ML20107D762
| ML20107D762 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-129, NPF-15-A-118) |
| Issue date: | 04/11/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20107D766 | List: |
| References | |
| NUDOCS 9604190023 | |
| Download: ML20107D762 (40) | |
Text
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4 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20555-0001
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l SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY l
1 THE CITY OF RIVERSIDE. CALIFORNIA l
THE CITY OF ANAHEIM. CALIFORNIA DOCKET N0. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 129 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated December 30, 1992, as supplemented by letters dated September 7, 1993, August 17, 1994, and March 7, 1996, complies with the standards and requirements of i
l the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (i) that the activities authorized l
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; l
and 1
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.
9604190023 960411 PDR ADOCK 05000361 P
. 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 amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 129, are hereby incorporated in the license. Southern California Edison Company 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.
l FOR THE NUCLEAR REGULATORY COMMISSION
[b i
Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 11, 1996 I
1
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.129 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 l
Revise Appendix A Technical Specifications, including the issued but not yet implemented Improved Technical Specifications (ITS), 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 areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT l
3/4 7-11*
3/4 7-11*
3/4 7-11a 3/4 7-12*
3/4 7-12*
3/4 7-12a B 3/4 7-3b*
B 3/4 7-3b*
B 3/4 7-3c B 3/4 7-4*
B 3/4 7-4*
l ITS iv ITS iv ITS viii ITS viii ITS 3.7-19a ITS 3.7-19b t
ITS 3.7-19c ITS B 3.7-43c ITS B 3.7-43d ITS B 3.7-43e ITS B 3.7-43f ITS B 3.7-43g ITS B 3.7-43h ITS B 3.7-431 ITS B 3.7-43j l
l
- No changes were made to these pages; reissued for consistency.
PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
i a.
With only one component cooling water loop OPERABLE, restore at least i
two loops 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 4
j 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 i
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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b.
With either one or both trains of the Backup Nitrogen Supply (BNS) system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> restore the BNS system train (s) to
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OPERABLE status or declare the associated CCW loop (s) inoperable.
SURVEILLANCE RE0VIREMENTS l
4.7.3.1 At least two component cooling water loops shall be demonstrated i
j OPERABLE:
At least once per 31 days by verifying that each valve (manual, 1
a.
power operated or automatic) servicing safety related equipment that i
is not locked, sealed, or otherwise secured in position, is in its correct position 3 i
b.
At least once per refueling interval during shutdown, by verifying i
that each automatic valve servicing safety-related equipment actuates to its correct position and each component cooling water pump starts automatically on an SIAS test signal.
3 4.7.3.2 The BNS system shall be demonstrated OPERABLE:
l a.
At least once per 7 days by verifying that at least nine nitrogen gas 4
bottles are installed with a minimum average bottle pressure of 4232 psig.
4 b.
At least once per refueling interval by verifying that the third j
stage pressure regulator of the BNS system is set at 55 psig (i 1.5 l
psi).
I 1
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4 SAN ON0FRE - UNIT 2 3/4 7-11 Amendment No. M,125 i
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PLANT SYSTEMS 3/4.7.3.1 COMPONENT COOLING WATER SAFETY RELATED MAXEUP SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 Two trains of Component Cooling Water (CCW) Safety Related Makeup System shall be OPERABLE with a contained volume in the Primary Plant Makeup Storage Tank at or above the level specified in Figure 3.7-2.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a.
With one CCW Safety Related Makeup flow path inoperable, restore the flow path to OPERABLE status within 7 days.
b.
With the Primary Plant Makeup Storage Tank level less than that required by Figure 3.7-2, and/or both CCW Safety Related Makeup flow paths inoperable, restore the Primary Plant Makeup Storage Tank level and one CCW Safety Related Makeup flow path to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
c.
With Actions a or b, above, not completed in the specified action times, be in 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 be in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.3.1.1 The Primary Plant Makeup Storage Tank shall be demonstrated OPERABLE at least once per 7 days by verifying the contained water volume is within its limits.
4.7.3.1.2 Each CCW Safety Related Makeup flow path shall be demonstrated OPERABLE at least once per 92 days by testing the CCW makeup pumps pursuant to Specification 4.0.5.
4.7.3.1.3 Measure CCW 1eakage at least once per refueling interval.
SAN ON0FRE - UNIT 2 3/4 7-11a Amendment No.129
- - - - - ~ ~ ~ ^
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PLANT SYSTEM 5 I
F4. 7. 4 SALT WATER COOLING SYSTEM l
LIMITING CONDITION FOR OPERATION i
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3.7.4 At least two independent salt water cooling loops shall be OPERABLE.
i 1-APPLICABILITY: PODES 1, 2, 3 and 4.
ACTION:
s i
With only one salt water cooling loop OPERABLE, restore at least two loo i
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 STA j
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUlDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l i
SURVEILLANCE REQUIREMENTS i
4.7.4 At least two salt water cooling loops shall be demonstrated OPERABLE:
i j
At least once per 31 days by verifying that each valve (manual, a.
power operated or automatic) servicing safety related equipment that i
is not locked, sealed or otherwise secured in position, is 16 its correct position.
i j
b.
At least once per refueling interval during shutdown, i
verifying j
that each automatic valve servicing safety-related equ paont actuates to its correct positibn and each salt water cooling pump starts automatically on an SIAS test signal.
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e' i
1' SAN ONOFRE-UNIT 2 3/4 7-12 AMENDMENT NO. 75 1
1 4
4 i
4 i
j l
TOTAL ALLOWABLE CCW LEAKAGE VERSUS THE PPMU TANK LEVEL 1
70 60 l
50 f
./*
i l
9 i
F 30
.i 20-4 10 f 1
01 $$4 i
$ 1'O 1'1 1'2 1'3 1'4 1'5 1'6 1'7 1'8 j
ALLOWABLE LEAKAGE, in gpm i
i i
FIGURE 3.7-2 I
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l j
SAN ONOFRE - UNIT 2 3/4 7-12a Amendment No.129
- PLANT SYSTEMS i
l BASES 3/4.7.1.6 ATMOSPHERIC DUMP VALVES (Continued)
The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not apply when only one ADV is inoperable, and the ADV can be made OPERABLE within the allowed action times. However, with two inoperable ADVs the plant must be
)
placed on shutdown cooling. Therefore, the provisions of Specification 3.0.4 do apply with two inoperable ADVs.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on secondary side steam' generator pressure and temperature i
ensures that the pressure induced stresses in the steam generators do not i
exceed the maximum allowable fracture toughness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RT, of 40*F and are sufficient to prevent brittle fracture.
3 3/4.7.3 COMPONENT COOLING WATER SYSTEM l
The OPERABILITY of the Component Coo 14.ng Water (CCW) system ensures that i
sufficient cooling capacity is availabic. for continued operation of safety i
}
related equipment during normal and accident conditions. The redundant cooling l
capacity of this system, assuming a single failure, is consistent with the i
assumptions used in the accident analyses.
l The CCW system is normally pressurized to maintain the CCW system water-i solid using nitrogen gas supplied to the CCW surge tank by the non-safety related Auxiliary Gas system. Makeup water to the surge tank is normally j
provided by the non-safety related, Nuclear Service Water system to compensate j
for normal system leakagp.
Following a Design Basis Event, both the non-safety related Auxiliary Gas i
System and Nuclear Service Water system are assumed to be unavailable. A postulated Design Basis Event could result in CCW system voiding and a 1
subsequent water hammer.
The Backup Nitrogen Supply (BNS) system is an independent, safety related, Seismic Category I source of pressurized nitrogen for both CCW surge tanks.
The BNS system is designed to minimize CCW system high-point voiding by maintaining the CCW critical loops water-solid during j
Design Basis Event aitigation.
l BNS syster. OPERABILITY ensures that both CCW surge tanks will be pressurized for at least seven days following a Design Basis Event without 1
bottle changeout. The BNS system is required to be OPERABLE whenever the associated train of CCW is required to be OPERABLE. The BNS system i
]
surveillance requirements provide adequate assurance that BN5 system OPERABILITY will be maintained.
