ML070670447
| ML070670447 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/25/2001 |
| From: | Vermont Yankee |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| ER-20012009 | |
| Download: ML070670447 (12) | |
Text
VERMONT YANKEE EVENT REPORT Event Level (Circle One)
(complete at screening meeting)
ER NO. ER-20012009 PART I: IDENTIFICATION OF EVENT (Originator) (Fill in all known data)
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MAIST-SUPPORT A) Initiated By (Print) LEONARD MURPHY Date 09/2s/2001 Phone #
5742 Department B) Event/Discovery (Date) 09/25/2001 Occurred (Time) 3:oo PM Equip No(s).
TRU-3 System(s) affected HVAC c ) Event
Title:
Sen-ice Waater Leak in TRU-3 Cooling Coil D) Reference Document (WO, Procedure, Calculation, Drawing, Audit/Surveillance No., etc. See Attached Page E) Event Descriotion (Describe the event and susuected cause. if known)
How Identified L Self-Revealing Self-Identified By Others External As a result of apparent increased water flow to Radwastc thc Operations Department invcstigatcd posiblc sourccs of leakage. Estimated Service Water leakage of approximately I gpm was observed at the condcnsatc drain of TRU-3. The SS, and iMaintcnancc management were notified. In 1999 a "Life Cycle Management" issuc with vintage recirculation unit cooling coils was idcntified by a serifs of through wall leaks caused by flow induced erosion over thc 28 year QAD
- Continued on Attached Page F) Immediate Action Taken - Recommendations. if any.
W W O NO.
Nonconformance Tags Installed? &NO
-YES (if segregation required)
NOTIFIED SHIFT SUPERVISOR YOTlFlED APPROPRIATE MANACERS/DEPT Shift Super5,isur notlfled PART 2: REVIEW OF EVENT (Department Head)
A) Deoartment Head Review
- 1.
- 2.
Security-Related Event?
X N O -
YES (immediately notify SSSISS)
SS Review Required (operability conceddegraded equipment AP 0156, LCO, TS)?-NO X N O L Y E S (deliver to SS)
YES (FAX ER to TreasuryIRisk Mgr. for
- 3.
Personnel InjuryIAccident?
Accident Type (Discuss with Safety Coord.)
VY Personnel)
- 4.
Recommended Event Level 3
X N O -
YES
- 5.
Nuclear Network entry required?
- 6.
Recommended Responsible Department?
SYSTEM ESCISEERISC B) If degraded or nonconforming SSC's will remain ouerable then record and attach Ouerabiliw Basis/ Justification. Refer to AP 0167.
Bnsed upon attached, Operation of TRU-3 nith a leak from the coil does not represent an uperability concern.
'I C) Additional CommentslActions Taken:
INITIATED W O R N 0 Department Head SignatureiDate BRIAX XAECK
/
09/25/2001 PART 3: REPORTABILITY AND OPERABILITY (SSISE)
A) Event reportable per AP 0156?
B) Per AP 0167 degraded or nonconforming SSCs will remain operable?
E N / A -NO
-YES C) Documentation for Operability Determination attached?
X NIA
-YES IfYES:
-Form attached (VYAPF 0167.01) and/or L N o t Reportable -Reponable Attach copy of VYAPF 0156.01 if reportable or if additional notifications required.
Evaluation attached or included in ER Shift Supervisor/Date/Time I
I Repan Pnnled On 12113R001 a14:48 PM
PART 4: EVENT SCREENING MEETING ER NO. ER-20012009 A) Additional Initial Notifications and Reviews Required? XNO
-YES B) BMO Required? 5 x 0 -YES (Processing Time -
Resp. Dept.
BMO #
)
C) Reportable?
L N O -YES Further Evaluation Required (Assigned To 1
E) Potential Reactivity Management Event?
G) NRC Performance Indicator?
D) Potential 1 OCFR50.65 Maintenance Rule Functional Failure?
X N O
-YES F) NRC Significance Determination Process?
