ML20206P389
| ML20206P389 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  (NPF-10-A-051, NPF-10-A-51, NPF-15-A-040, NPF-15-A-40) |
| Issue date: | 08/11/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206P394 | List: |
| References | |
| TAC-60722, TAC-60723, NUDOCS 8608270197 | |
| Download: ML20206P389 (14) | |
Text
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NUCLEAR REGULATORY COMMISSION
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e WASHINGTON, D. C. 20555 f
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s,s SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAP GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The apclication 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 February 7,1986, as supplemented by letters dated March 10 and May 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, as amerided, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations 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.
8608270197 860811 PDR ADOCK 05000361 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment and i
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. 51, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in the Technical Specifications are to become effective and f
be fully implemented on first entry into Mode 3 following installation of the TSP storage baskets.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during changeover shall be minimized.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0;
Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B Attactment:
Changts to the Technical Specifications Date of Issuance: August 11, 1986 I
August 11 1986 0
ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 I
l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and l
contain vertical lines indicating the area cf change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages l
3/4 6-16 3/4 6-15 B 3/4 6-4 8 3/4 6-3 I
7 h
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4-1 1
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CONTAINMENT SYSTEMS l
ls j_
SURVEILLANCE REOUIREMENTS (Continued) h a
1-3.
Verifying that each spray pump starts automatically on a Safety j
Injection Actuation test signal.
i 4.
Verifying that each ccntainment spray header riser is filled j
with water to within 10- feet of the lcwest spray ring.
l l
c.
At least once per 5 years by performing an air or smoke-flow test through each spray haader and verifying each spray noIZie is I
unobstruc.ted.
1 l
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i SAN ONOFRE-UNIT 2 3/4 6-15 AMEN 0 MENT NO.16 i
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CONTAINMENT SYSTEMS RECIRCULATION FLOW PH CONTROL LIMITING CONDITION FOR OPERATION 3.6.2.2 The recirculation flow pH control system shall be operable with a minimum of 15,400 lbs. (256 cu. ft.) of trisodium phosphate (w/12 hydrates), or equivalent, available in the storage racks in the containment.
APPLICABILITY: Modes 1, 2 and 3 ACTION:
With less than the required amount of trisodium phosphate available, restore the system to the correct amount 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 LOT 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 following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The recirculation flow pH control system shall be demonstrated operable during each refueling outage by:
a.
Visually verifying that the TSP storage racks have maintained their integrity and the TSP containers contain a minimum of 15,400 lbs. (256 cu. ft.) of TSP (w/12 tydrates) or equivalent.
b.
Verifying that when a sample of less than 3.00 grams of triso-dium phosphate (w/12 hydrates) or equivalent, selected at random from one of the storage racks inside of containment, is sub-merged, without agitation, in at least 1 litre of 120 1 10 degrees-F borated demineralized water bor'ated to at least 2482 ppm baron, allowed to stand for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then decanted and mixed, the pH of the solution is greater thar, or equal to 7.0.
SAN ONONFRE - UNIT 2 3/4 6-16 AMENDMENT NO. 51
i, CONTAINMENT SYSTEMS BASES 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.
Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.
To provide assurance that the 42-inch valves cannot be inadvert-ently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed or prevent power from being supplied to the valve operator.
The use of the containment purge lines is restricted to the 8-inch purge suppl.y and exhaust isolation valves since, unlike the 42-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and there-fore the site boundary dose guidelines of 10.CFR Part 100 would not be exceeded in the event of an accident during purging operations.
The design of the 8-inch purge supply and exhaust isolation valves meets the requirements of Branch Technical Position CSB 6-4, " Containment Purging During Normal Plant Operations."
Leakage integrity tests with a maximum allowable leakage rate for; purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.
The 0.60 L leakage limit shall not be exceeded when thf.-
leakage rates determined by t$e leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS i
3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
The containment spray system and the containment cooling system are radundant to each other in providing post accident cooling of the containment a tmosphere.
