Text

Forwards Summary Technical Rept of Containment Integrated Leak Rate Test Performed During 1986 Refueling Outage,Per 10CFR50,App J.Next Type a Test Will Be Performed at Normal Frequency of 40 +/- 10 Months.Approval Requested
	ML20211H005
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/31/1986
From:	Withers B; PORTLAND GENERAL ELECTRIC CO.
To:	Varga S; Office of Nuclear Reactor Regulation
References
	NUDOCS 8611040361
	Download: ML20211H005 (26)
	v • d • e

_ _ _ _ _ _ _ _ _ _ _ _

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But D. Wthers Vre Presoxt October 31, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:

Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

Reactor Containment Building Integrated Leak Rate Test Attached is the summary technical report of the containment integrated leak rate test (ILRT) performed during the 1986 refueling outage. This report is being submitted pursuant to 10 CFR 50, Appendix J.

Prior to the performance cf the ILRT, local leak rate testing was performed on the individual Containment penetrations. During this testing, Penetra-tion P-57-2, chilled water return line, was found to have excessive leakage.

The leakage exceeded the measurement capability of the test instrumentation.

This event was described in Licenseo Event Report 86-05.

The defective valves were replaced prior to performance of the ILRT.

In accordance with guidance provided in IE Information Notice 85-71, the leakage found and repaired during local leak rate testing must be added to the ILRT Icakage total when the two tests are performed during the same In this case, since the leak rate through Penetra-refueling outage.

tion P-57-2 was not measurable, it has conservatively been concluded the "as-found" integrated leak rate exceeded the Technical Specification limit.

I ol1 8

l 8611040361 861031 DR ADOCK 05000344 p

PDR R1'& Smen Em t rwun1 own 9mu

N M MC0rTV)E!rly s

Mr. Steven A. Varga October 31, 1986

- Page 2 In accordance with Technical Specification 4.6.1.2.b, failure of an ILRT (Type A test) requires the schedule for subsequent tests to be reviewed and approved by the NRC.

Since the chilled water valves have been replaced with new valves of a proven design, we propose to perform the next Type A test at its normal frequency of 40 i 10 months. We request your approval of this schedule.

Sincerely, f'

Bart es Vice President Nuclear Attachment c:

Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy

'l l

D l

q Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 1 of 24

)

TROJAN NUCLEAR PLANT REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST l

l The 1986 Integrated Leak Rate Test (ILRT) for the Trojan Nuclear Plant was successfully conducted during May 27-30, 1986. This was the third test of the set and was conducted during the 10-year inservice inspection as required by Technical Specification 4.6.1.2.a.

The actual test was conducted for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months as required by ANSI N45.4-1972,-

Leakage Rate Testing of Containment Structures for Nuclear Reactors, and the total time measured leak rate (LAM-TT) was less than the maximum allowed leakage of 0.75La.

A set of appendices follows the summary report. Appendices 1-9 display graphs and tables of various aspects of the test. Appendices 10-15 are l

supplemental reports required by 10 CFR 50, Appendix J.

4 A summary report'of the ILRT is as follows:

1.

1986 Type A Test Results The acceptance criteria for the test is:

i LAN-TT (Overall) 1 0.0750 %/ day 1 149,844 sec/ min s 5.2920 scfm "As Found" LAM-TT (Overall)

> 0.0750 %/ day

> 149,844 sec/ min i

> 5.2920 scfm l

"As Left" LAM-TT (Overall)

= 0.01703 %/ day

= 34,023 sec/ min 1

= 1.2016 scfm i

NOTE:

The "As Found" LAM-TT (Overall) failed the acceptance l

criteria of Technical Specification 3.6.1.2 since the I

. leakage rate through chilled water Penetration P-57-2 isolation valves could not be quantified during Type C testing performed before the Type A test was performed.

This determination was made based on guidance in IE Information Notice 85-71.

The compiled data for the test is listed in Appendix 8 and is graphed in Appendix 1.

i

O Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 2 of 24 2.

