ML061300350: Difference between revisions
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{{Adams | |||
| number = ML061300350 | |||
| issue date = 03/20/2006 | |||
| title = Letter to Samuel Collins, Dtd March 20, 2006, from PSEG (LR-N06-0053) | |||
| author name = Barnes G P | |||
| author affiliation = PSEG Nuclear, LLC | |||
| addressee name = Collins S | |||
| addressee affiliation = NRC/RGN-I/ORA | |||
| docket = 05000354 | |||
| license number = NPF-057 | |||
| contact person = | |||
| case reference number = CAL 1-05-001, LR-N06-0053 | |||
| document type = Letter | |||
| page count = 4 | |||
}} | |||
=Text= | |||
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 Mr. Samuel Collins, Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 ACTIONS TO CLOSE CAL 1-05-001 'B' REACTOR RECIRCULATION PUMP HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 rc rt .. 0 h) | |||
==References:== | |||
: 1) 2) PSEG letter LR-N05-0017 from C. Bakken to S. Collins, dated January 9,2005 ' NRC Confirmatory Action Letter (CAL) (1-05-OOI), dated January I I , 2005 | |||
==Dear Mr. Collins:== | |||
As discussed in References 1 and 2 above, PSEG committed to and has implemented a vibration-monitoring program to continuously monitor the | |||
'B' Reactor Recirculation Pump's primary and secondary harmonic parameters (total amplitude, 1X and 2X amplitude, and 1X and 2X phase angle). As stated in Reference 1, PSEG procedures HC.OP-AB.RPV-O003(Q), HC.ER-AP.66-0001 (Z), and HC.OP-AR.ZZ-O008(Q) | |||
Attachment E-4 fulfill this commitment. | |||
Prior to implementing any changes to the vibration monitoring procedures, PSEG committed to notify the NRC and provide sufficient time for the NRC to complete a review of the proposed changes. Further, PSEG committed to replace the 'B' Reactor Recirculation Pump's shaft and inspect the pump's rotating assembly and pressure boundary components (such as the pump casing and cover) at the earlier of the next refueling outage or during an outage of sufficient duration to accomplish pump replacement. | |||
PSEG has scheduled the replacement of the 'B' Reactor Recirculation Pump's rotating assembly during the upcoming 1 3'h Refueling Outage (RFOI 3) in April 2006. 95-2168 REV. 7/99 Mr. Samuel Collins LR-N06-0053 2 To complete the actions specified in Reference 2 and committed by PSEG in Reference 1 , PSEG intends to perform the following activities during RFOl3. The 'B" Reactor Recirculation pump rotating assembly will be replaced with a new rotating assembly. | |||
The replacement is being performed as a design change since the rotating assembly being installed is the new 4th generation assembly that is no longer susceptible to the shaft thermal cracking phenomenon of the early generation assemblies. The rotating assembly replacement will be performed during RF013 and per the current schedule, the replacement is expected to begin on April 16'h. It is PSEG's understanding that the NRC may be present during the rotating assembly removal so PSEG will keep the NRC verbally informed of any schedule changes. | |||
During the removal of the rotating assembly, a visual inspection of the assembly will be performed by the pump vendor (Flowserve). | |||
The visual inspection will be performed as the assembly is transported from the pump casing to a shielded storage container. | |||
The Flowserve personnel will inspect the rotating assembly for the following conditions; general conditions of the visual portions of the exterior of the pump assembly, general conditions of the visual portions of the impeller, any noticeable dents or scratches, any shining metal indicating possible interaction with the pump wearing ring, and any abnormalities outside of previous reactor recirculation pump experience. | |||
Upon removal, the rotating assembly will be placed in its shielded storage container and will remain onsite pending final disposition. | |||
Following the inspection of the rotating assembly, an inspection of the pressure boundary components will be performed. The pressure boundary components will be inspected in accordance with ASME Section XI Acceptance Criteria I WB-35 1 9. As required by Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, PSEG will inform the NRC in writing when the actions addressed in the CAL have been completed (i.e., 'B' Reactor Recirculation pump shaft replaced, rotating assembly and pressure boundary components inspected). | |||
In order to support start-up activities following RFOl3, PSEG requests that NRC provide verbal notification, in advance of NRC written correspondence, that the CAL actions have been satisfied as allowed by Section 4.7.7 of the NRC Enforcement Manual. PSEG also understands that upon confirmation by the NRC that the actions addressed in the CAL have been completed, future changes to PSEG procedures HC.OP-AB.RPV-O003(Q), HC.ER-AP.BB-0001 (Z), and HC.OP- AR.ZZ-O008(Q) | |||
Attachment E-4 will be controlled in accordance with PSEG's administrative processes and the need for NRC approval prior to implementation will be determined in accordance with lOCFR50.59. | |||
-. Mr. Samuel Collins LR-N06-0053 3 Should you have any further questions please contact James Barstow at 856- 339-1 384. Sin yrely, George P. Barnes Site Vice President - Hope Creek | |||
.I Mr. Samuel Collins LR-N06-0053 4 C Mr. S. Bailey, Project Manager Salem | |||
& Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B2 I 1555 Rockville Pike Rockville, MD 20852 Mr. J. White, Chief, Materials | |||
