ML17325A425
| ML17325A425 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/28/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17325A427 | List: |
| References | |
| AEP:NRC:0940H, AEP:NRC:940H, NUDOCS 8711030539 | |
| Download: ML17325A425 (10) | |
Text
I
~
T W'I~,
f ACCESSION NBR FAG IL: 50-315 AUTH. NAME ALEX ICHOR M. P.
RECIP. NAME l lURLEYt T. E.
P I
REGULATOR NFORMATIQN DISTR IBUTlON TEil (RIDS) 8711030539 DOC. DATE'7/10/28 NOTARIZED:
NO DOCKET ¹ Donald C.
Cook Nuclear Poeer Planti Unit ii Indiana 05000315 AUTHOR AFFILIATION Indiana
& Michigan Electric Co.
RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Foruiards info re plant Circle 10 reloads including Westinghouse peaking factor limit rept for cycle
& reload SER. Fee paid.
DISTRIBUTION CODE: '*00ID COPIES RECEIVED: LTR i
ENCL
(
SIZE:
TITLE:
OR Submittal:
GeneTal Dist'bution REC lP IENT ID CODE/l4AME PD3-3 LA WIQGINGTONT D INTERNAL'RM/DAF/LFMB NRR/DEST/CEB NRR/DEBT/RBB
/ILRB REQ FILE 01 EXTERNAL:
EG&G 'BRUBKEi S NRC PDR COP IES LTTR ENCL 1
0 1
1 0
1 1
1 1
1 1
1 1
1 REC IP IENT ID CODE/NAME PD3-3 PD NRR/DEST/ADS NRR/DEBT/MTB NRR/DQEA/TBB OQC/HDBi REB/DE/EIB LPDR NBIC COPIES LTTR ENCL 5
5 1
1 1
1 1
1 0
1 1
1 1
1 1
TOTAL NUMBER OF COPIEB REQUIRED:
LTTR 21 ENCL 18
0
~
I,
~ ~
b
Indiana Michigan Power Company One Summit Square P.O. Box 60 Fort Wayne, IN 46801 219 425 2111 INEMSINAl MCMEGQM
~ PQWElR AEP:NRC:0940H Donald C.
Cook Nuclear Plant Unit 1 License No. 50-315 Docket No.
DPR-58 UNIT 1 CYCLE 10 PEAKING FACTOR LIMIT REPORT AND RELOAD SAFETY EVALUATION REPORT U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley October 28, 1987
Dear Dr. Murley:
The purpose of this letter is to transmit information related to the D.
C.
Cook Unit 1 Cycle 10 reload.
The information includes the Peaking Factor Limit Report for the cycle, as well as the reload safety evaluation report (RSER), both of which were prepared for us by Westinghouse Electric Corp.
(Westinghouse),
our D.
C.
Cook Unit 1 fuel supplier.
Peakin Factor Limit Re ort Attachment 1 to this letter contains the Cycle 10 Peaking Factor Limit Report.
The report provides the burnup-dependent V(Z) function for the cycle calculated for a I band of +
5% 'at a core power level of 3250 MWt.
The function is provided for ten ranges of burnup from beginning of cycle to end of cycle.
Amendment 74 to the Unit 1 Technical Specifications (T/Ss),
issued September 20, 1983, required us to submit a Peaking Factor Limit Report by 60 days prior to the scheduled start-up date for the new cycle.
In a letter dated May 1, 1987 (Attachment 2), the NRC modified this requirement for Unit 1 Cycle 10 by allowing us to submit the report 30 days after initial criticality.
Transmittal of the Peaking Factor Limit Report fulfills this requirement for Cycle 10.
87ii030539 87i028 PDR ADOCK 050003i5 P
PDR'ee(D 43jch'<~
~gag-OAFb goo/
ill
0 "I
I I,,
Pg l~
P I
4 I
t
% ~
-4yr
~ ~~'g 4gw ~ ~,
II
~
A
~ '
Dr. T.
E. Murley AEP:NRC:0940H Reload Safet Evaluation Re ort For your staff's information, we have enclosed as Attachment 3 a copy of the RSER for Unit 1, Cycle 10.
