ML20082F444
| ML20082F444 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/03/1995 |
| From: | Terry C NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMP2L-1537, NUDOCS 9504120124 | |
| Download: ML20082F444 (8) | |
Text
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MV NIAGARA n UMOHAWK
' ' anAGARA 000 HAWK POWER 00RPORATIOWNINE MILE PolNT NUCLEAR STATION, P.O. BOX 63. LYCOMiNG. N.Y.13093 /TEL (315) 349 7263 FAX (315) 349-4753 EE"#
April 3,.1995 N a h r Er $ m e s NMP2L 1537 U. S. Nuclear Regulatory Commission
-- Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 2
.l Docket No. 50-410 NPF-69
Subject:
Pmposed Ilcense Amendment - Inenased MSIV Leakage, Response to Requestfor AdditionalInfonnation i
Gentlemen:
In a letter to the Nuclear Regulatory Commission (NRC) dated December 13,1994 (NMP2L 1515), Niagara Mohawk Power Corporation (NMPC) proposed a license amendment to allow Nine Mile Point Unit 2 (NMP2) to increase the maximum allowable MSIV leakage from 6.0 to 24.0 scfh..During the course of the Staff's review of this proposed license amendment, the NRC has determined that additional information as identified in its letter to NMPC dated March 23,1995, is required to complete its review of this matter. Attached to this letter is the requested additionalinformation.
Niagara Mohawk has provided a copy of this response to the appropriate state representative.
l Very truly yours,
[
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C. D. Terry Vice President - Nuclear Engineering D T/KWK/kab
' Attachment I
120016 0
-9504120124 950403 PDR ADOCK 05000410 p.
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Regional Administrator, Region I Mr. B. S. Norris, Senior Resident Inspector i
Mr. L.- B. Marsh, Director, Project Directorate I-1, NRR:
Mr. G. E. Edison, Senior Project Manager, NRR Ms. Donna Ross Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 Records Management a
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4 ATTACIBENT Reauest for AdditionalInformation 81auest 450.01:
Provide thefollowing information which will allow the staf to calculate ofsite dosesfrom increased AfSIV leakage (a drawing may be helpfid):
a.
biain steam line (AfSL) inside and outside pipe diameters b.
AfSL pipe length between the AfSIV and the drain line c.
AfSL pipe material d.
AfSL initial and ambient temperatures e.
Drain line inside and outside pipe diameters f
Drain line pipe length to the drain header g.
Drain line pipe material h.
Drain line header inside and outside diameters i.
Drain line header length to common drain line to condenser J.
Drain line header material k.
Drain line initial and ambient temperatures I.
Common drain line length to the condenser m.
Condenser total volume n.
Condenser air space volume o.
Condenser hotwell (liquid) volume p.
Condenser temperature q.
Type of material used to insulate the main steam and drain lines r.
Thickness ofinsulating material used on the main steam and drain lines Responsel a.
Main steam line (MSL) inside and outside pipe diameters - see Figure 1.
b.
MSL pipe length between the MSIV and the drain line - see Figure 2.
c.
MSL pipe material - see Figure 1.
d.
MSL initial temperature is 551 F. The ambient temperature is 286*F inside the drywell and 104 inside the reactor building.
e.
Drain line inside and outside pipe diameters - see Table 1.
f.
Drain line pipe length to the drain header - see Figure 2.
g.
Drain line pipe material - see Table 1.
h.
Drain line header inside and outside diameters - see Table 1.
i.
Drain line header length to common drain line to condenser - see Figure 2.
j.
Drain line header material - see Table 1.
k.
Drain line initial temperature is 551*F. The ambient temperature is 286 F inside the drywell and 104 F inside the reactor building.
1.
Common drain line length to the condenser - see Figure 2.
m.
Condenser total volume is 123,000 ft'.
n.
Condenser air space volume is 97,000 ft'.
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Condenser hotwell (liquid) volume is 160,200 gallons.-
p.
, Condenser temperature is 100*F.
