ML063050380

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E-MAIL: (PA-LR) Information from the Conference Call on 9/26/06
ML063050380
Person / Time
Site: Pilgrim
Issue date: 10/03/2006
From: Ford B
Entergy Corp
To: Williamson A
Office of Nuclear Reactor Regulation
References
%dam200612, TAC MD2296
Download: ML063050380 (5)


Text

Jý Alicia Williamson - Information from the Conference call on 9/26/06 Page i1 f~L~L4~

[

From:

"Ford, Bryan" <BFord@ ntergy.com>

To:

<arwl @ nrc.gov>

Date:

10/03/2006 10:44:21 A

Subject:

Information from the Conference call on 9/26/06 Please see the attached file that contains population dose risk (PDR) reduction in unit of % for each SAMA and for RAIs 5e, 5f, 5g, and 5h.

<<PDR reduction.doc>>

With 3 significant figures, the values for CDF, PDR, and OECR SAMAs 6 (equivalent to 18, and 20), 48, and 52 are as follows:

Original Submittal Re-analysis SAMA CDF PDR OECR CDF PDR 6,18,20 6.41 E-06 1.35E+01 1.46E+01 5.26E+04 48 6.41E-06 1.35E+01 4.59E 1.46E+01 5.26E+04 52 6.40E-06.

1.35E+01 4.59E 1.46E+01 5.26E+04 Base 6.41E-06 1.36E+01 4.59E 1.46E+01 5.26E+04 OECR 4.59E+04 6.41 E-06

-+04 6.41 E-06

~+04 6.40E-06 E+04 6.41 E-06 Small benefits could result from minor differences in CDF, PDF, or OECR.

For example, slight difference in PDR for SAMA 6 and Base results in a benefit of $2153 and an upper bound benefit of $12,915 with a multiplier of 6 in the original submittal. However, there is no such difference for the reanalysis. Therefore, the estimated benefit for SAMA 6 is $0.

Also, the Reduction in Off-site Economic Cost Risk (OECR) reduction for SAMA 27 on Table RAI.6-1should be 15.02% (same as RAI 5e) rather than 1.71%.

CC:

"Ellis, Douglas" <dellisl @entergy.com>, "Mogolesko, Fred" <fmogole@entergy.com>

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Information from the Conference call on 9/26/06 10/03/2006 10:43:11 AM "Ford, Bryan" <BFord@entergy.com>

BFord@entergy.com Recipients nrc.gov TWGWPO04.HQGWDOO1 ARWI (Alicia Williamson) entergy.com fmogole CC (Fred Mogolesko) dellisl CC (Douglas Ellis)

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  • Reduction in Population Dose Risk (PDR)

SAMA ID SAMA Description PDR Reduction 1

Install an independent method of suppression pool 4.79%

cooling.

2 Install a filtered containment vent to provide fission 18.49%

product scrubbing.

I3 Install a containment vent large enough to remove ATWS 1.37%

decay heat.

Create a large concrete crucible with heat removal 4

potential under the base mat to contain molten core 48.97%

debris.

5 Create a water-cooled rubble bed on the pedestal.

48.970/

6 Provide modification for flooding the drywell head.

0.00%

7 Enhance fire protection system and standby gas 1.37%

treatment system hardware and procedures.

8 Create a core melt source reduction system.

48.97%

9 Install a passive containment spray system.

4.79%

10 Strengthen primary and secondary containment.

26.03%

Increase the depth of the concrete basemat or use an 11 alternative concrete material to ensure melt-through does not occur 0.68%

12 Provide a reactor vessel exterior cooling system 0.00%

13 Construct a building to be connected to primary/

1.37%

secondary containment that is maintained at a vacuum 14 Dedicated Suppression Pool Cooling 4.79%

15 Create a larger volume in containment.

26.03%

16 Increase containment pressure capability (sufficient 26.03%

pressure to withstand severe accidents).

17 Install improved vacuum breakers (redundant valves in 0.00%

each line).

18 Increase the temperature margin for seals.

0.00%

19 Install a filtered vent 18.49%

20 Provide a method of drywell head flooding.

0.00%

21 Use alternate method of reactor building spray.

1.37%

22 Provide a means of flooding the rubble bed.

22.60%

Reduction in Population Dose Risk (PDR)

SAMA ID SAMA Description PDR (%)Ruction 23 Install a reactor cavity flooding system.

48.97%

24 Add ribbing to the containment shell.

26.03%

25 Provide additional DC battery capacity.

2.74%

26 Use fuel cells instead of lead-acid batteries.

2.74%

27 Modification for Improving DC Bus Reliability 16.44%

28 Provide 16-hour SBO injection.

2.74%

29 Provide an alternate pump power source.

5.48%

30 AC Bus Cross-Ties 8.22%

31 Add a dedicated DC power supply.

16.44%

32 Install additional batteries or divisions.

16.44%

33 Install fuel cells.

2.74%

34 DC Cross-Ties 2.05%

35 Extended SBO provisions.

2.74%

36 Locate RHR inside containment.

0.00%

37 Increase frequency of valve leak testing.

0.68%

38 Improve MSIV design.

0.00%

Install an independent diesel for the CST makeup pumps.

0.00%

Provide an additional high pressure injection pump with independent diesel.

2.05%

41 Install independent AC high pressure injection system.

2.05%

42 Install a passive high pressure system.

2.05%

43 Improved high pressure systems 1.37%

44 Install an additional active high pressure system.

2.05%

45 Add a diverse injection system.

2.05%

46 Increase SRV reseat reliability.

0.68%

47 Install an ATWS sized vent.

1.37%

Reduction in Population Dose Risk (PDR)

SAMA ID SAMA Description PDR Reduction 48 Diversify explosive valve operation.

0.00%

Increase the reliability of SRVs by adding signals to open them automatically.

0.68%

50 Improve SRV design.

3.42%

51 Provide self-cooled ECCS pump seals.

0.68%

52 Provide digital large break LOCA protection.

0.00%

Control containment venting within a narrow band of pressure 4.79%

Install a bypass switch to bypass the low reactor 54 pressure interlocks of LPCI or core spray injection valves.

0.68%

55 Improve SSW System and RBCCW pump recovery.

6.85%

56 Provide redundant DC power supplies to DTV valves.

3.42%

Proceduralize the use of diesel fire pump hydroturbine in the event of EDG A failure or unavailability.

3.42%

58 Proceduralize the operator action to feed B1 loads via B3 when A5 is unavailable post-trip.

3.42%

Provide redundant path from.fire protection pump discharge to LPCI loops A and B cross-tie.

17.12%

RAI 5e Equivalent to SAMA 27 16.44%

RAI 5f Firewater injection 4.11%

RAI 5g Reduntant diesel firewater pump 8.22%

RAI 5h Passive direct torus vent 14.38%