ML061770354
| ML061770354 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/22/2006 |
| From: | Griffith D Ameren Corp, Union Electric Co |
| To: | Graves D, Omid Tabatabai Office of Nuclear Reactor Regulation, NRC Region 4 |
| References | |
| 42658 | |
| Download: ML061770354 (6) | |
Text
0612212006 U.S. NuclearRegulatory Commission OperationsCenter Event Report Pa__geI Power Reactor Event# 42658 Site: CALLAWAY Notification Date/ Time: 06/21/2006 10:02 (EDT)
Unit: 1 Region: 4 State: MO Event DatelTime: 06/19/2006 16:00 (CDT)
Reactor Type: [1] W-4-LP Last Modification: 06/22/2006 Containment Type: DRY AMB NRC Notified by: DENNIS GRIFFITH Notifications: DAVID GRAVES R4 HQ Ops Officer: JEFF ROTTON OMID TABATABAI NRR Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH Unit Scram Code JRX CritjInit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 100 Power Operation 100 Power Operation INITIAL PART 21 NOTIFICATION - PRIME MEASUREMENT PRODUCTS, MODELS 763 AND 763A GAGE PRESSURE TRANSMITTERS AND MODEL 764 DIFFERENTIAL PRESSURE TRANSMITTERS "This report is made per 10CFR21.21 Notification of failure to comply or existence of a defect and its evaluation.
"Callaway Plant received a notification dated May 18, 2006, from PRIME Measurement Products (formerly ITT Barton) stating Barton Model 763 and 763A Gage Pressure Transmitters and Model 764 Differential Pressure Transmitters may have defective external lead-wire connectors, which could affect their performance during an accident. The notification provided by PRIME stated the affected transmitters were manufactured after May 1982 and shipped from the factory prior to April 1, 2006.
"The potential defect is characterized as follows: The transmitters' external lead wires enter the electronics enclosure through a hermetic seal called a connector assembly. The external lead wires are soldered to the glass sealed pins of the hermetic seal. Epoxy potting is used to structurally support the soldered wire connections and establish a seal to protect the solder connections from shorting, which could be caused by an electrically conductive accident environment. The defect is that the insulated portions of the wires in the connectors, manufactured after May 1982, may not be embedded deeply enough into the epoxy potting to provide an electrical connection that would not be affected in an accident environment. -
"The notification also states that actual transmitter installation may preclude shorting of exposed conductors due to the existence of conduit, conduit seals, and special wire connectors which could protect the exposed wires at a defective connector from conductive moisture.
"Callaway Plant identified thirty applicable Barton transmitters and connector assemblies in warehouse stock.
Inspections of these operational spare parts identified three connectors, which had exposed conductors external to their seal. One connector had this defect on one lead wire and two connectors had this defect on both lead wires.
T-06/22/2006 U.S. NuclearRegulatory Commission OperationsCenterEvent Report Pajqe 2 Power Reactor Event # 42658 "Callaway has also identified that thirty-nine potentially affected transmitters are installed in the plant. An inspection plan has been developed to perform the required inspections, based on safety significance, ALARA considerations, and potential accident environmental conditions. Additional reporting requirements associated with the installed components will be evaluated under 1 OCFR50.72 as required.
"On 06/19/06, Callaway Plant personnel completed evaluations and determined the defective connections constitute a defect per 10CFR21 require initial NRC notification within two days.
"The NRC resident inspectors have been notified of this issue."
- *
- UPDATE FROM LICENSEE (D. GRIFFITH) TO M. RIPLEY 1515 EDT 06/22/06 ***
"This report is a revision to report EN # 42658 reported on 06/21/2006.
Added statement: "The suppliers of the identified transmitters were Prime Measurement Products and Westinghouse Electric Corporation."
The licensee notified the NRC Resident Inspector. Notified NRR (0. Tabatabai), R4 DO (D. Graves)
06/22/2006 11:01 U.S. Nuclear Regulatory Commlssion 8172766594 1/2 06/21/200G 08:00 FAX 67842P2 QA So001/002 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EN *0 EVENT NOTIFICATION WORKSHEET NRC OPERATION TELEPHONE NUMBER! PRIMARY - 301-BI1S-6100 OR 6D00-=-34W",BACKUPS - (12B)301-951-0550 OR e00-44g-3SS4 (2'0) 301-415-0550 AND (3") 301-415-0553 .'Lcenaees vMo maintain Uhelr own ETS are provlded these telephone numbers.
NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CAULER CALL OACKV EDT Callaway Plant I / Dennis Wade *Grfffith V(/ David D
(573) R. Waller Dido676-8595 R6 Wele 10:02 EDT E-VENT TIME & ZONE EVENT DATE POWER I MODE BEFORE POWER I MODE AFTER 16:00 CDT 6/19/2006 100% POWER/MODE 1 100 % POWER/MODE 1
_OE.',P..AL CLASSIFICATIONS o35I*AAEC. ._-Hr.Non.EmargancyIOCFR5O.72(b)l)
EVENT L.*,kO'LNC'Y . T D,* f ^i I XA S)M5LlXfy Ab2,V AIA
-1, -O_ TS DawuA MIf) IHi Ctllog y WE7! M!AJK^MVKCV 5AAZC 4-Hr. Nnn-Emergenuv 10 CM 50-72(b)(2) j M Co nmia tIROM A
.......... AL)M .
ALAAEC I IIIir IoF TS I I t~aMd
-u- I ANDX Mli I -^.t S UNU, =Ercaro AMP L2AIJI!XP03RLM
-IAT. .. ' 8-Hr Non-Em *encv L0 CFRSM.72 b)(3) lAwid~pa g3*d~,u=mA= ion ANV RT%$SORDOW~T W*rr Dq~w-dAC ABwi I Otber UnspecifietdRequiremn~et (Idsniy DESCRIPTION Intbide: Systemr uffmted, 1Macdans and dthr iuf1f;11SSIplals, causeS, efToet of e9=t on plato, MaenctW= or plmnnd, (Comlnc on back)
INITIAL PART 21 NOTIFICATION - PRIME MEASUREMENT PRODUCTS, MODELS 763 AND 763A GAGE PRESSURE TRANSMITTERS AND MODEL 764 DIFFERENTIAL PRESSURE TRANSMITTERS This report is made per I OCFR21.21 Notification of failure to comply or existence of a defect and Its evaluation.
Callaway Plant received a notification dated May 18, 2006, from PRIME Measurement Products (formerly ITT Barton) stating Barton Model 763 and 763A Gage Pressure Transmitters and Model 764 Differential Pressure Transmitters may have defective external lead-wire connectors, which could affect tnelr performance during an accident. The notification provided by PRIME stated the affected transmitters were manufaclured after May 1982 and shipped from the factory prior to April 1, 2006.
The potential defect is characterized as follows: The transmitters' external lead wires enter the electronics enclosure through a hermetic seal called a connector assembly. The external lead wires are soldered to the glass sealed pins of the hermetic seal. Epoxy potting is used to structurally support the soldered wire connections and establish a seal to protect the solder connections from shorting, which could be caused by an electrically conductive accident environment. The defect Is that the Insulated portion& of the wires In the connectors, manufactured after May 1982, may not be embedded deeply enough into the epoxy potting to provide an electrical connection that would not be affected In an accident environment.
The noVication also states that actual transmitter Installation may preclude shorting of exposed conductors due to the existence of conduit, conduit seals, and special wire connectors which could protect the exposed wires at a defective connector from conductive moisture.
NOTIFCATIONS NRC RS1%"T ISTAT"E($) I x
YES NO X -DE WIULLBE-f ANYTHuNC UNUSUAL OR NOT UNDMSTOOD?
[0 YES (explain above)
ALL SYSTEMS UNCTION AS R.EQIR.ED?
- 0 NO LOCAC YES NO, (expain . above)
O0lIER CDVAGX _______MODE OF OPERATiON ESTIMATED RE~START IADDMTONAL. INFO ON MEDIAIPRESS RELEASE X UNTIL CORRECTED: I DATE: WA B YES E] NO NRC FORM 361 (12-2000) 06/22/2006 THU 12:53 [TX/RX NO 9317] lI001
06/22/2006 11:02 U.S. Nuclear Regulatory Commission 8172766594 2/2 06/21/2006 02:00 FAX 6764202 QA jt002/002
.ADDrTD7NdL ZAFORMd47TON PAGE2 OF2
'RADIOLOGICAL RELEASES: CHECK OR FILL INAPPLICALE PTEM9 (spidtl *ied~ixplansdo touls~d be cwftd in wsitadieatcldon),. I I01 1.0IL$.us OAEM"AS. (UiiLAN20_VIA PL&NNM NO I TDMMWATeo MO.TOD it UNM0NZTORM I DOPR.SAJr. A.Sr ,*S VTx CA~
P.ri.. AkAiMS IIAWbA EVACUATED IPQUON?4EILEOM OIL0S5 CObR MMIA DAI 0=P10T~CTV5ACTION'SECiM-: K!~l
£V0.{! I3a i rn11
_______Reluie Rxte (Clheed %/T.S. LIMEIT 1100 GUIDE TOWa ACtivity (CI) Vo T.S. LIMIT RO00 GLIDE Noble________ 0.1 Cl/ace 100 I_________
coo________
___ ___ ___ __ _ 1uCl/ee_
1___ __ _ __ 0.01 C1 tr"Oiulat.
