ML19312C512
| ML19312C512 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/23/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C507 | List: |
| References | |
| NUDOCS 7912160071 | |
| Download: ML19312C512 (2) | |
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4 UNITED STATES
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4 NUCLEAR REGULATORY COMMISSION s'*'
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AENDENT NO. 38 TO FACILITY LICENSE NO DPR-38 AENDENT NO. 38 TO FACILITY LICENSE NO. DPR-47 AENDENT NO. 35 TO FACILITY LICENSE NO. DPR-55 DUKE POWER COEANY OCONEE NUCLEAR STATION, UNITS NOS.1, 2 AND 3 DOCKETS NOS. 50-269, 50-270 AND 50-287 Introduction By letter dated October 1,1975, Duke Power Company (licensee), requested revisions to the Oconee Nuclear Station Technical Specifications which would incorporate changes to the Oconee Unit 1 pressurization, heatup and cooldown limitations (pressure-tenperature operating limit curves),
and to the reactor vessel material surveillance program.
Discussion The Oconee Nuclear Station Technical Specifications require that the curves for heatup and cooldown be updated within two years of power operation in accordance with appropriate criteria accepted by the NRC.
(Formerly AEC). Two years of power operation is defined as 1.7 x 106 thermal megawatt-days.
The licensee's October 1,1975 submittal is in response to this requirement.
Evaluation The Oconee Unit 1 pressure-temperature coerating limit curves, Figures 3.1.2-1A, 3.1.2-2A and 3.1.2-3 are based on calculations for operation through 5 effective full power years (EFPY). These curves were prepared based on data from a Babcock & Wilcox Report, " Analysis of Capsule OCl-F From Duke Power Conpany Oconee Unit 1 Reactor Vessel Materials Surveillance Program," BAW-1421 Revision 1, dated September 1975.
We have reviewed BAW-1421, Revision 1 and the proposed pressure-temperature operating limit curves.
The data does not adequately support the use of these curves for 5 EFPY. We have, therefore, performed independent calculations based on the methods of Regulatory Guide 1.99.
Based on our independent calculations and our review of BAW-1421, we have concluded l
however, that the use of these curves is acceptable through 4 EFPY.
79121600 7/
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_s Following discussion with the licensee, the amendment has been prepared reflecting this limitation.
Discussions with the licensee indicated that revisions to the Oconee reactor vessel material surveillance program are being evaluated by the licensee and will be submitted to the Commission prior to Unit 1 Cycle 4 operation.
Based on these discussions action on the Technical Specification change proposed October 1,1975, has been deferred.
We have determined that these amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Corclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in conpliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Date: Februa ry 23, 1977 i
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UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETS NOS. 50-269, 50-270 AND 50-287 DUKE POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Comission (the Comission) has issued Amendments Nos. 38, 38 and 35 to Facility Operating Licenses Nos. OPR-38, DPR-47 and DPR-55, respectively, issued to Duke Power Company which revised the Technical Specifications for operation of the Oconee Nuclear Station Units Nos.1, 2 and 3, located in Oconee County, South Carolina.
The amendments are effective as of the date of issuance.
These amendments revise the common Oconee Station Technical Specifications to incorporate changes to the Oconee Unit 1 pressurization, heatup and cooldown limitations.
The application for the al.endments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
The Comission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 951.5(d)(4) an environmental impact statement or negative ch 7 7ll27oSN
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declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated October 1,1975, (2), Amendments Nos. 38, 38 ar.d 35 to Licenses Nos. DPR-38, DPR-47 and DPR-55, respectively, and (3) the Comission's related Safety Evaluation. All of these items are available for public inspection at the Ccamission's Public. Document Room, 1717 H Street, NW., Washington, D.C. and at the Oconee County Library, 201 South Spring Street, Walhalla, South Carolina 29691.
A copy of items (2) and (3) may be obtained upon request addressed to the U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 23rd day of February 1977.
FOR THE NUCLEAR REGULATORY COMiISSION h/($d/$W A. Sc dencer, Chief Operating Reactors 3 ranch #1 Division of Operating Reactors e
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