Text

Amends 79 & 67 to Licenses NPF-10 & NPF-15,respectively, Changing Surveillance Interval for Tech Specs Re Turbine Overspeed Protection,Rcs Leakage & Operational Leakage from 18 Months to Each Refueling Interval
	ML19327C247
Person / Time
Site:	San Onofre
Issue date:	11/09/1989
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
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ML19327C248	List: ML19327C247;
References
	NUDOCS 8911210298
	Download: ML19327C247 (17)
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'o UNITED STATES

.:. 8 NUCLEAR REGULATORY COMMISSION J.

t WASHihG TON, D. C. 20'iS5

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l SOUJERN. CALIFORNIA. EDISON. COMPANY SAN.DIEGO. GAS AND. ELECTRIC.CONPANY THE. CITY OF. RIVERSIDE.. CALIFORNIA THE CITY OF ANAHEIN. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79

. License No. NPF-10 1.

TheNuclearRegulatoryCommission(theCommission)hasfoundthat:

e A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by' SouthernCaliforniaEdisonCompany(SCE)onbehalfofitself and San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (licensees) dated October 11, 1988, December 19, 1988 and December 28, 1988 comply with the standards and requirements of the Atomic Energy Act of 1954, as amendec (the Act), and the Comission'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; L

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 1-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 L

51 of the Commission's regulations and all applicable requirements L

have been satisfied.

1.

8911210298 8911op DR ADOCK 05000361 p

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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 I~'

paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:

(2) Technical Specification The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.79, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan..

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Geor g ht, Dir r

Proj l Directof' ate 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 9, 1989 I

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ATTACHMENT TO LICENSE. AMENDMENT.NO. 79 -

Y FACILITY OPERATING LICENSE N0..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 PAG _E OVERLEAF PAGf.

3/4 3-7b 3/4 3-7b 3/4 4-16 3/4 4-15 3/4 4-18 3/4 4-17

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INSTRUMENTATION L

3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY:

MODES 1, 2* and 3.*

ACTION:

With one stop valve or one control valve per high pressure turbine a.

steam lead inoperable and/or with one reheat stop valve or one I

reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the above required turbine overspeed protection system otherwise inoperable,.within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE:

At least once per 7 days by' cycling each of the following valves a.

through at least one complete cycle from the running position.

1.

Four high pressure turbine stop valves.

2.

Four high pressure turbine control valves.

3.

Six low pressure turbine reheat stop valves.

4.

Six low pressure turbine reheat intercept valves.

b.

At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position.

c.

At least once per refueling interval by performance of a CHANNEL l

CALIBRATION on the turbine overspeed protection systems.

d.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or Corrosion.

With any main steam line isolation valve and/or any main steam line isolation valve bypass valve not fully closed.

SAN ON0FRE-UNIT 2 3/4 3-76 AMENDMENT NO. 79 1

b-REISS' D 5/2E7?4 L

INSTRL> MENT ATION LOCSE-pART DETECTION' INSTRUMENTATION

' LIMITING CONDITION FOR OPERATION 3.3.3.10 The loose part detection system shall be OPERABLE.

APDL:CABILI2:

MODES 1 and 2.

. ACTION:

a.

With o'ne or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per refueling interval.

l SAN ONOFRE-UNIT 2 3/4 3-75 AMENDMENT NO. 75 m.

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Z oz TABLE 4.4-2 om

o rri STEAM GENERATOH TUBE IftSPECTION C

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-t IST SAasPLE INSPECTION 2ND SAllePLE INSPECTION 3RD SAaIPLE INSPECTION Sample Site Result Action Reiguired Result -

Action Herter ed Result Action Rerquwed I

A mmamum of C-1 None N/A N/A N/A N/A S Tubes per S. G.

C-2 Plug defective tubes C-1 None N/A N/A 8'd ""P'C' # d Plug defectsve tubes C-1 None 25 tubes in this S. G.

C-2 and inspect additional C-2 Ph1 defective tubes 45 tubes m thes S. G.

Perform action for j

C-3 C-3 result of fws to sample i

A Perform action for C-3 C-3 result of fwst N/A N/A AO samth i

e C-3 li% all tubes in Alt other this S. G., plug de S. G.s are None

. N/A N

tective tubes and C-1 sospect 2S tubes in Some S. G.s each other S. G-Perform action for N/A N/A C-2 but no i

C-2 reseA of second additional 3,,ps, Prornpt notification S. G. are I

to NRC pursuant C-3 to specification Additional Inspect all tubes in i

6.9.1 S. G. is C-3 each S. G. and plug defective tesbes.

Prompt notifict.teon N/A N/A to NRC pursuant to gsecaiscation 6.9.8 1

3,3 h Where N is the number of steem generators in the unit, and n is the number of steem generators wupected n

diaring an inspection t

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REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS' LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

A containment atmosphere particulate radioactivity monitoring a.

system, b.

