ML19325C392
| ML19325C392 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/09/1989 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19325C391 | List: |
| References | |
| NUDOCS 8910160160 | |
| Download: ML19325C392 (5) | |
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Docket Number 50-346 u,
License Number NPF-3 e
Serici Number 1713 Enclosure Page 1 L
I APPLICATION FOR AMENDMENT TO i
FACILITY OPERATING LICENSE NUMBER NPF-3 FOR DAVIS-BESSE NUCLEAR POVER STATION l
UNIT NUMBER 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit i-Number 1 Facility Operating 1.icense Number NPF-3.
Also included are the Technical Description and Significant flazards Consideration.
The proposed changes (submitted undes cover letter Serial Number 1713) concernt 5
Technical Specification 6.2.2.gl Technical Specification 6.3.11 Technical Specification 6.5.1.2.
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By:
D. C. SheVton, Vice President, Nuclear Sworn and subscribed before me this 9th day of October, 1989 Yidl.ub ALL Notary PuVllc, Stat'e of Ohio i
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EVELYN L DRESS NOTARY PUBUO, STATE OF OHIO MyCorrassianE@tesMy %1004 8910160160 891009 PDR ADOCK 05000346 P
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g". 1.,0, License Number NPF-5; j
. Docket Number 50-346 Seri:1 Number 1713'
-Enclosure l
l Page 2 s.
The following information is provided to support issuance of the requested
' changes to the Davis-Besse Nuclear Power Station, Unit. Number 1 Operating l
License Number NPF-3, Appendix A, Technical Specifications.
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A.
Time Required to implement:- This change vill be implemented within *5 w
days following NRC' issuance of the Licence Amendment.
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89-0013/DCR Number 89-0317) Revise the B.
Reason for Changes- (LAR Number license requirements for the Manager - Plant Operations, j
C.
Technical
Description:
See attacF.ed Technical Description i
. (Attachment Number 1).
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D.
Significant Hazards Consideration:
Ste attar.hed Significant Hazards-i l'
Consideration (Attachment Number 2).
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- - Docket Number 50-346 Lie:ns; Number NPF-3 S;ri:1 Number 1713 4
Page 1 TECHNICAL DESCRIPTION Title Revise the License Requirements for the Manager - Plant Operations Description The purpose of this technical description is to review proposed changes to the qualification requirements of the Assistant Plant Manager - Operations as described in Davis-Besse Nuclear Power Stetion (DBNPS) Technical Specification (TS) 6.2.2, Facility Staff. Technical Specification 6.3, Facility Staff Qualifications, vill also be revised to reflect these changes. The proposed changes vould allow a previously held Senior Reactor Operator (SRO) license. on the DBNPS or on another pressurized vater reactor to serve as acceptable qualification for this position. This request is consistent with a Licence Amendment issued by the Nuclear Regulatory Commission (NRC) to Florida Power and Light Company's Turkey Point Plant, Units 3 and 4, dated March 27, 1989.
Due to a recent reorganization at the DBNPS, the Assistant Plant Manager - Operations' title has been changed to Manager - Plant Operations.
This administrative title change is also requested at this time. The Manager - Plant Operations title vill be uaec in the remainder of this safety evaluation since it reflects the current plant nomenclature at the DBNPS.
I Systems and Components Affected None t
Documents Affected Davis-Besse Nuclear Power Station, Unit Nember 1 Operating License, Appendix A, Technical Specifications Safety Functions of Affected Systems and Components None Effects on Safety Technical Specification 6.2.2.g requires that the Manager - Plant Operations hold a SRO license.
The changes proposed herein vould revise TS 6.2.2.g to state that "The Manager - Plant Operations shall either hold or have held a senior reaciar operator license on the Davis-Besse Nuclear Power Station, or have held a senior reactor operator license on a similar plant (i.e., another pressurized water reactor)." This proposed change also reflects the current title for this position at the DBNPS.
In addition, Technical Specification 6.3.1 veuld be revised to state that the Manager - Plant Operations shall meet the requirements of Technical Specification 6.2.2.g rather than the explicit guidance of ANSI N18.1-1971, l
Selection and Training of Nuclear Power Plant Personnel, for the following l
reason.
