05000263/LER-1980-007-01, /01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors

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/01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors
ML112900662
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/14/1980
From: Galen Smith
Northern States Power Co
To:
NRC/OI/RGN-III/FO
Shared Package
ML112900663 List:
References
LER-80-007-01T, LER-80-7-1T, NUDOCS 8003240407
Download: ML112900662 (4)


LER-1980-007, /01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors
Event date:
Report date:
2631980007R01 - NRC Website

text

I--

REGULATORY #FORMATION DISTRIBUTION SY0EM (RIDS)

ACCESSION NBR:8003240407 DOC,0ATE: 80/03/14 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AVTHNAME AUTHOR AFFILIATION SMITHG.R.

Northern States Power Co.

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

SUBJECT:

DOCKET #

05000263 LER 80-007/01T-0:on 800303,during refuel shutdownrcable routing for HCPE & automatic depressurization sys cables identified lack of physical separation between automatic depressurization sys cables & ones for div of HPCI sensors.

DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR.L ENCL.

SIZE:.)

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

RECIPIENT ID CODE/NAME ACTION:

05 BC 6*18##.s INTERNAL:

09&T 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR AEOD HANAUER,S, JORDANE,/IE COPIES LTTR ENCL 4

4 1

1 2

2 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT.ANLYS AD/ORP*DOR DOUG MAY-TERA

IRELANDR, COPIES LTTR ENCL 1

3 1

1 1

1 1

1 1

1 1

3 EXTERNAL:

03 LPDR 29 ACRS 1

16 1

16 04 NSIC 4 Rb5,oe TOTAL NUMBER OF COPIES REQUIRED; LTTR 1

1 52 ENCL 52

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 March 17, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 HPCI-ADS Cable Separation 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 our prompt written notification dated March 4, 1980, it was stated that "cables for the 'AC Interlock' pressure permissive signals apparently did not meet the separation criteria stated in the FSAR". However, information received from General Electric now confirms that routing of AC Interlock cables is consistent with the licensing basis philosophy for ADS at Monticello.

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 8003240

NRC FORM 366 (7-77)

[DI 7

8 CON'T 7

8 PP1 7

8 7

8 EThJ U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:

(

I(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

lMINIMI NI I P1 I 0 ol 1-lol ol ol ol -l ol 0 4 1 11111 11 1 IL...J Q 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORE LLJ@l 01 5I 01 01 0l 2 1 6 3 l0l 0 1 310 13 118 l 0 l 0 1 3 1 11 41 81 0 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCESo IDuring refuel shutdown conditions a review of cable routing for HPCI and ADS cablesi lidentified a lack of physical separation between ADS cables and cables for one l

Idlivigion of HPCT stenm linp brpak spnsnr.

Review is associated with IE Informatiod I

Tic 79-32 Pe.orted u-e.

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Nn previius-eventA No effert iipnn pihlic I

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CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE LI OL LB I1A (

1 Z IZ 1 2 Z I Z I Z I LzI Lz 9

10 11 12 13 18

.19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.

CODE TYPE NO.

REORT L

J 010 17 L.

L.1LJ LTJ LJ Lo 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 LJLL J@ Lz@

L20 1 0101010 1 o

I J@ Ll N

z 1z9 1 91 9 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS I

Improper routing of HPCI steam line break sensor cables as a result of design modiff I cation performed to implement General.Electric FDCN-148. New cables are being I routed for proper separation.

I I

7 8

9 FACILITY STATUS

% POWER OTHER STATUS EJ) Li.J@ Ldni In@1 NA1 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY EE16 L @ LJOI NA I

1 8

9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

1T 1 lolol 01 L J [ NA 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 8 E

01 0181 NA 7

8 9

11 12 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

E L

l NA 7

8 9

10 PUBLICITY ISSUED

DESCRIPTION

77 L._J61 NA 7

8 9

10 NAME OF PREPARER METHOD OF DISCOVERY DISCOVERY DESCRIPTION 3

Lpj Engineering Investigation 45 46 8

LOCATION OF RELEASE I MA 45 80 NRC USE ONLY 68 69 80 PHO 612/295-5151 0 oo 24o O

80 1

0 1

80 80 80 T

8

NRC.FORM 36LV U. S.NUCLEAR REGULATORY COMMISSION an)

LICENSEE EVENT REPORT CONTROL BLOCK:

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9 LICENSEE CODE 14 1s LICENSE NUMBER 2-6 ICENSE TYPE 3

SREPOR 01 51 01 01 01 2 16 136 01 310 38 I0l(%O 0 3 11 418 O

7 8

60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Iuring refuel shutdown conditions a review of for HPC d ADS cables 0 identified a lack of p1hysical. separation between ADS cables and cables for one 04

-~i'nnof 14PCT tpam linp brpak n

Review is associated with IE Informatio INotice 79-32.

Reported under Tech Spec 6.7.B.l.i. No significant occurrence.

F N

nr1vious 6vents Nn Pffprt-upn publ I

7 80 7

8 9 COP.

VAV SYSTEM

CAUSE

CAUSE Comp.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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LsJ1 I IB @ L (

1 z I z z I z G

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7 8

9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE/0 FEVENT YEAR REPORT NO.

CODE TYPE NO.

~NUMBERl L§L 0107 LJ L..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 L JO OW M D Oj 0 1 0 l 0 1JZ 9

9L9 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 1 Improper routing of HPCI steam line break sensor cables as a result of design modif 11I cation performed to implement General.Electric FDCN-148.

New cables are being 1routed for proper separation.

FACILITY METHOD OF 8

7 89 STATUS

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 5o 2 3 NA Engineering Investigation 7 8 910 12 13 44 45 46 8

ACTIVITY CONTENTLOAINFREAS RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

=

LJ WINBI A I

I NAA a9 10 11 44 45so PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

I 0 1 0I 0L JV0

/

JI NA 7

8 9

11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION6 1E]I L 0n181 NA 7

8 9

11 12 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

19 L

J I

NA 7

8 9

10 PUBLIITY ON Q80 NRC USE ONLY ISSUED DESCRIPTIO r2T-1 Z 61NA It1 7

8 9

10 69 80 NAMEOFPREPARER Gary R Smith 612/295-5151 80O240 4'O