ML15077A422
| ML15077A422 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Hope Creek, Pilgrim, FitzPatrick |
| Issue date: | 03/17/2015 |
| From: | Debonis J Curtiss Wright Flow Control Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50900 | |
| Download: ML15077A422 (6) | |
Text
0311712015 P£1*P I 031/05U.S.
Nuclear Repuladorv Commission Onerations Center Event Rennrt P"00, Part 21 (PAR)
Event#
50900 Rep Org: CURTISS WRIGHT FLOW CONTROL CO.
Notification Date / Time: 03117/2015 09:59 (EDT)
Supplier: CURTISS WRIGHT FLOW CONTROL CO.
Event Date/ Time: 03/17/2015 (EDT)
Last Modification: 03/17/2015 Region:
1 Docket #:
City:
EAST FARMINGDALE Agreement State:
Yes County:
License #:
State:
NY NRC Notified by: JOHN DeBONIS Notifications: GLENN DENTEL R1DO HQ Ops Officer: STEVE SANDIN BINOY DESAI R2DO Emergency Class: NON EMERGENCY PART 21/50.55 REACTORS EMAIL 10 CFR Section:
21.21(a)(2)
INTERIM EVAL OF DEVIATION INTERIM PART 21 REPORT - POTENTIAL TEST INDUCED DEFECT IN A 0867F MAIN STEAM SAFETY RELIEF VALVES The following report was received from Curtiss - Wright via email:
"This letter provides interim notification of a potential test induced defect in a 0867F Series Main Steam Safety Relief Valves (MS-SRVs) manufactured and supplied by Target Rock (TR). The information required for this notification is provided below:
"(i) Name and address of the individual or individuals informing the Commission.
William Brunet Director of Quality Assurance James White General Manager Target Rock, Business Unit of Curtiss-Wright Flow Control Corporation 1966E Broadhollow Road East Farmingdale, NY 11735
"(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.
Target Rock 0867F Series of Main Steam-Safety Relief Valves Manufactured by Target Rock. This is a 3-stage piloted valve consisting of a main valve (the 'Main') with an actuator mounted to it (the 'Topworks'). The 0867F is the latest generation of the 67F line of MS-SRVs, including the original 3-Stage and 2-Stage designs, and this f
0311712015 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 2 product line has over 40 years of plant operational experience. Only the 0867F is under investigation. This is due to the differences between the 0867F design and the other designs.
"(iii) Identification of the firm supplying the basic component which fails to comply or contains a defect.
Target Rock, Business Unit of Curtiss-Wright Flow Control Corporation 1966E Broadhollow Road East Farmingdale, NY 11735
"(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.
As we understand it, the Pilgrim Station recently manually opened the Target Rock Main Steam Safety Relief Valves (MS-SRVs) as part of cooling down the reactor following a loss of offsite power. One of the four installed MS-SRVs may not have fully opened. As-found steam testing of the affected MS-SRV did not duplicate this failure; the valve opened on demand. However, the valve did not re-close as expected. Internal inspections found damaged parts in the main stage subassembly that could potentially affect the ability of the MS-SRV to operate as designed.
We are investigating potential root causes for this damage. However, we are still unable to determine if a specific defect exists. GE SIL-196, Supplement 17 determined Main Spring relaxation was caused by 'extreme dynamics encountered during limited flow testing. Valve dynamics under full flow conditions (i.e. discharge not gagged) are much less severe than those under limited flow conditions.' These extreme dynamics, under limited flow test conditions, are the focus of our investigation. Specific areas of investigation include; a) Testing of materials to verify they are consistent with our material specifications, b) evaluation of differences between the 0867F and earlier designs, and c) evaluation of the differences between different limited flow test loop configurations and test procedures
"(v) The date on which the information of such defect or failure to comply was obtained.
The Pilgrim event occurred on January 27, 2015. As-found testing occurred on February 2, 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.
While we have yet to determine if a specific defect exists, the following plants were supplied 0867F MS-SRVs:
- Pilgrim (Model 09J-001) Quantity Shipped = 8
- Fitzpatrick (Model 09H-001) Quantity Shipped = 4, Quantity on order= 8
- Hatch 1 and 2 (Model 09G-001) Quantity Shipped= 24, Quantity on order= 12 The following plants will be supplied 0867F MS-SRVs:
- Hope Creek (Models 14J-001, 14J-002) Quantity on order = 7
"(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.
The root cause of the potential test induced defect has not yet been confirmed as of the date of this report.
