ML17261A122: Difference between revisions

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| issue date = 05/07/1979
| issue date = 05/07/1979
| title = LER 79-008/03L-0 on 790406:boric Acid Flow Control Valve Leak Noted on Valve Outlet One Inch Nipple.Caused by Internal Weld Flow Through Defects & Deep External Pitting. Nipple Replaced w/40 Nipple
| title = LER 79-008/03L-0 on 790406:boric Acid Flow Control Valve Leak Noted on Valve Outlet One Inch Nipple.Caused by Internal Weld Flow Through Defects & Deep External Pitting. Nipple Replaced w/40 Nipple
| author name = SPECTOR S
| author name = Spector S
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:U.S.NUCLEARREGULATORYCOMMISSIONNRCFORM366(re)~0178CON'T[oats]7879-008/03L-0LICENSEEEVENTREPORT(CAR1719)Q7{PLEASEPRINTORTYPEALLREQUIREDINFORMATION)60000000Q341111Q~QRLICENSENUMBER26LICENSETYPE3057CAT58CONTROLBLOCK:1NYREG1Q2009LICENSEECODE1415,oomoo,~LR050002441040679Qs0507Qo6061DOCKETNUMBER6869EVENTDATE7475REPORTDATE80EVENTDESCRIPTIONANDPROBABLECONSEQUENCESQ10Duringmaintenanceonboricacidflowcontrolvalveleakwasnotedonvalveoutlet1"nipple.(T.S.6.9.2.b.(4))TwoflowpathsfromboricacidtankstoRCSwereverified.~os~088078978SYSTEMCAUSECAUSECOMP.VALVECODECODESUBCODECOMPONENTCODESUBCODESUBCODE~PCQ11EQ13~CQT3PIP9XXQ4~AQTE~ZQ'3910111213181920SEQUENTIALOCCURRENCEREPORTREVISIONLESBOEVENTYEARREPORTNO.CODETYPENO.Q11REPoRT~79~~009~W~03~L~~02122232426272829303132ACTIONFUTUREEFFECTSHUTDOWNATI'ACHMENTNPRDAPRIMECOMP.COMPONENTTAKENACTIONONPLANTMETHODHOURSQ22SUBMITTEDFORMSUB.SUPPLIERMANUFACTURER~Q~CGR~zQER~zQoooo~NQ33~NQ34NQEEQER3334353637404142434447CAUSEDESCRIPTIONANDCORRECTIVEACTIONS27Internalweldflowthroughdefectsanddeepexternalpitting.TheI"nippleis3-'"longsch10stainless.Itisheattraced,andnormaloperatingpressureis100psi.Thenipplewasreplacedwithasch40nipple.LatermaintenanceInthissectionofpipingresultedinreplacementofthenipples,checkvalveandcouplingfromflowcontrolvalvetothecoupling.789FACILITYSTATUSSIPOWEROTHERSTATUSQE092NA78910~TE~QER~QER8910121344ACTIVITYCONTENTRELEASEDOFRELEASEAMOUNTOFACTIVITYQ6~ZQ33~ZQ34NA7891044PERSONNELEXPOSURESNUMBERTYPEDESCRIPTIONQ391~0008L~J8NA789111213PERSONNELINJURIESNUMBERDESCRIPTIONQ413~OO0Q4oNA7891112LOSSOFORDAMAGETOFACILITYQ43TYPEDESCRIPTION9ZQ42NA4580808080METHODOFDISCOVERYDISCOVERYDESCRIPTIONQ32~AQ31Noticedduringmaintenanceonadjacent4546valve80LOCATIONOFRELEASEQNA.PUBLICITYISSUEDDESCRIPTION~KZuNQ78910NAMEOFPREPARER905>10yoS.SpectorNRCUSEONLY80686980g716/546-2700,ext.291-215  
{{#Wiki_filter:NRC FORM 366                                                                                                                U. S. NUCLEAR REGULATORY COMMISSION (re)                                                                             79-008/03L-0 LICENSEE EVENT REPORT (CAR 1719)
(),l+}}
CONTROL BLOCK:                                                Q7                 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 0000000Q341111Q~QR 1                                  6
  ~01 7    8    9 NY          RE LICENSEE CODE G1Q200  14      15                    LICENSE NUMBER                              26      LICENSE TYPE        30    57 CAT 58 CON'T
[oats]
7      8
                    ,oomoo,     ~LR 60          61 0    5      0    0  0    2    4  4 68 1
69 0    4    0 EVENT DATE 6    7    9 74 Qs 75 0    5    0 REPORT DATE 7
80 Qo DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                            Q10 During maintenance on boric acid flow control valve leak was noted on valve outlet 1" nipple. (T.S. 6. 9. 2.b. (4)) Two flow paths from boric acid tanks to                                                              RCS      were verified.
  ~os
  ~08 7      8 9                                                                                                                                                                      80 SYSTEM              CAUSE        CAUSE                                                      COMP.           VALVE CODE                CODE      SUBCODE                  COMPONENT CODE                  SUBCODE          SUBCODE 7      8
                                ~PC 9          10 Q11          E  Q13  ~CQT3 12              13 P    I    P    9    X X      Q4        ~AQTE           ~Z 20 Q'3 11                                                          18          19 SEQUENTIAL                          OCCURRENCE          REPORT                        REVISION Q11 LESBO REPoRT ACTION FUTURE EVENT YEAR
                                  ~79 21        22 EFFECT
                                                          ~
23 SHUTDOWN
                                                                        ~00 24 REPORT NO.
9 26
                                                                                                ~W 27
                                                                                                                ~03 28 ATI'ACHMENT CODE 29 NPRDA TYPE
                                                                                                                                      ~L 30
                                                                                                                                                    ~
PRIME COMP.
31
                                                                                                                                                                    ~0 NO.
32 COMPONENT TAKEN ACTION                ON PLANT            METHOD                  HOURS Q22        SUBMITTED      FORM SUB.         SUPPLIER              MANUFACTURER
              ~Q~CGR 33          34
                                            ~zQER 35
                                                                ~zQ 36            37 o    o    o    o 40
                                                                                                            ~NQ33 41
                                                                                                                            ~NQ34 42                43 N  QEE 44                47 QER CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 Internal weld flowthrough defects and deep external pitting. The                                                              I" nipple is            3-'" long sch 10 stainless.                       It is heat traced,             and normal operating pressure is 100 psi                                        . The nipple was replaced with a sch 40 nipple. Later maintenance In this section of piping resulted in replacement of the nipples, check valve and coupling from flow control valve to the coupling.
7      8    9                                                                                                                                                                    80 FACILITY STATUS              SIPOWER                        OTHER STATUS    Q        METHOD OF DISCOVERY                            DISCOVERY DESCRIPTION Q32
~TE 8
            ~QER 9
E          ~QER 10 0    9      2 12      13 NA 44
                                                                                            ~AQ31 45          46 Noticed during maintenance on adjacent valve 80 ACTIVITY CONTENT 6
RELEASED OF RELEASE
            ~Z AMOUNTOF ACTIVITY NA Q                                              LOCATION OF RELEASE NA.
Q Q33    ~ZQ34 7    8    9              10                                                      44            45                                                                            80 PERSONNEL EXPOSURES NUMBER              TYPE        DESCRIPTION Q39 1      ~00            0    8L~J8                        NA 7      8    9                11      12          13                                                                                                                            80 PERSONNEL INJURIES NUMBER              DESCRIPTION Q41 3      ~OO            0    Q4o                          NA 7      8    9                11      12                                                                                                                                        80 LOSS OF OR DAMAGE TO FACILITY TYPE        DESCRIPTION                  Q43 9          Z  Q42                                      NA 8
7          9 ISSUED 10 PUBLICITY DESCRIPTION      ~                                         905 > 10 yo                                                            NRC USE ONLY 80 KZ uNQ 7      8    9          10                                                                                                                  68    69                            80 g NAME OF PREPARER                              S. Spector                                                      716/546-2700,ext.291-215
 