I 3/4.7.4 SALT WATER COOLING SYSTEM c
The OPERABILITY of the salt water cooling system ensures that sufficient j
cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the 1
accident analyses.
'3 l
SAN ONOFRE - UNIT 2 B 3/4 7-3b Amendment No. 98,125 1
PLANT SYSTEMS BASES 3/4.7.3.1 COMPONENT COOLING WATER SAFETY RELATED MAKEUP SYSTEM The purpose of the Component Cooling Water Safety Related Makeup System is to provide a safety related, seismically qualified water supply to the CCW following a Design Basis Event.
The Component Cooling Water Safety Related Makeup System for each Unit consists of one Primary Plant Makeup Storage Tank (PPMU Tank) and two makeup flow paths, each supplying the associated CCW critical loop.
Each flow path incorporates one 100% capacity pump and associated remote manually operated valves. Tank T-056 is dedicated to Unit 2 and T-055 is dedicated to Unit 3.
For any point on the curve in Figure 3.7-2, the required water level is based on the associated leak rate from the CCW system, an unrecoverable volume and a level instrumentation Total Loop Uncertainty (TLU).
For example, a leak rate of 18 gpm for seven days corresponds to a volume of 181,440 gallons.
If the TLU and the unrecoverable volume are added to this, the total is 203,100 gallons. Dividing this number by the total tank volume of 303,500 gallons yields 67%.
A CCW Safety Related Makeup System is required to compensate for CCW System leakage out of the CCW system over a period of seven days after Design Basis Event. This seven days requirement is consistent with Standard Review Plan, Section 9.2.2.
Action b includes the following three circumstances:
1.
PPMU Tank level is less than that required by Figure 3.7-2, 2.
Both CCW Safety Related Makeup flow paths are inoperable, and 3.
Both circumstances 1 and 2, above, occur concurrently.
)
SAN ONOFRE - UNIT 2 B 3/4 7-3c Amendment No.129
. PLANT SYSTEMS BASES 3/4.7.5 CONTROL R00M EMERGENCY AIR CLEANUP SYSTEM 1
The OPERK81LITY of the control room emergency air cleanup systes ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous dut personnel during a)y rating for the equipment ahd instrume this system and 2 the control room will remain habitable for operations nd following all credible accident conditions. The OFenABILITY of this system in conjunction with control room design provisions 1.s based on '41aiting the radiation exposure to personnel occupying the control room to 5 nm or less whole body, or its equivalent.
This limitation is consister.t with the requirements of General Design Criteria 19 of Appendix A, 10 CFA 30.
Cumulative operation of the systen with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
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1 I
i e
t i
SAN ONOFRE-UNIT 2 8 3/4 7-4
t TABLE OF CONTENTS I
1 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1 Containment 3.6-1 3.6.2 Containment Air Locks 3.6-3 3.5.3 Containment Isolation Valves.'...........
3.6-8 3.6.4 Containment Pressure................ 3.6-16 3.6.5 Containment Air Temperature 3.6-17 3.6.6.1 Containment Spray and Cooling Systems 3.6-18 3.6.6.2 Containment Cooling System.............
3.6-21 3.6.7 Hydrogen Recombiners 3.6-23 3.6.8 Containment Dome Air Circulators.......... 3.6-25 i
3.7 PLANT SYSTEMS 3.7-1 l
3.7.1 Main Steam Safety Valves (MSSVs)..........
3.7-1 l
3.7.2 Main Steam Isolation Valves (MSIVs) 3.7-5 l
3.7.3 Main Feedwater Isolation Valves (MFIVs) 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs)...........
3.7-9 3.7.5 Auxiliary Feedwater (AFW) System..........
3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) 3.7-16 3.7.7 Component Cooling Water (CCW) System........ 3.7-18 1
3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System 3.7-19a 3.7.8 Salt Water Cooling (SWC) System 3.7-20 3.7.10 Emergency Chilled Water (ECW) 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) 3.7-24 i
3.7.12 Not Used 3.7.13 Not Used 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System 3.7-27 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration 3.7-30 3.7.18 Spent Fuel Assembly Storage 3.7-32 3.7.19 Secondary Specific Activity 3.7-35 3.8 ELECTRICAL POWER SYSTEMS................
3.8-1 3.8.1 AC Sources--Operating 3.8-1 3.8.2 AC Sources--Shutdown................ 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8-20 l
3.8.4 DC Sources--Operating 3.8-23 3.8.5 DC Sources--Shutdown................
3.8-27 3.8.6 Battery Cell Parameters 3.8-30 3.8.7 Inverters--Operating................
3.8-34 3.8.8 Inverters--Shutdown 3.8-36 3.8.9 Distribution Systems--Operating 3.8-38 3.8.10 Distribution Systems--Shutdown...........
3.8-40 l
(continued)
SAN ONOFRE--Unit t 6v Amendment No.129 l
I TABLE OF CONTENTS i
B 3.7 PLANT SYSTEMS B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs).........
B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs)
B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs)
B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs)..........
B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System......... B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120)
B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System.......
B 3.7-39 8 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System B 3.7-43c B 3.7.8 Salt Water Cooling System (SWC)
B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System.......
B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS)...................
B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System.............
B 3.7-63 B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level B 3.7-68 B 3.7.17 Fuel Storage Pool Baron Concentration B 3.7-71 B 3.7.18 Spent fuel Assembly Storage B 3.7-74 B 3.7.19 Secondary Specific Activity B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS...............
B 3.8-1 B 3.8.1 AC Sources-Operating B 3.8-1 B 3.8.2 AC Sources--Shutdown...............
B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air B 3.8-36 B 3.8.4 DC Sources-Operating B 3.8-46 B 3 8.5 DC Sources-Shutdown...............
B 3.8-56 B. 3.6 Battery Cell Parameters B 3.8-60 B 3.8.7 Inverters-Operating...............
B 3.8-67 B 3.8.8 Inverters--Shutdown B 3.8-71 B 3.8.9 Distribution Systems-Operating B 3.8-75 B 3.8.10 Distribution Systems-Shutdown..........
B 3.8-84 B 3.9 REFUELING OPERATIONS.................
B 3.9-1 B 3.9.1 Boron Concentration B 3.9-1 B 3.9.2 Nuclear Instrumentation B 3.9-5 B 3.9.3 Containment Penetrations.............
B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level.........
B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level B 3.9-21 B 3.9.6 Refueling Water Level B 3.9-25 I
II SAN ONOFRE--Unit 2 viii Amendment No.129
CCW Safety Related Makeup System 3.7.7.1 1
3.7 PLANT SYSTEMS 3.7.7.1 Component Cooling Water (CCW) Safety Related Makeup System LCO 3.7.7.1 Two trains of Component Cooling Water (CCW) Safety Related Makeup System shall be OPERABLE with a contair ?d volume in the Primary Plant Makeup Storage Tank 2 the level specified In Figure 3.7.7.1-1.
l i
NOTE----------------------------
LCO 3.0.4 is not applicable.
APPLICABILITY:
MODES 1, 2, 3, and 4.
l ACTIONS l
l CONDITION REQUIRED ACTION COMPLETION TIME i
I A.
One CCW Safety Related A.1 Restore the flow path 7 days Makeup flow path to OPERABLE status.
B.
Two CCW Safety Related D.1 Restore one CCW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Makeup flow paths Safety Related Makeup inoperable.
flow path to OPERABLE status.
OR/AND The Primary Plant 88Q Makeup Storage Tank Level < that required B.2 Restore the Primary by Figure 3.7.7.1-1.
Plant Makeup Storage Tank Level to OPERABLE status.
(continued)
SAN ONOFRE--UNIT 2 3.7-19a AMENDMENT NO.129
CCW Safety Related Makeup System 3.7.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Actions and C.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Times of Conditions A 6HD or B not met.
