NRC-91-0102, Application for Amend to License NPF-43,allowing Uprated Power Operation of 3430 Mwt,Representing Authorized Power Increase of Approx 4.2%.Details Withheld (Ref 10CFR2.790)

Application for Amend to License NPF-43,allowing Uprated Power Operation of 3430 Mwt,Representing Authorized Power Increase of Approx 4.2%.Details Withheld (Ref 10CFR2.790)

ML20083D494
Person / Time
Site:	Fermi
Issue date:	09/24/1991
From:	Orser W DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19302F196	List: NRC-91-0102, Application for Amend to License NPF-43,allowing Uprated Power Operation of 3430 Mwt,Representing Authorized Power Increase of Approx 4.2%.Details Withheld (Ref 10CFR2.790)
References
CON-NRC-91-0102, CON-NRC-91-102 NUDOCS 9110010038
Download: ML20083D494 (5)

Text

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U S NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-341 LICENSE NO. NPr 43 l

k Ferm' 2 i PROPOSED LICENSE AMENDMENT  ;

POWER UPRATE O)

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-4 Detroi.t 9110010038 910924 Edlw_kO s v PDR ADOCK 05000341 P PDR

William 6 orser Senan W:e hesar !

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Sept (eber 24, 1991 NRC-91-0102 U. S. Nuclear Regulatory Ccamission Attn: Document Control Desk Washingt on, D. C. 20555

References:

1) Femi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) General Elect ric Topical Report , NED C-31897 P-1

" Generic Guidelines for General Electric Boiling Water Reactor Power Uprate " June 1991 (LTRI)

(propriet e ry) h 3) General Electric Topical Reporc, NEDC-31984P

" Generic Evaluations of General Electric Boiling Wotar Reactor Power Uprate," July 1991 (LTR2)

(proprietary)

4) Fermi 2 Licensing Report.91-150 " Power Uprate Safety Analyses for Fermi 2," September 1991 (propriet a ry)

5) General El-ct ric Report, NEDC-31982P " Fermi 2 SAFER /GES" t-LOCA Loss-of-Coolant Accident," July 1991 (proprie t ary )

6) Det roit Edison let t er, NRC-90-0187, "P ropo sed Technical Specification Change (Liceuse Amendment) - Pressure-Temperature Limit s. " da t ed February 21, 1991

7) Det roit Edison let ter, NRC-91-0119 " Proposed Techcical Specification Change (License Amendment) - Rod Block Monitor Downscale Inst rument ation Setpoints," dated Septecber 24, 1991 C'i .

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USNRC September 24, 1991 NRC-91 -0102

Page 2

8) Detroit Edison letter, NRC-89-0215. " Proposed Technical Specification Change (License Amendment) - Control Rom Emergency Filtration System (3/4.7.2) " dated November 16, 1989

9) Detroit Edison letter, NRC-90-01SS, " Additional Information Concerning Proposed Change to Technical Specification 3.0.4," datal February 27, 1991

Subject:

Proposed License Amendment - Uprated Power Operation Pursuant to _10CFR50.90, Detroit Ediscn Company hereby proposes to amend Operatini: License NPF-43 for the Fermi 2 plant ly incorporating the enclosed changes into the Operating License and Plant Technical Specifications. The proposed changes will allow an upt ated power operation of 3430 megawatts therma.1 at Fermi 2. This power level represents an authorized power level increase of approxim,tely 4.2%.

This proposal follows the generic guidelines f or boiling water reactor power uprate described in Reference 2. As such, it relies on the generic recolutiun of topics provided in Reference 2 or Reference 3.

These documents hwe been submitted to the NRC by General Electric

-% under separate cover for review and approval on a generic basis.

The imple'nentation of Power Uprate et Fermi 2 will require a resetting of the safety relief talve setpoints as well as the recalibration of plant instrumentation to reflect the uprated power. Core reload design will also be modified to maintain the current 18 month reload cycle and procedure changes will be made where necessary to support uprated opetation. To support these required modifications planned during Fermi 2's third refueling outage, issuance of the proposed amendment by September 1992 is requested. The proposed amendment should be ef fective upon startup f rom the third refueling outage.

