ML19323E221
| ML19323E221 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/13/2019 |
| From: | Vaughn Thomas NRC/NRR/DORL/LPL4 |
| To: | Geoffrey Miller Dominion Energy Co |
| References | |
| Download: ML19323E221 (3) | |
Text
From:
Thomas, Vaughn Sent:
Wednesday, November 13, 2019 11:15 AM To:
gary.d.miller@dominionenergy.com Cc:
Miller, Ed
Subject:
RE: RAI on the SPS RTB CT Extension LAR Attachments:
RAI Regarding Surry TSTF-411 LAR to Extend Rx Trip Breaker TS CT to 24 Hours.docx
- Gary, The attached file constitutes the staffs issuance of the final RAI to you. As agreed upon on the clarification call on November 5, 2019, the staff expects your response to the RAI within 30 days from todays date, November 13, 2019.
Thanks Vaughn From: gary.d.miller@dominionenergy.com <gary.d.miller@dominionenergy.com>
Sent: Tuesday, November 12, 2019 3:45 PM To: Thomas, Vaughn <Vaughn.Thomas@nrc.gov>
Subject:
[External_Sender] RAI on the SPS RTB CT Extension LAR Hi Vaughn, Do you know when the final RAI will be issued on the SPS RTB CT Extension LAR?
Gary D. Miller Consulting Engineer - Corporate Licensing Nuclear Regulatory Affairs Dominion Energy, Inc.
(804) 273-2771
Hearing Identifier:
NRR_DRMA Email Number:
316 Mail Envelope Properties (BN7PR09MB25293C41F8714FD6D216BC44F4760)
Subject:
RE: RAI on the SPS RTB CT Extension LAR Sent Date:
11/13/2019 11:15:07 AM Received Date:
11/13/2019 11:15:00 AM From:
Thomas, Vaughn Created By:
Vaughn.Thomas@nrc.gov Recipients:
"Miller, Ed" <Ed.Miller@nrc.gov>
Tracking Status: None "gary.d.miller@dominionenergy.com" <gary.d.miller@dominionenergy.com>
Tracking Status: None Post Office:
BN7PR09MB2529.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 770 11/13/2019 11:15:00 AM RAI Regarding Surry TSTF-411 LAR to Extend Rx Trip Breaker TS CT to 24 Hours.docx 33090 Options Priority:
Normal Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
REQUEST FOR ADDITONAL INFORMATION PERTAINING TO TECHNICAL SPECIFICATION LICENSING AMENDMENT REQUEST FOR 24-HOUR ALLOWED OUTAGE TIME FOR INOPERABLE REACTOR TRIP BREAKERS 1
APLA RAI 01 - Avoidance of Risk Significant Plant Configurations RG 1.177, An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications, (ADAMS Accession No. ML100910008) states, [t]he licensee should provide reasonable assurance that risk-significant plant equipment outage configurations will not occur when specific plant equipment is out of service consistent with the proposed TS [technical specification] change.
The LAR states that the proposed change to the RTB completion time (CT) has been developed using the risk-informed processes described in WCAP-15376-P-A, "Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times," Revision 1. LAR Section 3.3 states that a detailed review of PRA importance metrics (Risk Achievement Worth, Fussell-Vesely) from the Tier 1 PRA model did not reveal any risk significant maintenance configurations when one RTB [reactor trip breaker] is unavailable. Furthermore, LAR Section 6.0 identifies only one system (i.e., Anticipated Transient without Scram (ATWS) Mitigating System Actuation Circuitry (AMSAC)) where no maintenance will be planned while one RTB is inoperable. However, Section 8.5 of WCAP-15376 identifies restrictions that should be placed on certain equipment when an RTB is out of service (i.e., reactor coolant system (RCS) pressure relief system, auxiliary feedwater flow, AMSAC, turbine trip, activities that degrade other components of the Reactor Protection System (RPS) (including master relays or slave relays and activities that cause analog channels to be unavailable), and AC and DC power distributions that support the restricted components).
Considering these observations; Explain how the importance factors were used to assess the risk-significant plant equipment configurations while an RTB is out of service during the extended CT. Include the criteria used (e.g., Risk Achievement Worth (RAW) and Risk Reduction Worth (RRW) threshold values, etc.)
to determine risk significance. In the response, also confirm (i.e., include justification) that the unavailability of the systems/components identified in Section 8.5 of WCAP-15376 (i.e., RCS pressure relief system, auxiliary feedwater flow, ASMAC, turbine trip, other RPS components including master and slave relays, and AC and DC power distribution) along with an out-of-service RTB would not create a risk significant configuration.