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 Revert Pa*e 1 Part 21 (PAR) Event# 51298 Rep 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: Yes County: License #:
State: TN NRC Notified by: JOHN ALEXANDER Notifications: ANTHONY MASTERS R20O HQ Ops Officer: DONG HWA PARK PART 21/50.55 REACTORS EMAIL Emergency 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 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 an extensive 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 for performing 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, 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 2 U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER NRC EVENT NOTIFICATION WORKSHEET EN # 51298 NRC 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 438361 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER 1200 EDT 10/23/2013 100% I Mode 1 100% / Mode 1 EVENT CLASSIFICATIONS 1-Hr Non-Emergency 10 CFR 50.72(b)(1) LI (v)(A) Safe SID Capability AINA El GENERAL EMERGENCY Gen/AAEC El TS Deviation ADEV El (v)(B) RHR Capability AINB o] SITE AREA EMERGENCY SIT/AAEC 4-Hr Non-Emergency 10 CFR 50.72(b)(2) El (v)(C) Control of Rad Release AINC El ALERT ALE/AAEC El (i) TS Required S/D ASHU El (v)(D) Accident Mitigation AIND El UNUSUAL EVENT UNU/AAEC El (iv)(A) ECCS Discharge to RCS ACCS El (xii) Offsite Medical AMED El 50.72 NON-EMERGENCY (see next columns) El (iv)(B) RPS Actuation (scram) ARPS El (xiii) Lost Comm/AsmtlResp ACOM El 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 AINV El 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 0* .10 CFR 21.21 NONR Li INFORMATION ONLY NINF El (iv)(A) Specified System Actuation AESF El NONR DESCRIPTION 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 an extensive 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 for performing 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, if uncorrected, could have created a substantial safety hazard.
The NRC Resident Inspector and the vendor were notified.
NOTIFICATIONS YES NO WILL BE Anything Unusual or Not NRC RESIDENT 0] El El 1Understood? El Yes (Explain above) 0] No STATE(s) [] El
[ Did All Systems Function As 0YsE oEpanaoe LOCAL 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] No Page 1 of 2 Page of 2NPG-SPP-03.5-1[08-06-2010]
NRC EVENT NOTIFICATION WORKSHEET Page 2 of 2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific detailslexlplanations should be covered in event descriotion)
ELiquid EMonitoredRelease I Gaseous Release Unmonitored EI Personnel Exposed or Contaminated EUnplanned EOffsite ReleaseRelease I Planned Release T.S. Exceeded L Offsite Protective Actions Recommended E
IEOngoing ERM Alarms I*Terminated Areas Evacuated
- Sat release path in description.
Release Rate (Cilsec) % T. S. Limit HOO Guide Total Activity (Ci) % T.S. Limit HOO Guide Noble Gas 0.1 Ci/sec ________1000 Ci Iodine 10 uCilsec _________0.01 Ci Particulate I uCilsec mCi 1_______
Liquid (excluding tritum & 10 uCilmin 0.1 Ci dissolved noble gases) ________
Liquid (tritium) 0.2 Ci/min __________________5 Ci Total Activity ______
_____________ Plant Stack CondenserlAir Ejector Min S~team Line SG Blowdw Other RAD Monitor Readings:II Alarm Setpoints:
% T.S. Limit (if applicable)
RCS or SG Tube Leaks: Check* or Fill in Applicable Items: (specific details/explanationsshould 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 & UNITS LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continuedfrom page 1)
Page 2 of 2 Pag 2 f 2NPG-SPP-03,5-1 [08-06-2010]