ML112900707

LER 80-017/01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified

ML112900707
Person / Time
Site:	Monticello
Issue date:	04/11/1980
From:	Day B Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900708	List: 05000263/LER-1980-017, Forwards LER 80-017/01T-0 ML112900707 ML19309E147
References
LER-80-017-01T, LER-80-17-1T, NUDOCS 8004180472
Download: ML112900707 (3)

Text

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REGULATORY *FORMATION DISTRIBUTION SY ACCESSION NBR:8004180472 DOC.DATE: 80/04/11 NOTARIZED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHOR AFFILIATION DAY,B.D, Northern States Power Co*

RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director

SUBJECT:

LER 80-017/01T-0:on 800328,reduction of control rod driveline hydraulic piping frame support.Caused by EDS computer code error.Supports modified.

DISTRIBUTION CODE; A002S COPIES RECEIVED:LTR .4 NCL t SIZE:

TITLE: Incident Reports NOTES: --- --- --- -- --- --- -- --- --- -- --- --- -- --- --- -- --- --- --

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 6CQ 4 4 INTERNAL: 1 1 02 NRC PDR 1 2 2 11 MPA 3 14 TA/EDO 1 1 15 NOVAK/KNIEL 1 16 EEB 1 1 17 AD'FOR ENGR 1 18 PLANT SYS BR 1 19 I&C SYS BR 1 20 AD PLANT SYS 1 1 22 REAC SAFT BR 1 23 ENGR BR 1 1 214 KREGER 1 25 PWR SYS BR 1 1 26 AD/SITE ANAL 1 27 OPERA LIC BR 1 1 28 ACDENT ANLYS 1 29 AUX SYS BR 1 AD/ORP-DOR 1 AEOD 10 10 BERLINGERC. 3 DOUG MAY-TERA 1 1 HANAUERS. 1 JORDANE./IE 1 1 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 29 ACRS 16 16

,980

• 1 TOTAL NUMBER OF COPIES REQUIRED; LTTR 61 ENCL 61

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 April 11, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Reduction of CRD Hydraulic Piping Frame Support Design Margins Caused by EDS Computer Code Error The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.

This event is reported in compliance with Technical Specification 6.7.B.1.i in that a condition was discovered which was contrary to the design requirements contained in the Final Safety Analysis Report.

Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc: Director, IE, USNRC (40)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman S

i/1

-over- $0 0,418 ()4 6 8

(1-77)

LICENSEE EVLNI REPORT CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 7 8 9 MI Nj Ml NJ P1 1101 01 01 LICENSEE CODE 14 15

- 0110 0 I01j0 LICENSE NUMIBEII 0 - 1O 14 l1 1 25 26 LICENSE TYPE 11j 30 1

57 CAT 58 (D

CON'T REPOR T [Lj Oj 5501010121_6131() [01312181810) 101411111810l(D 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 02 I During a refueling outage, Bechtel Power Corporation notified licensee that CRD l hydraulic piping frame supports will not meet OBE stress limits. This event is reportable under T.S.6.7.B.1.i. Supports will meet SSE limits. Health or safety j of public not affected. No previous similar reportable event. j 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCOQE SUBCODE 7

0 8 9 IR Bj(^ j (D Bj 10 11 12 AI 13 S jU IP 1O IR IT 18 19 L]

20 .

SEQUENTIAL OCCURRENCE REPORT REVISION TYPE NO.

07 LERRO REORT1 EVENT YEAR 8LoJ 0 -

REPORT NO.

1ol 11 7 1 j 1.0 CODE

! [J L- L R 21 22 23 24 26 -27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP, COMPONENT TAKEN ACTION ON PLANT METHOD HOURS. SUBMITTED FORM SUB. SUPPLIER MANUFACTURER LLJ@LJ@

33 34 IJ@

35 36

_ l 37 o a1 40 41 JJ 42 43 44 I 0 47.

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (2' 10 Error in computer code used by EDS Nuclear caused original support design loads to I 11 be inaccurate. Supportshave been modified to meet stress limits. Bechtel has re- I 12 viewed other systems affected by computer code error. No other modifications re- I 13 quired.

14 7 8 9 80 FACILITY METHOD OF STATUS %POWER - OTHER STATUS & DISCOVERY DISCOVERY DESCRIPTION 32 IT EJ@ Iololo0 1 N^MA D Notification from A/E 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE SI Z @U I lI NA INA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUM3ER TYPE DESCRIPTION 0 1]01 0 J5Z l NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION I 0 1o 1I NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION

[LU I NA 7 8 9 10 80 PUBLICITY ISSUED DESCRIPTION NRC USE ONLY 1 LL181 NA a 9 10.

NAME OF PREPAR ER-Byron D. Day 612 -5151 PH9 -

800.4 18 0472