ML20094S381

Suppl to 920305 Application for Amend to License DPR-40, Changing TS 5.9.5 to Incorporate Current NRC Approved Revs to Util Core Reload Methodologies

ML20094S381
Person / Time
Site:	Fort Calhoun
Issue date:	04/08/1992
From:	Gates W OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20094S379	List: ML20094S377 ML20094S381
References
NUDOCS 9204150008
Download: ML20094S381 (8)

Text

y, BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Omaha Public Power District Docket No. 50-285

-(Fort Calhoun Station Unit No. 1)

APPLICATION FOR AMENDMENT OF OPERATING LICENSE l

l Pursuant to Section 50.90 of the regulations of the U. S. Nuclear Regulatory Commission ("the Commission"), Omaha Public Power District, holder of Facility Operating License No. DPR-40, herewith requests that the Technical Specifications set forth in A)pendix A to that License be amended to incorporate the current NRC approved rev'sions of OPPD's core reload methodologies..

The proposed changes in Technical Specifications are provided in Attachment A to this Application. A Discussion, Justification and ho Significant Hazards Consideration - Analysis, which demonstrates that the proposed changes do not involve significant hazards considerations, is appended in Attachment B. The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of etfluents or a change in the authorized power level of the facility.

WHEREFORE, Anlicant resaectfully requests that Specification 5.9.5 of Appendix A to Fac- ity Operatin attached hereto as Attachment A. g License No. DPR-40 be amended in the form l

i l

9204150008 920408 PDR ADOCK 05000285 P pop

l A copy of this Application, including its attachments, has been submitted to the Director - Nebraska State Division of Radiological Health, as required by 10 CFR 50.91, t

~~

OMAHA PUBLIC POWER DISTRICT By &- /b?

Division Manager

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Nuclear Operations Subscribed and sworn to before me this k day of April, 1992.

2btR . Artmul th__ NNW" '

\ Notary Publi~c 0 gEkWD

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ATTACIBIENT A

5.9.5 CoIc_Ottrating Limits Report

a. Core Operating Limits shall be established and documented in the Core Operating Limits Report before each reload cycle or any remaining part of a reload cycle,

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC as follows:

1. OPPD-N A-8301-P- A, Rev. 3 4 " Reload Core Analysis Methodology Overview" dated April 4988.191l.

2. OPPD NA-8302-P-A, Rev. 2 "Neutronics Design Methods and Verification" dated April 1988. -

3. OPPD-NA-8303-P-A, Rev. 2 3 " Transient and Accident Methods and Verification" dated ApriH988 March 1991.

4 Safety EvaluationJ}y The Office of Nuclcadcaclodtgulation Related to Amendment No.143 to Facility.Doerating License No.

DPR-40. Omaha Public Power District. Fort Calhoun Station Unit No.1. Docket No. 50-285. dated April 2. M

c. The core operating limits shall be determined so that all applicable limits of the safety analysis are met. The Core Operating Limits Report, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copics to the Region IV Administrator and Senior Resident Inspecor.

5-17a Amendment No. 444 l

5.9.5 Core Operating Limits RcpoIl

a. Core Operating Limits shall be established and documented in tlie Core Operating Limits Report before each reload cycle or any remaining part of a reload cycle,

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC as follows:

1. OPPD-NA-83dl-P-A, Rev. 4 " Reload Core Analysis Methodology Overview" dated April 1991,

2. OPPD-NA-8302-P A, Rev. 2 "Neutronics Design Methods and Verification" dated April 1988. -

3. OPPD-NA-8303-P-A, Rev. 3 " Transient and Accident Methods and Verification" dated March 1991.

4. Safety Evaluation By The Office of Nuclear Reactor Regulation Related to Amendment No.143 to Facility Operating License No.

DPR-40, Omaha Public Power District, Fort Calhoun Station Unit No.1, Docket No. 50-285, dated April 2,1992.

c. The core operating limits shall be determined so that all applicable limits of the safety analysis are met. The Core Operating Limits Report, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Region IV

~ Administrator and Senior Resident inspector.

5-17a Amendment No. MF

l ATTACHMENT B

DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION The Omaha Public Power District (0 PPD) proposes to revise the Fort Calhoun Station Unit No. 1 Technical S)ecifications to incorporate the latest NRC approved revisions to core reloac methodologies. The proposed changes revises Specification 5.9.5 to reflect approval of Revision 4 to topical report OPPD-NA-8301-P-A, " Reload Core Analysis Methodology Overview," Revision 3 to topical report OPPD-NA-8303-P-A, " Transient and Accident Methods and Verification,"

contained in NRC Safety Evaluation Reports dated March 2,1992 and issuance of Amendmant 143 to the Fort Calhoun Station Unit No.1 Technical Specifications in a NRC Safety Evaluation Report dated April 2,1992.

BASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION:

The proposed changes do not involve significant hazards considerations because operation of Fort Calhoun Station Unit No.1 in accordance with these changes would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes are administrative in nature in that the revisions to the topical reports for < Scting reload analyses have been previously reviewed and app: cJ by the NRC in Safety Evaluation Reports dated March 2,1992. Amendment 143 to the Fort Calhoun Station Unit No.1 Technical Specifications dated April 2, 1992 approved the use of additional analysis methodologies. The proposed changes merely incorporate a reference to these approved revisions into the Technical Specifications. Therefore these proposed changes do not involve a significant increase in the probability or consequences of an accident.

(2) Create the possibility of a new or different Kind of accident from any previously analyzed. -

It has been determined that no new or different kind of accident will be created due to the proposed changes. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previcusly evaluated.

l (3) Involve a significant reduction in a margin of safety.

The proposed changes merely incorporate a reference to NRC approved methodologies for conducting core reload and accident

-analyses, therefore the proposed changes do not involve a significant reduction in margin of safety.

i t i s ' PPD' t position that this Therefore based on the proposed amendment above does considerations, not involve significanthazards considerations as defined by 10 CFR 50.92 and the proposed changes will not result in a condition which significantly alters the impact of the Station on the environment. Thus, the proposed changes meet the eligibilit; criteria for categorical exclusion set forth in 10 CFR 51.22(e)(9) and pursuant to 10 CFR 51.22(b) no environmental assessment need be prepared.

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