ML19325C393
| ML19325C393 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/09/1989 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19325C391 | List: |
| References | |
| NUDOCS 8910160161 | |
| Download: ML19325C393 (5) | |
Text
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p Dscket Number 50-346
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1.icense Number NPF-3 r y
'Jerial Number 1713 Page 4.
6.0 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF _
a.
Each on duty shift shall be composed of at.least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control
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room when fuel is in the reactor.
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c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor i
shutdown and during recovery from reactor trips.
J d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor 8 e.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reacter Operator or Senior Reactor Operator Limited to Fuel Handling who has no other con-current responsibilities during this operation.
f.
A site Fire Brigade of at least 5 members shall be maintained onsite at all timesi. The Fire Brigade shall not include 3 members of the minime shift crew necessary for safe shutdown of the unit and any personnel required for ether essential functions during a fire emergency.
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The Operations Superintendent shall hold a senior reactor operator license.
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t The individual qualified in radiation protection procedtres and the l
Fire Brigade Composition may be less than the minimum requirements l-for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acconsnodate L
unexpected absence, provided imediate action is taken to fill the required positions.
DAVIS-BESSE UNIT 1 6-la Amendment No. 9,J5,98.JJ5,135 (next page is 6 2) g p$dOljjocgo3000346 f61 s92oop p
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ADMINISTRAT!YE CONTROLS
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6.3 FACILI1Y STAFF 0]ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications.of AN51 N101-1971 for comparable positions, except for-(1) l the Chemistry and Health Phtsics Genere1' Superintendent who shall meet or-exceed the qualifications of Regulatory Guide 1.8, September 1975Miilk(2) the Shif t Technical Advisor who shall have a bachelor's degree or~ equiv-alent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidentsj(g l
6.4 TRAINING I
6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR 55.59.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Nuclear Training Director.
6.5 REVIEW AND AUDIT 6.5.1 STATION REY!EW BOARD (SRB)
FUNCTION 6.5.1.1 The Station Review doard (SRB) shall function to advise the Plant Manager on all matters related to nuclear safety.
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CONp0$ITION s
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6.5.1.2 The Station Review Board shall be composed of the 1
Chairman:
tation Review Board Chairman
- l Members tc:i::::: !L.;; Y z;;;;, ^;;;;ti;;;
l Member Assistant Plant Manager, Maintcnance Member:
Technical Support Manager Member Chemistry and Health Physics General Superintendent Member:
Operations Engineering Supervisor (Plant) i' Member:
An Ergineering Director or Performance Engineering Manager Member:
Operations cuality Assurance Manager Member:
Operations Superintendent (Plant)
- Designated in writing by the Plant Manaaer. The Chairman will be drawn from SRB members.
ALTERNATES 6.5.1.3 All altermate seabers shall be appointed in writing by the SRB Chatraan; however, no more than two alternates shall participate as voting i
members in SRB activities at any one time.
MEETING FREOUENCY 6.5.1.4 The SRB shall meet at least once per calendar montband as convened by the SRB Chairman or his designated alternate.
ODORUM 6.5.1.5 A quorus of the SRB shall consist of the Chairman or his desig-aated alternate and four members including alternates.
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RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be respc,nsible for:
a.
Review of plant administrative procedures and changes thereto.
b.
Review of the safety evaluation for 1) procedures, 2) channes to procedures, equipment or systems and 3) taats or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question.
Review of proposed procedures-and changes to procedures and c.
equipment detetsteed to involve an unreviewed safety question as defined in 10 CFR 50.59.
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6-6 Amendment No. !!,76.95.109 I
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DocktNumber50-346 N
License Number NPF-3 Seri;l Number 1713 Page 1 SIGNIFICANT HAZARDS CONSIDERATION Description 1
The purpose of this Significant Hazards Consideration is to review proposed changes to the Dr.vis-Besse Nuclear Power Station, Unit Number 1 Operating License, Appendix A, Technical Specifications. The proposed changes involve revising the license requirements for the Manager - Plant Operations.
The discussion below provides the Significant Hazards Consideration for the changes.as proposed in the Technical Description (Attachment 1).
Significant 15:ards Consideration The Nuclear Regulatory Commission has provided standards in 10CFR50.92(c) for determining whether a significant hazard exists.
A proposed amendmer.t to an Operating License for a facility involves no significant hazards if operation i
of the facility in accordance with the proposed changes would:
- 1) Not involve a significant increase in the probability or consequences of an accident previously evaluated 2) Not create the possibility of a new or different kind of accident from any accident previously evaluated; or 3) Not involve a significant reduction in a margin of safety.
Toledo Edison has reviewed the proposed changes as discussed in the Technical Description and determined that a significant hazard does not axist because operation of the Davis-Besse Nuclear Power Station, Unit Number 1 in accordance with these changes would:
Not involve a significant increase in the probability or consequences of an accident previously evaluated because the accident conditions and assumptions are not affected by the proposed Technical Specification changes. The l
proposed changes do not involve a test, experiment or a modification to a system.
Licensed operators vill continue to operate the plant under the supervision of the Operations Superintendent who is required to hold a current DBNPS SRO license. The proposed changes are 'idministrative in nature and do not increase the probability or consequences of an accident previously evaluated (10CFR50.92(c)(1)).
Not create the possibility of a new or different kind of accident from any accident previously evaluated 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 and io not affect any plant equipment or operational procedures which could create the possibility of a different accident.
The proposed changes are administrative in nature and involve no accident scenario.
Licensed operators vill continue to operate the plant under the supervision of the Operations Superintendent who is required to hold a current DBNPS SRO license.
On matters related to nuclear safety, all accidents are bounded by previous analysis and no new accidents are involved (10CFR50.92(c)(2)).
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Docket. Number 50-346
[ ';? ' J License Number NPF-3
' Serial Number 1713 Page 2 Not involve a significant reduction in a margin of safety because the proposed L
Technical Specification changes do not affect any operating practices or..
limits nor does it affect any equipment or system important to safety.
Licensed operators vill l continue to operate the plant under the supervision of the Operations Superintendent who is required-to hold a current DBNPS SRO license. The proposed changes are administrative in nature and vill not reduce the margin of-safety (10CFR50.92(c)(3)).
. Conclusion g
on the basis of the above, Toledo Edison has determined that the proposed
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. Technical Specification changes do not involve a significant hazard.
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