ML20085K411
| ML20085K411 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/01/1991 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085K416 | List: |
| References | |
| NUDOCS 9110310067 | |
| Download: ML20085K411 (22) | |
Text
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION k(Jhf, WASHINGTON. o C 20%5 y
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SOUTHERN CALIFORillA EDISON COMPAt4Y SAN DIEGO GAS At1D ELECTRIC COMPANY THE CITY OF RIVERS 10E, CAllf0RNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO S0-361 SAN Ot:0FRE NUCLEAR GENERATING STATION, UNIT t10. 2 AttENDPENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No Npf-10 1.
The Nuclear Regulatory Commission (the Conmission) hos found that:
A.
The application for amendment by Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside,) (the California, and the City of Anaheim, California (licensees licensee) dated June 17, 1991, 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 facility will operate ir, conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authoriked 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
'seen satisfied.
911o310067 m too t ADOCK0500(]},.jl PDR P
_-_-_-________-_-___-_____n_--__-____-
2 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 flo. NPF-10 is hereby amended to read as follows:
(?) Technical Specifications The Technical Specifications contained in Appendix A and the Envircnmental Protection Plan contained in Appendix B, as revised through Amendment flo.
99, are hereby incorporated license.
Southern California Edison Company shall operate t ity in accordance with the Techtlical Specifications and u conmental Protection Plan.
3.
This license amendment is effective as of the date of its i;.uanta and must be fully implemented no later than 30 days frofu the date of issuance.
FOR THE t40 CLEAR REGULATORY C0!'MISS10f1 k.
k James E. Dyer, Director Project Directorate V Division c f Reactor Projects 111/IV/V Offfce of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 1. 1991 t
. _ - ~ _ _. _.
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 09 TO FACILITY OPERATING LICENSE P0. NPF.10, DOCKET NO. 50 361 i
Revise Appendix A Technical Specifications by removing the pages identified
^
below and inserting the enclosed pages. The revised pages are identified by the captioned amendrnent number and contain rnarginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document conpleteness.
REMOVE INSERT 3/4 7 4 3/4 7-4 3/4 7 5 3/4 7 5 3/4 7.Sa 3/4 7 5b 8 3/4 7 2 B 3/4 7 2 B 3/4 7 2a I
1 5
i
(
____.___m 4
4 1
PLANT SYSTEMS I
AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2.1 At least three independent s'.n generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
Two motor-driven auxiliary feedwater pumps, each capable of being a.
powered from separate emergency busses, b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system, and c.
Manual valves in the correct position and automau c valves each capable of being opened and closed, with the following exceptions:
1.
Motor-driven auxiliary feedwater pump discharge bypass control valves, HV-4762 and HV-4763, need only be capable of being
- closed, i
2.
Steam turbine-driven auxiliary feedwater pump steam supply isolation valves, HV-8200 and HV-8201, and turbine stop valve, HV-47;S, need only be capable of being opened, and 3.
Manual crosstie valves 1305MV634 and 130MU635 may be open in Mode 3 provided a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> has elapsed since reactor shutdown.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
With one auxiliary feedwater pump or its asscciated flow path inoper-able, restore the required auxiliary feedwater pump and its associated flow path 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 HOT SHUT 00WN within the follow-ing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With either two auxiliary feedwater pumps, twn flow paths, or one pump and one separate flow path inoperable, be in at least HOT STANDBY within G hours and in HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, c.
With three auxiliary feedwater pumps or flow paths inoperable, immed-intely initiate corrective action to restore at laast one auxiliary feedwater pump and its associated flow path to OPERABLE status as soon as possible.
d.
With an automatic valve in any flow path incapable of closing upon receipt of a Main Steam Isolation Signal, closn the affected valve or its block valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and enter actions a, b, or c if r
there is a loss of the flow paths (s).. Testing pursuant to Technical Specification 3.3.2 does not constitute entry into this ACT:vN Statement.
SAN ONOFRE-UNIT 2 3/4 7-4 AMENDMENT NO. 99 s.
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2.1.1 Each auxiliary feedwater pump and associated flow path shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Testing the turbine driven pump and both motor driven pumps pursuant to Specification 4.0.5.
The provisions of Specification 4.0.4 are not applicable for the turbine driven pump for entry into MODE 3.
2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwite secured in position, is in its correct position.
3.
Verifying that both manual valves in the suction lines from the priniary AFW supply tank (condensate storage tank T-121) to each AFW pump, and the manual discharge line valve of each AFW pump are locked in the open position.
4.
Verifying that the AFW piping is full of water by venting the accessible discharge piping high points, b.
At least once per refueling interval during shutdown by:
1.
Verifying that each automatiet valve in the flow path actuates to its correct position upun receipt of an EFAS test signal.
2.
Verifying that each motor driven pump starts and the steam inlet valves to the turbine driven pump open automatically upon receipt of an EFAS test signal, 3.
Verifying that each automatic valve in the flow path actuates to it: correct position upon receipt of a MSIS test signal except-for HV-8200 and HV-8201, 4.7.1.2.1.2 The auxiliary feedwater system shall be demonstrated OPERABLE prior l
to entering MODE.2 following each COLD SHUTDOWN by performing a flow test to verify the normal flow path from the primary AFW supply tank (condensate stor-age tank T-121)_through each auxiliary feedwater pump to its associated steam generator.
SAN ONOFRE-UNIT 2 3/4 7-5 AMENDMENT N0. 99 1
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM-HOT SHUTDOWN LI_MITING CONDITION FOR OPERATION 3.7.1.2.2 At least one motor-driven auxiliary feedwater pump and associated flow path per steam generator required by LCO 3.4.1.3 (Reactee Coolant System
- Hot Shutdown) shall be OPERABLE with; a.
a motor driven auxiliary feedwater pump, and b.
Manual valves in the correct position and automatic valves each capa' ole of being opened and closed, with the following exceptions:
1.
Motor-driven auxiliary feedwater pump discnarge bypass control valves, HV-4762 and HV-4763, need only be capable of being closed; and 2.
Manual crosstie valves 1305MU634 and 1305MU635 may be open.
APPLICABILITY:
MODE 4 with a steam generator being used for decay heat removal.
ACTION:
With no auxiliary feedwater pump or its associated flow path OPERABLE as required to satisfy LC0 3.4.1.3, restore the required auxiliary feedwater pump (s) and flow path (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SAN ONOFRE-UNIT 2 3/4 7-Sa AMENDMENT NO. 99
- - -.. ~ -.--
I PLANT SYSTEMS-SURVEILLANCE REQUIREMENTS 4.7.1.2.2.1 Each auxiliary feedwater pump and flow path shall be oemonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Testing the required motor driven pump (s) pursuant to Specification 4.0.5 2.
Verifying that each valve (manual, power operated or automat 1c) in the required flow path (s) that is not locked, sealed, or otherwise secured in position, is in its correct position.
3.
Verifying that both manual valves in the suction lines from the pri,,ary AFW supply tank (condensate storage tank T-121) to each required AFW pump, and the manual discharge line valve of each required AFW pump are lockeo in the open position.
4.
Verifying that the AFW piping is full of water by venting the accessible discharge piping high points on the required flow paths.
-5AN ON0FRE-UNIT 2 3/4 7-5b AMEN 0 MENT NO. 99 a.
4 3/4.7 PLANT SYSTEMS
{
BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam safety valves (MSSVs) ensures that the secondary system pressure will not exceed 110% (1210 psia) of its design pressure of 1100 psia during the most severe anticipated system operational transient. The total relief capacity available is greater than the maximum steam flow required after a turbine trip from 102% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink.
The MSSV lift setpoints are staggered, as shown in Table 3.7-1, such that only those valves needed for pressure relief will actuate.
