Letter Sequence Request |
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Results
Other: ML043230163, ML043500645, ML043510279, ML043650296, ML050050111, ML050050112, ML050050116, ML050050470, ML050060022, ML050060025, ML050060041, ML050060054, ML050060074, ML050060110, ML050060114, ML050060252, ML050060256, ML050060384, ML050060387, ML050120303, ML050140232, ML050140236, ML050140245, ML050140247, ML050140253, ML050140298
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MONTHYEARML0500600411995-12-26026 December 1995
H-1-BB-MEE-1050 Hope Creek Recirculation System Large Bore Pipe Cracking Resolution, 12/26/1995
Project stage: Other
ML0501402362002-07-12012 July 2002
Reactor Coolant Pump Shaft Cracking, July 12, 2002
Project stage: Other
ML0500600252003-04-15015 April 2003
CR 70029861 Hope Creek 'B' Recirculation Pump Excessive Seal Leakage Condition Report, 03/01/2003
Project stage: Other
ML0501402982003-05-0707 May 2003
Drawing 1 of 2, M-43-1 P&Id, Reactor Recirculation System
Project stage: Other
ML0501402532004-04-29029 April 2004
HC-04Q-301 Hope Creek Extended Power Uprate Piping Vibration Monitoring, 4/29/2004
Project stage: Other
ML0500603842004-09-0707 September 2004
C-0031 Piping Code Compliance, 9/7/2004
Project stage: Other
ML0500600542004-10-19019 October 2004
Design Change Package 80062466 Revision 1 Extended Power Uprate Piping Vibration Monitoring Installation Package, 10/19/2004
Project stage: Other
ML0501402472004-10-26026 October 2004
Flowserve RAL-7483 Rev 0 Design Modification Report Assy 93-14347, 10/26/2004
Project stage: Other
ML0501402452004-10-26026 October 2004
Flowserve RAL-7482 Rev 0 Design Modification Report Assy 93-15122, 10/26/2004
Project stage: Other
ML0500603872004-10-29029 October 2004
H1BC-1-BC-V183 (CR 20208920) Handwheel Operator Spins Freely, 11/08/2004
Project stage: Other
ML0500501122004-10-30030 October 2004
HC.OP-SO.BB-0002(Q) Rev 50A Reactor Recirculation System Operating Procedures, 10/30/2004
Project stage: Other
ML0500501162004-10-30030 October 2004
HC-OP-AR.ZZ-0008(Q), Rev 25A, Overhead Annunciator Window Box C1, Operations Alarm Response Procedure, 10/30/2004
Project stage: Other
ML0500600742004-11-0303 November 2004
Structural Integrity Associates, Inc. HC-06-301 Hope Creek Recirculation System Vibration Testing (Vtd 326747) 11/03/2004
Project stage: Other
ML0432301632004-11-18018 November 2004
Expected Task Interface Agreement to Review 'B' Recirculation Pump High Vibration Report
Project stage: Other
ML0500601102004-12-10010 December 2004
Design Change Package 80062466 Revision 2 Extended Power Uprate Piping Vibration Monitoring Installation Package, 12/10/2004
Project stage: Other
ML0500501112004-12-12012 December 2004
H-1-FD-CEE-1879, Hope Creek HPCI Exhaust Piping Supports Analysis Reported Damage in RF12.
