Text

Reactor Containment Bldg Integrated Leak Rate Test
	ML20002C898
Person / Time
Site:	Yankee Rowe
Issue date:	09/30/1980
From:	Autio H, Henderson T, Warner B; YANKEE ATOMIC ELECTRIC CO.
To:	;
Shared Package
ML20002C894	List: ML20002C893; ML20002C898;
References
	NUDOCS 8101120296
	Download: ML20002C898 (84)
	v • d • e

{{#Wiki_filter:T o. REACTOR CONTAINMENT BUILDING l INTEGRATED LEAK RATE TEST SEPTEMBER 1980 YANKEE ATOMIC ELECTRIC COMPANY R0h'E, MASSACHUSETTS 01346 , h( g,3 Prepared By: W / f_4 7/ L h Reviewed By: Plant Re' actor Engineer i Approved By: 4 h ,L[,jfjf g;c Plant Superintendent I i 9 slo 13 20 W

_ = Page 1 i REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST d CONTENTS INTRODUCTION A. Type "A" Test 1. General Data i 2. Technical Data 3. Test Data 4. Verification Test i 5. Analysis and Irtterpretation B. Summary of Type "B" and "C" Test Events TABLES FIGURES I l i T I 4 a, I s m ___.__-__-.,_________._____________m_

a Page 2 INTRODUCTION During September, 1980, a periodic Reactor Containment Building Integrated Leak Rate Test (Type "A" Test) was conducted at Yankee-Rowe to demonstrate the leak tight integrity of the vapor container. The regulating docum:nts for the test were Appendix J of 10 CFR 50 and ANSI N45.4-1972, per Yankee-Rowe Technical Speci-fications (TS 4.6.1.2). In addition, ANS N274 Draft 3-July 1979 was followed extensively to conform with current NRC guidelines. A routine unannounced NRC inspection was conducted during the Type "A" Test (Report No. 50-29/80-17). No unresolved items or items of non-compliance were identified by the inspector. A minimum test pressure of 16 psig was maintained during the test. The vapor container air mass was calculated using the absolute method and data was analyzed using the mass point method. Since the last Type "A" Test in June, 1977, Type "B" and "C" tests have been conducted at intervals no greater than 24 months (6 months for the vapor container personnel hatch). A running total of the Type "B" & 'C" test leak rate results has been updated with each test to monitor continuous compliance with the Technical Specifications (TS 3.6.1.2.b). Testing was accomplished using the pressure decay method at a minimum test pressure of 32 psig. l l = l l e l l l l

P g2 3 A. TYPF,'"_ TEST 1. GE""RAL DATA (a) Owner: Yankee Atomic Electric Company (b) Docket No: 50-29 (c) Location: Yankee Nuclear Power Station (Yankee-Rowe) Star Route Rowe, Massachusetts, 01367 (d) Containment

Description:

The vapor container is a steel sphere 125 feet in diameter, with a minimum thickness of 7/8 inch. The vapor container is com-pletely above ground and is uninsulated. (e) Date Test was Con.pleted: September 24, 1980 2. TECHNICAL DATA: 3 (a) Containment net free volume: 860,000 ft (b) Design Pressure: 34.5 psig (c) Design Temperature: 249*F (d) Calculated Accident Peak Pressure: 31.6 psig (e) Calculated Accident Peak Temperature: 244 F 3. TEST DATA (a) Test Method: Absolute (b) Data Analysis Technique: Mass Point (c) Test Pressure: 16 psig (J) Maximum Allowable Leakage Rate, Lt: 0.1123%/24-hours (e) Maximum Acceptable Measured Leakage Rate, Ltm: 0.07861%/24-hours (fL Calculated Leakage Rate at 95% Upper Confidence Level: 0.03593o8%/24-hours (g) Type "C" Corrections for Systems in Operation During the Test Period: 0.0007117%/24-hours (h) Corrections for Liquid Level Changes in.the Containment Net Free Volume: 0.010539%/24-hours (i) Calculated Leakage Rate at 95% UCL Plus Correction Factors: 0.0471895%/24-hours (j) Measured Leakage Rate, Ltm: 0.0191308%/24-hours 4. VERIFICATION TEST (a) Mass Step Change Metc.ed Volume: 53.524% of Lt (b) Mass Step Change Measured by Type "A" Test Instrumentation: 60.441% of Lt

Page 4 5. ANALYSIS AND INTERPRETATION (a) Description of the Type "A" Test: The Type "A" test was conducted during the extended turbine repair outage using proredure No. OP-4701, Revision 6. Prior to the test, the strt-tural integrity of the containment vessel was verified by a visual inspection of the accessible interior and ex- 'ae'*r surfaces of the vessel (TS 4.6.1.6). No abnormal degradation was noted during the inspection, which was com-pleted at 1716 on September 21, 1980. Three portable 1200 cfm air compressors were connected to the vapor container. The main coolant system was vented to the vapor container atmosphere. An extensive valve line-up was completed. Pressurization of the vape container commenced at 1045 on September 22, 1980. At it. all containment isolation valves tripped closed, at 4.6 psig. The air charge was stopped and initial water collection data was taken on the pressurizer level, low pressure surge tank level, and the vapor container drain tank level. A post-isolation valve line-up was initiated to subject the vapor container pene-trations to backside atmospheric pressure to the extent practicable. A vapor container entry was made to check for oil mist and overall vapor container atmorphere condi-tions. The inspection was completed satisfactorily, and the air charge was continued at 1345. During the air charge to the test pressure, the post-isolation valve line-up was completed. Test pressure was reached and the air charge was stopped at'1915. The charging manifold was vented to atmosphere l anl the temperature stabilization period was begun. Using the temperature stabilization criteria of ANS N274 Draft 3-l July 1979, temperature stabilization was verified as of the data taken at 0004 on September 23, 1980. The test period was commanced at 0025. i During the night it was noticed that the graphs of the vapor container dry air pressure and the vapor container air mass were showing considerable data scatter. Investigation re-sulted in the discovery that the Mensor Quartz Manometer was oscillating. The oscillation was stopped at 0650, and sub-sequent data pointe were normal. The test period was continued until 0711 on September 24, 1980, approximately 24 hours following the ending of the Mensor oscillation. Preliminary computer data indications were that the leak rate was well within the acceptance criteria. m

Page 5 i The pumpback verification test was commenced at 0741. i*he pumpback was completed at 0837, and subsequent data collec-tion and reduction showed the Type "A" test instrumentation was quite sensitive and easily met the acceptance criteria. Data taking was continued until 1147 for unequivocal veri-fication of the sensitivity of the instrumentation. The vapor container was subsequently depressurized and final water collection data was taken on the pressurizer level, low pressure surge tank level, and the vapor container drain tank level. The post-test valve line-up was completed. (b) Instrumentation: In 1978 EDCR 78-07, "Upgraoe of Contain-ment Type "A" Test Instrumentation", was completed. This upgrade involved a total revamping of all instrumentation used in the data collection and reduction for Yankee-Rowe's future Type "A" tests, and included adherence to the Instru-mentation Selection Guide formula of ANS-N274 Draft. Vapor container temperatures were measured with twenty ARI Industries, Inc., Aridet Resistance Temperature Detectors, Model R-14.3-3E100. Vapor containtr pressure was measured with one Mensor Cor-poration Juartz Manometer, Model 10100-001. Vapor container dew probe readings were measured with lour Honeywell Dewprobe Sensors, Model SSP 129b061. Ambient temperature was measured with one ARI Industries, Inc., Aridet Resistance Temperature Detector, Medel R-14.3-3E100. Ambient pressure was measured with one Setra Systems Elec-tronic Manometer, Model 350A. Pumpback air flow was measured with one Singer, American Meter Division, American Aluminumcase Meter, Model AL-800. Signals from the resistance temperature detectors, dewprobe sensors, and manometers were collected and filed by one Consolidated Controls Corporation Datalogger, Model 90MC1-19. Instrumentation data from the datalogger was processed with one Digital Equipment Corporation computer,Model PDP 8/E. (c) Instrumentation Calibration: Instrumentatic1 used for the Type "A" test w re individually calibrated or checked as e applicable no more than six months prior to the start of the Type "A" test, using standards which are traceable to the National Bureau of Standards. The measured correction factors for each instrument were implemented in the computer program used to process the data. m

Page 6 (d) Data Processinri Tables 1 through 9 and Figures. through 9 show the results of the processed data of the Type "A" test. A program developed by the Macro Corporation was used to read the Consolidated Controls Corporation Datalogger file at five minute intervsls and to store the data in the PDP 8/E computer. The data sets stored in the PDP 8/E computer were read in groups of three and processed using a second computer program (see Table 10). For each data set the readings were corrected for decimal point and adjusted by the individual measured correc-tion factors. The vapor container temperature readings were then weighted for the vapor container volume they represented, and a vapor con-tainer average temperature was calculated. The four dewprobe readings were then averaged. Next, the following parameters were averaged fer the three data sets: ambient temperature, ambient pressu;e, vapor container average temperature, vapor containex total pressure, and the dewprobe readings. The dewprobe readings were then converted to vapor container dew point temperatures using the following equation which was developed from a calibration chart obtained from Honeywell: Dew Poin't Temp. = 42.8081 + 0.752944(A) 2 3 - 0.0004115(A ) - 0.00000722(A ) where A = Dewprobe reading - 108.393 The dew point temperature was then converted to partial water pressure using the following equation: Partial Water Press. = 0.362625 + 0.0123915(B) 2 3 + 0.00019115(B ) + 0.00000157(B ) l where B = Dew Point Temp. - 69.9998 An average vapor container air mass for the three data sets was then calculated using the ideal gas law. As each vapor container air mass number was obtained a linear least squares fit was performed. From the '.inear least squares fit a leak rate and a 95% upper confidence level leak rate were calculated. The 95% upper confidence level leak rate was de-veloped from formulas in ANS N274 Draf t 3-July 1979. After the test period had been running for 24 hours the leak rates were also calculated for the previous 24 hours. i Upon completion of processing each group of three data sets the I results were output on a hard copy computer terminal. l ~~

i i l t l Pagm 7 Due to the large amount of data taken during the test period, it was necessary to switch to a second data disk during the test period. This switch was anticipated and occurred following the output of the results at 1650 on September 23, 1980. When the next group of data sets was output, the time indicated was 1706. Thus, one minute of continuity was lost during the switching j of the data disks. In addition, a minor computer problem occurred following the output of the results at 2051 on September 23, 1980. l When the problem was corrected, the time indicated for the next l set of data was 2111. Thus, a set of data had been misplaced, l although it was still on file in the computer. Following the I completion of the Type "A" test the program was re-run to re-trieve the misplaced set of data. The five-minute time differ-ence resulted in essentially an insignificent change in the results. For example, the 95% upper confidence level leak rate changed from 0.035126%/24-hours to 0.0359388%/24-hours. Since this change for the five-minute time difference was so small, no attempt was made to account for the one minute of lost continuity. (e) Pumpback Verification Test. Acceptability is demonstrated if the instrumenta ion indicates the mass change to within 25% i of the allowable 24-hour mass loss. The initial air mass at the start of the pumpback test was 137,016 lbm. The air flow integrator calculations showed that 82.357 lbm. of air were pumped in. The instrumentation indicated that the resulting air mass was 137,109 lbm., a difference of 93 lbm. Using the l formula for mass change acceptability given in ANS N274 Draft 3-Jul3 1979, the result is 14.1098%, well within the 25% accep-tance criteria. (f) Type "C" Corrections. There were four Type "C" corrections to ( the 95% upper confidence level leak rate for systems in opera-tion. The corrections made were the most recent Type "C" test l results for the systems involved, at the concurrence of the I NRC inspector. The total correction was 0.0007117%/24-hours, and consisted of the following: l l Service Water: 0.00031;%/24-hours VC Heating: 0.00031%/24-hours Component Cooling Return: 0.000083%/24-hours l Valve Stem Leakoff: 0.0000037L'24-hours (g) Liquid Level Change Corrections: Three levels which coulo affect the net free volume of the vapor container I were monitored during the Type "A" test. These levels were the pressurizer level, the low pressure surge tank level, and the vapor container drain tank level. From the time of the initial vapor container isolation until the subsequent depressurization, the pressurizer level decreaced one inch, the low pressure surge tank level increased nine inches, and the vapor container drain tank level increased 8.5 inches. Corrections to the 95%

Page 8 upper confidence level leak rate due to the changes in pressurizer level and low pressure surge tank level amounted to 0.010539%/24-hours. The change in the vapor container drain tank level was not considered, as per ANS N274 Draft 3-July 1979. (h) Potentially Excessive Leakage Pcths. There were no potentially excessive leakage paths identified during the course of the Type "A" test. B. SLWiARY OF TYPE "B" AND "C" TEST EVENTS Type "B" and "C" leakage rates are monitored on a minimum two year basis for all but the vapor container personnel hatch which is on a six month basis. The results of the staggered tests are used to update the running total (see Figure 10) so that at any given time the combined leakage rate for all penetrations subject to Type "B" and "C" testing is available for comparison with Technical Specification and administrative limits. The pressure decay, absolute method of leak testing has been employed during the interval between the Type "A" test in June, 1977, and the latest Type "A" test in September, 1980. The pressure decay method utilizes a pressurized volume upstream of the Type "B" or "C" containment boundary. The downstream side of the boundary is vented where possible. The test volume is pressurized to greater than accident pressure, and the prersure source is disconnected. The rate of pressure decay will then indicate the leakage rate via the ideal gas law. All leakage is assigned to the boundary unless zero leakage through the boundary can be established with a halide detector. Type "C" tests caused the running total leakage rate to fail Technical Specification acceptance criteria on eight occasions during the interval. In addition, two Type "C" test periods exceeded the 24-month maximum allowed. All ten events were reported at their occurrence. Per Appendix J a separate report of these events will accompany this report. There were no events concerning Type "B" tests during the interval.

