ML15223B268
| ML15223B268 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/07/2015 |
| From: | Alexander J Westinghouse |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15223B268 (3) | |
Text
08/07/2015 U.S. Nuclear Regulatory Commission Operations Center Event Revert1Part 21 (PAR) Event# 51298Rep Org: SEQUOYAH Notification Date / Time: 08/07/2015 15:48 (EDT)Supplier:
WESTINGHOUSE ELECTRIC COMPANY Event Date / Time: 10/23/2013 12:00 (EDT)Last Modification:
08/07/2015 Region: 1 Docket #:City: SODDY-DAISY Agreement State: YesCounty: License #:State: TNNRC Notified by: JOHN ALEXANDER Notifications:
ANTHONY MASTERS R20OHQ Ops Officer:
DONG HWA PARK PART 21/50.55 REACTORS EMAILEmergency Class: NON EMERGENCY 10 CFR Section:21.21 (d)(3)(i)
DEFECTS AND NONCOMPLIANCE PART 21 -DAMAGED SURVEILLANCE CAPSULES"In April 2015, during Sequoyah Nuclear Plant Unit I End of Cycle 20 refueling outage, the Tennessee ValleyAuthority (TVA) identified that there was unanticipated damage to the 'S' and 'W' surveillance capsules that werelocated within the reactor pressure vessel. Inspections determined that the surveillance capsules were notcontained within the intact designated baskets.
TVA conducted an extensive foreign object search and recoveryinitiative to recover the specimen capsule contents prior to concluding the refueling outage.-"During the October 2013 Sequoyah Unit 1 refueling outage, the Westinghouse Electric Company (WEC)relocated the above referenced surveillance capsules in accordance with Westinghouse procedure MRS-SPP-2970. The procedure specified the requirements for performing specimen capsule relocations.
WEC created adeviation when an inadequate procedure referenced in the applicable purchase order, which did not ensure properseating of the sample capsule, was used at Sequoyah Nuclear Plant Unit 1."TVA considers the above condition to be reportable pursuant to 10 CFR 21.21 as a defect associated with acondition that, if uncorrected, could have created a substantial safety hazard.""The NlRC Resident Inspector and the vendor were notified."
NRC EVENT NOTIFICATION WORKSHEET Page 1 of 2U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTERNRC EVENT NOTIFICATION WORKSHEET EN # 51298NRC OPERATION TELEPHONE NUMBER: PRIMARY -301-816-5100 OR 800-532-3469, BACKUP -[1st] 301-951-0500 or 800-449-3694
[2nd] 301-415-0550 AND [3rd] 301-415-0553 NOTIFICATION TIME FACILITY OR ORGANIZATION j UN IT NAME OF CALLER CALL BACK #.1 54B EDT Seq uoyah 1I John Alexander 438361EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER1200 EDT 10/23/2013 100% I Mode 1 100% / Mode 1EVENT CLASSIFICATIONS 1-Hr Non-Emergency 10 CFR 50.72(b)(1)
LI (v)(A) Safe SID Capability AINAEl GENERAL EMERGENCY Gen/AAEC El TS Deviation ADEV El (v)(B) RHR Capability AINBo] SITE AREA EMERGENCY SIT/AAEC 4-Hr Non-Emergency 10 CFR 50.72(b)(2)
El (v)(C) Control of Rad Release AINCEl ALERT ALE/AAEC El (i) TS Required S/D ASHU El (v)(D) Accident Mitigation AINDEl UNUSUAL EVENT UNU/AAEC El (iv)(A) ECCS Discharge to RCS ACCS El (xii) Offsite Medical AMEDEl 50.72 NON-EMERGENCY (see next columns)
El (iv)(B) RPS Actuation (scram) ARPS El (xiii) Lost Comm/AsmtlResp ACOMEl PHYSICAL SECURITY (73.71) DODD El] (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)
El MATERIAL/EXPOSURE B??? 8-Hr Non-Emergency 10 CFR 50.72(b)(3)
El Invalid Specified System Actuation AINVEl FITNESS FOR DUTY HFIT El (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)
[] Other Unspecified Reqmt. (see last column) El (ii)(B) Unanaly-zed Condition AUNA .10 CFR 21.21 NONRLi INFORMATION ONLY NINF El (iv)(A) Specified System Actuation AESF El NONRDESCRIPTION Include:
Systems affected, actuations
& their initiating
- signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on page 2)In April 2015 during Sequoyah Nuclear Plant Unit 1 End of Cycle 20 Refueling Outage, The Tennessee Valley Authority (TVA), identified that there was unanticipated damage to the "S" and 'W" surveillance capsules that were located within the Reactor Pressure Vessel.Inspections determined that the surveillance capsules were not contained within the intact designated baskets.