The Unit 1 Cycle 10 reload was accomplished under the provisions of 10 CFR 50.59, with the exception of the T/S changes which were granted for the reload in Amendment ill to the Unit 1 T/Ss on June 10, 1987.
The RSER describes the Unit 1 Cycle 10 core and summarizes the safety reviews which were performed by Westinghouse in support of the reload.
Pursuant to the requirements of 10 CFR 170.12(c),
we have enclosed a
fee of $150.00 for this submittal.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M.
. Alex ch Vice President cm Attachments cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
Attachment 1 to AEP:NRC:0940H Unit 1 Cycle 10 Peaking Factor Limit Report
1 j
l I
l
.'s
\\
e o
}IN NldL N4 RlÃf fo Oo00000 Ro 0.200N
- 3. 0.400N
- i. OebQNO 5o OeSXNO 1.0000 1.2000 be t.CQN 9
1obNO 10o 1.8000 11o Z.MOO 12r RoRNO 13o 2e4NQ t4.
2.50N 15.
2.4000 fio 3oNN 1Te 3.2000 18.
3.CQN 19o 3.5DN Se8000 2 le 4.0NO 22o 4.20 23o 4.4000 Rie CebON 25e 4oNOQ Rbo S.NN 27o 5,20N Zbo 5oCNQ 29r 5.5NO 30o 5o80N 3lo deNN 32>>
d.20 33r bAON 3io bodQN 35.
be MOO 3de
'7.0000
'7o ToRDN 7.4000 39e 7.5000 CO.
TodQN 41.
4.0000 CRo dr2000 43, 8.4000 CC.
4.5QN 45.
dedQN Cbe 9o0000 47.
9o 2000 Cbe P.CON C'Po 9.5000 50.
9.I}N 51.
10oQQO
$2o 10.200 53o 10.400 54.
10.5N 5$.
1D.800 Sbo 11.000 57o 11.2N Sbo 11e400
$ 9e 11.500 60e 11 AN bio 12.0N
~
r ATTACHHKNT CZ) rNC1lo}
/NTU) 6NO 80N 1NOO 12ND 14QN 8NO 10000 fRON 14NO IQL 1 oOQN 1oNQO 1.NN 'loDIN 1oNOO 1.NOQ lo0000 toQQN 1.0Q foNOO 1oONO toOQQO 1.0QN teDON loQQN lo0000 1.0000 loN}0 t.N}00 1.QOQO 1 rOON 1.NOO 1,0000 1.0000 1 ~ 0000 1.0000 1o0000 1 o0000 1 QQN 1oQQQD 1.0792 1o0854 to0909 1.10bt 1 ~ l081 1e0796 1.0847 1.0897 fot048 1.1048 1o0793 1 0836 1 0881 1o1019 1 ~ 10'l9 tr0784 1oMZZ to0852 1.0984 to0984 fe077t to0804 to0839 te0944 te0944 le0754 fo0782 1 081'l 1 0898 1 ~ 0898 1o073$ te0756 1 e0779 1rQOIT 1e084'F 1e0712 1.0727 1A744 1.0792 1.0T92 fo0593 1.0694 1.07N fe0733 1.0733 1.D670 1 e0670'1.0560 1.0669 to0669 1.0647 'lo0647 1.0521 teMRt to0621 fr0632 1 0652, 1 0604 1o0619 1 0619 to0627 1.0527 t.MtO 1 0556 1.0566 1.0639 te0639 tA624 te0733 1 o0733 t.M$5 fe0555 1.0538 te0804 te0804 1r0565 1.0565 f.MSO to0872 'le0872 fA675 fo0675 1.0559 1.09%< te0936 f.0681 f.Mlt to0565 1.0995 1.0995 1 0685 foONS to0669 tof048 f.f048 1 o0685 te0685 1.Mdb tet094 'to1094 to0682 fo0682"t M68 t.tt32 tott32 1 0674 t.M74 1 0685 1 1164 1 1164 1 o0663 toOK5 fo0710 1 ~ 1187 1e118F t.MSL fo067f 1,0731 'l.1200 1 ~1200 1.Mdb fe0685 fo0744 f.f201 1e1201 fo0676 fA692 1.075f fett91 f.tf9f fe0679 1 o0693 '1.0751 1.1169 foft69 feM76 foOdN fo0744 lelf34 1 ft34 lo0667 toMTS fo0730 fet087 1 'l08F t.MSt fo065% to0705 1.1026 t.f026 1.0628 1eM49 fo058t 1.0953 1.0953 te0605 1o0540 1.0669 1.0867 1o0467 1e0$ 96 loD624 1.0649 1.07dF 1 0767 1 0581 1e060'l 1.Q5ZZ te06?$ 1.0675 1,0558 1.NF1 1.0588 1.0612 1.061R 1.0529 to0534 1 0548 1.0580 1.0580'.0492
