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| issue date = 08/21/1979
| issue date = 08/21/1979
| title = LER 79-008/03X-1 on 790406:during Maint on Boric Acid Flow Control Valve,Leaks Noted on Valve Outlet 1-inch Nipple. Caused by External Caustic Pitting.Actions to Minimize Caustics & Chlorides Are Being Taken
| title = LER 79-008/03X-1 on 790406:during Maint on Boric Acid Flow Control Valve,Leaks Noted on Valve Outlet 1-inch Nipple. Caused by External Caustic Pitting.Actions to Minimize Caustics & Chlorides Are Being Taken
| author name = SPECTOR S
| author name = Spector S
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:lINRCFORM366I7377ILER79-008/03X-1 I~!0178CONTROLBLOCK:INYREG1Q2009LICENSEECODE'1415U.S.NUCLEARREGULATORY COMMISSION UpdateReport-PreviousReportDate5/7/79~ENSEEEVENTREPORT~(CAR2229)Qi(PLEASEPRINTORTYPEALLREQUIREDINFORMATIONI 0-00Q'4''PE~QELICENSENUMBER'2526LICENSETYPE3057CAT58<<CON'Ti~Oi78~LQB050002447040679s082179Q6061DOCKETNUMBER6869EVENTDATE7475REPORTDATE80EVENTDESCRIPTION ANDPROBABLECONSEQUENCES Q10Duringmaintenance onboricacidflowcontrolvalveleakswerenotedonvalveoutlet1~031nipple(T.S.6.9.2.b.(4)).TwoflowpathsfromboricacidtankstoRCSwere4verified.
{{#Wiki_filter:INRC FORM366                                                                                                                              U. S. NUCLEAR REGULATORY COMMISSION l
Nipplewasreplacedwithsch40nipple.Later,nipples,checkvalveand<<~couplingfromcontrolvalvetocouplingwerereplaced.
I7377I                          LER      79-008/03X-1 Update Report                                Previous          Report Date 5/7/79 CONTROL BLOCK:
~~<<0e(~O7I~os.78980I~Osanalysisidentified thiscombinedwiththroughwall chloridestresscorrosion cracking.
                                                                                ~ENSEE Qi EVENT REPORT
SYSTEMCAUSECAUSECOMP.VAI.VECODECODESUBCODECOMPONENT CODESUBCODESUBCODE~PCQ<<1EQ12UcQ13PIPEXXQ<<4UAP<<6~ZQ1678910111213181920SEQUENTIAL OCCURRENCE REPORTREVISIONLER)ROEVENTYEARREPORTNO.CODETYPENO.Q17REPORTL77I.UUOOOSJUH~03UXU12122232426272829303132ACTIONFUTUREEFFECTSHUTDOWNATTACHMENT NPRDQPRIMECOMP.COMPONENT TAKENACTIONONPLANTMETHODHOURSQ22SUBMITTED FORMSUB.SUPPLIERMANUFACTURER UcPT.UcPE UzPEUZP21oooo~XP23UNQ24UNP>>z999P263334353637404142434447CAUSEDESCRIPTION ANDCORRECTIVE ACTIONSQ27oSevereexternalcausticpittingprobablystartedprocesscausingleaks.Metallurgical 3Otherheattracedpipingareasinvolving similarconditions examined; noproblemsfound.Actionstominimizecausticsandchlorides onpipeduetoinsulation, heat4traceandothermaterials arebeintaken.'.789FACILITYSTATUS%POWEROTHERSTATUS7~18EQ28~092Q28NA78910121344ACTIVITYCONTENTRELEASEDOFRELEASEAMOUNTOFACTIVITY(~16~ZP33~ZP,NA789101144PERSONNEL EXPOSURES NUMBERTYPEDESCRIPTION Q39~000Q37~ZQ38NA789111213PERSONNEL INJURIESNUMBERDESCRIPTIONQ l~<<8~000Q46NA7891112LOSSOFORDAMAGETOFACILITYQ43TYPEDESCRIPTION LzIQENA8910PUBLICITY 4ISSUEDDESCRIPTION
                                                                                                                                                      ~
~'H~ZPJQ44NA8910METHODOFDISCOVERY DISCOVERY DESCRIPTION Q32~AQ31Noticeddurinmaintenance onadacent4546vve80LOCATIONOFRELEASEQ8080458080790838073 (80NRCUSEONLY68698048PHoNE.716546-2700ext.291-215S.SpectorNAMEOFPREPARERj~j2The1"nippleis3-',"longsch10SS,heattraced,normaloperating pressure100psig.
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI (CAR 2229)
1 Attachment toLER79-008/03X-1 Rochester GasandElectricCorporation R.E.GinnaNuclearPowerPlant,UnitNo.1DocketNo.50-244W9ileperforming maintenance onboricacidflowcontrolvalvePCV-llOA, aleakwasnotedontheadjacentpiping.TwoflowpathsfromtheboricacidtankstotheReactorCoolantSystemwereverified.
I I~!0 7
Theleakingpipesectionwasa3-',"long1"schedule10stainless steel.Itisheattracedandnormaloperating pressureis100psig.Theexternalsurfaceexhibited numerousdeeppittingholes.Thenipplewasreplaced, andlaterthe.nipple,adjacentcheckvalve,nippleandcouplingwerereplaced.
1 8    9 NY            RE LICENSEE CODE G1Q200    '14    15                    LICENSE NUMBER 0   -     0    0
Metallurgical analysishasidentified themechanism causingtheleakstobeseverecausticpittingcombinedwiththroughwall chloridestresscorrosion cracking.
                                                                                                                                '25 Q'4   26 LICENSE TYPE
Seventeen sectionsofheattracedstainless steelpiping,containing varyingconcentrations ofboricacid,havebeenrandomlyselectedforexternalvisualinspection todetermine theextentoftheproblem.Parti-cularinterestwasgiventoareasofhighstressandareasthatmayhavehadnumerouswetting/drying cyclesduetoaccidental spillsorleakingvalves.Theseinspections revealedthatallthepipingwasinexcellent condition, withnosignsofthisphenomenon.
                                                                                                                                                                  '     30 PE~QE 57 CAT 58
Thesefindingsindicatethatlocalexternalcausesprobablyinitiated thisprocess,andthereplacement ofpiping,valveandfittingsinthisareashouldresolvetheproblem.Actionstofurtherminimizechlorideandcausticsonthepipingduetoinsulation, heattracingandothermaterials arebeingtaken.}}
      <<CON'T i~Oi 7        8
                                      ~LQB 60            61 0    5      0    0  0 DOCKET NUMBER 2    4    4 68 7
69 0    4    0 EVENT DATE 6      7      9 74 s
75 0    8    2    1 REPORT DATE 7      9 80 Q