The MSSV lift settings and relieving capacities meet the requirements of Section III of the ASME Boiler and Pressure Vessel Code, 1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A).
The total available relieving capacity for all valves on all of the steam lines is 15,473,628 lbs/hr at 1190 psia.
A minimum of one OPERABLE-safety valve per steam generator ensures that sufficient relieving capacity is available for removing decay heat.
STARTUP and/or POWER OPERATION is allowable with safety '/alves inoperable within the limitations of the ACTION requirements on the basis of the reduc-i tion in secondary system steam flow and THERMAL POWER required by the reduced i
reactor trip settings of the Pown Level-High channels.
The reduced reactor trip allowable values are derived on the followingfuases:
]
3p, (X) - (Y)(V) x 111.0 X
where:
j SP = reduced reactor trip allowable value in percent of RATED THERMAL POWER.
.--V = maximum number of inoperable safety valves per steam line.
i i
111.0 = Power Level-High Trip allowable value from Table 2.2-1.
X = Total relieving capacity of all safety valves per steam line in 1bs/ hour (7,736,814 lbs/hr at 1190 psia).
Y = Maximum relieving capacity of any one safety valve in 1bs/ hour (859,646 lbs/hr at 1190 psia).
SAN ONOFRE-UNIT 2 B 3/4 7-1 AMENDMENT NO. 91 1
PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coo ~iant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of off-site power.
In addition, the flow paths are automatically aligned to support an Emergency Feedwater Actuation Signal or a Main Steam Isolation Signal.
Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a pressure of 1170 psig to the entrance of the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a pressure of 1170 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less thhn 350 F when the shutdcwn cooling system may be placed into operation.
Each electric driven auxiliary feedwater pump is powered from an independent IE power supply, and feeds one steam generator through a set of valves powered from the same 1E scurce.
The AC powered valves associated with the same train electric driven auxiliary feedwater pump defines that flow path.
The steam-driven auxiliary feedwater pump can feed each steam generator through two sets of valves powered from 125VOC IE power sources.
Each set of valves aligned to a steam generator from the steam driven auxiliary feedwater pump, are powered from the opposite train from the valves from the corresponding electric driven auxiliary feedwater pump.
For purposes of identifying the appropriate action statement, the steam-driven auxiliary feedwater pump flow path is defined as both sets of valves aligned to steam generators.
Loss of Operability of one or more of the DC powered valves constitn+es loss of the steam-driven auxiliary
~
feedwater flow path.
If the steam generators are used for decay heat removal in Mode 4 under the provisions of Technical Specifications 3/4.4.1.3, at least one motor-driven auxiliary feedwater pump and associated flow path per steam generator is required to be OPERABLE to provide decay heat removal.
3/4.7.1.3 CONDENSATE STORAGE TANKS The OPERABILITY of the condensate storage tank T-121 with the mimimum water volume ensures that sufficient water is available to maintain the RCS at H0T STANDBY conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> followed by cooldown to shutdown cooling initia-tion, with steam discharge to atmosphere with concurrent loss of offsite power and most limiting single failure The OPERABILITY of condensate storage tank T-120 in conjunction with tank T-121 ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> _ including cooldown to shutdown cooling initiation, with steam discharge to atmosphere with concur-ren : loss of offsite power and most limiting single failure.
The contained water volume limits are specificd relative to the highest auxiliary feedwater SAN ONOFRE-UNIT 2 B 3/4 7-2 AMENDMENT NO. 99
PLANT SYSTEMS BASES 3/4.7.1.3 CONDENSATE STORAGE TANKS (Continued) pump suction inlet in the tank for T-121, and to the T-121 cross connect siphon inlet for T-120.
(Water volume below these datum levels is not considered recoverable for purposes of this specification.) Vortexing, internal structure, and instrument error are considered in determining the tank levels corresponding to the specified water volume limits.
Prior to achieving 100% RATED THERMAL POWER, Figure 3.7-1 is used to deter-mine the minimum required water volume for T-121 for tt.e maximum power level (hence maximum decay heat) achieved.
