ML19310G647

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Forwards Notice of Consideration of Issuance of Amend to License NPF-3 to Provide Auxiliary Feedwater Operability W/O Regard to Status of Startup Feedwater Pump Until Entering Mode 1 for Cycle 5
ML19310G647
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/06/1984
From: De Agazio A
Office of Nuclear Reactor Regulation
To: Crouse R
TOLEDO EDISON CO.
Shared Package
ML19284D497 List:
References
TAC-56390, NUDOCS 8501020521
Download: ML19310G647 (6)


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UNITED STATES

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,E NUCLEdR oEGULATORY COMMISSION

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Decamber 6,198\\

DOCKET NO(S). 50-346 Mr. Richard P. Crouse

.Vice President, Nuclear Toledo Edison Company Edison Plaza - Stop 712 300 Madison Avenue l

Tol edo Ohio 43552 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 l

' The following documents corcerning our review of the subject facility are transmitted i 3r your information.

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O Notice of Receipt of Application, dated O Draft / Final Environmental Statment, dated O Notice of Availability of Draft / Final Environmental Statement, dated O Safety Evaluatiori Report, or Supplement No.

, dated j

O Notice of Hearing on Application for Conttruction Permit, dated l

O Notice of Consideration of issuance of Facility Operating License, dated O Monthly Notice; Applications and Amendments to Operating Licenses involving no Significant Hazards Considerations, dated O Application ar.d 5.! sty Analysis Report, Volume O Ameadment No.

to Application /SAR dated _

O Construction Permit No. CPPR-

.. Amendment No.___

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O Facility Operating License No.

, Amendment No.

, dated O Order Extending Construction Completion Date, dated Q Other(Specify/Public Notice of consideration of issuance

  1. Amendment to Facility Operating License concerning amendment application dated December 3,1984, to provide for determinino AFW operability without reaard to status of SOFP until entering mode 1 for j

Cycle 5.

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ation ice of u Albert W. De Agazio, r ject Manager

Enclosures:

Operating Reactors Branch #4 As stated Division of Licensing cc: w/ enclosure:

See next page q$h I

e Toledo Edison Company cc w/ enclosure (s):

Mr. Donald H..Hauser, Esq.

U.S. Nuclear Regulatory Comirsion The Cleveland Electric Resident inspector's Office Illuminating Company 5503 N. State Route 2 P. O. Box 5000 Oak Harbor, Ohio 43449 Cleveland, Ohio 44101 Gerald Charnoff Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D. C.

20036 Paul M. Smart, Esq.

Fuller & Henry 300 thdison Avenue P. O. Box 2088-Recional Radiation Representative Toledo, Ohio 43603 EP Region V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock & Wilcox Nuclear Power Generation Division 1910 Wooduont Avenue, Suite 220 Bethesda, ilaryland 20814 Ohio Department of Health ATTH: Radiological Health Pre 'm Director P. O. Box lib President, Board of County Columbus, Ohio 43216 Comissioners of Ottawa County Port Clinton, Ohio 43452 -

Attorney General JamesW. Harris, Director (AddresseeOnly) s e

Division of Power Generation Colur.hus' Ohio 43215 Ohio Department of Industrial Relations 2323 West 5th Avenue Harold K,hn, Staff Scientist P. O. Box S25 Power Siting Comissitn 361 East Brcsd Street Columbus, Ohio 43216 Columbus, Ohio 43216 Mr. James 6. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Robert F. Peters Manager, Nuclear Licensing Toledo' Edison Company Fdison Plaza 300 Madison Avenue v.i -.

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PUBLIC NOTICE 1

NRC Staff Preposes to Amend Operating License ~for Davis-Besse Nuclear Power Station, Unit No.1 1

The Nuclear Rr ginatory Comm',ssion staff has received an application e

dated December 3,1984, from the Toledo Edison Company (the licensee) for an.

f amendment to the operating license for the Davis-Besse Nuclear Power Station, i

Unit No.1, located in.0ttawa County, Ohio.

