ML20138A995
| ML20138A995 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/30/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138A997 | List: |
| References | |
| TAC-56002, TAC-57875, TAC-57876, NUDOCS 8510110235 | |
| Download: ML20138A995 (16) | |
Text
_
[gf
%[1 UNITED STATES NUCLEAR REGULATORY COMMISSION g,iN i
WASHINGTON, D. C. 20555
'k.....
SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 f
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees), dated May 30 and June 21, 1985 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set fnrth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8510110235 850930 PDR ADOCK 05000361 p
. 2.
Accordingly, the license is amended by changes to the Technical Specifications 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 Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 36, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective imediately and is to be fully implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George Knighton, _
f i
Licensing Branch No. 3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 30, 1985 i
l l
September 30, 1985
, ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE N0. NPF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
I Amendment Pages Overleaf Pages 3/4 9-13 3/4 9-14 3
i
)
i k
l l
k l
REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter systems shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the storage pool.
ACTION:
With one fuel handling building post-accident cleanup filter system a.
inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the OPERABLE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of l
HEPA filters and charcoal absorbers.
b.
With no fuel handling building post-accident cleanup filter system OPERABLE, suspend all operations involvir.g movement of fuel within the storage pool or operation of fuel handling machine over the storage pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERABLE status, The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling building post-accident cleanup filter systems shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.
from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
SAN ONOFRE-UNIT 2 3/4 9-13 AMENDMENT NO. 36 i
1
REFUEL}NG DPERATIONS 1
SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying that with the system operating at a flow rate of 12925 cfm + 10% and recirculating through the HEPA filters and charcoal adsorbers, the total bypass flow of the system through the system diverting valves, to the facility vent is less than or equal to 1% when the system is tested by admitting cold 00P at the systbm intake.
2.
Verifying that the cleanup filter system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 12925 cfm 2 10%.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
4.
Verifying a system flow rate of 12925 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,
-meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
d.
At least once per 18 months by:
I 1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.3 inches Water Gauge while operating the systim at a flow rate of 12925 cfm i 10%.
2.
Verifying that on a Fuel Handling Isolation (FHIS) test signal, the system automatically isolates normal ventilation and starts recirculation through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the heaters dissipate 28.7 1 1.5 kw for E464, 32.3 1 1.7 kw for E465, and 3.8 1 0.2 kw for E652 when tested in accordance with ANSI N510-1975 with the measured heater dissipation corrected to correspond to nomir.al voltage.
SAN ONOFRE-UNIT 2 3/4 9-14 AMENDMENT NO. 26
~
i pasec.
- f h,
UNITED STATES y,-( ,p, NUCLEAR REGULATORY COMMISSION E
3 /'
W ASHINGTON, D. C. 20555 gh.
./
g s=.....f SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-15 1.
The Nuclear Pegulatory Commission (the Commission) has found that:
A.
The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees), dated May 9 and 30 and June 21, 1985, comoly with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I
. 2.
Accordingly, the license is amended by changes to the Technical Specifications 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 throingh Amendment No. 25, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective innediately and is to fully implemented within 30 days of the date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION eorge W< nighton, C Licensi Branch No.
j Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 30, 1985 5
t A
d 1
i September 30, 1985
,. I ATTACHMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. NPF-15
- l DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with 4
the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages, i
Amendment Pages Overleaf Pages
)
3/4 1-12 3/4 1-11 l
3/4 1-13 3/4 1-14 3/4 9-13 3/4 9-14 B 3/4 1-2 B 3/4 1-1 I
i I
l
)
l 2
4 e
i i
., -,,.... - - -. ~..
,, - - -, - - -. - - - -.., - - - - -, -~
-,,,,-.---.._,n-.