However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
SAN ON0FRE-UNIT 2 B 3/4 6-3
CONTAINMENT SYSTEMS d
BASES 3/4.6.2.2 RECIRCULATION FLOW PH CONTROL SYSTEM The operability of the recirculation flow pH control system ensures that there is sufficient trisodium phosphate available in containment to guarantee a sump pH of > 7.0 during the recirculation phase of a postulated LOCA.
This pH level is required to minimize the potential for chloride stress corrosion of austen-itic stainless steel.
The specified amount of TSP tiill result in a recircula-tion phase pH of 7.2 assuming complete dissolution and maximum allowed boric acid concentrations from the borated water sources.
Similarly, surveillance 4.6.2.2 will produce a pH of 7.2.
The specified temperature of 120 1 10 de-grees-F for the surveillance is based is consistent with expectea long term 1ecirculation phase sump temperature reported in the FSAR.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the contain-ment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
The ' containment cooling system and the containment spray system are redundant to each other in providing post accident cooling of the containment atmosphere.
As a result of this redundancy in cooling capability, the allowable out of ser' vice time requirements for the containment cooling system have been appropri-ately adjusted.
However, the allowable out of service time requirements for the containment spray system have been mair.tcined consistent with that assigned other inoperable ESF equipaent since the containment spray system also provides a mechanism for removing 'odine from the coatainment atmosphere.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures tha. the contain-ment atmosphere will be isolated from tiie outside environment in the event of a release of radioactive material to the containment atmosphere and is consis-tent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR 50.
Containment isolation within the time limits specified for those power operated isolation valves designed to close automatically upon a CIAS signal ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the ana.yses for a LOCA.
Such valves are listed in Sections A and B of Table 3.6-1 and Surveillance requirements to verify J
OPERABILITY of these valves are explicitly stated in 4.6.3.1 thru 4.6.3.3.
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Check valves located inside containment are considered OPERABLE provided their leak rate is within limits when tested pursuant to 10 CFR 50 Appendix J.
J i
SAN ONONFRE - UNIT 2 B 3/4 6-4 AMENDMENT NO. 51 y
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UNITED STATES 3'
'n NUCLEAR REGULATORY COMMISSION h
W ASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDIS0N 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. 40 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application 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 February 7, 1986, as supplemented by letters dated March Il ead May 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 tSe Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this 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. 40, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The changes in the Technical Specifications are to become effective and be fully implemented on first entry into Mode 3 following installation of the TSP storage baskets.
In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during changeover shall be minimized.
l 4.
This licence amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
h gw~
A Harry Rood, Senior Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: August 11, 1986
August 11, 1986 t
ATTACHMENT TO LICENSE AMENDMENT N0.
i FACILITY OPERATING LICENSE NO. NPF-15 gj DOCKET NO. 50-362 Replace the following pages of the Appendix A Technical Specifications with t
the enclosed pages. The revised pages are identified by Amendment number and 3
contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Paaes Overleaf Pages -
l i
3/4 6-17 3/4 6-18 B 3/4 6-4 8 3/4 6-3
~
CONTAINMENT SYSTEMS RECIRCULATION FLOW - PH CONTROL LIMITING CONDITION FOR OPERATION 3.6.2.2 The recirculaticn flow pH control system shall be operable with a minimum of 15,400 lbs. (256 cu. ft.) of trisodium phosphate (w/12 hydrates),
s or equivalent, available in the storage racks in the containment.
APPLICABILITY: Modes 1, 2 and 3 ACTION:
With less than the required amount of trisodium phosphate available, restore the system to the correct amount 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 H0T 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 H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1 SURVEILLANCE REQUIREMENTS 4.6.2.2 The recirculation flow pH control system shall be demonstrated operable during each refueling outage by:
a.
Visually verifying that the TSP storage racks have maintained their integrity and the TSP containers contain a minimum of 15,400 lbs.
(256 cu. ft.) of TSP (w/12 hydrates) or equivalent.
b.
Verifying that when a sanple of less than 3.00 grams of trisodium phosphate (w/12 hydrates) or equivalent, selected at random from one of the storage racks inside of containment, is submerged, with-i out agitation, in at least 1 litre of 120 1 10 degrees-F borated 1
demineralized water borated to at least 2482 ppm boron, allowed to stand for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then decanted and mixed, the pH of the solution is greater than or equal to 7.0.
