ML20249C512
| ML20249C512 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/19/1998 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20249C506 | List: |
| References | |
| NUDOCS 9806300208 | |
| Download: ML20249C512 (26) | |
Text
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I Exhibit D MNGP MSLBA Evaluation Summary The radiological evaluation of the Main Steam Line Break Accident (MSLBA) is described in USAR Section 14.7.3.
Assumptions 1
The postulated accident involves a guillotine break of one of the four main steam lines outside of
{
the containment, resulting in mass loss from both ends of the break. There is no fuel damage as a consequence of this event, therefore the only activity released to the environment is that associated with the steam and liquid discharged from the break. Initially only steam will issue
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from the broken end of the steam line. Subsequently, rapid depressurization due to the break I
causes the reactor pressure vessel water level to rise, resulting in a steam-water mixture flowing l
. from the break until the main steam isolation valves (MSIVs) are closed. For the MSIV closure time, an analysis input of 10Aseconds after the MSLBA is used. Activity associated with the discharged coolant is airborne in the turbine building instantaneously and released to the environment without delay.
1 The analysis assumes that the accident occurs at hot standby conditions. At these conditions, stearc. generation from the decay heat in the core is very low and cannot make up the steam loss through the break. The results are a high rate of vessel depressurization and rapid rising of water level to the main steam line inlet. In addition to hot standby conditions, the 10CFR50 Appendix K break flow model was assumed in order to maximize the two-phase break flow rate.
Both of these assumptions yielded the maximum coolant mass releases through the break.
l Two cases were analyzed. The first case assumes reactor pressure is at the safety relief valve opening setpoint of 1158 psia. The second case assumes the initial reactor pressure is at the
. pressure regulator setpoint of 965 psia. The results show that the mass leaving the reactor pressure vessel through the break is 71,574 lbm of liquid and 4,030 lbm of steam for the first case. 'In the second case the mass leaving the reactor pressure vessel thro Jgh the break is
' 66,223 lbm of liquid and 4,243 lbm of steam.
L Accident parameters relevant to the radiological analysis aia summarized in Table D-1. The -
atmospheric dispersion factors to the site boundary and to the control room intake, as well as
. control room parameters, are included in Table D-1_.
Noble Gas Concentration
- The assumed noble gas activity is the M' onticello Technical Specification limit which corresponds
- to an off-gas release rate of 0.26 Cl/sec (rounded to 0.3 Ci/sec in the USAR) at 30 minutes delay. This activity is assumed to consist of a standard isotopic fraction.
D-1
lodine Concentration The analysis used an input of 2 Ci/gm dose-equivalent of lodine-131 for the activity in the reactor coolant. A portion of the released coolant exists as steam prior to the accident.
Therefore, it is necessary to separate the initial steam mass from the total mass released and assign a certain percentage of the fission product activity contained in this portior of the steam by an equivalent mass of reactor coolant. A 2% carryover ratio was assumed for the analysis.
Offsite Dose and Control Room Dose Evaluations Activities released to the environment due to the MSLBA are calculated for both hot standby conditions. The case for reactor pressure at the safety relief valve opening setpoint and the case for reactor pressure at the pressure regulator setpoint. In addition, the analysis was performed for coolant concentrations based on both the TID-14844 and Regulatory Guide 1.109 thyroid dose conversion factors.
Offsite dose consequences are presented in Table D-3.
l Control room dose consequences are presented in Table D-4.
l l
D-2
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TABLE D-1 l
Assumptions for MNGP MSLBA Analysis I
PARAMETER VALUES l
Power Level Hot standby at 4% power (66.8 MWt)
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RPV Pressure (psia)
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Case 1 1158
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Case 2 965 Time Elapse for MSIV Full Closure (seconds) 10.5 Fuel Rod Damage 0
l Mass of Steam-Water Mixture Leaving Break (Ibm)
See Table D-2 Reactor Coolant Dose Equivalent 1-131 ( Ci/gm) 2 lodine Carryover Factor (%)
2 lodine Releases (pCi/cm )
For Total Release See Table D-2 j
TID-14844 l-131 0.77 l-132 3.38
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1-133 2.85 1
1-134 7.27 l-135 2.56 Reg. Guide 1.109 l-131 1.08 l-132 4.72 i
f 1-133 3.98 I-134 10.2 1-135 3.58 l
Thyroid Dose Conversion Factors (rem /Ci) l 1-131 1.08E+06
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1-132 6.44E+03 l-133 1.80E+05 l-134 1.07E+03 1-135 3.13E+04 D-3
TABLE D-1 (continued)
Assumptions for MNGP MSLBA Analysis PARAMETER VALUES Data for Control Room 3
Volume of Control Room (ft )
27,000 Filter intake (cfm),.
