ML20003A916
| ML20003A916 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/30/1981 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20003A917 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-2.K.2.13, TASK-2.K.2.14, TASK-2.K.3, TASK-2.K.3.02, TASK-2.K.3.07, TASK-2.K.3.30, TASK-TM 685, TAC-44841, TAC-45198, TAC-45205, NUDOCS 8102100057 | |
| Download: ML20003A916 (3) | |
Text
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TOLEDO Docket No. 50-346 EDISON Ac,a: A Cass License No. NPF-3 ...c.,,
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- '3j2' d?%- "i Serial No. 685 January 30, 1981 Director.of Nuclear Reactor Regulation Attn: Mr. Darrell G. Eisenhut, Director Division of Licensing - .
Nuclear Regulatory Commission C -
Washington, D.C. 20555 ' ' :
Dear Mr. Eisenhut:
On October 31, 1980, Clarification of TMI Action Plan Requirements (NUREG 0737), was issued. The document identifies a compilation of the recommendations to be completed on commercial facilities that resulted from the accident of March 28, 1979 at the Three Mile Island, Unit 2 facilities. On December 30, 1980 (Serial No. 670) Toledo Edison ident-ified its current plans for these recommendations for the Davis-Besse Nuclear Power Station Unit 1 (DB-1). This is a follow-up letter to provide documentatica related to three items on the list. These include:
II.E.4.2.5 Cont Isolation Dependability Contautent Pressure Setpoint The following information is provided to evaluate the appropriateness of the current DB-1 safety features actuation system (SFAS) containment pressure trip setpoint of < 18.4 psia (Technical Specification 3.3.2.1).
For consistency, note that_this value is given in absolute pressure.
Technical Specification 3.6.1.4 identifies primary containment internal pressure will be maintained between +25" and -14" W.G. (+0.8 and -0.5 psid) from the shield building. This shield building will be at atmospheric pressure. Historically the maximum atmospheric pressure observed in Toledo, Ohio is 31.04" Hg (15.24 psia). Thus, the highest expected containment pressure is 16.04 psia. A reasonable margin is 1 psi. This gives an analyzed setpoint of 17.04 psia. Containment pressure transmitter accuracy is + 0.5% (+ 0.3 psi) and drift is + 0.05%.
Safety Feature Action System (SFAS) accuracy is + 1.5% (+ 0.9 psi) and drift is + 0.2% (+ 0.12 psi).
These accuracies and drifts would result in the following. j O
Minimum Setpoint 18.24 psia g Minimum Allowable Value 18.39 psia
//
THE TOLEDO EDISON COMPANY EDISCN PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 f 81021000g7
Dockst No. 50-346 License No. NPF-3 Serial No. 685 January 30, 1981 These compared extremely close to the current values of Technical Specific-ations:
Trip Setpoint f 18.4 psia Allowable Value 3 18.52 psia Therefore, no change is c7nsidered necessary. No further submittals are planned on NUREG 0737 item II.E.4.2.
II.K.2.13 Thermal Mechanical Report Attachment A is Babcock,and Wilcox Topical Report BAW 1628, Reactor Vessel Brittle Fracture Analysis During Small Break LOCA Events with Extended Loss of Feedwater dated December 1980. No further submittals are planned for NUREG 0737 item II.K.2.13.
II.K.3.2 Report on PORV Failure II.K.3.7 Evaluation of PORV Opening Probability Attachment B is Report on Power-Operated Relief Valve Opening Probability and Justification for Present System Setpoints. No further submittals are planned for these NUREG 0737 items.
Very truly yours,
- 12-RPC/TJM: lab attachments (2) cc: NRC Davis-Besse Resident Inspector Y
9 4
Docket No. 50-346 License No. NPF-3 Serial No. 685 January 30, 1981 Copies to: C. R. Domeck C. T. Daft W. A. Johnson /J. G. Evans T. D. Murray W. C. Rowles i J. H. Shortt R. G. Schuerger R. E. Lapp W.*E. Nyer C. M. Rice P. M. Smart, Esq.
G. Charnof f, Esq.
D. H. Hauser, Esq.
T. J. Myers R. C. Luken R. Rosenthal J. W. Fay. .
D. G. Mardis T. J. Sullivan R. Gill E. C.- Simpson
, R. F. Wilson '
J. F. Fritzen S. Anderson i
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