Text

Amends 73 & 61 to Licenses NPF-10 & NPF-15,respectively, Revising Tech Specs to Increase Interval for 18-month Surveillance to Once Per Refueling Interval,Defined as 24 Months
	ML20247R947
Person / Time
Site:	San Onofre
Issue date:	05/31/1989
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20247R954	List: ML20247R947; ML20247R970;
References
	NUDOCS 8906080030
	Download: ML20247R947 (26)
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UNITED STATES 3

NUCLEAR REGULATORY COMMISSION s

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%....J SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-10 1.

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

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (licensees) dated April 26, October 11, and October 24, 1988, as supplemented March 20, 1989, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

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

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

8906080030 890531 PDR ADDCK 05000361.

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i e 2.

Accordingly,-the license is amended by changes to the Technical Speci-fications as indicated in the attachment to.this license amendment,=and paragraph 2.C(2) of Facility Operating License No. NPF-10.is hereby l

' 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. 73, are hereby incorporated

-in the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION AC s

George. Knighton irector

.Projec Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to-the Technical Specifications Date of Issuance:

May.31, 1989

. :s i

L ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified' below and inserting the enclosed pages. The revised.pages are. identified by amendment number and contain marginal lines indicating the area of change.

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

AMENDMENT PAGE OVERLEAF PAGE

'l-8 1-7 3/4 1-7 3/4 1-8 3/4 1-20 3/4 1 3/4 5-2 3/4 5-1 3/4 5-4 3/4 5-3 3/4 5-5 3/4 5-6 3/4 6-14 3/4 6-13 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-27 3/4 6-28

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1 TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY 5

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W At least once per 7 days.

M At least once per 31 days.

Q At lea t once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release.

N. A.

Not applicable.

Refueling Interval At least once per 24 months.

I SAN ONOFRE-UNIT 2 1-8 AMENDMENT NO.73 1

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REACTIVITY. CONTROL SYSTEMS FLOW PATHS - OPERATING

' LIMITING CONDITION FOR OPERATION

'3.1.2.2: The following boron injection flow paths to the.RCS via the charging p' umps (s) shall be OPERABLE:

a.

At least one of the following combinations:

1)

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

2)-

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

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

The flow. path from the refueling water storage tank.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With fewer than the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore the required boron injection flow paths to the Reactor Coolant System to 0PERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT

' STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k st 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore.the required flow paths to OPERABLE-status-within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:

a.

Intentionally deleted.

b.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

At least once per refueling interval during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a SIAS test signal.

. SAN ON0FRE-UNIT 2 3/4 1-7 AMENDMENT NO. 73

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,v REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

a.

T greater than or equal to 520 F, and avg b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With the drop time of any full length CEA determines to exceed the above limit, be in at least HOT STANDBY within six hours.

SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:

a.

For all CEAs following each removal and reinstallation of the reactor vessel head, b.

For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CFAs, and c.

At least once per refueling.

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SAN ONOFRE-UNIT 2 3/4 1-20 AMENDMENT NO. 73

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1

'l b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution I

volume increase of greater than or equal to 1% of tank volume by i

verifying the boron concentration of the safety injection tank I

solution.

c.

At least once per 31 days by verifying the fuses removed from each l

safety injection tank vent valve.

I 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.

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i e.

At least once per refueling interval by verifying that each safety injection tank isolation valve opens automatically under each of the following conditions:

1.

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

1 2.

Upon receipt of an SIAS test signal.

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SAN ONOFRE-UNIT 2 3/4 5-2 AMENDMENT NO. 73

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c EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2-Each ECCS subsystem shall be demonstrated OPERABLE:

a.

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

Valve Number Valve Function Valve Position a.

HV9353 SDC Warmup CLOSED b.

HV9359 SDC Warmup CLOSED c.

HV8150 SDC(HX) Isolation CLOSED d.

HV8151 SDC(HX) Isolation CLOSED e.

HV8152 SDC(HX) Isolation CLOSED f.

HV8153-SDC(HX) Isolation CLOSED g.

HV0396 SDC Bypass Flow Control CLOSED h.

HV8161 SDC(HX) Bypass Flow-OPEN Isolation

.i.

Deleted j.

Deleted

- k.

HV9420 Hot Leg Injection CLOSED Isolation 1.

HV9434 Hot Leg Injection CLOSED Isolation m..

HV8160 SDC Bypass Flow Control OPEN.

n.10-068 RWST-Isolation LOCKED OPEN (MANUAL) o.

HV8162 LPSI Miniflow Isolation OPEN p.

HV8163 LPSI Miniflow Isolation OPEN b.

At least once per 31 days by:

1.

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

Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise-secured in position is in the correct position.

- c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1.

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

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

L d.

At least once per refueling interval by:

1.

Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when RCS pressure is simulated I

greater than or equal to 715 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves when simulated RCS pressure is greater than or equal to 376 psia.

SAN ONOFRE-UNIT 2 3/4 5-4 AMENDMENT NO. 73

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Con'tinued) q 2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no

. evidence of' structural distress or' abnormal corrosion.

e.

At least once per refueling interval, during shutdown, by:

1.

Verifying.that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.

2.

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation-Test Signal:

a.

High-Pressure Safety Injection pump.

b.

. Low-Pressure Safety Injection pump.

c.

Charging pump.

3.

Verifying.that on a Recirculation Actuation Test. Signal, the containment sump isolation valves open; and that on a. RAS test signal coincident with a high-high containment sump. test signal, all the recirculation valves to the refueling water tank close.

f.

By verifying that each of the following pumps develops the indicated developed head and/or flow rate when tested pursuant to Specification 4.0.5:

1.

High-Pressure Safety Injection pumps developed head, at an indi-cated flow rate of 650 gpm, greater than or equal to 2142 feet for P017, 2101 feet for P018 and 2103 for P019 (see NOTE 1).

2.

. Low-Pressure Safety Injection pump developed head greater than or equal to 406.1 feet.

3.

Charging pump flow rate greater than or equal to 40 gpm.

g.

By performing a flow balance test, during shutdown, following comple-tion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying the following flow rates:

1.

For High-Pressure Safety Injection pump cold leg injection with a single pump running:

a.

The sum of the injection lines flow rates, excluding the highest flow rate, is greater than or equal to 657 gpm for P017 running, 667 gpm for P018 running and 672 gpm for P019 running, and b.

The total pump flow rate is greater than or equal to 900 gpm for P017 running, 913 gpm for P018 running and 918 gpm for P019 running.

SAN ONOFRE-UNIT 2 3/4 5-5 AMENDMENT N0. 73 1

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CONTAINMENTS'YSTEMS

.!3/4.6.2; DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT: SPRAY-SYSTEM LIMITING' CONDITION FOR OPERATION g

3.6.2.1~ Two independent containment spray systems shall be OPERABLE with each spray system capable of. taking suction from the RWST on a Containment Spray-Actuation Signal and automatically transferring suction to the containment-sump on a Recirculation Actuation Signal.

Each spray system flow path'from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY:

MODES 1, 2 and 3.

- ACTION:

' With one containment spray system inoperable, restore the inoperable spray-system.to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;-restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or-be in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position with suction aligned to the RWST.

b.

At least once per refueling interval, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Spray Actuation test signal.

[

2.

Verifying that upon a Recirculation Actuation Test Signal, the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

- SAN ONOFRE-UNIT 2 3/4 6-14 AMENDMENT N0. 73

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CONTAINMENT SYSTEMS-CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION

~3 6 2.3.Two'. independent groups of containment cooling fans shall be.0PERABLE 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.0PERABLE, 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD

, SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Restore both above required

-groups of cooling fans to OPERABLE status within 7 days of. initial loss or be in at least HOT STANDBY within the next 6. hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With one' group of the above required containment cooling fans inoperable and one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ~ Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD-SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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. SURVEILLANCE. REQUIREMENTS l

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.

j b.

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

SAN ONOFRE-UNIT 2 3/4 6-17 AMENDMENT NO. 73

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve (except check valves) specified in Section A and B of Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per refueling interval by verifying that on an ESFAS test signal, each-isolation valve actuates to its isolation position.

l 4.6.3.3 The isolation time of each power operated or automatic valve (except check valves) in Section A and B of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The manual isolation valves specified in Section C of Table 3.6-1 shall be demonstrated OPERABLE in accordance with Specifications 4.6.1.1.a and J

4.6.1.2.d.

)

4.6.3.5 The isolation valves specified in Section D of Table 3.6-1 shall be demonstrated OPERABLE as required by Specification 4.0.5 and surveillance re-quirements associated with those Limiting Conditions for Operation pertaining to each valve or system in which it is installed.

Valves secured ** in the ESFAS actuated position are considered OPERABLE pursuant to this specification.

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- Locked, sealed or otherwise prevented from unintentional operation.

SAN ON0FRE-UNIT 2 3/4 6-19 AMENDMENT NO. 73

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CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS

' LIMITING CONDITION F0'R OPERATION 3.6 4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

i ACTION:

With one hydrogen.recombiner system inoperable, restore the inoperable system

-to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS j;

4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying, during a recombiner system functional test, that the minimum heater sheath temperature

' increases to greater than or equal to 700 F within 90 minutes.

Upon reaching 700 F,. increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or equal to 60 kw.

b.

At least once per refueling by:

1 Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure

=(i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and 3.

