ML13319B033
| ML13319B033 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/02/1992 |
| From: | Ray H Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13319B032 | List: |
| References | |
| NUDOCS 9204070137 | |
| Download: ML13319B033 (19) | |
Text
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON
)
COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY
)
DOCKET NO. 50-206 for a Class 104(b) License to Acquire,
)
Possess, and Use a Utilization Facility as
)
Amendment Application Part of Unit No. 1 of the San Onofre Nuclear
)
NO. 203 Generating Station
)
SOUTHERN CALIFORNIA EDISON COMPANY and SAN DIEGO GAS & ELECTRIC COMPANY, pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 203.
This amendment consists of Proposed Change No. 254 to Facility Operating License No. DPR-13. Proposed Change No. 254 modifies the Facility Operating License to a "Possession Only License."
The proposed change will allow Southern California Edison (SCE) to possess special nuclear material but will remove authorization to operate the nuclear reactor. The change is requested to take effect at the completion of the current Fuel Cycle 11 once all fuel is off-loaded from the core to the spent fuel pool.
Once all fuel is placed in long term storage, SCE will provide certification that all special nuclear material as reactor fuel has been permanently off-loaded from the core.
This condition is consistent with SCE's intentions to permanently shutdown and defuel the reactor as a precursor to the decommissioning of SONGS 1.
Based on the significant hazards analysis provided in the Description and Significant Hazards Consideration Analysis of Proposed Change No. 254, it is concluded that (1) the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92, and (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change.
9204070137 920402 PDR ADOCK 05000206 P
Respectfully submitted, SOUTHERN CALIFORNIA EDISON COMPANY By:
Harold B. Ray Senior Vice Presid State of California County of Orange On APAl42 0?
129 bef ore me, 7-44e
.kcC
~~YY 7'at'l/ CQ personally appeared /1/M/R&LD 2?, #
, personally known to me to be the person whose name is subscribed to the within instrument and acknowledged to me that he executed the same in his authorized capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted, executed the instrument.
WITNESS my hand and official seal.
Signature James A. Beoletto Attorney for Southern California Edison Company By:
James Beoletto DESCRIPTION AND SIGNIFICANT HAZARD CONSIDERATION ANALYSIS OF PROPOSED CHANGE NO. 254 TO FULL TERM OPERATING LICENSE NO. DPR-13 DESCRIPTION This application to revise the Facility Operating License for San Onofre Nuclear Generating Station, Unit 1 (SONGS 1) is the first step for the orderly shutdown of SONGS 1. The purpose of the proposed change is to change the Facility Operating License to a "Possession Only License" where the licensee may possess special nuclear material, but not operate the reactor following the completion of Fuel Cycle 11.
The end of Fuel Cycle 11 may occur as early as November 1992 or as late as June 1993.
The proposed change is necessary to remove Southern California Edison's (SCE) authority to operate SONGS 1 as a nuclear power plant and establish the basis for the NRC to grant relief from certain regulatory requirements that are inappropriate for a permanently shutdown and defueled reactor.
EXISTING OPERATING LICENSE See Attachment 1.
PROPOSED OPERATING LICENSE See Attachment 2.
DISCUSSION BACKGROUND San Diego Gas and Electric Company (SDG&E), and SCE have decided to discontinue operation of SONGS 1 at the end of Fuel Cycle 11.
This decision was made among SCE, SDG&E, and the California Public Utilities Commission (CPUC) to permanently close SONGS 1. SONGS 1 began operation in 1968 and is jointly owned by SCE (80%) and SDG&E (20%). The site also includes two other nuclear generating stations that are unaffected by this decision to discontinue operations.
In accordance with the Facility Operating License, issued in September 1991, SCE and SDG&E are required to complete a number of plant modifications prior to Fuel Cycle 12.
These modification were confirmed in an NRC Order dated January 1990, and were estimated to cost $125 million.
Pursuant to the order, SCE began the engineering as required for the Cycle 12 Modifications, including procurement of a simulator. In parallel, SCE sought approval from the CPUC to make the required expenditures.
Extensive evaluations showing the cost-effectiveness of the expenditures were completed and submitted to the CPUC and the appropriate hearings were held. However, the CPUC Division of Ratepayer Advocates (DRA) strongly opposed approval of the expenditures.
While SCE sought vigorously to alter these-conclusions, SCE was not successful, and the DRA continued to believe that the Cycle 12 modification expenditures would not be cost-effective.
