ML14015A456
| ML14015A456 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/30/2014 |
| From: | Martin R Plant Licensing Branch II |
| To: | Pierce C Southern Nuclear Operating Co |
| Martin, Robert NRR/DORL 415-1493 | |
| References | |
| TAC MF2594, TAC MF2595 | |
| Download: ML14015A456 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 30, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MF2594 and MF2595)
Dear Mr. Pierce:
By letter dated August 20,2013, (Agency-Wide Documents Access and Management System (ADAMS) Accession Number ML13233A112), Southern Nuclear Operating Company, Inc.
(SNC) submitted a license amendment request (LAR, Reference 1) to facilitate an amendment to the Site Emergency Plan (SEP) for the Vogtle Electric Generating Plant (VEGP), Units 1 and
- 2. SNC requested review and approval of a revision to the VEGP SEP that revises the Emergency Action Level (EAL) thresholds for Initiating Conditions (ICs) RU1, RA1, RS1, and RG1. The proposed change would remove Main Steam line (MSL) radiation monitors RE 13119, RE-13120, RE-13121, and RE-13122 from the reference ICs to address limitations of these monitors.
Based on the U.S. Nuclear Regulatory Commission (NRC) staff's initial review, additional information (RAls) is requested. The following RAls are based upon information provided in SNC's August 20, 2013 LAR, as well as from Nuclear Energy institute (NEI) 10-05, "Assessment of On-Shift Emergency Response Organization Staffing and Capabilities," Revision 0 (ADAMS Accession Number ML111751698, Reference 2), and NRC Interim Staff Guidance (NSIR/DPR ISG-01), "Emergency Planning for Nuclear Power Plants" (ADAMS Accession Number ML113010523, Reference 3).
RAI No.1 Section 3.0 of SNC's LAR states in part:
The timely performance of dose assessments using actual meteorology and release information, including the evaluation of unmonitored release pathways (e.g., [Steam Generator Tube Rupture (SGTR)] releasing out the [Atmospheric Relief Valve (ARV)]/Code SafetieslTerry Turbine) utilizing the back-calculation capability of the Meteorological Information Dose Assessment System (MIDAS),
is required by procedure. Dose assessment capabilities are available on-shift.
RAI1.a Provide justification that SGTR releases out of the ARV/Code SafetieslTerry Turbine are sufficiently tracked to utilize the back-calculation capability of MIDAS.
This justification should include both procedures and any required training.
RAI1.b Clarify what positions(s) will perform dose assessments for the unmonitored pathway releases and provide justification to support the qualifications of on-shift personnel to evaluate unmonitored pathway releases, including back calculations.
C.R. Pierce
- 2 RAI No.2 Section 3.0 of SNC's LAR states in part:
Emergency implementing procedures are in place to ensure the availability of these dose assessments prior to the onset of core damage capable of providing the source term required to exceed the protective action guidelines.
Activation of the dose assessment function and rapid dispatch of field monitoring teams is performed to facilitate the timely assessment of radiological releases via unmonitored pathways in accordance with plant procedure.
RA12.a Provide justification that on-shift dose assessment capability will be available at all times.
RA12.b Explain the supporting documentation that provides the basis for the terms "rapid dispatch" and "timely assessment" in Section 3.0 of Reference 1.
RAI NO.3:
Provide relevant portions of SNC's On-Shift Staffing Analysis performed in accordance with 10 CFR Part 50 Appendix E.IV.A.9 that supports SNC's position that dose assessment capability will be maintained for all relevant scenarios as listed in References 2 and 3 above.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely,
~~roject Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 cc w/encl: Distribution via Listserv
C.R. Pierce
- 2 RAI No.2 Section 3.0 of SNC's LAR states in part:
Emergency implementing procedures are in place to ensure the availability of these dose assessments prior to the onset of core damage capable of providing the source term required to exceed the protective action guidelines.
Activation of the dose assessment function and rapid dispatch of field monitoring teams is performed to facilitate the timely assessment of radiological releases via unmonitored pathways in accordance with plant procedure.
RAI2.a Provide justification that on-shift dose assessment capability will be available at all times.
RAI2.b Explain the supporting documentation that provides the basis for the terms "rapid dispatch" and "timely assessment" in Section 3.0 of Reference 1.
RAI NO.3:
Provide relevant portions of SNC's On-Shift Staffing Analysis performed in accordance with 10 CFR Part 50 Appendix E.IV.A.9 that supports SNC's position that dose assessment capability will be maintained for a/l relevant scenarios as listed in References 2 and 3 above.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch /1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 cc w/encl: Distribution via Listserv DISTRIBUTION:
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RPascarelli RMartin IDATE 01/27/14 l01/27/14 01114114 01/29/14 01/30/14 OFFICIAL RECORD COPY