ML19312B966

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Forwards Proposed Tech Spec 3.5.2 Revising Rod Withdrawal Limits Per Util 731130,1231 & 0125 Ltrs & Jf Mallay 740221 to a Schwencer for Units 1 & 2.Also Forwards Graph Re Specific Heat of U Dioxide
ML19312B966
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/08/1974
From: Thies A
DUKE POWER CO.
To: Giambusso A
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19312B967 List:
References
NUDOCS 7911270748
Download: ML19312B966 (5)


Text

AEC DIS' ~BUTION FOR PART 50 DOCTET MATF

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(TEMPORARY FORM)

CONTROL NO: 2002 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Duka Power Company Charlotte, N. C. 28201 3-8-74 3-11-74 X

A. C. Thies TO:

ORIG CC OTHER SENT AEC PDR X

A. Gia::ibusso 3 signed SENT LOCAL PDR X

CLASS UNCLASS PROP INFO INPUT NO CYS REC'D NO:

XXX 40 0-26 270 DESCRIPTION:

ENCLCdURES:

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-73, & 1-25-74 ltr...... furnishing addl info

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March 8, 1974 g

Mr. Angelo Giambusso IC Deputy Director for Reactor Projects

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Washington, D. C.

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3 A et Re: Oconee Nuclear Station

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Units 1 and 2 4

Docket Nos. 50-269 and -270

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Dear Mr. Giambusso:

Please refer to my letters of November 30, 1973, December 31, 1973, and January 25, 1974 to you and Mr. J. F. Mallay's letter of February 21, 1974 to Mr. Al Schwencer.

In my letters of November 30 and December 31, we requested certain changes to the Oconee Units 1 and 2 Technical Specifications. These changes involved Technical Specification 3.5.2 and principally revised rod withdrawal limits for both Units 1 and 2.

Subsequently, upon discovery by B&W of a change in the calculation of the specific heat curve for uranium dioxide fuel, we requested in my letter of January 25, 1974 that you hold in abeyance your review of the requested technical specification changes. B&W has since advised us that they have issued a new specific heat curve and incorporated this curve into the af fected transient codes for plant safety analyses. A new specific heat curve is attached.

The safety implications of higher values of specific heat were investi-gated by re-analysis of the various transients using the new specific heat curve. The slower transients were unaffected. The rapid transients investigated yielded the following results:

1.

For the rod. ejection transient, DNBR was not noticeably affected.

0 The maximum cladding temperature decreased by 70 F to 1000F and the 0

maximum fuel temperature decreased by 200 F to 300 F.

2.

For locked rotor transient, the DNBR was not noticeably affected. The maximum cladding temperature increased by 5 F to 15 F and the fuel 2002

i Mr. Angelo Giambusso Page 2 March 8, 1974 temperatures fell off at a slower rate. The overall effect of this change is insignificant.

3.

For the four-pump coastdown transient, the increased specific heat value had no significant effect.

4.

For emergency core cooling analysis, the impact of the specific heat re-vision on safety limits was to lower some portions of the allowable linear heat rate by up to 0.65 kw/ft. The attached curve identified as "LOCA Limited Maximum Allowable Linear Heat Rate" determines the allowable linear heat rate as a function of elevation in the core. The revised linear heat rate is in compliance with the interim acceptance criteria.

The revised LOCA limits were determined by repeating the Oconee 2 calcu-lations. The allowable heat rate curve for Oconee 2 is lower by.65 kw/ft at the six foot elevation but is unchanged at the 10 foot elevation.

5.

For the reactor building pressure analysis, the initial stored energy in the core is increased by less than one million BTU's and the calcu-lation of maximum reactor building pressure shows no change.

A reanalysis of the Oconee 1 and 2 operating margins with respect to the revised LOCA limit curve was performed by B&W using the procedures developed in BAW-10078. This analysis shows that the revised LOCA limit could have been exceeded assuming licensed design conditions early in plant life.

However, based on Oconee 1 and 2 operation, these design conditions are known to be conservative and to exceed their limits and would have required the simultaneous existence of several " worst case" uncertainties. A review of operating data shows that the actual experienced quadrant power tilt for Unit 1 and the achieved power level for Unit 2 preclude the Interim Acceptance Criteria being exceeded.

In order for Oconee 2 to operate within the revised LOCA limit and to more accurately reflect the operating characteristics of Oconee 1 and 2 experience to date, revised te 12ical specifications are attached. As identified in my letter of Nove.ber 30, 1973, increased flexi-bility in power maneuvering over the existing approved technical specification is provided by a reduction in quadrant power tilt. The attached technical specifications for Unit 2 supersede those attached to my letter of December 31, 1973.

With regard to Oconee 1, the technical specifications submitted for your approval by my letter of November 30, 1973 were requalified with the revised LOCA limit. This requalification used the procedures of BAW-10073; the method identified as Attachment 1 in my November 30, 1973 letter; and also the effects of 92 effective full power day burnup on the Oconee 1, Cycle 1 core. The results of the requalification verify the acceptability of the proposed technical specification; therefore, approval and implementation is requested for the continued operation of Unit 1 through the completion of the first fuel cycle.

For your convenience, additional copies of the Unit 1 technical specification are attached.

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Mr. Angelo Giambusso Page 3 March 8, 1974 For your information, Oconee 3 technical specifications have been revised using the new LOCA limit curve and the procedures developed in BAW-10078.

These technical specifications will be submitted for your review by a Final Safety Analysis Report amendment in late March,1974.

We would appreciate receiving approval to revise the Units 1 and 2 technical specifications as soon as possible.

In order to allow sufficient time to make appropriate procedure changes and inform all operators of the technical specification revision, please make the effective date of technical specification change one week from your date of notification to us.

Very truly yours,

-uure-A. C. Thies ACT:vr Attachments O

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Mr. Ange..o Giambusso Page 4 March 8,1974 A. C. THIES, being duly sworn, states that he is Senior Vice President of Duke Power Company; that he is authorized on the part of said company to sign and file with the Atomic Energy Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38 and DPR-47; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

A. C. Thies, Senior Vice President A

ohn C. Goodman, Jr.

Assistant Secretary Subscribed and sworn to before me this 8th day of March, 1974.

j st Notary Public My Commission Expires:

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