Pagn 9 TABLE 1 VAPOR CONTAINER AIR MASS DATE TIME AIR MASS,1bm Temperature 22 Sept 80 2004 137126 Stabilization 2019 137148 Period 2034 137152 2049 137000 2104 137136 2119 137174 2134 137215 2149 137022 2204 137184 2219 137062 2234 136944 2249 137005 2304 137029 2319 137073 2334 137063 2349 137236 23 Sept 80 0004 137334 0019 137342 Test Period 23 Sept 80 0035 137159 0050 137188 0105 137021 0120 137002 0135 137040 0150 136962 0205 137222 0220 137163 0235 137136 0250 137027 0305 136987 0320 137140 0335 136960 0350 137105 0405 137012 0420 137197 0435 137053 0450 137071 0505 137090 0520 136911 0535 137009 0550 136988 0605 136994 0620 136989 0635 137034 0650 137092 0705 137016 0720 137010 0735 137007 0750 137011

Page 10 TABLE I (cont'd) VAPOR CONTAINER AIR MASS DATE TIME AIR HASS,1bm i Test Period 23 Sept 80 0805 136991 l 0820 136940 0835 136951 0850 136962 0905 136968 0920 136976 0935 136985 0950 136978 1005 136970 1020 136971 1035 136971 1050 136967 1105 136982 1120 137002 1135 137031 1150 137049 1205 137063 1220 137062 1235 137062 1250 137064 1305 137069 1320 137068 1335 137069 1350 137068 1405 137065 1420 137069 1435 137069 1450 137075 1505 137075 1520 137078 1535 137078 1550 137071 1605 137055 l 1620 137037 1635 137022 1650 137003 1706 136999 1721 136986 1736 136977 1751 136965 l 1806 136960 l 1821 136947 1836 136948 f 1851 136949 1906 136943 i 1921 136939 1936 136938 i

Page 11 TABLE 1 (cont'd) VAPOR CONTAINER AIR MASS DATE TIME AIR MASS,1bm Test Period 23 Sept 80 1951 136939 2006 136939 2021 136937 2036 136936 2051 136936 2106 136948 2121 136974 2136 136983 2151 136976 2206 136972 2221 136978 2236 136986 2251 136982 2306 136983 2321 136982 2336 136980 2351 136985 24 Sept 80 0006 136989 0021 136989 0036 136984 0051 136982 0106 136983 0121 136984 0136 136993 0151 136989 0206 136991 0221 136994 0236 136989 0251 136987 0306 136994 0321 146995 0336 136987 0351 136992 0406 136991 0421 137002 0436 137003 0451 136993 0506 137000 0521 137003 0536 137000 0551 137006 0606 137006 0621 137007 0636 137003 0651 137003 0706 137004 i

e Page 12 TABLE 1 (cont'd) VAPOR CONTAINER AIR MAS _S_ DATE TIME AIR MASS,1bm Pumpback 24 Sept 80 0732 137016 Verification 0747 137014 Period 0802 137036 0817 137055 0832 137078 0847 137100 0902 137109 0917 137115 0932 137114 0947 137114 1002 137121 1017 137123 1032 137125 1047 137126 1102 137112 1117 137122 1132 1371?? 1147 137124

Page 13 TABLE 2 VAPOR CONTAINER AVERAGE TEMPERATURE DATE TIME TEMP., *F Temperature 22 Sept 80 2004 73.9411 Stabilization 2019 73.5448 Period 2034 73.2218 2049 72.9495 2104 72.6944 2119 72.4659 2134 72.2493 2149 72.0586 2204 71.8632 2219 71.6861 2234 71.5128 2249 71.3534 2304 71.2118 2319 71.056 2334 70.9441 2349 71.1904 23 Sept 80 0004 71.494 0019 71.6863 Test Period 23 Sept 80 0035 71.8667 0050 72.0274 0105 72.1671 0120 72.2761 0135 72.3596 0150 72.4308 0205 72.4933 0220 72.564 i 0235 72.6703 0250 72.8004 0305 72.969 0320 73.1529 0335 73.3559 0350 73.5516 0405 73.7445 0420 73.9146 0435 74.0757 0450 74.1617 0505 74.231 0520 74.2744 0535 74.2995 0550 74.328 0605 74.3589 0620 74.3837 0635 74.4092 0650 74.4565 0705 74.4997 0720 74.5172 0735 74.5067

Pag 2 14 TABLE 2 (cont'd) VAPOR CONTAINER AVERAGE TEMPERATLHE DATE TIME TEMP., *F Test Period 23 Sept 80 0750 74.4923 0805 74.4668 0820 74.2033 0835 73.9369 0850 73.7792 0905 73.6659 0920 73.5817 0935 73.4993 0950 73.4321 1005 73.3117 1020 73.1803 1035 73.0478 1050 72.9368 1105 72.8511 1120 72.7859 1135 72.7766 1150 72.8076 1205 72.8278 1220 72.8407 1235 72.828 1250 72.8482 1305 72.9604 1320 73.1076 1335 73.2422 1350 73.3489 1405 73.4341 1420 73.4935 1435 73.5697 1450 73.6484 1505 73.6956 1520 73.7349 1535 73.7623 1550 73.7455 1605 73.6959 1620 73.6206 1635 73.4978 1650 73.3672 1706 73.2616 1721 73.168 1736 73.07 l 1751 72.963 1806 72.8166 l 1821 72.6626 1836 72.4353 1851 72.1751 1906 71.9246 j 1921 71.683 1936 71.4325

Page 15 TABLE 2 (cont'd) VAPOR CONTAINER AVERAGE TEMPERATURE DATE TIME TEMP.,'F Test Period 23 Sept 80 1951 71.1544 2006 70.9072 2021 70.6595 2036 70.4101 2051 70.1783 2106 69.9452 2121 69.8323 2136 69.7419 2151 '69.6465 2206 69.55 2221 69.434 2236 69.3287 2251 69.2414 2306 69.1312 2321 69.0014 2336 68.881 2351 68.761 24 Sept 80 0006 68.6672 0021 68.5691 0036 68.4689 0051 68.3851 0106 68.2731 0121 68.1742 0136 68.0709 0151 68.0171 0206 67.9239 0221 67.8334 0236 67.7507 0251 67.6691 0306 67.5579 0321 67.467 0336 67.3695 0351 67.268 0406 67.1623 0421 67.0639 0436 66.9841 0451 66.9423 0506 66.8612 0521 66.7965 0536 66.7333 0551 66.6402 0606 '6.5633 0621 66.4923 0636 66.4288 0651 66.3548 0706 66.3017

Page 16 TABLE 2 (cont'd) ' VAPOR CONTAINER AVERAGE TEMPERATLHE DATE TIME TEMP., 'F Pumpback 24 Sept 80 0732 66.1638 Verification 0747 66.1111 Period 0802 66.0595 0817 66.0105 0832 65.9523 0847 65.9757 0902 66.0281 0917 66.0562 0932 66.0769 0947 66.1434 1002 66.2255 1017 66.3158 1032 66.4464 1047 66.5511 1102 66.6927 1117 66.8306 1132 67.0068 1147 67.1915 e

P:g2 17 TABLE 3 ' VAPOR CONTAINER DEW POINT TEMPERATU_RE DATE TIME TEMP., 'F Temperature 22 Sept 80 2004 55.2768 Stabilization 2019 54.3281 Period 2034 53.324 2049 52.4484 2104 51.635 2119 51.064 2134 50.6618 2149 50.3296 2204 49.9495 2219 49.5698 2234 49.3559 2249 49.1128 2304 48.8832 2319 48.723 2334 48.6901 2349 49.3447 23 Sept 80 0004 50.6228 0019 51.8354 Test Period 23 Sept 80 0035 53.0266 0050 54.0241 0105 54.8312 0120 55.6072 0135 56.1231 0150 56.5841 0205 57.0499 0220 57.2764 0235 57.546 0250 57.8207 0305 58.0225 0320 58.2677 0335 58.5266 0350 58.6059 0405 58.7679 0420 58.8676 0435 58.9624 0450 59.0686 0505 59.0958 0520 59.216*- 0535 59.1S;b 0550 59.2666 0605 59.3727 0620 59.3438 0635 59.3432 0650 59.4059 0705 59.4506 0720 59.497 0735 59.6085

Pag 2 18 TABLE 3 (cont'd) VAPOR CONTAINER DEW POINT TEMPERATURE ~ DATE TIME TEMP., 'F Test Period 23 Sept 80 0750 59.5796 0805 59.7229 0810 59.6049 0835 59.222 0850 58.7516 0905 58.3621 0920 57.8643 0935 57.3839 0950 56.876 1005 56.2955 1020 55.7738 1035 55.3911 1050 55.1595 1105 54.7352 1120 54.4597 1135 54.3551 1150 54.1051 1205 53.8163 1220 53.6248 1235 53.4462 1250 53.2878 1305 53.0832 1320 52.9652 1335 52.833 1350 52.654 1405 52.5192 1420 52.3289 1435 52.1793 1450 52.0068 1505 51.9045 1520 51.7479 1535 51.6153 1550 51.5455 1605 51.303 1620 51.1894 1635 50.9306 1650 50.8039 ~ 1706 50.564 1721 50.5517 1736 50.4935 1751 50.2783 1806 50.2337 1821 50.1285 1836 49.8517 1851 49.7811 1906 49.6534 1921 49.4284 1936 49.2877 -r - - - - +, -.

Page 19 TABLE 3 (cont'd) VAPOR CONTAINER DEW POINT TEMPERATURE DATE TIME TEMP., *F Test Period 23 Sept 80 1951 49.3255 2006 49.0898 2021 49.0513 2036 48.9576 2051 48.8925 2106 48.728 2121 48,7739 2136 49.1822 2151 49.6888 2206 50.217 2221 50.5022 2236 50.6135 2251 50.9257 2306 51.0609 2321 51.0239 2336 51.2055 4 2351 51.2438 24 Sept 80 0006 51.1499 0021 51.0715 0036 51.1641 0051 51.0375 0106 51.0381 0121 51.0128 0136 50.925 0151 50.8052 e 0206 50.8299 0221 50.6265 l 0236 50.6036 0251 50.535 0306 50.35 0321 50.2436 0336 50.3247 0351 50.1186 0406 50.0053 0421 49.7984 0436 49.6764 0451 49.7984 0506 49.5995 0521 49.4997 0536 49.3888 0551 49.2747 0606 49.2381 0621 49.186 0636 49.1407 0651 49.0681 0706 49.0216

PD8e 20 TABLE 3 (cont'd) ' VAPOR CONTAINER DEW POINT TEMPERATURF; DAW. TIME TEMP., 'F Pumpback 24 Sept 80 0732 48.7633 Verification 0747 48.746 Period 0802 48.6628 0817 48.5156 0832 48.6435 0847 48.7398 0902 48.8515 0917 49.0284 0932 49.0557 0947 49.1835 1002 49.2957 1017 49.5958 1032 49.7563 1047 49.887 1102 50.3265 1117 50.4008 1132 50.4336 1147 50.6185 i l l

