ML20237A830

Amends 61 & 50 to Licenses NPF-10 & NPF-15,respectively, Defining as Limiting Conditions for Operation,Vols & Concentrations of Borated Water to Be Maintained in Refueling Water Storage Tank

ML20237A830
Person / Time
Site:	San Onofre
Issue date:	11/17/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237A832	List: ML20237A830
References
TAC-65827, TAC-65828, NUDOCS 8712150294
Download: ML20237A830 (60)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

^

W ASHINGTON, D. C. 205S5 y,.j l

SOUTHERN CALIFORNIA EDISON COMPANY l

SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA

]

THE CITY OF ANAHEIM, CALIFORNIA i

DOCKET NO. 50-361

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l SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 j

l fMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 61 l

License No. NPF-10 l

l l

1.

The Nuclear Regulatory Commission (the Comission) has found that-l A.

The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees) dated July 17, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; I

B.

The facility will operate in confomity with the application, as I

amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (1) that the activities authorized l

by this amenoment can be conducted without endangering the health I

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

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

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

8712150294 871117 PDR ADOCK 05000361 P

PDR

. l 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:

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

61, are hereby incorporated in the license.

SCE shall operate the facility in accordance with the Technical 3

Specifications and the Environmental Protection Plan.

3.

The changes in Technical Specifications are to become effective within 30 c'eys of issuance of the anenoment. In the period between issuance of the v er.drent and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at.the time. The period of time durino changeover shall be minimized.

4 Ttis license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION k-m2, George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation A ttachn ent :

Charces to the Technical Specifications Cate of Issuance: November 17, 1987 l

1 4.

4 e

t ATTACHMENT TO LICENSE AMENDMENT NO. 61 t

FACILITY OPEFATING LICENSE NO. NPF-10 DOCKET NO. 50-361 l

l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the fcilowing overleaf pages to the amended pages.

trendrent Petts Overleaf Faces 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-4 3/4 1-12 3/4 1-11 3/4 1-13 3/t 1 14 l

3/4 5-1 3/4 5-2 3/4 5-E 3/4 5-7 3/4 6-16 3/4 6-15 1

3/4 9-1 3/4 9-2 3/4 10-1 3/4 10-2 F 3/4 1-T B 3/4 1-1 E 3/4 1-3 8 3/4 1-4 F 3/4 5-2 8 3/4 5-1 F 3/4 5-3 F 3/4 9-1 B 3/4 9-2 l

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3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,y GREATER THAN 200 F LIMITING CONDITION FOR OPERATION 1

i 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 5.15% delta k/k.

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

ACTION:

)

With the SHUTDOWN MARGIN less than 5.15% delta k/k, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 5.15% delta k/k:

a.

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

If the inoperable CEA is immovable or untrippable, the above required SHUTOOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable CEA(s),

b.

When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at leastonceper12hoursbyveriihngthatCEAgroupwithdrawalis within the Transient Insertion Limits of Specification 3.1.3.6.

c.

When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criNbality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.

• See Special Test Exception 3.10.1.

SAN ONOFRE-UNIT 2 3/4 1-1 AMENDMENT NO. 61

REACTIVITY CONTROL SYSTEMS I

SURVEILLANCE REQUIREMENTS (Continued) d.

Prior to initial operation above 5% RATED THERMAL POWER after each l

fuel loading, by consideration of the factors of e. below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.

e.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of at least the following factors:

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted i

values to demonstrate agreement within + 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.1.1.e, above.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power l

Days after each fuel loading.

l l

1 e

SAN ONOFRE-UNIT 2 3/4 1-2

REACTIVITY CONTROL SYSTEMS SHUTDOWNMARGIN-T,yESSTHANOREQUALTO200F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 3.0% delta k/k.

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 3.0% delta k/k, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal j

to 3.0% delta k/k:

a.

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

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

1 b.

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

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration,and 6.

Samarium concentration.

7.

Whenever the reactor coolant level is below the hot leg centerline, one and only one charging pump shall be operable; by verifying that power is removed from the remaining chargirg pumps.

SAN ONOFRE-UNIT 2 3/4 1-3 AMENDMENT NO. 61

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

~4 a.

Less positive than 0.5 x 10 delta k/k/*F whenever THERMAL POWER is

< 70% of RATED THERMAL POWER, or

)

Less positive than 0.0 delta k/k/*F whenever THERMAL POWER is > 70%

of RATED THERMAL POWER, and

~4 b.

Less negative than -3.3 x 10 delta k/k/*F at RATED THERMAL POWER.

APPLICABILITY: MODES 1 and 2*#

ACTION:

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

(

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

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

Prior to initial operation above 5% of RATED THERMAL POWER, after a.

each fuel loading.

b.

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

c.

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

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

1. See Special Test Exception 3.10.2.

SAN ONOFRE-UNIT 2 3/4 1-4 AMEN 0 MENT NO. 47 i

1 REACTIVITY CONTROL SYSTEMS

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BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 The boric acid makeup pump (s) in the boron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the boric acid makeup pump (s) required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup l

pump (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F; restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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

SAN ONOFRE-UNIT 2 3/4 1-11 AMENDMENT NO. 43

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REACTIVITY CONTROL SYSTEMS j

BORATE 0 WATER SOURCE - SHUT 00WN

]

1 LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:

a.

One boric acid makeup tank with a minimum boron concentration of

{

2350 ppm and a minimum borated water volume of 4150 gallons, or l

J b.

The refueling water storage tanks with:

1.

A minimum borated water volume of 4150 gallons above the ECCS l

suction connection, 2.

A minimum boron concentration of 2350 ppm, and l

3.

A solution temperature between 40 F and 100 F.

APPLICABILITY: MODES 5 and 6.

ACTION:

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

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

a.

At least once per 7 days by:

1.

Verifying the baron concentration of the water, and 2.

Verifying the cor.tained borated water volume of the tank.