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES                                  Q10 During maintenance on boric acid flow control valve leaks were noted on valve outlet 1~03                1    nipple            (T. S .       6.9.2 .b.       (4)) . Two            flow paths from boric acid tanks to                                      RCS    were
    <<~      4          verified. Nipple was replaced with sch                                            40    nipple. Later, nipples, check valve and coupling from control valve to coupling were replaced.
    ~ ~<<0  e
(~O7 I~os
    .7        8 9                                                                                                                                                                                80 SYSTEM                CAUSE        CAUSE                                                              COMP.           VAI.VE CODE                CODE        SUBCODE                    COMPONENT CODE                        SUBCODE            SUBCODE I~Os                                ~PC            Q<<1        E    Q12    Uc      Q13        P    I    P    E    X X        Q<<4        UA      P<<6     ~Z      Q16 7        8                        9            10          11            12                13                                18            19              20 SEQUENTIAL                              OCCURRENCE               REPORT                        REVISION EVENT YEAR U
REPORT NO.                                  CODE                    TYPE Q17 LER)RO REPORT L77I 21          22 23 UOOOSJ 24                26 UH 27
                                                                                                                            ~03 28          29 UX 30 U
31 NO.
32 1
ACTION FUTURE                    EFFECT          SHUTDOWN                                      ATTACHMENT              NPRDQ          PRIME COMP.               COMPONENT TAKEN ACTION                    ON PLANT            METHOD                    HOURS Q22        SUBMITTED          FORM SUB.           SUPPLIER            MANUFACTURER UcPT.UcPE                       UzPE              UZP21 37 o      o    o    o        ~XP23              UNQ24              UNP>>               z    9  9  9    P26 33          34                  35                36                                      40    41                  42                  43              44                47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                              Q27 o          Severe external caustic pitting probably started process causing leaks.                                                                             Metallurgical analysis identified this combined with throughwall chloride stress corrosion cracking.
j~j2              The 1" nipple is 3-'," long sch                                10  SS, heat traced, normal operating pres sure 100 psig .
3          Other heat traced piping areas involving similar conditions examined; no problems found. Actions to minimize caustics and chlorides on pipe due to insulation, heat 4          trace and other materials are bein taken.
  '.7        8    9                                                                                                                                                                            80 FACILITY                                                                            METHOD OF STATUS              % POWER                        OTHER STATUS                  DISCOVERY                                  DISCOVERY DESCRIPTION Q32 7~18                E    Q28    ~09              2    Q28                  NA                        ~AQ31        Noticed durin maintenance on ad acent 7        8    9              10                12      13                              44      45          46                                                                  v ve 80 ACTIVITY CONTENT RELEASED OF RELEASE                          AMOUNT OF ACTIVITY                                                              LOCATION OF RELEASE          Q
(~16           ~ZP33           ~ZP,                             NA 7      8  9              10            11                                            44            45                                                                                  80 PERSONNEL EXPOSURES NUMBER              TYPE          DESCRIPTION Q39
                  ~00            0    Q37  ~ZQ38                  NA 7        8    9                11      12            13                                                                                                                                  80 PERSONNEL INJURIES NUMBER                DESCRIPTIONQ l~<<8           ~00            0    Q46                          NA 7        8    9                11      12                                                                                                                                                80 LOSS OF OR DAMAGE TO FACILITY TYPE        DESCRIPTION                    Q43 Lz IQE                                            NA                                        790838073                      (
8    9            10                                                                                                                                                              80
  'H~Z ISSUED PJQ44 PUBLICITY DESCRIPTION       ~                 NA 4
NRC USE ONLY 8    9            10                                                                                                                          68    69                            80    48 NAME OF PREPARER                                S. Spector                                                PHoNE. 7 1 6          546-2 700          ext . 2 9 1-2 1 5
 