SAN ON0FRE-Uh!- 2 B 3/4 7-2a AMEN 0 MENT NO 99
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y1 UN11ED ST ATES 5 kJ Jj i NUCLEAR REGULATORY COMMISSION k \\$f$2 / f WASHINGTON, D C. 20%5
%,, +..../
50'JTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CAllFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside,) (the California, and the City of Anaheim, California (licensees licensee) dated June 17, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (tne Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such &ctivities 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.
2-2.
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 amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
88, are hereby incorporated in the license.
Southern California Edhon 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 and must be fully implemented no later than 30 days from the date of issuance.
FOR iHE NUCLEAR REGULATORY COMMISSION
}we<. t. dyM James E. Dyer, Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
1 Changes to the Technical Specifications Date of Issuance: Octcber 1, 1991 l
l l
~
t ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 88 TO 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 the captioned anendment number and contain niarginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE I tGERT 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 3/4 7-Sa 3/4 7-5b B 3/4 7-2 8 3/4 7-2 B 3/4 7-2a
e--
I 1-l TABLE 3.7-2 MAXIMUM ALLOWABLE VALUE LINEAR POWER LEVEL-HIGH TRIP WITH INOPERABLE MAIN STEAM'5AFETY VALVES DURING OPERATIM WITH BOTH STEAM GEhERATOR5 Maximum Allowable Value Linear Maximum Number of Inoperable Safety Power Level-High Trip Valves on Any Operating Steam Generator (Percent of RATED THERMAL POWER) 1 98.6 2
86.3 3
74.0 4
61.6 i
SAN ONOFRE - UNIT 3 3/4 7-3 AMENDMENT NO. BI
-_.-________.-~___L__
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2.1 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
Two motor-uriven auxiliary feedwater pumps, each capable of being a.
powered from separate emergency busses, b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system, and c.
Manual valves in the correct position and automatic valves each capable of being opened and closed, with the following exceptions:
1.
Motor-driven auxiliary feedwater pump discharge bypass control valves, HV-4762 and HV-4763, need only be capable of being closed.
2.
Steam turbine-driven auxiliary feedwater pump steam supply isolat'on valves, HV-8200 and HV-8201, and turbine stop valve, i
HV-4716, need only be capable of bcing opened, and 3.
Manual crosstie valves 1305MU534 and 130MU635 may be open in Mode 3 provided a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> has elapsed since reactor shutdown.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION a.
With one auxiliary feedwater pump or its associated flow path inoper-able, restore the required auxiliary feedwater pump and its associated flow path 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 HOT SHUTDOWN within the follow-ing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
With either two auxiliary feedwater pumps, two flow paths, or one pump and one separate flow path inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three aus.iary feedwater pumps or flow paths inoperable, immed-iately ini
.te corrective action to rectore at least one auxiliary feedwater pump and its associated flow path to OPERABLE status as soon i
possible.
'n automatic valve in any flow path incapable of closing upon d.
re-4 of a Main Steam Isolation Signal, close the affected valve or 16s block valve wit _hin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and enter actions a, b, or c if there is a loss of the flow paths (s).
Testing pursuant to Technical Specification 3.3.2 does not constitute entry into this ACTION Statement.
I SAN ON0FRE-UNIT 3 3/4 7-4 AMENDMENT NO. 88 i-
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2.1.1 Each auxiliary feedwater pump and associated flow path shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Testing the turbine driven pump and both motor driven pumps pur-suant to Specification 4.0.5.
The provisions of Specifica-tion 4.0.4 are not applicable for the terbine-driven pump for entry into MODE 3.
2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
3.
Verifying that both manual valves in the suction lines from the primary AFW supply tank (condensate storage tank T-121) to each AFW pump, and the manual discharge line valve of each AFW pump are locked in the open position.
4.
Verifying that the AFW piping is full of water by venting the acce sible discharge piping high points, b.