& Structural Engineering Branch United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 USNRC Senior Resident Inspector - HC (X24) Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625 USNRC Document Control Desk Washington, DC 20555}} |
Revision as of 01:38, 20 March 2019
ML061300350 | |
Person / Time | |
---|---|
Site: | Hope Creek ![]() |
Issue date: | 03/20/2006 |
From: | Barnes G P Public Service Enterprise Group |
To: | Collins S Region 1 Administrator |
References | |
CAL 1-05-001, LR-N06-0053 | |
Download: ML061300350 (4) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 Mr. Samuel Collins, Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 ACTIONS TO CLOSE CAL 1-05-001 'B' REACTOR RECIRCULATION PUMP HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 rc rt .. 0 h)
References:
- 1) 2) PSEG letter LR-N05-0017 from C. Bakken to S. Collins, dated January 9,2005 ' NRC Confirmatory Action Letter (CAL) (1-05-OOI), dated January I I , 2005
Dear Mr. Collins:
As discussed in References 1 and 2 above, PSEG committed to and has implemented a vibration-monitoring program to continuously monitor the
'B' Reactor Recirculation Pump's primary and secondary harmonic parameters (total amplitude, 1X and 2X amplitude, and 1X and 2X phase angle). As stated in Reference 1, PSEG procedures HC.OP-AB.RPV-O003(Q), HC.ER-AP.66-0001 (Z), and HC.OP-AR.ZZ-O008(Q)
Attachment E-4 fulfill this commitment.
Prior to implementing any changes to the vibration monitoring procedures, PSEG committed to notify the NRC and provide sufficient time for the NRC to complete a review of the proposed changes. Further, PSEG committed to replace the 'B' Reactor Recirculation Pump's shaft and inspect the pump's rotating assembly and pressure boundary components (such as the pump casing and cover) at the earlier of the next refueling outage or during an outage of sufficient duration to accomplish pump replacement.
PSEG has scheduled the replacement of the 'B' Reactor Recirculation Pump's rotating assembly during the upcoming 1 3'h Refueling Outage (RFOI 3) in April 2006. 95-2168 REV. 7/99 Mr. Samuel Collins LR-N06-0053 2 To complete the actions specified in Reference 2 and committed by PSEG in Reference 1 , PSEG intends to perform the following activities during RFOl3. The 'B" Reactor Recirculation pump rotating assembly will be replaced with a new rotating assembly.
The replacement is being performed as a design change since the rotating assembly being installed is the new 4th generation assembly that is no longer susceptible to the shaft thermal cracking phenomenon of the early generation assemblies. The rotating assembly replacement will be performed during RF013 and per the current schedule, the replacement is expected to begin on April 16'h. It is PSEG's understanding that the NRC may be present during the rotating assembly removal so PSEG will keep the NRC verbally informed of any schedule changes.
During the removal of the rotating assembly, a visual inspection of the assembly will be performed by the pump vendor (Flowserve).
The visual inspection will be performed as the assembly is transported from the pump casing to a shielded storage container.
The Flowserve personnel will inspect the rotating assembly for the following conditions; general conditions of the visual portions of the exterior of the pump assembly, general conditions of the visual portions of the impeller, any noticeable dents or scratches, any shining metal indicating possible interaction with the pump wearing ring, and any abnormalities outside of previous reactor recirculation pump experience.
Upon removal, the rotating assembly will be placed in its shielded storage container and will remain onsite pending final disposition.
Following the inspection of the rotating assembly, an inspection of the pressure boundary components will be performed. The pressure boundary components will be inspected in accordance with ASME Section XI Acceptance Criteria I WB-35 1 9. As required by Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, PSEG will inform the NRC in writing when the actions addressed in the CAL have been completed (i.e., 'B' Reactor Recirculation pump shaft replaced, rotating assembly and pressure boundary components inspected).
In order to support start-up activities following RFOl3, PSEG requests that NRC provide verbal notification, in advance of NRC written correspondence, that the CAL actions have been satisfied as allowed by Section 4.7.7 of the NRC Enforcement Manual. PSEG also understands that upon confirmation by the NRC that the actions addressed in the CAL have been completed, future changes to PSEG procedures HC.OP-AB.RPV-O003(Q), HC.ER-AP.BB-0001 (Z), and HC.OP- AR.ZZ-O008(Q)
Attachment E-4 will be controlled in accordance with PSEG's administrative processes and the need for NRC approval prior to implementation will be determined in accordance with lOCFR50.59.
-. Mr. Samuel Collins LR-N06-0053 3 Should you have any further questions please contact James Barstow at 856- 339-1 384. Sin yrely, George P. Barnes Site Vice President - Hope Creek
.I Mr. Samuel Collins LR-N06-0053 4 C Mr. S. Bailey, Project Manager Salem
& Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08B2 I 1555 Rockville Pike Rockville, MD 20852 Mr. J. White, Chief, Materials
& Structural Engineering Branch United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 USNRC Senior Resident Inspector - HC (X24) Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625 USNRC Document Control Desk Washington, DC 20555