ML14051A397

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NFPA 805 IE PRA F&O Tables
ML14051A397
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/20/2014
From: Js Hyslop
NRC/NRR/DRA/APLA
To:
Hyslop J, NRR/DRA, 415-4107
References
Download: ML14051A397 (8)


Text

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 1 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE IE-2 A

IE-7 A

IE-8 A

SY-1 A

SY-2 A

SY-3 A

SY-7 A

SY-8 A

SY-9 B

SY-10 A

SY-11 See PRA-RAI-16a. Acceptable to the NRC staff because the licensee determined that isolation of CCW to the Spent Fuel Pool heat exchangers is not necessary for CCW to perform its function.

SY-13 A, C SY-19 A

SY-20 A

SY-21 See PRA-RAI-14.01, PRA-RAI-16b, and PRA-RAI-25 SY-22 A

SY-23 A

SY-24 A

SY-25 A

DA-1 A

DA-2 A

DA-5 A

DA-6 A

DA-7 A

DA-8 A

HR-1 A

HR-2 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore,

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 2 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-3 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-4 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-6 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-7 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-8 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-9 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 3 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-10 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-11 This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

DE-1 A

DE-2 A

DE-4 A, C QU-1 A

QU-2 A

See PRA-RAI-14.01. Acceptable to the NRC staff because the licensee determined that existing procedures direct the performance of reasonableness and correctness reviews, and that these procedures were followed for the model updates incorporating changes made in resolution to peer review F&Os.

QU-3 A

See PRA-RAI-14.01. Acceptable to the NRC staff because the licensee determined that existing procedures direct the performance of a dependency analysis for each revision of the model.

QU-4 A

See PRA-RAI-14.01. Acceptable to the NRC staff because asymmetries were addressed and documented; asymmetries for pumps normally experiencing operational rotation were removed from

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 4 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE the model.

QU-5 A

This F&O is from the 1999 peer review. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, the portion of the F&O related to HRA is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

QU-6 A

MU-1 A

MU-2 A

IF-A1-01 A

IF-B2-01 A

IF-C3-01 A

IF-E7-01 A

IE-01-GA A

IE-03-GA A

IE-04-GA A

IE-06-GA A

AS-01-GA A

HR-01-GA This F&O is from the 2006 gap assessment. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

HR-03-GA This F&O is from the 2006 gap assessment. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

IF-01-GA This F&O is from the 2006 gap assessment. The 2008 focused-scope peer review re-assessed the IF technical element (see PRA-RAI-14.01), therefore,

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 5 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

IF-04-GA This F&O is from the 2006 gap assessment. The 2008 focused-scope peer review re-assessed the IF technical element (see PRA-RAI-14.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

LE-01-GA A

LE-02-GA This F&O is from the 2006 gap assessment. The 2013 focused-scope peer review re-assessed the LE technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

QU-01-GA A

QU-02-GA See PRA-RAI-14.01, PRA-RAI-15d, and PRA-RAI-24 QU-03-GA A

SC-01-GA This F&O is related to the HRA and is from the 2006 gap assessment. The 2013 focused-scope peer review re-assessed the HR technical element (see PRA-RAI-18.01), therefore, this F&O is supplanted by F&Os from this peer review and associated resolutions (provided below in this table).

SY-01-GA See PRA-RAI-14.01, PRA-RAI-15c, and PRA-RAI-24 HR-A3-01 C

HR-E1-01 C

HR-E2-01 C

HR-G6-01 C

HR-I1-01 C

HR-I2-01 C

Record of Review Dispositions to Fort Calhoun Internal Events PRA Facts and Observations (F&Os) 6 FINDING/

SUGGESTION (F&O) ID ACCEPTABLE TO STAFF VIA Review of Plant Disposition (A/B/C)

RAI Response Not Discussed in SE Discussed in SE LE-C9-01 C

LE-F2-01 A

LE-G1-01 C

LE-G3-01 A

A: The NRC staff finds that the disposition of the F&O as described by the licensee in the LAR or its supplements 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.

B: The NRC staff finds that the disposition of the F&O as described by the licensee in the LAR and its supplements 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.

C: The NRC staff finds that the resolution of the F&O, as described by the licensee in the LAR or its supplements, 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.

Record of Review Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I 7

SUPPORTING REQUIREMENT (SR)

ACCEPTABLE TO STAFF VIA Review of Plant Acceptability Basis (A/B/C)

RAI Response Not Discussed in SE Discussed in SE IE-A8 See PRA-RAI-15a. Acceptable to the NRC staff because the licensee conducted formal interviews with licensed operators, Shift Technical Advisors, and system engineers and no new internal events initiators were identified.

SY-A4 See PRA-RAI-15b. Acceptable to the NRC staff because plant walkdowns were performed and a preliminary determination was made that there are no discrepancies between the PRA and as-built as-operated plant.

SY-A8 See PRA-RAI-14.01, PRA-RAI-15c, and PRA-

RAI-24

QU-A3 See PRA-RAI-14.01, PRA-RAI-15d, and PRA-

RAI-24

QU-E3 See PRA-RAI-14.01, PRA-RAI-15d, and PRA-

RAI-24

HR-I2 A

DA-A2 See PRA-RAI-14.01, PRA-RAI-15c, and PRA-

RAI-24

LE-C11 A

LE-C12 A

LE-C13 A

LE-G5 A

LE-D3 A

IFSN-A6 C

A: The NRC staff finds that the acceptability basis for the capability category of the SR as described by the licensee in the LAR and its supplements 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: The NRC staff finds that the acceptability basis for the capability category of the SR as described by the licensee in the LAR and its

Record of Review Supporting Requirements (SRs) Not Met or Met at Capability Category (CC) I 8

supplements 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: The NRC staff finds that the acceptability basis for the capability category of the SR, as described by the licensee in the LAR and its supplements, 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.