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of boratid water when the outside air temperature is less than 40 F or greater than 100 F.

SAN ONOFRE-UNIT 2 3/4 1-12 AMENDMENT NO. 61 L

Figure 3.1-1 MINIMUM STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION (Gallons) 12000 l

l Regio;n of Acchptable

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- - - - - - - t - - -- - - - ----- ---- - -- - r - p eration 1000o-

---

1----------

l l

l

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3.-

-l l

RWST at 2,350 ppm aE c

4- --------l------

RWST at 2,500 ppm.

sooo-c.e z.

e e

'=

l RWST at 2,650 ppm mE 2"

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{

RWST at 2,800 ppm fo o

e

<3 sooo-

- - - - - - - - t. - - - - - - - -:- -

--t---------q----------

ox gg i

e i

om DD l

l l

4--------

s--------- ;--------

s----------

4 coo-Regl' n of Undcceptabih l

p Operatton 2000 j

j j

i 2.30 2.50 2.75 3.00 3.25 3.50 (4,o21)

(4,371)

(4, sos)

(5,245)

(5,ss2)

(e,119)

Boric Acid Concentration WT% (ppm) 1AM CNCnt uMIT 2 3/4 1*U Amendment No. 61

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING l

I LIMITING CONDITION FOR OPERATION 3.1.2.8 The following borated water sources shall be OPERABLE:

l a.

At 1 cast one of t.he following combinations:

1)

One boric acid makeup tank, with the tank contents in accor-d_..ce with Figure 3.1-1, its associated gravity feed valve, and boric acid makeup pump, 2)

Two boric acid makeup tanks, with the combined contents of the tanks in accordance with Figure 3.1-1, their associated gravity feed valves, and boric acid makeup pumps, 3)

Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at least one boric acid makeup pump and, I

b.

The refueling water storage tank with:

{

1.

A minimum contained borated water volume of 362,800 gallons above i

the ECCS suction connection, 2.

Between 2350 and 2800 ppm of boron, and l

3.

A solution temperature between 40 F and 100 F.

APPLICABILITY: MODES 1, 2, 3 and 4.

i ACTION:

With the above required boric acid makeup tank (s) inoperable, restore a.

the tank (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F; restore the above required boric acid makeup tank (s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

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

SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water sources shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

SAN ONOFRE-UNIT 2 3/4 1-14 AMENDMENT NO. 61 L-

1 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS l

LIMITING CONDITION FOR OPERATION 1

l l

3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

a.

The isolation valve open and power to the valve removed, b.

A contained borated water volume of between 1680 and 1807 cubic

feet, c.

Between 1850 and 2800 ppm of boron, and I

d.

A nitrogen cover pressure of between 600 and 625 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a.

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next l

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

]

b.

Witt one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 h0urs.

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1.

Verifying that the contained borated water volume and nitrogen cover pressure in the tanks is within the above limits, and 2.

Verifying that each safety injection tank isolation valve is open.

• With pressurizer pressure greater than or equal to 715 psia.

I SAN ONOFRE-UNIT 2 3/4 5-1 AMENDMENT NO. 61 l

w_. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _

e i

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injection tank solution.

c.

At least once per 31 days by verifying the fuses removed from each safety injection tank vent valve.

d.

At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position.

At least once per 18 months by verifying that each safety injection e.

tank isolation valve opens automatically under each of the following conditions:

1.

Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.

Upon receipt of an SIAS test signal.

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

Is EMERGENCY CORE COOLING SYSTEMS

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3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350*F av9 LIMITING CONDITION FOR OPERATION 1

3.5.3 As a minimum,.one ECCS subsystem comprised of the following shall be OPERABLE:

One OPERABLE high pressure safety injection pump, and a.

b.

An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.

APPLICABILITY: MODES 3" and 4.

ACTION:

With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem a.

to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCE RE0VIREMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

With pressurizer pressure less than 400 psia.

SAN ONOFRE-UNIT 2 3/4 5-7 l

1 EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank shall be OPERABLE with:

a.

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

Between 2350 and 2800 ppm of boron, and c.

A solution temperature between 40*F and 100 F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the contained borated water volume in the tank, and 2.

Verifying the boron concentration of the water.

b.

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

I SAN ONOFRE-UNIT 2 3/4 5-8 AMENDMENT NO. 61

_m

CONTAINMENT SYSTEMS

(

SU:vEILLANCE :EOUIREPENTS (Centinued) 3.

Verifying that each spray pump starts automatically on a Safety Injection Actuation test signal.

4 Verifying that each containment spray header riser is filled with water to within 10 feet of the lowest spray ring.

c.

At least cnce per 5 years ey performing an air or smoke flew test thrcegh each spray header and verifying each spray nozzle 15 unobstructed.

I t

l l

1 l

i SAN ONOFRE-UNIT 2 3/4 6-15 AMENOMENT No.16 j

i

t CONTAINMENT SYSTEMS RECIRCULATION FLOW PH CONTROL LIMITING CONDITION FOR OPERATION 3.6.2.2 The recirculation flow pH control system shall be operable with a minimum of 17,461 lbs. (291 cu. ft.) of trisodium phosphate (w/12 l

hydrates), or equivalent, available in the storage racks in the containment.

APPLICABILITY: Modes 1, 2 and 3 ACTION:

With less than the required amount of trisodium phosphate available, restore the system to the correct amount 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 SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.2 The recirculation flow pH control system shall be demonstrated j

operable during each refueling outage by:

Visually verifying that the TSP storage racks have maintained a.

their integrity and the TSP containers contain a minimum of 1/,461 lbs. (291 cu. ft.) of TSP (w/12 hydrates) or equivalent.

l b.