1986 Total Type B Test Results "As Found" Type B Leakage

= 7.84E-5 %/ day

= 156.7 sec/ min

= 0.006 scfm "As Left" Type B Leakage

= 7.84E-5 %/ day

= 156.7.sec/ min

= 0.006 scfm 3.

1986 Type C Test Results "As Found" Type C Leakage

> 0.060 %/ day

> 119,875 sec/ min

> 4.234 scfm "As'Left" Type C Leakage

= 0.004 %/ day

= 8554.5 sec/ min

= 0.302 scfm NOTE: While conducting the initial Type C test on the chill water penetration, P-57-2, neither valve (MO-10013 nor CV-10014) would adequately seal to allow test pressure to reach the required 60 psig.

4.

1986 Type A Test Analysis The measured Containment leakage, calculated by the Total Time method, was corroborated by the Mass Point method. Both methods clearly indicate the measured Containment leakage was well below the l

maximum allowed leakage. The Type A test results, however, failed to meet the acceptance criteria after adding the Type C leakage from i

both the inside and outside Containment isolation valves on the chill l

water outlet penetration, P-57-2.

The valve leakage was due to the j

rubber seating material separating from the valve body. This problem was reported in Licensee Event Report 86-05.

The chill water valves were blank flanged during the Type A test and I

were replaced after the test. The new valves were then Type C tested and the measured leakage was added to the measured Containment leakage to obtain the "as left" leakage.

There were five penetrations which were not Type A tested on May 28-29, 1986. These penetrations were Type C tested later and the leakage added to the Type A results. These penetrations were:

a.

P-57-1 Chilled Water Inlet Penetration As Left Penetration Leakage = 11 sec/ min

s Trojan Nuclear Plant Mr. Steven A. Yarga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 3 of 24 b.

P-57-2 Chilled Water Outlet Penetration As Left Penetration Leakage = 11 sec/ min c.

P-37-3 ILRT Verification Test Penetration As Left Penetration Leakage = 6 sec/ min d.

P-39-3 ILRT Pressure Measurement Penetration As Left Penetration Leakage = 24 sec/ min e.

P-75 ILRT Pressurization Penetration As Left Penetration Leakage = 6 sec/ min Leakage added to the ILRT

= 58 sec/ min

= 3E-5 %/ day LAN-TT (measured leakage)

= 33,965 sec/ min

= 0.017 %/ day Therefore, the summation is:

"As Left" LAM-TT (overall)

= 34,023 sec/ min

= 0.01703 %/ day Penetrations P-75, P-37-3 and P-39-3 are in use during the ILRT and thus must be tested afterwards.

Penetrations P-57-1 and P-57-2 were modified after the ILRT and the "As Left" condition was determined using a Type C test, as described above.

5.

The following is a description of the Appendices attached to the report:

Appendix 1: Total Time Leak Rate The test commenced at 5.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months and concluded at 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Techni-cal Specification 3.6.1.2 requires the overall leak rate to be less than 0.75La.

The total time measured leak rate (LAM-TT), using the Total Time method described in ANSI N45.4-72, is less than the maxi-mum allowed leak rate. As can be seen on the graph, the total time upper confidence level (UCL-TT) did not decrease below La and there-i fore the test had to be continued for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A 24-hour test does not require an upper confidence limit calculation.

Appendix 2: Mass Point Leak Rate The Mass Point calculation method was used to corroborate the Total Time calculations. The Mass Point leak rate (LAN-MP) does validate the Total Time leak rate displayed in Appendix 1.

l o

1 Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 4 of 24 Appendix 3: Verification Test The verification test commenced et 31.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months and concluded at 35.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months . The calculated verification leak rate (Lc) was within the acceptance region at the end of the required 4-hour verification test period. Lo is the induced leakage through the calibrated orifice.

Appendix 4:

Containment Air Mass (large scale)

The Containment was vented for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months to 3.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months 1

to prevent pressure from exceeding the administrative limit of 60.5 psig due to an increasing Containment temperature.

Appendix 5: Containment Air Mass (Small Scale)

The scale for air mass has been reduced to display only the testing portion of the evolution.

