter and charcoal sbsorbers, b.

With no fuel handling building post accident cleanup filter system OPERABLE, suspend all operations involving movement of fuel within the storage pool or operation of fuel handling machine over the storage pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERABLE status, c.'

The provisions of Specification 3.0.4 are not applicable, d.

Temporary exception to item (a) and (b) above, applicable only during spent fuel pool teracking construction activities:

With no fuel handl$ng building post-accident cleanup filter system OPERABLE, all spent fuel pool reracking construction activities including continued operation of the fuel handling machine without fuel, cask handling crane er the temporary gantry crane are permitted provided that the irradiated fuel in the storage pools has decayed for a minimum of 88 days and that no more than 480 irradiated fuel assemblies are stored in the pools.

Fuel assemblies will only be moved with the post accident cleanup filter system OPERABLE per a and b above.

SAN ONOFRE - UNIT 3 3/4 9-13 AMENDMENT NO. 77

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling building post accident cleanup filter systems shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

l t

l l

l SAN ONOFRE - UNIT 3 3/4 9-13a AMENDMENT NO.77 h

i

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) l 1.

Verifying that with the system operating at a flow rate of i

12925 cfm i 10% and recirculating through the HEPA filters and charcoal adsorbers, the total bypass flow of the system through the system diverting valves, to the facility vent is less than or equal to 1% when the system is tested by admitting cold DOP at the system intake.

9 2.

Verifying that the cleanup filter system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C 5.c and C.5.d of Regulatory Guide 1.52. Revision 2, March 1978, and the system flow rate is 12925 cfm i 10%.

3.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

4.

Verifying a system flow rate of 12925 cfm i 10% during system operation when tested in accordance with ANSI N510-1975.

Af ter every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying c.

within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, d.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.3 inches Water Gauge while operating the system at a flow rate of 12925 cfm i 10%.

2.

Verifying that on a Fuel Handling Isolation (FHIS) test signal, the system automatically isolates normal ventilation and starts recirculation through the HEPA filters and charcoal adsorber banks.

3.

Verifying that the heaters dissipate 28.7 1 1.5 kw for E464, 32.3 i 1.7 kw for E465, and 3.810.2 kw for E652 when tested in accordance with ANSI N510-1975 with the measured heater dissipation corrected to correspond to nominal voltage.

SAN ONOFRE - UNIT.3 3/4 9-14 AMENDMENT NO. 15

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)

After each complete or partial replacement of a HEPA filter bank by e.

i verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 12925 cfm i 10%.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1976-while operating the system at a flow rate of 12925 cfm i 10%.

h i

SAN ONOFRE-UNIT 3 3/4 9-15

l 3/4.9 REFUELING OPERATIONS 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.13 The boron concentration in the spent fuel pool shall be maintained at a level greater than or equal to 1850 ppm.

Applicability:

With fuel assemblies in the spent fuel pool.

Action:

With the requirement of the above specification not satisfied:

Immediately suspend all additions or movement of fuel in the spent fuel pool and take action to restore the boron concentration to a value equal to or praater than 1850 ppm.

SURVEILLANCE REQUIREMENTS 4,9,13 A sample of spent fuel pool water shall be collected and analyzed for boron concentration at least:

a.

Once per month and b.

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to any fuel movement.

SAN ONOFRE - UNIT 3 3/4 9-16 AMENDMENT NO. 77

i 3/4.9 REFUELING OPERATIONS l

l BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will remain suberitical during CORE ALTERATIONS, and

2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses. The value of 0.95 or less for K includes a 1% delta K/K conservative allowance for uncertainties. SimilarlyIg(heboron concentration value of 2350 ppe or greater also includes a conservative l

uncertainty allowance of 50 ppm boron.

3/4.9.2 INSTRUMEN7ATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

~3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressuritation potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

SAN ONOFRE - UNIT 3 8 3/4 9-1

/dENDMENT tip 50

.. ~ - __...

. REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that:

(1) the refueling machine will be used for movement of all fuel assemblies including those witha a CEA inserted, (2) each machine has sufficient load capacity to lift a fuel assembly including those with a CEA, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle utilizing the reteatirg machine or can be removed without the associated fuel bundle utili.

4 the refueling machine auxiliary hoist.

