Letter Sequence Draft RAI |
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MONTHYEARML0214202542002-05-13013 May 2002
Memo -Draft Response to RAI Received Via e-mail on 04/08/02 from CP&L on Relief Request RR-6
Project stage: Draft RAI
ML0214200522002-05-13013 May 2002
Memo - Draft Response to RAI Received Via e-mail on 04/08/02 from CP&L on Relief Request RR-6
Project stage: Draft RAI
2002-05-13
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Category:Memoranda
MONTHYEARML24165A2362024-06-21021 June 2024
Duke Robinson Technical Report 5-22-24 Public Meeting Summary
ML24124A0342024-05-0101 May 2024
Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris
ML22299A0212023-01-10010 January 2023
Memo to File - Robinson Final EA 2017, 2019, 2021
ML21145A0182021-05-25025 May 2021
Public Meeting Summary - 2020 Annual Assessment Meeting Regard the H. B. Robinson Steam Electric Plant, Docket No. 50-261, Meeting Number 20210460
IR 05000261/20204012020-10-28028 October 2020
Security Baseline Inspection Report 05000261/2020401
ML20266G4412020-09-24024 September 2020
Insights Obtained from Review of Robinson Seismic Probabilistic Risk Assessment
ML20141L6282020-05-20020 May 2020
EOC Meeting Summary
ML19123A1592019-05-0101 May 2019
Summary of Public Meeting with H. B. Robinson Steam Electric Plant, to Provide Opportunities to Discuss the Annual Assessment of the H.B Robison Steam Electric Plant with the Public for Period of January 1, 2018 - December 31, 2018
ML18144A0632018-05-24024 May 2018
Summary of Meeting Concerning Annual Assessment of H.B. Robinson Steam Electric Plant Unit 2 for Period of January 1, 2017 - December 31, 2017
ML16103A2552016-04-14014 April 2016
05/02/2016 Notice of Forthcoming Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson and Shearon Harris Plants (CAC Nos. MF7443 and MF7444)
ML15253A4032016-03-11011 March 2016
Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants
ML15342A2052016-01-0808 January 2016
Regulatory Audit in Support of License Amendment Request to Adopt NFPA 805
ML15288A1312015-11-17017 November 2015
Summary of Meeting with Duke Energy Progress, Inc. to Discuss H. B. Robinson Steam Electric Plant Unit No. 2 - Proposed License Amendment Request Transmission Upgrades
ML15125A4382015-05-0505 May 2015
Public Meeting Summary - 2014 Annual Assessment Public Meeting Regarding H.B. Robinson Steam Electric Plant
ML14112A4712014-05-0202 May 2014
Conference Call Summary - Regarding the Spring 2014 Steam Generator Inspections During a Forced Outage
ML13295A3062013-10-22022 October 2013
Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC
ML13106A3372013-04-17017 April 2013
Notice of Forthcoming Meeting with Duke Energy, Inc. Concerning the Relocation of the Emergency Operating Facilities
ML13072B2022013-03-19019 March 2013
Meeting Notice with Duke Energy Concerning NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants License Amendment Request for Catawba, McGuire, and H. B. Robinson
ML12314A0292012-11-13013 November 2012
Forthcoming Meeting Notice Via Conference Call with Duke Energy Regarding Generic Letter 2004-02 and NRC Staff Review of Draft Proposed Strainer Fiber Bypass Test Plant for H.B. Robinson Steam Electric Plant, Unit 2
ML12300A4032012-10-26026 October 2012
11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events
ML12284A4612012-10-12012 October 2012
Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events
ML1210707142012-05-21021 May 2012
Memo from G. Taylor and N. Melly to M. Salley H.B. Robinson High Energy Arc Fault Event Cable Damage Evaluation
ML11180A0162011-07-0101 July 2011
Notice of Forthcoming Meeting with Carolina Power & Light Company Regarding H. B. Robinson Steam Electric Plant, Unit No. 2, to Introduce the New Management Team and Discuss Strategic Plan
ML1108406312011-03-29029 March 2011
Notice of Forthcoming Pre-Application Meeting with Carolina Power & Light Co. and Florida Power Corp., Brunswick Units 1 & 2, Crystal River Unit 3, and H.B. Robinson Unit 2, to Discuss Transition to the Requirements of National Fire..
