Event Notification Report for July 07, 2015

PART 21 INTERIM REPORT - NOTIFICATION OF PRESSURE SEAL VALVE YOKE MATERIAL COMPLIANCE

The following information was received via fax:

"This letter provides interim notification of Crane Nuclear's investigation into ASME Boiler and Pressure Vessel [B&PV] Section Ill Code design Pressure Seal Valve orders for yokes with integral hubs acting as retaining rings. The information required for this notification is provided below:

"(i) Name and address of the individual or individuals informing the Commission.

Jason Klein
Sustaining Engineering Manager

Rosalie Nava
Director Safety and Quality
Crane Nuclear
860 Remington Blvd
Bolingbrook, IL 60440

"(ii) Identification of the basic component supplied for such facility or such activity within the United States which may fail to comply or contains a potential defect

This is an interim report. Crane Nuclear is currently investigating Pressure Seal Valve orders potentially having misclassified material and non-destructive examination requirements for Yokes with integral hub retaining ring designs. The material requirements are specified per Crane Procedure 03-107 which utilizes ASME B&PV Code Case N-62-7 as guidance for material classification.

"(iii) Identification of the firm supplying the basic component which fails to comply or contains a defect.

Crane Nuclear
860 Remington Blvd
Bolingbrook, IL 60440

"(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.

Crane Nuclear 'Classification of Valve Parts', Procedure 03-107, is guidance for appropriate material and NDE requirements for processing valve and valve part orders. The procedure is based on the ASME Code Case N-62-7. A yoke incorporating a threaded hub should be treated in the same manner as a threaded retaining ring requiring the material to be purchased Safety Related, ASME B&PV Section II, Part D materials, and required NDE (reference Category 3 valve items per N-62-7). Yokes with integral hubs acting as retaining rings may have been processed to material requirements without required CNI Classification per Procedure 03-107.

"(v) The date on which the information of such defect or failure to comply was obtained.

Crane Nuclear Engineering initiated investigation correspondence to Crane Nuclear Director of Safety and Quality via email correspondence dated Feb 20th, 2015.

"(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part.

Crane has yet to determine the extent of Pressure Seal Valve designs sales order numbers (SO#) affected prior to 2001; the following Utility and Sites were supplied non-compliant CNI Procedure 03-107 Classification yokes for the following valve assemblies:

1. CNI SO# 24237-01, TVA, Browns Ferry, P.O. 00031943 - Quantity shipped = 1, Chapman, 8 [inch], Figure L953, Class 900, ASME Class 2, 95 Ed., 96 Add., no N stamp

2. CNI SO# 39501ú01, Georgia Power, Hatch, P.O. SNG10016537 - Quantity shipped = 3, Crane, 3 [inch], Figure 776U, Class 600, ASME Class 3, 71 Ed., W71 Add.

3. CNI SO# 39745-01, Southern California Edison, San Onofre, P .0. 4500456451 - Quantity Shipped = 1, Aloyco, 4 [inch], Figure N5247PSB, Class 900, ASME Class 3, 71 Ed., S73 Add.

"(vii) 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 taken to complete the action.

Crane Nuclear has completed sales orders search of Pressure Seal Valve designs with integral retaining ring hubs from 2001 to present identifying a total of 25 orders where three orders are impacted, as identified in part iv of this report (see above). Crane Nuclear is currently investigating sales orders previous to 2001, which will require an additional 30 days to complete (estimated completion date, August 6th, 2015).

Corrective action by Crane Nuclear is to review documentation of supplied material to determine if yokes can be recertified as currently supplied. A revision to Crane Nuclear Procedure 03-107 to add figures reflecting configurations, and clarify classifications with applicable training, is in-process.

"(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.

Crane Nuclear is notifying sites affected and are developing a plan to address the valve items.

"(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.

Not applicable.

"Should you have any questions regarding this matter, please contact Jason Klein, Sustaining Engineering Manager at (630) 226-4953 or Rosalie Nava, Director of Safety and Quality at (630) 226-4940."