C.2 Be in MODE 5.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> J
SURVEILLANCE REQUIREMENTS j
SURVEILLANCE FREQUENCY I
'lerify the contained water volume in the 7 days 4
Primary Plant Makeup Storage Tank is within its limits.
f SR 3.7.7.1.2 Verify each CCW Safety Related Makeup In accordance d
System pump develops the required with inservice i
differential pressure on recirculation testing program flow.
4 1
SR 3.7.7.1.3 Measure CCW Leakage.
24 months i
i i
SAN ONOFRE--UNIT 2 3.7-19b AMENDMENT NO.129 4
1
l CCW Safety Related Makeup System 3.7.7.1 l
l l
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TOTAL ALLOWABLE CCW LEAKAGE VERSUS THE PPMU TANK LEVEL 70 60 J
50--
$s A0 o4 30 20 10 f 0
0 1
2 3
4 5
6 7
8 9 10 11 12 13 14 15 16 17 18 ALLOWABLE LEAKAGE, in gpm Figure 3.7.7.1-1 J
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i SAN ONOFRE--UNIT 2 3.7-19c AMENDMENT N0.129
. -.-... - - - - - - - =. - -.-
CCW Safety Related Makeup System B 3.7.7.1 B 3.7 PLANT SYSTEMS B 3.7.7.1 Component Cooling Water (CCW) Safety Related Makeup System BASES BACKGROUND The SONGS Component Cooling Water (CCW) System consists of two independent critical loops (trains) and one non-critical loop (NCL). All-three loops are interconnected, such that the non-critical loop can be aligned to either one of the critical loops.
Each of the two CCW trains is provided with a dedicated pump and a surge tank. A third, swing pump is also provided and can be aligned to either CCW train.
Normal makeup to the CCW trains is provided from the non-safety related, Seismic Category II Nuclear Service Water (NSW) System via the CCW surge tanks.
The safety related makeup system is designed to supply water to the CCW trains following loss of normal CCW makeup from the nuclear service water system.
It is train-oriented and provides sufficient water inventory to accommodate a maximum allowable leakage from both CCW trains for a period of seven days. The CCW safety related makeup system is an integral part of the CCW system.
The CCW safety related makeup system for each Unit consists of one primary plant makeup water (PPMU) storage tank (T-055 for Unit 3 and T-056 for Unit 2) and two makeup transfer trains, each supplying the associated CCW train.
Each transfer train includes a 100% capacity makeup pump, pump discharge solenoid valve, check valve, isolation valves and interconnecting suction and discharge piping. A test loop is provided for each transfer train to enable In-service Testing (IST) of each pump. All components and piping of I
the CCW safety related makeup system are either designed or upgraded to Quality Class II, Seismic Category I.
Power to each transfer train component is provided from independent Class 1E sources.
Makeup to the safety related CCW trains is initiated /
terminated manually on loss of normal CCW makeup capability, as required. The pumps are started / stopped from the Control Room or from the associated Motor Control Center (MCC),
based on the CCW surge tank level indication (remote or i
local). Manual operation of the CCW safety related makeup is acceptable because:
4 i
(continued)
SAN ONOFRE--UNIT 2 B 3.7-43c AMENDMENT NO.129
i CCW Safety Related Makeup Systea B 3.7.7.1 SASES BACKGROUND sufficient time is available after the limiting event (continued) for the operator.to initiate manual action i
l emergency makeup is a continuously supervised
{
operation and continuous safety related CCW surge tank j
level indication is being provided.
4 i
Safety related CCW makeup utilizes the PPMU tank located in
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the Radwaste Building at E1. 9' for each unit as a source of j
makeup water. The PPMU tanks are provided with a floating diaphragm to maintain air tight integrity. This diaphragm is made of elastomer with a specific gravity less than 1.0.
L The nominal capacity of each PPMU tank is 300,000 gallons.
203,800 gallons in tank T-056 and 203,719 gallons in tank i
T-055 are dedicated to the CCW safety related makeup. This 1
amount includes the total tank level instrumentation loop l
uncertainty (TLU) and the unrecoverable volume.
For both tanks, this volume corresponds to the water level at plant j
elevation 30'-9 3/4" (or 65.6% tank level as indicated in i
the Control Room). The dedicated volume-allows makeup for CCW system leakage (from both CCW trains) of up to 18 gpm l
for a period of seven days. The minimum water level l
required in the PPMU tank for the CCW safety related makeup system to be considered OPERABLE is a function of the CCW system total leak rate.
The volume above that controlled by j
the TS is available for the PPMU system use.
A common suction header connects the CCW safety related j
makeup pumps to the PPMU tank at elevation 11'-0".
The i
suction nozzle has a pointing downward elbow attached inside the tank. This is done to increase the tank usable volume 1
and to provide an adequate margin to prevent vortex formation. After transferring the TS volume from the tank, 4
the level of water remaining in the tank is 10" above the
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pump suction nozzle inlet.
j To enable in-service testing of the CCW makeup pumps, a test i
loop capable of passing a flow approximately equal to the nominal makeup flow is provided.
i The high and low level alarms annunciate in the Radwaste j
Control Room on Panel 2/3L-5 at 95% (LSH-7133) and 75% tank i
level (LSL-7133), respectively. The high level alarm also j
annunciates in the main Control Room.
l l
(continued) 1 f
SAN ONOFRE--UNIT 2 B 3.7-43d AMENDMENT NO.129 l
CCW Safety Related Makeup Systea B 3.7.7.1 BASES i
r BACKGROUNO Safety related instruments are required to monitor the CCW 4
(continued) surge tank level. To satisfy the provisions of 10CFR 50, Appendix A, GDC-19, the capability to safely shutdown the plant from outside the Control Room is required. To operate the CCW safety related makeup system from outside the control room, the capability to start /stop the makeup pumps and to monitor the CCW surge tank level is required. QC II, SC I gages are used to monitor the tank level to support j
safe shutdown from outside the Control Room.
All components of_the CCW safety related makeup system are located within the Radwaste Building and Penetration Area (Seismic Category I structures), which are capable of withstanding the impact of tornado generated missiles. The i
only potential path for intrusion of tornado missiles into i
the PPMU tank rooms (127A and 1278) are external access doors AR307 and AR311 in the Radwaste Building east wall.
These metal doors are normally closed and are protected by i
L-shaped, 12" thick concrete enclosures (two walls and a roof).
These enclosures are open to the South in Unit 2 and i
to the North in Unit 3 I
APPLICABLE The CCW safety related makeup system for each. Unit consists SAFETY ANALYSES of one passive component (storage tank) and two redundant transfer trains employing active components. The CCW safety 1
i related makeup system is designed such that passive component failures do not have to be postulated.
Each 4
makeup transfer train is powered from a separate Class IE 1
Bus, the same as the CCW train it supports.
This design j
assures that only one CCW train can be affected by a single i
active component failure within the CCW safety related makeup system.
It is conservatively' assumed that such failure would result in loss of the affected CCW safety related makeup train and eventually in loss of the associated CCW train. The remaining CCW train (critical
~
loop) is available for accident mitigation, as required.
From the safety analysis-perspective, loss of one CCW train is acceptable as shown in the UFSAR Chapter 15 analyses.
However, loss of a CCW train is not a limiting consequence of some single failures within the safety related CCW makeup system.
The limiting consequence of inadvertent / spurious actuation of the CCW safety.related makeup system (makeup j
pump start) is the potential for depletion of the PPMU tank i
water inventory credited for long term accident mitigation, (continued) i l
SAN ON0FRE--UNIT 2 B 3.7-43e AMENDMENT NO. 129 1
4
CCW Safety Related Makeup System B 3.7.7.1 BASES APPLICABLE common for both CCW trains.
Such depletion of the inventory SAFETY ANALYSES would take place should relief valves on the CCW surge tank (continued) lift as a result of tank overfilling and water being discharged from the CCW system-into the plant vent stack.
