ML13309A341
| ML13309A341 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/30/1992 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13309A339 | List: |
| References | |
| NUDOCS 9211060149 | |
| Download: ML13309A341 (18) | |
Text
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTHERN CALIFORNIA EDISON COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption to Facility Operating License No. DPR-13 issued to Southern California Edison Company (the licensee), for operation of San Onofre Nuclear Generating Station Unit 1 located in San Diego County, California.
ENVIRONMENTAL ASSESSMENT Identification of Proposed Action The proposed action would allow exemptions to the leak rate testing requirements of 10 CFR 50.54(o) and all leak rate testing delineated in Appendix J, Title 10 of the Code of Federal Regulations, Part 50.
Permanent shutdown and defueling of the San Onofre, Unit 1, reactor following the current fuel cycle, Cycle 11, is proposed by the licensee.
Upon permanent shutdown, maintaining containment integrity will no longer be necessary to assure that the leakage of radioactivity will not exceed the allowable value specified in the Technical Specifications.
The proposed action is in accordance with the licensee's application for exemption dated October 1, 1992.
The Need for the Proposed Action The proposed exemption is required in order for the licensee to avoid 9211060149 921030 PDR ADOCK 05000206 P
-2 incurring unnecessary expense, radiation exposure, or delay to the planned defueling schedule.
Environmental Impact of the Proposed Action The Commission has completed its evaluation of the proposed exemption, and concludes that the proposed changes do not involve a modification to plant equipment or to methods of operation, but do permit the elimination of unnecessary testing. The proposed action affects a plant component's surveillance requirements only. Therefore, the proposed exemption does not increase the probability or consequences of accidents; no changes are being made in the types of any effluents that may be released offsite; and there is no significant increase in the allowable individual or cumulative occupational radiation exposure. Accordingly, the Commission concludes that this proposed action would result in no significant radiological environmental impact.
With regard to potential nonradiological impacts, the proposed exemption involves a plant component's surveillance requirements only. It does not affect nonradiological plant effluents and has no other environmental impact. Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption.
Alternative to the Proposed Action Since the Commission concluded that there are.no significant environmental effects that would result from the proposed action, any alternatives with equal or greater environmental impacts need not be evaluated.
-3 The principal alternative would be to deny the requested exemption.
This denial would not reduce environmental impacts of plant operation and would result in unnecessary expense, unnecessary radiation exposure to operating personnel and delay.
Alternative Use of Resources This action does not involve the use of resources not previously considered in the Environmental Assessment related to the conversion of the Provisional Operating License to a Full Term Operating License granted to the Southern California Edison Company for San Onofre Unit 1 dated September 16, 1991.
Agencies and Persons Consulted The NRC staff reviewed the licensee's request and did not consult other agencies or persons.
FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact statement for the proposed exemption.
Based upon the foregoing environmental assessment, the Commission concludes that the proposed action will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the licensee's application for exemption dated October 1, 1992, which is available for public inspection at the Commission's Public Document Room, Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the local
-4 public document room at the Main Library, University of California, Post Office Box 19557, Irvine, California 92713.
Dated at Rockville, Maryland, this 30th day of October, 1992.
FOR THE NUCLEAR REGULATORY COMMISSION Harry Ro, Acting Director Project Directorate V Division of Reactor Project III/IV/V Office of Nuclear Reactor Regulation
October 23, 1992 Docket No. 50-206 Mr. Harold B. Ray
. / O Senior Vice President Southern California Edison Co.
Irvine Operations Center 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
ISSUANCE OF AMENDMENT FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 (TAC NO. M83123)
The Commission has issued the enclosed Amendment No.150 to Facility Operating License No. DPR-13 for San Onofre Nuclear Generating Station, Unit No. 1.
This amendment is in response to your application dated April 2, 1992.
This amendment modifies License No. DPR-13 to a possession only license (POL) to be effective upon the permanent cessation of operations at SONGS-1 and the receipt of a letter certifying that all fuel has been offloaded from the core and stored in the spent fuel pool.
Although the NRC must approve the decommissioning alternative and major structural changes to radioactive components of the facility, Southern California Edison Company may proceed with activities after the POL becomes effective (such as additional decontamination, component disassembly, and shipment and storage of spent fuel), if these activities: (1) are permitted by the POL and 10 CFR 50.59, and (2) do not materially and demonstrably affect the methods or options available for decommissioning or substantially increase the cost of decommissioning.
A copy of our safety evaluation is also enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register Notice.