* * * UPDATE FROM JASON KLEIN TO JOHN SHOEMAKER AT 1802 EDT ON 8/10/15 * * *

The following excerpted information was received via fax:

"Crane Nuclear has completed the sales orders search of the ASME Section Ill Code Pressure Seal Valve designs with retaining rings from 1992 to present. Crane Nuclear identified a total of 112 orders that required review. Of these orders, two orders were supplied with non-compliant retaining ring material for the valve assemblies. The orders are as follows:

1. Walworth's Supplied Order #PP37653, Dominion, Millstone.
2. CNI SO# 32634-01, Dominion, Millstone.

"Corrective action being taken by Crane Nuclear is training held for engineers involved in classification of components, completed 8/10/15. Revise Procedure 03-107 to add figures reflecting configurations and clarify classifications 8/24/15. Revise assembly drawings to correct item identification as pressure retaining material, recertify ASTM material as ASME, and provide corrected documentation 8/28/15.

"Should you have any questions regarding this matter, please contact Jason Klein, Sustaining Engineering Manager at (630) 226-4953 or Rosalie Nava, Director of Safety and Quality at (630) 226-4940."

Notified R1DO (Powell), R2DO (Masters), R3DO (Orlikowski), R4DO (Hagar), and PART 21/50.55 REACTORS via email.

SECONDARY CONTAINMENT PRESSURE BOUNDARY VACUUM NOT MAINTAINED WITHIN SPECIFICATIONS

"On 7/7/2015 at approximately 1435 EDT, the Technical Specification for Secondary Containment Pressure Boundary was not met when vacuum could not be maintained greater than or equal to -0.125 inches of water gauge for approximately 41 seconds. As part of post-maintenance testing for the non-safety related Reactor Building HVAC Center Exhaust Fan, the fan was started while the safety-related Standby Gas Treatment system was also in operation. Shortly after the fan was started, operators observed degrading vacuum in secondary containment and subsequently secured the center exhaust and supply fans. Vacuum continued to degrade momentarily after the fans were secured, and then returned to a Technical Specification allowable value.

"Subsequent inspections discovered that the affected fan was operating in the reverse direction. This is believed to have caused Secondary Containment pressure to increase.

"Since vacuum could not be maintained with the safety-related Standby Gas Treatment system operating, the plant operated in an unanalyzed condition.

"The cause of the reverse rotation is under investigation. There were no radiological releases associated with this event.

"The NRC Senior Resident Inspector has been notified."

* * * UPDATE FROM CHRIS ROBINSON TO VINCE KLCO ON 7/7/2015 AT 2153 EDT* * *

"Based on plant configuration at the time of the event and further review of the Fermi 2 UFSAR, the plant did not operate in an unanalyzed condition. The Reactor Building HVAC fans would have tripped, as designed, upon receipt of a safety-related Standby Gas Treatment actuation signal during the time of the event. Therefore, the fans' pressurizing effect on secondary containment would have ceased within the time limits assumed in the existing accident analysis.

"The reporting criteria of 10CFR50.72(b)(3)(v)(C) remains valid."

The licensee notified the NRC Resident Inspector.

Notified the R3DO (Stone).

TECHNICAL SUPPORT CENTER VENTILATION OUT OF SERVICE

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility.

"A condition impacting functionality of the TSC Ventilation system was discovered on July 7, 2015 at 11:05 EDT. The issue involved a loss of cooling capability of the TSC Ventilation system due to failed ventilation system components. Maintenance started repairs immediately following the discovery of the component failures and completed repairs to restore functionality of the TSC Ventilation system on July 8, 2015 at 17:07 EDT. On July 8, 2015, at approximately 15:30 EDT, further review of the impact of this equipment failure determined that this condition was reportable as a loss of emergency assessment capability.

"If an emergency were declared requiring TSC activation during the non-functional period, the TSC would have been staffed and activated using existing emergency planning procedures unless the TSC became uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC became necessary, the Emergency Director would have relocated the TSC staff to an alternate location in accordance with applicable site procedures. The Emergency Response Organization team was notified of the maintenance and the possible need to relocate during an emergency. This condition did not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified."

* * * UPDATE ON 8/27/15 AT 1445 EDT FROM INGRID NORDBY AND JOHN CAVES TO HOWIE CROUCH * * *

"An extent of condition review revealed three additional instances of loss of cooling capability of the Technical Support Center due to failed ventilation system components: January 7, 2015; June 20, 2015; and June 30, 2015. Functionality was restored after these conditions were identified. Each of these instances was determined to be reportable in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspectors have been notified."

Notified R2DO (Rose).