Verifying the integrity of the heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for ary heater phase shall be greater than or equal to 10,000 ohms.

SAN ONOFRE-UNIT 2 3/4 6-27 AMENDMENT NO. 73

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UN1TED STATES u

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 N%.... p$

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-15 1.

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

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company,.the City of Riverside, California and the City of Anaheim, California (licensees) dated April 26, October 11, and

.i Uctober 24, 1988, as supplemented March 20, 1988, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable 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 conducted in compliance with the Commission's regulations; 1

D.

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

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

a

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^

^ 2.

- Accordingly, the license is amended by changes. to the Technical Speci-fications as indicated in the attachment to this license amendment, and

paragraph 2.C(2)-of Facility Operating License No. NPF-15 is hereby amende,d.to. read as-follows:

(2)- Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, F

as revised through Amendment No.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION U

h g

George - Knighton rector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May31, 1989 1

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,; a -

ATTACHMENT TO LICENSE AMENDMENT NO. 61 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and. inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of. change.

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

AMENDMENT PAGE OVERLEAF PAGE 1-8 1-7

3/4'1-7 3/4 1-8 3/4'l-20 3/4 1-19 L

3/4 5-2 3/4 5-1 3/4 E-4 3/4 5-3 L

3/4 5-5 3/4 5-6 3/4 6-15 3/4 6-16 3/4 6-18 3/4 6-17 3/4 6-20 3/4 6-19 3/4 6-28 3/4 6-27

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TABLE 1.2 FREQUENCY NOTATION.

NOTATION FREQUENCY 5

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

]

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

W At least once per 7 days.

M At least once per 31 days.

Q At.least once per 92 days.

'l SA At least once per 184 days.

i R

At least once per 18 months.

S/U-Prior to each reactor startup.

l P

Completed prior to each release.

N. A.

Not applicable.

Refueling Interval At least once per 24 months.

1 l

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l SAN ONOFRE-UNIT 3 1-8 AMENDMENT NO. 61 i

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 The following boron injection flowpaths to the RCS via the charging pump (s) shall be OPERABLE:

a.

At least one of the following combinations:

1)

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

2)

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

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

The flow path from the refueling water storage tank.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With fewer than the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore the required boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the required flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.2 The above required flow paths shall be demonstrated OPERABLE:

a.

Intentionally deleted.

b.

At least once per 31 days by verifying that each valve (manual, l

power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

At least once per refueling interval during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a SIAS test signal.

i SAN ONOFRE-UNIT 3 3/4 1-7 AMENDMENT NO. 61

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REACTIVITY CONTROL SYSTEMS 1

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CEA DROP TIME s

LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a. withdrawn position greater than or equal to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion posit. ion with:

a.

T greater than or equal to 520 F, and avg b.

All reactor coolant pumps operating.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With the drop time of any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:

l~

a.

For all CEAs following each removal and reinstallation of the l

reactor vessel head, b.

For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.

At least once per refueling.

i SAN ON0FRE-UNIT 3 3/4 1-20 AMENDMENT NO. 6I o

-4 i

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 i

in the open position.

e.

At least once per refueling interval by verifying that each safety injection 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.

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

gI g

EMERGENCY CORE COOLING SYSTEMS L*

SURVEILLANCE REQUIREMENTS 4.5;2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are

,in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position a.

HV9353_

SDC Warmup CLOSED b.

HV9359 SDC Warmup CLOSED c.

.HV8150 SDC(HX) Isolation CLOSED d.

HV8151 SDC(HX) Isolation CLOSED e.

HV8152 SDC(HX) Isolation CLOSED l

f.

HV8153 SDC(HX) Isolation CLOSED.

g.

.HV0396 SDC Bypass Flow Control CLOSED j

h.

HV8161 SDC(HX) Bypass Flow OPEN j

Isolation i.

Deleted I

j.

Deleted k.

HV9420 Hot Leg Injection CLOSED Isolation 1.

HV9434 Hot Leg Injection CLOSED Isolation zi m.

HV8160 SDC Bypass Flow OPEN Control n.

HV8162 LPSI Miniflow OPEN l

Isolation

.)

o.

HV8163 LPSI Miniflow OPEN l

Isolation j

1 b.

Atlleast once per 31 days by:

1.

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

Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

j c.

By a visual inspection which verifies that no loose debris (rags, trash, j

clothing, etc.) is present in the containment which could be transported j

to the containment sump and cause restriction of the pump suctions i

during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing.

CONTAINMENT INTEGRITY, and 2.

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

j d.

At least once per refueling interval by:

)

1.

Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when RCS pressure is simulated greater than or equal to 715 psia, and that the interlocks j

prevent opening the shutdown cooling system isolation valves When simulated RCS pressure is greater than or equal to 376 psia.

)

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

4' 4

e EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.

e.