Consequently, SCE, SDG&E, and the CPUC staff reached an agreement that will close SONGS 1 within the next two years. The plant will discontinue operation at the end of the current Fuel Cycle 11, and will be permanently shutdown and the reactor defueled. Fuel Cycle 11 includes the option for extended operation by performing a reload to reinsert prematurely discharged fuel.
This will extend operation by approximately 6 months.
CHANGES The requested changes to the Facility Operating License are to delete references to use special nuclear material as reactor fuel and authorization to operate the facility as a nuclear generating station at reactor power levels.
Implementation of the "Possession Only License" is SCE's first step toward permanent cessation of operations and the orderly shutdown of SONGS Unit 1.
Regardless of the issue and approval date of this license amendment by the NRC, SCE requests that the effective date of this amendment be the date SCE provides certification, by letter, that all fuel has been off-loaded from the core and stored in the spent fuel pool.
License condition item 2.C.(8) will allow the NRC to issue the Possession Only License prior to the permanent shutdown of SONGS 1.
SIGNIFICANT HAZARDS CONSIDERATIONS ANALYSIS In accordance with 10 CFR 50.91(a)(1), the following analysis is provided to demonstrate that the proposed changes do not represent a significant hazards consideration. According to 10 CFR 50.92(c), the proposed changes discussed above are deemed not to involve a significant hazards consideration if there is a positive finding in any one of the following areas:
- 1.
Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of any accident previously evaluated?
Response: No The proposed change will remove SCE's authorization to operate SONGS 1 as a nuclear generating station. The proposed amendment does not modify the present plant systems or administrative controls necessary to preserve and protect the integrity of the spent fuel pool.
The proposed amendment will actually involve a significant decrease in the probability or consequences of previously evaluated accidents since there will not be any fuel in the reactor. Those design basis accidents credible for an operating reactor are eliminated when SONGS 1 is permanently shutdown and completely defueled. In addition, a fuel handling accident has been previously analyzed to address the consequences of an accident while fuel is in the spent fuel pool, in the reactor, or in transit during core off load.
0 The probability or consequences from a fuel handling accident remains unchanged and bounded by the accident analysis. Therefore, the proposed change is deemed not to involve a significant hazard.
- 2.
Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No Upon permanent shutdown and defueling the reactor at the end of Fuel Cycle 11 under this proposed change, SCE's authorization to resume power operations is removed. Therefore, this change will not create the possibility of a new or different kind of accident from any accident previously evaluated. Any accident associated with this proposed change is bounded by current accident analyses. Existing analyses address potential accident scenarios from reactor startup through full power operation.
There are no new accident scenarios or failure modes created by maintaining the reactor in the defueled condition. In the permanently shutdown, defueled condition with all fuel stored in the spent fuel pool, there are no new credible accident conditions from those previously analyzed.
Therefore, the proposed change will not create the possibility of new or different kind of accident.
- 3.
Will operation of the facility in accordance with this proposed change involve a significant reduction in the margin of safety?
Response
No The proposed change removes SCE's authorization to operate SONGS 1 as a nuclear generating station. Defueling the reactor and placing the fuel in long term storage in the spent fuel pool in a subcritical condition does not affect previously accepted margins of safety. Therefore, the proposed change does not involve a significant reduction in the margin of safety.
SAFETY AND SIGNIFICANT HAZARDS DETERMINATION Based on the above Safety Analysis, it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.
ATTACHMENT 1 EXISTING FACILITY OPERATING LICENSE
0 UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 FACILITY OPERATING LICENSE Amendment No.
144 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found, that:
A. The application for a license filed by the Southern California Edison Company and the San Diego Gas and Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of.1954,,as amended (the Act), and applicable portions of *the Commission's regulations set forth in 10 CFR Chapter I. and all required notifications to other agencies or bodies--have been duly made; B. Construction of San Onofre Nuclear Generating Station, Unit 1 (the facility) has been completed in conformity with Construction Permit No. CPPR-13 and the application, as amended, the provisions of the Act, and the regulations of the Commission, and has been operating under a provisional license since March 27, 1967; C.1 The facility will operate in conformity with the application, as
'amended, the provisions of the Act, and the applicable rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with applicable portions of the Commnission 's regulations set forth in 10 CFR Chapter I; E. The licensee is technically qualified to engage in~ the activities authorized by this license in accordance with the Commission's regulations set forth in applicable portions of 10 CFR Chapter 1; F. The liceris~e has satisf-Ita the applicable provisions of 10 CFR Part 140, "Financial,Protection Requirements and Indemnity Agreements,"
of the Commission's regulations;
-2 G.,
Theissuance of.this license will not be inimical to the common defense and -security-or to the health and safety of the public; H. The issuance of this license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accordance with the.Commission's regulations in 10 CFR Parts 30, 40, and 70.
