ML14329A426
| ML14329A426 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/22/2014 |
| From: | Leslie Fields NRC/NRR/DRA/APLA |
| To: | |
| Fields L, NRR/DRA, 415-1183 | |
| References | |
| Download: ML14329A426 (5) | |
Text
Record of Review Dispositions to Arkansas Nuclear One Unit 2 (ANO-2) Fire PRA Facts and Observations (F&Os) and Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I October 22, 2014 1
Finding/
Suggestion (F&O) ID or Supporting Requirement (SR)i ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)
RAI Response Not Discussed in SE Discussed in SE CF-A1-01 A
CF-B1-01 See PRA RAI-01.a. Acceptable to staff because the licensee explains that a review of the Altered Events table was performed to identify and review discrepancies like those identified in F&O CF-BF-01 and by NRC staff in PRA RAI-01.a.
PP-B2 and PP-B3 (From Table V-3 of the LAR. No F&O)
A (With regards the part of the F&O addressing the partition between MCRs see PRA RAI-01.d)
PP-B5 (From Table V-3 of the LAR. No F&O)
A CS-A7-01 A
CS-A8-01 A
CS-A9-01 B
CS-B1 (From Table V-3 of the LAR. No F&O)
See PRA RAI-01.b and disposition to F&O CS-C4-01. Acceptable to staff because the licensee explains that all circuits and electrical distribution buses credited in the fire PRA have been analyzed for over-current coordination and protection. The licensee also explains that specific components have been excluded from failing in specific fire scenarios only after confirmation that their cabling could not be impacted by the scenario. The licensee also explains that corrections were made in the documentation associated with observations in PRA RAI-01.b to clarify the approach.
CS-C4-01 A
Record of Review Dispositions to Arkansas Nuclear One Unit 2 (ANO-2) Fire PRA Facts and Observations (F&Os) and Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I October 22, 2014 2
Finding/
Suggestion (F&O) ID or Supporting Requirement (SR)i ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)
RAI Response Not Discussed in SE Discussed in SE ES-C1-01 A
ES-C1-02 A
ES-D1-01 A
ES-D1-02 A
FSS-A4-01 See PRA RAI-01.c. Acceptable to staff because the licensee explains that the original target list was based on walkdowns, while the final listing also included drawing and database reviews to ensure the list was complete. The licensee also described updates made to the list since the peer review.
FSS-A5-01 A
FSS-B1-02 See PRA RAI-01.d in Section 3.4.2.2 FSS-B2-01 See PRA RAI 01.e and PRA RAI-01.e.01 in Section 3.4.2.2 FSS-C5-01 A
FSS-C8-01 B
FSS-D3-01 See FM RAI-01.f in Section 3.4.2.3.
FSS-D7-01 A
FSS-D8-01 See PRA RAI-01.f and PRA RAI-01.f-01 in Section 3.4.2.2 FSS-D10-01 A
FSS-E2-01 See PRA RAI-01.g and PRA RAI 21 in Section 3.4.2.2 FSS-G2-01 A
Record of Review Dispositions to Arkansas Nuclear One Unit 2 (ANO-2) Fire PRA Facts and Observations (F&Os) and Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I October 22, 2014 3
Finding/
Suggestion (F&O) ID or Supporting Requirement (SR)i ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)
RAI Response Not Discussed in SE Discussed in SE FSS-H1-01 See PRA RAI-01.f and PRA-RAI.f-01 in Section 3.4.2.2 (encompassed by F&O FSS-D8-01 discussion)
FSS-H7-01 See PRA RAI-01.g and PRA RAI 21 in Section 3.4.2.2 (encompassed by F&O FSS-E2-01 discussion)
FSS-H7-02 A
HRA-A2-01 See PRA RAI-01.h discussed in Section 3.4.2.2 HRA-A4-01 A
HRA-D2-01 A
IGN-A5-01 A
IGN-A7-01 See PRA RAI-01.i.
in Section 3.4.2.2 IGN-A10 (From Table V-3. No F&O)
A IGN-B4-01 A
PRM-B2-01 A
PRM-B9-01 A
PRM-C1-01 See PRA RAI-01.j. Acceptable to staff because the licensee explains that no additional initiating event accident sequences, success criteria, or data analyses, beyond that performed for the Internal Events analysis were required. All new failures, including fire-induced failures, and changes made to the Internal Events
Record of Review Dispositions to Arkansas Nuclear One Unit 2 (ANO-2) Fire PRA Facts and Observations (F&Os) and Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I October 22, 2014 4
Finding/
Suggestion (F&O) ID or Supporting Requirement (SR)i ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)
RAI Response Not Discussed in SE Discussed in SE for the Fire PRA are documented in the licensees analysis.
UNC-A1-01 See PRA RAI-01.k and PRA RAI 21 in Section 3.4.2.2.
MU-B4-01 A
Notes; A: For F&Os, the NRC staff finds that the disposition of the F&O as described by the licensee in the LAR provides confidence that the issues raised by the F&O have been addressed and, if needed, the PRA has been modified, and therefore the resolution of the F&O is acceptable for this application. For Not Met or met at CC-I SRs, the NRC staff finds that the acceptability basis for the capability category of the SR as described by the licensee in the LAR provides confidence that the requirements of the SR have been addressed and, if needed, the PRA has been modified, and therefore the PRA quality with respect to the SR is acceptable for this application. Examples of acceptable Not Met and CC-I SRs are modeling methods that yield conservative FRE and change evaluation results.
B: For F&Os, the NRC staff finds that the disposition of the F&O as described by the licensee in the LAR and further clarified during the audit provides confidence that the issues raised by the F&O have been addressed and, if needed, the PRA has been modified, and therefore the resolution of the F&O is acceptable for this application. For Not Met or met at CC-I SRs, the NRC staff finds that the acceptability basis for the capability category of the SR as described by the licensee in the LAR and further clarified during the audit provides confidence that requirements of the SR have been addressed and, if needed, the PRA has been modified, and therefore the PRA quality with respect to the SR is acceptable for this application. Examples of acceptable Not Met and CC-I SRs are modeling methods that yield conservative FRE and change evaluation results.
C: For F&Os, the NRC staff finds that the resolution of the F&O, as described by the licensee in the LAR, would have a negligible effect on the evaluations relied upon to support fire risk evaluations and has no impact on the conclusions of the risk assessment and therefore the resolution of the F&O is acceptable for this application. Examples of such F&Os may be suggestions, as well as those F&Os that don't affect the fire PRA. Documentation issues may fall into this category as well.
For Not Met or met at CC-I SRs, the NRC staff finds that the acceptability basis for the capability category of the SR, as described by the licensee in the LAR, would have a negligible effect on the evaluations relied upon to support fire risk evaluations and has no impact on the conclusions of the risk assessment and therefore the PRA quality with respect to the SR is acceptable for this application. Examples are those SRs that don't affect the fire PRA.
Record of Review Dispositions to Arkansas Nuclear One Unit 2 (ANO-2) Fire PRA Facts and Observations (F&Os) and Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I October 22, 2014 5
i Table includes: 1) all F&O listed in Table V-1 of the LAR from the original full-scope peer review in June 2009, 2) all F&Os from Table V-2 of the LAR from the two focused scope peer reviews conducted October 2011, and November 2012, and 3) all evaluations in Table V-3 of the LAR Supporting Requirements determined to be met only at Capability Category I, for which no F&Os appear in V-1 or V-2 of the LAR.