ML19305A796
| ML19305A796 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/04/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19305A794 | List: |
| References | |
| NUDOCS 8003180364 | |
| Download: ML19305A796 (3) | |
Text
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Docket No. 50-346 Lfcense No. NPF-3
' Serial No. 595 March 4, 1980 I.
Change to Davis-Besse Nuclear Power Station Unit No. 1 License Condition 1.C. (3)(r) - see proposed change attached.
A.
Time Required to Implement This change is to be effective upon NRC approval.
B.
Reason for Change (Facility Change Request 80-004)
License Condition 2.C. (3)(r) requires a seismic re-analysis and evaluation submitted to the Commission for its review and approval. This change would modify the submittal date and deliniate the Toledo Edison's responsibility only for its submittal.
C.
Safety Evaluation This operating License Amendment modifies the required submittal of the Davis-Besse Nuclear Power Station Unit No. 1 Seismic Reevaluation from the startup following the first refueling outage to December 1, 1980.
Assuming a startup date af ter the first refueling outage as July 1, ic80, this extends the current date by approximately 5 months.
Only July 9,1979 Toledo Edison submitted a reevaluation for a safe shutdown earthquake having an acceleration of 0.20g.
In this reevaluation appropriate ductwork and piping systems were found to have acceptable margin to accomo-date the change from 0.15 to 0.20g.
The appropriate equipment information examined by Toledo Edison and its consultants to date identified the existence of acceptable design margin to accomodate the increased ground acceleration.
Based on the short time period associated with the delay and the results to date indicating generally acceptable design margins, it is considered acceptable to request such a modification without adversely affecting the health and safety of the public.
This is not, therefore, an unreviewed safety question.
300S1
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e Docket No. 50-346 I'7 ~
Serial No. 595 J
License No. NPF-3
.y.
(p)
Prior to startup following ;the rirst (1st) regularly scheduled refueling ourage, Toledo Edison Cor:pany shall have submitted an analysis of design m:dification alter-natives to the present-key lock control in the manual bypass valves CH21 and DH23 arcund the decay heat re. oval suction line isolation valves, that will decrea::e the likelihood of the bypass path being opene inadvertently during periods when isolation of the decay heat removal loop is required; and subsecuently have completed the installation of the approved design codificaticas.
(q)
Within four (4) months frca the issuance of this 1icense, Toledo Edison Company shall subait an evaluation and proposed modifications, if reqeired, so that the hg facility design will assure adequate breaker cocedination and isolation of its ensite system in sufficient time to permit the required Class IE egaignent to cperate in the D
9 event of offsite grid degradation.
Prior to the Cc=ission k
approval of the modification, Toledo Edison Cc :cany snall maintain the normal operating range for the grid system 9
voltage between 98.3 percent to 102.3 percent of rated voltage (with corresp::nding safety-related bus voltage as defined in Attachment 1 of Toledo Edison Company's letter to the Co=nission dated Novem::er 13, 1976).
In the event the system conditions exceed these values, Toledo Edison Company shall proceed in an orderly manner to reduce load to 5 percent of rated power and take cor-rective action to stabilize the system to within the values stated above prior to return to higher pcoer levels.
no ia+ce
,% hauba 1,8%o (r) Toledo Edison Company shall submit,.a seismic rer.nalysis and evaluation to the Comission for its review and approval Lwuf+ielent-t4meto-obtun Codedoe-rep: oves of the l
adequacy of the plant sysrems needed to accomplish safe shutdown of the reactor and continued shutdown heat re::csal, pr-ior--to.hr ' rep--foRowse.q-L&e-f4r-st-( st '-res.h f
-ccheduled-.refw4-ing-outage, In performing the reanalysia a safe shutdown earthquake acceleration of 0.2Cg chall br applied at the foundation level of the plant and the response spectra shall be used as specified in regulatory Gaide 1.60, " Design Fesponse Spectra for seismic Design of Nuc'. ear power Plants." The seismic reanalysis and evaluation snall be conducted in accordance with guidelines to be specified by the Commission.
(s) Toledo Edison Company shall be exempted from the require-ments of Technical Specification 3/4.7.8.1 for the two (2) Ncericium-Seryllium-Copper startup sources to be installed or already installed for use during the first refueling cycle until such time as the sources are replaced.
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