1 Attachment to LER 79-008/03X-1 Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant, Unit No.     1 Docket No. 50-244 W9ile performing maintenance on boric acid flow control valve PCV-llOA, a leak was noted on the adjacent piping. Two flow paths from the boric acid tanks to the Reactor Coolant System were verified.
The  leaking pipe section was a 3-'," long 1" schedule 10 stainless steel. It is heat traced and normal operating pressure is 100 psig. The external surface exhibited numerous deep pitting holes. The nipple was replaced, and later the. nipple, adjacent check valve, nipple and coupling were replaced.
Metallurgical analysis has identified the mechanism causing the leaks to be severe caustic pitting combined with throughwall chloride stress corrosion cracking. Seventeen sections of heat traced stainless steel piping, containing varying concentrations of boric acid, have been randomly selected for external visual inspection to determine the extent of the problem. Parti-cular interest was given to areas of high stress and areas that may have had numerous wetting/drying cycles due to accidental spills or leaking valves.
These inspections revealed that all the piping was in excellent condition, with no signs of this phenomenon.
These findings indicate that local external causes probably initiated this process, and the replacement of piping, valve and fittings in this area should resolve the problem. Actions to further minimize chloride and caustics on the piping due to insulation, heat tracing and other materials are being taken.}}

Latest revision as of 10:05, 4 February 2020

LER 79-008/03X-1 on 790406:during Maint on Boric Acid Flow Control Valve,Leaks Noted on Valve Outlet 1-inch Nipple. Caused by External Caustic Pitting.Actions to Minimize Caustics & Chlorides Are Being Taken
ML17261A139
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/21/1979
From: Spector S
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17244A791 List:
References
LER-79-008-03X, LER-79-8-3X, NUDOCS 7908280731
Download: ML17261A139 (4)


