ML20087N247

Application for Amend to License NPF-3,changing Radiological Ets,Offsite Dose Calculation Manual & Process Control Manual

ML20087N247
Person / Time
Site:	Davis Besse
Issue date:	03/15/1984
From:	Murray T TOLEDO EDISON CO.
To:
Shared Package
ML20087N246	List: ML20087N245 ML20087N247 ML20087N252 ML20087N259 ML20087N263
References
NUDOCS 8404030263
Download: ML20087N247 (4)

Text

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APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NiiCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Unit 1 Facil'ity 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 MD Terry D. Murray ()

- Station Superintendent For R. P. Crouse Vice President, Nuclear Sworn and subscribed before me this 15th day of March, 1984.

/Nd Not'ary Publip/- State of Ohio My Commission Expires September 1, 1987 O'

PDR M P

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Docket No. 50-346

. Licenso Ns. 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 -

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SAFETY EVALUTION This amendment request incorporates all previous changes cade 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 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 in the previous revisions and to incorporate n'ev 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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-2 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 -^' Limiting Conditions for Operation and Surveillance Require-ments for itquid 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 inventory 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 an 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 remove the current Radiological Effluent Technical Specifications 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).

Dr.e of the examples (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-l '

- 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-l stricted areas as low as is reasonably achievable. To ensure compliance with this re'quirement, 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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