A containment sump inlet flow monitoring system, and A containment atmosphere gaseous radioactivity monitoring system.

c.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous or particulate radioactivity monitoring system is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.5.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere particulate monitoring system performance of a.

CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment sump inlet flow monitoring system performance of CHANNEL CALIBRATION at least once per refueling interval, l

Containment atmosphere gaseous monitoring system performance of c.

CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3.

SAN ONOFRE - UNIT 2 3/4 4-16 AMEN 0 MENT NO. 79

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REACTOR COOLANT SYSTEM L

U 0PERATIONAL LEAGGE LI"! TING COT! TION 004 OPERATION 3.4.5.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESEURE E0'.;h0aRY LEAKAGE, b.

1 gpm UN.'".ci',T!FIED LE AGGE,

c.

1 gp.? total pr.i.mery-to-secc.dary leaxage througn all steam generators

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and 720 gallons per day througn any one steam generator, d.

10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and 1 GFM leakage at a Reactor Coolant System prass.tre of 2235 e.

20 psig frcm any Rea: tor Cociant System Pressure Isolation Valve spe:ifie:

'i n Ta::l e 3. 4-1.

' APPLICABILITY: MODES 1, 2, 3 and 4 ACTICN:

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDEY a.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in' COLD SHUTO0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

.b.

With any Reactor Coolant System leakage greater than any one of toe

' Mits, excluding PRESSURE EOUNDARY LEAKAGE and leakage frcm Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 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 SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

s With any Reactor Coolant System Pressure Isolation Valve leakage c.

greater than the above limit, isolate the high pressure portion of the affected system from the icw pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or ceactivated automatic valves..

or be in at least HUT 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 REOUIREMENTS 4.4.5.2.1' Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

Monitoring the containment atmosphere gaseous or particulate a.

radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Monitoring the containment sump inlet flow at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SAN ONOFRE-UNIT 2 3/4 4-17 e

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,.i REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Performance of a Reactor Coolant System water inventory balance at c.

'least once.per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.5.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in' Table 3.4-1 shall be demonstrated OPERABLE by verifying valve leakage to be L

within.its limit:

a.

At least once per refueling interval.

l b.

Prior to entoring MODE 2 whenever the plant has been in COLD SHUTOOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performed in the previous 9 months.

Prior to declaring the valve operable following maintenance, repair c.

or replacement work on the valve, d.

Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months following valve actuation due to automatic or manual action or flow through the valve (for valves in Section B of Table 3.4-1).

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

r SAN ON0FRE - UNIT 2 3/4 4-18 AMEN 0 MENT NO. 79

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.'6 UNITED STATES t. ' !I g

NUCLEAR REGULATORY COMMISSION Ta cj WASHINGTON, D. C. 20555

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SOUTHERN CALIFORNIA EDISON. COMPANY SAN DIEGO GAS AND-ELECTRIC. COMPANY THE. CITY OF. RIVERSIDE CALIFORNIA u

E CITY OF ANAHEIN. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING. STATION.. UNIT,NO. 3 AMENDMENT T0; FACILITY.0PERATING. LICENSE Amendment No. 67 License No. NPF-15 1.

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

A.

The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself l

and San Diego Gas and. Electric Company, the City of Riverside, California'and the City of Anaheim, California-(licensees) dated October 11, 1988, December 19,'1988-and December 28, 1988 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 4

regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the applications, B.

the provisions of the Act, and the regulations of the Commission; 1

C.

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health i

and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; i

l D.

The issuance of this amendment will not be inimical to the comon

(

defense and security or to the health and safety of the public; and b

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.

l 1

1.

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3 2.

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

(2) Technical Specificati g The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 67, 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 George /. dt'

/k Knighton irector Proje6t Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical j

' Specifications Date of Issuance: November 9, 1989

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i ATTACHMENT TO LICENSE AMENDMENT NO. 67 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 anendment nunber and contain marginal lines indicating the area of change.

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

AMEhDMEN1 PACE OVERLEAF PAGE 3/4 3-77 3/4 4-17 3/4 4-18 3/4 4-19 3/4 4-20

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INSTRUMENTATION

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3/4.3.4 TURBINE OVERSPEED PROTECTION E

LIMITING CONDITION'FOR OPERATION

{

3.3.4 '. At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY:

MODES 1, 2* and 3^.

i L

ACTION:

i With one stop valve or one control valve per high pressure turbine a.

steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

b.