At least once per refueling interval during shutdown by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an EFAS test signal.
2.
Verifying that each motor driven pump starts and the steam inlet valves to the turbine drive pump open automatically upon receipt of an EFAS test signal.
3.
Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of a MSIS test signal except for HV-8200 and HV-8201.
4.7.1.2.1.2 The auxiliary feedwater system shall be demonstrated OPERABLE prior I
to enterino MODE 2 following each COLD SHUTDOWN by performing a flow test to verify the normal flow path from the primary AFW supply taak (condensate stor-age tank T-121) through each auxiliary feedwater pump to its associated steam generator.
SAN ON0FRE-UNIT 3 3/4 7-5 N4ENOMENT NO. 88 r________________________-__-___
. -. _ =.
--. _ ~ - _.
PLANI SYSTEMS
-AUX 1LIARY FEE 0 WATER SYSTEM-HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.7.1.2.2 At least one motor-driven auxiliary feedwater pump and associated flow path per steam generator required by LC0 3.4.1.3 (Reactor Coolant System
- Hot Shutdown) shall be OPERABLE with:
a.
a motor driven auxiliary feedwater pump, and b.
Manual valves in the correct position and automatic valves each capable of being opened and closed, with the following exceptions:
1.
Motor-driven auxiliary feedwater pump discharge bypass control valves, HV-4762 and HV-4763, need only be capable of being closed; and 2.
Manual crosstie valves 1305MU634 and 1305MU635 may be open.
APPLICABILITY:
MODE 4 with a steam generator being used for decay heat removal.
-ACTION:
With no auxiliary feedwater pump or its associated flow path OPERABLE as required to satisfy LCO 3.4.1.3, restore the required auxiliary feedwater pump (s) and flow path (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l SAN ONOFRE-UNIT 3 3/4 7-5a AMENDMENT NO.EE
- --l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2.2.1 Each auxiliary feedwater pump and flow path shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Testing the required motor driven pump (s) pursuant to Specification 4.0.5 2.
Verifying that each valve (manual, power ope ated or automatic) in the required flow path (s) that is not locked, sealed, or otherwise secured in position, is in its correct position.
3.
Verifying that both manual valves in the suction lines from the primary AFW supply tank (condensate storage tank T-121) to each required AFW pump, and the manual discharge line valve of each required AFW pump are locked in the open position.
4.
Verifying that the AFW piping is full of water by venting the accessible discharge piping high points on the required flow paths.
l SAN ONOFRE-UNIT 3 3/4 7-5b AMENDMENT NO.EE
o P;:s! SYSTEMS
- s!!ss:T! 5? ORA:!-TANr.5 L:w:T!s: CONO:i!0N FOR 0*ERATION 3.7.1.3 'The condensat.e st contained volume of at leaorage tants (OSTs) shall be OPERASLE with a st 144,000 gallons" in T-121'and 280,000,ga11ons in T-120.
APPLICABIL!TY:
MODES 1, 2 and 3.
ACTION:
Witn'the concensate storage tanks inestrable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either restore tne CSTs to CPERASLE status or be in at least HOT STAND 8Y within the ns-;
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> anc in NOT SHUTD0=w within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SUDVE: LLAN:!.REOUIREw!N's 4.7.1,3 The' concensate storage tanks shall be demonstrated OPERABLE at least once'per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ey verifying the containec =ater volume is'within its limits.
l Prior to.first echieving 100% power, the minimuN volume recuired to be contained in T-121 is that shown on Figure 3.7-1 corresponding to the maximum t
power level achieved to date.
i I'
SAN ONOFRE-UNIT 3 3/4 7 '
l
3/4,7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam safety vsives (MSSVs) ensures that the secondary system pressure will not exceed 110% (1210 psia) of its design pressure of 1100 psia during the most severe anticipated system operational transient.
The total relief capacity available is greater than the maximum steam flow required after a turbine trip from 102% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink.
