ML20087G518

Application to Amend License NPF-3,revising Tech Specs Re Radiological Plant Effluents,Offsite Dose Calculation Manual & Process Control Manual

ML20087G518
Person / Time
Site:	Davis Besse
Issue date:	03/15/1984
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20087G521	List: ML20087G518 ML20087G531 ML20087G557 ML20087G571
References
1035, NUDOCS 8403200046
Download: ML20087G518 (5)

Text

i I + TOLEDO

%me EDISON RcHAno P. CnouSE Docket No. 50-346 vo p,s,om w

License No. NPF-3 Serial No. 1035 March 15, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stoltz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Coumission Washington, D.C. 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 Oper-ating License NPF-3 for the Davis-Besse Nuclear Power Station Unit 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 are to the Radiological Effluent Technical Specifications (RETS), Revised Offsite Dose Calculation Manual, and Process Control Manual.

The attachment identifies the proposed change, its Safety Evaluation, and its significant hazard considerations for the RETS. This revised submittal of the RETS resulted from the NRC review of discussion between the staff and Toledo Edison. This request also includes all previous revisions providing one complete submittal of RETS.

This av.ndment request is a revision to a previous submittal. Therefore, no fee is incurred.

Very truly yours, R P C-/w RFC' GAB fg se c/1 g l

.cc: DB-1 NRC Resident Inspector State of Ohio

( THE TOLEDO EDISON TOMPANY EDISON PLAZA 300 MADISGN AVENUE . TOLEDO, OH10 43652 8403200046 840315 PDR ADOCK 05000346 P_ PDR

APPLICATION FOR AMENDMENT TO FACII.ITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit 1 Facility Operating License No. NPF-3, together with the Safety Evaluation for the requested change.

The proposed changes to the Radiological Effluent Technical Specifications.

Offsite Dose Calculation Manual, and Process Control Manual.

By /mb Terry D. MUrray j Station Superintendent For R. P. Crouse Vice President, Nuclear Sworn and st:bscribed before me this 15th day of March,1984, h @w Notary Publid - State of Ohio My Commission Expires September 1, 1987 l

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Dockst No. 50-346 License No. NPF-3 Serial No. 1035 March 15, 1984 Attachment I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications incorporating the Radiological Effluent Technical Specifications and deleting Appendix B.

A. Time required to implement. This change is to be effective 120 days after NRC approval.

B. Reason for change (Facility Change Request 79-114 Rev. D). To incorporate changes addressed in NRC Staff Review and all pre-vious revisions to the RETS. Also, the Revised Offsite Dose Calculation Manual and Process Control Manual.

C. Safety Evaluation (See Attached)

D. Significant Hazard Consideration -

(See Attached)

i SAFETY EVALUTION I This_ amendment request incorporates all previous changes made in the Radiological Effluent Technical Specifications (RETS) submitted by Toledo Edison.

The function of the RETS is to define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as reasonably l achievable. The concentration of radioactive materials in these effluents shall be within the limits specified in 10CFR20.

The changes proposed in this revision are to consolidate all changes made i

in the previous revisions and to' incorporate new changes made by the NRC in their draft 7 of NUREG-0472. The revision incorporated into this request resulted from a review of the NRC Staff and subsequent phone call between the NRC and Toledo Edison personnel.

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Significant Hazard Consideration The proposed amendment would revise the Technical Specifications applic-able to radiological plant effluents. The amendment was submitted by the licensee in response to the NRC request to propose new radiological effluent Technical Specifications which incorporate present NRC staff position to ensure compliance with 10 CFR 50.38a. The proposed amendment provides new Limiting Conditions for Operation and Surveillance Require-ments for liquid and gaseous effluent monitoring instrumentation require-ments, liquid and gaseous effluent release rates and gaseous effluent release rates and projected dose limits, operating requirements for the radioactive effluent treatment systems, temporary outside liquid storage inventery activity limits, and waste gas steam oxygen concentration limits. The proposed Technical Specifications also provide for require-ments to assure that all solid wastes meet applicable burial site require-ments and for radiological environmental monitoring that includes a monitoring program, a land use census, and cn interlaboratory comparison program. This amendment also would include bases that support the Limit-ing Conditions for Operation and Surveillance Requirements. Some changes would be made in administrative controls dealing with the Process Control Program and the Offsite Dose Calculation Manual. The proposed amendment would remrve the current Radiological Effluent Technical Specificaticus from the Appendix "B" Technical Specifications.

The Commission has provided guidance concerning the application of the standards in 10 CFR 50.92 by providing certain examples (48 FR 14870).

One of the enamples (ii) of actions not likely to involve a significant hazards consideration relates to changes that constitute additional restrictions or controls not presently included in the Technical Specifi-cations. Licensees are required by 10 CFR 50.36a to install, maintain, and operate the radioactive waste treatment systems in a manner that would keep releases of radioactive material during normal operation to unre-stricted areas as low as is reasonably achievable, To ensure compliance with this requirement, it is necessary to add additional restrictions and controls to the Technical Specifications as described above. The applica-tion does not involve a significant hazards consideration since the change constitutes additional restrictions and controls that are not currently included in the Technical Specifications in order to meet the Commission mandated release of "as' low as is reasonably achievable."

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