With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE:

At.least once per 7 days by cycling each of the following valves j

a.

through at least one complete cycle from the running position.

1.

Four high pressure turbine stop valves.

l 2.

Four high pressure turbine control valves.

3.

Six low pressure turbine reheat stop valves, j

4.

Six low pressure turbine reheat intercept valves, b.

At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running i

position.

I g

c.

At least once per refueling interval by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.

l d.

At least once per 40 months by disassembling at least one of each of q

the above valves and performing a visual and surface inspection of 4

valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

A With any main steam line isolation valve and/or any main steam line isolation valve bypass valve not fully' closed, t

SAN ON0FRE - UNIT 3 3/4 3-77 AMENDMENT NO.67 I

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REACTOR COOLANT SYSTEM 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.5.1 The following Reactor Coolant System'1eakage detectior, systems shall be OPERABLE:

A containment atmosphere particulate radioactivity monitoring a.

1

system, b.

A containment sump inlet flow monitoring system, and A containment atmosphere gaseous radioactivity monitoring system.

c.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous or particulate radioactivity monitoring system is inoperable; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in-COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.5.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere particulate monitoring system performance of a.

CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment sump inlet flow monitoring system performance of CHANNEL CALIBRATION at least once per refueling interval.

l Containment atmosphere gaseous monitoring system performance of c.

CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3.

SAN ONOFRE-UNIT 3 3/4 4-17 AMENDMENT NO. 67

ns.

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L REACTOR COOLANT SYSTEM L

OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.5.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 gpm UNIDENTIFIED LEAKAGE, c.

I gpm total primary-to-secondary leakage through all steam generators and 720 gallons per day through any one steam generator, i

d.

10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.

1 GPM leakage at a Reactor Coolant System pressure of 2235 1 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

L a.

.With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY I

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

I b.

With any. Reactor Coolant System leakage greater than any one of the limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor l

Coolant System Pressure Isolation Valves, reduce the leakage rate to 1

l within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within j

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 .

l c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by l

use of at least two closed manual or deactivated automatic valves, 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 l

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

SURVEILLANCE REQUIREMENTS I

4.4.5.2.1 Reactor Coolant System leaktges shall be demonstrated to be within i

each of the above limits by:

a.

Monitoring the containment atmosphere gaseous or particulate i

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

l

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b.

Monitoring the containment sump inlet flow at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

s SAN ONOFRE-UNIT 3 3/4 4-18

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o REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

Performance of a Reactor Coolant Systen water inventory balance at.

c.

least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

Monitoring the reactor head flange leakoff system at least once per

'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.5.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in-Table 3.4-1 shall be demonstrated OPERABLE by verifying valve-leakage to be within its limit:

9 a.

At least once per refueling interval.

E b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or more and if leakage testing has not been performed in the previous 9 months.

Prior to returning the valve to service following maintenance, c.

repair or replacement work on the valve.

d.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve (for valves in Section B of Table 3.4-1).

The provisions of Specifice* ion 4.0.4 are not applicable for entry into MODE 3 or 4.

SAN ON0FRE-UNIT 3 3/4 4-19 AMENDMENT NO. 67 e

f, 4

TABLE 3.4 1 t /.

REACTOR COOLANT SYSTEM PRESSURE !$0LATf0N VALVES I

SECTION A 3-018-A-551 HPSI Check 3-019-A 551 HPSI Check 3-020-A-551 HPS! Check 3-021 A-551-HPSI Check 3-152-A-551 Hot leg injection to loop #1 3-156-A 551 Hot leg injection to loop #2 3-157-A-551 Hot leg injection check 3 158 A-551 Hot leg injection check 3 HV-9337 SDC Suction Isolation 3 HV-9339 SDC Suction Isolation 3 HV-9377 SDC Suction Isolation 3 HV-9378 500 Suction isolation SECTION B 8-072 A-552 LPSI Check 8-073-A-552 LPSI Check 8-074-A-552 LPSI Check 8-075-A-552 LPSI Check 12-027-A 551*

Cold leg injection to ioop #1A 12-029-A b51*

Cold leg injection to loop #1B 12-031-A-551*

Cold leg injection to loop #2A 12-033-A-551*

Cold leg injection to loop #2B 12-040-A-551 SIT Check 12-041-A-551 SIT Check 12-042-A-551 SIT Check 12-043-A-551 SIT Check Redundant to LPSI and SIT checks SAN ONOFRE-UNIT 3 3/4 4-20 i

l

ML19327C247

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