ML19312B905

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Forwards Results of Unit 1 Clad Collapse Analysis Per B&W rept,BAW-10084 & Supports three-cycle Operation of Unit 1. Also Forwards Replacement Page 3.11-1 for Tech Specs Deleting Restriction Limiting Unit 1 Operation
ML19312B905
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 07/30/1974
From: Thies A
DUKE POWER CO.
To: Giambusso A
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19312B906 List:
References
NUDOCS 7911270695
Download: ML19312B905 (6)
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Text

f AEC DISEXMmGcG FON wwY 5 0 Y,WFft MTT*1I AL  !

(TDiPORARY FORM) CONTROL NO: 8140 FILE:

FRCH: . DATE OF EOC DATE REC'D LTR TWX PJT OTHER Duka Power Comoany Qcrictte, N.6. 28201 Mr. A.C. Thies 7-30-74 8-5-74 X TO: , ORIG CC OTHER SCiT AEC PDR XXX A. Cicmbusso 1 signed SCIT LCCAL PDR XXX CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

XXX XXX 40 (0-2j270/287 DESCRIPTION: ENCLCSUPJ:S :

Ltr requesting an andt to the tech specs to Proposed changes to tech specs....

dalsto the restriction limiting Oconee Unit di to 7500 effective full Power hours.. .. ..

NOTE Innut on '269 oniv .

(40 cys enc 1 ree'd)

PLANT NAME: Oconee roa Ac IcN/ m ex uTIc5 o-o-'" "

BUTLER (L) SCHWENCER (L) ZIEMANN (L) REGAN (E)

W/ CYS 'W/ CYS W/ CYS W/ CYS CLARK (L) STOLZ (L) DICKER (E)

W/ CYS W/ CYS W/ CYS W/ CYS rARR l_: VAS:ALLc (L' KNIGHTcN (E' W/ CYS W/ CYS W/ CYS W/ CYS KNIEL (L) / PURPLE (L) YOUNGBLGOD (E)

W/ CYS W/7CYS W/ CYS W/ CYS INTERNAL DISTRI5UTION

'# REG FILQ TECH REVIEW DENTON LIC ASST A/T IND ZI HENDRIE GRIMES DIGGS (L) BRAITMAN OCC SCHROEDER GAMMILL GEARIN (L) SALTZMAN

/ MUNTZING/ STAFF MACCARY ~KASTNER GOULBOUR';E (L) 3. HURT CASE KNIGHT BALLARD KREUTZER (E)

GLAMBUSSO PAWLICKI SPANGLER LEE (L) PLANS BOYD SHA0 MAIGRET (L) MCDONALD MOORE (L)(LWR-2) STELLO ENVIRO REED (E) CHAPMAN DEYOUNG (L)(LWR-1) HCUSTON MULLER SERVICE (L) W UBE w/ input SKOVHOLT (L) NOVAK DICKER #3HEPPARD (L) /E. CCUPE

/GOLLER (L) ROSS KNIGHTON SLATER (E) / Schemel P. COLLINS IPPOLITO YOUNGBLCOD SMITH (L) D. THOMPSON (2)

DENISE TEDESCO REGAN TEETS (L) KLECKER A LEG OPR LONG r PROJECT MCR WILLIAMS (E) EISENHUT LAINAS 'Scaletti WILSON (L)

FILE & REGION (Q)

MORRIS STEELE BENAROYA VOLLMER HARLESS 7 gli270@f [

EXTERNAL DISTRI2CTION

/1 - LOCAL POR Walhalla, S.C.

  1. 1 - TIC (.C dR::A!hY) (1)(2)(10)-NATIU','.L LA23 1-ASL3P(E/W SIds, Rm 329) 1-PDR-SA':/LAi:: Y[
  1. 1 - MSIC (3CC:LCAN) 1-32CCIGiAVEN NA! : G l 1 - ASLB 1-W. PENNINGTON, Ra E-201 GT 1-G. ULRIKS?;, 3R:,L 1 - P. R. DAVIS l 1-B&M SWINE 3 ROAD, Rn E-201 GT 1-AGMED (RUTM CUS3:X .

/16 - ACRS C:1:I.; Sent to Sheppard 1-CONSUL?. CTS Rm B-127

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,,c 8-6-74 . NEW". ARK /3LC E/.03s3LC 1-RD..MUELLIR, Sr. E - .

Regulater! Dcchat it!a 1 DUKE POWER COMPANY Powra Buzz.orwo en SouTit Cuchcrr StazzT, CnAntoTTE,N. C. asso A. C. Tu n e s see.... Wg Pes s.ct., P. O. Dox as78 DeGOwtt'ose anO Taansee.gs css July 30, 1974

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/% s ,/ N r Mr. Angelo Giambusso - N',-

Deputy Director for Reactor Projects Directorate of Licensing j8 [-nf O /,,<

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,q g O Office of Regulation D * $7gIl U. S. Atomic Energy Commission '

Washington, D. C. 20545 A Re: Oconee Nuclear Station H(Q\'<g' k.. ,

Docket No -270, -287

Dear Mr. Giambusso:

Oconee Nuclear Station Technical Specification 3.11, " Maximum Power Restriction," limits first fuel cycle operation until supporting analyses and data pertinent to fuel clad collapse under fuel densifi-cation conditions have been approved by the Directorate of Licensing.