XNO
-YES X N O
-YES X N O
-YES H) StartupiMode Restraint?LNO -YES Specific Action Rcquircd:
Rcsp. Dcpt.:
Modc Affcctcd:
I)
Human Performance Related?
x NO
-YES If YES
-Consequential
-Nan-consequential J) Event Level Determined 3
K) Responsibility for ER Investigation and Recommending Corrective Action Assigned to (Dept.):
L) Additional Considerations Additional Reviewers: -Training See Attached Page SYSTEM ENGINEERISG Maint. Rule Coordinator Reactor Engineer Fire Protection Engineer Radiation Protection Safety Coordinator Other: Specify M) Completed by/Date CRAIG XICHOLS 1
09/27/2001 PART 5: EVENT INVESTIGATION (Assigned Department)
A) Investigation Type: (RCA rcquircd for Lcvcl 1 ; Optional for Lcvcl 2)
B)
Investigation Results:
RCA ACE E M P C (DH check one)
I. Attach report for Level I and 2 ERs (see PP 7017 for details.)
X N O
-YES
- 2. Note Most Probable Cause Codes (Lcvcl3 ERs)
See Attached Page C) MRFF D) Event Reportable: L N O -YES (LER No.
)
- 3. Startup/Mode Restraint: -
Resolved Approved:
E) Estimated hours to perform investigation 2
- 4. Adverse Trend x NO -YES F) Actions Taken (Level 3 ER Disposition):
- 5. NRC PI color change L N O -YES See Attached Page Investigator (if other than Dept. Head)
Carlo Barton
/
10/23/2001 DH Review RICHARD ROSIN I
10/24/2001 PART 6: REVIEWS
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A) Additional Reviews:
I I
Design Eng. (Design Deficiency, "Use-As-Is dispositions)
B)
QAD (Level 1)
Comments:
See Attached Page PART 7: APPROVALS (Forward to the TSM after final approval)
A)
RICHARD RUSlN
/
10124/2001 I
/
Department Head (Level 1,2,3 ERs)
Plant Mgr (Level 1 ERs, Some Level 2s)
PART 8: CANCELLATIONKLOSEOUT SuptlDir designee (Level I & 2 ERs) air. Of Operations (Level 1 ERs)
PORC (Level 1 ERs)
B)
/
/
See Attached Page fur Comments A) Repairhework complete I
Nonconformance Tags removed I
B) ER Cancelled By (SuptlDiridesignee)
I Basis/Cancellation Comments:
C) Technical Support (ER Database Updated, Copies Distributed, Commitments Initiated)
ERCIDate Clikey Carun I
12/13/2001 VY APF-0009.0 I AI' 0009 Rev. I2 Pags 2 or2 ReponPnnlsdon 1211312001 a14:4BPM
Attached Page for Event Report ER-20012009 PART 1 Affected Eauiument Reference Documents 00-000490-000 Affected Svstems Work Orders Event Descriution
- +Continued From Page 1 life of vintage coils. A replacment plan was developed and a replacmeent coil and ready status WO are available for replacement of the cooling coil in TRU-3. WO 00-00490-000 is currently scheduled for 12/31/2001. The Control Room has indicated SW to TRU-3 will be isolated to control the effluent now to Radwaste.
Operability Assesment:
The NNS design funtion of TRU-3 is to maintain area temperatures appropriate for equipment and personnel.
TRU-3 is operable, but degraded because the estimated I gpm leakage is a small fraction of the design cooling water flow of 72.4 gpm. Assuming the leakage is from the supply header the reduction in service water flow through the coil would have a negligable effect on total heat removal.
Immediate Action Taken PART 2 Additional Comments I OrJerabilitv Justification DH Actions Taken PART 4 SDecific Action Reauired Additional Reviewers Suecified Additional Considerations Evaluate need to do additional periodic leak monitoring of RRUlTRU components.
Rescreened 9/27/01. No MRFF, TRUs not in scope.
PART 5 Causal Factors P2j4 Component aging.
Corrective Actions Action Description Status Department DueDate CTS CTS Number Tracked SYSTEM ENGINEERING 11124/01 N
INVESTIGATED THE Discussed issue with PROBLEM Lenny Murphy. He provided a list of coils that are original and may suffer end of life leaks. That list is attached. The list shows that the TRU-3 coil is scheduled for replacement per WO 00-00490-000 on 12/31/01.