Page 21 TABLE 4 AMBIENT TEMPERATURE DATE TIME TEMP., 'F Temperature 22 Sept 80 2004 67.71 Stabilization 2019 67.1366 Period 2034 66.8833 2049 66.41 2104 66.24 2119 66.0 2134 65.8466 2149 65.3733 2204 65.2166 2219 65.09 2234 65.0033 2249 64.68 2304 64.4266 2319 64.69 2334 64.48 2349 64.24 23 Sept 80 0004 64.1933 0019 64.4033 Test Period 23 Sept 80 ~0035 64.1733 0050 64.2533 0105 64.1333 0120 64.1366 0135 64.0833 0150 64.1266 0205 64.2966 0220 65.43 0235 67.3233 0250 72.6133 l 0305 74.9566 0320 75.58 0335 76.05 0350 76.1966 0405 75.8466 0420 74.4033 0435 70.74 0450 71.58 0505 70.49 0520 69.63 l 0535 69.0133 0550 69.1233 0605 69.9366 0620 71.44 l 0635 72.81 0650 72.45 0705 72.2066 0720 71.8233 0735 71.3733 v e,

Page 22 TABLE 4 (cont'd) AMBIENT TEMPERATURE DATE TIME TEMP., *F Test Period 23 Sept 80 0750 71.0033 0805 71.01 0820 71.7666 0835 71.7466 0850 70.9833 0905 70.5133 0920 70.3066 0935 69.6433 0950 68.55 1005 68.15 1020 68.82 1035 68.8566 1050 68.48 1105 68.5 1120 70.0333 1135 71.7566 1150 70.0733 1205 69.8266 1220 69.2666 1235 69.9233 1250 72.0 1305 72.3033 1320 72.9566 1335 72.1833 1350 73.0833 1405 73.9 1420 73.9533 1435 73.31 1450 73.29 ) 1505 73.1566 1520 72.9366 1535 70.7066 1550 69.2566 1605 68.7767 1620 67.1 1635 66.1566 1650 66.6066 1706 66.6533 1721 68.3766 1736 66.6866 1751 64.52 1806 63.7933 1821 62.11 1836 59.5467 1851 57.28 1906 56.05 4 1921 55.2833 1936 54.0833

Page 23 TABLE 4 (cont'd) AMBIENT TEMPERATURE DATE TIME TEMP., 'F Test Period 23 Sept 80 1951 53.0667 2006 52.19 2021 51.6466 2036 51.1333 2051 50.44 2106 50.3566 2121 50.3767 2136 50.36 2151 50.1066 2206 50.1567 2221 49.8 2236 49.4633 2251 48.8366 2306 48.6567 2321 48.1066 2336 48.2467 2351 48.5 24 Sept 80 0006 47.9966 0021 47.9367 0036 47.7167 0051 47.5067 0106 47.1966 0121 47.01 0136 46.5766 0151 46.97 0206 46.9566 0221 46.8767 0236 46.8433 0251 46.1266 0306 45.89 0321 45.26 0336 44.6967 0351 44.55 0406 44.2833 0421 44.08 0436 44.2767 0451 43.85 0506 43.5333 0521 43.3266 0536 =42.99 0551 42.6733 0606 42.3967 0621 42.32 0636 42.4 0651 42.3133 0706 42.3467

Pega 24 TABLE 4 (cont'd) AMBIENT TEMPERATURE DATE TIME TEMP., *F Pumpback 24 Sept 80 0732 42.9 Verification 0747 43.4267 Period 0802 43.96 0817 44.3767 0832 46.2333 0847 47.4267 0902 47.6433 0917 47.87 0932 48.1033 0947 49.2967 1002 49.78 1017 50.8833 1032 51.4766 1047 51.65 1102 52.39 1117 53.69 1132 55.0166 1147 55.9666 ) J

Page 25 TABLE 5 VAPOR CONTAINER TOTAL PRESSURE DATE TIME PRESS., psia Tempera'ture 22 Sept 80 2004 31.7405 Stabilization 2019 31.7141 Period 2034 31.689 2049 31.632 2104 31.6422 2119 31.6335 2134 31.6271 2149 31.5694 2204 31.592 2219 31.5517 2234 31.5123 2249 31.5159 2304 31.511 2319 31.511 2334 31.5022 2349 31.5602 23 Sept 80 0004 31.6095 0019 31.6308 Test Period 23 Sept 80 0035 31.6086 0050 31.6317 0105 31.6076 0120 31.6158 0135 31.6333 0150 31.6236 0205 31.691 0220 31.6836 0235 31.6858 0250 31.6704 0305 31.6733 0320 31.7212 0335 31.6938 0350 31.7397 0405 31.7307 l 0420 31.7843 0435 31.7617 0450 31.7718 0505 31.7803 0520 31.7426 0535 31.7667 I 0550 31.7646 l 0605 31.7689 I 0620 31.7682 0635 31.78 0650 31.7971 0705 31.7821 0720 31.7828 0735 31.7825 0750 31.7817 l l

Pegn 26 TABLE 5 (cont'd) VAP0'1 CONTAINER TOTAL PRESSURE DATE TIME PRISS., psia Test Period 23 Sept 80 0805 31.7775 0820 31.7492 0835 31.732 0850 31.7213 0905 31.713 0920 31.7059 0935 31.699 0950 31.6884 1005 31.6756 1020 31.664 1035 31.6531 1050 31.6438 1105 31.6381 1120 31.6367 1135 31.6428 1150 31.6469 1205 31.6482 1220 31.6479 1235 31.6461 1250 31.6467 1305 31.6525 1320 31.6599 1335 31.6671 1350 31.6722 1405 31.6756 1420 31.6789 j 1435 31.6825 1450 31.6866 1505 31.6894 l 1520 31.6912 1535 31.692 1550 31.6882 1605 31.6807 1620 31.6712 1635 31.6586 1650 31.6454 1706 31.6363 l 1721 '1.6276 1736 31.6199 1751 31.6099 { 1806 31.5989 l 1821 31.5869 l 1836 31.5718 l 1851 31.5556 1906 31.5386 1921 31.5223 1936 31.5063 l

Page 27 ) TABLE 5 (cont'd) VAPOR CONTAINER TOTAL PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 1951 31.4902 2006 31.4745 2021 31.4586 2036 31.4435 2051 31.4289 2106 31.417 2121 31.4171 2136 31.4158 2151 31.4127 2206 31.4091 2221 31.4056 2236 31.402 2251 31.3981 2306 31.3927 2321 31.385 2336 31.3783 2351 31.3724 '24 Sept 80 0006 31.3668 0021 31.3609 0036 31.355 0051 31.3486 0106 31.3422 0121 31.3366 0136 31.3314 0151 31.3265 0206 31.3214 0221 31.3156 0236 31.3097 0251 31.3035 0306 31.2975 0321 31.2912 0336 31.2848 0351 31.278 0406 31.2714 0421 31.2662 0436 31.2616 0451 31.257 0506 31.2527 0521 31.2486 0536 31.2442 0551 31.2391 0606 31.2345 0621 31.2296 0636 31.2248 0651 31.2206 0706 31.2156

s o e = Page 28 TABLE 5 (cont'd) VAPOR CONTAINER TOTAL PRESSURE DATE TIME PRESS., psia Pumpback 24 Sept 80 0732 31.2101 Verification 0747 31.2066 Period 0802 31.2075 0817 31.2079 0832 31.2107 0847 31.2171 0902 31.2232 0917 31.2273 0932 31.2293 0947 31.2332 1002 31.2406 1017 31.2484 1032 31.2576 1047 31.265 1102 31.273 1117 31.2835 '~ 1132 31.2952 1147 31.3073 e e

Pege 29 TABLE 6 VAPOR CONTAINER PARTIAL WATER PRESSURE DATE TIME PRESS., psia Temperature 22 Sept 80 2004 0.217 Stabilization 2019 0.209 Period 2034 0.202 2049 0.196 2104 0.19 2119 0.186 2134 0.183 2149 0.181 2204 0.178 2219 0.176 2234 0.174 2249 0.173 2304 0.171 2319 0.17 2334 0.17 2349 0.174 23 Sept 80 0004 0.183 0019 0.191 Test Period 23 Sept 80 0035 0.2 0050 0.207 0105 0.213 0120 0.219 0135 0.223 0150 0.227 0205 0.231 0220 0.233 0235 0.235 0250 0.237 0305 0.239 0320 0.241 0335 0.243 0350 0.244 0405 0.245 0420 0.246 0435 0.247 0450 0.248 0505 0.248 0520 0.249 0535 0.249 0550 0.25 0605 0.251 0620 0.25 0635 0.25 0650 0.251 0705 0.251 j 0720 0.252 1 0735 0.253 0750 0.252 0805 0.254

l Page 30 TABLE 6 (cont'd) VAPOR CONTAINER PARTIAL WATER PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 0820 0.253 0835 0.249 0850 0.245 0905 0.242 i f 0920 0.238 0935 0.234 0950 0.229 1005 0.225 1020 0.221 1035 0.218 1050 0.216 l 1105 0.212 1120 0.21 r 1 1135 0.21 1150 0.208 1205 0.205 1220 0.204 1235 0.203 1250 0.202 1305 0.2 1320 0.199 i 1335 0.198 1350 0.197 1405 0.196 1420 0.195 1435 0.194 1450 0.192 1505 0.192 1520 0.191 1535 0.19 1550 0.189 1605 0.188 1620 0.187 1635 0.185 1650 0.184 1706 0.182 1721 0.182 1736 0.182 1751 0.181 1806 0.18 1821 0.18 1836 0.178 1851 0.177 1906 0.176 1921 0.175 1936 0.174 1951 0.174 .m ~

Paga 31 TABLE 6 (cont'd) VAPOR CONTAINER PARTIAL WATER PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 2006 0.173 2021 0.172 2036 0.172 2015 0.171 2106 0.17 2121 0.171 2136 0.173 2151 0.177 2206 0.18 2221 0.182 2236 0.183 1 2251 0.185 2306 0.186 2321 0.186 2336 0.187 2351 0.187 24 Sept 80 0006 0.186 0021 0.186 0036 0.187 0051 0.186 0106 0.186 0121 0.186 0136 0.185 0151 0.184 0206 0.184 0221 0.183 0236 0.183 0251 0.182 0306 0.181 0321 0.18 0336 0.181 0351 0.179 0406 0.179 0421 0.177 0436 0.177 0451 0.177 0506 0.176 0521 0.175 0536 0.175 0551 0.174 0606 0.174 0621 0.173 0636 0.173 0651 0.173 0706 0.172

i Page 32 TABLE 6 (cont'd) VAPOR CONTAINER PARTIAL WATER PRESSt%E DATE TIME PRESS., psia Pumpback 24 Sept 80 0732 0.171 Verification 0747 0.171 Period 0802 0.17 0817 0.169 0832 0.17 0847 0.17 0902 0.171 0917 0.172 0932 0.173 0947 0.173 1002 0.174 1017 0.176 1032 0.177 1047 0.178 1102 0.181 1117 0.181 1132 0.182 1147 0.183 e S

Page 33 TABLE 7 VAPOR CONTAINER DRY AIR PRESSURE j DATE TIME PRESS., psia Temperature 22 Sept 80 2004 31.5235 Stabilization 2019 31.5051 Period 2034 31.487 2049 31.436 2104 31.4522 2119 31.4475 2134 31.4441 2149 31.3884 2204 31.414 2219 31.3757 2234 31.3383 2249 31.3429 2304 31.34 2319 31.341 2334 31.3322 2349 31.3862 23 Sept 80 0004 31.4265 0019 31.4398 Test Period 23 Sept 80 0035 31.4086 0050 31.4247 0105 31.3946 0120 31.3968 0135 31.4103 0150 31.3966 0205 31.46 0220 31.4506 0235 31.4508 0250 31.4334 0305 31.4343 0320 31.4802 0335 31.4508 0350 31.4957 0405 31.4857 0420 31.5383 0435 31.5147 0450 31.5238 0505 31.5323 0520 31.4936 0535 31.5177 0550 31.5146 0605 31.5179 0620 31.5182 0535 31.53 0650 31.5461 0705 31.5311 j 0720 31.5308 0735 31.5295 0750 31.5297

Page 34 TABLE 7 (cont'd) VAPOR CONTAINER DRY AIR PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 0805 31.5235 0820 31.4962 0835 31.483 0850 31.4763 0905 31.471 0920 31.4679 0935 31.465 0950 31.4594 1005 31.4506 1020 31.443 1035 31.4351 1050 31.4278 1105 31.4261 1120 31.4267 1135 31.4328 1150 31.4389 1205 31.4432 1220 31.4439 1235 31.4431 1250 31.4447 1305 31.4525 1320 31.4609 1335 31.4691 1350 31.4751 1405 31.4796 1420 31.4839 1435 31.4885 1450 31.4946 1505 31.4974 1520 31.5002 1535 31.502 1550 31.4992 1605 31.4927 1620 31.4842 1635 31.4736 1650 31.4614 1706 31.4543 1721 31.4456 1736 31.4379 1751 31.4289 1806 31.4189 1821 31.4069 1836 31.3938 1851 31.3786 1906 31.3626 1921 31.3473 1936 31.3323 1951 31.3162

