ML20205P912: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
| project =  
| project = TAC:55352, TAC:59932
| stage = Request
| stage = Request
}}
}}

Latest revision as of 18:48, 6 December 2021

Forwards Application for Amend to License NPF-3,revising Tech Spec Tables 3.3-1 & 4.3-1 in Response to Generic Ltrs 83-28 & 85-10 Re Silicon Controlled Rectifier Relays & Reactor Protection Sys Instrumentation
ML20205P912
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/27/1987
From: Shelton D
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20205P917 List:
References
1312, GL-83-28, GL-85-10, TAC-55352, TAC-59932, NUDOCS 8704030404
Download: ML20205P912 (2)


Text

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TOLEDO EDISON Docket No. 50-346 DONAU) C. SHB. TON ve. w-mo.or (419)249 2399 License No. NPF-3 Serial No. 1312 March 27, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Gentlemen:

Under separate cover, we are transmitting an application for an Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1.

This application requests that the Davis-Besse Nuclear Iower Station, Unit No. 1 Operating License, be revised to reflect the changes attached. The proposed changes involve Appendix A, Technical Specification Table 3.3-1 and Table 4.3-1.

These proposed changes are being submitted in response to the NRC's Safety Evaluation Report (Log No. 1683), which addressed Generic Letter 83-28, Item 4.3, Reactor Trip Breaker Automatic Shunt Trip, and Generic Letter 85-10 (Log No. 1756), Technical Specifications for Generic Letter 83-28, Items 4.3 and 4.4. Item 4.4 of Generic Letter 83-28 requires that the appropriate surveillance and test sections of the Technical Specifications be revised to include testing of the Silicon Controlled Rectifiers used to interrupt power to the control rods. The enclosed application requests that Silicon Controlled Rectifier (SCR) relays be added to the functional unit list for Table 3.3-1, Reactor Protection System Instrumentation, and to the functional unit list for Table 4.3-1, Reactor Protection System Instrumentation Surveillance Requirements.

This application also requests that the Technical Specifications be revised to explicitly note that testing independently confirms the oper-ability of the shunt and undervoltage devices.

Toledo Edison requests that this amendment request be approved and issued by the NRC by August 31, 1987 and effective 30 days after approval.

40 % $ $ 6 1 \Ob[

P THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652 u-________________._____.__________________.-----.___-.-

Docket No. 50-346 License No. NPF-3 Serial No. 1312 Page 2 This application supersedes our previous submittal-dated May 5, 1985 (Serial No. 1155) and, therefore, no license application fee per 10CFR170.12(c) is required.

Very truly yours,

/

DCS:DRW:JSL:plf Attachments cc: DB-1 NRC Resident Inspector A. B. Davis, Regional Administrator (2 copies)

State of Ohio A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager i