ML081910406: Difference between revisions
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{{#Wiki_filter:David Loveless From: | {{#Wiki_filter:David Loveless From: | ||
Sent: | Sent: | ||
To: | |||
cc: | |||
==Subject:== | ==Subject:== | ||
Furr, Virgel T. [vtfurr@nppd.com] | |||
Wednesday, July 02,2008 350 PM David Loveless Neil OKeefe; Wayne Walker; Kline, Gary J.; Van Der Kamp, David; Sutton, Kent E.; Bhardwaj, Vasant N. [Vas]; Colomb, Michael [Mike] J. | |||
Supporting information for the final SDP | Supporting information for the final SDP | ||
: David, We are trying to quantify the deltas between the NRC methods and results with the CNS methods and results. | : David, We are trying to quantify the deltas between the NRC methods and results with the CNS methods and results. | ||
Unfortunately, there is not enough detail in the final significance determination for us to completely understand these deltas. Therefore, we are requesting the following supporting information | Unfortunately, there is not enough detail in the final significance determination for us to completely understand these deltas. Therefore, we are requesting the following supporting information | ||
: 1. The change sets for the non-control room evaluation cases. | : 1. | ||
: 2. | |||
: 3. | |||
probability of 7.9E-02, or the quantified event with the branch and end state values shown. | |||
: 4. | |||
cases. | |||
Virgel Furr Rusk Management Cooper Nuclear Station | : 5. | ||
of Figure 2? | |||
: 6. | |||
and the basis for the branch assignments for the split fraction? | |||
The change sets for the non-control room evaluation cases. | |||
The SPAR-H sheets to support the HRA values The HRA event tree used to determine the non-recovery The linked event tree model used to evaluate the MCR evacuation The basis for the use of the same HRA value in sequence 5 and 7 The basis for the 0.1 and 0.9 SRV-STATUS split fraction value Virgel Furr Rusk Management Cooper Nuclear Station | |||
David Loveless From: | David Loveless From: | ||
Sent: | Sent: | ||
To: | |||
cc: | |||
==Subject:== | ==Subject:== | ||
Follow-up information | Furr, Virgel T. [vtfurrQnppd.com] | ||
Tuesday, July 08,2008 4:Ol PM David Loveless Sutton, Kent E.; Bhardwaj, Vasant N. [Vas]; Van Der Kamp, David; Flaherty, James R.; Ward, Mark R.; Neil OKeefe Follow-up information | |||
: David, First of all, thanks for the information you have sent thus far. The information on the HRAs cleared up a lot of confusion. Looking at my original e-mail it looks like items 1 through 3 have been sent. After review of this information, we would like the following additional information: | : David, First of all, thanks for the information you have sent thus far. The information on the HRAs cleared up a lot of confusion. Looking at my original e-mail it looks like items 1 through 3 have been sent. After review of this information, we would like the following additional information: | ||
: 1. All the cutsets from figure 1 | : 1. | ||
: 2. | |||
: 3. | |||
All the cutsets from figure 1 The timeline used in the evaluation of the HRA for Supporting information for the "Best Estimate of Fraction" for "OPEN-MO-25B-5/7" "SRV-STATUS. | |||
This information is the same as asked for earlier, but a little more focused on justification for the HRA assumptions. | This information is the same as asked for earlier, but a little more focused on justification for the HRA assumptions. | ||
Virgel Furr Risk Management Cooper Nuclear Station 1}} | Virgel Furr Risk Management Cooper Nuclear Station 1}} | ||
Latest revision as of 16:08, 14 January 2025
| ML081910406 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/02/2008 |
| From: | Furr V Nebraska Public Power District (NPPD) |
| To: | David Loveless Division of Reactor Safety IV |
| References | |
| Download: ML081910406 (2) | |
Text
David Loveless From:
Sent:
To:
cc:
Subject:
Furr, Virgel T. [vtfurr@nppd.com]
Wednesday, July 02,2008 350 PM David Loveless Neil OKeefe; Wayne Walker; Kline, Gary J.; Van Der Kamp, David; Sutton, Kent E.; Bhardwaj, Vasant N. [Vas]; Colomb, Michael [Mike] J.
Supporting information for the final SDP
- David, We are trying to quantify the deltas between the NRC methods and results with the CNS methods and results.
Unfortunately, there is not enough detail in the final significance determination for us to completely understand these deltas. Therefore, we are requesting the following supporting information
- 1.
- 2.
- 3.
probability of 7.9E-02, or the quantified event with the branch and end state values shown.
- 4.
cases.
- 5.
of Figure 2?
- 6.
and the basis for the branch assignments for the split fraction?
The change sets for the non-control room evaluation cases.
The SPAR-H sheets to support the HRA values The HRA event tree used to determine the non-recovery The linked event tree model used to evaluate the MCR evacuation The basis for the use of the same HRA value in sequence 5 and 7 The basis for the 0.1 and 0.9 SRV-STATUS split fraction value Virgel Furr Rusk Management Cooper Nuclear Station
David Loveless From:
Sent:
To:
cc:
Subject:
Furr, Virgel T. [vtfurrQnppd.com]
Tuesday, July 08,2008 4:Ol PM David Loveless Sutton, Kent E.; Bhardwaj, Vasant N. [Vas]; Van Der Kamp, David; Flaherty, James R.; Ward, Mark R.; Neil OKeefe Follow-up information
- David, First of all, thanks for the information you have sent thus far. The information on the HRAs cleared up a lot of confusion. Looking at my original e-mail it looks like items 1 through 3 have been sent. After review of this information, we would like the following additional information:
- 1.
- 2.
- 3.
All the cutsets from figure 1 The timeline used in the evaluation of the HRA for Supporting information for the "Best Estimate of Fraction" for "OPEN-MO-25B-5/7" "SRV-STATUS.
This information is the same as asked for earlier, but a little more focused on justification for the HRA assumptions.
Virgel Furr Risk Management Cooper Nuclear Station 1