Page 35 l l TABLE 7 (cont'd) j l, VAPOR CONTAINER DRY AIR PRESSURE ( DATE TIME PRESS., psia l l Test Period 23 Sept 80 2006 31.3015 2021 31.2866 2036 31.2715 i 2051 31.2579 2106 31.2469 2121 31.2461 2136 31.2428 2151 31.2357 2206 31.2291 j 2221 31.2236 l 2236 31.219 2251 31.2131 2306 31.2067 2321 31.199 2336 31.1913 r l 2351 31.1854 24 Sept 80 0006 31.1808 0021 31.1749 0036 31.168 l 0051 41.1626 0106 31.1562 ( 0121 31.1506 0136 31.1464 0151 31.1425 0206 31.1374 0221 31.1326 0236 31.1267 0251 31.1215 0306 31.1164 0321 31.1112 0336 31.1038 0351 31.0989 0406 31.0924 0421 31.0891 0436 31.0846 0451 31.08 0506 31.0767 ^ 0521 31.0736 0536 31.0692 0551 31.0651 0606 31.0605 0621 31.0566 0636 31.0518 0651 31.0476 1 0706 31.0446 I

Page 36 TABLE 7 (cont'd) VAPOR CONTAINER DRY AIR PRESSLTE DATE TIME PRESS., psia Pumpback 24 Sept 80 0732 31.0391 Verification 0747 31.0356 Period 0802 31.0375 0817 31.0389 0832 31.0407 0847 31.0471 l 0902 31.0522 0917 31.0553 0932 31.0563 0947 31.0602 1002 31.0666 1017 31.0724 1032 31.0806 1047 31.087 1102 31.092 1117 31.1025 1132 31.1132 1147 31.1243 i l

Psg2 37 TABLE 8 VAPOR CONTAINER GAUGE PRESSURE DATE TIME PRESS.,psig f Temperature 22 Sept 80 2004 17.7035 Stabilization 2019 17.6758 I Period 2034 17.6481 2049 17.5853 2104 17.5928 2119 17.5784 2134 17.5681 2149 17.5069 2204 17.5282 2219 17.4857 2234 17.4454 2249 17.4508 2304 17.4463 2319 17.4476 2334 17.4414 i 2349 17.5047 23 Sept 80 0004 17.5563 0019 17.5833 l Test Period 23 Sept 80 0035 17.5632 0050 17.5902 0105 17.5657 0120 17.5792 0135 17.6024 0150 17.5958 0205 17.6671 0220 17.665 0235 17.6716 0250 17.6619 l 0305 17.6666 l 0320 17.7153 0335 17.6919 0350 17.7378 0405 17.7288 0420 17.785 0435 17.7615 0450 17.7743 0505 17.7824 0520 17.7447 -0535 17.7679 0550 17.7609 0605 17.7661 0620 17.7575 0635 17.7601 0650 17.7772 0705 17.7605 0720 17.7576 0735 17.7551

Page 38 TABLE 8 (cont'd) VAPOR CONTAINER GAUGE PRESSLTE DATE TIME PRESS.,psig Test Period 23 Sept 80 0750 17.7547 0805 17.7524 0820 17.7231 0835 17.7042 0850 17.6931 0905 17.6825 0920 17.6728 0935 17.6624 0950 17.65 1005 17.6381 1020 17.6252 1035 17.6117 1050 17.5989 1105 17.59'.8 1120 17.5909 1135 17.5952 1150 17.5963 1205 17.5967 1220 17.5928 1235 17.5902 1250 17.5886 1305 17.593 1320 17.6026 1335 17.6098 1350 17.6171 1405 17.6201 1420 17.6212 1435 17.6222 1450 17.6227 1505 17.6242 1520 17.6203 1535 17.6163 1550 17.6086 1605 17.5984 1620 17.5854 1635 17.5679 1650 17.5487 l 1706 17.536 1721 17.5238 l 1736 17.5086 l 1751 17.4929 1806 17.4766 1821 17.4603 1836 17.4408 1851 17.4228 1906 17.4014 1921 17.3834 1936 17.3594

Paga 39 TABLE 8 (cont'd) VAPOR CONTAINER GAUGE PRESSURE DATE TIME PRESS.,psig Test Period 23 Sept 80 1951 17.3403 2006 17.3197 2021 17.2999 2036 17.2804 2051 17.2619 2106 17.2468 2121 17.2452 2136 17.2448 2151 17.2452 2206 17.242 2221 17.2368 2236 17.2315 2251 17.2284 2306 17.2217 2321 17.2122 2336 17.2037 2351 17.1983 24 Sept 80 0006 17.1914 0021 17.1851 0036 17.1792 0051 17.1719 0106 17.1629 0121 17.1577 0136 17.1538 0151 17.1458 0206 17.1376 0221 17.1319 0236 17.1256 0251 17.1193 0306 17.1141 0321 17.1088 0336 17.1028 0351 17.0951 0406 17.0868 0421 17.0802 0436 17.0712 0451 17.0601 0506 17.054 0521 17.0451 0536 17.0376 0551 17.0303 0606 17.024 0621 17.0191 0636 17.013 0651 17.003 0706 16.996

Page 40 TABLE 8 (cont'd) VAPOR CONTAINER GAUGE PRESSURE DATE TIME PRESS.,psig Pumpback 24 Sept 80 0732 16.9912 Verification 0747 16.9847 Period 0802 16.9842 0817 16.9838 0832 16.9809 0847 16.9882 0902 16.9933 0917 16.9974 0932 16.9976 0947 17.0025 1002 17.0107 1017 17.0208 1032 17.0256 1047 17.0329 1102 17.0432 1117 17.055 1132 17.0688 1147 17.0845 i i ,_y, 3 vew---, % e- -e.,e----- ,-ew e-==g w

Page 41 TABLE 9 AMBIENT PRESSURE DATE TIME PRESS., psia Temperature 22 Sept 80 2004 14.037 Stabilization 2019 14.0383 Period 2034 14.041 2049 14.0467 2104 14.0493 2119 14.055 2134 14.059 2149 14.0625 2204 14.0638 2219 14.066 2234 14.0669 2249 14.0651 2304 14.0647 2319 14.0634 2334 14.0607 2349 14.0555 23 Sept 80 0004 14.0533 0019 14.0476 Test Period 23 Sept 80 0035 14.0454 0050 14.0414 0105 14.0419 0120 14.0366 0135 14.0309 0150 14.0278 0205 14.0239 0220 14.0186 0235 14.0142 0250 14.0085 0305 14.0067 0320 14.0058 0335 14.0019 0350 14.0019 0405 14.0019 0420 13.9993 0435 14.0001 0450 13.9975 0505 13.9979 0520 13.9979 0535 13.9988 0550 14.0336 0605 14.0028 0620 14.0107 0635 14.0199 0650 14.0199 0705 14.0217 0720 14.0252 0735 14.0274 y

Pagt 42 TABLE 9 (cont'd) AMBIENT PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 0750 14.0269 0805 14.0252 0820 14.026 0835 14.0278 0850 14.0282 0905 14.0304 0920 14.0331 0935 14.0366 0950 14.0383 1005 14.0375 1020 14.0388 1035 14.0414 1050 14.0449 1105 14.0462 1120 14.0458 1135 14.0476 1150 14.0506 1205 14.0515 1220 14.055 1235 14.0559 1250 14.0581 1305 14.0594 1320 14.0572 1335 14.0572 1350 14.055 1405 14.0555 1420 14.0577 1435 14.0603 1450 14.0638 1505 14.0651 1520 14.0709 1535 14.0757 1550 14.0796 1605 14.0823 1620 14.0858 1635 14.0906 1650 14.0968 1706 14.1003 1721 14.1038 1736 14.1113 1751 14.117 1806 14.1222 1821 14.1266 1836 14.131 1851 14.1328 1906 14.1372 1921 14.1389 1936 14.1468

Paga 43 TABLE 9 (cont'd) AMBIENT PRESSURE DATE TIME PRESS., psia Test Period 23 Sept 80 1951 14.1499 2006 14.1547 2021 14.1587 2036 14.1631 2051 14.167 2106 14.1701 2121 14.1719 2136 14.171 2151 14.1675 2206 14.167 2221 14.1688 2236 14.170: 2251 14.1697 2306 14.171 2321 14.1728 2336 14.1745 2351 14.1741 24 Sept 80 0006 14.1754 0021 14.1758 0036 14.1758 0051 14.1767 0106 14.1793 0121 14.1789 0136 14.1776 0151 14.1807 0206 14.1837 0221 14.1837 0236 14.1842 0251 14.1842 0306 14.1833 0321 14.1824 0336 14.182 0351 14.1829 0406 14.1846 0421 14.1859 0436 14.1903 0451 14.1969 0506 14.1987 0521 14.2035 0536 14.2066 0551 14.2088 0606 14.2105 0621 14.2105 0636 14.2118 0651 14.2176 0706 14.2206

Pege 44 TABLE 9 (cont'd) AMBIENT PRESSURE DATE TIME PRESS., psia Pumpback 24 Sept 80 0732 14.2189 Verification 0747 14.2219 Period 0802 14.2233 0817 14.2241 0832 14.2298 0847 14.229 0902 14.2298 0917 14.2298 0932 14.2316 0947 14.2307 1002 14.2298 1017 14.2277 1032 14.232 1047 14.232 1102 14.2298 1117 14.2285 1132 14.2263 1147 14.2228 .e

Paga 45 0 TABLE 10 COMPUTER PROGRAM USED FOR DATA PROCESSING TYP'E TYPED.BA 1000 REM THIS PROGRAM IS FOR USE IN THE TYPE 'A' TEST A 1040 REM COMPLETE DESCRIPTION IS AVAILABLE IN THE RE FILE. 1080 REP DIMENSION VARIABLES 1120 DId D(64),M1(240) 1160 FILENil 'SYS: MASS

1200 INPUTil:R 1240 FOR I=1 TO R\\INPUTti:M1(I)\\NEXT I\\CLOSE #1 1280 R=R+1 1320 N=601+R*3 1360 IF N<800 THEN 1480 1400 N=N-197 1440 GO TO 1360 1480 G$="-------

1520 Fl=0\\V=1\\ REM CLOCK 1560 FOR I=1 TO F\\NEXT I\\ GO TO 1720 1600 F=F+1000*Fl\\F1=F1+1 1640 FOR I=1 TO 1000*F1\\NEXT I 1680 REM NOW READ HEADER AND SEE IF 3 SETS ARE READY 1720 FILENti:'RXA1: HEADER" 1760 INPUTf1:A\\CLOSE41 1800 IF A<N THEN 1600 1840 PRINT \\ PRINT \\ PRINT G$;G$;G$;GS;G$;G$;G$;G$;G$ 1880 IF F1>0 THEN 1960\\F=F-10000 1920 REM NOW READ IN THE DATA CONTAINED IN THE LAST THREE 1960 P4=0\\PS=O\\P6=0\\X=-108.393\\Z1=0 i 2000 FOR I=3 TO 1 STEP -1\\B=N-I\\C$="TH"SSTR$(B) 2040 FILET 1:'RXA1:"SC$\\FOR J=1 TO 5\\ INPUT 81:T(J)\\NEXT J j 2080 FOR K=1 TO 64 2120 IF K=16 THEN 2160\\INPUTJ1:D(K) i 2160 NEXT K 2200 CLOSEli 2240 REM NOW CORRECT THE DECIMAL POINT ON THE INPUTS. 2320 FOR J=32 TO 64\\D(J)=D(J)/100\\NEXT J ~ 2360 D(64)=D(64)/10 2400 REM NOW PRINT GUT THE THREE SETS OF DATA. 2440 PRINT \\ PRINT-C$r"R =";Rrr; 2480 FOR J=1 TO 5\\ PRINT T(J);\\NEXT'J\\ PRINT 2520 PRINT D(23)/10;\\FOR K=32 TO 64\\ PRINT D(K);\\NEXT K\\ PRINT 2525 REi! CORRECTION FACTORS 2526 REM RTD'S 2530 FOR J=32 TO 61 2532 READ F4 2540 D(J)=D(J)+F4 2545 NEXT J 2550 REM MENSOR 2555 D(64)=D(64)*1.00110-0.310 2675 REM ARE THE RTD READINGS IN RANGE??T? h

