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Event Notification Report for October 24, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/21/2016 - 10/24/2016

** EVENT NUMBERS **


51915 52218 52296 52315

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Part 21 Event Number: 51915
Rep Org: ELECTROSWITCH
Licensee: ELECTROSWITCH
Region: 1
City: WEYMOUTH State: MA
County:
License #:
Agreement: Y
Docket: 99900833
NRC Notified By: LARRY FRIEDMAN
HQ OPS Officer: BETHANY CECERE
Notification Date: 05/10/2016
Notification Time: 15:59 [ET]
Event Date: 05/10/2016
Event Time: [EDT]
Last Update Date: 10/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
ART BURRITT (R1DO)
JAMIE HEISSERER (R2DO)
ERIC DUNCAN (R3DO)
VIVIAN CAMPBELL (R4DO)
PART 21/50.55 REACTO (EMAI)

Event Text

PART 21 REPORTING OF DEFECTS AND NONCOMPLIANCE

The following is a synopsis of information received via fax:

"Various Electroswitch products - Series 24 Instrument & Control (Part #24XX, 24XXX, 243XX, 74XXX), Series 24 LOR (part #78XX), Series 24 LOR/ER (part #78XX), Series 24 CSR (part #88XX), Series 24 LSR (part #92XX), Series 31 Instrument & Control (part #31XXX, 65XXX, 75XXX), Series 31 TR/LSR (part #93XX), Series 20 Cam (part #20KB, 20KD, 20LB, 20LD, 20MB, 20MD, 20MF, 20MG, 20PF, 20PG, 20PH, 20PJ, 20PL, 20PY), Series 20 Module (part #10XXX, 17XXX, 18XXX, 19XXX, 29XXX, 30XXX, 32XXX,38XXX,40XXX, 60XXX, 61XXX, 62XXX, 63XXX) [have a potential deviation (departure from the technical requirements included in the procure document)]

"It was determined on May 10, 2016 that Electroswitch does not have the capability to perform the evaluation to determine if a defect, which could create a substantial safety hazard, exists.

"Any Electroswitch product that has a part number listed above and was sold as a Safety-Related Class 1E product [may contain the deviation].

The two nonconformance issues are:

"Initial Product Qualification Tests for Dielectric Withstanding Voltage, Insulation Resistance and Contact Resistance as defined in Electroswitch's ESC-STD-1000 Rev. 3 dated 9/3/1984 General Specifications for Rotary Switches and Auxiliary Relays for Utility Applications including Class 1E Equipment for Nuclear Power Generating Stations was found to be in contradiction to IEEE C37.90-1978 Relays and Relay Systems Associated with Electric Power Apparatus.

"Electroswitch did not procure materials, parts, equipment and/or services from an Appendix B supplier nor were applicable Commercial Grade Surveys, Source Inspections and Material Analyses performed for the following materials:
Precious metal blade overlay material
Red metal blade material
Precious metal overlay thickness of switch blade material
Molding compound of switch insulators (terminal decks and barriers)
Carbon steel for securing rods
Solenoids
Relays
Services (test labs) pertaining to product qualification

Electroswitch is attempting to determine which NRC licensees are potentially affected.

"The following personnel may be contacted regarding this notification:

Larry Friedman
Quality Assurance Manager
781-607-3309

Ed Reszenski
Engineering Manager
781-607-3341"


* * * UPDATE FROM LARRY FRIEDMAN TO DONALD NORWOOD AT 1656 EDT ON 5/11/2016 * * *

The following information was received via fax:

Below is the list of utilities (and plants where specified) which were notified of Electroswitch's decision to end the Appendix B Quality Assurance Program:

Ameren Energy

Dominion Energy

Duke Energy

Energy Northwest

Entergy Nuclear (Waterford 3 Nuclear)

Entergy Nuclear (Pilgrim Power Plant)

Entergy Nuclear (Indian Point Energy)

Xcel Energy (Monticello Nuclear)

MPR Associates for FPL

Nebraska Public Power (Cooper Nuclear)

Nextera (Point Beach Nuclear)

Xcel Energy (Prairie Island Gen)

Southern Power (Hatch)

Southern Power (Vogtle)

TVA

TVA (Watts Bar Nuclear)

Wolf Creek Nuclear

Notified R1DO (Burritt), R2DO (Heisserer), R3DO (Duncan) and R4DO (Campbell) and via E-mail Part 21/50.55 Reactors Group.

* * * UPDATE FROM LARRY FRIEDMAN TO DONG HWA PARK AT 1617 EDT ON 8/25/2016 * * *

The following information was received via fax:

"Electroswitch is formally requesting a thirty (30) day extension to complete the evaluation by Sept. 24, 2016 in order to provide detailed answers to the questions and provide any needed updates to the Part 21 notification report."

Notified R1DO (Dimitriadis), R2DO (Michel), R3DO (Cameron) and R4DO (Kellar) and Part 21/50.55 Reactors Group via E-mail.

* * * UPDATE FROM LARRY FRIEDMAN TO JOHN SHOEMAKER AT 1349 EDT ON 10/21/2016 * * *

The following information was received via fax:

"Subject: Response to questions about Electroswitch's response to the U.S. Nuclear Regulatory Commission Inspection Report NO. 99900833/2016-201 and Notice of Nonconformance (Letter from Terry W. Jackson, Branch Chief dated August 5, 2016."

