ML19308B203
| ML19308B203 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/03/1978 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19308B199 | List: |
| References | |
| NUDOCS 7912160080 | |
| Download: ML19308B203 (2) | |
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NUCLE AR REGULATORY CO*.iMist.lOrJ 4
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SAFETY CVALUATION BY THE OFFICE OF f!UCLEAR REACTOR REGULATI0fl
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SUPPORTIflG AMEflDMEf!T f;0. 61 TO FACILITY OPERATIt!G LICEtlSE fi0. DPR-38 1
AMENDMEllT !!0. 61 TO FACILITY OPERATIflG LICEflSE fiO. OPR-47, i
AMEtlDMEflT NO. 58 - TO FACILITY OPERATIrlG LICEtiSE NO. DPR-55 DUKE POWER COMPAfiY OC0 flee flVCLEAR STATI0ff, UtilT f10S.1, 2 At:D 3 00CKETS NOS. 50-269, 50-270 Afl0 50-287 i
Introductiqn_
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By letter dated February 16, 1970, Duke Power Company (DPC)
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l requested changes to the Oconee ficclear Station, Units flos.1, 2 and 3 Technical Specifications which would eliminate reactor trip on loss of-a single reactor coolant puap for Oconee Units flos. 2 and 3 and to nake other ninor corrections.
Discussion /Evalurtion The ma.ior change proposed by DPC is to' eliminate the pump monitor trip on less of one pump for Oconee Units f:os. 2 and 3.
This pump monitor s
trip was originally proposed by DPC in the license amendment request of So. e ac 1
'u l.he Oconee 1 Cycle 4 relosd in order to ir.ciuct in t% flux-lion trip setpoint a Departure fecm.:rleute i:oi. i~. N (C':.;P.) marqin f u rod bcw.
For Units flos. 2 cnd 3 this nrcir can be obtained fro:n excess reactor coolant flow rate.
Previous tiRC Safety Evaluations dated July-27,1977 and flovember 21, 1977, ccncluded that there was sufficient margin in excess coolant flow-so that a reactor trip on loss of a single reactor coolant pump was not needed for Units 2 and 3.
The sinole pump trip limit had been inadvertently applied to Units 2 and 3.
The pump monitor trip is only required for Oconee 1 as indicated in our Safety Evaluation of.0ctober 4,1977.
The proposed changes delete the loss of one. pump trip setitint for_ Oconee 2 and 3.
The licensee has rcoasured and veriffed.the excess reactor coolant flow.
The pecposed chiges ~also include correcuons to Technical-Specificaticqs-which were. pertinent only to Oconee 1 Cycle 2 which are ro longer re: n'nt
-as _ Unit 1 is currently in Cycle 4 operation; and deletion of setpoints ass statui with sinole loop operation which are no loncer applicable
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2 changes have been reviewed and they do establish a more appropriate set of Technical Specifications for current operations at the Oconee Units.
On these bases we find the proposed change to the Oconee Technical Specifications to be acceptable.
Environmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in po.zer level and will not result in any significant environmental impact.
Having made this deternination, we have further concluded that the amend :ents involve an acticn which is insignificant frem the standpoint of environmental innact cnd, pursuant to 10 CFR 551.5(d)(4), that an environmental inpact statement or negative declaration and envirencental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequenecs of accidents previously considered and do not involve a significant decrease in a safety margin, the e.::.end:.ents do not involve a significant hazarcs consideration, (2) there is reasons:ie assurance that the healtn and safety of the puolic will not be endannerec by operatien in the proposed manner, and (3) such activities will be conducted in cemplicnce with the.Commissicn's regulations and tne issuance of these cmsecrents will not be inimical to the co.1=on defense and security or to tne health and safety of the public.
Dated: May 3, 1978 e
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKETSj[0S_. 50_26,9, 50-270 AND 50-287 DUKE POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendments Nos. 61, 61 and 58 to Facility Operating Licenses Nos.
DPR-38, DPR-47 and DPR-55, respectively, i; sued to Duke Power Company 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 Technical Specifications by eliminating reactor trip on loss of a single reactor coolant pump for Oconee Units Nos.2 and 3.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rule; and regulations.
The Commission has made appro-priate 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 7 w@0"'
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7590-01
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The Cem. mission has determined that the issuance of these amendmants will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) en environmental impact statement or negative 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 February 16, 1978, (2) Amendments Nos.
61 61,
and 58 to Licenses Nos. DPR-38, DPR-47 and DPR-55, respectively, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document Recm, 1717 H Street, N.W., Washington, D. C. and at the Oconee County Library, 201 South Spring Street, Walhalla, South Carolina.
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 3rd day of May 1978.
FOR THE NUCLEAR REGULATORY COMMISSION r)
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Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors 6
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