-,.,--~,...,
,n -,.,,-- nar--
4 REACTIVITY CONTROL SYSTEMS i
BORIC ACIO MAKEUP PUMPS - OPERATING 1
LIMITING CONDITION FOR OPERATION 3.1.2.6 At least the boric acid makeup pump (s) in the boron injection flow path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump (s) in Specification 3.1.2.2a is l
)
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
i With one boric acid makeup pump required for the boron injection flow path (s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup i
pump 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 NOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F; restore the above required boric acid makeup pump (s) to l j
OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 1
i I
l SURVEILLANCE REQUIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0.5.
t 9
a t
4 i
4 AMENDMENT NO. 17 SAN ONOFRE-UNIT 3 3/4 1-11 i
i
-.m r---g---n-- -.. -- -~-<,,,,
--,,wm-ew~--e
- ~
-=rme-
,--p-1-m-,-v,,--w
,ww-o--
e~w---w-ve,~,,-+-w-~-w-m ma g --r v-
~ww-,-
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.7 As a minimum, one of the following borated water sources shall be OPERABLE:
One boric acid makeup tank and at least one associated heat tracing a.
circuit with the tank contents in accordance with Figure 3.1-1.
b.
The refueling water storage tanks with:
1.
A mini.num borated water volume of 9970 gallons above the ECCS suction connection, 2.
A minimum boron concentration of 1720 ppe, and 3.
A solution temperature between 40 F and 100*F.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS a
4.1.2.7 The above required borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration of the water, 2.
Verifying the contained borated water volume of the tank, and 3.
Verifying the boric acid makeup tank solution temperature when it is the source of borated water, b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water when the outside air temperature is less than 40*F or greater than 100*F.
SAN ONOFRE-UNIT 3 3/4 1-12 AMENDMENT NO. 25 i
~
6000
- MODES 1,2.3 & 4 i
VOL UM E 5500 un i
0 5000 i
so 3200 k%4, MODES 5 & 6 x
x.
m 5
x x
g 3150
's s
3 w
o N
140 y
$! 3100 E
f 130 Of '
S 120 m
_ iiO i
9.0 %
10.0 %
11.0 %
12.0%
(iuso -)
(n. - )
(.no.,)
(n. coo...)
CONCENTR ATION - WT%,(ppm N 80 )
3 3
STORED BORIC ACID Figure 3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND MINIMUM TEMPERATU N 803 BEFORE PRECIPITATION AS A FUNCTION OF STORED 80RIC ACID 3
CONCENTR ATION SAN ONOFRE-UNIT 3 3/4 1-13 AMEN 0 MENT NO. 25
I REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING l
LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:
a.
At least one boric acid makeup tank and at least one associated heat tracing circuit with the contents of the tanks in accordance with Figure 3.1-1, and b.
The refueling water storage tank with:
1.
A minimum contained borated water volume of 362,800 gallons above the ECCS suction connection, 2.
Between 1720 and 2300 ppe of boron, and 3.
A solution temperature between 40'F and 100'F.
2 APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
l a.
With the above required boric acid makeup tank inoperable, restore the tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT 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 borated to a SHUTDOWN MARGIN equivalent to at least 3.0% delta k/k at 200*F; restore the above l
required boric acid makeup tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.8 Each borated water source shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the boron concentration in the water, 2.
Verifying the contained borated water volume of the water source, and 3.
Verifying the boric acid makeup tank solution temperature.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40*F or greater than 100*F.
I AMENDMENT NO. 17 SAN ONOFRE-UNIT 3 3/4 1-14 l
l
. __=
f 1
REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter j
systems shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the storage pool.
l l
ACTION:
With one fuel handling building post-accident cleanup filter system a.
inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the OPERABLE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal absorbers.
b.
With no fuel handling building post-accident cleanup filter system OPERABLE, suspend all operations involving movement of fuel within the storage pool or operation of fuel handling machine over the storage pool until at least one fuel handling building post-accident i
cleanup filter system is restored to OPERABLE status.
i t
i c.
The provisions of Specification 3.0.4 are not applicable.
[
SURVEILLANCE REQUIREMENTS i
4.9.12 The above required fuel handling building post-accident cleanup filter systems shall be demonstrated OPERA 8LE:
1 a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal L
adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> i
with the heaters on.