, p Paga 46 Q )g 6 D TABLE 10 (cont'd) C0tfPUTER PROGRAM USED FOR DATA PROCESSING 2680 Z=0\\E=0\\Y=0\\3=0\\T=0\\G=0\\H=0\\H1=0 2760 FOR J=32 TO 55 2800 READ F4 2840 IF J < 44 THEN 2960 2880 IF J >47 THEN 2960 2920 GO TO 3200 2960 IF D(J)<40 THEN 3040 3000 IF D(J)<150 THEN 3200 3040 PRINT \\ PRINT 'RTD ";Ji' READS OUT OF RANGE AT 'iD(J); 3080 PRINT ' DEGREES F. IT HAS BEEN SUPRESSED FROM THE CALCULATION 'l 3120 PRINT 'AND THE WEIGHTING FACTORS HAVE BEEN ADJUSTEl) ACCORDINGLY." 3160 F4=0 3200 E=E+F4\\Z=Z+D(J)*F4 3240 NEXT J\\ RESTORE 3280 REM NOW CHECK AND AVERAGE THE DEW PROBES. 3320 FOR J=56 TO 61 3360 IF J=58 THEN 3630 3400 IF J=59 THEN 3680 3440 IF D(J)<65 GO TO 3520 3480 IF D(J)<153 GO TO 3640 3520 PRINT \\ PRINT ' DEW PRODE ";Ji READS OUT OF RANGE AT 's D(J); 3560 PRINT DEGREES F IT HAS BEEN SUPRESSED FROM THE CALCULATION." 3600 D(J)=0\\ GO TO 3680 3640 G=G+1 3680 NEXT J 3720 D1=(D(56)+D(57)+D(60)+D(61))/G 3760 X=X+D1/3 l 3800 P6=P6+D(59)/3 l 3840 P4=P4+D(64)/3 3880 P5=PS+D(23)/30 3920 REM NOW CALCULATE THE AVERAGE CONTAINMENT TEMPERATURE 3960 E=E+F4\\Z=Z+D(J)*F4 4000 Z=Z/E 4040 Z1=Z1+Z/3 4080 NEXT I 4120 REM NOW CONVERT THE DEW PROBE CAVITY TEMPERATURES TG DEU 4160 REM POINT TEMPERATURESrAVERAGE THE FOUR AND CALCULATE 4200 REM THE PARTIAL WATER PRESSURE 4480 T=42.GOS1+.752944*X.0004115*X**2.OOOOO722*X**3 4520 X=T-69.9998 4560 Y=.362625F.01239153X+.00019115*X**2+.00000157*X**3 4600 Y= INT (Y*1000+.5)/1000 4640' REM NOW CALCULATE THE AIR PRESSUREr VC PRESSURE, 4680 REM DRY VC PRESSURErAND THE AIR MASS. 4760 P1=13.9247+.0131766*(PS-260.441) 4800 P2=(P4*.4912)-P1 4040 P3=(P4*.4912)-Y 4880 M1(R)=P3*060000*144/(5'3.35*(459.69+Z1))

Pag 2 47 (D tb O TABLE 10 (cont'd) COMPUTER PROGRAM USED FOR DATA PROCESSING-, 5120 REM NOW CALCULATE THE LEAK RATE FOR THE ENTIRE TEST 5160 D2=R\\IF R<3 THEN 6280 5200 Sl=0\\S2=0\\A3=0\\A4=O\\A5=O\\A6=0\\A7=0\\A8=0\\SO=0 524u FOR I=V TO D2 5280 So=SO+1 5320 Si=Si+M1(I) 5360 S2=S2+.25*SO 5400 NEXT I 5440 SO=0 5480 Al=S1/R 5520 A2=S2/R 5560 FOR I=V TO D2 5600 SO=SO+1 5640 A3=A3+((50*.25-A2)*(M1(I)-A1)) 5680 A4=A4+((S0*.25-A2)**2) 5720 AS=A5+(M1(I)-A1) 5760 A6=A6+((S0*.25)**2) 5800 A7=A7+((M1(I)-A1)tSO*.25) 5840 A8=A8+((M1(I)-A1)**2) 5860 NEXT I 5920 A=A3/A4 5960 B=(((AS*A6)-(A7*S2))/(R*A6-S2**2))+Al 6040 S3=((1/(R-2))*((R*A8-A5**2)/(R*A6-S2**2)-A**2))**.5 6080 L1=(-2400)*A/B 6120 D3=R-2 6160 T9=(1.6449tD3+3.5283+(.85602/D3))/(D3+1.2209-(1.5163/D31) 6200 U=L1+2400*T9t(S3/B) 6240 IF V1=1 THEN 7320 6280 PRINT \\ PRINT \\ PRINT \\ PRINT,,'***********\\ PRINT 6320 PRINT "THE THIRD READING FOR THIS OUTPUT WAS TAKEN AT *; 6330 PRINT T(1)*100+T(2) 6650 PRINT 'THE TEST HAS BEEN RUNNING FOR*iR*.25;" HOURS." ~ 6720 PRINT \\ PRINT 'THE AVERAGE READINGC FOR THE LAST 15 MINUTES *; 6760 PRINT 'WERE..............' 6000' PRINT \\ PRINT TAB (5),'OUTSIDE TEMPERATURE.....*iF67' DEGREES F.* 6840 PRINT \\ PRINT TAB (5),"OUTSIDE PRESSURE........";Pli" PSI." 6880 PRINT \\ PRINT TAB (5),'UC AVERAGE TEMPERATURE..*iZ1;' DEGREES F.' 6920 PRINT \\ PRINT TAB (5),'VC DEW POINT............";T;" DEGREES F.* 6960 PRINT \\ PRINT,'VC GAUGE PRESSURE......."iP25" PSI." 7000 PRINT \\ PRINT TAB (5),' PARTIAL WATER PRESSURE..";Y;' PSI.* 70~0 PRINT \\ PRINT TAB (5),"UC DRY AIR PRESSURE.....";P3;' PSI." 7080 PRINT \\ PRINT.*VC AIR MASS.............";M1(R);' LBM.* 7120 PRINT \\ PRINT " LEAK RATE'0VER THE ENTIRE TEST IS..*; 7125 PRINT Lii' PERCENT /24 HRS." 7200 PRINT \\ PRINT 'THE UCL LEAN RATE

i 7220 PRINT U;' PERCENT /24 HRS.'

7200 IF R<97 THEN 7620 7300 V1=1\\V=R-95\\R=96\\GO TO 5200

P gn 48 D

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SEPARATE ACCOMPANYING

SUMMARY

REPORT OF TYPE "B" AND "C" EVENTS SINCE THE JUNE 1977 TYPE "A" TEST SEPTEMBER 1980 YANKEE ATOMIC ELECTRIC COMPAhT R0WE, MASSACHUSETTS 01346 i Prepared By: M CL h n i Reviewed By: ./ 2 2r & h Plant Reictor Engineer Approved By: 7 ) f 474 g.4 [. HUO i Plant Superintendent e I 9 ,-,,,y-.

l Page 1 In the interval between the June 1977 Type "A" test and the September 1980 Type "A" test, all Type "B" and "C" vapor l container penetration barriers subject to testing under l Appendix J to 10 CFR 50 were tested at accident pressure on a two year basis (vapor container personnel hatch on a six month basis). During that time, eight Type "C" failures occurred. In addition, two Type "C" test periods exceeded the 24-month maximum allowed. All ten events were reported at the time and are summarized in Table 1. Copies of the Licensee Event Reports are also attached. There were no events concerning Type "B" tests during the interval. 1 1 l l t O

TABLE 1 TYPE "C" TEST EVENTS, JUNE 1977 to SEPTEMBER 1980 LER # SYSTEM BARRIER DISPOSITION 77-44 VC Pressure Sensing / Service Water TV-211/TV-408 TV-211: Underwent seat and disc machining TV-408: Diaphragm replaced 78-010 Post Accident liydrogen Vent ilV-SOV-1 Cleaned internals; replaced rubber seal 78-034 Neutron Shield Tank Sample TV-207 Cycled under pressure 79-05 Service Water TV-408 Valve seat cleaned 79-14 Post Accident liydrogen Vent CA-V-688 Cleaned internals 79-27 Post Ac'cident flydrogen Vent ilV-SOV-1 & 2 Cleaned internals 79-29 Post Accident liydrogen Vent ilV-SOV-1 & 2 Cleaned internals 80-13 Steam Generator Blowdown TV-401D Foreign material removed 78-09 Post Accident liydrogen Vent ilV-SOV-1 & 2 Missed surveillance performed 79-20 Main Coolant Drain VD-TV-202 Missed surveillance performed W m

A ,y i J..; a. c ;.,a.a A u s n.u - -.a..Q.-. d.u' id \\ ", ..as,,. 1e age 3 t u r c,. j

I'.

.b u. l .i f 1 %. t. YANKEE ATOMIC ELECTRIC COMPANY c '. :<S ' ' '- 4, Ydp"N i... .. e.. 4' Rowe,Mossochusens 01367 "Tr v m ~. S. a v September 16, 1977 q, .. b 't. ..- s ~t!: (s, q, -j- .'p, i ~;.I -r p .V. _e= ,4 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Connission p Office of Inspection and Enforcement Region I "A

I. ;

~h.. 631 Park Avenue i 'A;r ~.t King of Prussia, Pennsylvania 19406 u 1 2r'C

Subject:

Reportable Occurrence 50-29/77-44/03L L ,,p Failure of Vapor Container Isolation . 'f",

t4.

Trip Valves TV-211 and TV 408 to Seat '.t.. ;,. 1 .. g c 7;

Dear Mr. Grier:

w i. s %._ .. '1 ' pl In accordance with Technical Specifications, Section 6.9.4.b, the E, - "10 attached Licensee Event Report is hereby submitted. ' h 4,- [. ].;;' Uz Very truly yours, -gn;1 ....M.@ An s b.'% h d ll la M . 1,. MJ j f//. nd** 4 /Ap IIerbert A. Autio f.' d Plant Superintendent (,',rd +m 1

g

!.2. EIN/mid .s ?57]:. V-i h. ify

Enclosures:

, p . T I 0y ec: l30] Director, Office of Ir. Section and linforcement - ;i I ~ ' J' U.S. Nuclear Regulatory Cocmission I.- j Washington, D.C. 20;5, <e ' '9

.g o

[3] Director, Office of 61nago,ent Infonnation 6 Program Control 3'O U.S. Nuclear Regulatory Commission l.'i') Washington, D.C. 20555 j t g. i D ) s, r. 1 sv -.-g ( s e'l . ].. ~ y E,^ i u,..', .Q b. .q W f. l s 's's..."... L., c 4 ,.L l I ~ ~'~P a-

L-I_ .m._. ..a.,. + -- Page 4 l f II.R 77-41/031. e s l' I UCENSEE EVENT REPORT t - D cowinot eLocx I I III I I pua nau u ,==3 i '. - i a i' 'T"' 'C:" ',"ll' ics u e. e..- iToi ' x i A k lx la 111 10101-10101010101-10 l 0 I I 4 l 11111111 in 13 I Oo 14 is as as ao 3 m k.' 'Yl' Eu*n"cs' oceae,aume a sw e se L-,' "e QCDN'T l l l W y l0 l 5 l 0 l-.l 0 l 0l 2l 9l l0 l 8 l 1 lT,f 7 l 7l l0l9l7lhe7l*l l'

cArnoon,

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5. 7

[ EVENT DESCPPTON DE l During Class C testing of vah 's TV 211 and TV 408 it was observed that the valves' l J, f .] 7 89 co 3 i3 @ l 1eakage were greater than the accaptable limits. These are the only trip valves l ( j 7 e9 Lu + - 0 l associated with their respective piping. Both the valves had wor 7: gaskets replaced l i [' l 7 e9 m (1 l en 11/29/75. Seat and disc machining (TV-211) and diaphragm replacement (TV-408) werej 89 eo j d I proposed to reduce the leakage. (1.ER 77-44/03L) I r ea 4r i 7 ee r,rw cauw cm=>.,, ec-i eauesre,=, 'e'. gtj t _,1DJ [Ej l Vl Al !.lV j E l X l [LJ l Ml 1l 2l0 l g ,, g' ' p j i acos cca:e co.esows%, coes mute csson 4matos 6 o .t 7 89 10 11 12 17 43 44 47 46 E.. Q.'} Y. CAUSE CESC9pfCN E. l Two Masencilan Trip valves Fbdel 138-RBS-11 (TV-211) and hbdel 138R-16 (TV-408) l ,. e !y,.' d, 7 89 80 @ l exceeded their allowable leak rate because of worn seat and disc and a deteriorated [ s. i e9 oo ,I .I @ l dirohracn respectivelv. After TV-211 underwent seat and (Cont'd in Additional r/;torsil l 51 L raw,, uss co ce [..; i } q'; 8 LGJ ,1010101 I N/A l [B J l N/A l l a-s'arue t powte of se status es a sar pecovsa, otsceptoe .G = .g 7 8 9

