ML20196C003

Application for Amend to License DPR-28,consisting of Change 146,revising Fuel Cladding Integrity Safety Limit for Use in Calculating Critical Power Operating Limits in Future Reload Analyses.Fee Paid

ML20196C003
Person / Time
Site:	Vermont Yankee
Issue date:	11/30/1988
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20196C006	List: ML20196C003 ML20196C009
References
FVY-88-99, NUDOCS 8812070133
Download: ML20196C003 (3)

Text

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VSRhlONT YANKEE NUCLEAR POWER CORPORATION Proposed Change No. 146

. RD 5, Box 169, Ferry Road Brattleboro, VT 05301 y ENGINEERING OFFICE

$80 MAIN STREET

. November 30, 1988 soLToN. MA 01740

• (508)779 4 711 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter and SER, USNRC to General Electric Company, dated December 27, 1987 (c) NED0-30060, Vermont Yankee Nuclear Power Station, Single Loop Operation, February 1983

Subject:

Proposed Technical Specification Change to Incorporate the 1.04 Fuel Cladding Integrity Safety Limit

Dear Sir:

Pursuant to the Corraissions rules and regulations as set forth in 10CFR50.90, Vermont Yankee Nuclear Power Corporation (VYNPC) hereby proposes the following changes to Appendix A of the Vermont Yankee plant operating license (Reference (a)).

Proposed Change VYNPC will incorporate a revised Fuel Cladding Integrity Safety Limit (FCISL) for use in calculating critical power operating limits in future reload analyses. The NRC has approved the use of a 1.04 FCISL for D-lattice plants with a second successive reload of P8X8R, BP8X8R, GE8X8E, or GE8X8EB fuel types with high bundle R factor (1 04). 1 VYNPC meets these conditions, therefore, the use of a 1.04 FCISL is appropriate. VYNPC intends to leave the current 1.07 FCISL in the Technical Specifications for situations where fuel types not meeting the conditions for the 1.04 FCISL are used.

Changes in the Technical Specifications are proposed to define and reference the FCISL and to adjust the Minimum Critical Power Ratio (MCPR)

Operating Limits. Safety Limit definition 1.1.A is revised to specify that a MCPR equal to or greater than 1.04 (1,05 for single loop operation) for the fuel types and conditions stated above constitutes compliance with the FCISL; otherwise a 11.07 MCPR constitutes compliance with the FCISL. Table 3.11.2 contains the MCPR Operating Limits. This table is revised to reflect the 1.04 FCISL. The proposed change limits in Table 3.11.2 were derived by subtracting .03 from the current limits since the current limits are based on -

a 1.07 FCISL.

Reason for Change Cg Administrative changes are necessary to define 1.04 as a FCISL.

Table 3.11.2 is changed to make use of the 1.04 FCISL for future operation /'

of VYNPS. f 0['

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' Unitsd Stctes Nuclear Rsgulatory Commission Novsmbar 30, 1988

. Attention: Document Control Desk Paga 2 Basis for Change GE has obtained approval to use 1.04 as the FCISL for current GE fuel designs. Reference (b) is quoted as:

"We find Amendment 14 to be acceptable for referencing in license applications to the extent specified and under the limitations delineated in Amendment 14 and the associated NRC technical evaluation. The evaluation defines the basis for acceptance of the amendment.

We do not intend to repeat our review of the matters described in Amendment 14 and found acceptable when the report appears as a reference in license applications, except to assure that the material presented is applicable to the specific plant involved. Our acceptance applies only to the matters described in the Amendment 14."

Amendment 14, as specified above, proposed the upgraded FCISL (1.04) for the loading of current GE fuel designs.

Per Reference (b) the 1.04 FCISL is appilcable to the second successive reloao core of P8X8R, BP8X8R, GE8X8E or GESX8EB GE fuel types with high R factocs (>1.04). l'n particular. Vermont Yankee currently uses P8X8R and BP8X8R with R factors greater than 1.04. Thus, the use of the 1.04 FCISL is appropriate for Vermont Yankee according to the criteria set forth in Reference (b).

For single loop operation, the FCISL is raised by .01 to 1.05. The increase in FCISL accounts for the additional instrumentation uncertainties under single loop operating conditions as discussed in Reference (c).

Safety Considerations The proposed change does not constitute an unreviewed safety question as defined in 10CFR50.59(a)(2). The change has been reviewed by the Plant Operations Review Committee and the Nuclear Safety Audit and Review Committee.

No Significant Hazards Considerations Determination Three standards defined in 10CFR50.92 are used to arrive at a determination that this request for amendment involves no significant hazards considerations. The discussion below addresses these three standards and demonstrates that operating the facility in accordance with this proposed change involves no significant hazards considerations.

1. The proposed change will not involve any significant increase in the probability or consequences of an accident previously evaluated.

No changes are being made to the facility or its equipment so there is no increase of the probability of any previously analyzed event.

For the P8X8R, BP8X8R, GE8X8E. or GE8X8EB with R factors >1.04, the 1.04 FCISL provides the same degree of assurance for fuel cladding integrity during an abnormal event as the 1.07 FCISL does for all other core loadings. Since Vermont Yankee uses and will install these GE fuel types in future reloads, the use of the 1.04 FCISL does not increase the consequences of any event previously analyzed.

n

. United Statss':!ucle.r 4gula.ory Commission Novambar 30, 1988 Attentions koetch Mntr 31 Lesk Page 3

2. The proposed ciange will not create the possibility of a new or different kind M accident from any accident previously evaluated since.the facility is act being changed.

3. The proposed change will not involve a significant eduction in the margin of safety. The use of 1.04 as the MCPR FCISL reflects the utilization of current GE fuel designs and does provide the same margin of safety as 1.07 does with the older GE fuel types as discussed in the SER included with Reference (b).

Fee Determination ~

In accordance with the provisions of 10CFR170.12, an application fee of $150.00 is enclosed.

Schedule of Chang We request that your review and approval of this proposed change be completed by April 1, 1989 in order to ensure that the change is incorporated in the Vermont Yankee Technical Specifications prior to startup of Cycle 14.

This change will be incorporated into the Vermont Yankee Technical Specifications as soon as practicable following receipt of your approval.

We trust that the information above adequately supports our request; however, should you have any questions in this matter, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION W . Murp WPM /0084u V e Pres t nd Manager of Operations Enclosure cc U. S. Nuclear Regulatory Commission Region I Office U. S. Nuclear Regulatory Comission Resident Inspector, VYNPS Vermont Department of Public Services 120 State Street Montpelier, Vermont 05602 Attention: Mr. G. Sterzinger, Chairman STATE OF VERMONT )

)ss OF WINDHAM C0 g Then Fabnally appeare efore me, Warren P. Murphy, who, oeing duly

. sworn, di state t e is a (cePresidentandManagerofOperationsof I

Vermont i nkee g'yy wer Co $ oration, that he is duly authorized to execute a ,nd fil t M fore oing d >cument in the name and on the behalf of j Vermont "ankee Po er Cgroration and that the statements therein are

) ofbi owled e and belief.

true to Ihe bes uclearh O

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Diane McCue NftaryPublic My Comission Expires February 10, 1991

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