lJqWd CcWr*ifu iqtla (itdim 1 u /sec I________
10 aCUznix 0.2 Cumin :15 I MCI 0.1C1 Ci FLAT STACK CONDENSERIAIR EJCO MANT&LINE ISO BLWO OTHER P.AD 1610NITORRIADrOW ALAW EIN PAa..047 RCS ORSG TUBE LEAKS! CHECK OR FIL 12N APPLICABLE ITrEMS! (sgldaexlnix hudreovtdInrdozoJ E.CATION OF THE LEAK (eg..Y WO . valve, XIIIM. ex)
LEAK JAWE IUNITS; prrfpd IT.S. LIMITS SUDDEN OR.LONG-TERM DEVELOPMENT LEAK STAR3 DATE~ TftEt COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS:
LIST OFF SAFETY RELATED EQUIPMENT NOT OPERATIONAL LVZN ILJ~~Iu AVINiL~lh~lWjrOflmfl Callaway Plant identified thirty applicable Barton transmitters and connector assemblies In warehouse stock. Inspections of these operational spare parts identified three connectors, which had exposed conductors external to their seal. One connector had this defect on one lead wire and two connectors had this defect on both lead wires.
Callaway has also Identified that thirty-nine potentially affected transmitters are Installed in the plant. An Inspection plan has been developed to perform the required Inspections. based on safety significance, ALARA considerations, and potential accident environmental conditions. Additional reporting requirements associated with the installed components will be evaluated under 10CFR50.72 as required.
On 08119/2006, Callaway Plant personnel completed evaluations and determined the defective connectors constitute a defect per IOCFR21 requiring initial NRC notification within two days.
All other affected customers have been notified via the PRIME Nuclear Industry Advisory discussed above.
The NRC resident Inspectors have been notified of this Issue.
06/22/2006 THU 12:53 [TX/RI NO 9317] ID002
06/22/Z0036 14:14 FAX 6764202 QA Z001/002 NRC FORM 361
-H DK*.c
-m ~
U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EN#
EVENT NOTIFICATION WORKSHEET NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 OR 600-532-3469°. BACKUPS - (1aT) 301.951-0550 OR 800-449.3694-(2n) 301-415-0550 AND (3') 301-415-0553 'Licensees who maintain their own ETS are provided these telephone numbers.
NOTIFICATION TIME FACILTY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
David R. Waller 15:15 EDT Callaway Plant 1 Dennis Wade Griffith (573) 676-8595 EVENT TIME & ZONE EVENT DATE POWERI /MOD BEFORE POWER / MOPE AFTER 16:00 CDT 6/19/2006 1 100%/. POWER/ MODE 1 100 % POWER / MODE 1 I
EVENT CLASSIFICATIONS I1-Ir. Non-Emergency 10 CFR 50.72(b)(1) -(vXA) Sate S/I Capnlnity AINA GEN/AAEC ITS TF.F.RALEMLKGPNCY Dervnion ADEV tv)(R) P" C.PoNITV J AIN errs AR.EA EMbRGNCY SIT/AAC 4-Hr. Non-Emergency 10 CFR 50.72b)(2Z) (v)l Ca nf Rin ikelme AINC AtEST AI.PJAAPC _i_ TS RnAvls ,/D .M_.t(D,Amxdem rtikn AIND UNUSUAl.FV2NT UNUWAABC IKA) PCS DiDcharce1RCS ACCS _ xii) OffzxoMed.lAS SO 70"3NON-EM.ERGENC*Y (seenexicohi=) lvt1 [ JS Mmin' rWram) IAR.PS (;t{fi) LOM C001VAArm/Re-*p ACOMv FHYSICALSI&CURTUY (7171) DDDD (m)' Ofsi. I AF*., 60-Day Optional 10 CFR 50.73(a)(1)
AP.RIAI.FAXPOSUP,. B717 I-1r. Non-Emergencv 10 CFR 50.72(b)(3) I 1alwid Sp*:ahdSyWmAc1uxnon AINV
,tESS FOR DUMY Ms ID (A) rgtzrade.a2inin ADrG Other Unspecified Requirement (Identfy)
X r'rHFA UNSPEWILDRD *)( tlnCOInl*ne {Ifl) j n- AUNA X . 1 1 l..OCR1ZIrtrnmotldcxt/Nonconlanne NONRt INFUMArIoN ONLY NIN ! I vI l S A AI* NONR DESCRIPTION Include: System nftccted, actadous and their initiatng signals, causes, effect of event on plant, actions taken or planned. etc (Continue on back)
This report is a revision to report EN # 42658 reported on 06/21/2006.
INITIAL PART 21 NOTIFICATION - PRIME MEASUREMENT PRODUCTS, MODELS 763 AND 763A GAGE PRESSURE TRANSMITTERS AND MODEL 764 DIFFERENTIAL PRESSURE TRANSMITTERS This report is made per 10CFR21.21 Notification of failure to comply or existence of a defect and its evaluation.