Appendix 6: Containment Pressure (Weighted Averame)

Average pressure drops sharply during the venting process. The slow pressure increase is due to the rising air temperature, as shown on Appendix 7.

Appendix 7:

Containment Temperature vs Time l

The air temperature increase is attributed to the RCS acting as a l

heat source. The RCS temperature was ~ 100*F.

l Appendix 8:

24 Hour Test Data I

The test began at 1700 on May 28, 1986 (data set #24) and was com-pleted satisfactorily at 1700 on May 29, 1986 (data set #120). The Total Time leak rate (TTM CALC. LR) at data set #120 was 0.017%/ day.

The Mass Point leak rate (MASS PT. LEAKRATE), was 0.009 %/ day.

Because the Total Tima upper confidence level (TTM UCL LR) never fell below 0.10 %/ day, the test was continued for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The duration of the test could have been shortened if the Total Time upper confi-dence level had fallen below 0.10 %/ day.

Appendix 9: Verification Test Data The verification test began at 1830 on May 29, 1986 (data set #126) and was completed satisfactorily at 2230 on May 29, 1986 (data set l

142).

The verification leak rate (TTM CALC. LR) of 0.127 %/ day was within the acceptance band at the end of the 4-hour test.

l

= _ _ _

4 Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 5 of 24 Appendix 10: Containment Modifications containment boundary modifications which were completed subsequent to the 1983 ILRT are described. The post-modification leak rate of each component is also provided.

Appendix 11: Containment Inspection Results of the Containment visual inspections are described.

Appendix 12: 1985 Type B and C Leak Rate Testing Summary The 1985 Type B and C leak rate test results are summarized.

Appendix 13:

1984 Type B and C Leak Rate Testing Summary The 1984 Type B and C leak rate test results are summarized.

Appendix 14: Type B and C Leak Rate Test Failure Report Types B and C leak rate test failures which' occurred in 1984, 1985, and 1986 are described.

Appendix 15: Verification Test Summary The verification test which validated the ILRT is summarized.

l 4

l l

TIM Calettlated (.) and UCL (o) Leaktates (X/ day) vs.ElapsedTime

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MassPt.Leakrate()&llCLLeakrate(o)(x/ day) vs.ElapsedTine

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Verification Test pgg aww

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%s Elapsedfine(hours)

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Appendix 3.

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AirMass(lbs) vs Elapsed Tine

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Appendix 4.

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Appendix 5.

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Wei 76.000-ghted Average Pressure (psia) vs.ElapsedTine

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Appendix 7.

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J Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF Attachment Page 13 of 24 APPENDIX 8 24-Hour Test Data ILRT TREND REPORT Data Clock TTM TTM TTM Mass Pt Mass Pt Set Time Measured Calc. LR UCL LR LEAK RATE UCL LR

(%/ Day)

%/ Day)

(%/ Day)

(%/ Day) 24 17:00 0.000 0.000 0.000 0.000 0.000 25 17:15

-0.470 0.000 0.000

-0.470 0.000 4

26 17:30 0.164 0.000 0.000 0.164 2.475.

27 17:45 0.056 0.180 3.113 0.131 0.612 28 18:00

-0.024 0.116 1.524 0.045 0.297 4

29 18:15

-0.055 0.063 1.043

-0.012 0.153 30 18:30

-0.076 0.021 0.795

-0.050 0.069 31 18:45 0.010 0.035 0.670

-0.018 0.075 32 19:00 0.002 0.039 0.587

-0.005 0.066 33 19:15

-0.024 0.031 0.521

-0.011 0.045

-34 19:30

-0.005 0.031 0.475

-0.006 0.039 35 19:45 0.016 0.037 0.445 0.005 0.044 36 20:00 0.004 0.038 0.417 0.008 0.041 37 20:15 0.049 0.051 0.405 0.026 0.060 38 20:30 0.045 0.059 0.392 0.037 0.069 39 20:45 0.017 0.058 0.376 0.036 0.063 40 21:00 0.051 0.065 0.367 0.045 0.071 41 21:15 0.006 0.061 0.352 0.038 0.062 42 21:30 0.045 0.065 0.344 0.044 0.065 43 21:45 0.015 0.062 0.333 0.039 0.059 44 22:00 0.030 0.063 0.324 0.040 0.058 45 22:15 0.019 0.061 0.315 0.038 0.054 I