'l.DCVZ 1.0499 1ASTO teQSTQ 1.0445 1.0CC5 1.0CCZ 'lo0584 1.0584 1.DCZb 1.0426 1.0455 1,0540 1.0d40 1 DC53
'l e0453 1 o0507 1 0713 1 oDT13 1.NOC 1.0$ QS 1.0$ $9 1.0784 1.0784 1.0547 1o05$ 1 1o0510 1.0452 t>>0452 1.0590 1.0596 1.0557 1.0917 1.0917 1e0529 toMB9 1.0702 to09FF 1.0977 te0555 'l.0674 1.0743 tot033 t.f033 1.0596 1AT14 1.0780 t.f082 fot082 1.0721 1eOTik 1o08'l2 le 1'125 1.1125 1e0741 fo0775 1.0840 fottbb tottd8 1.0756 fe0798 tA853 1.1204 1.1204 1.0000 toNOO 1eNQQ 1 oOO}Q 1o0000 1.0000 1.00N to NQO le QQN t.0000 1.QQN loQQN 1 o0000 'l.0000 leDNO 1
QOQQ 1 oOON ioNN 'lAQQQ teNOO toQNO. to0000 1 0000 1.0000 1.0000 1.0000 foQQN 1o0000 1.0000 toQQN
'l o NQQ 1 QNQ 1o0000 1.0000 1 0000 1oDQQQ 1 0000 1.0NO leQQQO 'l.0000. C. CaX ultT 1 CTCLI 10 V ~ RBNt IANN (NO 0 150 10 ZQN 40N f58 lON RON. 40N dDN 1.0000 1 oNOO 1.0000 1 o00 1.ONO 'lrQQN 1.00N loODQQ t.O}00 fo0000 1o0000 1.NQO 1oNQQ 1.0000 'loOQN 1e0000 t.OON 1.NOO 1.0000 loNQQ 1o0000 1.NQQ 'l.QNO 1.0000 foDNO 1.0000 1eQDQD 1.0000 1.00 1 ~ 0000 'l.0759 te07$ 9 1 0732 1 0746 1 A791 1.0751 1.075t 1.0731 1.0743 f.QYt}5 1 0742 te0742 1.0725 to0739 1.0776 1.0731 'toQF$ 1 toOTtb te0732 1.0755 1e0719 1.0719 to0709 to0723 fe075t 1.07N fo0705 1.0598 teQFtt 1.0734 1.0589 1 o0589 1-t}585 1.0595 1.0T15 1oD671 1.0571 1.0570 1.0579 1.0693 te0552 1 05SR 1.0554 to0560 1.0672 1.0656 to0536 tA637 teM38 1A648 1oMRS to0525 to06Zf 1.0521 to0624 toM'13 1.0513 1.0606 te0506 1.0504 te0603 1.0go 1.0595 to0595 1.0592 1.0595 ie0$ 95 1.0589 1.0593 1A594 1.0592 1o0592 1A589 1.0501 '1 ObOf 1oQS90 1 0592 1.0592 tr0506'1.06M 1o0$ 90 1.0592 1.0592 1o0511 1.0bft 'lo0589 1 ~ 0591 1 e0591 1eM14 fodbtb 1.Ndb lo0$90 'to0590 f.Mt5 lo0615 to05bf t.N88 1.0$ ab 1 r0614 1.0614 1o0574 1.0544 1.0544 1.0611 1.06'll feNQ feNTF 1 ~ 0577 1.0404 foOd04 1e0555 1.0548 fo0568 1.0594 fo0596 . fo0542 1o0556 1.0556 te0582 1A$8R to0527 1.0S40 1-N40 1.0562 'lA56R 1.05 foQSRf fo0521 1.0549 fo0558 'l.0486 1.0498 1 e0498 te0552 1 0564 1.0458 1 o0483 fo0491 fo0$49 'lo0564 f.OAF '1 047'l 1.0481 1 0538 l 0558 1e0420 1.0460 1.0471 1.0533 1.0548 1.0413 1,0455 1.0459 1.0534 1 0542 1.0419 1.0458 1.0472 to053f 1 0544 1 o0419 1.0454 1 0459 lo0$23 to0539 1.0C17 1.DCCd toQCbt to0$ 09 fe0528 1.0401 1 o0432 1.0444 1 A4N 1o0511 1.0CDC 