Verifying that when a sample of less than 3.43 grams of triso-l dium phosphate (w/12 hydrates) or equivalent, selected at random from one of the storage racks inside of containment, is sub-merged, without agitation, in at least 1 litre of 120 1 10 degrees-F borated demineralized water borated to at least 2812 l

ppm boron, allowed to stand for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then decanted and mixed, the pH of the solution is greater than or equal to 7.0.

SAN ONOFRE - UNIT 2 3/4 6-16 AMENDMENT NO. 61

Q a

3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.

With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity conditions is met:

a.

Either a K of 0.95 or less, eff b.

A boron concentration of greater than or equal to 2350 ppm, l

APPLICABILITY: MODE 6*

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or its l

]

equivalent until K is reduced to less than or equal to 0.95 or the baron concentration is r$Nored to greater than or equal to 2350 ppm, whichever is l

the more restrictive.

l SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrict 1.e of the above two react'vity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length CEA in excess of 3 feet from its fully inserted position within the reactor pressura vessel.

4.9.1.2 The boron concentration of the reactor coolant system and the l

refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

"The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.

SAN ONOFRE-UNIT 2 3/4 9-1 AMENDMENT NO. 61

o REFUELING OPERATIONS I

3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minimum, two source range neutron flux monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY: MODE 6.

ACTION:

a.

With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

b.

With both of the above required monitors inoperable or not operating, determine the boron concentration of the reactor coplant system at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

k SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and c.

A CHANNEL FUNCTIONAL TEST at least once per 7 days.

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

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a

1 4

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUT 00WN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTOOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

APPLICABILITY: MODES 2 and 3*

ACTION:

a.

With any full length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-ately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm l

boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored, b.

With all full length CEAs fully insorted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or its j

equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS l

4.10.1.1 The position of each full length and part length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

• 0peration in MODE 3 shall be limited to 6 consecutive hours.

SAN ONOFRE-UNIT 2 3/4 10-1 AMENDMENT NO. 61

1 SPECIAL TEST EXCEPTIONS 3/4.10.2 GROUP HEICHT, INSERTION AC POWER O!S*;;EUT:0N LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of l

Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7 and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

AP LICABILITY: MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2 1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, k

3.2.3, 3.2.7 and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended, either:

I a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY wthin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.l.3, 3.1.3.1, 3.1. 3. 5, 3.1. 3. 6, 3. 2. 2, 3. 2. 3, 3. 2. 7 or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1. 3, 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6, 3. 2. 2, 3.2.3, 3.2.7 or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.

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SAN ONOFRE-UNIT 2 3/4 10-2 AMEN 0 MENT No. 16 L---_-_____.

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3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.I and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subtritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.

SHUTOOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg.

The most restrictive condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trollad RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 5.15% delta k/k is required to control the reactivity transient.

Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety a.9alysis assumptions. With T,yg less than or equal to 200*F. the reactivity transients resulting from any postulated accident are minical arid a 3.0% delta k/k shutdown margin provides adequate protection.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coef-ficient will be maintained within acceptable values throughout each fuel cycle.

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

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 520 F.

This limitation is required to ensure 1) the moderator temperature coefficient is

)

within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT temperature.

J NOT 3/4.1.2 BORATION SYSTEMS The baron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to i

perform this function include 1) borated water sources, 2) charging pumps,

3) separate flow paths, 4) boric acid makeup pumps, and 5) an emergency power <

j supply from OPERABLE diesel generators.

With the RCS average temperature above 200 F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.

The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN frem expected operating conditions of 3.0% delta k/k after xenon decay and cooloown to 200 F.

The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and volumes of Specification 3.1.2.8 plus approximately 13,000 gal-lons of 2350 ppm borated water from the refueling water tank or approximately 26,000 gallons of 2350 ppm borated water from the refueling water tank aione.

However, for the purpose of consistency the minimum required volume of 362,800 gallons above ECCS suction connection in Specification 3.1.2.8 is identical to the more restrictive value of Specification 3.5.4.

With the RCS temperature below 200*F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

The boron capability required below 200*F is based upon providing a 3% delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200 F to 140 F.

This condition requires 4150 gallons of 2350 ppm borated water from either the l

refueling water tank or boric acid solution from a boric acid makeup tank.

SAN ONOFRE-UNIT 2 B 3/4 1-2 AMEN 0 MENT NO. 61 l

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i 4

REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

The water volume limits are specified relative to the top of the highest suction connection to the tank.

(Water volume below this datum is not considered recoverable for purposes of this specification.) Vortexing, internal structures and instrument error are considered in determining the tank level corresponding to the specified water volume limits.

The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

The limits on water volume and boron concentration of the RWST also ensure a pH value of greater than 7.0 for the solution recirculated within containment after a LOCA. This pH minimizes the effect of chloride and caustic stress cor-rosion on mechanical systems and components. The maximum RWST volume is not specified since analysis of pH limits and containment flooding post-LOCA con-sidered RWST overflow conditions.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-i tained, and (3) the potential effects of CEA misalignments are limited to acceptable levels.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.

The ACTION statements applicable to a stuck or untrippable, CEA to two or more inoperable CEAs and to a large misalignment (greater than or equal to 19 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUTDOWN MARGIN.

For small misalignments (less than 19 inches) of the CEAs, there is 1) a small effect on the time dependent long term power distributions relative to those used in generating LCOs and LSSS setpoints, 2) a small effect on the available SHUTDOWN MARGIN, and 3) a small effect on the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with small misalignments of CEAs permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment requirements. The one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.

SAN ONOFRE-UNIT 2 B 3/4 1-3 AMENDMENT NO.61

REACTIVITY CONTROL SYSTEM 8ASES MOVABLE CONTROL ASSEMBLIES (Continued) i The CPCs provide protection to the core in the event of a large I

misalignment (greater than or equal to 19 inches) of a CEA by applying appropriate penalty factors to the calculation to account for the misaligned CEA.

However, this misalignment would cause distortion of the core power di s t.-i b uti on.