Tt'e M55V lif t setpoints are staggered, as shown in Table 3.7-1, such that ohly those valves needed for pressure relief will actuate.
The MSSV lift settings and relieving capacities meet the requirements of Section III of the ASME Boiler and Pressure Vessel Code, 1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A).
The total available relieving capacity for all valves on all of the steam lines is 15.473,628 lbs/hr at 1190 psia.
A minimum of or.e OPERABLE safety valve per steam generator ensures that sufficient relieving capacity is available for removing decry heat.
STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduc-tion in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reduced reactor trip allowable values are derived on the following bases:
SP = (*) ~X (Y)IY) x 111.0 where:
SP = reduced reactor trip allowable value in percent of RATED THERMAL POWER.
V = maximum number of inop:. able safety valves per steam line.
111.0 = Power Level-High Trip allowable value from Table 2.2-1.
X = Total relieving capacity of all safety valves per steam line in 1bs/ hour (7,736,814 lbs/hr at 1190 psia).
Y = Maximum relieving capacity of any one safety valve in lbs/ hour (859,646 lbs/hr at 1190 psia).
SAN ONOFRE-UNIT 3 B 3/4 7-1 AMENDMENT NO. BI
PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEE 0 WATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of offsite power.
In addftion, the flow paths are automatically aligned to support an Emergency Feedwater Actuation Signal or Main Steam Isolation Signal.
Each electric-driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a pressure of 1170 psig to the entrance of the steam generators.
The steam-driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a pressure of 1170 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System te.aperature to less than 350 F when the shutdown cooling system may be placed into operation.
Each electric driven auxiliary feedwater pump is powered from an independent 1E power supply, and feeds one steam generator through a set of valves powered from the same 1E source.
The AC powered valves associated with the same train electric driven auxiliary feedwater pump defines that flow path.
The steam-driven auxiliary feedwater pump can feed each steam generator through two sets of valves powered from 125VDC IE power sources.
Each set of valves aligned to a steam generator from the steam driven auxiliary feedwater pump, are powered from-the opposite train from the valves from the corresponding electric driven auxiliary feedwater pump.
For purposes of identifying the appropriate action statement, the steam-driven auxiliary feedwater pump flow path is defined as both sets of valves aligned to steam generators.
Loss of Operability of one or more of the DC powered valves constitutes loss of the steam-driven auxiliary feedwater flow path.
If the steam generators are used for decay heat removal in Mode 4 under the provisions of Technical Specifications 3/4.4.1.3, at least one motor-driven auxiliary feedwater pump and associated flow path per steam generator is required to be OPERABLE to provide decay heat removal.
3/4.7.1.3 CONDENSATE STORAGE TANKT The OPERABILITY of_the condensate storage. tank T-121 with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> followed by cooldown to shutdown cooling initiation, with steam discharge to atmosphere with concurrent loss of offsite power and most limiting single failure.
The OPERABILITY of condensate storage-tank T-120 in conjunction with tank T-121 ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> including cooldowr, to shutdown cooling initiation, with steam discharge to atmosphere with concurrent loss of offsite power and most limiting single failure.
The contained water volume limits are specified relative to the highest auxiliary feedwater pump suction inlet in the tank for T-121, and to the T-121 cross connect siphon inlet for T-120.
(Water volume below these datum levels is l
SAN ON0FRE-UNIT 3 B 3/4 7-2 AMENDMENT NO. 88 L
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PLANT SYSTEMS BASES 3/4.7.1.3 UONDENSATE STORAGE TANKS (Continued) not considered recoverable for purposes of this specification.) Vortexing, internal structure and instrument error are considered in determining the tank levels corresponding to the specified water volume limits.
Prior to achieving 100% RATED THERMAL POWER, Figure 3.7-1 is used to determine the minimum required water volume for T-121 for the maximum power level (hence maximum decay heat) achieved.
SAN ONOFRE-UNIT 3 B 3/4 7-2a AMENDMENT N0. 8E.
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