- 2. Provisional Operating License No. DPR-13, dated March 27, 1967, as amended, is superseded in its entirety by Facility Operating License No. DPR-13 hereby issued to the licensee to read as follows:
A. This license applies to the San Onofre Nuclear Generating Station, Unit 1, a pressurized water reactor and associated equipment (the faci-lity). iThe facility is located on the site of Southern California Edison Company and San Diego Gas and Electric Company near the northern boundary of Camp Pendleton in San Diego County, California, and is described in the licensee's Updated Final Safety Analysis Report, as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B. -Subject to the conditions and requirements incorporated herein, the
,Commission hereby licenses Southern California Edison (SCE) and San Diego Gas and Electric (SDG&E), with SCE acting for itself and as agent for SDG&E:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in San Diego County, California, in accordance with
.,auxthe procedures-and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material a.s reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutrone sources for reactor startup, sealed sources for reactor instrumentation, dnd radiation monitoring equipment calibration, and as fission detectors in amounts as required; Amendment No. 144
-3 (4),Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical.or.physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Act and the applicable provisions of the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject tothe additional conditions specified or incorporated.below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 1347 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 144 is hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
(3)
Spent Fuel Transshipment The licensee is authorized to transship spent fuel from the Unit 1 spent fuel pool to the Unit 2 and 3 spent fuel pools in accordance with licensee's application for amendment dated April 28, 1988, as supplemented April 25, June 10, September 23, October 18, November 10, and December 1, 1988.
This authorization is limited to those activities needed for transshipment only. The matter of heavy load handling using the turbine gantry crane for purposes other than transshipment is being reviewed separately.
The licensee may make changes to the transshipment methods referenced above without prior NRC approval only if the change does not involve an unreviewed safety question as defined in 10 CFR 50.59.
Amendment No. 144
-4 (4) Physical Protection SCE shall fully implement and maintain in effect all provisions of'the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50,54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with revisions submitted through April 22, 1988; "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan," with revisions submitted through October 22, 1986; and "San Onofre Nuclear Generating Station, Units 1, 2, and 3, Safeguards Contingency Plan," with revisions submitted through December 29, 1987. Changes made in accordance with 10 CFR 73.55-shall be implemented in accordance with the schedule set forth therein.
(5) Integrated Implementation Schedule Southern California Edison Company shall implement a plan for vschedulling fall capital.modifications-ba-sed-on the.Integrated Implementation;Schedule Program Plan (the "Plan") issued in License Amendment No. 98 on April 20, 1987.
(a) The Plan shall be followed by the licensee from and after the effective date of Amendment 98.
(b) Changes to completion dates for items identified in Schedules B and C do not require a license amendment.
Dates specified in Schedule A shall be changed only.in accordance with applicable NRC procedures.
(6) Cycle 11 Thermal Shield Monitoring Program The neutron noise/loose-parts detection system shall be used to monitor the condition of the reactor vessel thermal shield -,
throughout Cycle 11.
Periodic monitoring of both neutron noise and loose-parts vibrations confirms that no long-term unacceptable trend of degradation is occurring. The details of this program are described below.
(a) Acceptance criteria for neutron noise/loose-parts monitoring will be established by performing baseline evaluations for.60 days at greater than or equal to 85%
power following return to service for Cycle 11 operation.
The base line data will be established by recording a minimum of 16 segments of data information, each of Amendment No. 144
-5 20 minute duration at greater than or equal to 85% power.
-Adjustments to the acceptance criteria will be made for cycle burnup and boron concentration changes throughout the cycle.
(b) The neutron noise/loose-parts monitoring system shall be OPERABLE in MODE 1 with:
(i) at least two horizontal loose-parts detectors monitored for at least 5 minutes two times per day; and, (ii) at least three (3) neutron noise inputs monitored for at least 20 minutes once a week, and be analyzed for cross power spectral density, including phase and coherence.
cThe-data provided by the loose-parts/neutron noise.
monitor shall be analyzed once per week and compared with the established criteria. If the data exceeds the acceptance criteria:
(i) within 1 day the NRC will be informed;
.- ) -within 14..days.the cond.itionsswillbe evaluated
. and a report provided to the NRC documenting future plans and actions.