46 22:30 0.043 0.063 0.309 0.041 0.057 47 22:45 0.038 0.065 0.304 0.043 0.057 48

-23:00 0.049 0.067 0.300 0.047 0.060 49 23:15 0.054 0.070 0.297 0.051 0.064

.50 23:30 0.032 0.069 0.291 0.049 0.062 51 23:45 0.022 0.067 0.284 0.046 0.058 52 00:00 0.045 0.069 0.281 0.048 0.059 53 00:15 0.028 0.067 0.275 0.046 0.057 54 00:30 0.024 0.066 0.270 0.044 0.054 55 00:45 0.033 0.065 0.266 0.043 0.053 56 01:00 0.062 0.068 0.265 0.048 0.058 57 01:15 0.016 0.065 0.260 0.044 0.054 58 01:30 0.019 0.063 0.255 0.041 0.051 59.

01:45

-0.003 0.059 0.248 0.035 0.046 60 02:00 0.023 0.058 0.244 0.034 0.044 i

i

. =.. -. -,., -.,, - -. -

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 14 of 24 APPENDIX 8 Data Clock TTM TTM TTM Mass Pt Mass Pt Set Time Measured Calc. LR UCL LR LEAK RATE UCL LR

(%/ Day)

%/ Day)

(%/ Day)

(%/ Day) i 61 02:15 0.009 0.055 0.239 0.031 0.041 62 02:30 0.010 0.053 0.235 0.028 0.038 63 02:45 0.012 0.051 0.231 0.026 0.036 64 03:00 0.012 0.049 0.227 0.024 0.034 65 03:15 0.025 0.048 0.224 0.025 0.034 66 03:30 0.007 0.046 0.220 0.022 0.031 67 03:45 0.011 0.045 0.216 0.021 0.030 68 04:00 0.027-0.044 0.214 0.022 0.030 69 04:15 0.013 0.044 0.211 0.021 0.029 70 04:30 0.008 0.042 0.207 0.019 0.027 71 04:45

-0.001' O.040 0.203' O.017 0.024 72 05:00 0.031 0.040 0.202 0.018 0.026 73 05:15 0.006 0.039 0.199 0.016 0.024 j

74 05:30-0.011 0.038 0.196 0.016 0.023 75 105:45 0.000 0.036 0.193 0.014 0.021 76 06:00 0.010 0.035 0.190 0.013 0.020 77 06:15 0.002 0.033 0.187 0.012 0.018 78 06:30 0.015 0.033 0.185 0.012 0.018 79 06:45

-0.006 0.031 0.182 0.009 0.016 80 07:00 0.011 0.030 0.180 0.009 0.016 81 07:15 0.011-0.029 0.178 0.009 0.015 82 07:30 0.009 0.029 0.176 0.009 0.015 83 07:45 0.004 0.028 0.174 0.008 0.014 84 08:00 0.012 0.027 0.172 0.008 0.014 85 08:15

-0.007 0.026 0.169 0.006 0.012 86-08:30 0.005 0.025 0.167 0.006 0.011 87.

08:45 0.003 0.024 0.165 0.005 0.010' 88 09:00 0.031 0.025 0.165

'O.007 0.013 89 09:15 0.008 0.024 0.163 0.007 0.012 90 09:30 0.003 0.023 0.161 0.006-0.011 91 09:45 0.004 0.023 0.159 0.006 0.011 92 10:00 0.003 0.022 0.157' O.005 0.010 93 10:15 0.005 0.021 0.156 0.005 0.010 94 10:30 0.006 0.021 0.154 0.004

,0.009 95 10:45 0.005 0.020 0.153 0.004 0.009 96 11:00-0.004 0.020 0.151 0.004-0.008 97 11:15 0.006 0.019 0.150 0.004 0.008 98 11:30 0.008 0.019 0.148 0.004 0.008 99~