Attached Page for Event Report ER-20012009 INVESTIGATED THE Additionallperiodic leak SYSTEM ENGINEERING 11124101 PROBLEM monitoring is not required. The RRUs and TRUs are to be replaced per the attached list. If additional leaks become greater, they will be addressed at that time.
PART 6 Additional Reviews Reviewer Comments RICHARD RUSlN (System Engineering DH)
N A long term plan has been established to replace coils throughout the plant (KIL2000-IO). I agree that no additional monitoring is necessary at this time.
PART 7 ApDrOVer Comments RICHARD RUSIN (System Engineering DH)
The CAS with due dates of 11/24/01 do not require AP0028 commitment items. Both items are complete as of 10/24/01.
PART 8 Basis I Cancellation Comments Recart Pmleaon 1211312001 a1 4-48 PM
VERMONT YANKEE Event Level (Circle One)
ER NO. EX-20012009 (complete at screening meeting)
EVENT REPORT m@yd
?A?/*,
PART 1: IDENTIFICATION OF EVENT (Originator) (Fiil in alt known data)
A) Initiated By (Print) LEONARD MURPHY Dat wmooi Phone#
$742 Department MAIM - SUPPORT B) EventDiscoveiy (Date)
WRMOOI Occurred (Time) 3:w PM Equip No(s).
m u - 3 System(s) affected HYAC C) EventTitle: ~ervinw D)
(WO, Procedure, Calculation, Drawing, AudiUSurveillance No., etc.) o0-ooo49o-ooo How Identified: 5 Self-Revealing Self-Identified By Others QAD External E) -eevent-As n result of apparent increased water flow to Radwaste the Operations Depnrtmcnt investigated posible source? of leakagc Estimated Service Water leakage of approximately 1 gpm wns obscrved at the condenrate drain of TRU-3. The SS, and Maintenance management were notified. In 1999 a "Life Cycle Management" issue with vintage recirculation nnlt coolng coils wms identified by P series of through wall leaks caused by flow induced erosion over the 28 year life of vintage coils. A rcplacment plan was developed nnd a rcplacmeent coil rnd ready status WO nre avvtlilable for replrcernent of the cooling coil in TRU-3. WO W-oo49O-OOO b currently scheduled for 12/31/2001. The Control Room hus indieatcd SW to TRU-3 will be isolated to control the eMucnt flow to RadwasteOperrbilily AsscsmcntzThc NNS design funtion of TRU-3 is to mnintain nren temperaturcs npproprinte for equipmenl and penonneLTRU-3 is opernble, but degraded because the estimated I gpm lenkrgc is a small fraction of the design
- Event Description Continued on Attnchment *****
F j
-Recorn-I W-0.
@ - $73 Nonconformance Tags Installed? &NO
-YES (if segregation required)
NOTIFIED SHIFT SUPERVISOR NOTIFIED APPROPRIATE MANAGERSmElT Shirt Supervisor notirsd
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PART 2: REVIEW OF EVENT (Department Head)
A) D e o a r t m c n t R e v i e a I.
- 2.
Security-Related Event?
t40 YES (immediately notify SSSlSS)
- 3.
Personnel Injury/Accident?
SS Review Required (operability conceddegraded equipment AP 0156, LCO, TS)? -NO
&(deliver to SS)
YES (FAX ER to Treasurymisk Mgr. for VY Personnel)
Accident Type (Discuss with Safety Coord )
4 Recommended Event Leve 3 5
Nuclear Network entry required?
6 Recommended Responsible Department')
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Department Head SignalurdDate L$
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PART 3: REPORTABILITY AND OPERABILITY (SSISE)
A) Event reportable per AP 01%?
B) Per AP 0167 degraded or nonconforming SSCs will remain operable?
C ) Documentation for Operability Determination attached?
01 Reportable -Reportable Attach copy of VYAPF 0156.01 if reportable or if additional notifications required.
YES 3
S
- YES
Form attached (VYAPF 0167.01) and/or Evaluation attached or included in ER Shift Supervisor/DatefTirne I 9&?54@/
J /&=
WAPF-0009.01 (Sample)
AP 0009 Rcv.12 Pnge I of 2
'ART 4: EVENT SCREENING MEETING ER NO. ER-20012009
-~
- 1) Additional Initial Notifications and Reviews Required? A0 -YES
- 3) BMO Required?
Rap. Dept.