(d) Each channel of the loose-part detection system shall be.demonstrated OPERABLE in MODE 1 by~performance of a:
Ci) CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (ii)
CHANNEL TEST at least once per 31 days The surveillance requirements for neutron noise monitor are covered by the Appendix A Technical Specification 4.1.1 for the Power Range Neutron Flux.
(e)
With the neutron noise/loose-parts detection instrumentation inoperable for more than 7 days, licensee shall submit a Special Report to the Commission pursuant to Appendix A Technical Specification 6.9.2 within the next 3 days outlining the cause of the malfunction and the plans for restoring the system to operable status.
(f) The provisions of Appendix A Technical Specification 3.0.4 are not applicable to this license condition.
Amendment No. 144
-6 (7) Plant Modification to Eliminate Single Failure Susceptibility
<of Vital Bus Automatic Transfer Function Southern California Edison Company shall modify the electrical distribution system to ensure that the availability of a power source for vital buses 1, 2, 3, and 3A is not subject to a single failure susceptibility. The plant modification shall satisfy the design requirements of the safety-related portions of the existing electrical distribution system and shall be operable prior to restart from the Cycle 12 refueling outage.
(8) Confirmatory Order dated January 2, 1990 The licensee shall comply with commitments documented in the NRC confirmatory order issued on January 2, 1990, as amended.
The confirmatory order contains a list of required plant modifications and evaluations with associated implementation schedules.
D. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency
.Notification. System with, written follow-up.within.30 days in accordance with the-procedures described in 10 CFR 50.73(b), (c),
and (e).
E.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover.public liability claims.
F. This license is effective as of the date of issuance and shall expire at midnight on March 2, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A -
Technical Specifications Date,of Issuance:
September 26, 1991 Amendment No.
144
ATTACHMENT 2 PROPOSED POSSESSION ONLY LICENSE
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 FACILITY OPERATING LICENSE Amendment No.
License No. DPR-13
- 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. The application for a license filed by the Southern California Edison Company and the San Diego Gas and Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and applicable portions of the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. Construction of San Onofre Nuclear Generating Station, Unit 1 (the facility) has been completed in conformity with Construction Permit No.
CPPR-13 and the application, as amended, the provisions of the Act, and the regulations of the Commission, and has been operating under a provisional license since March 27, 1967; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the applicable rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with applicable portions of the Commission's regulations set forth in 10 CFR Chapter I; E. The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in applicable portions of 10 CFR Chapter I; F. The licensee has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations;
-2 G. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H. The issuance of this license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I. The possession of source, byproduct, and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
- 2.
Facility Operating License No. DPR-13, dated September 26, 1991, as amended, is superseded in its entirety by Facility Operating License No.
DPR-13 as a Possession Only License hereby issued to the licensee to read as follows:
A. This license applies to the San Onofre Nuclear Generating Station, Unit 1, a pressurized water reactor and associated equipment (the facility).
The facility is located on the site of Southern California Edison Company and San Diego Gas and Electric Company near the northern boundary of Camp Pendleton in San Diego County, California, and is described in the licensee's Updated Final Safety Analysis Report, as supplemented and amended, and in the licensee's Environmental Report, as supplemented and amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Southern California Edison (SCE) and San Diego Gas and Electric (SDG&E),
with SCE acting for itself and as agent for SDG&E:
(1)
Pursuant to Section 104b of the Act and 10 CFR Part 50, to possess but not operate the facility at the designated location in San Diego County, California, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to possess at any time special nuclear material as reactor fuel, in accordance with the limitations for storage as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed sources for reactor instrumentation, and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Amendment No. 144,
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess or use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Act and the applicable provisions of the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is not authorized to operate the facility as a nuclear reactor.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 144 is hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
(3) Spent Fuel Transshipment The licensee is authorized to transship spent fuel from the Unit 1 spent fuel pool to the Unit 2 and 3 spent fuel pools in accordance with licensee's application for amendment dated April 28, 1988, as supplemented April 25, June 10, September 23, October 18, November 10, and December 1, 1988.
This authorization is limited to those activities needed for transshipment only. The matter of heavy load handling using the turbine gantry crane for purposes other than transshipment is being reviewed separately.