This distribution may, in turn, have a significant ef fect on

1) the available SHUTOOWN MARGIN, 2) the time dependent long term power distributions relative to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with the large misalignment of a CEA requires a prompt realignment of the misaligned CEA.

The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA.

Conformance with these aligt. ment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints. However, extended operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup, 2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoints determination. Therefore, time limits have been imposed on

(

operation with inoperable CEAs to preclude such adverse conditions from developing.

Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits. The CEA " Full In" and " Full Out" limits provide an addi-tional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions. Therefore, the ACTION statements appilcable to inoperable CEA position indicators permit continued operations when the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits. Setting the "RSPT/CEAC Inoperable" addressable coristant in the CPC's to indicate to the CPC's that one or both of the CEAC's is inoperable does not necessarily constitute the inoper-ability of the RSPT rod indications from the respective CEAC. Operability of the CEAC rod indications is determined from the normal surveillance.

CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

The maximum CEA drop time restriction is consistent with the assumed CEA drop time used in the safety analyses. Measurement with T,yg greater than or equal to 520'F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced i

during a reactor trip at operating conditions.

SAN ONOFRE-UNIT 2 8 3/4 1-4 AMEN 0 MENT NO. 32

4 s

s 3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITY of each of the Reactor Coolant System (RCS) safety injection tanks ensures that a sufficient volume of borated water will be i

immediately forced into the reactor core through each of the cold legs in the 1

event the RCS pressure falls below the pressure of the safety injection tanks.

This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on safety injection tank volume, boron concentration and pressureensurethattheassumptionsusedforsafetyinjectiontankinjection in the accident analysis are met.

The safety injection tank power operated isolation valves are considered to be " operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these safety injection tank isolation valves fail to meet single failure criteria, removal of power to the valves is required.

(

The limits for operation with a safety injection tank inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occuring concurrent with failure of an additional safety injection tank which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be immediately opened, the full capability of one safety injection tank is not available and prompt action is required to place the reactor in a mode where this capability is not required.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.

In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.

SAN ONOFRE-UNIT 2 B 3/4 5-1

EMERGENCY CORE COOLING SYSTEMS BASES 1

ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 350 F, one OPERABLE ECCS subsystem is j

acceptable without single failura consideration on the basiA of the stable reactivity condition of the reactor and the limited core cooling requirements.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained.

Surveillance requirements for flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:

(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 REFUELING WATER STORAGE TANK (RWST)

The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure that

1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. The limit on maximum boron concentration is to ensure that boron does not precipitable in the core following LOCA. The limit on RWST solution temperature is to ensure that the assumptions used in the LOCA analyses remain valid.

f l

SAN ONOFRE-UNIT 2 B 3/4 5-2 AMENDMENT NO. 61 i

i

s EMERGENCY CORE COOLING SYSTEMS BASES l

REFUELING WATER STORAGE TANK (Continued)

The water volume limits are specified relative to the top of the highest suction connection to the tank.

(Water volume below this datum is not considered recoverable for purposes of this specification). The specified volume limits consist of the minimum volume required for ECCS injection above the Recirculation Actuation Signal (RAS) setpoint, plus the mimumum volume required for the transition to ECCS recirculation below the RAS setpoint, plus the volume corresponding to the range of the RAS setpoint, including RAS corresponding to the error high and low. Vortexing, internal structure, and instrument error are considered in determining the tank level corresponding to the specified water volume limits.

The limits on water volume and boron concentration of the RWST also ensure that the solution recirculated within containment after a LOCA has a pH value i

of greater than 7.0.

This pH minimizes the effect of chloride and caustic I

stress corrosion on mechanical systems and components. The maximum RWST volume is not specified since analysis of pH limits and containment flooding post-LOCA considered RWST overflow conditions.

SAN ONOFRE-UNIT 2 B 3/4 5-3 AMENDMENT NO. 61

c 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uni-form boron concentration is maintained 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 in the accident analyses.

Thevalueof0.95orlessforK)If includes a 1% delta K/K conservative allowance for uncertainties.

Similarl the boron concentra-tion value of 2350 ppm or greater also includes a conservative uncertainty l

allowance of 50 ppm baron.

3/4.9.2 INSTRUMENTATION 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 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 i

sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

i 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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SAN ONONFRE - UNIT 2 8 3/4 9-1 AMEN 0 MENT NO. 61 1

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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 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 uncoupligg is verified by weighing the drive shaft extensions.

(

3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING 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 a single fuel assembly and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

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 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 dilution incident and prevent boron stratification.

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

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-l 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

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operating shutdown cooling train, adequate time is provided to initiate emer-i gency procedures to cool the core.

SAN ONONFRE - UNIT 2 8 3/4 9-2 AMEN 0 MENT NO. 48 l

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1. "......'o UNITED STATES

~,

j NUCLEAR REGULATORY COMMISSION j

W ASHINGTON, D. C. 20655

\\...../

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA CCCKET NO. 50-362 SAN ONOFFE NUCLEAR GENERATING STATION, UNIT 3 i

APENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 50 License No. NPF-15 The Nuclear Reguietory Commission (the Coninission) has found that:

A.

The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern l

California Edison Company (SCE) on behalf of itself and Sar. Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licensees)datedJuly 17, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFP Chapter I; b.

1he f acility will operate in confonnity with the application, as arrended, the trovisions of the Act, and the regulations of the Commission; C.

There is reascnable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the l

comon defense and security or' to the health and safety of the public; E.

The issuance of this aniendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirerrents have been satisfiec.

I 1

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and Paragraph 2.C(2) of Ft.cility Operating License No. NPF-10 is hereby amended to read as follows:

(2) Technical Specifications l

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 50, are hereby incorporated in the license.

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

3.