Si rel John 0. Bradfute, ting Project Manager Project Directorate V Division of Reactor Projects -
III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
- 1. Amendment No.150 to DPR-13
- 2. Safety Evaluation cc w/enclosures:
See next page
- previou y concurred XP PDV: L! g.,PDNP:PE*
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l.a UNITED STATES NUCLEAR REGULATORY COMMISSION 40 WASHINGTON, D. C. 20555 October 23, 1992 Docket No. 50-206 Mr. Harold B. Ray Senior Vice President Southern California Edison Co.
Irvine Operations Center 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
ISSUANCE OF AMENDMENT FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 (TAC NO. M83123)
The Commission has issued the enclosed Amendment No. 150to Facility Operating License No. DPR-13 for San Onofre Nuclear Generating Station, Unit No. 1.
This amendment is in response to your application dated April 2, 1992.
This amendment modifies License No. DPR-13 to a possession only license (POL) to be effective upon the permanent cessation of operations at SONGS-1 and the receipt of a letter certifying that all fuel has been offloaded from the core and stored in the spent fuel pool.
Although the NRC must approve the decommissioning alternative and major structural changes to radioactive components of the facility, Southern California Edison Company may proceed with activities after the POL becomes effective (such as additional decontamination, component disassembly, and shipment and storage of spent fuel), if these activities: (1) are permitted by the POL and 10 CFR 50.59, and (2) do not materially and demonstrably affect the methods or options available for decommissioning or substantially increase the cost of decommissioning.
A copy of our safety evaluation is also enclosed. The notice of issuance will be included in the Commission's biweekly Federal Register Notice.
Sincerely, John 0. Bradfute, Acting Project Manager Project Directorate V Division of Reactor Projects -
III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
- 1. Amendment No. 150to DPR-13
- 2. Safety Evaluation cc w/enclosures:
See next page
Mr. Harold B. Ray San Onofre Nuclear Generating Southern California Edison Company Station, Unit I Docket No. 50-206 cc:
Mr. Howard J. Wong U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Robert G. Lacy Manager, Nuclear Department San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U.S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92674 Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672 Chairman, Board of Supervisors County of San Diego 1600 Pacific Highway, Room 335 San Diego, California 92101 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Hank Kocol Radiologic Health Branch State Department of Health Services P. 0. Box 942732 Sacramento, California 94234 Mr. Don J. Womeldorf Chief, Environmental Management Branch California Department of Health Services 714 P. Street, Room 616 Sacramento, California 95814 Mr. Richard J. Kosiba, Project Manager Bechtel Power Corporation 12440 E. Imperial Highway Norwalk, California 90650
1,%REGU UNITED STATES NUCLEAR REGULATORY COMMISSION 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 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 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; C. The facility will be maintained 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 amended 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 Possession Only License (POL)
No. DPR-13, hereby issued to the licensee to read as follows:
A. This license applies to the San Onofre Nuclear Generating Station, Unit No. 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 a 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 locration 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; (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 Amendment No. 150
-3 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. 150 are hereby incorporated in the license. Southern California Edison Company shall maintain 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.150
0-4 (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 Licensee 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.
Amendment No. 150
- 5 The base line data will be established by recording a minimum of 16 segments of data information, each of 20 minutes 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 Amendment No.150
-6 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 operable status.
(f) The provisions of Appendix A Technical Specification 3.0.4 are not applicable to this license condition.
(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.
Amendment No.150
-7 F. This amended license is effective as of the date the licensee provides certification that operation of the reactor has been permanently terminated and all special nuclear material as reactor fuel has been permanently removed from the reactor and stored in the spent fuel pool.
This amended license shall expire at midnight on March 2, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION Jack W. Roe, Director Division of Reactor Projects -
III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Appendix A - Technical Specifications Date of Issuance:
October 23, 1992
tpREGUC UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
By letter dated April 2, 1992, Southern California Edison Company (SCE or the licensee) proposed to amend Facility Operating License No. DPR-13 to a Possession-Only License (POL) for the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1 or the facility). The POL would permit the licensee to possess but not operate the facility. Although the SONGS-1 reactor has not been shut down, the licensee has proposed that a POL be approved while the facility is still operating, to become effective upon the permanent cessation of operation and certification to the NRC that all fuel has been offloaded from the reactor and stored in the spent fuel pool.
On May 13, 1992, the NRC published in the Federal Register (57 FR 20518), a Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing for the requested amendment. No public comments nor requests for intervention were received.
2.0 BACKGROUND
SONGS-1 received a Provisional Operating License on March 27, 1967 and began commercial operation on January 1, 1968. A Full-Term Operating License (OL) was not issued until September 26, 1991.
