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Event Notification Report for August 30, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/29/2017 - 08/30/2017

** EVENT NUMBERS **


52857 52936

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Part 21 Event Number: 52857
Rep Org: CRANE NUCLEAR, INC.
Licensee: CRANE NUCLEAR, INC.
Region: 3
City: BOLINGBROOK State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: SAMSON KAY
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/13/2017
Notification Time: 17:59 [ET]
Event Date: 06/05/2017
Event Time: [CDT]
Last Update Date: 08/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
BRIAN BONSER (R2DO)
PART 21/50.55 REACTO (EMAI)

Event Text

PART 21 - DEFECTIVE SAFETY RELATED VALVES

The following was excerpted from a letter by Crane Nuclear, Inc.:

"The plug valve designs provided for XOMOX model figure numbers 037AX, 067EG, and 037. These valves have been identified as used in nuclear and/or safety related applications.

"The stem for the Subject valve models was identified as being undersized based on allowable yield stress analysis of the stem while in torsion. The high stress condition was due to the high torque required to seat/unseat the plug when installed with a Ultra High Molecular Weight Polyethylene (UHMWPE) sleeve material. High friction factor inherent with this material causes torsional stress to exceed the upper limit of yield strength of the valve which could result in fatigue/yielding of the stem, thus preventing the valve from opening and closing while in service. Historical research performed thus far has not identified any notifications from the customer(s) regarding stem failure of the subject valves, indicating that the valves may still be in operation with no performance related or operating issues.

"The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be .token to complete the action.

"Notifications letters have been sent to the affected plants advising them of the condition, and recommending that the sleeve material be replaced with a lower friction Polytetrafluomethylene (PTFE) material that would significantly reduce the required input operating torque, thereby reducing the risk of failure of the stem material.

"XOMOX has been advised to modify design calculations to provide a larger margin for allowable yield strength of the stem material to ensure the stem is properly sized when Ultra High Molecular Weight Polyethylene (UHMWPE) sleeve material is used.

"Crane will continue to review XOMOX records to determine if any other sites are impacted, which we expect to complete by August 31, 2017.

"Should you have any questions regarding this matter, please contact Samson Kay, Manager of Engineering at (630) 226-4983 or Jennifer Bregovy, Manager of Quality and Safety at (630) 226-4949."

The following facilities received these safety related orders: TVA Sequoyah, Pennsylvania Power & Light Susquehanna.

* * * UPDATE AT 1205 EDT ON 8/29/17 FROM SAMSON KAY TO MARK ABRAMOVITZ * * *

The following information was received via fax:

"Crane Nuclear (CNI) has initiate the final phase of the Part 21 research and is currently reviewing over 15,000 documents from the original XOMOX Canada historical archive to determine if any other nuclear sites were impacted by the subject Part 21. The investigation encompasses sales orders spanning from 1968 to 1992. CNI expects to complete the review by 10/30/2017."

Point of Contact: Samson Kay (630-226-4983) or Jennifer Bregovy (630-226-4949)

Notified the R1DO (Cook), R2DO (Lopez), and Part 21 Resources (via e-mail).

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Power Reactor Event Number: 52936
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RYAN MEYER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/29/2017
Notification Time: 14:42 [ET]
Event Date: 08/29/2017
Event Time: 12:00 [CDT]
Last Update Date: 08/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
VINCENT GADDY (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 65 Power Operation 65 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

"On August 22, 2017 at 2321 hours, Grand Gulf Nuclear Station entered Technical Specification conditions for three Limiting Condition for Operations (LCOs) not met due to Residual Heat Removal 'A' (RHR 'A') being declared inoperable.

"LCOs not met:
1) 3.5.1 for one low pressure ECCS [Emergency Core Cooling System] injection/spray subsystem.
2) 3.6.1.7 for one RHR containment spray subsystem, and
3) 3.6.2.3 for one RHR suppression pool cooling subsystem.

"The station has made the decision to shutdown the plant based on the results of troubleshooting performed on the RHR 'A' pump. The restoration of RHR 'A' pump will not be completed prior to the end of the 7 day LCO completion time.

"Grand Gulf Nuclear Station initiated plant shutdown required by Technical Specifications 3.5.1, 3.6.1.7, and 3.6.2.3 at 1200 hours CDT on 08/29/2017 due to expected restoration of RHR 'A' exceeding the completion time of 7 days prior to restoring operability."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, August 30, 2017
Wednesday, August 30, 2017