900 Efficiency of Charcoal adsorber (%)
98 Unfiltered inleakage (T < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) (cfm) 250 Unfiltered inleakage (T > 8 hourr 'cfm) 10 Occupancy Factor 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 1 - 4 days 0.6 4-30 days 0.4 l
Control Room Intake Atmospheric Dispersion Factors (sec/m )
3 Ground Level Release 0 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.67E-03 8 -24 hours 1.41E-03 1 - 4 days 9.65E-04 4 - 30 days 5.62E-04 3
Offsite Atmospheric Dispersion Factor (sec/ m )
Ground Level Release 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (EAB/LPZ) 9.20E-04/7.93E-05 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (LPZ) 7.93E-05 8 -24 hours 5.35E-05 1 - 4 days 2.28E-05 4 - 30 days 6.68E-06 1
I D-4
TABLE D-2 Mass Release From MSLBA (Ibm)
CASE 1 CASE 2 Total liquid released through break 71,574 66,223 Liquid released flashing to steam 10,548 8,151 Initial steam prior to steam line covered 4,030 4,243 i
lodine Release From MSLBA (Cl) l TID-14844 l
l-131 28.8 26.2 1-132 126 114 l
l-133 106 96.3
(
l-134 271 246 l-135 95.6 86.6
[
Reg. Guide 1.109 l-131 40.2 36.4 l
l-132 176 160 l
l-133 148 135 l-134 379 343 1-135 134 121 1
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TABLE D-3 MNGP MSLBA Offsite Dose (REM) l 2 - Hour Exclusion Area Boundary 30 Day Low Population Zone l
TID-14844 DCF Thyroid Whole Body Thyroid Whole Body Case 1 17.3 0.28 1.49 0.02 Case 2 15.7 0.26 1.35 0.02 I
Reg. Guide DCF Case 1 24.2 0.40 2.08 0.03 Case 2 21.9 0.36 1.89 0.03 l
l 10CFR100 300 25 300 25 I
TABLE D 4 l
MNGP MSLBA Control Room Dose (REM)
Thyroid Whole Body TfD DCF Case 1 7.26 0.003 Case 2 6.58 0.002 l
i Reg. Guide DCF Case 1 10.1 0.004 Case 2 9.18 0.003 GDC 19 30 5
l L
D-6 l
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L 0,
Exhibit E MNGP RWCU Evaluation Summary l
TABLE E-1 Inputs for MNGP RWCU Evaluation PARAMETER VALUES Time Elapse for Operator Action from Break initiation (Min.)
10 Time Elapse for RWCU Valve Closure (seconds) 29 l
Fuel Rod Damage 0
l Mass of Steam-Water Mixture Leaving Break (Ibm) 443,460 l
I Data for Control Room l'
Volume of Control Room (ft )
27,000
]
Filter intake (cfm) 900 Efficiency of Charcoal adsorber (%)
98 l
l Unfiltered Inteakage (cfm) 250 l
Control Room Intake Atmospheric Dispersion Factors 8
Ground Level Release (sec/m )
1.67E-03 l
Offsite Atmospheric Dispersion Factor Ground Level Release (sec/ m )
Exclusion Area Boundary 9.20E-04 Low Population Zone) 7.93E-05 I
)
Reactor Coolant Dose Equivalent 1-131 ( Ci/gm) 0.25 lodine Releases 3
Isotope Concentration ( Ci/cm )
Total Release (Ci)
Thyroid Dose Conversion Factors (rem /Cl) 1-131 0.135 27.2 1.10E+06 l-132 0.590 119 6.30E+03 l
L l-133 0.497 100 1.80E+05 I
l-134 1.27 255 1.10E+03 1-135 0.447 89.9 3.10E+04 E-1
TABLE E-2 MNGP RWCU Line Break Offsite Dose (REM) i 2-Hour Exclusion Area Boundary 30 Day Low Population Zone
{
Thyroid Whole Body Thyroid Whole Body j
Dose (REM) 16.5 1.66 X 10" 1.42 1,43 X 10" l
)
10CFR100 300 25 300 25 Guideline TABLE E-3 i
MNGP RWCU Line Break Control Room Dose (REM)
Thyroid Whole Body Dose (REM) 6.98 9.04 X 10'#
f GDC 19 Guideline 30 5
I j
1 l
l E-2
Exhibit F EFT System Commitment and ASME N510-1989 Testing Exception l
l Commitment Within 9 months of the date of the approval of this amendment, NSP will conduct an independent evaluation of the testing methodology and system testing configuration of the Emergency Filtration (EFT) system by HEPA and charcoal l
filter testing experts. All of the exceptions to the testing standards listed below j
l' will be evaluated. The results of this review will be reported to the staff.
l.
ASME N510-1989 Testing Exceptions 1.
Section 5.5.1 of ASME N510-1989 Section 5.5.1 of ASME N510-1989 provides guidance for visual inspection of the air treatment system.
