ML20236C983

Application for Amend to License NPF-3,changing Tech Specs 6.2.2b & 6.2.2c & Tech Spec Table 6.2-1 Re Number of Operators in Control Room Area When Fuel in Reactor & in Control Room & Onsite When Plant in Modes 1-4.Fee Paid

ML20236C983
Person / Time
Site:	Davis Besse
Issue date:	10/16/1987
From:	Shelton D TOLEDO EDISON CO.
To:
Shared Package
ML20236C978	List: ML20236C974 ML20236C983 ML20236C997
References
1399, NUDOCS 8710270432
Download: ML20236C983 (5)

Text

__ _ _ _. __-_ ___________

Dockst No. 50-346

' License No. NPF Serial.No. 1399

' Enclosure Page 1

. APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit No. 1 Facility Operating License No. NPF-3. Also included are the Safety Evaluation and Significant Hazards Consideration.

The. proposed changes (submitted under cover letter Serial No. 1399) concern:

Specification 6.2, Organization, Section 6.2.2b, Facility Staff, specification 6.2, Organization, Section 6.2.2c, Facility Staff, and Table 6.2-1, Minimum Shift Crew Composition.

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D. C. Shelton, Vice President, Nuclear Sworn and subscribed before me this 16th day of October 1987.

tLAAL Notar)/ Public, State of Ohio My commission expires / /

Ni 2 ersons:

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'Dockot'No'. 50 i346-p; License'No. NPF Serial No.'1399

. Enclosure-

'Page ,

,1 The following information is provided to support issuance.of the requested changes to, the Davis-Besse Nuclear Power Station,

Unit No. '0perating' License No. NPF-3, Appendix A,-Technical-Specifications.

.Seetions.6.2.2b,;6.2.2c,"and Table-6'.2-1.

A. . Time Required to. Implement: lThis change is to be effective upon NRC.issuanceLof the. License Amendment and to'be: implemented within

, t the following=30 days'by the: licensee.

B. Reason for Change-(Facility Change Request 83-122): 10CFR50.54,.

paragraphs (m) and-(k; establish the minimum licensed operator staffing

-requirements at nuclear power plants. The requested changes revise the Technica1' Specifications to incorporate the requirements of the NRC. rule.

'C. < Safety Evaluation:

See attached Safety Evaluation (Attachment No. 1).

D.-- ~Significant Hazards:. Consideration: See attached Significant Hazards

. Consideration (Attachment No. 2),

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• Dock:t'No. 50-346 License No. NPF-3 Serial No 1399 Attachment.1 Page 1 i

SAFETY EVALUATION l

INTRODUCTION This Amendment Request is to amend Technical Specification Sections j 6.2.2b, 6.2.2c, and Table 6.2-1 relative to staffing requirements at nuclear power plants. To comply with the NRC requirement addressed in

<10 CFR Part 50.54, Paragraph (m) on staffing at nuclear power plants, the Technical Specifications should be revised as follows.

FACILITY STAFFING Section 6.2.2b should be revised to "At least one licensed Operator shall be'in the control panel area when fuel is in the reactor". Section  !

6.2.2c should be revised to "At least two Licensed Operators, one of-which has a-Senior Operator License, shall be present in the control room while in MODES 1, 2, 3 and 4".

TABLE 6.2-1 (MINIMUM SHIFT' CREW COMPOSITION)

This table should be revised to require two (2) Senior Operator's Licenses when the station is in Modes 1, 2, 3 and 4. The safety function of qualified operators in the Control Room is to respond to normal and emergency conditions of the plant. The increased number of Senior Operator licensed personnel is based on Three Mile Island (TMI) Action Plan Requirements, NUREC-0737, to ensure the staffing adequacy at a nuclear power plant. idequate staffing will improve the safety function

'of the operators dur.ng plant operation.

4 Pursuant to the above, there is no unreviewed safety question involved in the proposed change to the Technical Specifications.

