ML20087M662

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Forwards Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in post-accident Sampling Sys & post-accident Instrumentation for in-core Thermocouple,Per NUREG-0737 & Generic Ltr 83-37
ML20087M662
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/22/1984
From: Crouse R
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20087M663 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.E.1.1, TASK-2.F.1, TASK-2.F.2, TASK-3.D.3.4, TASK-TM 1032, GL-83-37, TAC-54388, TAC-54528, NUDOCS 8403300149
Download: ML20087M662 (3)


Text

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%s EDISON RcsAno P. CAOUSE V(e Prevoent 4xwe Docket No. 50-346 uisas+ san License No. NPF-3 Serial No. 1032 March 22, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Stolz:

Under separate cover, we are transmitting three (3) original and forty (40) conformed copies of an application for 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 Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes involve:

1. Section 6.84 and,
2. Tables 3.3-10 and 4.3-10 The attachments identify the proposed changes and its safety evaluation and significant hazard consideration. Item 1 concerns establishment of administrative controls of the Post-Accident Sampling System for training of personnel, procedures and equipment maintenance. Item 2 concerns Post-Accident Instrumentation for In-Core Thermocouple and Reactor Coolant Hot Leg Level (wide range).

The NRC issued Generic Letters 83-37 (GL 83-37) on November 11, 1983 (Log No. 1402) requesting Technical Specification on NUREG 0737 items contained in Enclosure 1. Toledo Edison has reviewed the letter and the attached amendment requests are being submitted for items not covered by present Technical Specifications or previous amendment request. Listed below is each item contained in Enclosure 1 of GL83-37 and the status of the requested items.

1. Reactor Coolant System Vents (II.B.1)

Reactor Coolant System Vent (High Point Vent) Amendment request was  !

submitted on May 5, 1982 (Serial No. 803). El THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 EklO33OO149 SUND322 l PDR ADOCK 05000346 P PER j

2. Post-Accident Sampling (II.B.3)

Post-Accident Sampling Amendment request is contained in Attachment 1 of this letter.

3. Long Term Auxiliary Feedwater System Evaluation (II.E.1.1)

Long Term Auxiliary Feedwater System Evaluation (II.E.1.1) is being addressed as a separate item in response to Mr. J. F. Stolz letter of February 21, 1984 (Log No. 1455) concerning the same item.

4. Noble Gas Effluent Monitors (II.F.1.1)

The Noble Gas Effluent Monitors (II.F.1.1) has been submitted with the Radiological Effluen.t Technical Specifications (RETS) submittal.

5. Sampling and Analysis of Plant Effluents (II.F.1.2)

Sampling and Analysis of Plant Effluents has been submitted with the RETS Submittal.

6. Containment High-Raage Radiation Monitor (II.F.1.3)

Containment High-Range Radiation Monitor is encompassed in our present Technical Specifications see Section 3.3.3.6.

7. Containment Pressure Monitor (II.F.1.4)

Containment Pressure Monitor Amendment request was submitted on May 5, 1982 (Serial No. 803).

8. Containment Water Level Monitor (II.F.1.5)

Containment Water Level Monitor amendment request was submitted on May 5, 1982 (Serial No. 803).

9. Containment Hydrogen Monitor (II.F.1.6)

Containment Hydrogen Monitor is encompassed in our present Technical Specifications, see Section 3.6.4.1.

10. Instrumentation for Detection of Inadequate Core Cooling (II.F.2)

Instrumentation for Detection of Inadequate Core Cooling is contained in Attachment 2 of this letter for In-Core Thermocouples and Reactor Coolant Hot Leg Level (Wide Range). Subcooling margin monitor is encomposed in our present Technical Specification (see Tables 3.3-10 and 4.3-10).

11. Control Room Habitability Requirements (III.D.3.4)

Control Room Habitability Requirements are encompassed in our present Technical Specifications (see Section 3.7.6.1).

This amendment request involves two changes of Class II type. Enclosed is a check for $2,400 as requested by 10 CFR 170.22. ,

Very truly yours, Yf = = = - -

RPC: GAB Attachment cc: DB-1 NRC Resident Inspector State of Ohio