BMO ##
)
Further Evaluation Required (Assigned TO 1
- 2) Reportable?
-YES
&O
-YES (Processing Time ___
I) Potential 10CFR50.65 Maintenance Rule Functional Failure?
- 3) Potential Reactivity Management Event?
A0 -
YES
- )
NRC Significance Determination Process?
-40
-YES
- 3) NRC Performance Indicator?
- 4) StartupiMode Restraint? &
-YE Specific Action Re uired:
.) Human Performance Related7
& YES If YES
-Consequential
-Nan-consequential I)
Event Level Determined L N O 9
e
+/./
Resp. De@.:
Mode AWcted K) Responsibility for ER Assigned to (Dept.):
Reactor Engineer Fire Protection Engineer Radiation Protection Safety Coordinator Other: Specify M) Completed byma PART 5: EVE6INVESTIGATION (Assigned Department)
PART 7: APPROVALS (Forward to the TSM after final approval)
I
-.cc --f-&
t I
PORC (Level 1 ERs)
A@Z &
& ' ] J 1 c J y l i y Department Head (Level 1,2,3 ERs)
-designee (Level 1 & 2 nzS)
B)
I I
Plant Mgr (Level I ERs, Some Level 2s)
Dir. OfOperations (Level I ERs)
PART 8: CANCELLATIONKLOSEOUT A) Repairlrework complete I
Nonconformance Tags removed I
B) ER Cancelled By (Supt/Dir/designee)
I Basis/Cancellation Comments:
I VY APF-0009.0 I
AP 0009 RN. I2 P ~ e Z o f 2
Attachment for Event Report ER-ZOOt2009 PART 1 Affected Equipment Affected Svstems Reference Documents Event Description
- .** Event Description Continued from Page One nm cooling water flow of 72A gpm. Assuming the teakage is from the supply header the reduction in senrice water flow through the coil would have a negligable effect on total heat removal. - End of Event Description rr*ll immediate Actlon Taken PART 2 Additional Comments I Operabllitv Justiffcatton Event Description Continued from Page One-cooling water flow of 724 gpm. Assuming the leakage is from the supply header the reduction In service Water flow through the coil would have a negligable effect on total heat removal.
- End of Event Descrfptlon -
Additional Comments I Actions Taken PART 4 Specific Actlon Reauired Additional Reviewers Speclfled PART 5 Causal Factors Corrective Actions
A S S I G N M E N T S I CR-VTY-2001-02009 En%w I
Version: 1 Significance Code: C Classification Code: C Owner Group: Eng SYS System Eng Mgmt Performed By: Nichols,Craig J 09/27/2001 0O:OO Assignment
Description:
Pre-screening Comments / Operability Justification:
Based upon attached, Operation of TRU-3 with a leak from the coil does not represent an operability concern.
DH Review Performed By: NAECK,BRIAN on 09/25/2001 Screening Comments:
Evaluate need to do additional periodic leak monitoring of RRU/TRU components.
Rescreened 9/27/0 1. No MRFF, TRUs not in scope.
Niagara indicators set at screening.
How Identified :: Self-Revealing
Enfefg-y CA Number:
I Assigned By: CRG/CARB/OSRC Nichols,Craig J Assigned To: Eng SYS System Eng Mgmt Subassigned To : Eng SYS System Eng Staff CORRECTIVE ACTION CR-VTY -2001-02009 Originated By: Nichols,Craig J Performed By: Rusin,Richard L 9/27/200 1 0O:OO:OO 10/24/2001 11:38:0C Subperformed By: Barton,Carlo 10/23/200 1 I2:32:0C Approved By:
Closed By: Rusin,Richard L 10/24/200 I 1 1 :42:0C
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Current Due Date: I 1 /24/200 I CA Type: CR DISPOSITION Initial Due Date: 1 1 /24/200 1 Plant Constraint: NONE CA
Description:
This CA for Disposition was generated during Niagara to PCRS Conversion Screening Comments:
Evaluate need to do additional periodic leak monitoring of RRU/TRU components.
Rescreened 9/27/0 1. No MRFF, TRUs not in scope.
