ML17331A419
| ML17331A419 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/18/1980 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0455, IEB-79-14, NUDOCS 8008260424 | |
| Download: ML17331A419 (3) | |
Text
REGULATO IVFORHATION DISTRIBUTION STE~
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ACCESS IG."i VBR: 8008260424 OOC ~ DATE: 80/08/18 QATAR I ZEO:
>>VO DOCKET FACIL:50 315 Oonal d C ~
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1 ant r Uni t 1< Indiana 8
05000315 50"316 Oonal d C ~
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>>Jni t 2i Indi ana F
05000316 AUTH'h>>4E AUTHOR AFFILIATION HUNTERpR ~ ST Indiana 4 '>>ichiqan Electric Co.
REC IP ~ t"A'iE RECIPIEVT AFFILIATIO~l BENTON,H,R.
Office of Vuclear Reactor Requlationi Oirector
SUBJECT:
>>Votifies that response to Question 5.74 of reQuirements of IE Bulletin 79-14 has been found to be inconsistent w/FSAR design criterion for oioing.A>>>>>>end to FSAR will be filed to include correct response
>>l actual design practice
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INDIANA II MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLIN G GR E EN STATION NEW YORK, N. Y. 10004 August 18, 1980 AEP:NRC:0455 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear MI. Denton:
During the review efforts being made to comply with the requirements of I.E. Bulletin No. 79-14, we have found an inconsistency between the main body of the FSAR and part of our response to question 5.74.
The main body of the FSAR accurately reflects the practice followed by AEP in the design of piping for the Donald C.
Cook Nuclear Plant when it states for the design of "engineered safety features" that:
"...by designing the engineered safety features to be operative under a maximum horizontal ground acceleration of 20 percent of gravity and a maximum vertical acceleration of 13.33 percent of gravity."
(FSAR, page 2.5-4)
That is the practice consistently followed in the design of the Plant's engineered safety features piping systems employed at least two thirds (2/3) of the appropriate horizontal response spectrum at the base slab for the vertical acceleration.
This 'is, incidentally, the same practice followed by at least five other facilities of simi lar vintage to Cook
~
Our response to guestion 5.74 (Amendment No.
17 to the facility's FSAR, issued in September of 1971) was consistent with the above stated FSAR design criterion except that the sentence related to piping inexplicably omitted the reference to the two thirds (2/3) fraction.
Thus, it stated that:
"...The analysis of piping includes the vertical loads equal to the appropriate horizontal ground response spectrum."
8008260 424
Nr. Harold R. Denton, Director AEP:NRC:0455 This, of course, did not represent the design practice followed at the Cook Plant.
While our own personnel and an outside consultant noted this erroneous response in the 1971-73 period, the efforts to correct the record apparently were not followed through to completion.
In 'the next two months we are filing an amendment to our FSAR.
This amendment will include the corrected response to question 5.74, which will reflect the actual design practice followed at the Donald C.
Cook Nuclear Plant.
Very t uly yours, R. S. Hunter Vice President cc:
R.
C. Callen G. Charnoff J.
E. Dolan R.
N. Jurgensen D. Y. Shaller - Bridgman