ML112900685

LER 80-016/01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements

ML112900685
Person / Time
Site:	Monticello
Issue date:	04/10/1980
From:	Overlid T Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900686	List: ML112900685 ML19305D338
References
LER-80-016-01T, LER-80-16-1T, NUDOCS 8004140437
Download: ML112900685 (3)

Text

REGULATORY I*0ORMATION DISTRIBUTION SYS4 (RIDS)

ACCESSION NBR:8004140437 DOC,DATE: 80/04/10 NOTARIZED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHOR AFFILIATION OVERLIDT.W, Northern States Power Co.

RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director

SUBJECT:

LER 80-016/01T-0:on 800327,during refuelingtsupports for SRV pneumatic supply sys would not meet seismic:Class I requirements.Caused by inadequate design & installation of sys.Sys was upgraded to satisfy requirements.

DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR I ENCL ./ SIZE:_jt.:L,..

TITLE: Incident Reports N0 TES :- --

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC OR6 3 4 4 INTERNAL: -REL1 LE 1 1 02 NRC PDR 1 1 09 I&E 2 2 11 MPA 3 3 14 TA/EDO 1 1 15 NOVAK/KNIEL 1 1 16 EEB 1 1 17 AD FOR ENGR 1 1 18 PLANT SYS BR 1 1 19 I&C SYS BR 1 1 20 AD PLANT SYS 1 1 22 REAC SAFT BR 1 1 23 ENGR BR 1 1 24 KREGER 1 1 25 PWR SYS BR 1 1 26 AD/SITE ANAL 1 1 27 OPERA LIC BR 1 1 28 ACDENT ANLYS 1 1 29 AUX SYS BR 1 AD/ORP*DOR 1 1 AEOD 10 10 BERLINGERC, 3 3 DOUG MAY-TERA 1 1 HANAUERS. 1 1 JORDANE./IE 1 1 EXTERNAL: 03 LPDR 1 04 NSIC 1 1 29 ACRS 16 16 Z4PR 1?

C P'oI~

'1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 61 ENCL 61

0 IMSIP NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 April 10, 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 Safety/Relief Valve Air Line Seismic Problems 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.l.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

) )o

-over- 3 0041

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77) 17-77) LICENSEE EVENT REPORT CONTROL BLOCK: Di IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

[T1 IMI NI MI NI P1I2I 15 olol-l olol ol01 01 LICENSE NUMBER

- o 01141 111111TYPE11130 25 26 LICENSE LJ...J 57 CAT 58 7 8 9 LICENSEE CODE 14 CON'T REPOR Ljl 15 10 10 1 01 21 6L 3 1 01 31 21 71 8d 1 0L1 41 11 01 81 0 7 8 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 60 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (3 During refueling. a followun inspection to T.E. Billetin 80-01 revealed that the I supports for the SRV pneumatic suoply system would not meet Seismic Class I require-I ments speritig- .1 In Llngi agauiti M 0.

No effect on public health or safety.

084 80 7 8 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 9 L 10 J@ LAO 11 LA 12 IS IUIPlOj RI TiO 13 18 wI 19 20 wL SEQUENTIAL OCCURRENCE REPORT REVISION REPORT NO. CODE TYPE NO.

LER/RO REPOR NUMBER EVENT YEAR I g II-J 21 22 23 I Lill 24 26 27 IiJ 28

.. J 29 L30 31 LdJ 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 34 LJ 35 LzJ 2 36 10101 oo 37 40 L.JNJ 41 42 LA 43 lB1 11 31 01 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS I cnc Tw;; inaderniite rQe ign and installation of the system by the Architect l l Engineer. System was ipraded to satisfy FSAR Seismic Clas T requirements during I QJ~ I refueliniz outaee.

~EJ 7

rrrn 8 9 80 METHOD OF FACILITY STATUS %POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION FL5 .. 101 01 0 1I NA 11CJ I Licensee inquiry 80 1

7 89 10 12 13 44 45 46 ACTIVITY CONTENT M T RELEASED OF RELEASE OUN OF ACTIVITY LOCATION OF RELEASE A

7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 17ID L0oL I o i zNA 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 80 7

D 1I01 8 9 01 91 11 12 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 7

l LzLJ j NA 8 9 10 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION @

2I0 Lal81 NA 7 8 9 10 68 69 80 T mierid .(612) 295-5151 0 NAME OF PREP ARER H v4a

. 00D41 40 157