The OL was to expire on March 2, 2004, 40 years after the issuance of the SONGS-1 Construction Permit. The delay in issuing the OL was due primarily to an NRC staff reevaluation of the plant design to reconfirm its safety in light of operating experience and updated design standards that had developed since the plant was built in the 1960s.
The NRC staff review concluded that numerous modifications were required to SONGS-1 to upgrade the plant to safety standards that were in effect at newer nuclear power stations. SCE made many of the identified upgrades and
-2 committed to complete most of the modifications before restarting the reactor from Refueling Outage 12.
Refueling Outage 12 was scheduled at the end of 1992. The NRC formalized the licensee's commitment to complete the SONGS-1 modifications by issuing a Confirmatory Order on January 2, 1990. Based on the formalized commitment to upgrade the plant to contemporary safety standards, the NRC issued the OL in 1991.
While reviewing the SCE rate case, the California Public Utilities Commission (CPUC) concluded that the required upgrades for SONGS-1 were not cost effective and refused to permit the licensee to pass on the cost of the plant modifications to the ratepayers. Lacking a means to recoup the cost of the NRC mandated upgrades, SCE decided to stop power operations at SONGS-1 and requested to amend the license to a POL.
3.0 DISCUSSION AND EVALUATION The licensee has requested that the POL become effective upon certification that all reactor fuel has been removed from the reactor and stored in the spent fuel pool. The SCE letter of April 2, 1992, requested changes to the license that would permit the licensee to possess and maintain the facility but not operate it. The requested changes to the license are consistent with the expected permanent cessation of operation and reactor defueling. The staff's safety evaluation of the requested license changes is provided in the following paragraphs.
The probability of previously analyzed design basis accidents occurring with the plant in a defueled condition will be significantly reduced for the following reasons: (1) no significant safety hazards could result as the facility will be in a nonoperating condition and the entire core will be in the spent fuel pool; the consequences of credible fuel pool accidents, which are analyzed in Chapters 9 and 15 of the Final Safety Analysis Report, would be unchanged by the POL issuance; and (2) there is reasonable assurance that the common defense and security and the health and safety of public will not be endangered by the defueled, nonoperating status of the reactor. Based on the above, the staff concludes that there are no significant hazards considerations that would result from the issuance of a POL that becomes effective upon the complete defueling of the reactor vessel to the spent fuel pool.
The licensee's letter of April 2, 1992, proposed modifications to the Facility Operating License in order to convert it to a Possession Only License. The staff reviewed these proposals and determined that they are acceptable for the future nonoperating and defueled status of the reactor. In summary, the changes permit the licensee to maintain and possess the facility but not to operate it. The staff's evaluation of these changes is presented below:
- 1. Modify license paragraph 2.B.(1) to replace the reference to use and operation with possession but not operation.
Evaluation: This change is acceptable as it removes the facility from an operating status.
00
-3
- 2. Modify license paragraph 2.B.(2) to remove the authorization to receive and use special nuclear material used as reactor fuel at the facility.
Evaluation:
This change is acceptable as it removes the licensee's authority to receive and use special nuclear material as reactor fuel.
This change is consistent with the eventual nonoperating status of the facility.
- 3. Modify license paragraph 2.B.(3) to remove the reference to reactor startup.
Evaluation:
This change is acceptable as it removes an unnecessary use of special nuclear material as sealed neutron sources used only for startup. In addition, the remainder of this paragraph would properly allow the licensee to receive, possess, and use radioactive devices needed for radiation monitoring and instrument calibration as this use enables monitoring plant and environmental conditions which remain a condition of the POL and the Technical Specifications.
- 4. Modify license paragraph 2.C.(1) to remove the wording which authorizes the facility to operate at core power levels not in excess of 1346 megawatts thermal.
Evaluation:
This change is acceptable as it removes the licensed authority to operate the facility. The new paragraph 2.C.(1) will read:
"The licensee is not authorized to operate the facility as a nuclear reactor."
- 5. Modify license paragraph 2.F to reflect that this amendment is effective when the licensee provides certification in writing that all reactor fuel has been permanently offloaded from the reactor and stored in the spent fuel pool.
Evaluation:
This change is acceptable in that it reflects the conditions of the reactor vessel that provide the basis for the staff's finding of no significant hazards considerations that would result from the issuance of this POL.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative
-4 occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards considera tion, and there has been no public comment on such finding (57 FR 20518).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: John P. Moulton Date: October 23, 1992