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MONTHYEARML13093A0642013-03-28028 March 2013 License Amendment Request Pursuant to 10 CFR 50.90: Adoption of NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request ML13093A0652013-03-29029 March 2013 Transition Report to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition - Transition Report, Redacted Version. Enclosure 2 Project stage: Request ML13161A2852013-06-0505 June 2013 NRR E-mail Capture - Acceptance Review Concerning Request to Adopt National Fire Protection Association Standard NFPA-805, Project stage: Acceptance Review ML13162A4402013-06-20020 June 2013 R. E. Ginna Nuclear Power Plant - Acceptance Review Concerning Request to Adopt National Fire Protection Association Standard NFPA-805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants Project stage: Acceptance Review ML13261A1142013-09-12012 September 2013 R. E. Ginna Nuclear Power Plant, E-mail Re. NFPA 805 License Amendment Request, Audit RAIs Project stage: Acceptance Review ML14343A9902014-12-0909 December 2014 NRR E-mail Capture - Ginna Nuclear Power Plant-Request for Additional Information Regarding NFPA-805 Amendment Request. Project stage: RAI ML15154B6552015-06-0202 June 2015 E-mail Request Conference Call to Discuss Ginna'S 4/24/15 Supplement for the Proposed NFPA-805 Amendment Project stage: Other ML15167A5042015-06-11011 June 2015 Transmittal of Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Adopt NFPA 805 Project stage: Response to RAI ML15167A5052015-06-11011 June 2015 (Redacted Version) Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Adopt NFPA 805, Attachment 3 Project stage: Response to RAI ML15181A1132015-06-30030 June 2015 NRR E-mail Capture - Request for Additional Clarification of Ginna'S Response to PRA RAI 44.01.b Project stage: RAI ML15191A4132015-07-10010 July 2015 NRR E-mail Capture - Summary of the Conference Call with Ginna Re. the Proposed NFPA-805 Amendment Project stage: Other ML15210A9042015-07-29029 July 2015 NRR E-mail Capture - NRC Staff Comments on the Roadmap Project stage: Other ML15188A2132015-08-20020 August 2015 Report of Audit to Support Proposed Amendment to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis Project stage: Other 2014-12-09
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From: Tam, Peter Sent: Tuesday, June 02, 2015 4:40 PM thomas.hardingjr@exeloncorp.com To: Cc: Goel, Vijay; Mathew, Roy; Dudek, Michael; Mozafari, Brenda; Helton, Shana; Zimmerman, Jacob Subject: Request conference call to discuss Ginna's 4/24/15 supplement for the proposed NFPA-805 amendment (TAC MF1393) Tom: As you and I discussed by phone this afternoon, following please find talking points to support the subject proposed conference call. We plan to use the talking points to guide us in the conference call to understand better Ginna's 4/24/15 supplemental information (ADAMS Accession No. ML 15119A055), and also to provide you and your staff, perhaps retroactively, clarification of the RAI that led to the 4/24/15 supplement. Please contact me to pick a date and time for the conference call. In that conference call, we will discuss disposition of the issues depicted by these talking points. This email will be immediately docketed into NRC's Official Agency Record system, ADAMS, but we will withhold public release for 10 days pending your confirmation that there is no proprietary or security-related information in this email. 1. The staff found some discrepancies in the submittal provided by the licensee on April 24, 2015. Please provide clarifications to resolve the following: a) In Attachment 1, Page 2 (response to NRC Question 2), the licensee states: "The 2400 Amp pickup setting is not too low even though the estimate of the short time current has increased to 6,609 Amp RMS (Reference Rev. 8 of DA-EE-93-104-07, Page 243 [Attachment 2])." The staff could not find the "6,609 Amp" in Attachment 2, Page 243. b) In Attachment 1, Page 2 (response to NRC Question 2), the licensee states: "At 6,609 Amps RMS, the overcurrent portion of the COV-8 relay takes about 1 second to time out (Reference Page 245 of EE-93-104-07, Rev. 8 [Attachment 2])." The staff could not find the "overcurrent portion of the COV-8 relay" in Attachment 2, Page 245. c) In Attachment 1, Page 2 (response to NRC Question 2): The licensee referred to Calculation DA-EE-92-111-01, Rev. 2 [Attachment 3). The licensee stated that the maximum reset of the LOV [loss of voltage) relay is assumed to be 79.42% of 480V ... " The staff finds the 79.42% is shown as the "maximum dropout of LOV" on Page 38 of Calculation EE-92-104-07, Rev. 8 [Attachment 2), and as "maximum analytical limit of 381.2 voltage (79.42% of 480V)" on Page 31 of DA-EE-92-111-01, Rev. 2 [Attachment 3). 1 d) In Attachment 1, Page 3 (response to Question 2a): The licensee stated that the existing overcurrent setting of the COV-8 (2400 Amps) will provide thermal protection for the EOG (Reference Page 245 of DA-EE-93-104-07 Rev. 8 [Attachment 2]) during faulted conditions. The staff could not find the "thermal protection for the EOG" in Reference Page 245 of DA-EE-93-104-07 [Attachment 2]. 