TVA conducted anextensive Foreign Object Search and Recovery initiative to recover the specimen capsule contents prior to concluding the refueling outage.During the October 2013 Sequoyah Unit 1 refueling outage, the Westinghouse Electric Company (WEC) relocated the above referenced surveillance capsules in accordance with Westinghouse procedure MRS-SPP-2970.
The procedure specified the requirements forperforming specimen capsule relocations.
WEC created a deviation when an inadequate procedure referenced in the applicable purchase order, which did not ensure proper seating of the sample capsule, was used at Sequoyah Nuclear Plant Unit 1.TVA considers the above~condition to be reportable pursuant to 10 CFR 21.21 as a defect associated with a condition that, ifuncorrected, could have created a substantial safety hazard.The NRC Resident Inspector and the vendor were notified.
NOTIFICATIONS YES NO WILL BE Anything Unusual or NotNRC RESIDENT 0] El El 1Understood?
El Yes (Explain above) 0] NoSTATE(s)
[] El [ Did All Systems Function As 0YsE oEpanaoeLOCAL El 0] El Required?
]Ys[Noxpanbve Other Gov Agencies El 0] El Mode of Operation Estimated Additional INFO on page 2?MedialPress Release ____ [] El Until Corrected:
1 Restart Date: N/A El Yes 0] NoPage 1 of 2Page of 2NPG-SPP-03.5-1
[08-06-2010]
NRC EVENT NOTIFICATION WORKSHEET Page 2 of 2RADIOLOGICAL RELEASES:
CHECK OR FILL IN APPLICABLE ITEMS (specific detailslexlplanations should be covered in event descriotion)
ELiquid Release I Gaseous Release EUnplanned Release I Planned Release IEOngoing EMonitored Unmonitored EOffsite Release T.S. Exceeded ERM Alarms Areas Evacuated EI Personnel Exposed or Contaminated E L Offsite Protective Actions Recommended
- Sat release path in description.
Release Rate (Cilsec)
% T. S. Limit HOO Guide Total Activity (Ci) % T.S. Limit HOO GuideNoble Gas 0.1 Ci/sec ________1000 CiIodine 10 uCilsec _________0.01 CiParticulate I uCilsec 1_______
mCiLiquid (excluding tritum & 10 uCilmin 0.1 Cidissolved noble gases) ________Liquid (tritium) 0.2 Ci/min __________________5 CiTotal Activity
___________________
Plant Stack CondenserlAir Ejector Min S~team Line SG Blowdw OtherRAD Monitor Readings:II Alarm Setpoints:
% T.S. Limit (if applicable)
RCS or SG Tube Leaks: or Fill in Applicable Items: (specific details/explanations should be covered in event description)
LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.)LEAK RATE UNITS: gpm/gpd T. S. LIMITS SUDDEN OR LONG TERM DEVELOPMENT LEAK START DATE TIME COOLANT PRIMARY -SECONDARY
-ACTIVITY
& UNITSLIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continued from page 1)Page 2 of 2Pag 2 f 2NPG-SPP-03,5-1
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