NSP Exception 1
l NSP performs a visualinspection of applicable items from Section 5.5.1, NSP l
performs a visual inspection by procedure, but many of the standard's l
inspections items are not applicable to the Monticello EFT system. Examples of items that are not applicable to Monticello include: 1) dovetail type access j.
gaskets with a seating surface suitable for a knife edge seal, and 2) shaft seals.
l
?.
Section 6.2.2 and Table 1 of ASME N510-1989 L
Section 6.2.2 and Table 1 of ASME N510-1989 state that a housing leak test l.
shall be performed every 10 years.
NSPException This test is not performed at Monticello. The EFT system at Monticello was built j
to be tested to ANSI /ASME N510-1980 which does not require these tests to be performed periodically. No provisions were provided to accommodate this test.
The entire EFT housing is contained within the protective envelope supplied by
- the system, and any leakage into the housing would be filtered air. Periodic performance of a test that verifies the ability to maintain the control room envelope at a positive pressure is an adequate demonstration of system leak integrity.
F-1 i
L____.________.__________________
3.
Section 7.1 of ASME N510-1989 Section 7.1 of ASME N510-1989 recommends a mounting frame pressure leak test to verify the absence of leaks through seal welds of the HEPA filter and adsorber frames, and between the frames and housings be performed.
NSP Exception This test is not performed at Monticello. Leaks of this nature are detected by the visual inspection test or the in-place filter test, and credit is taken for these tests as allowed by the standard.
4.
Section 8.5.1.4 of ASME N510-1989 Section 8.5.1.4 of ASME N510-1989 requires that a housing component pressure drop airflow test be performed which requires that maximum pressure drops across each of the components be simulated. The unit is run at this maximum l
pressure drop across the system, and adequate airflow is ensured.
NSP Exception l
This test is not performed at Monticello. The EFT system was designed to be tested to the ANSI /ASME N510-1980 standard which does not require that this test be performed periodically. The system at Monticello contains a low flow trip.
If airflow is too low through the system due to debris loading of the filters, the running train will automatically trip, and the standby train will start.
5.
Section 8.5.2.2 of ASME N510-1989 Section 8.5.2.2 of ASME N510-1989 requires a periodic airflow distribution test-through the adsorber banks.
NSP Exception This test is not performed at Monticello. Monticello's EFT system was designed to be tested to the ANSI /ASME N510-1980 standard which does not require this test be performed periodically. No provisions were made in the design of the Monticello EFT to perform this test periodically.
6.
Section 10.3 of ASME N510-1989 Section 10.3 of ASME N510-1989 states that sample points for DOP sampling shall be downstream of a fan, or downstream sample manifolds shall be qualified per ASME N509.
NSP Exception At Monticello, the downstream sampling is performed upstream of the fan using a single injection point. No shaft seals are installed on the system's fans, therefore F-2
L o
l i
sampling downstream of the fan would obtain a diluted air sample. Section 10.3 of the ANSI /ASME N510-1980 standard, which the EFT System was originally
)
l designed to, does not require the use of a sampling manifold. No provisions l
were made in the design of the Monticello EFT for sampling manifolds.
1 7.
Section 10.5.8 of ASME N510-1989 Section 10.5.8 of ASME N510-1989 states that upstream and downstream DOP concentrations are repeated until readings within +/- 5 % of respective previous readings are obtained. The final set of readings is then used to calculate penetration.
i NSP Exception At Monticello, the readings are taken until the concentrations are within +/- 10%,
and the highest penetration reading is conservatively used with a minimum of three readings tr. ken. Because of the injection point location for the Monticello EFT system, it is difficult to consistently achieve +/- 5% between readings.
' 8.
Section 11.3 of ASME N510-1989 Section 11.3 of ASME N510-1989 states that sample points for halide challenge gas shall be downstream of a fan or downstream sample manifolds shall be qualified per ASME N509.
NSP Exception See item 6 above.
9.
Section 11,4 of ASME N510-1989 l
Section 11.4 of ASME N510-1989 states that R-11 is the preferred test gas with R-117. or R-112A as acceptable altematives.
NSP Exception NSP reserves the ability to use alternate test gases that are found to be l
l acceptable alternatives by the industry. Monticello currently employs R-11 as the test gas; however, environmental concems regarding the use of such halide gases may result in use of these gases not being feasible in the future.
10.
Section 11.5.8 of ASME N510-1989 I
Section 11.5.8 of ASME N510-1989 states that when a housing contains more than one bank of adsorbers in series, the halide gas test shall be repeated for each bank.
I F-3
NSP Exception At Monticello, the two adsorber banks are tested as a single unit. This i
i requirement was not present in ANSI /ASME N510-1980, which the EFT System was designed to, and a qualified injection manifold between the two banks was not provided.
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