ML19327B397

Application for Amends to Licenses NPF-72 & NPF-77, Authorizing Use of Vantage 5 Fuel & Combination of Vantage 5 Fuel & Present Optimized Fuel Assembly Core at Plant

ML19327B397
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	10/19/1989
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML19327B398	List: ML19327B397 ML19327B401 ML19327B405
References
NUDOCS 8910310099
Download: ML19327B397 (4)

Text

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October 19, 1989 l

Dr. Thomas'E. Murley, Director

Office of Nuclear Reactor Regulation j

U.S. Nuclear Regulatory Commission j

' Washington, DC 20555 l

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' Attn:

Document Control Desk i

Subject:

Braidwood Station Units 1 and 2 Li Application for Amendment to facility L

Operating Licenses NPF-72 and NPF-77 h

NRC Docket Nos.'50-456 and 50-452

Reference:

a) July 31, 1989, RA Chrzanowski letter to T.E. Murley l

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Dear Dr. Hurley:

i Pursuant'to 10 CFR 50.90, Commonwealth Edison-proposes to amend (Appendix'A Technical Specifications'of Facility Operating Licenses NPF-72 and f

NPF-77..This proposed amendment will be required for unit startup following the next refueling outage.at Braidwood Unit 2.

Commonwealth Edison, j

l therefore,'riguests anoroval of this orops id_amendmeat by March 1. 1990 The proposed amendment requests the use of VANTAGE 5 fuei and the l

combination.of VANTAGE 5 fuel and the present Optimized Fuel Assembly core at Braidwood Station. Units 1 and 2.

This request is identical to'the same recuest made for Byron Units 1 and 2 in reference-(a).

This request also

. adcresses' comments made by the NRC staff in teleconferences held on October 3 and 4, 1989.

These are provided in Enclosure III.

The Summary of Proposed Changes is provided in Enclosure I.

Enclosure II provides Attachments I through 7.

The Safety Evaluation is contained in Attachment 1.

The revised Technical Specification pages are

. contained in Attachment 2.

The documentation for the reviews of the Non-LOCA analyses, LOCA analyses, and Radiological Assessment are contained in Attachments 3, 4, and 5 respectfully.

The proposed changes have been reviewed and approved by both on-site and off-site review in accordance with Commonwealth Edison procedures.

Commonwealth Edison has reviewed this proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists.

This evaluation is documented in Attachment 6.

Also, Commonwealth Edison has evaluated the proposed amendment in accordance with the requirements of 10 CFR 51.21. Attachment 7 contains the resulting Environmental Assessment.

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Dr. T.E. Murley October 19, 1989

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Commonwealth Edison is notifying the State of Illinois of our application.for.this amendment by transmitting a copy of this letter and its.

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~y' attachments to the designated State Official.

Please direct any questions regarding this submittal to this office.

Very truly yours,.

,/c A A S.C. Hunsader Nuclear Licensing Administrator J

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Enclosure I:

Summary of Proposed Changes Enclosure II:'

Attachment.1 Safety Evaluation

' Attachment 2 Revised Technical Specification Pages

- Non-LOCA Accident Analyses LOCA Accident Analyses

? Radiological Assessment

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! Significant Hazards Evaluation i' Environmental Assessment Enclosure III:

Responses to NRC Staff Questions on the Proposed use of VANTAGE 5.

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cc: Braidwood Resident Inspector S.P. Sands - NRR Office of Nuclear Reactor Safety - IDNS I

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ENCLOSURE I

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SUMMARY

OF PROPOSED CHANGES The proposed change to Braidwood Station Technical Specifications will License Vantege 5 fuel for use starting with Unit 2 cycle 2 and Unit I cycle 3.

The following is a summary of the proposed changes:

>1)

Table 2.2-1, includes revised F Delta I offset wings and gains due to Vantage 5 OPDT/0 TDT setpoint differences, n

2) 2.1.1 bases, includes added DNB correlations and Safety Analysis DNBR Limits and added new FNDH values for the Vantage 5 fuel.

3) 3.1.1.3 and associated bases, beginning of cycle life are being deleted from Action A, and 3.0.4 not appilcable is being added to action A.

These changes are necessary because moderator temperature coefficient (HTC) will be initially increasing (becoming more positive) with core exposure. As such the least negative value for MTC will be during core 11fe, not necessarily at the beginning.

The provisions of 3.0.4 are not applicable is being added to allow transition into modes 2 and 1 from mode 3 as long

'as rod withorawal'11mits are' established per action statement A.

The surveillance requirements associated with MTC have also been revised to address the concerns above.-

4).'3.1.3.4, has been revised to address an increase in rod drop times associated with the Vantage 5 fuel.

5) 3.2.2 and associated bases, have been revised to address the increased FQ(Z) limits associated with Vantage 5 fuel.

In addition, the surveillance requirement exempting the area surrounding the grid straps associated with the Vantage 5 fuel does not significantly alter the flux distribution.

6) 3.2.3 and associated bases, have been revised to address the new FNDH limits associated with Vantage 5 fuel.

1 7) 3.2.1 bases, has been revised to reflect the change made to the FQ(Z) limits, and the use of rod bow penalties due to extended burnup.

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ENCLOSURE II

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Licensing Submittal for Braidwood Station Units 1 and 2 Transition to Hestinghouse 17x17 VANTAGE 5 fuel Iable.of Contenti Attachment l' Safety Evaluation Technical Specification Change Pages Non-LOCA Accident Analyses LOCA Accident Analyses Radiological' Assessment Significant Hazards Evaluation e

Environmental Assessment

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