ML20080P303
| ML20080P303 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/28/1995 |
| From: | Fields M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20080P306 | List: |
| References | |
| NUDOCS 9503070311 | |
| Download: ML20080P303 (14) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20046 0001
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA IHE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.117 License No. NPF-10 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated December 30, 1993, as supplemented by letters dated June 3,1994, August _25,1994, and i
January 3, 19, and 30, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the l
Act), and the Commission's regulations set forth in 10 CFR Chapter i
I; 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 (1) that the activities authorized
{
by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
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-I 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.
9503070311 950228 PDR ADOCK 05000361 1
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i Accordingly, the license is' amended by changes to the-Technical Speci-
'2.-
fications.as indicated in the attachment to this license amendment, and
.i paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby-i amended to read as follows:
1
-(2)
Ischnical Snecifications
- The Technical Specifications contained in Appendix A' and the I
Environmental Protection Plan contained in Appendix B, as revised j
through Amendment No.117, are hereby incorporated.in the license. Southern California Edison Company shall operate the i
facility.in accordance with the Technical Specifications and the Environmental Protection P1an.
3.
This license amendment is effective as of the date of its issuance and l
must be fully. implemented no later than 30 days. from the date of ~
issuance.
FOR THE NUCLEAR REGULATORY C00911SSION g/// &&d2.
1 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: February 28, 1995 l
l
l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.117 TO FACILITY OPERATING LICENSE NO. 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 amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 9-4 3/4 9-4 3/4 9-4a B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 i
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REFUELING OPERATIONS 3/4.9.4 CONTAlletENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be'in the following status:
a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed,* and c.
Each penetration providing direct access from the containment
.I atmosphere to the outside atmosphere shall be either:
)
1.
Closed by an isolation valve, blind flange, or manual valve, or.
2.
Be capable of being closed by an OPERABLE automatic containment purge valve.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within i
the containment.
l l
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
1 l
- Both doors of the containment personnel airlock may be open provided:
a.
one personnel airlock door is OPERABLE, and i
bl. the plant is in MODE 6 with 23 feet of water above the fuel in the reactor vessel, or b2. defueled configuration with fuel in containment (i.e., fuel in refueling machine or upender).
SAN ON0FRE-UNIT 2 3/4 9-4 AMENDMENT NO.117 l
~
-l SURVEILLANCE REQUIREMENTS
)
4.9.4 Each of the above required containment building penetrations shall be j
determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior j
to the start of and at least once per 7 days during CORE ALTERATIONS or i
movement of irradiated fuel in the containment but ding by:-
I Verifying the penetrations are in their closed / isolated condition, or a.
b.
Testing the containment purge valves per the applicable portions of Specification 4.6.3.2.
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.l SAN ON0FRE-UNIT 2 3/4 9-4a AMENDMENT NO.117
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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will. remain subcritical during CORE ALTERATIONS, and 2).a uni--
)
form boron concentration is maintained for reactivity control in the. water-volume having direct access to the reactor vessel. These limitations are con-sistent with the initial conditions assumed for the boron dilution incident in the accident analyses. The value of 0.95 or less for Km includes a 1% delta 3
e K/K conservative allowance for uncertainties. Similarly, the boron concentra-J tion value of 2350 ppe or. greater also includes a conservative uncertainty
- 1 allowance of 50 ppm boron.
3/4.9.2 INSTRUMENTATION 2
redundant monitoring capability is available to detect changes in the The OPERABILITY of the source range neutron flux monitors ensures that reactivity condition of the core.
3/4.9.3 DECAY TIME i
The minimum requirement for reactor subcriticality prior to movement of-irradiated fuel assemblies in the reactor pressure vessel ensures that suffi-cient time has elapsed to allow the radioactive decay of the short lived fis-i sion products. This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
Operability r,f the containment airlock door requires that the door is capable of being closed; that the door is unblocked and no cables or hoses are being run through the airlock; and that a designated individual is continuously available to close the airlock door. This individual must be stationed at the outer airlock doc.r.
i i
SAN ONOFRE - UNIT 2 8 3/4 9-1 AMENDMENT NO. O II7
=-
g?UELING OPERATIONS i
BASES 3/4.9.5 COMUNICATIONS r
The requirement for communications capability ensures that refueling i
station personnel.can be'promptly informed of significant changes in the-facility status or core reactivity condition during CORF ALTERATIONS.
3/4.9.6 REFUELING MACHig the The OPERABILITY requirements for the refueling machine ensure that:- (1) ding refueling machine will be used for movement of all fuel assemblies inclu those with a CEA inserted, (2) each machine has sufficient load capacity to lift a fuel assembly including those with a CEA, and.(3) the core internals and i
pressure vessel are protected from excessive lifting force in the event-they are inadvertently engaged during lifting operations.
Five finger CEAs are removed from the reactor vessel either along with the associated fuel bundle utilizing the refueling machine or can be removed without the associated fuel bundle utilizing the refueling machine auxiliary hoist. The four finger CEAs are inserted through the upper guide structure with two fingers in each of the two adjacent fuel bundles in the periphery of
-i the core. The four finger CEAs are either removed with the upper guide struc-ture and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or the refueling machine auxiliary hoist.
Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is I
accomplished using one of the gripper operating tools. The coupling and uncoupling is verified by weighing the drive shaft extensions.
.l 3 /4.9. 7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING A.
Refueling Operations The restriction on movement of loads in excess of the nominal weight cf a l
fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in six fuel assemblies, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption-is based on the calculated results which demonstrate that, with credit taken for the fuel handling building filters, the offsite doses would be well within (less than 25%)
i the 10 CFR 100 limits.