At least once per refueling interval, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.

2.

Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:

a.

High-Pressure Safety Injection pump.

b.

Low-Pressure Safety Injection pump.

c.

Charging pump.

3.

Verifying that on a Recirculation Actuation Test Signal, the containment sump isolation valves open; and that on a RAS test signal coincident with a high-high containment sump test signal, all the recirculation valves to the refueling water tank close.

f.

By verifyi.1g that each of the following pumps develops the indicated developed head and/or flow rate when tested pursuant to Specification 4.0.5:

1.

High-Pressure Safety Injection pumps developed head, at an indicated flow rate of 650 gpm, greater than or equal to 2093 feet for P017, 2132 feet for P018 and 2099 for P019 (see NOTE 1).

2.

Low-Pressure Safety Injection pump developed head greater than or equal to 396 feet at miniflow.

3.

Charging pump flow rate greater than or equal to 40 gpm.

g.

By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying the following flow rates:

i l

1.

For High-Pressure Safety Injection pump cold leg injection with a single pump running:

a.

The sum of the injection lines flow rates, excluding the highest flow rate, is greater than or equal to 647 gpm for P017 running, 656 gpm for P018 running, and 661 gpm for P019 running, and b.

The total pump flow rate is greater than or equal to 882 gpm for P017 running, 894 gpm for P018 running, and 901 gpm for P019 running.

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

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST on a Containment Spray Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.

Each spray system flow path from the containment sump shall be via an OPERABLE shutdown cooling heat exchanger.

APPLICABILITY:

MODES 1, 2 and 3.

ACTION:

With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in H01 SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position with suction aligned to the RWST.

b.

At least once per refueling interval, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Spray Actuation test signal.

2.

Verifying that upon a Recirculation Actuation Test Signal, the i

containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

SAN ONOFRE-UNIT 3 3/4 6-15 AMENDMENT NO. 61

u.,3

.a b

i-

'4 CONTAINMENT SYSTEMS

' CONTAINMENT COOLING SYSTEM-n F

~ LIMITING' CONDITION FOR OPERATION 7

3.6.2.3, Two independent groups of containment cooling fans shall be OPERABLE with two fan systems'to each group.

I APPLICABILITY:

MODES l', 2, 3 and 4.

]

~l ACTION:

q 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

. i be in at.least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With two groups of the above required containment cooling fans inoperable, and both containment spray systems OPERABLE, restore at-2 least one group of cooling fans to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

)

or be in'at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD i

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Restore both above required.

groups:of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in

-COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i l

c.

With one. group of the above required containment cooling fans inoperable and one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN' within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

SURVEILLANCE REQUIREMENTS i

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

i 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 refueling interval by verifying that each fan group starts automatically on a Containment Cooling Actuation test signal.

SAN ONOFRE-UNIT 3 3/4 6-18 AMENDMENT NO. 61 i

~

a CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve (except check valves) specified in Section A and B of Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per refueling interval by verifying that on an ESFAS test signal, each isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve (except check valves) in Section A and B of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The manual isolation valves specified in Section C of Table 3.6-1 shall be demonstrated OPERABLE in accordance with Specifications 4.6.1.1.a and 4.6.1.2.d.

4.6.3.5 Tne isolation valves specified in Section D of Table 3.6-1 shall be demonstrated OPERABLE as required by Specification 4.0.5 and surveillance re-quirements associated with those Limiting Conditions for Operation pertaining to each valve or system in which it is installed.

Valves secured ** in the ESFAS actuated position are considered OPERABLE pursuant to this specification.

- Locked, sealed or otherwise prevented from unintentional operation.

SAN ONOFRE-UNIT 3 3/4 6-20 AMENDMENT NO. 61

fQ*

I CONTAINMENT' SYSTEMS g

ELECTRIC HYDROGEN RECOMBINERS

[.

LIMITING CONDITION'FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

. APPLICABILITY:

MODES 1 and 2.

i ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

-l l

SURVEILLANCE REQUIREMENTS

^l 4.6.'4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:

~

a.

At 1 east once per 6 months by verifying, during a.recombiner system functional test, that.the minimum heater. sheath temperature increases to greater than or equal to 700 F within 90 minutes.

Upon 4

reaching 700 F, increase the power setting to maximum power for j

2 minutes and verify'that the power meter reads greater than or equal to 60.kw.

b.

At least once per refueling by:

i 1.

-Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.

'2.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and j

3.

Verifying the integrity of the heater electrical circuits by performing a resistance to ground test following the above required functional test.

The resistance to ground for any

{

heater phase shall be greater than or equal to 10,000 ohms.

l l

i SAN ONOFRE-UNIT 3' 3/4 6-28 AMENDMENT NO.61

__-__d

ML20247R947

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