Callaway Plant received a notification dated May 18. 2006, from PRIME Measurement Products (formerly ITT Barton) stating Barton Model 763 and 763A Gage Pressure Transmitters and Model 764 Differential Pressure Transmitters may have defective external lead-wire connectors, which could affect their performance during an accident. The notification provided by PRIME stated the affected transmitters were manufactured after May 1982 and shipped from the factory prior to April 1, 2006.
The potential defect Is characterized as follows: The transmitters' external lead wires enter the electronics enclosure through a hermetic seal called a connector assembly. The external lead wires are soldered to the glass sealed pins of the hermetic seal. Epoxy potting is used to structurally support the soldered wire connections and establish a seal to protect the solder connections from shorting, which could be caused by an electrically conductive accident environment. The defect is that the insulated portions of the wires in the connectors, manufactured after May 1982, may not be embedded deeply enough into the epoxy potting to provide an electrical connection that would not be affected In an accident environment.
The notification also states that actual transmitter Installation may preclude shorting of exposed conductors due to the existence of conduit, conduit seals, and special wire connectors which could protect the exposed wires at a defective connector from conductive moisture.
II - - I NOTIFICATIONS 'YES NO NWILLBE ANYTHING UNUSUAL OR NOT UNDERSTOOD?
NRC RESIDENT X El YES (explain above) NO STATE(s) X DID ALL SYSTEMS FUNCTION AS REQUIRED?
LOCAL X YES E NO (explain above)
OTHER GOV AGENCIES X MODE OF OPERATION ESTIMATED RESTART ADDITIONAL INFO ON MEDIA/PRESS RELEASE X UNTIL CORRECTED; I DATE: N/A BACK? N YES E] NO NRC FORM 361 (12-2000) 06/22/2006 THU 15:12 [TX/RX NO 9320] [001
06/22/2*006 14:15 FAX 6764202 OIA Z 002/002 PAGE 2OF2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE (TEMSpecific e "Tla ons should be covered in event deScrpin).
IQUID REASE RELEASE UNPLANNED RPLRýA- LANNED REL-ASE F1GASEOUS ONGOING TER.NATED MONITORED I IUNMONITORED I I a l PE I I T,& EXCEEDED ?M AL.AMS AREAS EVACUATED POR,.ONNE.LL*OSD O-CONTAMNATED I IOF'$ PRO"7ZnV, ACTIONS R*C*MMENDED state idele Pat to derlItlo100
_ _RslraseRate (Ci/sec) % T.S. LIMIT HOO GUIDE Total Activity (Ci) %T.S. LIMIT HO .GUIDE Nabk C."J 0.1 Ci/sec 1000 CI 10o1ie 10 uCi/sec 0.01 C1 ayrderhlae . : 1.uClfsee ________ I mCi lIqUid (,0WA VUM 10 uCi/min 0.1 C1 and uir Nd ,,obh,ren)_
Liquid Qt"ilt) 0.2 Ci/min 5 Ci Towl Activily I - II fLANT STACK CONDENSER/AIR EJ_,(,ETOR MAIN STEAM LINE SG BLOWDOW'N OTHER RAD MONITOR READIOGS t AA RM 3ETMVM"I RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMtS:, (tpeed!. derail./explanarionsshould be coycred in event descriion)
LOCATION OF THE LEAK (e.g.. SG #. valve, pipe, ere)
LEAK RATE UNITS: gpm/gpd T.S. LIMITS SUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS:
LIST OPSAPSTY RELATED EQUIPMENT NOT OPERATIONAl.
EVENT DESCRIPTION (Continuedfiom frunt)
Callaway Plant identified thirty applicable Barton transmitters and connector assemblies in warehouse stock. Inspections of these operational spare parts identified three connectors, which had exposed conductors external to their seal. One.
connector had this defect on one lead wire and two connectors had this defect on both lead wires.
Callaway has also identified that thirty-nine potentially affected transmitters are installed in the plant. An inspection plan has been developed to perform the required inspections, based on safety significance, ALARA considerations, and potential accident environmental conditions. Additional reporting requirements associated with the installed components will be evaluated under 10CFR50.72 as required.
UkP0LkV-.I The suppliers of the identified transmitters were Prime Measurement Products and Westinghouse Electric Corporation.
On 06/19/2006, Callaway Plant personnel completed evaluations and determined the defective connectors constitute a defect per 10CFR21 requiring initial NRC notification within two days.
All other affected customers have been notified via the PRIME Nuclear Industry Advisory discussed above, The NRC resident Inspectors have been notified of this Issue.
06/22/2006 THU 15:12 [TX/RX NO 9320] ID002