ML1015901992010-06-0808 June 2010
the Nuclear Regulatory Commission Staff Spot-Check Review of Progress Energy Carolina'S Ownership Interest of H.B. Robinson Steam Electric Plant Unit 2, Brunswick Steam Electric Plant Units 1 and 2 & Shearon Harris Nuclear Power Plant Unit
ML1001910052010-01-29029 January 2010
Notice of Conference Call with Progress Energy Carolinas, Inc., to Discuss H. B. Robinson Steam Electric Plant, Unit 2, Generic Letter 2004-02 Supplemental Response
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0524400382005-09-21021 September 2005
Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors.
ML0506100282005-03-0303 March 2005
Closeout Memo, Bulletin 2003-02 SP-1500 Examination of RPV Lower Head Penetration Leakage
ML0426003882004-09-16016 September 2004
Safety Evaluation on H. B. Robinson Request Involving Full Implementation of the Alternative Source Term,
ML0409001302004-04-23023 April 2004
Renewal of Full-Power Operating License for H.B. Robinson, Unit No. 2
ML0410606752004-04-15015 April 2004
Ltr, Steam Generator Tube Inspection Letter
ML0404104222004-02-0404 February 2004
Request Approval of Excused Absence for Employees Affected by Inclement Weather Conditions
ML0327400092003-09-30030 September 2003
Results of the Robinson SDP Phase 2 Notebook Benchmarking Visit, During June 2003
ML0306504452003-03-0606 March 2003
Closeout of TAC Number for Best Estimate large-break loss-of-coolant Accident Methodology
ML0301602062003-01-0808 January 2003
Level 1, Revision 3i Standardized Plant Analysis Risk (SPAR) Model for Robinson 2
ML0229703632002-10-23023 October 2002
Meeting with NEI, Surry & North Anna Units 1 & 2, McGuire & Catawba Units 1 & 2, Peach Bottom Units 2 & 3, St. Lucie Units 1 & 2, Fort Calhoun, H. B. Robinson Unit 2, R.E. Ginna, and Virgil C. Summer. the Proposed Agenda Is Attached
ML0226700072002-09-24024 September 2002
Technical Specification Change Regarding Selective Implementation of Alternative Radiological Source Term
ML0225601832002-09-13013 September 2002
Assessment of Radiological Consequences for 1.7% Power at H. B. Robinson Unit 2 Power
ML0225502282002-09-12012 September 2002
Assessment of Atmospheric Dispersion & Radiological Dose Assessment for Fuel Handling Accident at H. B. Robinson Unit 2 Power
ML0224003342002-08-27027 August 2002
NRR Notification of Significant Licensing Action for Proposed Issuance of Orders Re Responses to Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
ML0218305842002-07-0808 July 2002
(HBRSEP2)-Additional Information Sent Via e-mail on June 6, 2002, by Carolina Power & Light Company (Cp&L) Regarding TS Change Request for Implementing Alternate Source Term
ML0214202542002-05-13013 May 2002
Memo -Draft Response to RAI Received Via e-mail on 04/08/02 from CP&L on Relief Request RR-6
ML0214200522002-05-13013 May 2002
Memo - Draft Response to RAI Received Via e-mail on 04/08/02 from CP&L on Relief Request RR-6
ML0212301842002-04-26026 April 2002
Memo-Request for Additional Information Sent Via e-mail on January 10, 2002, to CP&L on a Relief Request
NRC Generic Letter 1989-111989-06-30030 June 1989
NRC Generic Letter 1989-011: Resolution of Generic Issue 101 Boiling Water Reactor Water Level Redundancy
ML0710202191983-05-24024 May 1983
Memo from Themis Speis to Roger Mattson Re Draft CRGR Package on A-30, DC Power
2024-06-21
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Text
NOTE: THIS IS NOT CONSIDERED OFFICIAL OR FINAL INFORMATION. THIS IS PROVIDED FOR INFORMATIONAL PURPOSES ONLY TO ASSIST WITH THE REVIEW OF IST-RR-6.
The following examples are in addition to the examples previously provided by letter dated February 20, 2002, as discussed in a conference call on March 11, 2002.
FOUR ADDITIONAL EXAMPLES FROM PAST DATA FCV-1933B Maintenance performed on 1/3/98 resulted in a stroke test closure time of 1.34 seconds. Based on application of the ASME OM 95/96 Code, this result would have been established as the new reference value.
Date Lower (50%) Upper (50%) Lower (75%) Upper (75%) Test Result 12/5/98 0.67 sec. 2.01 sec. 0.34 sec. 2.34 sec. 2.11 sec.
8/14/99 0.67 sec. 2.01 sec. 0.34 sec. 2.34 sec. 2.05 sec.
3/25/01 0.67 sec. 2.01 sec. 0.34 sec. 2.34 sec. 2.25 sec.
