ML19276E477

Requests Change to App a of Tech Specs to Include Max Critical Power Ratio Operating Limits Beyond Cycle Exposures of end-of-cycle 6 Minus 2GWD/T.Forwards Class 3 Amend Fee

ML19276E477
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/05/1979
From:	Vandenburgh D VERMONT YANKEE NUCLEAR POWER CORP.
To:	Office of Nuclear Reactor Regulation
References
PC-73-1, WVY-79-30, NUDOCS 7903140258
Download: ML19276E477 (6)

Text

'

Proposed Change No. 73 Supplement No. 1 4TERMONT YAN KEE NUCLEAR POWER CORPORATION SEVENTY SCVEN OROVE STRECT B.3.2.1 RUTLAND, VERMONT 05701 REPLY TO:

ENGINEERING OFFICE TURNPIKE ROAD WESTBORO. M ASSACHUSETTS 01581 TELEPHONE 617 366-908I WY 79-30 PC-73-1 March 5, 1979 United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Office of Nuclear Reactor Regulation

Reference:

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

(2) Letter, D. E. Vandenburgh (VYNPC) to USNRC, Proposed Change No. 73, WY 78-59, June 21,1978 (3)

" Generic Reload Fuel Application," General Electric Report NEDE-24011P, Amendment 3, dated March 1978

Subject:

Completion of Reload 5 Licensing Submittal Pursuant to Section 50.59 of the Commission's Rules and Regulations Yankee Atomic Electric Company hereby proposes the following modification to Appendix A to the Technical Specificaticns.

PROPOSED CHANGE:

Table 3.11-2, "MCPR Operating Limits," page 180-01 is amended to include MCPR operating limits beyond cycle exposures of end-of-cycle 6 minus 2GWD/T (EOC6 - 2GWD/T). A revised Table 3.11-2 is attached.

REASON FOR CHANGE:

The original Reload 5 Licensing Submittal (Reference 2) did not contain EOC6 MCPR operating limits.

It was expected that a new submittal, based on measured scram times, could be submitted with sufficient time for re-view before it was needed in Cycle 6.

However, the analytical work necessary to support such a submittal is not yet available. Therefore, in order to assure that there is some documented basis for continued opera-tion beyond EOC6 - 2GWD/T, an analysis of the limiting overpressurization transients, based on the current technical specification scram times, is hereby submitted. A new submittal, based on measured scram times, will be made when the new analysis is available.

BASIS FOR CHANGE:

The analysis supporting the proposed change is based on NRC approved methods (Reference 3) and the current technical specification scram times.

The two most limiting overpressurization transients, load-rejection-without-bypass (LRW/0LP) and turbine-trip-without-bypass (TTW/0BP), were analyzed 7903140268

[

United States Nuclear Regulatory Commission March 5, 1979 p.ttention: Office of Nuclear Reactor Regulation Page 2 at EOC6-lGWD/T and EOC6 core conditions, which were defined in Attachment 2 of the original Reload 5 Submittal (Reference 2).

In order to provide a comparison with other transients and to arrive at the operating limit MCPR's, Tables 6.1 and 7.3 of Attachment 2, Reference 2, were amended to include the results of the LRW/0BP and TTW/0BP analyses.

The amended Tabl.es are attached.

In summary, the results show that the currsat technical specification MCPR operating limits can be extended in range out to EOC6-lGWD/T, and that from that point out to EOC6, the 7x7 and 8x8 limits should be increased to 1.21 and 1.27, respectively.

SAFETY CONSIDERATIONS:

The analyses supporting the proposed change are based on NRC approved methods (Reference 3) and the current technical specification scram times; therefore, there are no unrevieued safety questions involved.

This submittal has been reviewed by the Vermont Yankee Nuclear Safety Audit and Review Committee.

FEE DETERMINATION:

This proposed change requires an approval that involves a single safety issue and is deemed not to involve a significant hazards considera-tion.