11:45 0.009 0.019 0.147 0.004 0.008 100 12:00 0.010 0.018 0.146 0.004 0.008 101

~12:15 0.013 0.018 0.145 0.004 0.008 102 12:30 0.011 0.018 0.144 0.004 0.008

- _ _ ~

=

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 15 of 24 APPENDIX 8 Data Clock TTM' TTM TTM Mass Pt Mass Pt Set Time Measured Calc. LR UCL LR LEAK RATE UCL LR

(%/ Day)

%/ Day)

(%/ Day)

(%/ Day) j-103 12:45 0.008 0.018 0.143 0.004 0.008 104 13:00 0.005 0.017 0.142 0.004 0.008

.105 13:15 0.013 0.017 0.141 0.004 0.008 106-13:30 0.005 0.017 0.140 0.004 0.008 101-13:45 0.011 0.017 0.139 0.004 0.008 108 14:00 0.011 0.017 0.138 0.005 0.008 I

109 14:15 0.017 0.017, 0.137 0.005 0.009 110 14:30 0.009 0.017 0.136 0.005 0.009 111 14:45 0.008 0.017 0.135 0.005 0.008 112 15:00.

0.007 0.016 0.134 0.005 0.008 113 15:15 0.014 0.016 0.134 0.005 0.009 114 15:30 0.009 0.016 0.133 0.006 0.009 115 15:45 0.017 0.016

-0.132 0.006 0.009 116 16:00 0.013 0.016 0.131 0.006 0.009

-117 16:15 0.017 0.016 0.131 0.007 0.010 l

118 16:30 0.016 0.017-0.130 0.007 0.010 l

119 16:45 0.024 0.017 0.130 0.008 0.011 l

120 17:00 0.021 0.017 0.130 0.009 0.012 l

-121 17:15 0.015 0.017 0.129 0.009 0.012 l

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 16 of 24 APPENDIX 9 Verification Test Data ILRT TREND REPORT Data Clock TTM TTM TTM Mass Pt Mass Pt Set Time Measured Calc. LR UCL LR LEAK RATE UCL LR

(%/ Day)

%/ Day)

(%/ Day)

(%/ Day) 126 18:30 0.000 0.000 0.000 0.000 0.000 127 18:45

-0.228 0.000 0.000

-0.228 0.000 128 19:00 0.091 0.000 0.000 0.091 1.252 129 19:15 0.073 0.129 1.460 0.107 0.349 130 19:30 0.089 0.146 0.759 0.116 0.229 131 19:45 0.130 0.174 0.590 0.144 0.219 132 20:00 0.095 0.167 0.525 0.130 0.183 133 20:15 0.061 0.144 0.477 0.102 0.151 134 20:30 0.097 0.144 0.438 0.105 0.142 135 20:45.

0.122 0.152 0.416 0.118 0.151 136 21:00 0.108 0.152 0.395 0.119 0.145 137 21:15 0.108 0.151 0.379 0.119 0.141 138 21:30 0.064 0.137 0.359 0.102 0.127 139 21:45 0.104 0.137 0.347 0.104 0.126 140 22:00 0.066 0.127 0.331 0.093 0.115 141 22:15 0.095 0.126 0.320 0.094 0.114 142 22:30 0.102 0.127 0.312 0.097 0.115 143 22:45 0.081 0.122 0.302 0.093 0.109

... ~.,

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 17 of 24 APPENDIX 10 Pursuant to 10 CFR 50, Appendix J, Section IV.A. the following modifica-tions to the Trojan Containment, completed subsequent to the 1983 Integrated Leak Rate Test, are listed below. Following each valve is the leakage measured after the installation was complete.

1. Chill Water Supply Valves: Penetration P-57-1 MO-10016 6 sec/ min CV-10015 11 sec/ min These valves were replaced by RDC 82-045, completed in June 1986.

2. Chill Water Return Valves: Penetration P-57-2 MO-10013 6 sec/ min CV-10014 11 sec/ min l

These valves were replaced by RDC 82-045, completed in June -1986.