Notified R1DO (Cahill), R2DO (Masters), R3DO (Orth) and R4DO (Kramer) and Part 21/50.55 Reactors Group via E-mail.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 52218
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: LARRY HAUTH
HQ OPS Officer: STEVEN VITTO
Notification Date: 09/02/2016
Notification Time: 11:29 [ET]
Event Date: 09/02/2016
Event Time: 08:08 [CDT]
Last Update Date: 10/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
GREG WARNICK (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 0 Hot Standby

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

"While operating in MODE 1 at 100 percent rated thermal power and placing Excess Letdown in service for Reactor Coolant System (RCS) leak detection, RCS operational leakage exceeded 1 gpm [gallon per minute] unidentified leakage as identified by performing RCS Water Inventory Balance using the Nuclear Plant Information System Computer. This required the entry into Technical Specification (TS) Limiting Condition of Operation (LCO) 3.4.13 Condition B at 0808 [CDT] on 9/2/16. The associated action is to place the unit into Mode 3 in 6 hours. Trending of containment sump level indicates the leakage is inside containment with the exact location within containment unknown. Containment inspection is being performed to try and identify the source of Reactor Coolant System leakage. NRC Resident Inspector has been notified. Re-alignment of the Letdown System back to its normal arrangement has subsequently reduced RCS leak rate to 0.521 gpm at 0652 CDT on 9/2/16.

"Unusual or Not Understood - Leak Location is not known at this time."

Maximum leak rate recorded was 1.358 gpm. The leak was first discovered at 08/31/16 at 1519 CDT.
Safety Related Equipment not operational - Reactor Vessel Level Indicating System (TS 3.3.3).

* * * RETRACTION AT 1101 EDT ON 10/21/2016 FROM LARRY HAUTH TO JEFF HERRERA * * *

"Wolf Creek Nuclear Operating Corporation is retracting the 10 CFR 50.72(b)(2)(i) notification based on subsequent review of the event. The calculation of unidentified leak rate which triggered entry into the Mode 3 Required Action Statement was performed immediately after placing RCS Excess Letdown in service. An evaluation of the leak rate calculation determined that the leak rate was invalid due to performance of the RCS water inventory balance during non-steady state operating conditions. This was contrary to the requirements of TS Surveillance Requirement 3.4.13.1, as this test was performed while charging and letdown flows were being stabilized following the alignment of excess letdown. A walk down of the Excess Letdown system while in-service determined no leakage. Subsequent RCS water inventory balances performed with Excess Letdown in service under steady state operating conditions while in Mode 3 at normal operating pressure and temperature determined the maximum calculated unidentified leak rate was 0.675 gpm.

"After the plant entered Mode 3 a non-RCS pressure boundary leak was identified during equipment walk downs on a seal weld from the reactor vessel head core exit thermocouple nozzle assembly 77.

"The leakage did not impact the ability to shut down the unit. No TS limits were exceeded during this event.

"Therefore, the plant shutdown to investigate and correct leakage past the seal weld of a threaded connection does not meet the reporting requirements of 10 CFR 50.72.

"The NRC Resident Inspector has been notified."

Notified the R4DO (Kramer).

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Non-Agreement State Event Number: 52296
Rep Org: BAYER CORPSCIENCE LP
Licensee: BAYER CORPSCIENCE LP
Region: 3
City: KANSAS CITY State: MO
County:
License #: 24-03830-01
Agreement: N
Docket:
NRC Notified By: STEVEN SCHERICH
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/14/2016
Notification Time: 14:17 [ET]
Event Date: 10/13/2016
Event Time: 15:00 [CDT]
Last Update Date: 10/14/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

STUCK SHUTTER ON A DENSITY GAUGE

The licensee Radiation Safety Officer (RSO) determined that the shutter to a Berthold Model LB7442 gauge with a 1 Ci Cs-137 source (serial number: 012\06) did not shut during biannual maintenance checks. Personnel is informed about the gauge with proper signage, and the RSO does not believe any exposure to personnel occurred, because the shutter is normally in the open position. A licensed Berthold technician has been contacted and will come to the site to repair the gauge.

The licensee notified NRC Region 3 (Nieves).

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Power Reactor Event Number: 52315
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CURTIS MARTIN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/23/2016
Notification Time: 23:41 [ET]
Event Date: 10/23/2016
Event Time: 19:08 [CDT]
Last Update Date: 10/23/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN KRAMER (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

CONTROL ROOM EMERGENCY VENTILATION FAN INOPERABLE DUE TO ELEVATED VIBRATION

"At 1908 CDT on 10/23/16, elevated vibration readings were identified on Cooper Nuclear Station [CNS], Control Room Emergency Filter System (CREFS) supply fan A. Vibration readings were evaluated by Engineering and were determined to be indicative of bearing failure on supply fan A. The Control Room declared CREFS inoperable and entered LCO 3.7.4, Condition A, which requires restoration of CREFS to operable status in 7 days. Repair activities have been initiated for this condition.

"The plant is currently in Mode 5, with refueling activities and OPDRVs [Operation with Potential to Drain Reactor Vessel] in progress. CNS is not currently in the mode of applicability for a USAR defined accident. This condition is being conservatively reported under 10 CFR 50.72(b)(3)(v)(D) as a single train safety system that is required to be OPERABLE during situations under which significant radioactive releases can be postulated."

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Monday, October 24, 2016
Monday, October 24, 2016