Enclosure 1 provides a description and evaluation of the proposed change. Enclosure 2 provides the proposed Technical Specification and Operating License pages.

t Enclosure 3 (Reference 4) provides the plant specific submittal information prescribed by Reference 2. For topics that have been generically evalustal, it refers to the generic evaluations in Reference 2 or Reference 3 as appropriate. Thus, Enclosur e 3 summarizes the results of all of the rignificant safety and operational evaluations needed to justify a licensing amend snt to allow for uprated power operation at Fermi 2.

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USNRC NRC-91-0102 '

l Page 3.

A substantial portion of- Enclosure 3 was provided by General Elect ric and has been identified therein as proprietary information. Pages containing proprietaty information are labelled "GE Proprietary Information" at the top of the page. Enclosure 4 prevides GE's affidavit to that ef fect. Therefore..in accordance with 10CFR2.790, it is requent ed - that _ Enclosure 3 information. that is identified as

_ proprietary be withheld f rom public disclosure.

Enclosure 5 (Reference 5)- providts a description of the resulte of the-loss of coolant accident analyses based on cycle 3 fuel designs using the NRC approved SAFER /GESTR methodology which was endorsed by the genetic power-uprate guidelines described in Reference 2. This is the ,

first time application of the SAFER /GESTR codes for Fermi 2. Results of -that evaluation will be confirmed for subsequent fuel reload analyses using the SAFER /GESTR methodology. The Enclosure 5 report is considered by GE to be proprietary. Enclosure 6 provides GE's af fidavit to that ef fect. Therefore, in accordance with 10CFR2.790 it is requested that Enclosure 5 be withheld f rom public disclosure.

Reference 6 proposes Technical Specification chsnges for Pressure Temperature Limits which conform to Regulatory Guide 1.99, Revision 2 as required by. Generic Lstter 88-11. Portions 'of .this change are O based upon the changes previously proposed in Reference 6.

therefore, requet ted that Reference 6 be approved prior to or It is, concurrently with the proposed changes in this submitt ed.

In Reference- 8. Detroit Edison proposed surveillance testing for determining leakage -rates for portions of the Control Room Emergency Filtration System ductwork which could allow unfiltered air inleakage to the Control Room during accident conditions. _ Included in Reference 8 are dose calculations for the contrn.1. room personnel under assumed z unfiltered inleakage. . The asstuec inleakage - for the uprated power b control room dose calculations presented -in Enclosure 3 is consistent with Refe rence 8. The Enclosure 3 control roco dose results are

, smaller then the Reference 8 resulta .because of updated assumptions L us.ed in the Enclosure 3 analyses. If changed _ solely by-uprating the L core power, the Reference 8 dose results would increase slightly.-

Nowever, the ef fect is small and the conclusion drawn in Reference 8 remai ns unchange d..

l Detroit Edison has evaluated the proposed Technical Specifications _

against the criteria o' 10CFR50.92 and determined _ that no significant hazards consideration-~is involved. The Fermi 2 Onsite Review l Organization has approved and the Nuclear Safety Review Group has j reviewed the proposed Technical Specifications and concurs with the-l enclosed determinations. In accordance with 10CFR50.91. Detroit 1

Ediscn is providing a copy of this letter to the State of Michigan.

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I USNRC Sept embe r . 24, 1991 14RC-91-0102 O_s

. 'Page 4 If you have any questions, please contact Mr. Robert J. Salmon at (313) 586-4273.

Since rely, Enclosures ec: A. B. Davis R. W. DeFayett e J. F. Stang S. Stasek R. Stransky Supervisor. Electric Operators Michigan Public Service Ocamission - J. R. Padget t O

1 USNRC  !

September 24, 1991 i NRC-91-0102 Page 5 I, WILLIAM S. ORSER, do hereby af firm that the foregoing statments are based on f acts and circumstances which are true and accurate to the best of my knwledge and belief, h'f .

W1LLI AM S. ORSER Senior Vice President O)

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on this ,d t' day or [ 1991, before me personally appeared Eilliam S.g/being Order, ehndt t .duly sworn and first says that he executed the foregoing as his free act and deed.

A d/b<  ! d Notary Public kOSAtlE A ARMrTA Notary Publ.c. Monroo CoJnty. Mi MyCommission Expuesat it iM

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