ML19207B138

Discusses Tech Spec Change Request 83 Re Prepressurized 8x8R Fuel.Changes Requested for Incorporation Into Tech Specs by 791103

ML19207B138
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	08/21/1979
From:	Vandenburgh D VERMONT YANKEE NUCLEAR POWER CORP.
To:	Office of Nuclear Reactor Regulation
References
PC-83-1, NUDOCS 7908230436
Download: ML19207B138 (6)

Text

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~!roposed Change No. 83 Q VERMONT Y AN KEE NUCLEAR POWER CORPORATION L*N>N SEVENTY SEVEN GROVE STREET PC-83-1 RUTLAND, VeasoxT osvon B.3.2.1 REPLY TO:

ENGINEERING OFFICE TURN?lKE RO AD August 21, 1979 WESTBORO, M ASS ACHUSETTS 015 81 TELEPHONE 617-3 6 6- 9 0 f t 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) " Generic Reload Fuel Application," General Electric Licensing Topical Repert, NEDE-240ll-P-A (3) Letter, Thomas A. Ippolito, DOR, to Richard Gridley, GE, MFN-ll7-79, April 16, 1979.

Subject:

Technical Specification Changes to Prepressurized 8x8R Fuel

Dear Sir:

Pursuant to Section 50.59 of the Commission's Rules and Regulations Vermont Yankee Nuclear Power Corporation hereby proposes the following changes to Appendix A, the Technical Specifications.

PROPOSED CHANGE:

Table 3.11-1G, page 180-a5, "MAPLHGR Limits," is atended to include pre-pressurized 8x8 retrofit fuel type, P8DPB289. Also, Table 3.11-2, "MCPR Operating Limits," page 180-o3, is amended to include MCPR operating limits for prepressurized 8x8 retrofit fuel, and to increase the MCPR operating limits at certain cycle exposures for other 8x8 fuel types. A revised Tabic 3.11-1G and Table 3.11-2 are attached.

REASON FOR CHANGE:

Prepressurized 8x8 retrofit fuel will be used by Vermont Yankee beginning with Cycle 7 operations. The introduction of this fuel type will require the changes to the Technical Specifications outlined above.

BASIS FOR CHAdGE:

A standard " Supplemental Reload Licensing Submittal" has been provided to Vermont Yankee by General Electric Company for Cycle 7 operations. A review of the results of the analysis presented in that report, when compared to the current (Cycle 6) results, revealed the need to make the changes to the Technical Specifications identified above. 'M 238 The transient results which form the basis for the proposed change to the MCPR cperating limits are sunnarized in Table 1. The MCPR operating limits shown on the cevised Table 3.11-2 were detartined by choosing the cost limiting transient change in critical power ratio (LCPR) fron Table 1 for the fuel type, exposure range, and Red Block Monitor setpoint of interest. The addition of the limiting LCPR to the fuel cladding integrity limit MC.R of 790.8230 s

United States Nuclear Regulatory Commission August 21, 1979 Attention: Office of Nuclear Reactor Regulation Page Two  !

1.07 results in the MCPR operating limit.

The inclusion of the prepressurized 8x8 retrofit in Table 3.ll-1G,

'71APLEGR Limits," is based on evaluations by General Electric that show that the effect of prepressurization of a given fuel type is to reduce the calculated peak cladding temperature because of tha improvement in the fuel-to-cladding gap thermal conductivity. Conversely, the MAPLEGR limits calculated for unpressurized 8x8 retrofit fuel will be conservatively bounding for the equivalent prepressurized 8x8 retrofit fuel.

SAFETY CONSIDERATIONS:

The analyses supporting these proposed changes were based on the standard reload analysis methods as presented in General Electric's Generic Reload Fuel Application (Reference 2), The use of prepressurized 8x8 retrofit fuel in Vermont Yankee's core is not considered to involve an unreviewed safety question, and is supported by the NRC staff safety evaluation of proposed amendments to the above Generic Reload Fuel Application (Reference 3).

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

FEE DETERMINATION:

This letter provides information that involves approval of a single safety issue and is deemed not to involve a significant hazards consideration.

For these reasons, Vermont Yankee Nuclear Power Corporation proposes this evaluation to be Class III. A payment of $4000.00 is enclosed.