10 12 13 44 43 46 60 i.g y acew.tv cowit=v 4. 'S EE Y

'El E' l i ' '971" l [- ~ I

s>::s 7 8 9

10 11 44 43 80

4'l PERSONNEL EXPOSURES

,e uww. c..c.e,c. ?j u l') 1010i Lt.J l N/A l ,. : i 7 89 11 12 13 80 ( g PEASCNNEL NJURIE5 -1 bq'd ' E l d 0l Ol l N/A l =uunt a et scoetc.s / 89 11 12 60 J ~ h OFF5ffE CONSEQUENCES T 4 DE I N/A I .t 7 s9 m a 80 i D. m m,D) LOSS OR DAMACE TO FACILITY u d

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S: f *PG DikamefCN a I E L;J l N/A =' ,' h 7 89 10 BC PUBLCffy ,.f HI N/A l 7 89 ed 40cffCNAL FACTCAS @ l (Cont. Cause Description) disc machining and the diaphragm of TV-408 was replaced l 7 89 80 . l*' [ H l both valves were satisfactorily retested. l 7 89 60 3 NAME IdWIM I. SIV - PHONE (413) 625-6140 see e.e..., y., 7,

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1 _j Pase 5 ~f-a & YANKEE ATO?AIC ELECTRIC 00fdPANY m, Yape?,N Rowe,Mossochusetts 01367 uxney April 13, 1978 -e Mr. B. H. Grier, Director U.S. Nuclear Regulatory Co::nission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 50-29/78-010 Hydrogen Centrol System Sticking Solenoid '~alve b

Dear Mr. Grier:

In accordance with Technical Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. Very truly yours, ut?F d~W Herbert A. Autio Plant Superintendent EUVmid

Enclosure:

cc: [30) Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Camission Washington, D.C. 20555 [3] Director, Office of Management Information 6 Program Control U.S. Nuclear Regulatory Comission Washington, D.C. 20555 9 e

( u.ns LICENSEE EVENT REPORT Paga 6 CONTROL 8 LOCK: l l l l l l lh (PLEASE PAINT OR TYPE ALL REQUIRED INFORMATIONI i e foITl lM l A lY lK lR l1 l@l0 l0 l-10 l0 l 0l O! 0l -l 0l 0l@l4 l1 l1 l 1l 1l@l-l lg i t 9 tlCENSEE Coot 14 IS tiCENSE NUMsER 25 26 tiCENSE TYPE JQ $7 GAT 58 sE$$ ll l@l0 l5 l0 [0 l0 l0 l2 l9 l@lo l3 l1 l,1 I; lg ]@lnl4 l1 l3 lv l4 l@ ? 8 to 61 ocCnET Nuve ER 64 67 EVENT CATE '6 75 REPORT C ATE $3 EVENT DESCRIPTION AND PROB A8LE CCNSECUENCES h Io ial i See attached narrative. i 10131 l l Io I4l l J \\h l go + - T l'TITI l M h6\\ .- 4 -- I lo (6 l l 'l l o 171 I I Iois i I __.J so ? ss

- $ECo ' stsCi$E COMPONENT Coof SUS c'E

$U E 'oE C loisi I s i n l@ LLJ@ (Lj @ l v l A l t i vl F I x l@ l F l@ [Qj @' StoVENTlat . OCCURRENCE REPORT R EV,5loN EVENT YE AR REPeav CooE TYPE No. @ ;LER moI 71 si l-l I o f I-No.l of l/l 1013I IL I l-l LO_] ';;g ,, 21 22 23 24 06 27 28 29 J3 , 31 32 xN A oN oNPLANT VET MOURS S e IT roA 8. SUPPtiE M NUPACTUAER V IB l@l Zl@ lZ l@ l Zl@ l0 10 l0 la l l Ylg l N[g l L j@ lAl5l3l5l 33 34 05 36 37 40 el 42 43 44 47 E CESCRIPTICN AND CCRRECTIVE ACTICss h CAu: g l See attached narrative. I i L' l.' J l I L'_L1j l I LLi.1.] I 'l LLl 4 ] I -.I 7 8 9 30 .e STA us %#CwtA ETHER STATUS otSCO RY oISCOVERY oESCRIPTioN li 151 l E l@ l1 l0 l0 l@l N/A l lBlgl N/A l l A!TiviTY Co'4TE NT l L'lSJ W, sto or aELEasE@ 12 l@l N/A AucuNr or CTiviTY @ l toCATion or REttAsE @ l ator l N/A l PEasoNNEl e PosdAts CEsCaiPrioN @ Nuussa TvPE I t 171 1010 l 01@l I l@l N/A l asoNNE t,N,u'n',ts ,i otsCaiPrioN@ Nuvata 1010101@l N/A I W'N ks,5p oa o$,y,do rac>urY @ I:I@l N/A l i., 7 8 9 to SO ttiudf @oEsCRePrioN L; l N/A I 1111111ll111l 2 n rt.J1 iu 60 69 80

Pag 3 ? LER 78-010/03L-0 'lankee Atomic Electric Company Yankee - Rowe 050 029 EVENT DESCRIFTION AND P'ROBABLE CONSEQUENCES At 1520 hours, during nomal operation in operational hbde 1, the containment hydrogen control system containment isolation valve (HV-SOV-1) failed to seat properly after actuation of its solenoid operator. The solenoid operated valve failed to hold the 32 psig test pressure for any length of time, while perfoming leak ate procedure OP-4702, Attachment Y. HV-SOV-1 is required to be operable while in bbde 1 by Technical Specification Section 3.6.2, "Contain-ment Isolation Valves". Bis is the first occurrence of this nature .ssociated with the valve. A redundant solenoid operated valve is not part of this sample line. H e operation of the Hydrogen Venting System requires HV-SOV-1 to be in the open position. As such, the valves inability to seat properly did not reduce the system's capacity to perfom its intended function. Valves down stream of HV-SOV-1 were successfully type "C" tested prior to the occurrence, therefore vapor container integrity Based upon the above discussion the health and was maintained. safety of the public and plant personnel were not adversely affecte'd. CAUSE DESCRIPTION AND CORRECTIVE ACTIONS _ It has been determined that the failure of HV-SOV-1 to seat properly was caused by a build-up of oil and dirt throughout the valve intemals. HV-SOV-1 is a 1-1/2 inch; Atkomatic Valve Co., Inc.; Cat. No. 32861-CV; G Serial No..254334; 3000 psig rated; stainless steel solencid valve. He valve internals were cleaned and inspected and the rubber seal replaced in kind. Petest of the valve, after being re-installed, was satisfactorily completou at 1059 hours,hhrch 16, 1978. No abnormal conditions have been identified which could have caused the buildup within the valve. Herefore, further corrective actions i have not been proposed or implemented at this time. PLAVT OPERATIONS REVIEN CGMITTEE RECGfENDATIONS [ h is occurrence was reviewed by the Plant Operations Review Committee at bbeting No. 78-13 on abrch 24, 1978, with no additional comments ] or recommendations. \\ t

k Paga S 1 l Q'ANKEE AT0f.1IC ELECTRIC C0fo1PANY Rowe, Massachusetts 01367 YA,uxes -= January 4, 1979 Mr. B. H. Grier, Director U.S.~ Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19306

Subject:

Reportable occurrence 150-29/78-34IO3L-0 Neutron Shield Tank Sample Line Trip Valve h TV-207, Failed Type C Test

Dear Mr. Grier:

In accordance with Technical Specifications, Section 6,9.4.b, the attached Licensee Event Report is hereby submitted. Very trufy yours, hfur u Herbert A. Autio Plant Superintendent RLB/mid

Enclosure:

~

cc: [30] Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [3] Director, Office of Management Information & Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RT: 17-R-94 013 IMS: D-96-01-91 w? 8 e

ravvw LICENSEE EVENT REPORT Paga 9 con, TROL block: l l l l l l lh (PLEASE PZINT OR TYPE ALL REQUl:ED INFORMATIONI e i e @ lM l A l Yl K l Rl 1 l@l 0 l 0l-l 0l 0 l 0l 0 l 01 - l 0l 0 !@l 4 l 1l1 l 111 l@l l l@ > I

9 LICEN5EE Co0E le 15 uCENSE NUM8EM 24 26 uCEN5E TYPg 40 SF CAT S4

" ] l L )@l 01 510 l 0l01012 l 9l@l 112 I a ls ! 71@l0 l 110 l 417 l 91@ uR 7 8 60 El coCKET NuvSER Ga 69 EVENT QATg 74 75 REPORT DATE 80 EVENT DESCRIPTICN' AND PROBABLE CONSEQUENCES h foTTl Fhile performing a Class C test of trip valve, TV-2'07, valve leakage exc1 o a leeded T.S. 3.6.1.2.b. The plant was in Mode 5 and < 300 psie. The linel io pi pontaining the trip valve was isolated by another valve during the test I goisiland is normally isolated during operations. Based on this discussion theI lo is 1 Ire was no effects upon the public health and safety. l o 7 I I I FBTTI I

O 1

E Co E SL8C E COMPONENT CooE Sus of 5 E

l0l9l l S l Dl@ IX l@ lX l@ lV l A! L l VlE l XI@ I F l@ y @ '

7 s 9 10 11 12 13 ta is 20 StoufNT!AL OCCURRENCE REPORT REVI33cN LER EVENT YE A R R EPoRT No. CooE TYPE No. @, ass,mo1 718 I l-l 10 1314 I l/l lo I 31 l LI l-l I of g u ,,,,, 21 22 2J 24 26 27 28 29 33 31 32 Abhf CNPLANT MET HOURS SS IT Fo 9. Sus *L E MAN FACTURER KN G,1Xl@l2l@ l Z 1@ II l@ l 010 l 010 l ,lN l@ lNl@ lL l@ l M ll l 2 l 0l@ 33 34 ab M JJ 40 41 42 43 u 47 i CAUSE DESCRIPTION ANo CCARECTIVE ACTIONS h i ( iiioi[The cause of this event was suspected to be foreign material under the I IMasoneilan one-half inch valve (SR #P-72987) seat. The valva wne evelnA I i i lunder pressdre and then retested. The Class C retest was satisfactorv. i = t l EI Ei So 7 4 9' us % power oTHER STATUS otSCo RV oISCoVERY DESCRIPTION l @ 5T[cj@ 10 l 0lo l@i NA l [3J@l Routine Surveillance l '5 ',1Tiv,TY CsTE~T AucuNT or,CTiv,Tv @ l toc, Tion or REu,3E @ <tu Asio orRE u Ast NA l NA l 8 Izj @ [1J@SE, l ,iRsoN,'a rx,os oEscRIPTioN @ i ~uvoER Tv,E l FiTil l0 lo I o l@l z l@l NA EnsoN~EL t~,uns otscRipflo~ @ N A ~uve E R l 1T1 1101 olo l@l 30 I A9 it 12 i ~

e55 oF oH oavAGE To FACILITY h I

."YPE oESCniPfloN v l til@l NA i 80 2 a 9 10 PUULICITY NRC USE oNLY otsCRIPTioN t r essvEn@l l1,J NA I llll111111IIII 2 o 68 69 80 I eg .0 om O_ u-m m

Page 10 I AN((EE AT0f'ilC El.ECTRIC COMPANY y Rowe,MassachuscIts 01367 .Ya'm x. F, se March 16,1979 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 50-29[/ 79-05 }03L-0 TV-408, Service Water From VC 1 solation Valve Fai'ed Type C Test

Dear Mr. Grier:

In accordance with Technical Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. l' ' Very truly yours, 1 Herbert A. Autio Plant Superintendent RLB/mid

Enclosure:

cc: [30] Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [3] Director, Office of Management Information & Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RT: 17-R-04-013 IMS: D-96-01-91 Mi) hJ'