-.Dochet No. 50-346 License No. NPF-3 Serial No. 1399 Attachment 2 Page 1 SIGNIFICANT HAZARDS CONSIDERATION l

INTRODUCTION The purpose of this Significant Hazards Consideration is to review a proposed change to the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications. The proposed changes involve revising the Control Room staffing requirements outlined in Sections 6.2.2b'and 6.2.2c, Facility Staffing, and Table 6.2-1, Minimum Shift Crew Composition. This change is to comply with the NRC requirements addressed in 10CFR50.54, paragraphs (m) and (k) on staffing nuclear power plants.

SYSTEMS AFFECTED None REFERENCES

1. Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications

2. Davis-Besse Administrative Procedures AD1839.00, Revision 15, Station Operations

3. 10CFR50.54

4. NRC Safety Evaluation Related to Shift Staffing of Davis-Besse Unit 1, transmitted by NRC letter to Toledo Edison dated June 14, 1984 (Log No. 1531).

PROPOSED AMENDMENT REQUEST DISCUSSION The proposed License Amendment Request revises the following sections of the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications:

6.2.2b - Replace " control room" with " control panel area". This change clarifies that at least one licensed operator shall be present at the controls at all times during the operation of the facility as required by 10CFR50.54, paragraph (k). This requirement is currently met by Davis-Besse Administrative Procedure AD1839.00, Station Operations.

6.2.2c - Revise to read "At least two licensed Operators, one of which has a Senior Reactor Operator license, shall be present in the control room L while in Modes 1, 2, 3 or 4." 10CFR50.54, paragraph (m) requires single l unit nuclear plants to have two senior operators onshift with at least one of the senior operators required to be in the control room when the unit l

is in a mode other than cold shutdown or refueling. The " control room"

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- 'atLDavis-Besse' includ<s the-Shift Supervisor's office which is linked audibly with the contal room panel area via a direct. intercom.- This

% 4 configuration ~has been found to be acceptable, as' documented in NRC's

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'i Safety' Evaluation related to shift: staffing at Davis-BesseLUnit 1 and j 4

. transmitted by:NRCilettsr to: Toledo. Edison. dated June 14, 1984;(Log y lNo. 1531)'. -Administrative; ProcedureAD1839.00, Station. Operations,

. presently-meets:10CFR50.54(m) requirements,1and the propose ~d Technical specification ~ change.will' reflect (these requirements.

Table:6'2 The number of-shift' crew members with Senior' operator-

- Licenses (SOLs)-required when;the plant'is in Modes.1,:2,' 3 and 4 will.be Lchanged from "1" to "2 to, reflect the change to .6.2.2c. The -evised 2

table;would-comply _with450.54(m) and be' consistent with.AD1839.00, Station Operations.. ,

SIGNIFICANT HAZARDS: CONSIDERATION

.. The! proposed changes _do not' involve a significant hazards consideration Lbecause operation of;the; Davis-Besse Nuclear Power Station, Unit No. 1 in-Jaccordance'with this chang'e'would not:

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1. ' Involve a significant increase in the probability or cons v ences of an accident previously evaluated (10CFR50.92(c)(1)). j TheLaddition of the proposed changes _to Sections.6.2.2b, 6.2.2c, and Table _6.2-1 increases both the number and qualification requirements

. , . :of Control Room. Operators necessary to satisfy the minimum shift crew requirements. . These changes support the.liklihood of detecting

/ abnormal events early enough to. mitigate potentially adverse conditions.

- 2. Create the possibility.of La new or different kind of accident from any accident 'previously evaluated (10CFR50.92(c)(2)) .-

It has been determined that a new or different kind of accident will not;be possible due to this change. These changes which increase- j Control Room staffing requirements do not create the possibility of a new or different kind of accident.

3. Involve a'significant reduction in a' margin of safety

' (10CFR50.92 (c) (3)) .

'The addition of the proposed changes to Sections 6.2.2b, 6.2.2c, and Table 6.2-1' increase the Control Room staffing requirements and.

Y therefore, will not reduce the margin of safety.

CONCLUSION

' On the basis of the'above, Toledo Edison has determined that the amendment request does not involve a significant hazards consideration.

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