ML17317B403

Amends Info Contained in 790504 & 08 Submittals.Floor Response Damping Factor Used to Determine Max Upset Condition Stresses Was 4% Instead of 2%.Stresses within Allowable Values

ML17317B403
Person / Time
Site:	Cook
Issue date:	07/27/1979
From:	Dolan J INDIANA MICHIGAN POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:00186C, AEP:NRC:186C, NUDOCS 7908060233
Download: ML17317B403 (4)

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REGULA~HY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR.7908060233 DOC CHOATE. 79/07/27 NOTARIZED.

YES FAC IL:50-315 Donalo CD Cook Nuclear Power Plant< Unit l~ Indiana 8

50-316 Oonala C,

Cook Nuclear Power Planti Unit 2i Indiana AUTH'APE AUTHOR AFFILIATION DOLANpJ ~ ED Indiana 8 Michigan Power Co ~

REC IP ~ NAblE RECI<< IENT AFFILIATION DENTONJH ~ R Office of Nuclear Reactor Regulation

SUBJECT:

Amends info contained in 790504 8

08 Submittals.Floor response damping factor used to determine upset condition stresses was 4X instead of aporopriate 2X ~

DOCKET 0500031 OSOO 16 DISTRIBUTION CODE t AOO 1 S COPIES RECE I VEO ~ LTR

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INDIANA IL MICHIGAN POWER COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. I0004 KMLNmlMI,I<P FI~~

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

References:

(1) AEP:NRC:00182 Dated May 8, 1979 (2) AEP:NRC:00186A Dated May 4, 1979

Dear Mr. Denton:

A This letter serves to amend the information contained in our AEP:NRC:00182 and AEP:NRC:00186A submittals, dated May 8, 1979 and May 4, 1979, respectively.

We have been informed by Westinghouse that the floor response damping factor used" in the determination of the maximum upset condition (OBE + normal) stresses reported in our recent submittals referenced above was four percent (45).

Specifically, Westinghouse utilized a floor response based on a four percent (4X) structural damping factor for the analyses of the Pressurizer Surge Line and the six inch Safety Injection Lines to the Reactor Coolant System Hot Legs (the latter applicable to Unit 1 only).

The appropriate structural damping factor of two percent (2X) corresponding to the upset condition has been used in the reanalysis of these lines.

The results of the reanalyses are attached.

Subsequent to completion of the reanalysis of the Pressurizer Surge Line, Westinghouse has reevaluated the loads on the Pressurizer Surge Line Nozzle and determined that the loads are within the allowable limits.

Nr. Harold R.

Denton AEP: NRC: 00186C The results of this reevaluation clearly indicate that the maximum hypothetical combined upset condition stresses in the Pressurizer Surge Line and the six inch Hot Leg Injection Lines of Unit 1 are well within the allowable values set forth in the B31.1 Power Piping Code, 1967 edition.

Very truly yours, JED/emc Attachment ohn E. Dolan ice President Sworn agd subscribed to before me this+7~+day of July, 1979 in New ork County, New York Notar Pub GRSGGRY M. GiiRICA'.l p Sic Sia'te oi 8ew Yo tio 31 4643431 Qualified in Hew York Commission Expiree Sarch g, cc:

R.

C. Callen G. Charnoff R.

S. Hunter R.

M. Jurgensen D. V. Shaller - Bridgman

ATTACHMENT TO AEP:NRC:00186C 1

STRESS

SUMMARY

FOR PRESSURIZER SURGE LINE D. C.

COOK UNIT NOS; 1

AND 2 LOADING CONDITION OBE + NORMAL CALCULATED OCATltl

~Ei E

L PIPING 13496 psi INTERFACE PIPE/

PRESSURIZER.".

11874 ps i NOZZLE ALLOWABLE STRESS LOAD 19200 psi 19200 psi MARGIN 5704 psi 7326 psi PIPE SUPPORT 12.96 Kips 70.0 Kips(*)

57.04 lips DBE + NORMAL PIPING 21092 psi INTERFACE PIPE/

17848 psi PRESSURIZER NOZZLE 28800 psi(*)

7708 psi 28800 psi(*)

10952 psi PIPE SUPPORT 20.21 Kips 70.0 Kips(*)

49.79 Kips 2

SIX-INCH HOT LEG INJECTION LINES UPSET CONDITION D. C.

COOK UNIT NO.

1 LOOP 8 PIPING STRESS, 13,540 psi 14,483 psi 16,198 psi 14,834 psi ALLOWABLE STRESS 19,200 psi 19,200 psi 19,200 psi 19,200 psi MARGIN 5660 psi 4717 psi 3002 psi 4366 psi

(*) CONSERVATIVE NOTE'ORMAL = PRESSURE

+ DEADWEIGHT