Therefore, no specific corrective actions have been initiated. Target Rock Problem Report 080 will document the corrective actions when they are determined and complete the 10 CFR Part 21 evaluation of the potential test induced defect. This determination will be based on further mechanical and material evaluations. TR anticipates completing these evaluations within 45 days; however, in the event the evaluations are not completed, TR will forward another interim report within 45 days.
03/17/2015 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 3
"(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.
We are working with all three (4) sites to identify appropriate precautions.
"(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 Michael Cinque, Director of Program Management at (631 ) 293-3800."
Valve Group - Target Rock CURT Industrial Division 1966E Broadhollow Road E Farmingdale, NY 11735, USA T: +1.631.293.3800 1 F: +1.631.293.4949 www.cw-industrial.com NID#1 5155 16 March 2015 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-001
Subject:
10 CFR Part 21 Interim Report Notification of a Potential Test Induced Defect 0867F Series Main Steam Safety Relief Valves
Dear Sir or Madam:
This letter provides interim notification of a potential test induced defect in a 0867F Series Main Steam Safety Relief Valves (MS-SRVs) manufactured and supplied by Target Rock (TR). The information required for this notification is provided below:
(i) Name and address of the individual or individuals informing the Commission.
William Brunet Director of Quality Assurance James White General Manager Target Rock, Business Unit of Curtiss-Wright Flow Control Corporation 1966E Broadhollow Road East Farmingdale, NY 11735 (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 Target Rock 0867F Series of Main Steam-Safety Relief Valves Manufactured by Target Rock.
This is a 3-stage piloted valve consisting of a main valve (the "Main") with an actuator mounted to it (the "Topworks"). The 0867F is the latest generation of the 67F line of MS-SRVs, including the original 3-Stage and 2-Stage designs, and this product line has over 40 years of plant operational experience. Only the 0867F is under investigation. This is due to the differences between the 0867F design and the other designs.
(iii) Identification of the firm supplying the basic component which fails to comply or contains a defect.
Target Rock, Business Unit of Curtiss-Wright Flow Control Corporation 1966E Broadhollow Road East Farmingdale, NY 11735 (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.
As we understand it, the Pilgrim Station recently manually opened the Target Rock Main Steam Safety Relief Valves (MS-SRVs) as part of cooling down the reactor following a loss of offsite power. One of the four installed MS-SRVs may not have fully opened. As-found steam testing of the affected MS-SRV did not duplicate this failure; the valve opened on demand. However, the valve did not re-close as expected. Internal inspections found damaged parts in the main stage subassembly that could potentially affect the ability of the MS-SRV to operate as designed.
We are investigating potential root causes for this damage. However, we are still unable to determine if a specific defect exists. GE SIL-196, Supplement 17 determined Main Spring relaxation was caused by "extreme dynamics encountered during limited flow testing.... Valve dynamics under full flow conditions (i.e. discharge not gagged) are much less severe than those under limited flow conditions." These extreme dynamics, under limited flow test conditions, are the focus of our investigation. Specific areas of investigation include; a) Testing of materials to verify they are consistent with our material specifications, b) evaluation of differences between the 0867F and earlier designs, and c) evaluation of the differences between different limited flow test loop configurations and test procedures (v) The date on which the information of such defect or failure to comply was obtained.
The Pilgrim event occurred on January 27, 2015. As-found testing occurred on February 2, 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.
While we have yet to determine if a specific defect exists, the following plants were supplied 0867F MS-SRVs:
Pilgrim (Model 09J-001) Quantity Shipped = 8 Fitzpatrick (Model 09H-001) Quantity Shipped = 4, Quantity on order = 8 Hatch 1 and 2 (Model 09G-001) Quantity Shipped = 24, Quantity on order = 12
The following plants will be supplied 0867F MS-SRVs:
0 Hope Creek (Models 14J-001, 14J-002) Quantity on order = 7 (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.
The root cause of the potential test induced defect has not yet been confirmed as of the date of this report. Therefore, no specific corrective actions have been initiated. Target Rock Problem Report 080 will document the corrective actions when they are determined and complete the 10 CFR Part 21 evaluation of the potential test induced defect. This determination will be based on further mechanical and material evaluations.
TR anticipates completing these evaluations within 45 days; however, in the event the evaluations are not completed, TR will forward another interim report within 45 days.
(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.
We are working with all four (4) sites to identify appropriate precautions.
(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 Michael Cinque, Director of Program Management at (631) 293-3800 Very Truly Yours, General Manager Target Rock, Business Unit of Curtiss-Wright Flow Control Corporation cc:
Michael Cinque William Brunet Steve Pauly Alex DiMeo John DeBonis Ed Bradshaw