Project stage: Other
ML0501402322004-12-12012 December 2004
H-1-BB-MEE-1878, Rev 0, Hope Creek 'B' Recirculation Pump Vibration Analysis, 12/12/2004
Project stage: Other
ML0434801642004-12-13013 December 2004
Questions Regarding 'B' Recirculation Pump High Vibrations and High Pressure Coolant Injection System Exhaust Damage
Project stage: Request
ML0500504702004-12-16016 December 2004
H-1-BB-MEE-1878, Hope Creek 'B' Recirculation Pump Vibration Analysis, Revision 1
Project stage: Other
ML0435006452004-12-16016 December 2004
Pseg'S Preliminary Responses to NRC Staff Questions Regarding 'B' Recirculation Pump Vibration
Project stage: Other
ML0435102792004-12-16016 December 2004
PSEG Preliminary Responses to NRC Staff Questions
Project stage: Other
ML0502100682004-12-17017 December 2004
Hope Creek Generating Station - Summary of Meeting with PSEG to Discuss B Recirculation Pump High Vibrations (TAC MC5111), Attendance Sheet
Project stage: Meeting
ML0500601142004-12-23023 December 2004
Design Change Package 80062466 Revision 3 Extended Power Uprate Piping Vibration Monitoring, Installation Package, 12/23/2004
Project stage: Other
ML0436502962004-12-30030 December 2004
Public Availability and Docketing of Documents
Project stage: Other
ML0500600222004-12-30030 December 2004
'B' Recirculation Pump Stuffing Box Measurements Summary
Project stage: Other
ML0500602522004-12-30030 December 2004
Summary of Hope Creek Vibration Issues and Planned Actions
Project stage: Other
ML0500602562004-12-30030 December 2004
'B' Reactor Recirculation Pump Vibration Troubleshooting Summary
Project stage: Other
ML0501202552005-01-12012 January 2005
Response to Task Interface Agreement - TIA 2004-006, Request for Evaluation of Sargent and Lundy Report on Hope Creek 'B' Reactor Recirculation Pump and PSEG Nuclear LLC Evaluation of High Pressure Coolant Injection System Exhaust Snubbers
Project stage: Acceptance Review
ML0501203032005-01-12012 January 2005
Flowserve Response to NRC Questions Station 'B' Recirculation Pump
Project stage: Other
ML0500301602005-01-19019 January 2005
Hope Creek Generating Station - Summary of Meeting with PSEG to Discuss B Recirculation Pump High Vibrations
Project stage: Meeting
2004-12-10
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Category:Memoranda
MONTHYEARML18269A2522018-10-12012 October 2018
F&O Closure Observation Hope Creek Fire PRA
ML17023A1452017-01-23023 January 2017
Summary of Teleconference with PSEG Regarding Hope Creek HPCI
ML16259A2042016-09-20020 September 2016
Hope Creek Generating Station - Safety Evaluation - Request to revise technical specifications - safety limit minimum critical power ratio.(TAC NO. MF7793)
ML15015A6772015-01-16016 January 2015
Forthcoming Closed Meeting with PSEG Nuclear, LLC, Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1
IR 05000272/20132022013-12-20020 December 2013
IR 05000272-13-202, 05000311-13-202 & 05000354-13-201, September 9-13, 2013, Salem Nuclear Generating Station and Hope Creek Generating Station - Cover Letter
ML13309A0802013-12-11011 December 2013
Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors
ML13233A1132013-08-22022 August 2013
Notice of Forthcoming Meeting with PSEG Nuclear, LLC Regarding a Planned Digital Instrumentation and Controls License Amendment Request Associated with Hope Creek Generating Station, Unit 1
ML13154A4952013-06-0404 June 2013
Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station
ML13196A2202012-06-0606 June 2012
Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon
ML1209002372012-03-29029 March 2012
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information
ML1129901422011-10-25025 October 2011
Draft Request for Additional Information
ML1129700652011-10-21021 October 2011
Summary of PSEG Drop-in Visit, 9-28-2011 and Slides
ML11250A1712011-09-14014 September 2011
Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs)
ML1118605722011-07-0505 July 2011
Draft Request for Additional Information
ML11181A1772011-06-30030 June 2011
June 29, 2011 Summary of Public Meeting to Discuss Observations and Lessons Learned During the Hope Creek Nuclear Generating Station Application of the Nuclear Energy Institute'S Nuclear Safety Culture Assessment Process
ML11137A0762011-06-0202 June 2011
