ML18219D795
| ML18219D795 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 01/23/1978 |
| From: | Tillinghast J Indiana Michigan Power Co |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18219D795 (5) | |
Text
U,S, NUCLEAR REGULATORV C i MISSION NRC CFORM 195 I2-76)~
I NRC DISTRIBUTIONFoR'ART 50 DOCKET MATERIAL OQC H/
FII'E74UQSER TO:
Mr. Edson Gi Case FROM:
& Michigan Power Co, New York, N Y 10004 John Tillinghast OATS QF OOCUMENT 01/23/78 OATE RECEIVEQ 05/26/78 ODETTE R
~QRIGINAI Ocopv NQTORI2EO
~NCLASSIFIEO PROP INPUT FORM NUMBER OF COP IES R 6 CE IVE 0 OESCRIPTION 2p ENCL,OSURE
Response
to NRC ltr dtd 04/13/77 '
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Forwarding analysis of the short-term steam generator sub-compartment pressure response on Subject Facility, Units 1 & 2 ~ ~ +Notarized 01/23 78, poli~ 6 AIRC gvesf j I dz.~- /
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PLAiIT'Ai4E: COOK UNITS 1 & 2 jcm 05/26/78 rf'r Q6
/=Pea FOR ACTION/INFORMATION ENVIRON KNTAL CH CHIEF:
PROJECT MANAGER:
LIC. ASST:
&.~vwczAC ASSIGNED AD:
BRANCH CHIEF:
HARLESS INTERNALDISTRIBUTION VT SYSTEMS SITE SAFETY G
ENVIRON ANALYSIS DEiVTON G blULLER GOSSICK C STAFF AGENEVi T EiVGIIVEERING ACTOR SAFETY ROSS B
R TO CTORS
'IVIRON TECH ERNST BALLARD OD TECH GAIeIILL ( 2 ViOVAK ROSZTOCZY CHECK TLER VOLLNER YSIS LTZiiN NS PDRIAJ~
HANCHETT) 16 CYS SENT CATEGOR.
EXTERNALDISTRIBUTION XO ACRS CONTROL NUMBER 781460124
INDIANA L MICHIGAN POWER COMPANY P. O. BOX 18 Bo WL I N G G R E EN STAT ION NEW YORK, N. Y. 10004 January 23, 1978 Donald C. Cook Nuclear Plant Unit Nos.
1 5 2 Docket Nos.
50-315 8 50-316 DPR Nos.
58 5 74
Subject:
Steam Generator Subcompartment Pressure
Response
Analysis A
Nr. Edson G. Case, Acting Director Office'f Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Nr. Case:
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~ Kl tD This letter transmits the'nalysis of the short-term steam genera-
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tor sub-compartment pressure response on Donald C. Cook Nuclear Plant Units 1 and 2.
The information presented herein is in response to NRC guestion 022.3 attached to Mr. K. Kniel's letter of April 13, 1977, and to Section 2.C.3.b of the Facility Operating License for Donald C. Cook Nuclear Plant Unit No. 2.
The analysis contained herein is based on Unit 2 data but is applicable to Unit 1 also, since both Units are iden-tical in the areas of concern.
Attachment 1 to this letter responds to NRC guestion 022.3.
Attachment No.
2 discusses the structural adequacy of the steam genera-tor sub-compartment to meet the pressure results associated with the subject analyses cited in Attachment 1.
This structural analysis shows that in all cases the structure is capable of withstanding the pres-sures corresponding to the postulated breaks within the compartment with a safety factor (load factor) of 1.5.
In addition to the sub-compartment structural analysis, an analy-sis was also performed as to the adequacy of steam generator supports.
The results of this analysis are shown in response to guestion 022.3-1 (j), as well as in Attachment No.
3 and these results show that no components were overstressed.
A dynamic load factor of two (2) was used in this analysis to convert each dynamic load to its equivalent static load.
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Mr. Edson G.
Case January 23, 1978 We believe the information contained herein completes our obli-gation with regard to NRC guestion 022.3.
Since we are currently scheduled to go to Mode 2 operation on Unit 2 on February 9, 1978 we must assume that unless we are advised differently by your staff, this letter satisfies the NRC concerns expressed by the license conditions in Section 2.C.3.b and that there is no reason why this condition of license will prevent us from entering into Mode 2 operation for the initial startup of Donald C.
Cook Nuclear Plant, Unit No. 2.
Very truly yours, nghast ice President Sworn and subscribed to before me this ~3'"day of January, 1978 in New York County, New York CC:
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W. Jurgensen D. V. Shaller - Bridgman R.
W. Steketee R. J. Vollen
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