ML19256G564
| ML19256G564 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/22/1979 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912310463 | |
| Download: ML19256G564 (5) | |
Text
,1 TOLEDO Docket No. 50-346
-b EDISON License No. NPF-3 Serial No. 567 Acs:.AD P. CAousE ve smcent December 22, 1979 uw M19,259-5221 Director of Nuclear Reactor Regulation Attention:
Mr. Robert N. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors Uaited States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Reid:
Under separate cover we are transmitting three (3) original and forty (40) copies of an application for amendment to the Facility Operating License No. NPF-3 for Davis-Besse Nuclear Power Station, Unit No. 1.
This application requests a revision to License Condition 2.C(3)h that would delay the completion schedule of fire protection modifications until September 30, 1980.
This amendment request involves a Class III change.
Enclosed is $4,000.00 as required by 10CFR170.
Attachment A identifies the proposed change and its safety evaluation.
Attachment B identifies additional design modifications necessitated by detailed engineering.
A su= mary schedule is also included.
Very truly yours, Sf W RPC/TJM cc:
Dan Garner Operating Reactors Branch No. 4-Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C. 20555 1658 120 THE TOLEDO EDISON COMPANY ED! SON PLAZA 300 MADISON AVENUE TOLEDO, OH:0 43552 1912310kb3
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b APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested change to the Davis-Besse Nuclear Power Station Unit No. 1, Facility Operating License No. NPF-3, condition 2.C(3)h concerning fire protection system modifications.
By em Vice President, Nuclear Sworn to and subscribed before me this twenty-second day of December, 1979.
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Notary Public LINDA L. COSTELL' Notary PubEc - Ste c of cN, My Ccmm:ssion Expires Fet. 9.10
1658 121
Docket No. 50-346 License No. NPF-3 Serial No. 567 December 22, 1979 Attachment A Change to Davis-Besse Nuclear Power Station Unit No. 1 License Condition 2.C(3)h 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 79-442)
This change is requested to alter the currently required April 22, 1980 completion date.
This would provide relief from currently projectad craft manpower support throughout the planned spring outage.
C.
Safety Evaluation The ef fective delay of approximately five months in the implementation of fire protection modifications provides no unreviewed safety question.
Critical areas of the fire protection upgrade were separated from the overall implementation schedule, as outlined in Table 1 of the NRC Staff's Safety Evaluation Report items Al, A2 and A3 and assigned earlier completion dates for safety concerns.
1658 122
Docket No. 50-346 License No. NPF-3 Serial No. 567 December 22, 1979 ATTACHMENT B FIRE PROTECTION MODIFICATIONS of c
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't.1 CLEAR POWER STATION UNIT 1 A. Design Modification Items 1.
Revision 5 of the DB-1 Fire Hazards Analysis Report identified the selection of automatic sprinkler protection for portions of the turbine building instead of a passive type fire-proofing.
This is the design which we are installing.
It is noted that Revision 5 is not reflected in the "NRC Staff Safety Evaluation Report" Table 1, item 9.
2.
Storage Room 405, mechanical and electrical penetration rooms are being provided with automatic sprinkler protection in lieu of passive fire proofing due to access and layout difficulties.
B. Schedule 1.
Service water pump and valve room fire protection system modifications are scheduled to be completed December 31, 1979.
2.
All fire protection system modifications will be completed by September 30, 1980 with the exception of the service water system backup system being independent of offsite power by mid-1984.
The new sprinkler system modifi-cations are being installed such that portions of these will be placed La service as available prior to September 30, 19 80.
i658 123
(e)
Prior to startup following the first (1st) regularly scheduled refueling outage, Toledo Edison Ccrpany 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.
(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.
(g) Prior to startup following the first (1st) regularly sches aled refueling outage, Toledo Edison Oct.rany snail modify the emergency core cooling system by provicing 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 1ines installed between the high pressure makeup pr.p suction and the Icw pressure injection disenarge.
277 Seple Lu 30,i980, (h)
Wi_hin thre (Z j:r: c f th d=
o f-issrc.u--ef-tes 1i::n:: except as noted below, Toledo Edisen Company shall increase the 3evel of fire protection in the facility to the levels reco= ended in Appendix A to the Standard' Review Plan 9.5.1, Revision 2, " Fire Protection System," or with alternatives acceptable to the Co=ission.
Prior to startup following the first (1st) regularly scheduled refueling ourage, Toledo Edison C :pany shall i;rplement Section 3 of Appendix A, "Adninistrative Procedures, Controls and Fir e Brigade," and Section C of Appendix A, " Quality Assurance Program."
(i)
If the anbcock & Wilcox prooosed rod bow model has not been approved by the Cc=ission upon completicn of one hundred (100) effective full power days of cgeration for the facility, the Toledo Edison Ccepany must re;ise the plant technical specifi:ations to reflect the rod bow model used by the Co=ission for Babcock & Wilcox plants which requires the following D?GR penalties as a function of burnup:
Burnup- ( K.0/t.TJ)
D:GR Penaltv 0-5,651 5.9 percent 5,653-15,000 8.2 percent 15,000-24,000 9.8 percent 24,000-33,000 11.2 percent 10RORMAL 1658 124 t