Vermont Yankee Nuclear Power Corporation believes that the NRC revised fee schedule is illegal. Vermont Yankee Nuclear "ouer Corporation is aware that this f ee schedule is being contested before the U. S. Court of Appeals for the Fifth Circuit and, therefore, submits the enclosed 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:

The proposed changes are requested for incorporation into the Technical Specifications no later than November 3, 1979, which is the currently planned startup date for Cycle 7.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION

. E. Vandenburgh Vice President BCS/stw r, ,

Enclosure O

United States Nuclear Regulatory Commission August 21, 1979 Attention: Office of Nuclear Reactor Regulation Page Three COSDIONWEALTH OF MASSACIIUSETTS)

)ss.

COUL'Y JF WORCESTER )

Then personally appeared before me, D. E. Vandenburgh, who, being duly sworn, did state that he is Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and fue the foregoing request in the name and on the behalf of Vere ,at Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

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p. Robert II. Groce y 4+

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Table 3.11-1G MAPLHGR, PCT, Oxidation Fraction Versus Exposure, Fuel Type 8DFB289 and P8DPB289 l Average Planar Exposure MAP 11LGR P.C.T. Oxidation (Mk'Dd / t) (kw/ft) (Deg-F) Fraction 200.0 11.2 2126 0.027 1000.0 11.2 2119 0.026 5000.0 11.8 2178 0.030 10000.0 12.0 2185 0.030 15000.0 12.1 2200 0.032 20000.0 11.8 2187 0.031 25000.0 11.3 2120 0.025 30000.0 11.1 2095 0.023

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Table 3.11-2 MCPR OPERATING LIMITS Value of "N" Fuel Ty g in Exposure Range RBM Equation (1) 7x7 8x8 8x8R P8x8R BOC to EOC-2 GWd/t 42% 1.23 1.27 1.22 1.27 41% 1.23 1.24 1.22 1.24 d40% 1.23 1.23 1.22 1.22 EOC-2 GWd/t to EOC-1 GWd/t 42% 1.23 1.27 1.23 1. ?. 7 41% 1.23 1.24 1.23 1.24

_40% 1.23 1.23 1.23 1.24 EOC-1 GWd/t to EOC 42% 1.23 1.28 1.28 1.30 41% 1.23 1.28 1.28 1.30

_40% 1.23 1.28 1.28 1.30 (1) The Rod Block Monitor trip setpoints a.e determined by the equation shown in Tabic 3.2.5 of the Technical Specifications.

180-o1 g .

P. C. 83 Table 1 Transient Analysis Summary ALL TRANSIENTS ANALYZED AT 104.5% POWER, 100% FLOW 4 - a a Core Wide $ Q/A Ps1 Pv ACPR Transient Exposure (%NBR) ('CiER), (PSIG) (PSIG) 8x8 8x8R P8x8R Load EOC7 290.1 117.5 1202 1238 0.21 0.21 0.23 rejection without EOC7 -

bypass 1 GWd/t 239.3 113.9 1193 1228 0.16 0.16 0.17 EOC7 -

2 GWd/t 182.5 107.2 1175 1211 0.06 0.06 0.06 Turbine EOC7 288.9 117.4 1205 1240 0.21 0.21 0.23 trip without bypass EOC7 -

1 GWd/t 236.8 113.7 1196 1231 0.16 0.16 0.17 EOC7 -

2 GWd/t 172.2 107.3 1178 1213 0.06 0.06 0.06 Loss of 100 F FW BOC7 to Heater EOC7 124.0 123.5 1020 1066 0.15 0.15 0.15 Feedwater Controller BOC7 to Failure EDC7 116.4 110.2 1021 1065 0.05 0.05 0.06 Local Rod Withdrawal Error (With Limiting Instrument Failure)

Transient Summary Rod Block A CPR*

Reading ** 8x8 8x8R P8x8R 104 0.12 0.09 0.11 105 0.14 0.10 0.13 106 0.16 0.11 0.15 107 0.17 0.12 0.17 _

108 0.20 ' O.14 0.20 109 0.24 0.16 0.25 110 0.27 0.17 - 0.27

• Based on estimated initial MCPR of 1.28 (8x8, 8x8R) and 1.37 (P8xbR).

• • Indicates setpoint selected.

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