3. Radioactive Gaseous Waste: Penetration P-54 l

CV-4301 21 sec/ min l

This valve was modified by RDC 84-011, completed in July 1986.

4. Hydrogen Vent Supply Valves: Penetrations P-101-1, P-101-2 MO-10005 6 sec/ min MO-10007

-26 sec/ min l

MO-10006 6 sec/ min MO-10008

.26 sec/ min These valves were replaced by RDC 81-106, completed in 1984.

5. Hydrogen Vent Exhaust Valves: Penetrations P-68, P-72 MO-10009 0 sec/ min MO-10011 36 sec/ min MO-10010 36 sec/ min MO-10012 11 sec/ min These valves were replaced by RDC 81-106, completed in 1984.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October.31, 1986 License NPF-1 Attachment Page 18 of 24 6.

Pressurizer Steam Sample Valve: Penetration P-1-1 CV-5659 11 sec/ min This valve was modified by RDC 79-040, completed in 1984.

7.

Reactor Coolant Drain Tank Sample: Penetration P-14-1

.CV-5661 6 sec/ min This valve was modified by RDC 79-040, completed in 1984.

8.

Accumulator Fample Valve: Penetration P-14-2 CV-5652 6 sec/ min This valve was modified by RDC 79-040, completed in 1984.

9.

Reactor Coolant Hot Leg Sample: Penetration P-14-3 l

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l CV-5655 1156 sec/ min i

i This valve was modified by RDC 79-040, completed in 1984.

l 10.

In-Core Thermocouples (Electrical Penetrations)

E-160 (AZ-08) 6 sec/ min E-168 (BZ-08) 6 sec/ min These electrical penetrations were modified by RDC 84-040, completed in June 1986.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 19 of 24 APPENDIX 11 Inspection results of the Reactor Containment Building are provided pursuant to 10 CFR 50, Appendix J, Section V.A.

1.

The Containment liner plate was inspected before and after the ILRT, as required by Technical Specification 4.6.1.6.3 and there was no evidence of structural deterioration.

2.

End anchorages and adjacent concrete surfaces were inspected before the ILRT and while at maximum test pressure during the ILRT, as required by Technical Specification 4.6.1.6.2 and there was no evidence of structural deterioration.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 20 of 24 APPENDIX 12 The following summary report of the 1985 Type B and C leak rate tests is provided in accordance with 10 CFR 50, Appendix J, Section V.B.3.

Summary Analysis of the 1985 Type B and C Leak Rate Tests 122 sec/ min Type B Leakage

=

6E-5 %/ day

=

7,572 sec/ min Type C Leakage

=

4E-4 %/ day

=

7,694 sec/ min Total Leakage

=

0.004 %/ day

=

Maximum Allowed Leakage = 119,875 sec/ min 0.06 %/ day

=

The summation of "as left" leakage from all penetrations was less than the maximum allowed leakage specified by Technical Specification 3.6.1.2, and the "as left" leakage from each penetration was acceptable.

During the local leak rate testing, Penetration P-50, the "B" train recirculation sump suction line, failed due to a 1/2-in circumferential crack at the base of the test connection pipe. The failure was attributed to fatigue and the test connection line was replaced. The penetration

.was then retested satisfactorily.

The final results of the 1985 local leak rate test (Type B and C tests) demonstrated the integrity of the containment boundary.

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4 Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1

' Attachment Page 21 of 24 APPENDIX 13 The following summary report of the 1984 Type B and C leak rate tests is provided in accordance with 10 CFR 50, Appendix J, Section V.B.3.

Sumary Analysis of the 1984 Type B and C Leak Rate Tests 680 ccc/ min Type B Leakage

=

3E-4 %/ day

=

14,411 sec/ min Type C Leakage

=

0.007 %/ day

=

15,091 sec/ min Total Leakage

=

0.008 %/ day

=

Maximum Allowed Leakage- = 119,875 sec/ min 0.06 %/ day

=

The summation of "as left" leakage from all penetrations was less than the maximum allowed leakage specified by Technical Specification 3.6.1.2, and the leakage from each penetration was acceptable.