The four finger CEAs are inserted through the upper guide structure with two fingers in each of.the two adjacent fuel bundles in the periphery of the core. The four finger CEAs are either removed with the upper guide structure and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or the refueling machine auxiliary hoist.

Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is accomplished using one of the gripper operating tools.

The coupling and uncoupling is verified by weighing the drive shaft extensions.

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

' Refueling Operation The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in six fuel assemblies, and (2) any possible distortion of fuel in the storage racks will not resrlt in a critical array.

This assumption is based on the calculated results which demonstrate that, with credit taken for the fuel handling building filters, the of fsite doses would be well within (less than 25%) the 10 CFR 100 limits.

B.

Spent Fuel Pool Reracking Construction Activities The restriction on movement of heavy loads over spent fuel ensures that in the event a heavy load is dropped:

SAN ONOFRE - UNIT 3 B 3/4 9-2 AMENDMENT NO. 77

REFUELING OPERATIONS BASES 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING (Continued) 1.

The radiological consequences due to complete rupture of all spent fuel assemblies in the spent fuel pool and the cask pool (480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses.

This analysis takes no credit for fuel handling building filters (i.e., the fuel handling building hatches are open).

l 2.

Any possible distortion of all fuel assemblies and racks will not l

result in a critical array and K will remain less than 0.95, as longasfuelisstoredperTechn$1 Specification 5.6," Fuel i

Storage," and 3.9.13 " Spent Fuel Pool Boron Concentration."

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and main-tain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a com-plete loss of decay heat removal capacity.

With the reactor vessel head re-moved and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to cool the core.

l l

SAN ONOFRE - UNIT 3 B 3/4 9-2a AMENDMENT NO. 77

REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly.

The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM The limitations on the fuel handling building post-accident cleanup filter system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the i

accident analyses.

An exception to these limitations, the fuel handling building post-accident cleanup filter system can be taken out of service during reracking 4

construction activities based on the new limitation of 88 days minimum decay time and limiting the number _of spent fuel assemblies to a maximum of 480.

These added limitations ensure that all potential radioactive releases are enveloped by existing accident analysis without regard to the OPERABILITY of this system.

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

SAN ONOFRE - UNIT 3 B 3/4 9-3 AMENDMENT NO. 77

3/4.9 REFUELING OPERATIONS I

BASES 3/4.9.13 SPENT FUEL POOL BORON CONCENTRATION The minimum requirement of 1850 ppm boron ensure that K,9f 1 0.95 in the Region 11 racks in the event of fuel assembly misloading with an enrichment /burnup combination not meeting the criterion for storage in Region II.

Calculations show that with 1800 ppm boron the Region II racks can be completely filled with misloaded fresh unshimmed fuel with an assembly average enrichment of up to 4.1 w/o and maintain K Therefore,1850ppmofbor$$i<0.95,includingallii specified to allow for uncertainties.

measurement uncer+

aty.

t

$AN ONOFRE - UNIT 3-B 3/4 9-4 AMENDMENT NO. 77

DESIGN FEA1URES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 11,800 + 600/-0 cubic feet at a nominal T,yg of 582.1'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

A k,ff equivalent to less than or equal to 0.95 when flooded with a.

unborated water, and when fully loaded with fuel which meets the burnup requirement of Technical Specification 5.6.2.

This includes a conservative allowance for uncertainties as described in the UFSAR.

b.

A nominal 10.40 inch center-to center distance between fuel assemblies placed in the Region I storage racks and a nominal 8.85 inch center-to-center distance between fuel assemblies placed in the Region II storage racks.

5.6.2 The enrichment-fuel assembly discharge burnup shall be above (greater than) the curves shown on Figure 5.6-1, for Unit 3 fuel assemblies, or Figure 5.6-2 for Unit I fuel assemblies for unrestricted storage.

New or burned fuel which does not meet the enrichment versus discharge burnup criteria of Figures 5.6-1/5.6-2 may be stored in Region I.

It may also be stored in Region II if all the following conditions are met.

I Fuel Type 1 new or burned fuel which does not meet the

=

criteria of Figures 5.6-1/5.6-2.

