ML20245A225

From kanterella
Revision as of 13:37, 22 January 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Application for Amend to License NPF-3,clarifying That DHR Valve DH23 Not Subj to Type C Test Requirements. Type C Testing of Valve Not Required Since Valve Does Not Meet App J Criteria
ML20245A225
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/13/1989
From: Shelton D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245A227 List:
References
1667, TAC-73244, NUDOCS 8906210160
Download: ML20245A225 (1)


Text

,

. . .j

. i i

TOLEDO j Docket Number 50-346 EDISON l License Number NPF-3 Serial Number 1667 DONALD C. SHELTON va pres.nent_No.,

[419] P49-2300 June 13, 1989 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ect: License Amendment Application to Clarify That Decay Heat Removal Valve DH23 Is Not Subject to Type C Test Requirements (TAC Number 73244) i Gentlemen:

The enclosed application requests that the Davis-Besse Nuclear Power Station, Unit Number 1 Operating License, Appendix A, Technical Specifications-be revised to reflect the change attached. The proposed change' involves Section 3/4.6.3.1, Containment Isolation Valves, Table 3.6-2. This request proposes  ;

to apply an existing Table 3.6-2 footnote to decay heat removal valve DH23 which will clarify that the valve is not subject to 10CFR50, Appendix J, Type C testing. . Valve DH23 is a normally locked closed, manually operated 3 containment isolation valve, located inside the containment vessel in series j vith valve DH21 (also normally closed) in the bypass line around valves DH11 J and DH12, decay heat pump suction isolation valves. Type C testing of valve  !

DH23 is not required since the valve does not meet the Appendix J criteria -

i which requires Type C testing.

Toledo Edison requests that this revision be completed prior to commencement of the sixth refueling outage and the associated Type C testing. Therefore, 1 Toledo Edison requests that this amendment be issued by the NRC by December 15, 1989, for implementation within the following 4h days. Should you have any questions or require additional information, please contact Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-2366.

Very truly yours, Ch GBK/dlm Attachment l cc: P. H. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III T. V. Vambach, DB-1 NRC Senior Project Manager 0( .

State of Ohio / i THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 I%

8906210160 890613 -

PDR ADOCK 05000346 I P PDC '