Makeup water inventory depletion would impact the CCW safety related makeup system capability to perform its safety function.
Operator action is required outside the control room to mitigate the single active failure of a CCW pump motor control relay stuck in the " operate" position, because this failure prevents both pump trip and discharge valve closure using the control switches. The specific mitigating action is to open the respective pump breaker at the MCC in the El.
50' switchgear room.
The assumed above operator action time
(
of 30 minutes is sufficient to mitigate this failure.
l The single tank and common suction nozzle configuration of the CCW makeup system is subject to the single passive failure criteria of ANSI Standard N658-1976, because the system is required to operate for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
post-accident. Concurrent.. passive failures which must be l
considered under this standard are flow path blockage and pressure boundary failures.
Flow path blockage due to entrainment of foreign material is not credible because the system is operated using only filtered and demineralized water.
Furthermore, blockages due to component internal failures are not credible because:
a) there are no valves in the common flow path, and b) the tank diaphragm is made of material with the specific gravity less than 1.0 (closed cell elastomer which would float even if the diaphragm were to disintegrate), and c) the system l
suction line is provided with a pointing downward elbow l
inside the tank (which ensures sufficient submergence of the suction inlet to prevent entrainment of any floating debris even at the maximum suction velocity).
Passive failure of the pressure boundary may be limited to failed valve packing and pump mechanical seals for systems designed and maintained to ASME Section III and Section XI criteria. All such failures in the proposed makeup system can be isolated because the suction isolation valve for each train has a back seat to prevent leakage due to failure of its packing. This valve can be used to isolate all other I
{
(continued) l SAN ONOFRE--UNIT 2 B 3.7-43f AMEN 0 MENT NO.129
CCW Safety Related Makeup System B 3.7.7.1 BASES APPLICABLE packing or seal failures in this train. Therefore, the SAFETY ANALYSES limiting passive failure is a pump shaft seal failure.
(continued)
The design function of the safety related CCW makeup system is to maintain the water inventory in the CCW trains during a 7-day post-accident period.
For this purpose, sufficient water inventory is contained in the single PPMU storage tank for both CCW trains.
From the PPMU tank water is transferred to the CCW return heads by two safety related pumps.
LC0 The water source for the Component Cooling Water Safety Related Makeup System is the PPMU Tank.
The total capacity of each PPMU Tank is approximately 303,500 gallons.
The curve for PPMU Tank volume represents a seven day supply of makeup water at a specific allowable leakage rate from the CCW system. The requirement for seven days is consistent with Standard Review Plan, Section 9.2.2.III.c.
Specification 3.0.4 requires that entry not be made into an OPERATIONAL MODE or other specified condition unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the Action requirements. The exemption from this requirement gives Operations more flexibility to change MODES while still performing required Actions.
Exemption from Specification 3.0.4 will not restrain Operations from changing MODES. The CCW Safety Related Makeup System is only required to support the CCW system in the event of a Design Basis Earthquake.
It should be noted that the CCW system itself does not have a 3.0.~ exemption. Therefore, the CCW system is always OPERABLE during up MODE changes.
The Probabilistic Risk Assessment (PRA) has demonstrated that the allowed outage times specified would result in an acceptably small risk of core damage. Therefore, a 3.0.4 exemption for the CCW Safety Related Makeup System is considered acceptable.
(continued)
SAN ONOFRE--UNIT 2 B 3.7-43g AMENOMENT N0.129
CCW Safety Related Makeup Syste B 3.7.7.1 BASES APPLICABILITY The Component Cooling Water Safety Related Makeup System is a support system to the CCW System.
This means whenever the CCW System is required to be OPERABLE its support system should be OPERABLE also.
In MODES 1, 2, 3, and 4, Technical Specification 3.7.7, " Component Cooling Water" requires "At least two independent component cooling water loops shall be OPERABLE." Therefore, in MODES 1, 2, 3, and 4, the PPMU Tank and both trains of the makeup flow of the Component Cooling Water Safety Related Makeup System shall be OPERABLE.
ACTIONS L.1 With one CCW Safety Related Makeup System's flow path inoperable, action must be taken to restore OPERABLE status within 7 days.
The allowable completion time of 7 days is considered reasonable based on the low probability of a DBE occurring during the 7 days and the redundant capability of the OPERABLE CCW Safety Related Makeup flow path. A Probabilistic Risk Assessment (PRA) was performed to assess the increased risk of core damage from a 7 day allowed 4
outage time for one train of the CCW Safety Related Makeup i
System.
The PRA indicated that the increased risk of core4 damage from a 7 day allowed outage time is less than lx10 per year. This increase in core damage risk is considered acceptable small.
5 B.1 and 8.2 This operating condition is more restrictive than the Action A condition.
If the level in the PPMU Tank drops below that g
4 required to support two CCW critical loops operation for 1
seven days, the condition is similar to loss of both CCW Safety Related Makeup System flow paths. Actions should be taken to restore the PPMU Tank level within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
If both CCW Safety related Makeup flow paths are inoperable, one CCW Safety Related Makeup flow path should be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed completion time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is based on operating experience and a Probabilitic Risk Assessment (PRA).
(continued)
SAN ONOFRE--UNIT 2 B 3.7-43h AMENDMENT N0.129
CCW Safety Related Makeup Systen B 3.7.7.1 i
BASES ACTIONS B.1 and B.2 (continued)
Operating experience shows that the likelihood of Primary Plant Makeup Storage Tank level dropping below 66% (which corresponds to an allowable CCW 1eakage of 18 gpa based on Figure 3.7.7.1-1) is extremely low. 'Also, a Probabilistic Risk Assessment (PRA) was performed to assess the increased i
risk of core damage from an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> allowed outage time for l
two trains of the CCW Safety Related Makeup System. The PRA l
indicated that the increased risk of core damage from an 8 l
hour allowed outage time is less than lx10 per year. This 1
l increase in core damage risk is considered acceptably small.
C.1 and C.2 4
i In MODES 1, 2, 3, and 4, two CCW System critical loops
)
provide cooling to a number of safety related systems, such i
as HPSI, LPSI, shutdown cooling, emergency chillers, etc.
The CCW Safety Related Makeup System is a support system for l
the CCW System. Two CCW Safety Related Makeup flow paths are required to provide. makeup to the two CCW critical l
loops.
If one CCW Safety Related Makeup flow path cannot be i
restored to OPERABLE status in seven days, the Unit must be placed in a MODE in which the LIMITING CONDITION FOR OPERATION does not apply.
To achieve this status, the Unit must be placed 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 I
within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l Similarly, action should be taken if the-PPMU Tank level is below that required for two CCW critical loops operation and/or both CCW Safety Related Makeup flow paths are inoperable.
If both the PPMU Tank level and at least one flow path are not OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the Unit must then be placed in a MODE in which the LIMITING CONDITION FOR OPERATION does not apply. To achieve this status, the Unit must be placed 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 the COLD SHUTDOWN within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The allowed completion Time is consistent with other Technical Specification completion Time requirements to (continued) f SAN ONOFRE--UNIT 2 B 3.7-43i AMENOMENT NO.129
CCW Safety Related Makeup System B 3.7.7.1 BASES ACTIONS C.1 and C.2 (continued) reach the required unit conditions from full power conditions in an orderly manner.
SURVEILLANCE SR 3.7.7.1.1 REQUIREMENTS This SURVEILLANCE REQUIREMENT verifies that the PPMU Tank contains the required volume of makeup water. The 7 days frequency is based on similar SURVEILLANCE REQUIREMENT frequencies. The 7 days frequency is considered adequate in view of other indications in the control room, including alarms, to alert the operator to abnormal PPMU Tank level deviations.
SR 3.7.7.1.2 This SURVEILLANCE REQUIREMENT verifies that the CCW makeup pumps develop sufficient discharge pressure to deliver the required flow to the CCW system from the Primary Plant l
Makeup Tank.