The cFerges in Technical Specifications are to become effective upon initiel startup for Cycle 4 of operation. in the period between issuance of the amendtrent and the effective date of the new Technical Specifications, the licensees shall adhere to the lechnical Specifications existing at the tirre. The period of time during changeover shall be minimized.

a.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C4sb m,sn&Q George W. Knighton, 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: November 17, 1987 i

o l ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Peplace the following pages of the Appendix A' Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating.the area of change. Also to be replaced I

are the following ovt.rleaf pages to the amended pages.

Ac endme,nt_ Pac,e, Overleaf Pace 3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-4 1

3/4 1-12 3/4 1-11 3/4 1-13 3/4 1-14 3/4 5-1 3/4 5-2 l

3/4 5-E 3/4 5-7.

3/4 6-17 3/4 6-18 3/4 9-1 3/4 9-2 3/4 10-1 3/4 10-2 b 3/4 1-2 8 3/4 1-1 6 3/4 1-3 8 3/4 1-4 B 3/4 5-2 B 3/4 5-1 B 3/4 5-3 1

E 3/4 9-1 B 3/4 9-2 l

3

I 3/4.1 REACTIVITY CONTROL SYSTEMS l

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3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,y GREATER THAN 200 F LIMITING CONDITION FOR OPERATION l

3.1.1.1 The SHUTOOWN MARGIN shall be greater than or equal to 5.15% delta k/k.

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

ACTION:

With the SHUTDOWN MARGIN less than 5.15% delta k/k, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored, i

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTOOWN MARGIN shall be determined to be greater than or equal to 5.15% delta k/k:

1 a.

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

If the inoperable CEA is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable CEA(s).

b.

When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at.

leastonceper12hoursbyveri?yfngthatCEAgroupwithdrawalis within the Transient Insertion Limits of Specification 3.1.3.6.

c.

When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achievingreactorcri&fbalitybyverifyingthatthepredicted critical CEA position is within the limits of Specification 3.1.3.6.

See Special Test Exception 3.10.1.

SAN ONOFRE-UNIT 3 3/4 1-1 AMENDMENT NO. 50

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.

e.

When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of at least the following factors:

1.

Reactor coolant system boron concentration, l

2.

CEA position, l

3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD).

Tiiis comparison shall consider at least those f actors stated in Specification 4.1.1.1.1.e, above.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

I l

l l

l

/

SAN ONOFRE-UNIT 3 3/4 1-2

o REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,y LESS THAN OR EQUAL TO 200*F l

LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTOOWN MARGIN shall be greater than or equal to 3.0% delta k/k.

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 3.0% delta k/k, immediately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm boron or equivalent until the required l

SHUTDOWN MARGIN is restored.

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

a.

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

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

b.

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

1.

Reactor coolant system boron concentration, 2.

CEA position, 3.

Reactor coolant system average temperature, 4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration,and 6.

Samarium concentration.

7.

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

i SAN ONOFRE-UNIT 3 3/4 1-3 AMENDMENT NO. 50

\\

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

~4 a.

Less positive than 0.5 x 10 delta k/k/*F whenever THERMAL POWER is 1 70% of RATED THERMAL POWER, or less positive than 0.0 delta k/k/*F whenever THERMAL POWER is > 70% of RATED THERMAL POWER, and

~4 b.

Less negative than -3.3 x 10 delta k/k/*F at RATED THERMAL POWER.

APPLICABILITY: MODES 1 and 2*#

ACTION:

With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS

]

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

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

Prior to initial operation above 5% of RATED THERMAL POWER, after a.

each fuel loading.

b.

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

c.

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

\\

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

4

1. See Special Test Exception 3.10.2.

{

SAN ONOFRE-UNIT 3 3/4 1-4 AMENOMENT NO. 36 l

I

'o REACTIVITY CONTROL SYSTEMS.

(

BORIC ACID MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2,6 The boric acid makeup pump (s) in the baron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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

pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup pump (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within l

the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTOOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F; restore the above required boric acid makeup pump (s) to OPERABLE status within the next 7 days or be in COLD SHUT 00WN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

(

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

I SAN ONOFRE-UNIT 3 3/4 1-11 AMENDMENT NO., 32

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUT 00WN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following barated water sources shall be OPERABLE:

a.

One boric acid makeup tank with a minimum boron concentration of 2350 ppm and a minimum borated water volume of 4150 gallons, or b.

The refueling water storage tanks with:

1.

A minimum borated water volume of 4150 gallons above the ECCS l

suction connection, 2.

A minimum boron concentration of 2350 ppm, and 3.

A solution temperature between f and 100 F.

APPLICABILITY: MODES 5 and 6.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.1.2.7 The above required borated water source shall be demonstrated i

OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration of the water, and 2.

Verifying the contained borated water volume of the tank.

b.

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

i SAN ONOFRE-UNIT 3 3/4 1-12 AMEN 0 MENT NO. 50 l

{

Figure 3.1-1 MINIMUM STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION (Gallons) 12000 J

l l

l Regio ln of Acchptable t

l l

lOperatioh 10000- -------i---------'----------t--------~~l-~~~~~~~~-

l l

l l

l l

3 RWST at 2,350 ppm

=

aE l

e

• j 800o-.-- -

4- ------- :------ RWST at 2,500 ppm.

c.ze l

RWST at 2,650 ppm e e eE 23 l

=s RWST at 2,800 ppm o

o e

<3 sooo---------t,-----

s--

oe ce l

l o=

MD l

l l

l 4ooo- -------

2--------

s---------

s----------

Reghn of Unicceptabli Operatton l

l 1

l l

l l

l l

2000 j

j 2.30 2.50 2.75 3.00 3.25 3.50 (4,o21)

(4,371)

(4,808)

(5,245)

(5,682)

(6,119)

Boric Acid Concentration WT% (ppm)

SAN openPWTf 3 1/4 FU Amendment No. 50

s REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 The following bort.tod water sources shall be OPERABLE:

a.

