NRC-91-0019, Application for Amend to License NPF-43,consisting of Proposal Eliminating Cycle Specific Parameter Limits from Tech Spec in Accordance W/Nrc Generic Ltr 88-16

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Application for Amend to License NPF-43,consisting of Proposal Eliminating Cycle Specific Parameter Limits from Tech Spec in Accordance W/Nrc Generic Ltr 88-16
ML20070D037
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 02/21/1991
From: Orser W
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070D039 List:
References
CON-NRC-91-0019, CON-NRC-91-19 GL-88-16, NUDOCS 9102280071
Download: ML20070D037 (5)


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Februa ry 21, 1991 1;RC-91 -0019 U. S. Iluelear Regulatory Commission Attn: Document Control Dock Waahingt on, D. C. 20555 Referenecc: 1) Fermi 2 NRC Docket No. 50-341 NRC Licence 11o. IIPF-43

2) Det roit Edi con 1,ct t er t o ITRC, !!KC-89-0299 "Propoced Technical Specification Change (Licence Amendtent) - Elimination of Cycle Speci fic Paraneter Limit o", dat ed tiarch 26, 1990

Subject:

Supplement to Technical Specification Change (Licence Amendment) - Elimination of Cycle Speci fic Parameter Lircite (TAC No. 77832) _

Detroit Edicon in Reference 2 cubmit ted a propocal to climinate cycle specific parameter limits from the Technical Spc ficatione in accordance with NRC Generie Letter 88-16. Based upon diccucciona with the UFC ctaf f, Detroit Edinon is cubmitting reviced Technical Specifications for the implenentation of Generic Letter 88-16 at Fe rmi

2. The revisiona involve the Technical Specification f or !!ininum Critical Power Ratio and the referencen to NRC approved methodc which Jetermine the cycle cpecific limitc.

The No Significant Hazards Consideration determination contained in Reference 2 remains applicaule to the modified proponal. The Fermi 2 Onsite Review Organization has approved and the Nuc1 car Safety Review

, Croup has reviewed the proposed Technical Specifications and concurs with the enclosed determinationc.

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USNEC February 21, 1991 NRC-91-0019 Page 2 If you have any questions concerning thic mat t er, please contact Mr. Glen Ohiceachet at (313) 566-4275.

Sincerely,

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Enclosure cc: A. B. Davis P. W. DeFayette W. G. Pogere J. F. Stang Supervisor, Elect ric Ope rators, Michigan Public Service Commission - J. P. Padget t i

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USNRC February 21, 1991 NRC-91-0019 Fage 3 I, WILLI AM S. ORSER, do hereby af firm that the f oregoing statecients are based on facts and circunstances which are true and accurate to the best of my knowledge and belief, f_...

WILLI AM S. ORSER Senior Vice President on thia Ok day of d-/ eyjg 21 _, 1991, before ce fL personally appeared William S. Orcer, being .irst duly sworn and says that he executed the foregoing as his ree act and deed, k All AG b' (WJ hotary Public ROSAUE A ARME1TA Notcry Pub!!O. Mexco Ccunty, MI MyComm!ssionEm! csJon.11,1992 I

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Enclosure to NRC-91-0019 Page 1 REVISED TECHNICAL. SPECIFICATIONS FOR CENERIC LITI'ER 88-16 The proposed Technical Specifications (TS) of Reference 2 have been revised as follows:

1) TS 3/4.2.3, Minimum Critical Power Ratio (MCit), is revised to t etain the equations which define a t erm designated as t au. Minimum Critical Power Ratio Operating Limit s (OLMCFR) are provided as a f unction of tau. The use of the tau term provides a OLMCPR based upon measured control rod scram tines. The NRC st af f has determined t hat the relocation 'of the tau equations is inappropriate since the equations do not typically change cycle to cycle. Therefore, Detroit Edison has included the tau equations, unchanged f rom the cur rent TS, in the proposed TS 3.2.3. In addition, the provisions in Surveillance Requirement 4.2.3.1 which concern t au havt been retained without change.
2) Proposed TS 6.9.3 defines a new report, the Core Operating Limit s Report (COLR), which will contain the relocated cycle specific limit s. Included in TS 6.9.3 is a reference to the NRC appr oved report containing the methodology used to determine these limits.

Following discussion with the staf f, a necond reference has been added t o include the General . Elect ric (GE) report on loss-of-coolant accident (LOCA) evaluation methodology. This is appropriate since the cycle specific limits are haced, in part, on a cycle specific evaluation using this methodology. TS 6.9.3 has been editorially changed to refer to the NRC approved reports by their GE teport number. These reports are fully cited as references in the TS bases.

Finally, the parenthetical listing of the types of applicable limits has been revised to conform with the Generic Letter.

3) In the TS Bases for Specifications containing cycle specific limitc, the " latest approved revision" is referenced for the General Elect ric Standard Application for Reactor Fuel, NEDE-24011-P-A. To more clearly show which revision has been used for the deteruination of the cycle _ specific limits, it is proposed to replace the phrase " latest approved revision" with a statement that the COLR chall . indicate the approved-version at the time the analyses were perf ormed. This change also resulted f rom the discussions of the Reference 2 proposal with the NRC staff.

The GE report which describes the LOCA evaluation methodology is similarly subject to revision. Consistent with the above, a statement is included to show that the COLR will indicate the approved version of the report at the time the analyses wer e performed.

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Enclosure to NRC-91-0019 Page 2 In addition, the location and numbering of these TS Bases references have been editotially modified. Consistent wit h t he St andard Technical Specifications, the references have been consolidated at the end of the Power Distributian Limits section. Finally, a-text reference to the h0CA nethodology report is provided since none currently exists and a UFSAR reference has been updated to be consistent with a change in UFSAR format.

In order to allow flexibility in the in:plementation of the new TS provisions.

Detroit Edison requests that this license asiendtaent be issued in a manner which

- allows full implementation of the changes to take place any _ time prior to startup following the second Icfueling outage. The current TS limits ate applicable until that time.

Attached are the required TS page changes. All pages required for the proposed amendment have-been provided. In addition, overleaf pages have been included for NRC convenience in preparing the amendment package.

These revisions to-the proposed TS change represent resolution of details inherent in the implementation of thia Generic Letter. These details do not affect the basic concept that the liating of cycle specific parameters in a report separate f rom the TS is an administrative change. This concept formed the basis of Detroit Edison's determination that the proposed change did not involve a Significant Hazards Consideration. Therefore, the conclusion and hasis of the No Significant Hazards Consideration evaluation contained in Reference 2 is unchanged.

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