ML20197A735

Application for Amend to License DPR-3,revising Tech Specs to Allow for Performance of 10CFR50.59 Reviews for Future Core Reloads.Fee Paid

ML20197A735
Person / Time
Site:	Yankee Rowe
Issue date:	10/20/1986
From:	Heider L YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20197A742	List: ML20197A735 ML20197A761
References
DCC-86-160, FYR-86-101, PC-199, NUDOCS 8610270384
Download: ML20197A735 (4)

Text

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Telephone (617) 872-81CD TWX 710 380 7619 YANKEE ATOMIC ELECTRIC COMPANY d4 + 1671 Worcester Road, Framingham, Massachusetts 01701 DCC 86-160

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October 20, 1986 FYR 86-101 PC-199 Supplement #1 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Office of Nuclear Reactor Regulation

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) YAEC Letter to USNRC, dated August 30, 1935 (FYR 85-91)

(c) YAEC Letter to USNRC, dated June 24, 1986 (FYR 86-057)

Subject:

Core Operating Limits

Dear Sir:

Pursuant to Section 50.59 of the Commission's Rules .nd Regulations, the Yankee Atomic Electric Company (YAEC) hereby requests the authorization to make the following changes:

Proposed Change Reference is made to the Technical Specifications and the " Yankee Nuclear Power Station Core XVIII Performance Analysis," (Reference (b)) of License No. DPR-3. This proposed change replaces Reference (c) in its entirety.

We propose to modify the Technical Specifications as described below.

The proposed Technical Specification changes are given in Attachment A.

1. Modify Page 6-27 by inserting Specification 6.17, Core Operating Limits.

2. Modify Specifications 3.1.3.5, 3.2.1, and 4.2.1.2.b to add reference to Specification 6.17.

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3. Delete the following figures:

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3.1-2, Page 3/4 1-29, 3.2-1, Page 3/4 2-4, 3.2-3, Page 3/4 2-6, l

3.2-4, Page 3/4 2-7.

4. Modify Pages 3/4 1-28, 3/4 2-1, and B3/4 1-1 and B3/4 2-1 to remove reference to the deleted figures.

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5. Modify Page 3/4 2-2 by replacing existing cycle specific values in Technical Specification 4.2.1.2.b with a generic description consistent with the proposed modification of Technical Specification 3.1.3.5.

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F United States Nuclear Regulatory Commission October 20, 1986

, Attention: Office of Nuclear Reactor Regulation Page 2 FYR 86-101 PC-199 Supplement #1

(. Modify Page 5-1, The Fuel Assembly Description, to allow for a maximum nominal enrichment of 4.0 weight percent U-235.

7. Modify Page B3/4 1-1 to correct a typographical error.

Reason and Basis for Change The reason for this proposed change is to allow for the performance of 10CFR50.59 reviews for future core reloads. Presently, NRC approval for each core reload is obtained through a submittal of a Core Performance Analysis Report (CPAR) and the amended Technical Specifications. Changing the specifications has become fairly routine with the same specifications being changed only slightly from cycle to cycle. The above mentioned modifications remove specific figures from the Technical Specifications and include them instead in plant operating procedures. In the case of reload fuel enrichment, a bounding upper limit is provided. Adequate controls are retained by reference to Specification 6.17, which controls the analytical methods used to generate the information.

f It should be noted that among the Technical Specification changes

! proposed is the change to provide control of the analytical methods used to generate the specified core operations limits. Specification 6.17 provides administrative control of the analytical methods, which were reviewed and approved by the staff pursuant to approving previous Technical Specifications changes. The Yankee Nuclear Power Station Core XVIII Performance Analysis Report contains references and summary descriptions of the analytical methods which have previously been reviewed and approved by the NRC for reload licensing. Reference to our analytical methods provides an additional control mechanism regarding the use of 10CFR50.59 to assure that the information

! contained in these core operating limits are determined with methods l previously approved by the staff for application to the Yankee plant.

According to 10CFR50.59 of the Commission's regulations, changes may be made without prior Commission approval unless the change involves a change in the rechnical Specifications incorporated in the license or an unreviewed safety question. Changes in analytical methods previously approved by the Commission have been treated as an unreviewed safety question. Thus, referencing the analytical methods in the Technical Specifications provides assurance that the information contained in these core operating limits are j constructed with methods previously approved by the staff. If a change in

methods is deemed necessary, Yankee will submit a description of the change to the NRC for their review and approval prior to its use in the reload analysis.

. The technical information contained in the four operating limits curves will be used by the plant in the same manner that the information presently contained in the Technical Specifications is now used. Currently, the information contained in the Technical Specifications is incorporated into plant controlled documents. Compliance to the limits provided in the

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s United States Nuclear Regulatory Commission October 20, 1986 Attention: Office of Nuclear Reactor Regulation Page 3 FYR 86-101 PC-199 Supplement #1 Technical Specifications is shown via periodic surveillances. Removal of the information from the Technical Specifications will not change the way the information is incorporated into plant operating procedures, or the way compliance to operation within these limits is now performed. Compliance.and verification of the proper use of this information can be accomplished through normal inspection and audit processes as currently performed by the Inspection and Enforcement (I&E) ani Regulatory (NRR) branches of the Commission.

The change to the fuel assembly description is being submitted to provide a bound on fuel enrichment for future Yankee cycles of operation. Previous Yankee operation has utilized up to 4.0 w/o U-235 Zircaloy clad fuel as a fuel assembly design reload enrichment.

SAFETY CONSIDERATION This change is requested in order to reduce the USNRC and lankee Staff review time and related costs associated with the amendment process. Yankee views this proposed change to be purely administrative. As such, this proposed change would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. This change merely modifies the manner in which analysis results are referenced in the Technical Specifications, as well as correcting a typographical error.

Therefore, the change cannot increase the probability or consequences of an accident.

l 2. Create the possibility of a new or different kind of accident from any previously analyzed. This modification of changing the

! referencing of analysis results and correcting typographical errors is administrative in nature. Therefore, it does not create the i possibility of a new or different kind of accident since it does not I

impact the plant analysis methods, operation, or plant components.

3. Involve a significant reduction in a margin of safety. This modification of changing the referencing of analysis results and correcting typographical errors does not modify any analysis assumptions, methodologies, or results. Thus, this change does not impact the scfety margins which currently exist.

Based on the consideration contained herein, it is concluded that there is reasonable assurance that operation of the Yankee plant consistent with the proposed Technical Specifications will not endanger the health and safety of the public. This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.

Fee An application fee of $150.00 is enclosed in accordance with 10CFR170.21.

Y

United States Nuclear Regulatory Commission October 20, 1986 Attention: Office of Nuclear Reactor Regulation Page 4 FYR 86-101 Pc-199 Supplement #1 Schedule of Change These changes to the Yankee Technical Specifications will be implemented upon Commission approval. A timely review and approval of this submittal to be consistent with our plans for the Cycle 19 reload analysis would be appreciated.

We trust that you will find this submittal satisfactory; however, should you desire additional information, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY L. H. Heider Vice President / Manager of Operations LHH/dps Attachments COMMONWEALTH OF MASSACHUSETTS)

)ss MIDDLESEX COUNTY )

Then personally appeared before me, L. H. Helder, who, being duly sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and oon the behalf of Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and belief, b-Robert H. Groce Notary Public My Commission Expires August 29, 1991

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