ML19319A600
| ML19319A600 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/07/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319A602 | List: |
| References | |
| NUDOCS 7908090686 | |
| Download: ML19319A600 (2) | |
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.s 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-346 THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear F.;gulatory Comission (the Comission) has issued Amendment No.16 to Facility Operating License No. NPF-3, issued j
to The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees), which revised Technical Specifications for operation of the Davis-Besse Nuclear Power Station, Unit No.1 (the facility) located in Ottawa County, Ohio. The amendment is effective as of its date of issuance.
The amendment changes the Technical Specifications concerning the Reactor Core Safety Limit Curve, the Reactor Protection System Instru-mentation Trio Setpoints and the maximum Reactor Coolant Hot Leg Temperature for departure from nucleate boiling margin. This amendment also makes minor editorial corrections to Technical Specifications Figure 2.1-2 and Table 5.7-1.
The application for the amendment complies with the standards and i
requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior 2
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public notice of this amendment was not requirld since the amendment does not involve a significant hazards consideration;.
j The Comission has detennined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CER 551.5(c)(4) an environmental impact statement or negative declaration and envi;onmental impact appraisal need not be prepared in connection with issuance of this amendment.
t For further details with respect to this action, see (1) the i
application for amendment dated October 23, 1978, (2) Amendment No.16 to License No. NPF-3, and (3) the Comission's related Safety i
Evaluation. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W.,
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Washington, D. C., and at the Ida Rupp Pe. oc Library, 310 Madison Street, Port Clinton, Ohio.
A copy of items (2) and (3) may be obtained upon request addressed i
to the U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attention: Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 7th day of June 1979.
FOP. THE NUCLEAR REGULATORY COMMISSION cY Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors e
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FEB o B 1979 Docket Number: 50-346 FEMORANDUH FOR: Robert W. Reid, Chief, Operating Reactor Branch 14, Division of Operating Reactors FROM:
Paul S. Check, Chief, Reactor Safety Branch, Division of Operating Reactors
SUBJECT:
TECHNICAL SPECIFICATION CHANGE REQUEST TO REFLECT THE AS-HEASURED RCP CHARACTERISTICS AND ITS EFFECT CN THE REACTOR CORE SAFETY LIMITS AND RPS TRIP SETPOINTS PLANT HAltE: Davis Besse - 1 DOCKET NUMBER: 50-346 RESPONSIBLE BRANCH & PROJECT MANAGER: OR3-4, G. Vissing REVIEW BRANCH: Reactor Safety REVIEW STATUS: Complete The Reactor Safety Branch has completed its review of the subject Technical Specification Change Request. The licensee requests changes in the Reactor Core Safety Limit (RCSL) curve and the Reactor Protection System Instrumentation. Trip Setpoints (RPSITS) to reflet the as-:neasurco one Reactor Coolant Pucip (RCP) coastcown curve which is steeper than the design one RCP coastdown curve presented in the FSAR. After re-viewing Reference 1*.:e concluded that the requested change is acceptable.
The licensee has stated that the as-measured RCP characteristics indicate a 14.5% excess flow and a steeper-than-design one RCP coastdown curve.
The RCP excess flow was partially used (by an earlier suomittal by the licensee) to offset the DNBR penalty due to Rod Bow effect, and partially used to compensate for the steeper coastdown curve in case of a Loss of Flow Accident (LCFA). In the spring of 1978, the licensee removed all BPRAs and a'il but two ORAs. One result of SPRA and ORA removal is a
- For clarification and follow up, two telephone conversations were held with the licenseee (Mr. Ray Sund) on 01/09/79 and 01/10/79.
790319043
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0 Robert W. Reid reduced coolant flow along the fuel rod assemblies, a situation wnicn could produce a DNB in case of a LCFA. In ttay,1978, B&W analysis showed that the excess flow provided adequate cooling in case of a LOFA. However, B&W discovered an error in their Hay,1978 analysis, and subsequently reanalysed the transient. This LOFA transient reanalysis has resulted in the proposed cnanges to the RCSL and RPSITS and their associated bases. The B&W reanalysis was performed using RADAR, an NRC-approved code for the loss of flow transient.
Since the requested changes preserve the DMB ratio margin for the loss of flow transient we find them acceptable.
Paul S. Check, Chief Reactor Safety Branch Division of Operating Reactors cc:
V. Stello Jr./D. Eisenhut R. Yellmer C. Berlinger F. Cof fman S. Weiss G. Vissing K. Kniel Section C, RS/DGR S. Diab c
Reference:
Letter from L. E. Roe, Toledo Edison Co. to the Director, Office of Nuclear Reactor Regulation, USNRC, November 23, 1976.
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