Performance of inservice testing, discussed in I
the ASME Code,Section XI at three month intervals, satisfies this requirement.
SR 3.7.7.1.3 This SURVEILLANCE REQUIREMENT measures CCW 1eakage to ensure j
the PPMU Tank level is adequate in accordance with Figure 3.7.7.1-1.
The specified frequency is considered adequate l
in view of the special alignment required to perform this l
l test. This measurement can be performed only when one CCW critical loop can be removed from service. Therefore, this measurement needs to be performed during refueling outages.
l l
i 1
3 1
SAN ON0FRE--UNIT 2 B 3.7-43j AMENDMENT N0.129
p stoog p%
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20SEH001
\\...../
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEG) GAS AND ELECTRIC COMPANY -
THE CITY OF RIVERSIDE. CALIFORNIA THE CITf 0F ANAHEIM. CALIFORNIA
{0CKET NO. 50-362 SAN _0NQERE_ M CLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. NPF-15 1.
The Nuclear Regulatory Commtssion (the Commission).has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated December 30, 1992, as supplemented by letters dated September 7,1993, August 17, 1994, and March 7, 1996, complies 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 faci?ity will operate in conformity with the application, the provjsions of the Act, and the rules and regulations of the
-Commi s s i on ;
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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
i
, 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 j
amended to read as follows:
)
(2)
Technical Snecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 118, are hereby incorporated in the license.
Southern California Edison Company shall operate the j
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.
FOR THE NUCLEAR REGULATORY COMMISSION Mel B. Fields, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 11, 1996
l l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 118 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications, including the issued but not yet
)
implemented Improved Technical Specifications (ITS), by removing the pages l
identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas l
of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT l
3/4 7-11*
3/4 7-11*
3/4 7-Ila 3/4 7-12*
3/4 7-12*
3/4 7-12a B 3/4 7-3b*
B 3/4 7-3b*
B 3/4 7-3c B 3/4 7-4*
B 3/4 7-4*
ITS iv ITS iv ITS viii ITS viii ITS 3.7-19a ITS 3.7-19b ITS 3.7-19c ITS B 3.7-43c ITS B 3.7-43d ITS B 3.7-43e ITS B 3.7-43f ITS B 3.7-43g ITS B 3.7-43h ITS B 3.7-431 ITS B 3.7-43j i
l l
- No changes were made to these pages; reissued for consistency.
i PLANT SYSTEMS
$/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION i
}
LIMITING CONDITION FOR OPERATION i
3
~
3.7.2 be greater than 90'F when the pressure of the secondary generator is greater than 200 psig.
APPLICABILITY: At all times.
1 ACTION:
With the requirements of the above specification not satisfied:
Reduce the steam generator pressure of the secondary side to less a.
l than or equal to 200 psig within 30 minutes, and b.
Perform an engineering evaluation to determine the effect,of the overpressurization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.
i i
SURVEILLANCE REQUIREMENTS.
\\
4.7.2 The pressure in the secondary side of the steam generators shall be determined to be less than 200 psig at least once per hour when the temperature of the secondary coolant is le'ss than 90'F.
SAN ONOFRE-UNIT 3 3/4 7-11 AMENDMENT NO. 82
PLANT SYSTEMS 3/4.7.3.1 COMPONENT COOLING WATER SAFETY RELATED MAKEUP SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 Two trains of Component Cooling Water (CCW) Safety Related Makeup System shall be OPERABLE with a contained volume in the Primary Plant Makeup i
Storage Tank at or above the level specified in Figure 3.7-2.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
a.
With one CCW Safety Related Makeup flow path inoperable, restore the flow path to OPERABLE status within 7 days.
b.
With the Primary Plant Makeup Storage Tank level less than that required by Figure 3.7-2, and/or both CCW Safety Related Makeup flow paths inoperable, restore the Primary Plant Makeup Storage Tank level l
and one CCW Safety Related Makeup flow path to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l c.
With Actions a or b, above, not completed in the specified action times, be in 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 be in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.3.1.1 The Primary Plant Makeup Storage Tank shall be demonstrated OPERABLE at least once per 7 days by verifying the contained water volume is within its limits.
4.7.3.1.2 Each CCW Safety Related Makeup Flow path shall be demonstrated OPERABLE at least once per 92 days by testing the CCW makeup pumps pursuant to Specification 4.0.5.
i 4.7.3.1.3 Measure CCW 1eakage at least once per refueling interval.
j SAN ON0FRE - UNIT 3 3/4 7-11a Amendment No.118
PLANI SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LINITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.
APPLICABILITY:. MODES 1, 2, 3 and 4.
ACTION:
a.
With only one component cooling water loop OPERABLE, restore at least I
two loops 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 SHUTDOWN 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 either one or both trains of the Backup Nitrogen Supply (BNS) system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> restore the BNS system train (s) to OPERABLE status or declare the associated CCW loop (s) inoperable.
SURVEILLANCE REOUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated l
OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otharwise secured in position, is in its correct position.
b.
At least once per refueling interval during shutdown, by verifying that each autorr.atic valve servicing safety-related equipment actuates to its correct position and each component cooling water pump starts automatically on an SIAS test signal.
4.7.3.2 The BNS system shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that at least nine nitrogen gas bottles are installed with a minimum average bottle pressure of 4232 psig.
b.
At least once per refueling interval by verifying that the third stage pressure regulator of the BNS system is set at 55 psig (i 1.5 psi).
I SAN ON0FRE - UNIT 3 3/4 7-12 Amendment No. 63,114
j I
TOTAL ALLOWABLE CCW LEAKAGE VERSUS THE PPMU TANK LEVEL 70 60 id 50 8 40 k30 20 f
l 0
~
0 1
2 3
4 5
6 7
8 9 101112131415161718 ALLOWABLE LEAKAGE, in gpm l
FIGURE 3.7-2 l
SAN ONOFRE - UNIT 3 3/4 7-12a Amendment No.118 i
PLANT SYSTEMS BASES 3/4.7.1.6 ATMDSPHERIC DUMP VALVES (Continued) the ADVs are subject to inservice testing per Surveillance 4.7.1 3, the frequency of Surveillance 4.7.1.6.1 is based on the length of a /u 1 cycle.
The provisions of Specification 3.0.4 in MODES 2, 3, and 4 do not gply when only one ADV is inoperable, and the ADV can be made OPERABLE within the allowed action times.. However, with two inoperable ADVs the plant must be placed on shutdown cooling.
Therefore, the provisions of Specification 3.0.4 do apply with two inoperable ADVs.
j 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION l
The limitation on secondary side steam generator pressure and temperature i
ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 90*F and 200 psig are based on a steam generator RT, of 60*F and are sufficient to prevent brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM l
The OPERABILITY of the Component Cooling Water (CCW) system ensures that l
sufficient cooling capacity is available for continued operation of safety l
related equipment during normal and accident conditions. The redundant cooling l
capacity of this system, assuming a single failure, is consistent with the l
assumptions used in the accident analyses.
l The CCW system is normally pressurized to maintain the CCW system water-l solid using nitrogen gas supplied to the CCW surge tank by the non-safety related Auxiliary Gas System. Makeup water to the surge tank is normally provided by the non-safety related, Nuclear Service Water system to compensate for normal system leakage.
Following a Design Basis Event, both the non-safety related Auxiliary Gas system and Nuclear Service Water system are assumed to be unavailable. A postulated Design Basis Event could result in CCW system voiding and a subsequent water hammer. The Backup Nitrogen Supply (BNS) system is an l
independent, safety related, Seismic Category I source of pressurized nitrogen j
for both CCW surge tanks. The BNS system is designed to minimize CCW system high-point voiding by maintaining the CCW critical loops water-solid during Design Basis Event mitigation.
l BNS system GPERABILITY ensures that both CCW surge tanks will be pressurized for at least seven days following a Design Basis Event without bottle changeout. The BNS system is required to be OPERABLE whenever the associated train of CCW is required to be OPERABLE. The BNS system surveillance requirements provide adequate assurance that BNS system OPERABILITY will be maintained.
l 3/4.7.4 SALT WATER COOLING SYSTEM The OPERABILITY of the salt water cooling system ensures that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
SAN ONOFRE - UNIT 3 B 3/4 7-3b Amendment No. 80,114
PLANT SYSTEMS BASES 3/4.7.3.1 COMPONENT COOLING WATER SAFETY RELATED MAKEUP SYSTEM The purpose of the Component Cooling Water Safety Related Makeup System is to provide a safety related, seismically qualified water supply to the CCW following a Design Basis Event.