2. In response to NRC Question 2, the licensee stated: "Calculation DA-EE-92-111-01, Rev.2, "Diesel Generator A Dynamic Loading Analysis" provides insight on the relationship between EOG voltage and current. Page 8 of that calculation summarizes the LOV pickup duration for the various simulations. Since the maximum reset of the LOV relay is assumed to be 79.42% of 480V, page 8 also effectively summarizes the maximum amount of time that the voltage element of the COV-8 relay will be picked up (80%)." The licensee also stated: "The above-mentioned simulation (DGA_FU9) suggests that it might be possible for the COV-8 relay to operate during a very low probability LOCA [Loss-of-Coolant Accident] sequencing event. However, for the more realistic LOCA sequencing scenarios involving contingencies (DG_FU6) and for manual motor starts after the LOCA sequencing event (DG_FU8), the COV-8 relay will not trip." The staff notes that there is a potential for tripping the EDGs under the required design basis accident loading conditions. Please clarify whether the COV-8 relay settings have adequate margin to account for tolerances in relay setting, drift, inaccuracy in calculations due to data assumptions etc. 3. In response to NRC Question 3, the licensee states: "Actual motor starting simulations in DA-EE-92-111-01 [Attachment 3] demonstrate that the voltage element pickup will only be between 0.76 and 2.26 seconds rather than 5 seconds (See page 8 of DA-EE-92-111-01, Rev. 2)." Section 2.3 of Calculation DA-EE-92-111-01 [Attachment 3] stated that some scenarios may cause the Bus 14 loss of voltage (LOV) relay to inadvertently operate during the sequencing of loads. Section 2.4 of the calculation also identifies the need for further investigation in order to increase the existing margins in order to avoid an inadvertent operation of the LOV relay. Please explain why the above condition (some scenarios may cause the Bus 14 loss of voltage (LOV) relay to inadvertently operate during the sequencing of loads) is considered acceptable, considering COV-8 undervoltage setting is approximately same as LOV relay. Please also explain the design function of LOV relay and consequences of inadvertently actuating the relay during sequencing or operation of the EOG. 4. In response to NRC Question 5, the licensee stated: The DB-75 Amptector (52/EG1A1) is not bypassed on an SI. It is noted that 52/EG1A1 is the equipment designation being used for the DB-75 Amptector between the EOG and Bus 14 that is shown on page 245 of DA-EE-93-104-07, Rev. 8 [Attachment 2]. This device will isolate Bus 14 from the EOG if a fault exists on Bus 14. This Amptector is not considered a "diesel generator protective trip" because it sees only a portion of the EOG current (Bus 18 current not seen by this Amptector -See Drawing 33013-2539, Rev. 28). Isolating Bus 14 because of a "bus fault" or a failure of one of the load breakers to clear a "fault or serious overload" is a desirable action during an SI event because Bus 18 can still be supplied by the EOG. This Amptector may also limit the amount of EOG damage during such an event. A "faulted" Bus 14 will not be of any use in mitigating an accident so there is no credible reason to bypass the Amptector during an SI [Safety Injection]. Regarding the above response, the licensee is requested to provide the following additional information: a) The staff could not find the "DB-75 Amptector between the EOG and Bus 14 on Page 245 of DA-EE-93-104-07 [Attachment 2]. Please provide appropriate pages of Calculation of DA-EE-93-104-07. 2 b) Please provide time-current coordination curves for the 52/EG1A 1, 52/EG1A2, 52/EG1 B1, 52/EG1 B2, and 52/EG1 B3 breakers (which have built-in an Amptector protection device), showing the coordination with the upstream protection device (COV-8) and the most-limiting downstream protection device(s). c) Please describe physical location of breaker 52/EG1 B3 in relation to the DG "B". d) Please confirm whether the maximum current which can pass through 52/EG1A 1, 52/EG1A2, 52/EG1 B1, 52/EG1 B2, and 52/EG1 B3 during worst case scenarios can cause tripping of these breakers. e) Provide a description of the Amptector overcurrent protection devices of DG breakers 52/EG1A1, 52/EG1A2, 52/EG1 B1, 52/EG1 B2, and 52/EG1 B3. 5. The licensee also provided a copy of the calculation DA-EE-98-089, Rev 1 [Attachment 4). Section 2.2 of this calculation states: "Coordination of these relays [COV-8 relays] with any downstream devices is not relevant during the time period that an SI signal is present since the effective operation of these relays is blocked during that time." The staff finds that above statement will be no longer valid if the LAR "to not bypass these controlled overcurrent relays" is approved. Please provide an update or mark-up copy of the above calculation with changes based on the requested amendment. 6. Section 2.3 of calculation DA-EE-98-089, Rev 1 [Attachment 4) also states: "The 51/27 [COV-8) relays will also not coordinate with 52/EG1 B3 for phase faults on Bus 17 or the feeder cable to Bus 17. Since this issue may cause a common mode failure for both Emergency Diesel Generators during a fire in the Screen House, setting changes to the 52/EG1 B3 breaker is required." Please explain how a common mode failure for both Emergency Diesel Generators can occur during a fire in the Screen House, and how the changes made to the settings of 52/EG1 B3 breaker helped to avoid the common mode failure. Senior Project Manager Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 3