ML17321A284
| ML17321A284 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/20/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0745P, AEP:NRC:745P, NUDOCS 8411270275 | |
| Download: ML17321A284 (9) | |
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REGULATOR LNFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION'NBR:8rll 1270275 DOC.DATE: 8rl/11/20 NOTARIZED:
NO DOCKET FACIL:50 315 Donald G.
Cook, Nucl ear
- Power Plantr Unit lr Indiana 8
05000315 AUTH BYNAME AUTHOR AFFILIATION ALEXICHiM,P, Indiana L Michigan Electric Co."
RECIP ~ NAME RECIPIENT AFFILIATION DENTONr H ~ R ~
Office, of Nucle'ar Reactor Regulationr =Director
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'SUBJECT!- Supp'1 s 840613 1 tr w/conf irmatory, cal cul at> ons per formed on, inter nal r.rod pressures in fuel suppl ied by Exxon Nuclear Car per-841031 telcon Tech Spec change
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 November 20, 1984 AEP:NRC:0745P Donald C. Cook Nuclear Plant Unit No.
1 Docket No. 50-315 License No. DPR-58 ADDITIONALANALYSIS SUPPORTING TECHNICAL SPECIFICATION CHANGE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
This letter and its attachment supplement letter AEP:NRC:0745M, dated August 23, 1984.
As requested during an October 31, 1984 telephone conference call with members of your staff, we have had confirmatory calculations performed on internal rod pressures in fuel supplied by Exxon Nuclear Company (ENC).
These calculations were to be performed with power levels at the Technical Specification limit of FA H up to a peak pellet burnup of 48,000 MWD/MTU, or if this resulted in the rod internal pressure exceeding the system
- pressure, to use power levels which bound the measured and predicted power levels.
The internal rod pressure calculated with the Technical Specification limit of F A H throughout its entire burnup exceeded the system pressure.
However, it is physically impossible for a single rod to run at the Technical Specification limit throughout its entir'e burnup.
A power history which bounds the ENC fuel currently in the Donald C. Cook Unit 1 reactor produced a calculated rod internal pressure of 1903 psia at a rod burnup of 43,700 MWD/MTU.
This result is less than the system pressure of 2250 psia and corresponds to a peak pellet burnup of 48,000 MWD/MTU, when calculated on a best estimate basis.
The attached letter ENC-AEP/401, dated November 13, 1984, discusses these calculations in more detail.
The current burnup limit is expected to be reached. on December 2,
1984 based on an updated calculation.
Without the burnup extension requested in letter AEP:NRC:0745M, we would be unable to continue operation of Cycle 8
because of the current requirements of Technical Specification 3.2.2.
These analysis changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meeting.
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Mr. Harold R. Denton AEP:NRC:0745P In compliance with the requirements of 10 CPR 50.91(b)(1),
a copy of this letter and its attachments have been transmitted to Mr. R.C. Callen of the Michigan Public Service Commission.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours,
(~(sy
. Alexich Vice President JLB/bjs Attachment cc: John E. Dolan W.G Smith, Jr. - Bridgman R.C. Callen G. Charnoff NRC Resident Inspector Bridgman G. Bruchmann
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ACHNENT.TO:
AEP:
NRC: 0745P.
$ pN hkJCLEAR CONIPANY,Inc.
NO - iONh Avenue N.E.. C-00777, Bellevue, Washington 98009, Teiephone (206) 4S3-4300
-:, November 13; 1984
.:-'". 'ENC-AEP/401 Nr. George
- John, Sr. Engineer Nuclear Materials 5 Fuel Management Indiana 5 Michigan Electric Company c/o Anerican Electric Power one Riverside Plaza
- Columbus, OH 43215
Subject:
D.C.
Cook Unit 1 Rod Internal Pressures
Dear Hr. John:
Attached is a description of the"rod i'nternal.pressur'e"analyses done in response to the NRC question on the Exx'on:,.Nuclear fuel"in O.C.
Cook Unit 1.
In the -analysis, the~a'pproved version of ROOEX2 was used to calculate the internal fuel rod pressures for rods having the maximum burnup and bounding power histories supplied by AEPSC.
In @)th. cases, the
.internal pressure,was less.
than the;system, prdss.
e.and therefore was accept ab Ie.
~ I If there are questions, or if I cari be further help, please 'call me.
Sin rel
/
I H.
G.
Shaw Contract Admin strator HGS:RAC:naa AFFILIATEOF EXXON CORPORATlON
ATTACHHEliT TO:
AEP:
NRC:
0745P Th'e end-of 1ife fuel rod inter nal pressures were calculated for two O.C, Cook Unit 1 cases provided by AEPSC,with the approved ROOEX2 code using the methodology described in Reference 1.
The f~rst case was for the Exxon Nuclear fue1 which would see the maximum burnup and-the second case was for a bounding, composite power history.
For the bounding case, the peak LHGR for any of the Exxon Nuclear fuel currently in Cycle 8 was used, regar dless of where the peak occurred.
Both histories were developed from th in-core flux traces and the projected Cycle 8 history.
Both his o
'stries e
also include a factor of 1.04 to account for measurement uncertainty.
(
third case was calculated in which the actual power history of the peak power rod was uniformly increased such that the maximum power during its irradiation reached the Technical Specification limit.
For this unreal-istic case, in which the peak rod exposure of 43,700 MWD/MTU was reached cput the middle of the third cycle, the internal rod pressure signi.
ficantly exceeded the system pressure.)
"The resu'its of the ana.lyses were. that the maximum burnup rod had an internal pressure of 1453 and the boundir'ig case rod hard'n 'inter nal pressure of 1903 psia.
Both satisfy the des,'ign cr iter ion of being less than system pressure.
Therefore, the end-of-'life rod internal pressure is satisfactory for peak rod exposures of up,to.43,700 MWD/MTU (as described in Reference 2).
s x,,
2.
XN-NF-81-58{P)(A), Revision 2,
and Supplements 1
and 2,
"RODEX2:
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11,'"E Co., March 1984.
AN-NF-84-25{P), "Mechanical Design Report Supplement for D.C.
Cook Unit ttxtended Burnup Fuel Assemblies,"
Exxon nuclear co.,
August
- 1984,
7
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