The licensee may make changes to the transshipment methods referenced above without prior NRC approval only if the change does not involve an unreviewed safety question as defined in 10 CFR 50.59.
Amendment No. 144,
-4 (4) Physical Protection SCE shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain safeguards Information protected under 10 CFR 73.21, are entitled:
"San Onofre Nuclear Generating Station, Units 1, 2, and 3 Physical Security Plan," with revisions submitted through April 22, 1988; "San Onofre Nuclear Generating Station, Units 1, 2, and 3 Security Force Training and Qualification Plan,"
with revisions submitted through October 22, 1986; and "San Onofre Nuclear Generating Station, Units 1, 2, and 3, Safeguards Contingency Plan," with revisions submitted through December 29, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(5) Integrated Implementation Schedule Southern California Edison Company shall implement a plan for scheduling all capital modifications based on the Integrated Implementation Schedule Program Plan (the "Plan") issued in License Amendment No. 98 on April 20, 1987.
(a) The Plan shall be followed by the licensee from and after the effective date of Amendment 98.
(b) Changes to completion dates for items identified in Schedules B and C do not require a license amendment. Dates specified in Schedule A shall be changed only in accordance with applicable NRC procedures.
(6) Cycle 11 Thermal Shield Monitoring Program The neutron noise/loose-parts detection system shall be used to monitor the condition of the reactor vessel thermal shield throughout Cycle 11.
Periodic monitoring of both neutron noise and loose-parts vibrations confirms that no long-term unacceptable trend of degradation is occurring. The details of this program are described below.
(a) Acceptance criteria for neutron noise/loose-parts monitoring will be established by performing baseline evaluations for 60 days at greater than or equal to 85% power following return to service for Cycle 11 operation. The base line data will be established by recording a minimum of 16 segments of data information, each of Amendment No. 144,
-5 20 minute duration at greater than or equal to 85% power.
Adjustments to the acceptance criteria will be made for cycle burnup and boron concentration changes throughout the cycle.
(b) The neutron noise/loose-parts monitoring system shall be OPERABLE in MODE 1 with:
(i) at least two horizontal loose-parts detectors monitored for at least 5 minutes two times per day; and, (ii) at least three (3) neutron noise inputs monitored for at least 20 minutes once a week, and be analyzed for cross power spectral density, including phase and coherence.
(c) The data provided by the loose-parts/neutron noise monitor shall be analyzed once per week and compared with the established criteria. If the data exceeds the acceptance criteria:
(i) within 1 day the NRC will be informed; (ii) within 14 days the conditions will be evaluated and a report provided to the NRC documenting future plans and actions.
(d) Each channel of the loose-part detection system shall be demonstrated OPERABLE in MODE 1 by performance of a:
(i) CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (ii)
CHANNEL TEST at least once per 31 days The surveillance requirements for neutron noise monitor are covered by the Appendix A Technical Specification 4.1.1 for the Power Range Neutron Flux.
(e) With the neutron noise/loose-parts detection instrumentation inoperable for more than 7 days, licensee shall submit a Special Report to the Commission pursuant to Appendix A Technical Specification 6.9.2 within the next 3 days outlining the cause of the malfunction and the plans for restoring the system to operable status.
(f) The provisions of Appendix A Technical Specification 3.0.4 are not applicable to this license condition.
Amendment No. 144,
-6 (7) Plant Modification to Eliminate Single Failure Susceptibility of Vital Bus Automatic Transfer Function Southern California Edison Company shall modify the electrical distribution system to ensure that the availability of a power source for vital buses 1, 2, 3, and 3A is not subject to a single failure susceptibility. The plant modification shall satisfy the design requirements of the safety-related portions of the existing electrical distribution system and shall be operable prior to restart from the Cycle 12 refueling outage.
(8) Confirmatory Order dated January 2, 1990 The licensee shall comply with commitments documented in the NRC confirmatory order issued on January 2, 1990, as amended. The confirmatory order contains a list of required plant modifications and evaluations with associated implementation schedules.
(9) Licensee Certification of Permanently Shutdown Condition Regardless of the issue and approval date of this license Amendment No. _,
the effective date of this amendment shall be the date the licensee provides certification that all special nuclear material as reactor fuel has been permanently offloaded from the reactor for storage in the spent fuel pool.
D. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
E. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
F. This license is effective as of the date of issuance and shall expire at midnight on March 2, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A - Technical Specifications Date of Issuance:
Amendment No. 144,