Text

INRC FORM366 U. S. NUCLEAR REGULATORY COMMISSION l

I7377I LER 79-008/03X-1 Update Report Previous Report Date 5/7/79 CONTROL BLOCK:

~ENSEE Qi EVENT REPORT

~

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI (CAR 2229)

I I~!0 7

1 8 9 NY RE LICENSEE CODE G1Q200 '14 15 LICENSE NUMBER 0 - 0 0

'25 Q'4 26 LICENSE TYPE

' 30 PE~QE 57 CAT 58

<<CON'T i~Oi 7 8

~LQB 60 61 0 5 0 0 0 DOCKET NUMBER 2 4 4 68 7

69 0 4 0 EVENT DATE 6 7 9 74 s

75 0 8 2 1 REPORT DATE 7 9 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During maintenance on boric acid flow control valve leaks were noted on valve outlet 1~03 1 nipple (T. S . 6.9.2 .b. (4)) . Two flow paths from boric acid tanks to RCS were

<<~ 4 verified. Nipple was replaced with sch 40 nipple. Later, nipples, check valve and coupling from control valve to coupling were replaced.

~ ~<<0 e

(~O7 I~os

.7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAI.VE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE I~Os ~PC Q<<1 E Q12 Uc Q13 P I P E X X Q<<4 UA P<<6 ~Z Q16 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR U

REPORT NO. CODE TYPE Q17 LER)RO REPORT L77I 21 22 23 UOOOSJ 24 26 UH 27

~03 28 29 UX 30 U

31 NO.

32 1

ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER UcPT.UcPE UzPE UZP21 37 o o o o ~XP23 UNQ24 UNP>> z 9 9 9 P26 33 34 35 36 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o Severe external caustic pitting probably started process causing leaks. Metallurgical analysis identified this combined with throughwall chloride stress corrosion cracking.

j~j2 The 1" nipple is 3-'," long sch 10 SS, heat traced, normal operating pres sure 100 psig .

3 Other heat traced piping areas involving similar conditions examined; no problems found. Actions to minimize caustics and chlorides on pipe due to insulation, heat 4 trace and other materials are bein taken.

'.7 8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 7~18 E Q28 ~09 2 Q28 NA ~AQ31 Noticed durin maintenance on ad acent 7 8 9 10 12 13 44 45 46 v ve 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q

(~16 ~ZP33 ~ZP, NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Q37 ~ZQ38 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ l~<<8 ~00 0 Q46 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Lz IQE NA 790838073 (

8 9 10 80

'H~Z ISSUED PJQ44 PUBLICITY DESCRIPTION ~ NA 4

NRC USE ONLY 8 9 10 68 69 80 48 NAME OF PREPARER S. Spector PHoNE. 7 1 6 546-2 700 ext . 2 9 1-2 1 5

1 Attachment to LER 79-008/03X-1 Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 W9ile performing maintenance on boric acid flow control valve PCV-llOA, a leak was noted on the adjacent piping. Two flow paths from the boric acid tanks to the Reactor Coolant System were verified.

The leaking pipe section was a 3-'," long 1" schedule 10 stainless steel. It is heat traced and normal operating pressure is 100 psig. The external surface exhibited numerous deep pitting holes. The nipple was replaced, and later the. nipple, adjacent check valve, nipple and coupling were replaced.

Metallurgical analysis has identified the mechanism causing the leaks to be severe caustic pitting combined with throughwall chloride stress corrosion cracking. Seventeen sections of heat traced stainless steel piping, containing varying concentrations of boric acid, have been randomly selected for external visual inspection to determine the extent of the problem. Parti-cular interest was given to areas of high stress and areas that may have had numerous wetting/drying cycles due to accidental spills or leaking valves.

These inspections revealed that all the piping was in excellent condition, with no signs of this phenomenon.

These findings indicate that local external causes probably initiated this process, and the replacement of piping, valve and fittings in this area should resolve the problem. Actions to further minimize chloride and caustics on the piping due to insulation, heat tracing and other materials are being taken.