Summary of Telephone Conference Call Held on May 11, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning the Hope Creek License Condition for the Drywell
ML11126A0962011-05-12012 May 2011
Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
ML11105A0372011-05-0404 May 2011
Summary of Telephone Conference Call Held on March 25, 2011, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Gas Turbine
ML1111108862011-04-20020 April 2011
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information
LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums2011-03-31031 March 2011
2011 Annual Report - Guarantees of Payment of Deferred Premiums
ML1106801152011-03-0808 March 2011
Draft Request for Additional Information
ML1106005572011-03-0101 March 2011
Minutes of the Meeting of the Subcommittee on Plant License Renewal Regarding Hope Creek Generating Plant on November 3, 2010, in Rockville, Maryland
ML1034909292011-02-0909 February 2011
Summary of Telephone Conference Call Held on November 18, 2010, Between the U.S. Nuclear Regulatory Commission and PSEG Nuclear, LLC, Concerning Findings on the Hope Creek Generating Station Recent Outage
ML1101901352011-01-18018 January 2011
Draft Request for Additional Information
ML1029500062010-10-28028 October 2010
11/17/10 Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Hope Creek Generating Station and Salem Nuclear Generating Station Units 1 and 2
ML1027100672010-09-30030 September 2010
Advisory Committee on Reactor Safeguards Review of the Hope Creek Generating Station License Renewal Application - Safety Evaluation Report with Open Items
ML1027207232010-09-29029 September 2010
Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal (Hope Creek), November 3, 2010
ML1024407062010-09-20020 September 2010
Summary of Telephone Conference Call Held on August 18,2010 Between Us NRC and PSEG Nuclear, LLC Concerning Questions Pertaining to the Hope Creek Generating Station License Renewal Application
ML11263A0282010-09-16016 September 2010
E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo
ML11263A0272010-09-14014 September 2010
E-mail with Attachment from T. Ghosh, RES, to L. Perkins, NRR Et Al, on Fyi Salem SAMA Transmittal
ML1023201782010-09-0303 September 2010
Summary of Telephone Conference Call Held on 8/16/10, Between Us NRC and PSEG Nuclear,Llc,Concerning Draft Request for Additional Information Pertaining to the Hope Creek Generating Station, License Renewal Application
ML1023201792010-09-0202 September 2010
Summary of Telephone Conference Call Held on 6/21/10 Between the USNRC and PSEG Nuclear LLC Concerning Responses to Requests for Additional Information Pertaining to the Hope Creek Generating Station License Renewal Application
ML1022204762010-08-18018 August 2010
Summary of Telephone Conference Call Held on 8/4/10,Between Us NRC and PSEG Nuclear, LLC, Concerning Draft RAI Pertaining to the Hope Creek Generating Station, License Renewal Application
ML1022200122010-08-13013 August 2010
Summary of Telephone Conf Call Held on 7/29/10, Between the USNRC and PSEG Nuclear LLC, Concerning Follow-Up Questions Pertaining to the Salem Nuclear Generating Station, Units 1 & 2, and Hope Creek Generating Station License Renewal Enviro
ML1020105012010-07-20020 July 2010
Draft Request for Additional Information
ML1018303472010-07-0202 July 2010
Draft Request for Additional Information
ML1017600102010-06-24024 June 2010
Draft Request for Additional Information
ML1011004322010-04-19019 April 2010
PSEG Slides for Salem and Hope Creek Annual Assessment Meeting, April 6, 2010
ML1009904032010-04-0808 April 2010
Draft Request for Additional Information
LR-N10-0115, Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums2010-04-0101 April 2010
Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums
ML11259A2702010-03-0101 March 2010
E-mail with Attachment from D. Logan, NRR, to S. Duda, Aecom Et Al, on Mitigation Memo
ML1002907322010-01-28028 January 2010
Draft Request for Additional Information
ML0934405582009-12-10010 December 2009
Notice of Closed Meeting with PSEG Nuclear LLC (PSEG) to Discuss Exemption from Schedular Requirements of 10 CFR 73.55 for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2
ML0928706352009-10-23023 October 2009
11/05/2009 Notice of Meeting to Discuss License Renewal Process and Environmental Scoping for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station, License Renewal Application Review