If approved, the amendment would eliminate consideration of the status

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of the startup #eedwater system from the determination cf the operability of j

the auxiliary feedwater system for a-limited period only. This period would extend from the date of issuance of the amendment until the time the station i

makes the transition into operational mode 1, that is, enters power range 1

operations. Operating at full power is the subject of a Notice published in j

the Federal Reoister on September 28, 1984 (49 FR 38412).

The licensee has requested NRC action on its request as soon as possible.

l Following an initial review of this application, the NRC staff has made a proposed (preliminary) determination that the requested amendment involves no significant hazards consideration. Under NRC regulations, this means that the proposed amendment does not involve a significant increase in the J

probability or consequences of an accident, would not create the possibility of a new or different kind of accident from any accident previously

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evaluated, or involve a significant reduction in a safety margin.

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Ths application of these criteria for the prelininary determination that f

the proposed amendment involves no significant ha-.ds consideration is as

i follows:

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No Sionifi nnt Increase in the Probability or Consecuences of an Accident Prev'ously Analyzed The operation of the startup feedwater system, portions of which are l

located in aren where rniliary feedwater system components are located, i

pmsents a risk to the auxiliary feedwater system. This risk would be due to the effects of pipe whip, high temperature, or flooding if a portion of the startup feedwater system were to rupture. The estimated

. probability of such a rupture occurring has been compared to the estimated probability of auxiliary feedwater failure from all other causes. This e

I comparison shows the expected increase in the probability of auxiliary feedwater failure is not significant. The consequences of auxiliary feedwater system failures would be less due to the period of time that the plant has been shutdown for refueling (about 95 days) resrlting in inw decay heat combined with the fact that the plant will not enter Operating Mode 1 under this amendment.

2.

Nn Creation of a New or Different Kind of Ace' dent Than Previously Analyzed Any loss of auxiliary feedwater due to a failure of the startup feedwater system prior to cycle 5 mode 1 operation would not be a new or different 1

accident than previously analyzed due to the period of time that the

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l plant has been shutdown for refueling (about 95 days) resulting in low i

decay heat.

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No Significant Reduction in a Safety Margin The startup feedwater system pump suction and discharge piping is not designed to safe shutdown earthquake requirements nor is the startup pump cooling water piping. An amendment allowing operation of the i

present startup feedwater system involves a reduction in the safety margin that otherwise would be provided against a seismic event.

l However, the licensee has committed to station operating personnel in the startup feedwater pump-auxiliary feedwater pump room to take >.ction to isolate the startup feedwater system in the event leaks or piping failure, occur which could,ieopardize the auxiliary feedwater function.

Therefore, the associated reduction in margin is at least partially compensated for and is not considered significant.

Therefore, based on these considerations and.the three criteria given above, the NRC staff has made a proposed determination that the amendment request involves no significant hazards consideration.

The NRC has determined that due to exigent circumstances, there is no time to publish, for public comment before issuance, its usual notice in the Federal Register of the proposed action. The exigent circumstances result from the licensee's late recognition that a Technical Specification change was necessary in order to 01tain approval for use of the startup feedwater system. While the plant could be started up and operated at low power without this change, initial startup from a refueling octage without this change is undesirable because it could extend or prevent performance of required zero-power core physics testing and could result in unnecessary challenges to the plant safety systems.

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If the proposed determination becomes final, the NRC staff will issue the amendment without first offering an opportunity for a public hearing.

An opportunity for a hearing will be published in the Federal Register at a later date and any hearing request will not delay the effective date of the amendment.

If tne NRC decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Register and, if a hearing is granted, it will be held before the amendment is issued.

Comments on the proposed determination may be teleohoned to John F.

Stolz, Chief of Operating Reactors-Branch No. 4, by collect call to (301) 492-8960. All comments received by December 19, 1984, will be considered in reaching a final determination. A copy of the application may be examined at the NRC's local public document room located at the University of Toledo Library, Documents Department, 2801 Bancroft Avenue, Toledo, Ohio 43606.

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