ML19331B896
| ML19331B896 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/06/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 634, NUDOCS 8008130499 | |
| Download: ML19331B896 (5) | |
Text
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TOLEDO h EDISON Aicsaac P. CacusE
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Docket No. 50-346 License No. NPF-3 Serial No. 634 August 6,1980 Director of Nuclear Reactor Regulation Attention:
Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 Division of Licensing United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Reid:
The Davis-Besse Nuclear Power Station, Unit 1 (DB-1) Operating License (NPF-3) contains several conditions that require completion prior to startup following the first regu.'arly scheduled refueling outage. A consolidation of the status of these conditions is provided in the attachment to this letter.
There are no delays in meeting these conditions beyond entering Mode 2 that have not been previously documented in formal license anendment requests.
As a result of discussions with your staff, it is expected that these conditions will be removed from the license concurrent with the issuance of the license amendment providing technical specifications necessary for Cycle 2 operation or prior to transition into Mode 2 operations.
Very truly yours, l/
W Aoo/
RPC/TJM b
Attachment
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be b/l THE TOLEDO EDISON COMPANY -
ED! SON PLAZA 300 MADISCN AVENUE TCLEDO, CHIO 43652 0008130 h
Docket No. 50-346 Attachment License No. NPF-3 Page 1 of 4 Serial No. 634 August 6, 1980 Status of License Conditions Requiring Completion Prior to Startup (Mode 2) for the Davis-Besse Nuclear Power Station, Unit 1 (Operating License No. NPF-3)
The following is a status of the license conditions for DB-1 requiring completion prior to transition into Mode 2 operations following the first regularly scheduled refueling outage currently in progress.
Condition 2.C. (3) (d)
Prior to startup following the first (1st) regularly scheduled refueling outage, Toledo Edison Company shall install a long-term means of protection against reactor coolant system overpressurization.
Status The final step in the implementation of this license condition is the modification i the DB-1 Technical Specifications.
Upon incorporation of the technical specifications issued July 25, 1980 and modifications of the setpoints, this license condition (as well as associated license condition 2.C.(3)(j)) has been satisfied.
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Docket No. 50-346 Attachment License No. NPF-3 Page 2 of 4 Serial.No. 634 August 6, 1980 Condition 2.C.(3)(e)
Prior to startup following the first (1st) regularly scheduled refueling outage, Toledo Edison Company shall modify the reactor coolant system flow indication to meet the single failure criterion with regard to pressure sensing lines to the flow differential pressure transmitters.
Status RCS flow indication modifications are being completed to provide redundancy as described in Toledo Edison's letter of July 21, 1980 (Serial No. 633).
This license condition should be deleted upon confirmation of completion by the NRC Resident Inspector.
Condition 2.C. (3)(f)
Prior to startup following the first (1st) regularly scheduled refueling outage, Toledo Edison Company shall modify the auxiliary feedwater system by providing diverse direct current power to one of the redundant auxiliary feedwater trains.
Status This modification to the auxiliary feedwater system valve operators as described in Section 9.2.7 of the DB-1 Final Safety Analysis Report is being completed. This license condition should be deleted upon confirma-tion of :ompletion by the NRC Resident Inspector.
Condition 2.C.(3)(g)
Prior to startup following the first (1st) regularly scheduled refueling outage, Toledo Edison Company shall modify the emergency core cooling system by providing motor operated valves with control and position indication in the control room in lieu of the manually operated valves in each of the two crossover connection lines installed between the high pressure makeup pump suction and the low presstre injection discharge.
Status This modification to the DB-1 emergency core cooltag system is being completed. This condition should be deleted upon confirmation of comple-tion by the NRC Resident Inspector.
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Docket No. 50-346 Attachment License.No. NPF-3 Page 3 of 4 Serial No. 634 August 6, 1980 t
Condition 2.C. (3)(h) - partial Prior to startup following the fir:t (1st) regularly scheduled refueling outage, Toledo Edison Company shall implement Section B of Appendix A,
" Administrative Procedures, Controls and Fire Brigade," and Section C of Appendix A, " Quality Assurance Program."
Status Sections B and C of Appendix A to Standard Review Plan 9.5.1 (Revision
- 2) " Fire Protection System" have been implemented at DB-1.
This part of condition 2.C. (3)(h) should be deleted.
Condition 2.C.(3)(n)
Previously deleted by License Amendment No. 10, dated May 26, 1978.
Condition 2.C. (3)(p) l Prior to startup following the first- (1st) regularly scheduled refueling outage, Toledo Edison Company shall have submitted an analysis of design modification alternatives to the present key lock control in the manual bypass valves DH21 and DH23 around the decay heat removal suction line isolation valves, that will decrease the likelihood of the bypass path being opened inadvertently during periods when isolation of the decay 9
heat removal loop is required; and subsequently have completed the installation'of the approved design modifications.
Status On January-11,'1979, an analysis was submitted justifying the key control scheme for bypass valves DH21 and DH23. A unique key is issued for the
-valve control locks. This license condition should be deleted.
Condition 2.C.(3)(r)
Toledo Edison Company shall submit a seismic reanalysis and evaluation to the Commission for its review and approval in sufficient time to-obtain Commission approval of-the adequacy of the plant systems needed
_, r complish safe shutdown of the reactor and continued shutdown heat i
removal prior to startup following the first (1st) regularly scheduled refueling outage. In performing the reanalysis a safe shutdown earthquake
- acceleration of 0.20g shall be applied at the foundation level of the plant and the' response spectra shall be used'as specified in Regulatory Guide 1.60,'" Design Response Spectra for Seismic Design of Nuclear Power Plants. ~ The seismic reanalysis and evaluation shall be conducted in
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accordance with guidelines to be specified by the Commission.
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Docket No. 50-346 Attachment License No. NPF-3 4 of 4 Serial No.'634 August 6,'1980 Status The' seismic reevaluation analysis was provided on July 9, 1979 (Serial No. 525) and later supplemented on May 16 and July 9, 1980 (Serial Nos.
614 and 630).
This analysis illustrated the adequacy of plant systems to accomplish safe reactor shutdown and continued shutdown heat removal. This license condition should be deleted.
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