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Docket Number 50-346' License N:mber NPF-3 a
Serial Number 1713
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Page 2 The Manager - Plant Operations is an upper level manager with responH bility for plant operations, chemistry, and operations engineering sections.
The proposed changes ensure that the Manager - Plant Operations Fat the knowledge and experience commensurate with his levr:1 of responsibility. However, direct supervision of the reactor operators is the responsibility of the Operations Superintendent who is required to hold a current SRO license on the DBNPS per TS 6.2.2.g.
Therefore, there remains an intermediate in-line manager, between the reactor operators and the Manager - Plant Operations, who is required to maintain a current SRO license and who has direct supervisory responsibility for operations.
ANSI 18.1-1971 provides that the individual below the Plant Manager who has direct responsibility for operator supervision hold u SRO license. The proposed changes meet the intent of ANSI 18.1-1971 and are sufficiently rigid to ensure safe operation of the DBNPS.
In TS 6.5.1.2, Station Review Board - Composition, "Assistnnt Plant Manager, Operations" would be revised to " Manager - Plant Operations." This is an administrative change to reflect the current plant nomenclature at the DBNPS.
Unreviewed Safety Question Conclusions The following conclusions are provided as a result of Toledo Edison's safety review and evaluation of the proposed changes to the DBNPS, Unit Number 1 Operating License, Appendix A, Technical Specifications.
The proposed changes are administrative in nature. Therefore, the implementation of the changes would:
Not increase the probability of occurrence of an accident previously evaluated in the USAR because the accident conditions and assumptions are not affected by the proposed Technical Specification changes.
The proposed changes do not involve a test, experiment, or a modification to a system. The proposed changes are administrative in nature and do not increase the probability of occurrence of an accident previously evaluated (10CFR50.59(a)(2)(i)).
Not increase the consequences of an accident previously evaluated in the USAR because the accident condtlons and assumptions are not atfected by the i
proposed Technical Specification changes.
Licensed operators will continue to operate the plant under the supervision of the Opera *lons Superintendent who is required to hold a current SRO license. The proposed changes do not involve a test, experiment, or a modification to a system.. The proposed changes are administrative in nature and do not increase the consequences of an accident previously evaluated (10CFR50.59(a)(2)(i)).
Not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the USAR because the proposed changes do not involve a test or experiment, and no station equipment is being modified. The proposed changes are administrative in nature and do not increase the probability of occurrence of a malfunction of equipment important to safety (10CFR50.59(a)(2)(i)).
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F Docket Number 50-346 License Number NPF-3 L. C.
Serial Number 1713 i
Page 3 Not increase the consequences of a malfunction of equipment important to safety previously evaluated in the USAR becauce the proposed changes do not I
fnvolve a test or experiment, and no station equipment is being modified.
Licensed operators vill continua to operate the plant under the supervision of the Operations Superintendent who is required to hold a current SRO license.
The proposed changes are administrative in nature and do not increase the consequences of a malfunction of equipment important to safety (10CFR50.59(a)(2)(i)).
t Not create the possibility for an accident cf a different type than any evaluated previously in the USAR because the accident conditions,and l
assumptions are not affected by the proposed Technical Specification changes.
The propoted changes do not involve a test or experiment, or a modification to a system and do not affect any plant equipment or operation procedures which could create the possibility of a different accident.
Licensed operators vill continue to operate the plant under the supervision of the Operations Superintendent who is required to hold a current SRO license. The propcsed changes are administrative in nature and involve no accident scenario. On matters related to nuclear safety, all accidents are bounded by previous analyses and no new accidents are involved (10CFR50.59(a)(2)(ii)).
Not create the possibility for a malfunction of a different type than any 6
evaluated previously in the USAR because no station equipment is being modified by the proposed Technical Specification changes. The proposed changes do not involve a test or experiment, or a modification to a system which could create a different malfunction scenario (10CFR50.59(a)(2)(ii)).
Not reduce the margin of safety as defined in the basis of any Technical Specification because the proposed Technical Specification changes do not affect any operating practices or limits nor any equipment or systen important to safety. The proposed changes are administrative in nature and will not reduce the mergin of safety (10CFR50.59(a)(2)(iii)).
Conclusion P
Based on the above, it is concluded that the proposed Tecnnical Specification changes do not constitute an Unreviewed Safety Question.
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