ML19270H124
| ML19270H124 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/21/1979 |
| From: | Jeffery Grant TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1-71, IEB-79-05A, IEB-79-05B, IEB-79-5A, IEB-79-5B, NUDOCS 7906230037 | |
| Download: ML19270H124 (4) | |
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TOLEDO
%me EDISON JAMES S. GRANT May 21, 1979 sY.*,s'$l Dockct No. 50-346 Licensa No. NPF-3 Serial !!o. 1-71 Mr. James G. Keppler Regional Director, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
IE Bulletin 79-05B requested that we review certain items at Davis-Besse. Nuclear Power Station Unit I related to the March 28, 1979 incident at Three Mile Island Unit 2.
Enclosed are responses to items 5 and 7 of this bulletin.
This submittal, in conjunction with Toledo Edison letters of May 4, 15 and 18 (Scrial Nos.1-65; l-67; and 1-68 respectively) complete the Davis-Besse Unit I response to this Bulletin.
Yours very truly, JSG:TJM 2247 216 Enclosure cc:
U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspections Washington, D. C. 20555 2 4 1979 THE TCLEDO EDl SON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 7906230637'
Docket No. 50-346 License No. NPF-3 Serial No. 1-71 May 21, 1979 Item 5 Provide for NRC approval a design review and schedule for implementation of a safety grade automatic anticipatory reactor scram for loss of feedwater, turbine trip, or significant reduction in steam generator level.
Response
Attached are three (3) copies of e.he proposed final anticipatory reactor trip system design (Drawings No. SK-E 410, Revision 0 and E-18, Revision 11) for the Davis-Besse Nuclear Power Station Unit 1 (DB-1) for your review. This system design criteria identifies the extent to which the design is safety grade.
The schedule for implementation is dependent upon the NRC's review.
It would be installed during the first major outage occurring twelve months af ter indicated acceptability by the NRC.
In the interim the additional reactor trip system described in Toledo Edison's letter to Mr. Robert Reid, NRR, dated May ll, 1979 (Serial No.501 ) will provide additional automated reactor trip functions for loss of feedwater and turbine generator trip.
2247 217 5-1
-a Docket No. 50-346 License No. NPF-3 3
Serial No. 1-71 May 21, 1979 Item 7 Propose changes, as required,to those technical specifications which must be modified as a result of your implementing the above items.
Response
Implementation of the items of IE Bulletin 79-05B /s not in any way require operation of the Davis-Besse Nuclear Power Station Unit 1 (DT;-1) outside the technical specifications currently in affect. However to insure consistency of documentation ot reactor protection system trip setpoints, Toledo Edison is preparing an operating license amendment request to NRR to alter Item 6 of Table 2.2-1 of Appendix A to Facility Operating License NPF-3.
A copy of the proposed page change is attached.
2247 218 7-1
E t
TABLE 2.2-1 5
REACTOR PROTECTI0ff SYSTEM IflSTRUf!EllTATIOf1 TRIP SETPOIllTS FUtiCTIO!1AL UtlIT
' TRIP SETP0IllT ALLOWABLE VALUES y
1.
ilot Applicable flot Applicable E
< 105.5% of RATED TilERMAL POWER
< 105.6% of RATED TilERMAL POUER q
2.
High Flux With four pumps operating sith four pumps operating #
m
< 80.7% of RATED TilERMAL POWER
< 80.8% of RATED TilERMAL P0i!ER Eith three pumps operating Eith three pumps operating #
< 53.0% of RATED TilERMAL POWER with
< 53.1% of RATED TilERMAL POWER with 5ne pump operating in each loop one pump operating in each loopt 3.
RC High Temperature
< 619'F
< 619.08"F Allowable Values not to exceed Flux - A Flux-flow (1)
Trip Setpoint not to the limit line of Figure 2.2-2.j 4.
exceed the limit line of Figure 2.2-1.
N' 5.
RC Low Pressure
> 1985 psig
> 1984.0 psig*
> 1976.5 psig**
II) d
_64Soo 3 sic ia3ot.o g*
da30s.5psip **
- 235G-p4 =3 6.
RC liigh Pressure 1 2355.0
....y 1 2353.5 p.g y
N 7.
RC Pressure-Temperature
> (16.25 T F - 7873) psig
>(16.25T F - 7873.64) psig#
II) ou,t out k
3 CD a
F
.