1.0412 1.0428 toDC53 1 0487 to 0453 1.0453 1.0402 to0430 1.04%6 1e0497 1o0497 1o0359 1.0390 1oQC'l9 1.0539 1.0539 1.0325 1.0335 1.0370 te0502 1 0582 1 0320 1.0322 to0573 1.0524 1e0524 1.0355 1.0356 1oDC25 '}.0555 1.0555 1.0369 te0391 1.0456 'loO?QS 1.070$ 1.0423 1.0426 1.0506 to QT44 1 ~ 0744 1.0456 1.0Cbl 1o0546 1.0781 1.0781 to0488 teDC94 1eNbi 1.0btb 1.08th f.Ntb to0525 1.0619 to08CI 1 o0548 '1.N45 1.0557 1 o0652 te0879 1.0879 1.0570 1.0584 te0681 1.09tt 1.0911 1.0592 to0509 1.0703 1.00N 1eDON 1 ODQQ 1 0000 teDDQQ 1.0000 1oNOQ 1.0000 f.O}00 'lo0000 'loODQO 1.00N 1 0000 teNNO 1.0000 \\.QDN 1oOON 1.0000 teNNQ 1AOQO Note t}tat top ~nd hotico} tOX of oora are eaoluded aa I ~r teehntcal Ipeotftcatton ~ ~ ~ ~ ~e
Attachment 2 to AEP:NRC:0940H Letter from D. L. Wigginton (USNRC) to John E. Dolan (IMECo) dated May 1, 1987
r ~y,rI IIEqy c< ~4 O r rrO I1I O +~ ~O +y*y4 Docket Nos. 50-315 50-316 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. O. C. 20555 gP;f 0 1 'I937 Hm' 4 ISN'T HAY 5 $986, Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Hr. Dolan:
N. P. ALEXICH R. W. JURGENSEN T. O. ARGENTA S. J. BREWER J. H. CLEVELAND C. A. ERIKSON J. G. FEINSTEIN R F KROECrER J. B. SHINNOCK D. H. VILLIAHSr JR. JOHN E. DOLAN On September 20, 1983, the NRC issued Amendment 74 to Facility Operating License No. DPR-58 for the Donald C. Cook Nucleat Plant, Unit No. 1. The Safety Evaluation supporting the amendment found that changes to specification 4/3.2.6 were acceptable on the condition that the peaking factor limft report be transmitted to the NRC for review 60 days prior to the scheduled startup date for the new cycle. By letter dated March 26, 1987, the Indiana and Mfchfgan Electric Company proposed to change this condition and submit the report 15 days prior to the Cycle 10 initial criticality. The IHEC letter also proposed techn'ical specifications to that effect. We are in the process of evaluating our requirements, including an acceptable change to technical specifications. We will be discussing these changes with your staff in the near future; therefore, we agree that a change for Cycle 10 is appropriate. For Cycle 10, IHEC should submit the peaking factor limit report 30 days after initial criticality. This change in submittal date does not change plant operation or the safety analysis and continues to provide timely notice to the NRC. If there are any questions on this matter, please let us know. Sincerely, cc: See next page David L. W nton, Acting Project Director Project Directorate III-3 Division of Reactor Projects}}