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Latest revision as of 19:08, 29 October 2019

LER 79-008/03L-0 on 790406:boric Acid Flow Control Valve Leak Noted on Valve Outlet One Inch Nipple.Caused by Internal Weld Flow Through Defects & Deep External Pitting. Nipple Replaced w/40 Nipple
ML17261A122
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/07/1979
From: Spector S
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17244A515 List:
References
LER-79-008-03L, LER-79-8-3L, NUDOCS 7905110104
Download: ML17261A122 (2)


Text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (re) 79-008/03L-0 LICENSEE EVENT REPORT (CAR 1719)

CONTROL BLOCK: Q7 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 0000000Q341111Q~QR 1 6

~01 7 8 9 NY RE LICENSEE CODE G1Q200 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT 58 CON'T

[oats]

7 8

,oomoo, ~LR 60 61 0 5 0 0 0 2 4 4 68 1

69 0 4 0 EVENT DATE 6 7 9 74 Qs 75 0 5 0 REPORT DATE 7

80 Qo DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During maintenance on boric acid flow control valve leak was noted on valve outlet 1" nipple. (T.S. 6. 9. 2.b. (4)) Two flow paths from boric acid tanks to RCS were verified.

~os

~08 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

~PC 9 10 Q11 E Q13 ~CQT3 12 13 P I P 9 X X Q4 ~AQTE ~Z 20 Q'3 11 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LESBO REPoRT ACTION FUTURE EVENT YEAR

~79 21 22 EFFECT

~

23 SHUTDOWN

~00 24 REPORT NO.

9 26

~W 27

~03 28 ATI'ACHMENT CODE 29 NPRDA TYPE

~L 30

~

PRIME COMP.

31

~0 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~Q~CGR 33 34

~zQER 35

~zQ 36 37 o o o o 40

~NQ33 41

~NQ34 42 43 N QEE 44 47 QER CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 Internal weld flowthrough defects and deep external pitting. The I" nipple is 3-'" long sch 10 stainless. It is heat traced, and normal operating pressure is 100 psi . The nipple was replaced with a sch 40 nipple. Later maintenance In this section of piping resulted in replacement of the nipples, check valve and coupling from flow control valve to the coupling.

7 8 9 80 FACILITY STATUS SIPOWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~TE 8

~QER 9

E ~QER 10 0 9 2 12 13 NA 44

~AQ31 45 46 Noticed during maintenance on adjacent valve 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE

~Z AMOUNTOF ACTIVITY NA Q LOCATION OF RELEASE NA.

Q Q33 ~ZQ34 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 1 ~00 0 8L~J8 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION Q41 3 ~OO 0 Q4o NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 Z Q42 NA 8

7 9 ISSUED 10 PUBLICITY DESCRIPTION ~ 905 > 10 yo NRC USE ONLY 80 KZ uNQ 7 8 9 10 68 69 80 g NAME OF PREPARER S. Spector 716/546-2700,ext.291-215

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