At least one of the following combinations:

1)

One boric acid makeup tank, with the tank contents in accordance with Figure 3.1-1, its associated gravity feed valve, and boric acid makeup pump, 2)

Two boric acid makeup tanks, with the con 3ined contents of the tanks in accordance with Figure 3.1-1, tMir associated gravity feed valves, and boric acid makeup pumps, 3)

Two boric acid makeup tanks, each with contents in accordance with Figure 3.1-1, at least one gravity feed valve, and at least one boric acid makeup pump and, l

b.

The refueling water storage tank with:

l 1.

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

Between 2350 and 2800 ppm of boron, and l

3.

A soluticn temperature between 40'F and 100 F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With the above required boric acid makeup tank inoperable, restore the tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F; restore the above required boric acid makeup tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> a d in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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

a.

At least once per 7 days by:

1.

Verifying the boron concentration in the water, 2.

Verifying the contained borated water volume of the water

source, j

SAN ONOFRE-UNIT 3 3/4 1-14 AMENDMENT NO. 50 i

1 l

{

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS l

LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with; a.

The isolation valve open and power to the valve removed, b.

A contained borated water volume of between 1680 and 1807 cubic

feet, c.

Between 1850 and 2800 ppm of boron, and d.

A nitrogen cover pressure of between 600 and 625 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a.

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1.

Verifying that the contained borated water volume and nitrogen cover pressure in the tanks is within the above limits, and 2.

Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure greater than or equal to 715 psia.

SAN ONOFRE - UNIT 3 3/4 5-1 AMENDMENT NO. 50

EMERGENCY CORE COOLING SYSTEMS i

l SURVEILLANCE REQUIREMENTS (Continued)

I

\\

b.

At least once per 31 days and withirt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution '

volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration of the safety injection tank

solution, t

i At least once per 31 days by verifying the fuses removed from each c.

safety injection tank vent valve.

d.

At least once per 31 days when the RCS pressure is above 715 psia, by verifying that the isolation valve operator breakers are padlocked in the open position, At least once per 18 months by verifying that each safety injection e.

tank isolation val've opens automatically under each of the following conditions:

1.

Before an actual or simulated RCS pressure signal exceeds 715 psia, and 2.

Upon receipt of an SIAS test sianal.

(

l

(

l SAN ONOFRE-UNIT 3 1/a ;-?

EMERGENCY CORE COOLING SYSTEMS

(

3/4.5.3 ECCS SUBSYSTEMS - T,yg LESS THAN 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE high pressure safety injection pump, and b.

An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.

APPLICABILITY: MODES 3* and 4.

?.CTION:

I With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem a.

to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b.

(

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCE REQUIREMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

r With pressurizer pressure less than 400 psia.

SAN ONOFRE-UNIT 3 3/4 5-7

.l EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK 1

LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank shall be OPERABLE with:

a.

A minimum borated water volume of 362,800 gallons above the ECCS j

suction connection, b.

Between 2350 and 2800 ppm of boron, and c.

A solution temperature between 40 F and 100*F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.5.4 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the contained barated water volume in the tank, and 2.

Verifying the boron concentration of the water.

b.

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

SAN ONOFRE - UNIT 3 3/4 5-8 AMENDMENT NO. 50

CONTAINMENT SYSTEMS RECIRCULATION FLOW - PH CONTROL LIMITING CONDITION FOR OPERATION 3.6.2.2 The recirculation flow pH control system shall be operable with a minimum of 17,461 lbs. (291 cu. ft.) of trisodium phosphate (w/12 hydrates),

or equivalent, available in the storage racks in the containment.

APPLICABILITY: Modes 1, 2 and 3 ACTION:

With less than the required amount of trisodium phosphate available, restore 1

the system to the correct amount 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 l

within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.2 The recirculation flow pH control system shall be demonstrated operable during each refueling outage by:

a.

Visually verifying that the TSP storage racks have maintained their integrity and the TSP containers contain a minimum of 17,461 lbs.

(291 cu. ft.) of TSP (w/12 hydrates) or equivalent.

b.

Verifying that when a sample of less than 3.43 grams of trisodium l

phosphate (w/12 hydrates) or equivalent, selected at random from one of the storage racks inside of containment, is submerged, with-out agitation, in at least 1 litre of 120 1 10 degrees-F borated demineralized water borated to at least 2812 ppm boron, allowed to l

stand for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then decanted and mixed, the pH of the solution is greater than or equal to 7.0, i

{

SAN ONOFRE-UNIT 3 3/4 6-17 A!!ENDMENT NO. 50 l

-1 CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with two fan systems to each group.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one group of the above required containment cooling fans inoperable and both containment spray systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With two groups of the above required containment cooling fans inoperable, and both containment spray systems OPERABLE, restore at least one group of cooling fans 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 STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00VN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

f c.

With one group of the above required containment cooling fans incperable and one containment spray system inoperable, restore the inoperable spray systen 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 COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOCWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Starting each fan group from the control room and verifying that each fan group operates for at least 15 minutes.

2.

Verifying a cooling water flow rate of greater than or equal to 2000 gpm to each cooler.

]

b.

At least once per 18 months by verifying that each fan group starts automatically on a Containment Cooling Actuation test signal.

SAN ONOFRE-UNIT 3 3/4 6-18

I 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION j

i 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boren concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of following reactivity l

conditions is met:

l l

I Either a K,ff of 0.95 or less, l

a.

b.

A boron concentration of greater than or equal to 2350 ppm, l

l APPLICABILITY: MODE 6*.

l ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm i

of a solution containing greater than or equal to 2350 ppm boron or its l

equivalent until K is reduced to less than or equal to 0.95 or the boron concentration is r$Nored to greater than or equal to 2350 ppm, whichever is l

the more restrictive.

I SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length CEA in excess of 3 feet from its fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

"The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.

SAN ONOFRE - UNIT 3 3/4 9-1 AMENDMENT NO. 50

i REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 As a minirus, two source range neutron flux monitors shall be OPERABLE and operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY: MODE 6.

