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Category:Meeting Briefing Package/Handouts
MONTHYEARML24100A8062024-04-0909 April 2024 Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024 ML23341A1522023-12-0707 December 2023 December 11, 2023 Public Meeting - RIPE Exemption Request - Licensee Slides ML22251A2352022-09-14014 September 2022 Presentation Slides for September 14, 2022, Observation Public Meeting ML22153A3842022-06-0606 June 2022 Duke Energy Presentation Material for June 6, 2022 Public Meeting on GSI-191 Closeout ML22091A1332022-04-0101 April 2022 Bru Har Combined 2021 Assessment Meeting Slides ML20100G6342020-04-0909 April 2020 Revised- Bru 2019 Annual Assessment Meeting Slides ML19318F2912019-11-18018 November 2019 Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request ML19214A0562019-08-0707 August 2019 Presentation: Duke Energy Presubmittal Meeting - August 7, 2019 ML19077A3672019-03-14014 March 2019 March 14, 2019 Pre-submittal Meeting TS DNBR Safety Limit Change LAR Meeting Slides ML18351A1342018-12-20020 December 2018 December 20, 2018 Pre-submittal Meeting Slides for Escw Risk-Informed LAR ML18333A1822018-11-0808 November 2018 Pre-Submittal Meeting - November 8, 2018 - License Amendment Request for Shearon Harris Nuclear Power Plant Emergency Plan Revision ML17331A6272017-11-29029 November 2017 Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69 ML17250B2382017-08-30030 August 2017 TMRE Presubmittal NRC ML17044A0892017-03-0202 March 2017 EDG SR Presubmittal Meeting March 2, 2017 ML16267A0292016-09-29029 September 2016 SFP Pre-Submittal Meeting Slides - BWR Storage Rack Inserts, Updated NCS Analysis at Harris Nuclear Plant ML16112A2932016-05-0202 May 2016 05/02/2016 Presentation for 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) RA-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)2015-09-18018 September 2015 Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted) ML14129A3352014-05-0909 May 2014 Summary of Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML13312A9882013-11-0808 November 2013 Summary of Public Meeting with Duke Energy Carolinas, LLC, to Provide Opportunities to Discuss the Planned Fukushima-Related Modifications ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13212A3372013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting2013-07-31031 July 2013 NRC NEI-01-01 Meeting Presentation on 7/31/13 Digital I&C Meeting NEI 01-01, 7/31/2013 NRC Public Meeting Presentation on NEI 01-012013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13218B3372013-07-30030 July 2013 Handout for 7/30/13 Conference Call Re. Harris Emergency Response Facility Activation Timeliness and Criteria ML13211A3782013-07-30030 July 2013 7/31/2013 NRC Public Meeting Presentation on NEI 01-01 ML13204A2562013-07-0909 July 2013 Handout - LOOP Voltage Setpoint Change Presubmittal Conference Call - July 9, 2013 ML13170A3352013-06-13013 June 2013 Presentation - NRC Special Inspection Meeting - Harris Reactor Pressure Vessel ML12277A0272012-10-0202 October 2012 Slides - Summary of Meeting with Duke Energy Carolinas to Discuss Noncenservative Technical Specifications License Amendment Requests ML12242A4322012-08-28028 August 2012 Summary of Category 1 Public Meeting - Regulatory Conference and Predecisional Enforcement Conference ML12206A3252012-08-0707 August 2012 G20120513/EDATS: OEDO-2012-0436 - Briefing Book for Meeting with Duke Energy on August 7, 2012 ML12188A0712012-07-11011 July 2012 G20120473/ EDATS: OEDO-2012-0404 - Briefing Book - Briefing Package for Meeting with Duke Energy on July 11, 2012 ML12107A0012012-04-16016 April 2012 Meeting Summary - Category 1 Public Meeting - Annual Assessment of Shearon Harris Nuclear Plant ML11354A3782012-02-0808 February 2012 Meeting Handout - Meeting with Carolina Power and Light Suggested Discussion Items Regarding Realistic Large Break Loss-of-Coolant Accident HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-0282012-01-11011 January 2012 Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028 ML12076A1652012-01-11011 January 2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting ML1118011132011-06-29029 June 2011 NRC Staff Response to NFPA 805 Transition FAQ 10-0059, Revision 1 ML1113704082011-05-0909 May 2011 Meeting Slides Regarding Human Performance Improvement ML1107301382011-04-21021 April 2011 February 22, 2011, Summary of Pre-application Meeting with Carolina Power & Light and Representatives Regarding Upcoming BWR Boraflew License Amendment Request W/ Public Meeting Slides ML1111000242011-04-20020 April 2011 Meeting Summary - Shearon Harris - List of Attendees ML1014102712010-05-18018 May 2010 Shearon Harris Nuclear Plant Annual Assessment Meeting Slides ML0922900342009-08-17017 August 2009 08/19/09-Meeting Slides for 11th International Seminar on Fire Safety in Nuclear Power Plants and Installations, Risk-Informed, Performance-Based Fire Protection: a U.S. Regulatory Perspective ML0916605042009-06-24024 June 2009 04/21-22/2009 Summary of Category 2 Meeting with Progress Energy Carolinas, Inc., and Duke Energy Carolinas, LLC, to Discuss Topics Involving the License Amendment Requests to Transition Shearon, Unit 1 and Oconee to NFPA 805 ML0904906122009-02-18018 February 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, February, 2009 ML0829601532008-11-17017 November 2008 Summary of Meeting with Progress Energy Carolinas, Inc., to Discuss Shearon Harris Unit 1 National Fire Protection Association Standard 805 License Amendment Request ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0820703912008-07-17017 July 2008 Meeting Handouts from 7/17/08 Public Meeting on the Harris and Oconee LARs to Transition to NFPA-805 M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0818407352008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris Fire PRA Lessons Learned ML0818407312008-06-20020 June 2008 NFPA-805 Workshop Handouts - Harris NFPA-805 Results and Lessons Learned ML0812003342008-04-17017 April 2008 NFPA 805 Transition Pilot Plant FAQ Log - April 2008 2024-04-09