On May 31, 1974, Babcock & Wilcox submitted their proprietary report BAW-10084, " Program to Determine In-Reactor Performance of B&W Fuels-Cladding Creep Collapse." The techniques defined in this report were utilized to perform cladding collapse analyses for Oconce Unit 1.

Attachment 1, "Oconee 1 Clad Collapse Analysis," presents the results of this analysis and supports three-cycle operation of Oconee Unit 1.

Pursuant to 10CFR50.59, it is requested that the restriction limiting Oconee Unit 1 to 7500 effective full power hours be deleted from Technical Specification 3.11. Attachment 2 is the proposed replace-ment page 3.11-? for the Oconee Nuclear Station Technical Specifications.

Very truly yours, l A. C. Thies o

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Mr. Angelo Giambusso Page 2 July 30, 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, DPR-47, and DPR-55; 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 ATTEST:

o &, ,

ohn C. GoodmanMr.

i Assistant Secretary Subscribed and sworn to before me this 30th day of July, 1974.

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% 'd i-a . /b $5 L :u'.L/

Notary Public My Commiscion Expires:

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ATTACHMENT 1 '

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OCONEE 1 CLAD COLLAPSE ANALYSIS /

The analysis of Oconee 13-cycle fuel assenblies for cladding creep collapse is complete and indicates no collapse of fuel rod cladding into axial gapped regions of the fuel. .The analysis uns' performed according to Section 4, design analysis procedures, of Topical Report BAM-10084 " Program to Determine .

In-Reactor Performance of 3MT Fuel - Cladding Creep Collapse", May,1974.

Densification was assumed to occur in two ways. The first cethod was to assume densification occured i= mediately at beginning of lif e while the second assumed the fuel densified slowly and was complete at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />.

Section 4 of BAW-10084 specifies that densification be assumed completc in 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, however in this analysis 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> was used for calcclational convience and introduces only a slight conservative effect.

Power histories of the 3-cycle assemblies in the core were used as input for '

cladding temperature determination and in calculating the flux and internal pressure histories. Because of synmetry,one eighth of the core is represent-ative of all 3-cycle assemblics. The appropriate nucicar uncertainty factors were applied to the power histories.

The fuel rod geoncery, initial prepressure level, and the prepressure level after densification were determined from Oconce 1 as-built data.

Attached are the predicted times to collapse (Table 1) and the flux, pin pressure, and cladding temperature histories for the vorst case assembly (Table 2).

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7 TABLE 1

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TDfES TO COLLAPSE. EFPH *

. ASSDfBLY

  • DENSIFICATION ASSU:!ED CO:!PLETE AT:

THIE = 4 TIME = 2400

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. A , >30,000 >30,000 B >30,000 >30,000 -

C >30,000 >30,000 D >30,000' 28,640 E 28,490 25,650 G >30,000 ,28,790 H >30,000 >30,000 -

I >30,000 28,480 3-Cycle ti=e = 21,500 Hours

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  • The e.ight different cases t'lculated rentesent all

.. core locations for Batch 3 when symetry is considered.

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TABLE 2 '

ASSDt3LY F INPUT TIME HISTORY

. DENSIFICATION AT TIME = 0 HOURS TIME, EFPH CLAD TElfP., F PIN PRESSURE, PSI FLUX *n/cb/secx10 I.D. O.D. -

0 605.8* 604.4 - 675

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9.04 96 606.9 605.4 676 . 9.40 1200 608.0 606.5 681 9.58 2400 615.5 613.9 699 11.10 3600 616.6 614.9 706 10.40 4800 615.5 613.9 706 -

10.30 6000 615.6 613.9 711 10.40 6840 617.7 616.0 716 9.43 7439 617.7 616.0 718 9.43 7441 612.8 610.3 704 8.27 7536 610.3 608.1 699 7.83 8040 610.3 608.1 698 7.76 8640 616.0 613.6 712 8.63 -

9840 613.8 611.3 710 8.27 11040 612.8 610.3 712 8.27 12240 616.0 613.6 714 8.12 13800 616.0 613.6 725 8.63 14399 . 598.4 596.8  ; 727 8.63 14401 598.4 596.8 718 6.66 .

14496 598.4 596.8 655 6.66 15000 598.3 596.8 655 ,

6.66 15600 598.4 596.8 655

  • 6.66

'16800 599.4 597.8 655 6.74 18000 600.6 598.9 655 -

6.90 19200 600.8 599.0 660 6.98 20803 643.2 638.6 750 13.48 21403 638.9 635.0 740 12.91 CLADDING CE0}LeTRY:

. Wall Thickness, h = 0.0262 inches Initial Ovality, Wo = 0.62 ils Outside Diameter, O.D. = 0.43 inches

  • Flu.5 greater than 1 MEV at indicated EFPH considering boron , dilution, red position, and refueling. -

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