The 1984 local leak rate ~ test (Type B and C tests) demonstrated the integrity of the containment boundary was maintained.

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o Trojan Nuclear Plant Mr. Steven A. Varga l

Docket 50-344 October 31, 1986 1

License NPF-1 Attachment Page 22 of 24 APPgNDIX 14 l

The following failures of Type B or C tests conducted in years 1984,

.1985, and 1986, is provided in accordance with 10 CFR 50, Appendix J, Section V.B.3.

1984 Type B or C Test Failures There were no Type B or C leak rate test failures in 1984.

1985 Type B or C Test-Failures Penetration P Test Connection Weld Failure On June 1, 1985, LLRT was conducted on Penetration P-50, "B" Train recirculation sump suction line. The penetration could not be pressurized due to a through-wall crack in a weld at the base of the test connections for the penetration. The "as found" leakage rate could not be determined.

Analysis:

The failure was determined to be a cyclic fatigue failure. The test connection pipe was replaced and the penetration was retested satisfactorily.

- A least-squares-fit analysis was not performed for a LLRT. The instru-

~

mentation error for an LLRT consists of the flow meter uncertainty which is added to the measured leak rate. The uncertainty of the flow meter used for this test was t 100 sec/ min.

The failure of this penetration was reported to the NRC in Licensee Event Report 85-05.

The following valves had leakage >0.6La as measured during the initial LLRT in 1985:

SF-046 (P-25, Spent Fuel Pool Cooling)

CV-10014 (P-57-2, Chill Water Return)

The redundant Containment isolation valve in each of the subject penetrations had no leakage. The penetrations, therefore, were operable.

The degraded valves were subsequently repaired and the leakage was reduced.to acceptable levels.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 October 31, 1986 License NPF-1 Attachment Page 23 of 24 1986 Type B or C Test Failures Penetration P-57 MO-10013 Both valves failed to reach test CV-10014 pressure.

On April 21, 1986, LLRT was conducted on Penetration P-57-2, chill water return valves. The penetration could not maintain test pressure (60 psig), and thus leakage could not be measured. It was therefore assumed the actual leakage was greater than the maximum allowed limit of 0.6La (199,875 sec/ min).

Analysis:

The failure was due to the rubber valve seat separating from the valve body. The chilled water valves have had a history of this failure mode since 1981. All of the chilled water containment isolation valves were replaced during the 1986 refueling outage.

A least-squares-fit analysis was not conducted for an LLRT.

The instrumentation error for LLRT is the uncertainty of the flow meter which is added to the measured leak rate. For the chilled water valve failures, the uncertainty of the flow meter was 100 sec/ min.

The chill water valve failures were reported in Licensee Event Report 86-05.

2 Mr. Steven A. Varga-Trojan Nuclear Plant October 31, 1986 Docket 50-344 Attachment License NPF-1 Page 24 of 24 APPENDIX 15 The following summary report of the verification test employed to validate the ILRT is provided in accordance with 10 CFR 50, Appendix J, Section V.B.3.

Verification Test Results The verification test began at 1830 on May 29, 1986 and was satisfactorily completed at 2230 the same day.

The acceptance limits for the verification test were as follows:

UPPER LIMIT = (LAN-TT) + Lo + 0.25La = 0.142 %/ day LOWER LIMIT = (LAM-TT) + Lo - 0.25La = 0.092 %/ day Where:

LAM-TT = the ILRT leak rate (0.017 %/ day)

Lo

= the verification leak rate induced by the mass flow meter

= 0.100 %/ day La

= the maximum allowed integrated leak rate

= 0.100 %/ day The measured verification leak rate (Lc) was 0.127 %/ day, which was within the established limits.

The 1986 Integrated Leak Rate Test, therefore, was validated by the verification test results.

Refer to Appendix 9 for the compiled data and to Appendix 3 for a graph of the verification test.

t SAB/kal 1196W.1086

.

ML20211H005

Text

Dear Sir:

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