Investigate Type :: Most Probable Cause
Response
CA for Disposition Reviews:
System Engineering : RUSIN,RICHARD : 10/24/2001 1 1 :38:50 AM : A long term plan has been established to replace coils throughout the plant (KIL2000- IO). I agree that no additional monitoring is necessary at this time.
Approvals:
System Engineering : RUSIN,RICHARD : 10/24/2001 1 1:42:32 AM : The CAS with due dates of 11/24/01 do not require AP0028 commitment items. Both items are complete as of 10/24/01.
Niagara indicators set during investigation.
Subresponse :
Cause Codes ::
P2j4 - Component aging.
Corrective Actions identified during Investigation:
Action : Description : Done : Department : Due Date : CTS Number : CTS Tracked INVESTIGATED THE PROBLEM : Discussed issue with Lenny Murphy. He provided a list of coils that are original and may suffer end of life leaks. That list is attached. The list shows that the TRU-3 coil is scheduled for replacement per WO 00-00490-000 on 12/3 1/01. : Open : SYSTEM ENGINEERING : 1 1/24/2001 : : N INVESTIGATED THE PROBLEM : Additional/periodic leak monitoring is not required. The RRUs and TRUs are to be replaced per the attached list. If additional leaks become greater, they will be addressed at that time. : Open : SYSTEM ENGINEERING : 1 1 /24/200 1 : : N Closure Comments:
This CA for Disposition was generated from ER Investigation information from the VY Niagara application on 10/30/2003.
Entegy CONDITION REPORT Originator: Murphy,Leonard W Originator Group: Maint Support Mgmt Supervisor Name:
Discovered Date: 09/25/200 1 15:OO CR-VTY -2001-02009 Originator Phone: 5742 Operability Required: N Reportability Required: N Initiated Date: 09/25/200 I 0O:OO Condition
Description:
Service Waater Leak in TRU-3 Cooling Coil As a result of apparent increased water flow to Radwaste the Operations Department investigated posible sources of leakage.
Estimated Service Water leakage of approximately 1 gpm was observed at the condensate drain of TRU-3. The SS, and Maintenance management were notified. In 1999 a "Life Cycle Management" issue with vintage recirculation unit cooling coils was identified by a series of through wall leaks caused by flow induced erosion over the 28 year life of vintage coils. A replacment plan was developed and a replacmeent coil and ready status WO are available for replacement of the cooling coil in TRU-3. WO 00-00490-000 is currently scheduled for 12/31/2001. The Control Room has indicated SW to TRU-3 will be isolated to control the effluent flow to Radwaste.
Operability Assesment:
The NNS design funtion of TRU-3 is to maintain area temperatures appropriate for equipment and personnel.
TRU-3 is operable, but degraded because the estimated 1 gpm leakage is a small fraction of the design cooling water flow of 72.4 gpm. Assuming the leakage is from the supply header the reduction in service water flow through the coil would have a negligable effect on total heat removal.
Immediate Action
Description:
NOTIFED SHIFT SUPERVISOR : Complete : Shift Supervisor notified NOTIFIED APPROPRIATE MANAGERSDEPT : Complete Suggested Action
Description:
INITIATED W O W 0 : Complete : 00-490 EQUIPMENT:
Tag Name TRU-3 REFERENCE ITEMS:
Tvpe Code wo Tap Suffix Name Component Code Process Svstem Code W A C Description 00-000490-000 TRENDING (For Reference Purposes Only):
Trend Tvue Trend Code HOW IDENTIFIED HI-SELF-REVEALING KEY ACTIVITY KA-PM PERSONNEL INJURY PI-NON-INJURY WORK PROCESS WP-MN CAUSAL FACTOR CODES CFC-P2 J4 Attachments:
Closure Description VINTAGE COIL DATA TABLE 2.DOC T T 1 r n
n V
d
ADMIN CR-VTY -2001-02009
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Initiated Date: 9/25/200 I 0:OO Owner Group :Eng SYS System Eng Mgmt Current
Contact:
Current Significance: C Closed by: Caron,Mikey 12/13/200 1 0:OO Summary
Description:
Service Waater Leak in TRU-3 Cooling Coil Remarks
Description:
The ER 200 12009 was migrated from the VY Niagara application on 10/30/2003 to generate this CR.
Closure
Description:
Attachment Header Document Name:
Document Location blosure Description Attach