LICENSEE EVENT REPORT Page 11 ' CONTROL OLoCK: l l l l l l lh (FLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 2 ' M lA l Y lK l R l1 j@l0 l 0 l - l 0,l 0l 0 l 0 l 0 l-l 0 l 0l@l 4 l1 l Il1 l 1l@l l lg 1' UCENSEE CODE 14 IS LICENSE NUMUUt 25 26 LICENSE TYPE JG $1 4A T 58 dy C0:EE7 iOIiI $ UnN l L}@l0 l 5 l 010 I Ol n l2 l 9 l@l n i 211 l 4l 7 l o @l 0l 3 l Il 6 l 71 7 8 . 60 61 DOCAET NuvtlER 68 G3 EVENT DATE 74 7% REPORT D AT E 80 ' EVENT DESCRIPTION AND PROS ABLE CONSEQUENCES h ! O 121 lWhile performing a Type C test of TV-408, service water from VC Isolati; go,3, ion valve the leakage exceeded T.S. 3.6.1.2.6. A similar event was report l There were no a I to,,,ied as LER 78-34. The actions required by T.S. were met. ldverse effects upon the public health and safety. I go,3, ~ l _l O l6 l I I 'ITITl l l _'l O 18 l l So OE CODE SueCO E COvPONENT CODE SUSC DE SU E

oisl lS l Dl@ l Xl@ lX l@ lV l Aj L l VjE l Xl@ y@ lD l@

7 8 9 to it 12 33 18 te 20 SEQUENTi AL OCCURRENCE REFORT REVISION _ EVENT YEAR REPORT NO. COOE TYPE NO. @ R POa7 l 7l9 l l_l l 0l 0 l 5l l/l l0 l 3 l l Ll l-l l 0l LE R/RO 27 22 23 24 26 27 28 29 30 31 32 EN ACTC 0 PLAPT MET MOURS SS iT POR 8. SUPPLIE MAN FACTURER ^ ' [X_J@l l@ l Z l@ lZ l@ l 0 l 0l 0101 (({,.J @ INl@ l Al@ l M l 1l 2 l Ol@ 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION dND CORRECTIVE ACTIONS [iiq0i lThe root cause of this event was foreign material under the Masoneilan fi Lg g jour inch valve (Model No. 138-16, SR #P-72985) seat. The valve seat was I was satisfactory. I g l cleaned and the valve retested. The retest i I " L' 1.4 ! I 80 7 8 9 STA 3 % POWER OTHER STATUS 015 O RY DISCOVERY DESCRIPTION ,li is l l E l@ l0 l 9 l 6 l@l NA l l B l@l Surveillance Test l 80 22 n 44 45 46 A!TiviTy Av0VNT Or ACTiviTv @ l CO TENT LOCATION OF RELE ASE NA l NA l r.EtE AsEO 05 RE tr AsE [l1161 l Z l @ y@l PEnsONNEt ExPOsSES NUMBER TYPE DESCRIPTION 10Inl0_l@ W @l NA l i 7 PEnsONNE t iN7UniEs NUv8 E n OESCRtPTION l 0 l0 l 0 l@l NA l i 80 7 9 11 12 Tpfgo L 5 Of On DA TAG TO F ACILITY l ITTil i Z l@l NA 7 8 9 10 W l NA l l l l l l l l 1 1 1 1 1 l ;, t$tVE"@DESCnIPTION 7 0

Pag 2 12 YANKEE ATOMIC ELECTRIC COMPANY Rowe, Massachusetts 01367 YAux, se, May 11, 1979 ~ Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Subj ect: Reportable Occurrence 50-2 9 3L-0 CA-V-688 Failed Class "C" est

Dear Mr. Grier:

In accordance with Technical Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. Very truly yours, ? *f-4f.4. & ~ Herbert A. Autio Plant Superintendent i EI21/mid

Enclosure:

cc: [30] Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Coc: mission Washington, D.C. 20555 (3) Director, Office of Management Information & Program Centrol U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RT: 17-R-04-013 IM3: D-06-01-01

r-o CoNrnetatoCiei I I I I I l@ (PLEASE PRINT CR TYPE ALL REoUIRED INFO AMATioNI i lM l Al Yl K lR l 1l@l 0 l 0l - l0 l 0 l 0l 0l 0 l - l 0 l 0l@l 4 l 1l 1 l 1 [1 l@[ l lg 9 UCENSEE COOL 84 IS

UCENSE NUMBER 2S 25 UCENSE TYPE JO S3 GAT Se t

E's l Ll@l ot s 1010 l o lo 12191@l 01411 12 l7191@l 0 l5 ll l ll 719l@ . 7 8 60 el DOCK ET NUMB E R 64 69 EVENT D ATE 74 75 REPORTQATE 80 EVENT DESCRfPTioN AND pro 8 ABLE CONSEQUENCES h lDuring normal operation, while performing containment type C test, CA-V-l O 2 l688 failed the containment leakage rate (T.S.3.6.1.2). Testing and repail O 3 iO gjfring the valve isolated the hydrogen venting system contrary to T.S.3.6 1 9

2. This is the first occurrence of this nature associated with CA-V-681 3

O 3 1. Redundant isolation valves exist for CA-V-688 and durine testing a mal - 8 O s (f5TTlIn is available to valve in the hydrogen venting system if needed. No advl iO9iierse effects to the health or safety of the public resulted by the event! "T E CODE $U8C E COMPONENT CODE 5e c'E SU E

IOTil i SID l@ l E l@ [Bj@ l VI A l LIV l ElX l@ [F_j@ QJ @

7 8 9 to 11 12 13 16 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LE EvtNT VE A R REPORT NO. CODE TYPE N O. @,ajg*ttRO17 19 I l-l I O I 114 i L<J l 013 I ItI L-J 10 I 28 22 23 24 26 27 28 29 30 34 32 N A CN O PL NT MET NOURS s8 i POR S. SUPPLit MANUFACTURER C" T K Bl@LZ_J@ l2l@ l 21 @ 10 1010101 L13fJ@ W@ lAl@ IV I 113 I s l@ i 34 JS 36 37 40 41 42 4J 44 47 33 CAUSE oESCRIPTloN AND CORRECTIVE ACTIONS h g lThe root cause of this occurrence was crud on the valve's seatinc surfacI [ g les. CA-V-688 is a 2" gate valve; working pressure 800 nsi-tenem+nra I ,, ;850*F;. number SW-12148; manufactured by Henry Vogt Machine Co. The valve l g g ;was isolated, cleaned, retested and returned to service. The time out of 1 , service yas 6.25 hrs. No future corrective actions are necessary. l 80 T g g 'sT % POWER OTHER STATUS CisCO RY DISCOVERY DESCRIPTION

liIsl(E_j@ l019l 8l@l N/A l

[3_,j@l Surveillance Test I 'dfiviry CO4 TENT EELEASED OF RELE AsE AMOUNT OF ACTIVITY LOCATION OF RELEASE l N/A I l N/A l [ITIIl [2 ] @ [_Z.j@MEs PERsONNEt Expos DEseRiPTiON @ ~uM.ER TvPE l 010 l Ol@[2 j@l N/A I i 7 ' PERsONNEt iN;URiEs otsCRiPfiON@ NuvaER ET_] 1010 I Ol@l N/A I 80 7 ti 12 TYPE CEsc PT ON i J ll_J@l N/A l 80 7 8 9 to ts5UE @ DESCRIPTION N/A l l l l l 11 I I I I I I II, lN_J l 2 o 65 49 80 3 7 3 3 10 c.) e n v

s Fage 14 &.... YAflNEE ATCUIC ELECilllC CCUPANY Ya;,u,, x., h. Rowe, Massachusetts 01367 as December 4, 1979 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement ~ Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 50-29/79-27303L i HV-SOV-1& 2, Failed Surveillance and Failed Type "C" Test Mr. Grier: In accordance with Technical Specifications, Section 6.9.4.a, the attached Licensee Event Report is hereby submitted. Very truly yours, e b614 d2 I Herbert A. Autio Plant Superintendent LDF/amt

Enclosure:

cc: [30] Director, Office of Inspection and Enforcement c U. S. Nuclear Regulatory Commission Washington, D. C. 20555 [3] Director, Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 [14] NSARC Chairman 1 [1] Manager of Operation Quality Assurance g Yankee Atomic Electric Company

control BLOCK: I l l I I l Ih (PLEASE PRINT c3 TYPE ALL REIUIRb MATioN) o 1 6 l M j6 l Y lK l Rl1 l@l 0 l 0 l-l 0 l 0 l 0 l0 l 0 l - l 0 l 0l@l4 l1 l 1l 1l 1l@l l l si car se @ i ucENsE NuveEH 2s 2. LICENSE Tv,E 40 r 9 uCENsEE Cont is is y C Ts $$Rc{ l 1 l@l 0 l 5 l 0 l 0 l 010 l ~2 I 9 l@l 1 l 110 l Sl 7 l 91@lil?Iol4l7Iol@ klYl I 8 60 El OOCKET NUMBER 63 b) EVENT OATE 74 7s HEPORT OATE 80 EVENT DESCRIPTION AND PRoR ABLE CoNSEoUENCES h d lDuring plant startup in Mode 3 while performing surveillance on the Postl Accident Hydrogen Control System HV-SOV-1 and 2 failed to seat properly; This is a violation of T.S. 3.6.2. The valves were c1 caned, retested, al i. i o, ind passed surveillance required tv T.S. but failed Type C test, T.S.3.6.l o 3 l l1.2.b. Since a manual isolation valve was closed before and after the tei _ o 3 iol,jist as required by procedure, containment integrity was maintained so the; io,,, ire were no adverse effects to the public health and safety. l 80 ~ C QE COE SUSC E COYPONENT CO OE COOE 5 E 19 l 5:l@ l E l@ [B_J @ IV l Al t i VlE l X l@ h_J@ l Dl @ B O 9 7 8 9 to 11 12 13 18 89 20 SEQUENTI AL OCCURRENCE REPORT REVf$ TON LE R/RO EvtNTvEAR RE' ORT NO. COOE TYPE N O, @atg; I 71 91 [-J l 0121 71 lel 10131 l LI l-l 1 01 _ 21 22 23 24 26 27 28 29 30 31 32 u AK N AC O ON PLA T MET HOURS S8 T FOR 8. SUPPLIE M ANL'F ACTURE R DLj@l F l@ LIJ@ [2_J@ l O l0 l 01 nl (N l@ lNi@ l Nl@ l A l 3l 3 l5 j@ W JJ 34 Js 36 31 40 el 42 43 44 47 CAUSE DESCRIPTioqAND CORRECTIVE ACTloNS h [ lilollThe root cause of the event was an oil and dirt buildup on valve intet ut ils. The valves are 1-1/2 in. Atkomatic Valve Co., Inc.; Cat. No. 32861-Ci i i V. The valves were cleaned and tested on 11/4/79. On 11/5/79 the valves I ,, I - g lthat f ailed Type C test were cleaned, retested and returned to service al g in 11/05/79. The requirements of T.S.3.6.3.2 and 3.6.2 were met. I 7 8 9 stANs

POWER OTHERSTATUS 15CO HV DtsCOVERY CESCRiPTION

, Ii is l l C l@ l0 l 0 l0 l@l NA l lB l@l Operator Observation l ACitvlTY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTivlTY LOCATION OF RELE ASE I n i I n rrm 12J @ Ld@l 80 7 8 9 10 11 44 es PERSONNEL f xPOsunts NOVR E R TYPE OESCRIPTION l0l0l0l@lZl@l NA l i 7 ,ERso~Na'iN;uns OEsCniP1,0N@. jololol@l NA l ~uvu n i x 80 9 11 12 ' LOSS OF On OAM AGE TO F ACILITY TYPE DESCniPilON NA l lZl@l 80 7 8 9 10 155UE"@DE CniPitON [fj_j l NA l l l l l l l 1 I l'l l I l 2 a n G8 69 80 7. 7 8 9 10 Lester D. French (413) 625-6110 ? PiloNE: o NAME OF PREPAnEn

kg3 16 QYANNEE ATOMIC ELECTRIC 00f,1PANY gh Rowe,Mossachusetts 01367 Yhase N -e December 6, 1979 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

ReportableOccurrence50-29d79-29/33L HV-SOV-1& 2, Failed Surveillanc,e Mr. Grier: In accordance with Technical Specifications, Section 6.9.4.a, the attached Licensee Event Report is hereby sub:aitted. Very truly yours, J. -h Herbert A. Autio Plant Superintendent LDF/amt