ACTION:

With one of the above required monitors inoperable or not operating, a.

immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, b.

With both of the above required monitors inoperable or not operating, determine the boron concentration of the reactor coolant system at least once 7er 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i i

4

(

SURVEILLANCE REQUIREMENTS 4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by perfonsance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of CORE ALTERATIONS, and A CHANNEL FUNCTIONAL TEST at least once per 7 days.

c.

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

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j 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUT 00WN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion fror. OPERABLE CEA(s).

I APPLICABILITY: M0nES 2 and 3*.

ACTION:

a.

With any full length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedi-ately initiate and continue boration at greater than or equal to 40 gpm of a solution containing greater than or equal to 2350 ppm l

boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all full length CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 40 gpm of a.

solution containing greater than or equal to 2350 ppm boron or its l

equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length and part length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

4 4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insortion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

• 0peration in MODE 3 shall be limited to 6 consecutive hours.

l SAN ONOFRE - UNIT 3 3/4 10-1 AMENDMENT-NO. 50 I

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SPECIAL TEST EXCEPTIONS 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION i

3.10.2 The moderator" temperature coefficient group height, insertion and power distribution limits of Specifications 3.1.1. 3, 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6, 3.2.2, 3.2.3, 3.2.7 and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

APPLICABILITY: MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2,

(

)

3.2.3, 3.2.7 and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended, either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7 or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7 or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.

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SAN ONOFRE-UNIT 3 3/4 10-2

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3/4.1 REACTIVITY CONTROL SYSTEMS I

BASES 3/4.1.1 BORAT10N CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made suberitical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.

SHUT 00WN MARGIN requirements vary,throughout core life as a function of fuel depletion, RCS boren concentration, 'and RCS T,yg.

The most restrictive j

condition occurs at EOL, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-

[

. trolled RCS cooldown. In the analysis of this accident, a minimum SHUTOOWN

[

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

Accordingly, the SHllTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions.

With T less than or equal to 200*F, the reactivit/ transients resulting from any postulated accident are minimal and a 3.0% delta k/k shutdown margin provides l

adequate protection.

E4.1.1. 3 N00ERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle.

The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient charges slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coef-ficient will be maintained within acceptadle values throughout each fuel l

cycle.

i SAN CNOFRE-UNIT 3 8 3/4 1-1 I

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REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 520*F.

This limitation is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE l

status with a stears bubble, and (4) the reactor pressure vessel is above its minimum RT temperature.

l NDT 3/4.1.2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid makeup pumps, and (5) an emergency power supply from OPERABLE diesel generators.

l With the RCS average temperature above 200*F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capa-bility in the event an assumed failure renders one of the systems inoperable.

Allowable out-of-service periods ensure that minor component repair or correc-tive action may be completed without undue risk to overall facility safety from injection system failures during the repair period.

The boration capability of either system is sufficient to provide a SHUT OWN MARGIN from expected operating conditions of 3.0% delta k/k after xenon decay and cooldown to 200 F.

The maximum expected boration capability requirement j

occurs at EOL from full power equilibrium xenon conditions and requires boric acid solution from the boric acid makeup tanks in the allov.able concentrations and volumes of Specification 3.1.2.8 plus approximately 13,000 gallons of 2350 ppm barated water from the refueling water tank or approximately 26,000 gallons of 2350 ppm borated water from the refueling water tank alone. However, for the purpose of consistency the minimum required volume of 362,800 gallons above ECCS suction connection in Specification 3.1.2.8 is identical to more restrictive value of Specification 3.5.4.

With the RCS temperature below 200*F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

l The boron capability required below 200 F is based upon providing a 3.0% delta k/k SHUT 00WN MARGIN after xenon decay and cooldown from 200*F to 140'F.

This condition requires 4150 gallons of 2350 ppm borated water from l

either the refueling water tank or boric acid solution from the boric acid makeup tank.

SAN ONOFRE-UNIT 3 B 3/4 1-2 AMENDMENT N0.50 1

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i REACTIVITY LONTROL x"/ EMS BASES B0 RATION SYSTEMS (Continued)

J The water volume limits are specified relative to the top of the highest suction connection to the tank.

(Water volume below this datum is not 1

considered recoverable for purposes of this specification.) Vortexing, internal structures and instrument error are considered in determining the tank level corresponding to the specified water volume limits.

The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

The limits on water volume and boron concentration of the RWST also ensure 1

a pH value of greater than 7.0 for the solution recirculated within containment l

after a LOCA. This pH minimizes the effect of chloride and caustic stress cor-I rosion on mechanical systems and components. The maximum RWST volume is not specified since analysis of pH limits and containment flooding post-LOCA con-sidered RWST overflow conditions.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES 1

The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTOOWN HARGIN is main-tained, and (3) the potential effects of CEA misalignments are limited to acceptable levels.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.

The ACTION statements applicable to a stuck or untrippable CEA, to two or more inoperable CEAs and to a large misalignment (greater than or equal to l

19 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUTDOWN MARGIN.

For small misalignments (less than 19 inches) of the CEAs, there is 1) a small effect on the time-dependent long term power distributions relative to those used in generating LCOs and LSSS setpoints, 2) a small effect on the available SHUTDOWN MARGIN, and 3) a small effect on the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with small misalignments of CEAs permits a 1-hour timt interval during which attempts may be made to restore the CEA to within its alignment requirements. The 1-hour time limit is sufficient to (1) identify causes of a misaligned CEA, l

(2) take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.

1 l

SAN ONOFRE-UNIT 3 B 3/4 1-3 AMENDMENT NO. 50

REACT}VITY CONTROL SYSTEMS BASES MOVABLE CONTROL ASSEMBLIES (Continued)

The CPCs provide protection to the core in the event of a large misalignment (greater than or equal to 19 inches) of a CEA by applying appropriate penalty factors to the calculation to account for the misaligned CEA.