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h SAN ONOFRE - UNIT 2 8 3/4 9-2 AMENDMENT NO. 37,104, 117 i
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g-UNITED STATES
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NUCLEAR REGULATORY COMMISSION N
2 WASHINGTON, D.C. 20056 0001
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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 ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 106 l
License No. NPF-15 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, 1993, as supplemented by letters dated June 3,1994, August 25, 1994, and January 3, 19, and 30, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the pubitc; and 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.
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2.
Accordingly, the license;. is amended by changes to the Technical..Speci--
fications as indicated in the attachment to this. license amendment, and paragraph 2.C(2) of Facility. Operating License No. NPF-15 is hereby amended to read as follows: '
(2)_
Technical Snecifications.
.i The Technical Specifications contained in Appendix A and the-Environmental Protection Plan contained in Appendix B,- as revised 3
through Amendment No.106, are' hereby incorporated in the i
license. Southern California Edison-Company shall operate the facility in~accordance with the Technical Specifications and the i
Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY C ISSION-ff E'
C' Nel B. Fields, Project Nanager Project Directorate IV-2' Division of Reactor Projects III/IV Office of Nuclear Reactor. Regulation
Attachment:
Changes to the Technical Specifications 4
Date of Issuance:
February 28, 1995 I
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 106 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 amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain L
document completeness.
REMOVE INSERT 3/4 9-4 3/4 9-4 3/4 9-4a B 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 1
i J
SURVEILLANCE REQUIREMENTS 4.9.4 Each of the above required containment building penetrations shall be.
determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE-automatic containment page valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or i
movement of irradiated fuel in the containment building by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Testing the containment purge valves per the applicable pertions of Specification 4.6.3.2.
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SAN ONOFRE - UNIT 3 3/4 9-4a AMENDMENT NO. 106
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i REFUELING OPERATIONS j
6 3/4.9.4 CONTAlletENT BUILDING PENETRATIONS
'l LINITINg rnamITION FOR OPERATION
. 3.9.4 The containment' building penetrations 'shall be in the following status:
f a.
The equipment door closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed,* and
.j c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:.
l I.
Closed by an isolation valve, blind flange, or manual valve, or j
2.
Be capable of being closed by an OPERABLE automatic containment purge valve.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within -
the containment.
j E UQN:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
j i
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)
- Both doors of the containment personnel airlock may be open provided:
a.
one personnel airlock door is OPERABLE, and bl. the plant is in MODE 6 with 23 feet of water above the fuel in the reactor vessel, or b2. defueled configuration with fuel in containment (i.e., fuel in refueling machine or upender).
SAN ONOFRE - UNIT 3 3/4 9-4 ANENOMENT N0.106
- e i
3/4.9 REFUELING OPERATIONS
)
RASES l
t 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELI C ensure--
- 7
~ that:. 1) the reactor will remain subcritical during CORE ALTERATIONS, and'
- 2) a uniform boron concentration is maintained for reactivity control in'the water volume having direct access to the reactor vessel. These limitations i"
are consistent with the initial. condition's assumed for the boron dilution includes r
The value of 0.95 or less for 4'the boron incident in the accident anal ses.
Similarly, a 1% delta'K/K conservative a lowance for uncertainties.
concentration value of 2350 ppe or greater also includes a conservative uncertainty allowance of 50 ppe boron.
i I
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that l'
redundant monitoring capability is available to detect changes in the reactivity condition of the core.
j l
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of i
irradiated fuel assemblies in the reactor pressure vessel ensure; that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in 4
the accident analyses, f
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS I
The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be i
restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization l
potential while in the REFUELING MODE.
i Operability of the containment airlock door requires that the door is capable of being closed; that the door is unblocked and no cables or hoses are being run through the airlock; and that a designated individual is continuously l
available to close the airlock door. This individual must be stationed at the outer airlock door.
f SAN ONOFRE - UNIT 3 8 3/4 9-1 AMEN 0 MENT NO.4 106 t
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REFUELING OPERATIONS
' RASES i
3/4.g.5 C0fMUNICATIONS The requirement for communications capability ensures that refueling i
station personnel can be promptly informed of significant changes in the, v
facility status or core reactivity condition during CORE-ALTERATIONS.
3/4.9.6 REFUELING MACHINE
.l t
The OPERABILITY requirements for the refueling macnine ensure that:
(1) the 1
refueling machine will be used for movement of all fuel assemblies including l
those witha a CEA inserted, (2) each machine has sufficient load capacity to lift a fuel. assembly including those with a CEA, and (3). the core internals and pressure vessel are protected from excessive lifting force in the event
-l they are inadvertently engaged during lifting operations.
Five finger CEAs are removed from the reactor vessel either along with the
~
associated fuel bundle utilizing the refueling machine or can be removed without the associated fuel bundle utilizing the refueling machine auxiliary hoist. The four finger CEAs are inserted through the upper guide structure with two fimers in each of the two adjacent fuel bundles in the periphery of 1
the core. The four finger CEAs are either removed with the upper guide structure and lift rig or can be removed with separate tooling prior to upper guide structure removal utilizing the auxiliary hoist of the polar crane or l
the refueling machine auxiliary hoist.
.1 Coupling and uncoupling of the CEAs and the CEDM drive shaft extensions is 1
accomplished using one of the gripper operating tools. The coupling and i
uncoupling is verified by weighing the drive shaft extensions.
j 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING l
A.
Refueling Operation
}
The restriction on movement of loads in excess of the nominal weight.of a fuel assembly, CEA and associated handling tool over other fuel i
assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in six i
fuel assemblies, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is based on l
the calculated results which demonstrate that, with credit taken for the fuel handling building filters, the offsite doses would be well within (less than 25%) the 10 CFR 100 limits.
i t
)
i SAN ONOFRE - UNIT 3 B 3/4 9-2 AMENOMENT N0.h, 03,106 l
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