-;q. -
Type of material used to insulate the main steam and drain lines is fiberglass.
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Thickness ofinsulating material used on the 26 inch and 28 inch main steam lines is 4 inches. : See Table 1 for thickness of insulating material on the main steam drain lines.
Request 450.02 Pmvide thefollowing irgformation which will allow the stqito calculate control room
. operator doses from increased MSIV leakage:
a.
Control momfree volume (cubicp) bi Emergency makeup air intakes (cfm) c.
Url filtered inleakage (cfm) d.
Recirculationflow rate (cfm) e.
Charcoal adsorber thickness in inches f.
Adsorber eficiency (%)
Resoonse:
a.
Control room free volume is 3.81E+05 ft'.
b.
Emergency makeup air intakes is 1500 cfm.
c.
Unfiltered inleakage is O cfm based on Updated Safety Analysis Report Section -
6.4.2.3.
d.
Recirculation flow rate is 750 cfm.
c.
Charcoal adsorber minimum thickness is 4 inches.
f.
Adsorber efficiency is 99%.
1 Request.450.03:
l Justify the reduced Traversing Incore Probe (TIP) System leakage' value of 0.11 La.
Describe the methodology and assumptions used to recalculate the frictional loss through an unisolated TIP System primary containment penetration.
l
Response
l The drywell flow rate through the TIP System lines is calculated based on critical L
flow through an adiabatic duct 'with friction fed by an isentropic converging nozzle.
l This approach results in the largest possible flow.
The leak rate through the TIP tubes is conservatively calculated using a peak drywell L
pressure of 45 psig which is the design pressure of the primary containment. The L
maximum calculated pressure inside primary containment during a design basis - loss
[
of coolant accident is 36.8 psig for the power uprate condition [see Table 4-1 of -
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- 1. Enclosure 3 to NMPC's letter to the Staff dated July 22,1993 (NMPL 1397)]. The.
drywell is assumed to be filled with steam for the entire duration of the accident..
1 Steam flow is about 20% higher than volumetric air flow.
The reduced TIP System l'eakage _value of 0.11 La has been calculated by removing the following conservatisms from the original calculation:
l.-
- The drywell volume was 7% conservative.
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The friction factor.was about 1/3 of actual value.
Elimination of these conservatisms results in a significant reduction in the TIP System Leakage from _0.19 La to 0.11 La.
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TABLE 1 Insulation Thickness Line No.
~ Material OD (inches)
ID (inches).
(r, inches)-
2-MSS-006-18-4 A1%, Gr B 6.625 5.761 3
2 MSS-006-21-4 Al%, Gr B 6.625 5.761 3
2-MSS-006-12-4 A106, Gr B 6.625 5.761 3
2-MSS-006-117-4 A106, Gr B 6.625 5.761 3
2-MSS-002-16-4 A106, Gr B 2.375 1.687 2
2-MSS-002-13-4 A106, Gr B 2.375 1.687 2
2-MSS-002-22-4 A106, Gr B 2.375 1.687 2
2-MSS-002-19-4 A106, Gr B 2.375 1.687 2
2-MSS-002-177-4 A335, P2'2 2.375 1.687 1.5 2-MSS-002-178-4 A335, P22 2.375 1.687 1.5 2-MSS-002-180-4 A335, P22 2.375 1.687 1.5 2-MSS-002-181-4 A335, P22 2.375 1.687 1.5 2-MSS-002-182-4 A335, P22 2.375 1.687 1.5 2-MSS-002-179-4 A335, P22 2.375 1.687 1.5 2-MSS-002-176-4 A335, P22 2.375 1.687 1.5 l
2-MSS-002-173-4 A335, P22 2.375 1.687 1.5 2-MSS-002-188-4 A335, P22 2.375 1.687 1.5 2 MSS-002-187-4 A335, P22 2.375 1.687 1.5 2-MSS-002-184-4 A335, P22 2.375 1.687 1.5 2-MSS-002-183-4 A335, P22 2.375 1.687 1.5 4
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