For these reasons, Vermont Yankee Nuclear Power Corporation proposes this change as a Class III Amendment. A payment of $4,000.00 is enclosed.

Vermont Yankee Nuclear Power Corporation believes that the NRC revised fee schedule is illegal. Vermont Yankee is aware that this fee schedule is being contested before the U.S. Court of Appeals for the Fifth Circuit and therefore submitted the referenced fee under protest without waiving its right to contest the validity of this fee or the entire NRC fee schedule, and without waiving any right to recover, in whole or in part, all fees paid or to be paid under the invalid fee schedule.

SCHEDULE OF CHANGE:

Given the unexpected fuel problems at Vermont Yankee, we solicit NRC approval of this proposed change supplement on or before April 2,1979, to ensure continuation of scheduled operation.

Should you have any questions, please feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION D. E. Vandenburgh Vice President Enclosure COMMONWEALTH OF MASSACHUSETTS)

)ss.

COUNTY OF WORCESTER

)

March 5, 1979 Then personally appeared before me, D. E. Vandenburgh, who, being duly sworn did state that he is Vice President of Vermont Yankee Nuclear

United States Nuclear Regulatory Commission March 5, 1979 Attention: Office of Nuclear Reactor Regulation Page 3 Power Corporation, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

A,,,,...?..o %,,.

Hw

.'+-

.'. +

Robert H. Groce Notary Public

% }>

My Commission Expires September 14, 1984

-4 J,

>u 6

..J >

cs

. v, >q rb%,/

s.

f o

o

. A

't v r s.....,4%

g,e,

.~

~

Table 3.11-2 MCPR OPERATING LIMITS Value of "N" MCPR Operating Limits Over the Exposure Range Noted in RBM Equation (1)

BOC to EOC - IGliD/T EOC-IGWD/T to EOO 4

7x7 8x8 8x8R 7x7 8x8 8x8R 40%

1.23 1.22 1.24 1.23 1.27 1.27 39%

1.23 1.22 1.22 1.23 1.27 1.27 Note:

(1) The Rod Block Monitor trip setpoints are deternined by the equation shown in Tabic 3.2.5 of the Technical Specifications.

180-01

Tabic 6.1

SUMMARY

OF RESULTS (ACPR)

LIMITING ABNORMAL OPERATIONAL TRANSIENTS ACPR Transient Exposure 7x7 8x8 8x8R Loss of 1000F FW Heater BOC to EOC 0.13 0.15 0.15 4

FW Controller Failure BOC to EOC 0.05 0.07 0.07 Rod Withdraw 1 Error (106% RBM)

BOC to ECC 0.15 0.17 (105'i RBM)

BOC to ECC 0.13 0.15 Load Rejection Without Bypass EOC6 0.14 0.20 0.20 EOC6-1GWD/T 0.10 0.15 0.15 Turbine Trip Without Bypass EOC6 0.14 0.19

- 0.19 EOC6-1GWD/T 0; 10 0.14 0.14

• 7x7 fuel is located only on core periphery and is not liciting, therefore, response is not given.

Table 7.3 TRANSIENT DATA SID%iRY ALL TRANSIENTS ANALYZED AT 104.5% POUER, 100% FLOW 4

Q/A Pgt Py Transient Exposure

(% NBR)

(% NBR)

(PSIC)

(PSIG)

Load rejection without bypass EOC6 288.6 116.9 1199 1235 EOC6-1G:lD/T 249.2 113.9 1191 1227 EOC6-2GWD/T 112.9 104.5 1151 1188 Turbine trip without bypass E006 275.2 116.2 1201 1237 EOC6-1CWD/T 231.7 112.9 1193 1228 E0C6-2GUD/T 114.5 104.5 1155 1191 Loss of 100 F FW IIcater BOC6-EOC6 124.0 123.2 1021 1069 Fecdwater Controller Failure BOC6-EOC6 118.7 110.8 1023 1070

.