The subsequent test results exceeded the 50% threshold; however, the proposed 75% threshold would have been met. The subsequent test results of 2.11 seconds on 12/5/98, 2.05 seconds on 8/14/99, and 2.25 seconds on 3/25/01 are consistent and repeatable results for this valve. This example shows that the relief request would have prevented an unwarranted declaration of inoperability based on nominal stroke time deviations.
PS-956A Maintenance performed on 3/18/98 resulted in a stroke test closure time of 1.24 seconds. Based on application of the ASME OM 95/96 Code, this result would have been established as the new reference value. Adaptation to a rapid-acting designation may have been considered, although it would not normally be used for a valve that has typical test results that are very close to or greater than 2 seconds.
Date Lower (50%) (50%) .Upper Lower (75% Up r (75%) Test Result 2/17/99 0.62 sec. 1.86 sec. 0.31 sec. 2.17 sec. 1.97 sec.
The subsequent test result exceeded the 50% threshold; however, the proposed 75% threshold would have been met. This example shows that the relief request would have prevented an unwarranted declaration of inoperability based on nominal stroke time deviations.
PS-956H
Maintenance performed on 3/18/98 resulted in a stroke test closure time of 1.57 seconds. Based on application of the ASME OM 95/96 Code, this result would have been established as the new reference value.
Date Lower (50o) Upper (50%) Lower (75%) Upper (75%) Test Result 6/6/98 0.79 sec. 2.35 sec. 0.40 sec. 2.74 sec. 2.59 sec.
10/24/98 0.79 sec. 2.35 sec. 0.40 sec. 2.74 sec. 2.37 sec.
The subsequent test results exceeded the 50% threshold; however, the proposed 75% threshold would have been met. This example shows that the relief request would have prevented an unwarranted declaration of inoperability based on nominal stroke time deviations.
RC-519A Maintenance performed on 10/7/99 resulted in a stroke test closure time of 1.76 seconds. Based on application of the ASME OM 95/96 Code, this result would have been established as the new reference value. Adaptation to a rapid-acting designation may have been considered, although it would not normally be used for a valve that has typical test results that are very close to or greater than 2 seconds.
Date (50%) Upper (50% .LowerLower (75%) Upper (7.%) Test Result 11/28/99 0.88 sec. 2.64 sec. 0.44 sec. 3.08 sec. 2.84 sec.
6/29/00 0.88 sec. 2.64 sec. 0.44 sec. 3.08 sec. 2.78 sec.
The subsequent test results exceeded the 50% threshold; however, the proposed 75% threshold would have been met. This example shows that the relief request would have prevented an unwarranted declaration of inoperability based on nominal stroke time deviations.
THREE ADDITIONAL EXAMPLES SINCE FEBRUARY 19. 2002 Since implementation of the new OM Code requirements, HBRSEP, Unit No. 2, has experienced three events in which the as-found stroke time was greater than 50% of the reference value and less than 75%. HBRSEP, Unit No. 2, procedures are currently written to the OM Code requirements as amended by IST-RR-6 as submitted to the NRC on 2/20/2002, therefore, corrective actions, e.g.,
additional stroke time measurements and subsequent analysis of the deviation was not performed.
The following table depicts the events occurring since 2/19/2002.
Note: Reference values were established by averaging the results obtained from recent 'as-found' testing (no maintenance) encompassing five consecutive tests.
Valve I.D: FCV-1933A ReferenceValue = 1.90 seconds Limiting Value = 5 seconds.
Date Lower (50%) Upper (50%) Lower (75% Upper (75%) Test result 2/26102 9j5 see' 2.85 see. 0.48 sec. 3.32 sec. 0.91 sec.
Valve I.D: WD-1789 Reference Value = 2.29 seconds Limiting Value = 7 seconds.
Date .UpperLower (5.0%) (50%) Lower (75%) _ Upper (75%) Test result 2/24/02 1.15 sec. 3.43 sec. 0.58 see. 4.00 sec. 3.71 sec.
Valve I.D: WD-1794 Reference Value = 2.41 seconds Limiting Value = 7 seconds.
Date Lower (50%) Upper (50%) Lower (75%) Upper (75%) Test result 2/24/02 1.21 sec. 3.61 sec. 0.61 sec. 4.21 see. 4.08 sec.
The results were reviewed and test personnel were contacted. There was no conclusive determination pertaining to the cause of the deviations. It was postulated that the most likely cause was a result of the inherent timing inconsistencies associated with the coordination of the measurement between separate individuals using verbal communications in conjunction with the inherent deviation associated with the valve type.