SAN ON0FRE-UNIT 3 3/4 6-17 AMENDMENT NO. 40
CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM
(
LIMITING CONDITION FOR OPERATION I
3.6.2.3 Two independent groups of containment cooling fans shall be OPERABLE with two fan systems to each group.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one group of the above required containment cooling fans a.
inoperable and both containment spray systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN sithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With two groups of the above required containment cooling fans inoperable, and both containment spray systems OPERABLE, restore at least one group of cooling fans to OPERABLE status within 72 hours8.333333e-4 days <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 />.
Restore both a60ve required groups of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <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 />.
c.
With one group of the above required containment cooling fans inoperable and one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <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 />.
Restore the inoperable group of containment cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <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 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Starting each fan group from the control room and verifying that each fan group operates for at least 15 minutes.
2.
Verifying a cooling water flow rate of greater than or equal to 2000 gpm to each cooler.
b.
At least once per 18 months by verifying that each fan group starts automatically on a Containment Cooling Actuation test signal.
SAN ON0FRE-UNIT 3 3/4 6-18
CONTAINMENT SYSTEMS I
BASES 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 42-inch containment purge supply and exhaust isolation valves are
~
required to be closed during plant operation since these valves have not been 4
demonstrated capable of clo. sing during a LOCA or steam line break accident.
Maintaining these valves closed during plant operations ensures that excessive l
quantities of radioactive materials will not be released via the containment purge system. To provide assurance that the 42-inch valves cannot be inadvert-ently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock tae valve closed or prevent power from being supplied to the valve operator.
The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 42-inch valves, the 8-inch valves will close during a LOCA or steam line break accidcnt and there-fore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.
The design of the 8-inch purge supply and exhaust isolation valves meets the requirements of Branch Technical Position CSB 6-4, " Containment Purging During Normal Plant Operations."
r Leakage integrity tests with a maximum allowable leakage rate for purge supply anc exhaust isolation valves will provide early indication of resilient material I
seal degradation and will allow the opportunity for repair before gross leakage failure develops.
The 0.60 L leakage limit shall not be exceeded when the leakage rates determined by tRe leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment l
depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
l The containment spray system and the containment cooling system are redundant to each other in providing post accident cooling of the containment i
atmosphere.
However, the containment spray system also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have i
been maintained consistent with that assigned other inoperable ESF equipment.
i i
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i SAN ON0FRE-UNIT 3 8 3/4 6-3 1
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CONTAINMENT SYSTEMS BASES 3/4.6.2.2 RECIRCULATION FLOW PH CONTROL SYSTEM The OPERABILITY of the recirculation flow pH control system ensures that there is sufficient trisodium phosphate available in containment to guarantee a sump pH of > 7.0 during the recirculetion phase of a postulated LOCA.
This pH level is required to minimize the potential for chloride stress corrosion of austentitic stainless steel.
The specified amount of TSP will result in a recirculation phase pH of 7.2 assuming complete dissolution and maximum allowed boric acid concentraticas from the borated water sources.
Similarly, surveil-lance 4.6.2.2 will produce a pH of 7.2.
The specified temperature of 120 1 10 degrees-F for the surveillance is based is consistent with expected long term recirculation phase sump te.mperature reported in the FSAR.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
The containment cooling system and the containment' spray system are redundant to each other in providing post-accident cooling of the containment atmosphere.
As a result of this redundancy in cooling capability, the allow-able out-of service time requirements for the containment cooling system have been appropriately adjusted.
However, the allowable out-of-service time requirements for the containment spray system have been maintained consistent with that assigned other inoperable ESF equipment since the containment spray system also provides a mechanism for removing iodine from the containment atmosphere.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50.
Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environ-ment will be consistent with the assumptions used in the analyses for a LOCA.
SAN ONOFRE - LINIT 3 B 3/4 6-4 AMENDMENT N0. 40
.