ML0923606212009-08-27027 August 2009
Logistics Trip Report to Delaware Emergency Management Agency Regarding Salem-Hope Creek License Renewal
ML0920103212009-07-30030 July 2009
Logistics Trip Report to Salem and Hope Creek Nuclear Stations and Salem, New Jersey
ML0919504062009-07-14014 July 2009
Draft Request for Additional Information
ML0917302782009-06-22022 June 2009
PSEG Drop-in Visit (Salem and Hope Creek) on 6-18-2009
ML0913502412009-05-14014 May 2009
Draft Request for Additional Information
ML0911701652009-04-27027 April 2009
Draft Request for Additional Information
2018-10-12
[Table view] |
Text
December 13, 2004 MEMORANDUM TO: Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Senior Project Manager /RA/
Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, QUESTIONS REGARDING B RECIRCULATION PUMP HIGH VIBRATIONS AND HIGH PRESSURE COOLANT INJECTION SYSTEM EXHAUST DAMAGE The attached questions were developed during the Nuclear Regulatory Commission (NRC) staffs review of PSEGs actions taken in response to high vibrations experienced on the B recirculation pump and identified damage to the high pressure coolant injection system turbine exhaust. The questions were communicated verbally to PSEG Nuclear, LLC (PSEG).
The purpose of this memorandum is to make the questions available for public inspection prior to a public meeting between the NRC and PSEG. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-354
Enclosure:
Questions
December 13, 2004 MEMORANDUM TO: Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Daniel S. Collins, Senior Project Manager /RA/
Project Directorate I, Section 2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
HOPE CREEK GENERATING STATION, QUESTIONS REGARDING B RECIRCULATION PUMP HIGH VIBRATIONS AND HIGH PRESSURE COOLANT INJECTION SYSTEM EXHAUST DAMAGE The attached questions were developed during the Nuclear Regulatory Commission (NRC) staffs review of PSEGs actions taken in response to high vibrations experienced on the B recirculation pump and identified damage to the high pressure coolant injection system turbine exhaust. The questions were communicated verbally to PSEG Nuclear, LLC (PSEG).
The purpose of this memorandum is to make the questions available for public inspection prior to a public meeting between the NRC and PSEG. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-354
Enclosure:
Questions DISTRIBUTION:
PUBLIC DRoberts ECoby, RGN-I RFretz ACRS DCollins RLorson GMiller PDI-2 Reading ADAMS Accession Number: ML043480164 OFFICE PDI-2/PE PDI-2/PM NAME GMiller DCollins DATE 12/13/04 12/13/04 OFFICIAL RECORD COPY
VERBALLY COMMUNICATED QUESTIONS TO PSEG NUCLEAR, LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 The following questions were communicated verbally to PSEG Nuclear, LLC:
- 1. The S&L report does not contain a conclusive statement that it is acceptable to start-up without implementation of the GE SIL 459 recommendation regarding the need to inspect the RR shafts after 80,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of operation. Did S&L reach a conclusion on whether the postulated shaft cracking issues at HC could lead to a shaft failure? The statements seem to support a strong need for contingency planning versus continued reliability to the next refueling outage.
- 2. What is the technical basis for the requirement to inspect the shafts at 80,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />?
Have fatigue crack growth calculations been performed to simulate the observed cracking of the RR pump shafts? Discuss the applicability of these calculations to the Hope Creek RR pumps, if these calculations exist. What actions contained within GE SIL 459 have been implemented? Has your RR pump seal cooling system been modified (as discussed in the GE SIL) to mitigate the thermal stresses on the pump shaft? Page 15 of the S&L report provides an apparent incomplete assessment of the GE SIL recommendations (i.e. only addresses the SIL item related to vibration monitoring).
- 3. Does the known shaft bow worsen the potential for shaft cracking? If so where is this addressed in your review and what is the impact? Similarly, is the vibration issue related to the potential shaft cracking issue? Could potential shaft cracking be worsened by the recirc pump vibrations?