The Component Cooling Water Safety Related Makeup System for each Unit consists of one Primary Plant Makeup Storage Tank (PPMU Tank) and two makeup flow paths, each supplying the associated CCW critical loop.
Each flow path incorporates one 100% capacity pump and associated remote manually operated valves.
Tank T-056 is dedicated to Unit 2 and T-055 is dedicated to Unit 3.
l For any point on the curve in Figure 3.7-2, the required water level is based on the associated leak rate from the CCW system, an unrecoverable volume I
and a level instrumentation Total Loop Uncertainty (TLU).
For example, a leak rate of 18 gpm for seven days corresponds to a volume of 181,440 gallons.
If the TLU and the unrecoverable volume are added to this, the total is 203,100 gallons.
Dividing this number by the total tank volume of 303,500 gallons yields 67%.
A CCW Safety Related Makeup System is required to compensate for CCW System leakage cut of the CCW system over a period of seven days after Design Basis Event. This seven days requirement is consistent with Standard Review Plan, Section 9.2.2.
1 l
Action b includes the following three circumstances:
l 1.
PPMU Tank level is less than that required by Figure 3.7-2, 1
l 2.
Both CCW Safety Related Makeup flow paths are inoperable, and 3.
Both circumstances 1 and 2, above, occur concurrently.
l SAN ONOFRE - UNIT 3 B 3/4 7-3c Amendment No.118
BASES 3/4.7. 5 CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup systes en that 2 for con)tinuous dut the ambient air temperature does not exceed the allowable temperature this systes and 2)y rating for the equipment and instrumentation cooled by the control room will remain habitable for operations personnel during and following all credible accident conditions.
OPERABILITY of this system in conjunction with co The room to 5 rea or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appen 10 CFA 50.
Cumulative operation of the system with the heaters on for at least 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> over a 31-day period is sufficient to reduce the butidup of moisture on the adsorbers and HEPA filters.
l i
4 SAN ONOFRE-UNIT 3 8 3/4 7-4 w
TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1 Containment 3.6-1 3.6.2 Containment Air Locks 3.6-3 3.6.3 Containment Isolation Valves............
3.6-8 3.6.4 Containment Pressure................
3.6-16 3.6.5 Containment Air Temperature 3.6-17 3.6.6.1 Containment Spray and Cooling Systems 3.6-18 3.6.6.2 Containment Cooling System.............
3.6-21 3.6.7 Hydrogen Recombiners 3.6-23 3.6.8 Containment Dome Air Circulators..........
3.6-25 3.7 PLANT SYSTEMS 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)..........
3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs)...........
3.7-9 3.7.5 Auxiliary Feedwater (AFW) System.......... 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) 3.7-16 3.7.7 Component Cooling Water (CCW) System........ 3.7-18 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System 3.7-19a 3.7.8 Salt Water Cooling (SWC) System 3.7-20 3.7.10 Emergency Chilled Water (ECW) 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Fuel Handling Building Post-Accident Clernup Filter System 3.7-27 3.7.15 Not-Used i
3.7.16 Fuel Storage Pool Water Level 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration 3.7-30 i
3.7.18 Spent Fuel Assembly Storage
............ 3.7-32 3.7.19 Secondary Specific Activity 3.7-35 3.8 ELECTRICAL POWER SYSTEMS................
3.8-1 3.8.1 AC Sources-Operating 3.8-1 3.8.2 AC Sources--Shutdown................
3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8-20 3.8.4 DC Sources-Operating 3.8-23 3.8.5 DC Sources-Shutdown................ 3.8-27 3.8.6 Battery Cell Parameters 3.8-30 3.8.7 Inverters-Operating................
3.8-34 3.8.8 Inverters--Shutdown 3.8-36 3.8.9 Distributica Systems-Operating 3.8-38 3.8.10 Distribution Systems-Shutdown...........
3.8-40 (continued)
SAN ONOFRE--Unit 3 iv Amendment No.118
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334Ma9'M a.e 234+**
raLem --
nae 430-^A'>-4 W
TABLE OF CONTENTS B 3.7 PLANT SYSTEMS B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs)......... B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs)
B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs)
B 3.7-13 8 3.7.4 Atmospheric Dump Valves (ADVs).......... B 3.7-17 8 3.7.5 Auxiliary Feedwater (AFW) System......... B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120)
B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System.......
B 3.7-39 8 3.7.7.1 Component Cooling Water (CCW)
Safety Related Makeup System B 3.7-43c B 3.7.8 Salt Water Cooling System (SWC)
B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System....... B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup Systen (CREACUS)................... B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Fuel Handling Building Post-Accident cleanup Filter System.............
B 3.7-63 8 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage B 3.7-74 B 3.7.19 Secondary Specific Activity B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS............... B 3.8-1 8 3.8.1 AC Sources--Operating B 3.8-1 B 3.8.2 AC Sources--Shutdown............... B 3.8-30 B 3.8.3 Diesel Fuel 011, Lube Oil, and Starting Air B 3.8-36 B 3.8.4 DC Sources--Operating B 3.8-46 8 3.8.5 DC Sources--Shutdown............... B 3.8-56 i
B 3.8.6-Battery Cell Parameters B 3.8-60 B 3.8.7 Inverters--Operating................ B 3.8-67 B 3.8.8 Inverters--Shutdown B 3.8-71 B 3.8.9 Distribution Systems--Operating B 3.8-75 8 3.8.10 Distribution Systems--Shutdown..........
B 3.8-84 B 3.9 REFUELING OPERATIONS................. B 3.9-1 B 3.9.1 Boron Concentration B 3.9-1 B 3.9.2 Nuclear Instrumentation B 3.9-5 B 3.9.3 Containment Penetrations.............
B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation--High Water Level.........
B 3.9-16 I
B 3.9.5 Shutdown Cooling (SDC) and Coolant l
Circulation--Low Water Level B 3.9-21 B 3.9.6 Refueling Water Level B 3.9-25
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SAN DNOFRE--Unit 3 viii Amendment No.118 w
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CCW Safety Related Makeup Systea 3.7.7.1 3.7 PLANT SYSTEMS l
3.7.7.1 Component Cooling Water (CCW) Safety Related Makeup System LCO 3.7.7.1 Two trains of Component Cooling Water (CCW) Safety Related Makeup System shall be OPERABLE with a contained volume in the Primary Plant Makeup Storage Tank ;t the level specified in Figure 3.7.7.1-1.
NOTE----------------------------
LCO 3.0.4 is not applicable.
APPLICABILITY:
M00ES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 4
A.
One CCW Safety Related A.1 Restore the flow path 7 days Makeup flow path to OPERABLE status.
i i
B.
Two CCW Safety Related B.1 Restore one CCW 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Makeup flow paths Safety Related Makeup inoperable.
flow path to OPERABLE status.
OR/AND The Primary Plant ANJ Makeup Storage Tank Level < that required P.2 Restore the Primary by Figure 3.7.7.1-1.
Plant Makeup Storage Tank Level to OPERABLE status.
(continued) l l
SAN ONOFRE--UNIT 3 3.7-19a AMENDMENT NO.118
CCW Safety Related Makeup Systea 3.7.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.
Required Actions and C.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Times of Conditions A 8110 or B not met.
C.2 Be in MODE 5.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1.1 Verify the contained water volume in the 7 days Primary Plant Makeup Storage Tank is within.
its limits.
