ML20024C211

Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization

ML20024C211
Person / Time
Site:	Davis Besse
Issue date:	07/08/1983
From:	Crouse R, Murray T TOLEDO EDISON CO.
To:
Shared Package
ML20024C209	List: ML20024C208 ML20024C211 ML20024C213
References
TAC-43333, NUDOCS 8307120413
Download: ML20024C211 (3)

Text

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APPLICATION FOR AMENDMENT TO

, FACILITY 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 No. 1 Facility Operating License No. NPF-3, together with the Safety Evaluation for the requested change.

• The proposed changes include Sections 6.5.1.2, 6.5.2.2, Figure 6.2-1, and Figure 6.2-2.

By /s/ T. D. Miirrny Station Superintendent For n. p. croir ,

Vice President, Nuclear Sworn and subscribed before me this,8th day of July, 1983.

/s/ Nora Lynn Flood Notary Public, State of Ohio ,

My coma:ission expires September 1,1987 SEAL -

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8307120413 830708 PDR ADOCK 05000346 P PDR

I' Docket No. 50-346 License No. NPF-3 Serial No. 966 July.8, 1983 Attachment I. Changes to Davis-Besse Nuclear Power Station Unit 1, Appendix A Technical Specifications 6.5.1.2, 6.5.2.2, Figure 6.2-1, and Figure 6.2-2.

A. Time required to Implement. This change is to be effective upon URC approval.

B. Reason for Change (Facility Change Request 80-249, Rev. E).

This change incorporates those organizational changes made in names and titles of both Company Nuclear Review Board (CNRB) and Station Review Board (SRB) member requirements. These changes have been made to be consistent with those title designations used within the Company and Station organization structure.

C. Safety Evaluation (See attached)

D. Significant Hazards Considerations Toledo Edison has reviewed the above Amendment Request in accord-ance with 10 CFR 50.92(c) and has determined the proposed amend-ment would not:

(1) involve a significant increase in the probability or con-sequences of an accident previously evaluated. Only title changes are made to the CNRB and SRB. No functional changes are made to these boards or the plant staff. The Station and Company organization charts are only increased in size with no functional changes made. Accident Analyses are un-affected.

(2) create the possibility of a new or different kind of acci-dent from any accident previously evaluated. As stated in (1) above, no potential accidents or accident analyses are affected.

(3) involve a significant reduction in a margin of safety.

Margins of safety are also unaffected due to the administra-tive nature of the changes.

SAFETY EVALUATION 80-249, Rev. E The Technical Specification change requested reflects only organizational changes.

The safety function of the Company Nuclear Review Board (CNRB), which remains un-changed, is to:

A. Review per Section 6.5.2.7 of Technical Specifications

1. Safety Evaluations

2. Unreviewed Safety Questions on procedures, equipment, systems, tests or experiments

3. Changes to Facility Operating License

4. Violations having nuclear safety significance

5. Abnormalities or deviations that affect nuclear safety

6. . Events requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification

7. Unanticipated deficiency in safety related structure systems or components .

8. Station Review Board (SRB) Minutes ,

B. Perform audits of facility activity per Section 6.5.2.8 of Technical Specifications.

The safety functions of the Station Review Board (SRB), as described in Sections 6.5.1.6 and 6.5.1.7, also remain unchanged.

The organizational changes to the CNRB and SRB will only change some members and titles, and not the function of the Board. The changes improve independence and expertise on the Board and facilitate their function.

The operating license requirements have been deleted from the Station organization chart. Tla number of licenses in the crew composition is governed under Section 6, Table 6.2-1. Any license required functions by the control room organization ~shall be dispatched in accordance with 10 CFR 50.54 and Part 55.

There are no physical or safety related functional changes, therefore, this is not an unreviewed safety related issue.

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