[Table view] |
See also: RIS 2004-03
Text
Note: RG = Ray Gallucci
JC = Jeff Circle
SL = Steve Laur
FPIP-0122 Expert Panel Review of Multiple Spurious Actuations
(1) 9.1. The expert panel review may be the only one of the three inputs (SSD
analysis and internal events PSA reviews are the others) that can identify
previously unknown or dismissed circuit failure combinations. The guidance from
RIS 2004-03 (note incorrect reference to RIS 2003-04) is intended for inspection
purposes and not as a limiting factor for fire PSA. The expert panel should
consider combinations of >2 cables if the "3-4 circuit failures" are possible, as
well as intercable thermosets. (RG)
(2) Att. 3, 1.2. Under Phase 2, while it is appropriate to discuss regulatory
guidance, note that the fire PSA is not limited in scope by regulatory guidance for
MSOs (see above). (RG)
(3) Att. 3, 1.2.1. In light of Duke's recent armored cable tests, you may want to
remove the armored cable example under the second bullet. (RG)
(4) It would aid my understanding if the term "required cable" was defined,
similar to the RIS 2004-03 sentence: If damage to the circuits or cables under
consideration would have a direct impact on the operation of equipment or
systems that are relied on to perform an essential shutdown function, the circuits
and cables are considered "required circuits." (SL)
(5) Definition 3.10, "Risk Significant," is not about risk but likelihood. Since we
use risk as a defined term, I think they should change this to something like
"Candidate Spurious Actuations" or delete the definition. (SL)
(6) In Section 9.3, there is no requirement for how much experience the
"experts" need to have. Further, the quorum specifies a number of members, but
does not ensure key individuals are present - for example, I would say that an
electrical or I&C engineer who is very familiar with the plant wiring diagrams and
schematics would be a "must" for any such meeting. (SL)
(7) In Section 9.4 - I do not agree that no training is necessary. I would say that
training on the definitions ("required cable;" "Bin 1," etc.) and on the meaning of
the criteria would be necessary. (SL)
(8) Section 3.10, Risk Significant.: Guidance is for selection of concurrent
multiple spurious actuations based on RIS-2004-03 classification of "most risk
significant". What are the actual criteria for that assessment? (JC)
(9) Section 9.1 Background. Circuit Analysis.: Focuses the expert panel on
reviewing "high risk", potential two cable failures per scenario. There may be
combinations that are overlooked using that approach. Has the licensee
considered other means to achieve this goal? (JC)
FPIP-0202 Fire PRA Component Selection
(1) 9.2.2. Ensure that initiators, although not mapped to specific basic events in
the internal events PSA, cannot be caused by equipment failures that would
otherwise have been excluded from mapping if such equipment were fire
affected. E.g., if an automatic turbine (reactor) trip could be caused by a fire-
induced faulty signal on some instrument(s) that would not normally be part of
the internal events PSA, ensure that such instrument(s) is identified as potentially
relevant for fire-induced turbine (reactor) trip. (RG)
(2) 9.3. Again, do not limit inclusion of an SSEL component only to those whose
fire-induced failure would affect mitigation capability - include any that could
induce initiators. (RG)
(3) 9.4.6. RAW is only one measure of risk importance. Fussell-Vesely (F-V)
should also be considered, and the list of potentially risk-significant components
should be drawn from the union of the two sets. (RG)
(4) 9.4.7. In conjunction with above, assign an "L" only if both RAW and F-V
indicate low risk-significance. (RG)
(5) In section 9.4, plan to start equipment list with SSEL and non-App R
equipment that has the potential to be highly risk significant. This is fine as it's a
start. Curious to know how they intend to establish risk significance prior to doing
the analysis. Note that this is a Standard issue. General assumptions regarding
existence of highly redundant trains could be an approach, but the procedure
doesn't say. Curious to know licensees thoughts, as it may be relevant to our
resolution of this issue in the Standard.
(6) 9.4.7 says cannot have a fire induced Large Break LOCA. For a BWR, we
have identified inspection findings, i.e. potential spuriously multiple stuck open
MSRVs, which could be a large break LOCA. I presume this can occur with a
PWR. Right?
(7) Section 9.1, Overview: Is there any guidance on the need to reconcile
internal event PRA components which might have been screened out on low
probability such as flow diversion paths? (JC)
FPIP-0104, Safe Shutdown Equipment List and Fault Tree Logics
(1) Item 4.1.8: Why is the shutdown engineer directed to have fault tree
database files be revised by individuals familiar with IRRAS/MAR-D text files
since Progress Energy uses CAFTA? Note that the name IRRAS has been
SAPHIRE for the last 14 years. (JC)
(2) Section 9.1.2, Safe Shutdown Component Selection Criteria, Item 17:
Shouldnt guidance on interlocking circuitry should also include CWDs (or
elementaries) which will model the actual transmitters and their associated power
supplies? An important interaction might be overlooked if only P&IDs
("instrument schematics") were employed. (JC)
(3) Attachment 1 on Fluid System Modeling Rules: Assuming that this is set up
for modular fault trees however, there is no key to the module top gates. It might
be cryptic for licensee personnel to use. (JC)