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SR 3.7.7.1.2 Verify each CCW Safety Related Makeup In accordance System pump develops the required with inservice
{
differential pressure on recirculation testing program l
flow.
i SR 3.7.7.1.3 Measure CCW Leakage.
24 months I
SAN ONOFRE--UNIT 3 3.7-19b AMENDMENT N0.118
i CCW Safety Related Makeup System 3.7.7.1 i
TOTAL ALLOWABLE CCW LEAKAGE VERSUS THE PPMU TANK LEVEL 1
70 M
J 50 40 30 20 i
10 f 1
0 0
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 ALLOWABLE LEAKAGE, in gpm Figure 3.7.7.1-1 l
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I SAN ONOFRE--UNIT 3 3.7-19c AMENDMENT N0.118
CCW Safety Related Makeup System B 3.7.7.1 8 3.7 PLANT SYSTEMS 8 3.7.7.1 Component Cooling Water (CCW) Safety Related Makeup System BASES BACKGROUND The SONGS Component Cooling Water (CCW) System consists of two independent critical loops (trains) and one non-critical loop (NCL). All three loops are interconnected, such that the non-critical loop can be aligned to either one of the critical loops.
Each of the two CCW trains is provided with a dedicated pump and a surge tank. A third, swing pump is also provided and can be aligned to either CCW train.
Normal makeup to the CCW trains is provided from the non-safety related, Seismic Category II Nuclear Service Water (NSW) System via the CCW surge tanks.
The safety related makeup system is designed to supply water to the CCW trains following loss of normal CCW makeup from the nuclear service water system.
It is train-oriented and provides sufficient water inventory to accommodate a maximum allowable leakage from both CCW trains for a period of seven days. The CCW safety related makeup system is an integral part of the CCW system.
The CCW safety related makeup system for each Unit consists of one primary plant makeup water (PPMU) storage tank (T-055 for Unit 3 and T-056 for Unit 2) and two makeup transfer trains, each supplying the associated CCW train.
Each transfer train includes a 100% capacity makeup pump, pump discharge solenoid valve, check valve, isolation ~ valves and interconnecting suction and discharge piping. A test loop is provided for each transfer train to enable In-service i
Testing (IST) of each pump. All components and piping of the CCW safety related makeup system are either designed or upgraded to Quality Class II, Seismic Category I.
Power to each transfer train component is provided from independent Class IE sources.
Makeup to the safety related CCW trains is initiated /
terminated manually on loss of normal CCW makeup capability, as required. The pumps are started / stopped from the Control Room or from the associated Motor Control Center (MCC),
based on the CCW surge tank level indication-(remote or local). Manual operation of the CCW safety related makeup is acceptable because:
(continued)
SAN ONOFRE--UNIT 3 B 3.7-43c AMENDMENT NO. 118
CCW Safety Related Makeup System B 3.7.7.1 BASES i
BACKGROUND sufficient time is available after the limiting event l
(continued) for the operator to initiate manual action emergency makeup is a continuously supervised operation and continuous safety related CCW surge tank level indication is being provided.
Safety related CCW makeup utilizes the PPMU tank located in the Radwaste Building at El. 9' for each unit as a source of makeup water. The PPMU tanks are provided with a floating diaphragm to sair.tain air tight integrity. This diaphragm is made of elastomu wM a specific gravity less than 1.0.
The nominal capacity of each PPMU tank is 300,000 gallons.
203,800 gallons in tank T-056 and 203,719 gallons in tank T-055 are dedicated to the CCW safety related makeup. This amount includes the total tank level instrumentation loop uncertainty (TLU) and the unrecoverable volume.
For both i
tanks, this volume corresponds to the water level at plant l
elevation 30'-9 3/4" (or 65.6% tank level as indicated in i
the Control Room). The dedicated volume allows makeup for CCW system leakage (from both CCW trains) of up to 18 gpm for a period of seven days.
The minimum water level required in the PPMU tank for the CCW safety related makeup l
system to be considered OPERABLE is a function of the CCW system total leak rate. The volume above that controlled by the TS is available for the PPMU system use.
l A common suction header connects the CCW safety related makeup pumps to the PPMU tank at elevation 1.1'-0".
The suction nozzle has a pointing downward elbow ettached inside l
the tank. This is done to increase the tank ustble volume and to provide an adequate margin to prevent voris formation. After transferring the TS volume from the tank, the level of water remaining in the tank is 10" above the pump suction nozzle inlet.
To enable in-service testing of the CCW makeup pumps, a test loop capable of passing a flow approximately equal to the nominal makeup flow is provided.
The high and low level alarms annunciate in the Radwaste l
Control Room on Panel 2/3L-5 at 95% (LSH-7133) and 75% tank level (LSL-7133), respectively.
The high level alarm also annunciates in the main Control Room.
(continued)
SAN ONOFRE--UNIT 3 B 3.7-43d AMENDMENT N0.118 l
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CCW Safety Related Makeup System j
B 3.7.7.1 j
l BASES l
BACKGROUND Safety related instruments are required to monitor the CCW (continued) surge tank level. To satisfy the provisions of 10CFR 50, Appendix A, GDC-19, the capability to safely shutdown the plant from outside the Control Room is required. To operate the CCW safety related makeup system from outside the I
control room, the capability to start /stop the makeup pumps and to monitor the CCW surge tank level is required. QC II, SC I gages are used to monitor the tank level to support safe shutdown from outside the Control Room.
All components of the CCW safety related makeup system are located within the Radwaste Building and Penetration Area (Seismic Category I structures), which are capable of withstanding the impact of tornado generated missiles. The i
only potential path for intrusion of tornado missiles into the PPMU tank rooms (127A and 1278) are external access doors AR307 and AR311 in the Radwaste Building east wall.
These metal doors are normally closed and are protected by L-shaped, 12" thick concrete enclosures (two walls and a roof). These enclosures are open to the South in Unit 2 and to the North in Unit 3.
l APPLICABLE The CCW safety related makeup system for each Unit consists SAFETY ANALYSES of one passive component (storage tank) and two redundant transfer trains employing active components. The CCW safety
)
related makeup system is designed such that passive component failures do not have to be postulated. Each makeup transfer train is powered from a separate Class IE Bus, the same as the CCW train it supports..This design assures that only one CCW train can be affected by a single active component failure within the CCW safety related makeup system.
It is conservatively assumed that such failure would result in loss of the affected CCW safety related makeup train and eventually in loss of the associated CCW train. The remaining CCW train (critical loop) is available for accident mitigation, as required.
From the safety analysis perspective, loss of one CCW train is acceptable as shown in the UFSAR Chapter 15 analyses.
However, loss of a CCW train is not a limiting consequence of some single failures within the safety related CCW makeup system. The limiting consequence of inadvertent / spurious actuation of the CCW safety related makeup system (makeup pump start) is the potential for depletion of the PPMU tank water inventory credited for long term accident mitigation, (continued) 4 SAN ONOFRE--UNIT 3 8 3.7-43e AMENDMENT N0.118
CCW Safety Related Mskeup System B 3.7.7.1 BASES APPLICABLE common for both CCW trains.
Such depletion of the inventory SAFETY ANALYSES would take place should relief valves on the CCW surge tank (continued) lift as a result of tank overfilling and water being discharged from the CCW system into the plant vent stack.
Makeup water inventory depletion would impact the CCW safety related makeup system capability to perform its safety function.
Operator action is required outside the control room to mitigate the single active failure of a CCW pump motor control relay stuck in the " operate" position, because this I
failure prevents both pump trip and discharge valve closure using the control switches. The specific mitigating action is to open the respective pump breaker at the MCC in the El.
50' switchgear room. The assumed above operator action time of 30 minutes is sufficient to mitigate this failure.
The single tank and common suction nozzle configuration of the CCW makeup system is subject to the single passive failure criteria of ANSI Standard N658-1976, because the system is required to operate for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
post-accident. Concurrent passive failures which must be considered under this standard are flow path blockage and pressure boundary failures.