However, this misalignment would cause distortion of the core power distribution. This distribution may, in turn, have a significant ef fect on

1) the available SH' TDOWN MARGIN, 2) the time dependent long term power J

distributions relative to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with the large misalignment of a CEA requires a prompt realignment of the misaligned CEA.

i The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA.

i Conformance with these alignment requirements bring the core, within a

{

short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints. However, extended operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup, 2) peaking factors and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO l

and LSSS setpoints determination. Therefore, time limits have been imposed on

/

I operation with inoperable CEAs to preclude such adverse conditions from

\\

l developing.

Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits. The CEA " Full In" and " Full Out" limits provide an additional independent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.

Therefore, the ACTION statements applicable to inoperable CEA position indicators permit centinued operations when the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits.

Setting the "RSPT/CEAC Inoperable" addressable constant in the CPC's to indicate to the CPC's that one or both of the CEAC's is inoperable does not necessarily constitute the inoperability of the RSPT rod indications from the respective CEAC. Operability of the CEAC rod indications is determined from the normal surveillance.

CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.

These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.

The maximum CEA dror time restriction is consistent with the assumed CEA drop time used in the safety analyses. Measurement with T,yg

~

greater than or equal to 520*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

SAN ONOFRE-UNIT 3 8 3/4 l*4 AMENDMENT No. 21

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3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITY of each of the Reactor Coolant System (RCS) safety injection tanks ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure f alls below the pressure of the safety injection tanks.

This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on safety injection tank volume, boron concentration and pressure ensure that the assumptions used for safety injection tank injection in the accident analysis are met.

The safety injection tank power-operated isolation valves are considered to be " operating bypa:;ses" in the context of 2EEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these safety injection tank isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limits for operation with a safety injection tank inoperable for any

(.

reason except an isolation valve closed minimizes the time exposure of the Plant to a LOCA event occurring concurrent with failure of an additional safety injection tank which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be immediately opened, the full capability of one safety injection tank is not available and prompt action is required to place the reactor in a mode where this capability is not required.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with tha safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double-ended break of the largest RCS cold leg pipe downward.

In addition, each ECCS subsystem provides long tern core cooling capability in the recirculation mode during the accident recovery period.

(

SAN ONOFRE-UNIT 3 B 3/4 5-1

c EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continaed)

With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for flow balance testing provide assurance that proper ECCS flows

)

will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions j

when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

3/4.5.4 REFUELING WATER STORAGE TANK (RWST)

The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure that

1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. The limit on maximum boron concentration is to ensure that boron does not precipitate in the core following LOCA. The limit on RWST solution temperature is to ensure that the assumptions used in the LOCA analyses remain valid.

SAN ONOFRE-UNIT 3 B 3/4 5-2 AMENDMENT NO, 50

EMERGENCY CORE COOLING SYSTEMS BASES REFUELING WATER STORAGE TANK (Continued)

J l

The water volume limits are specified relative to the top of the highest l

suction connection to the tank.

(Water volume below this datum is not considered recoverable for purposes of this specification.) The specified volume limits consist of the minimum volume required for ECCS injection above the Recirculation Actuation Signal (RAS) setpoint, plus the minimum volume required for the transition to ECCS recirculation below the RAS setpoint, plus the volume corresponding to the range of the RAS setpoint, including RAS instrument error high and low. Vortexing, internal structure, and instrument error are considered in determining the tank level corresponding to the specified water voiume limits.

The limits on water volume and boron concentration of the RWST also ensure that the solution recirculated within containment after a LOCA has a pH l

value greater than 7.0.

This pH minimizes the effect of chloride a1d caustic

]

stress corrosion on mechanical systems and components. The maximem'RWST volume is not specified since analysis of pH limits and containment flooding post-LOCA considered RWST overflow conditions.

SAN ON0FRE-UNIT 3 B 3/4 5-3 AMENDMENT N0. 50

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3/4.9 REFUELING OPERATIONS BASES i

3/4.9.1 BORON CONCENTRATION l

{

The limitations on reactivity conditions during REFUELING ensure that:

1) the reactor will remain subcritical 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 includes incident in the accident analyses. The value of 0.95 or less for K'f(he boron Similarly I

a 1% delta K/K conservative allowance for uncertainties.

concentration value of 2350 ppm or greater also includes a conservative l

uncertainty allowance of 50 ppm boron.

l 3/4.9.2 INSTRLHENTATION The OPERABILITY of the source range neutron flux monitors ensures that 4

redundant monitoring capability is available to detect changes in the reactivity condition of the core.

l 3/4.9.3 DECAY TIME l

l The minimum requirement for reactor subtriticality prior to movement of I

irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived j

fission products. This decay time is consistent with the assumptions used in I

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 pressurization potential while in the REFUELING MODE.

I 3/4.9.5 COMMUNICATIONS 1

The requirement for communications capability ensures that refueling j

station personnel can be promptly informed of significant changes in the i

facility status or core reactivity condition during CORE ALTERATIONS.

l 4

l i

i SAN ONOFRE - UNIT 3 B 3/4 9-1 AMENDMENT NO. 50 j

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1 a i REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE 1

The OPERABILITY requirements for the refueling machine ensure that:

(1) the l

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 I

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 l

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 colar crane or j

the refueling machine auxiliary hoist.

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

The ctupling and uncoupling is verified by weighing the drive shaf t extensions.

3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemolies in the storage pool ensures that in the event this load is dropped (1) the activity release will be linited to that contained in a single fuel assembly and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release a u umed in the accident analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION l

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

'boren stratification.

The requirement to have two shutdown cooling trains OPERALBE 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 capability. 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 I

operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to coci the core.

SAN ONOFRE - UNIT 3 8 3/4 9-2 AMENOMENT NO. 37

,