- 4. What is the risk significance associated with shaft cracking? Has it been evaluated by the PRA group? What is the risk of shaft failure based upon its current condition -
bowed and potentially cracked?
- 5. What is the plant response to a rapid failure of the pump shaft? Are vibration levels indicated and alarmed in the control room. Can you reliably detect initiation and/or growth of a crack in the pump shaft during operation with your current instrumentation?
Has the ability to detect shaft cracking, using vibration monitoring been demonstrated at any other facility that uses the same RR pump design as Hope Creek? How much time would operators have to recognize (based on vibration change) and respond to a rapid pump shaft failure?
- 6. If a shaft were to fail what would be the consequences (i.e. would it damage the associated recirculation piping or result in a LOCA due to loss of the shaft from the stuffing box area)?
- 7. Is end of useful life modeled for a Flowserve generation 2 pump?
- 8. On page 21 of the S&L report it is stated that Hope Creek RR pumps likely have some degree of shaft cracking. Has PSEG evaluated this non-conformance? What were your conclusions?
- 9. Since thermal stress, not bowing, is the predominate mechanism cited for the shaft cracks then provide the basis for why S&L does not recommend replacement of both the A&B RR pump shafts at the next refueling outage.
- 10. Describe the pump vibration monitoring program that will be implemented during the operating cycle.
Recirculation pump and system vibration
- 11. Will vibrations continue to damage safety-related components? (Example discussed in Table 6.1, page 49 of 71 of the HC Recirc/RHR Pipe Vibration Common Cause Analysis). Were any safety-related components rendered inoperable or unavailable due to recirculation system vibrations during the last operating cycle?
- 12. What was the reason for the anomalous RR pump vibration levels observed during RF 11? The reason for step change in B RR pump vibrations after RF11 is apparently NOT known yet S&L concluded that vibration data does not indicate signs of degrading condition for either pump (p. 10). Is this statement adequately supported?
- 13. What was the effect of swapping the vibration probes on the pump shaft on the reliability of collected data?
- 14. The evaluation did not address the apparent accelerated rate of vibration related problems. The operating cycle between RFO9 and RF10 actually had the highest pump vibrations. Why have symptomatic problems become more apparent within the last operating cycle and what conclusions can be determined wrt to the next operating cycle?
- 15. Did S&L review the current outage (RF12) small bore ISI weld exams or did they only review data from previous outages?
- 16. Provide a copy of references 6.2 and 6.3 cited in the S&L report section which evaluates the large bore piping vibrations. The S&L report provides several critique comments regarding the March 2004 testing and references 6.2/6.3 but does not provide any justification as to why the these references provide acceptable results with the documented deficiencies.
- 17. On page 12 the S&L report states that other Mark 1 plants do not have a recirculation pump rigid thermal restraint. Is Hope Creeks rigid thermal restraint inducing unnecessary or damaging stresses? Page 12 of the S&L report also states that the HC pump snubber support are less than other plants and recommends that HC investigate to ensure that this is not the cause for the high vibration. How is PSEG addressing this recommendation?
- 18. Should S&Ls report be so conclusive without displacement data? See pages 23 and 24.
Core Flow Degradation
- 1. PSEG has not yet determined the cause of a 3% degradation in core flow. Note, this is within technical specification requirements. When will instrumentation issues be ruled out? If it is not instrumentation, what are the other likely sources of the degradation and what are the next steps to resolve?
Other/General
- 1. Please provide a copy of PSEGs responses to the concerns raised by UCS following their review of the S&L report.
- 2. Provide the status of implementing all the recommendations contained within the S&L report. If not complete indicate which items will be completed prior to start-up and which items are planned to be completed following start-up.
- 3. The S&L report (page 3) states that the A and B RR pumps should be monitored for capacity and vibration and the pump shutdown following a rapid rise in vibration.
Provide a copy of your operating procedure which will implement this recommendation along with the basis for the procedure action levels.