4 Flow path blockage due to entrainment of foreign material is not credible because the system is operated using only filtered and demineralized water.
Furthermore, blockages due to component internal failures are not credible because:
a) there are no valves in the common flow path, and b) the tank diaphragm is made of material with the specific gravity i
less than 1.0 (closed cell elastomer which would float even if the diaphragm were to disintegrate), and c) the system suction line is provided with a pointing downward elbow inside the tank (which ensures sufficient submergence of the suction inlet to prevent entrainment of any floating debris even at the maximum suction velocity).
Passive failure of the pressure boundary may be limited to failed valve packing and pump mechanical seals for systems designed and maintained to ASME Section III and Section XI criteria. All such failures in the proposed makeup system can be isolated because the suction isolation valve for each 2
train has a back seat to prevent leakage due to failure of its packing. This valve can be used to isolate all other (continued) 4 i
SAN ON0FRE--UNIT 3 B 3.7-43f AMENDMENT N0.118 1
CCW Safety Related Makeup Systra B 3.7.7.1 BASES APPLICABLE packing or seal failures in this train. Therefore, the SAFETY ANALYSES limiting passive failure is a pump shaft seal failure.
(continued)
The design function of the safety -related CCW makeup system is to maintain the water inventory in the CCW trains during a 7-day post-accident period.
For this purpose, sufficient water inventory is contained in the single PPMU storage tank for both CCW trains.
From the PPMU tank water is transferred to the CCW return heads by two safety related l
pumps.
i LCO The water source for the Component Cooling Water Safety Related Makeup System is the PPMU Tank. The total capacity of each PPMU Tank is approximately 303,500 gallons.
The curve for PPMU Tank volume represents a seven day supply of makeup water at a specific allowable leakage rate from the CCW system. The requirement for seven days is consistent with Standard Review Plan, Section 9.2.2.III.c.
Specification 3.0.4 requires that entry not be made into an OPERATIONAL MODE or other specified condition unless the l
conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the Action requirements. The exemption from this requirement gives Operations more flexibility to change MODES while still performing required Actions.
Exemption from Specification 3.0.4 will not restrain Operations from changing MODES. The CCW Safety Related Makeup System is only required to support the CCW system in the event of a Design Basis Earthquake.
It should be noted that the CCW system itself does not have a 3.0.4 exemption. Therefore, the CCW system is always OPERABLE during up MODE changes. The Probabilistic Risk Assessment (PRA) has demonstrated that the allowed outage times specified would result in an acceptably small risk of core damage. Therefore, a 3.0.4 exemption for the CCW Safety Related Makeup System is considered acceptable.
(continued)
SAN ONOFRE--UNIT 3 B 3.7-43g AMENDMENT N0.118 l
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CCW Safety Related Makeup Systca B 3.7.7.1
]
BASES APPLICABILITY The Component Cooling Water Safety Related Makeup System is a support system to the CCW System. This means whenever the CCW System is required to be OPERABLE its support system should be OPERABLE also.
In MODES 1, 2, 3, and 4, Technical Specification 3.7.7, " Component Cooling Water" requires "At least two independent component cooling water loops shall be OPERABLE." Therefore, in MODES 1, 2, 3, and 4, the PPMU Tank and both trains of the makeup flow of the Component Cooling Water Safety Related Makeup System shall be OPERABLE.
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ACTIONS Ad l
With one CCW Safety Related Makeup System's flow path inoperable, action must be taken to restore OPERABLE status within 7 days.
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The allowable completion time of 7 days is considered l
reasonable based on the. low probability of a DBE occurring during the 7 days and the redundant capability of the OPERABLE CCW Safety Related Makeup flow path. A Probabilistic Risk Assessment (PRA) was performed to assess the increased risk of core damage from a 7 day allowed outage time for one train of the CCW Safety Related Makeup i
System. The PRA indicated that the increased risk of core4 damage from a 7 day allowed outage time is less than 1x10 per year. This increase in core damage risk is considered acceptable small.
B.1 and B.2 This operating condition is more restrictive than the Action A conditior,.
If the level in the PPMU T64k drops below that required to support two CCW critical loops operation for seven days, the condition is similar to loss of both CCW Safety Related Makeup System flow paths. Actions should be taken to restore the PPMU Tank level within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
If both CCW Safety related Makeup flow paths are inoperable, one CCW Safety Related Makeup flow path should be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The allowed completion time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is based on operating experience and a Probabilitic Risk Assessment (PRA).
(continued)
SAN ONOFRE--UNIT 3 B 3.7-43h AMENDMENT NO. 118
f CCW Safety Related Makeup System B 3.7.7.1 i
BASES ACTIONS B.1 and B.2 (continued)
Operating experience shows that the likelihood of Primary Plant Makeup Storage Tank level dropping below 66% (which corresponds to an allowable CCW 1eakage of 18 gpm based on Figure 3.7.7.1-1) is extremely low. Also, a Probabilistic l
Risk Assessment (PRA) was performed to assess the increased risk of core damage from an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> allowed outage time for two trains of the CCW Safety Related Makeup System. The PRA l
indicated that the increased risk of core damage from an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> allowed outage time is less than 1x10 per year. This 4
increase in core damage risk is considered acceptably small.
l C.1 and C.2 l
l In MODES 1, 2, 3, and 4, two CCW System critical loops l
provide cooling to a number of safety related systems, such as HPSI, LPSI, shutdown cooling, emergency chillers, etc.
The CCW Safety Related Makeup System is a support system for the CCW System. Two CCW Safety Related Makeup flow paths are required to provide makeup to the two CCW critical loops.
If one CCW Safety Related Makeup flow path cannot be r
l restored to OPERABLE status in seven dayt., the Unit must be l
placed in a MODE in which the LIMITING CONDITION FOR l
OPERATION does not apply.
To achieve this status, the Unit must be placed 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Similarly, action should be taken if the PPMU Tank level is below that required for two CCW critical loops operation i
and/or both CCW Safety Related Makeup flow paths are inoperable.
If both the PPMU Tank level and at least one flow path are not OPERABLE within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the Unit must then be placed in a MODE in which the LIMITING CONDITION FOR OPERATION does not apply. To achieve this status, the Unit must be placed 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 the COLD SHUTDOWN within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The allowed completion Time is consistent with other Technical Specification completion Time requirements to I
(continued)
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SAN ONOFRE--UNIT 3 B 3.7-431 AMENDMENT NO.118 l
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CCW Safety Related Makeup Systea B 3.7.7.1 BASES ACTIONS C.1 and C.2 (continued) reach the required unit conditions from full power conditions in an orderly manner.
SURVEILLANCE SR 3.7.7.1.1 REQUIREMENTS This SURVEILLANCE REQUIREMENT verifies that the PPMU Tank contains the required volume of makeup water. The 7 days frequency is based on similar SURVEILLANCE REQUIREMENT j
frequencies. The 7 days frequency is considered adequate in view of other indications in the control room, including alarms, to alert the operator to abnormal PPMU Tank level deviations.
i SR 3.7.7.1.2 This SURVEILLANCE REQUIREMENT verifies that the CCW makeup pumps develop sufficient discharge pressure to deliver the required flow to the CCW system from the Primary Plant Makeup Tank.
Performance of inservice testing, discussed in l
the ASME Code,Section XI at three month intervals, j
satisfies this requirement.
i f
l This SURVEILLANCE REQUIREMENT measures CCW 1eakage to ensure j
the PPMU Tank level is adequate in accordance with Figure 3.7.7.1-1.
The specified frequency is considered adequate in view of the special alignment required to perform this l
test. This measurement can be performed only when one CCW critical loop can be removed from service.
Therefore, this i
measurement needs to be performed during refueling outages.
i REFERENCES None.
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SAN ONOFRE--UNIT 3 B 3.7-43j AMENDMENT NO.118
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