I b.
At least once per 18 months or (1) after any structural maintenance
[
on the HEPA filter or charcoal adsorber housings, or (2) following i
painting, fire or chemical release in any ventilation zone communicating with the system by:
I l
l i
i i
I l
SAN ONOFRE - UNIT 3 3/4 9-13 AMENDMENT NO. 25 i
i i
i i
I
. ~ _,. _
- - -, ~ -_.. _. - _ __.. _,. _, _ _
REFUEL}NG OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying that with the system operating at a flow rate of 12925 cfm 2 10% and recirculating through the HEPA filters and charcoal adsorbers, the total bypass flow of the system through the system diverting valves, to the facility vent is less than or equal to 1% when the system is tested by admitting cold D0P at the syst'em intake.
2.
Verifying that the cleanup filter s'ystem satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 12925 cfm 10%.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
4.
Verifying a system flow rate of 12925 cfm 1 10% during system operation when tested:in accordance with ANSI N510-1975.
c.
Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.3 inches Water Gauge while operating the system at a flow rate of 12925 cfm 1 10%.
2.
Verifying that on a Fuel Handling Isolation (FHlS) test signal, the system automatically isolates normal ventilation and starts recirculation through the HEPA f,ilters and charcoal adsorber banks.
3.
Verifying that the heaters dissipate 28.7 1 1.5 kw for E464, 32.3 1 1.7 kw for E465, and 3.8 1 0.2 kw for E652 when tested in accordance with ANSI H510-1975 with the measured heater dissipation corrected to correspond to nominal voltage.
SAN ONOFRE-UNIT 3 3/4 9-14 AMEN 0 MENT NO 15
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 80 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,yg.
The most restrictive condition occurs at E0L, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 5.15% delta k/k is required to control the reactivity transient.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T,yg less than or equal to 200*F. the reactivity transients resulting from any postulated accident are minimal and a 3.0% delta k/k shutdown margin provides l
adequate protection.
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The Ifmitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coef-ficient will be maintained within acceptable values throughout each fuel
- cycle, i
SAN ONOFRE-UNIT 3 8 3/4 1-1 i
i l
l_.___,
I 3
I REACTIVITY CONTROL SYSTEMS 3
BASES t
i 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY
{
This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 520*F.
This limitation i
is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor pressure vessel is above its minimum RT temperature.
NOT 3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to
.i perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid makeup pumps, (5) associated heat trac-j ing systems, and (6) an emergency power supply from OPERABLE diesel generators.
With the RCS average temperature above 200'F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capa-bility in the event an assumed failure renders one of the systems inoperable.
j Allowable out-of-service periods ensure that minor component repair or correc-tive action may be completed without undue risk to overall facility safety from j
injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUTOOWN MARGIN from expected operating conditions of 3.0% delta k/k after xenon l
decay and cooldown to 200'F.
The maximum expected boration capability require-ment occurs at EOL from full power equilibrium xenon conditions and requires l
boric acid solution from the boric acid makeup tanks in the allowable concentra-i tions and volumes of Specification 3.1.2.8 or 81,970 gallons of 1720 ppe borated l
1 water from the refueling water tank. However, for the purpose of consistency
)
the minimum required volume of 362,800 gallons above ECCS suction connection in i
j Specification 3.1.2.8 is identical to the more restrictive value of Specifica-tion 3.5.4.
With the RCS temperature below 200*F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injaction system becomes inoperable.
The boron capability required below 200*F is based upon providing a j
3.0% delta k/k SHUTDOWN MARGIN after xenon decay and cooldown from 200'F to 140*F.
This condition requires either 9970 gallons of 1720 ppe borated water from the refueling water tank or boric acid solution from the boric acid makeup tanks in accordance with the requirements of Specification 3.1.2.7.
l SAN ONOFRE-UNIT 3 8 3/4 1-2 AMEN 0 MENT NO.25 i
l
- -, -, -..