Fuel Type 2 fuel which does meet the criteria of

=

7 Figures 5.6 I75.6-2.

Fuel Type 1 shall have initial enrichment 14.1 w/o U-235.

a.

L l

SAN ONOFRE-UNIT 3 5-7 AMENDMENT NO. 77

J DESIGN FEATURES 5.6.2 (Continued) b.

Fuel Type I shall be stored in Region II in either (not both l

i simultaneously a checkerboard pattern or an alternating row pattern per Figure 5.6-3.

{

Fuel Type I shall be separated from Fuel Type 2 by at least one (1) c.

completely empty row of storage cells, d.

Fuel Type 1 shall not be stored in the same row as Fuel Type 2.

One (1) completely empty row of Region 11 storage cells shall e.

separate Fuel Type 1 stored in Region !! from fuel storage Region I.

f.

Except for the purposes of a fuel reconstitution station described below (g), Fuel Type 1 and Fuel Type 2 storage arrays shall not alternate in Region II.

l g.

For purposes of fuel reconstitution / inspection work, it is permissible to have the three (3) row (empty - every other Fuel Type 1 - empty) arrangement of Figure 5.6-4 any where in the Fuel Type 2 storage array.

Additional empty rows are allowed.

This l

three (3) row pattern may be repeated in the Fuel Type 2 storage array if at least eight (8) rows separate repetitions.

DRAINAGE l

5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below the Technical Specification 3.9.11 value (23 feet above the top of irradiated fuel L

assemblies seated in the storage racks).

CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.

5. 7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1' The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

l l

SAN ONOFRE-UNIT 3 5-7a AMENDMENT NO. 77

TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS E

R A

CYCLIC OR DESIGN CYCLE E-COMPONENT TRANSIENT LIMIT OR TRANSIENT l

Reactor Coc.lant System 500 system heatup and coeldoen Heatup cycle - T from t 200*F cycles at rates < 100*F/hr.

to > 545'F; coe183En cycle -

lyfrom>545'Ftoi200*F.

1 500 pressurizer heatup and Meatup cycle - Pressurizer temperature cooldown cycles at rates free < 200*F to > 653*F; coeldoen j

$ 200*F/hr.

> 653'F to i 200*F ~

10 hydrostatic testing cycles.

RCS pressurized to 3125 psia with RCS temperature in accordance with i

~

SpectfIcation 3.4.8.

[

T 200 leak testing cycles.

RCS pressured to 2250 psia with RCS l

temperature greater then minious for hydrostatic testing, but less then l

minimum RCS temperature for critica11y.

l t

i 200 sefsmic stress cycles.

Subjection to a seismic event egual l

to one half the design basis l

earthgeake (00E).

j 480 cycles (in any codination)

Trip from 1995 of RATED THEIWWE.

of reacter trip, turbine trip power; turbine trip (total l

with delayed reacter trip, leaf rejection) from 100K of or complete less of forced RATED THEIWWE. POWER fellemed i

rea:ter coolant flow.

by resulting reacter trip; i

simultaneews less of all Reacter Coelant Pumps at 100K of RATE 0 j

THEIBOW POWER.

i i

1

l TABLE 5.7-1 (Continued) z COMPONENT CYCLIC OR TRANSIENT LIMITS

~

E o5

~

^

CYCLIC OR DESIGN CYCLE 7

COMPONENT TRANSIENT LIMIT OR TRANSIENT E

Pressurizer Spray System w

Calculational Nethod:

l 1.

The spray cycle is defined as any initiation and termination of main or auxiliary spray flow through the pressurizer spray nozzle.

i 2.

If the maximum temperature difference between the pressurizer and the I

i pressurizer spray during the spray cycle exeeds 200*F, each spray cycle and the corresponding temperature difference is logged.

l

?

3.

The spray system usage factor is calculated as follows:

A.

Fill in Column "N" above.

i 8.

Calculate "N/N " (Divide N and N ).

g g

C.

Add Column "N/N " to find IN/N. N s total is W cumulatt w 1

g g

usage factor.

4.

A.

If the cumulative usage factor is equal to or less than 0.65 no further action is required.

B.

l E

If the cumulative usage factor exceeds 0.65, subsequent pressurizer spray I

E operation shall continue to be monitored and an engineering evaluation of h

spray system fatigue shall be performed within 90 days.

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