Enclosure:

cc: [30] Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 [3] Director, Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 29555 [14] NSARC Chairman [1] Manager of Operation Qoality Assurance y, My Yankee Atomic Electric Company

s e control 8 LOCK: l l l l l lh (PLE ASE P; TNT C3 TYPE ALL cECUIRE TNF MATl!N1 6 { i -l Ml A l YlK l Rll l@l0 l 0l-l 0 l0 l 0 l 0l 0 l-l 0 l0 l@l 4l 1 l 1l 1l1 l@l l l@ 7 9 LICENSEE CODE le 15 LtCENSE Nuv9ER 25 26 LICENSE TYPE JO 57 CAY 58 CL III r l' 3$$ l L )@l0 l 5 l0 l 0 l0 l 0l 2 l 9 l@l 11 11016 l 7 l9 @l1 l 2 l Ol 6 l7 l 9 l@ 7 8 60 El OOCK ET NUM8ER 68 63 EVENT QATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Firg1 l During plant startup in mode 1 while performing OP-4216 testing o f the PI r5Til1ost Accident Hydrogen Ventine System HV-SOV-1 and 2 failed tn Rent n r nn el 'ffTT11riv. This was a violation of T.S.3.6.2. 2 similar occurrences were repori firTTl I t ed a s LER 7 8-10 and LER 7 9-2 7. Since a manual isolation valve was closel FOTirl I d before and af ter the test as reauired by procedure, containment integri lOl lIity was maintained so there were no adverse effects to the public health; F5Ts1 I and safety. I 80 T 89 CE CO E SUSCC E COMPONENT CCCE SU8C CE SU E fiTel iS l El@ y@ l3 l@ lV l Al L l VlE l Xl@ l Xl@ lD l@ y 8 9 to 11 12 13 18 19 20 SE QUE NTI AL OCCURRENCE REPORT REveslON g n,gO EVENT YE AR REPORT NO. CCCE TYPE NO O,a(j, Post,1 719 I l-l 10 l 2 l 9 l l/l l0 l 3l l Ll l_l l 0j _ 21 22 23 24 26 27 28 23 30 31 32 Mb NOURS S 8vlT FOR 3. $U PLIE M ANUF A TURER Ah0N CNPLANT 7K N D I X lgl34F lg l35 2l@ lZl@ l 0l0 l 0] 0] lN l@ lNl@ lN ]@ l A l 5 l 3 l5j@ 36 37 40 41 42 43 44 47 33 CAUSE DESCRIPTIO (AND CORRECTIVE ACTIONS h , li lo ; lThe root cause nf the event was an oil and dirt buildun on valve in t e rn al r (_L] ! 1 s. Th e va lve s a re 1 - 1/ 2 in. Atkonatic Valve Co. Tnc.- Cat. Nn. 32861-n1 i s t u l. The ivalves were cleaned. inspected and returned to service on 11/o/70.1 I FTTT1 [ The reauirement s of T. S. 3. 6. 3. 2 and 3. 6. 2 were net. I 1 14 l I s 80 7 8 9 ST S % POWE R OTHE R STATUS disco RY DISCOVERY DESCRIPTION l C l@ l 0 l5 l 5 l@l NA l [B_j@l operator observation I f s 'S a Aa,v,TY CCbT CELEASED OF RELE ASE AMOUNT OF ACTivlTY LOCATION OF RELEASE LusJ l z I @ LLJ@l NA l l NA l 7 8 9 to 11 44 45 80 PER50NNEL f xPO5VHES NUM6ER TYPE DESCRIPTION li l 21 1010101@l Z l@l NA l ,En50NNEl',N2tLS NUVRE R L ESCRIPTION I l o l 010 l@L. NA i a 80 8 9 11 12 LOS5 OF 09 OAMAGE TO f LCILITY C43 TYPE DE SCRIPTION %/ M', o [_z_J@l NA l 80 7 8 9 10 DESCRIPTtON ISSUE"Ol LN_j NA I llllIll11II!12 2 n 69 80 7 7 8 9 10 (4131 625-6140 I# ster D. French pnoug: NAME oF PitEPAREn._

l o Pa63 18 Q YANKEE AT0f,110 ELECTRIC C0f>1PANY Yal,ux[,]es Rowe, Massachusetts 01367 pe July 30, 1980 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I l 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

LicenseeEventReport50-29f!0-13J i No. 4 S/G Blowdown Trip Valve, TV-401D, Type "C" Test Failure

Dear Mr. Grier:

In accordance with Technical. Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. Very 'truly yours, sua ad Herbert A. Autio Plant Superintendent I LDF/amt i

Enclosure:

[30] Director, Office of Inspection and Enforcement cc: U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [3] Director, Office of Management Information & Program Ccntrol U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [14} NSARC Chairman [1] Manager of Operational Quality Assurance Yankee Atomic Electric Company l f.4 RT: 17-R-04-pl3 l

~

l l

1.ll,tINacc c v tiv i ncrvne Para 19 control block: l l l l l l lh (PLEASE PRINT oR TYPE ALL REQUIRED INFoRMATION) 1 6 & i l Ml A l Y'lK l Rl1 j@l0 l 0 l-l 0 l 0l 0 l 0 l 0 l - l 010 l@l 411 l 111 l 1l@l l l@ 7 9 LICENSEE COOF. f4 15 LICENSE NUMBER 25 26 UCENSE TYPE Jo Si car 58 SC"c' lL ]@l0 l 5101010101219 I@l 0 l 6l 3 l 0 l 810 l@l Ol 7 l 3 l 0 I S o ? 8 60 61 COCKET NUMOE R 68 69 EVENT OATE 74 75 REPORT O ATE 80 EVENT DESCRIPTION AND PRO 8 ABLE CONSEQUENCES to 1012l l During a maintenance outage in dode 5 while performing a Class "C" Test ]

on trip valve TV-401D valve leakage exceeded T.S. 3.6'.1.2.b limits. This;

,o,3, go 9 j lis the first event of this nature. The trip valve is in the secondary syl and both primary and secondary system pressures were below 300 psi; go,3,, stem, Based on the above discussion there were no adverse effects on the puj-g o go, l g. l go!7; ;blic health or safety. l IOla i I so OE CODE S BC E COMPONENT COCE SU8 CODE SU E lSl Dl @ [E_j @ IB l @ IV lAll l VlE lXI@ lEl@ [D_l @ l0l9l 7 8 9 to it 12 IJ 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVtSICN LE RtRO EVENT VE A R REPORT NO. CODE TYPE No. Ogg I 810 I l-l 1011l3 J Ld I'013 l l Ll l-l l01 _ 21 22 23

24 26 27 28 29 30 31 32 KN AC ON ON PLANT MET HOURS SB IT FORNt 8.

S PPL1 MAN FACTURER lBl@lzl@ l Z l@ lZ l@ l 0101010 l W@ [N_j@ IN l@ lMlIl2IOl@ JJ 34 JS 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION *AND CORRECTIVE ACTIONS h ltl0llThe root cause of this event was foreien material under the valve seat. I lilijIThe valve is a Masoneilan 2" air operated globe valva. Tha vn 1 "a vns ist g golatec' and the material removed. The valve was successfully retested. N1 this time. l

g g further actions are planned at I

WI 80 7 8 9 ST S % POWER OTHER STATUS ISCO RY DISCOV ERY DESCRIPTION > W lGl@ l0l 010l@l NA l l B l@! Class "C" Test l A!TiviTY CORTENT LOCATION OF RELE ASE AMOUNT OF ACTIVITY I G. ELE ASED@OF RELE ASE l NA l l MA !Z Y 6 PERSONNEL EXPOSURES ITT71 l 0 l 0 l 0 l@l Z l@l NA l NUMBER TYPE DESCRIPTION 80 ' PERSONNEL INJUnlES NUUR E R DESCRIPTION l 10 l Ol 0 j@l NA i a 80 7 r. 9 11 12 l.'(.v.4 LOSS OF On OAMAGE TO FACILtTY b43 l 96 TYPE DESCntPTION v [uyj l Z l@l NA 7 8 9 10 NRC USE oNLY PUBLICITY r l lllll1IIIIIIII ISSUED DE SCRIPTION 300iDLfLM lSL - MA

k s a p r,, hga 20 j & YANKEE ATOMIC ELECTRIC COUPANY ]. Rowe, Massachusetts 01367 ANKEk March 22, 1978 Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportzble Occarrence 50-29,'78-009f03L-0 l Missed Surveillance

Dear Mr. Grier:

h In accordance with Technical Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. Very truly yours, h Herbert A. Autio Plant Superintendent RM4/mid

Enclosure:

i cc: [30] Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [3] Director, Office of Management Infomation 6 Program Control ~ U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1..%

g..,

8 e

a,.c euwa a. ~-LER 78-009/03L-0 '#~ # # ' LICENSEE EVENT REPORT Paga 21 CONTROL BLOCK: l' ] l 1 l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e B lMIAlYlKlRl1l@l0l0l-10l0l0l010l-l010l@l4l1l111l1l@l l l@ 3 4 .9 LICENSEE CODE 14 lb LaGENSE NUM6ER 25 26 LICENSE TYPE JG SF GAT Sd Eu% lLl@iOI 510101010 ! 219 l@l 01212 ll'l 718 l@l013 I? l' I 7 li l@ 7 8 60 6i OOCK E T NUMS E R 68 t> 9 EVENT OATE I4 75 REPORT OATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h I IOl2IISee attached I F6TTl I I ITTT1 1 I ITm I i LO_tsj i 1 10l71 1 I f5TTI I .O E CO E SUSC E COMPONENT CODE SUB dE Su fiTTl I S I E l@ [Lj@ IX l@ l 2 l ZI Z I Il Il Z l@ []_j@ (J_j @' 7 8 9 10 it 12 13 18 19 20 SEQUENTJAL OCCURRENCE REPORT R EVISION gg g.RO EVENT YE A R REPORT NO. CODE TYPE N O. @,aEg l217 18 l l-l l 01 01 9l l/l l0l3l lLl l-l l0l 22 23 24 26 27 28 29 3e , 31 32 K N ACT CN O PL NT MET HOURS SB t FOR B. SUPPL E MAN FACTURER [X_j@lX l@ lZl@ l Il@ l0 l0 l 01 0l l Yl@ lNi@ l Z l@ lZ l9 19 19 l( 33 34 35 36 31 40 44 42 4 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I liiOl*] See attached I LLDJl I ITTT1 I I LLL3_I I I fiTTI I e0 T 8 9 .4 5 % power OTHER STATUS 015 0 Y OtSCOVERY CESCRIPTION l 'st l E l@'l 0l Sl Sl@l NA l l Cl@ l Surveillance' Review I i s '8 A!TiviTY CO TENT LOCATION OF RELEASE REtEAsE AMOUNT OF ACTIVITY l-Ii 16 I W @C eP RELEASE l Il@l NA l l NA PERsONNEt ExPCsVAEs CEsCRiPTiCN @ I NuMeER TveE 101010l@lCl@l NA t 7 ' PERsONNELiNau'iliEs CESCRIPTION@ l NuMeEa 10 l 0 l 0 l@l NA i n 80 7 .4.* 9 it 12

- I' LOSS 08 OR DAMACE TO F ACILITY I

'vPE CESClitPTION l Z l@l NA

2 80 8,

i0 NRC l'SE ONLY PU8LICITY l lllll1IIIIIIl LN_j8l)E%CniPflCN 155UE p t NA 2 O C8 6 'J 80 n o rm

IER 78-009/03L-0 Yankee Atomic Electric Co. Yankee Rowe 050-29 j EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I Technical Specification 4.6.1.2.d requires that Type B and C test shall be conducted at intervals no greater than 24 months. Table 3.6-1 of the Technical Specification requires that the Hydrogen Vent System solenoid valves, HV-50V-1 and hT-SOV-2 be tested. On November 26, 1977, the 24 month interval elapsed. The Hydrogen Vent System was tested on August 17, 1977, within the 24 month interval, but in a manner which eliminated the testing of hY-SOV-1 and HV-SOV-2. As the system was tested within the 24 month interval to Appendix J' criteria, the integrity of the system was proven. Based upon the above the health and safety of the public was not adversely affected. CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i Re cause of the event was a misinterpretation of the testing require-ments for HV-SOV-1 and hV-SOV-2 by plant personnel. There were no previously reported occurrences of this nature. The two isolation valves will be tested with-a Type C test prior to, April 1, 1978. Table 3.6-1 of the Technical Specification has been reviewed and it has been detemined that no other testable valve (s) have been over-looked. i This event was reviewed by the Plant Operational Review Comittee at meeting No. 78-11 on March 6,1978, with no additional coments or recommendations, i N e e e 9 e 8 e r y l 4 6 4

c u Page 23 S QYANKEE ATOh110 ELECTRIC 00&1PANY 00 Rowe, Massachusetts 01367 Ynse September 12, 1979 w ~ Mr. B. H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania

Subject:

Reportable Occurrence 50-29479-20/D3L-0 Missed Surveillance (VD-TV-202) i Mr. Grier: In accordance with Technical Specifications, Section 6.9.4.b, the attached Licensee Event Report is hereby submitted. Very truly yours, If I Herbert A. Autio Plant Superintendent ELM /amt

Enclosure:

cc: [30] Director, Office of Inspection and Enforcement e U.S. Nuclear Regulatory Commission Washington, D.C. 20555 [3] Director, Office of Management Information & Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l

Ck)NTRol block: I l l l l l Pa IPLEASE PRINT oR TYPE ALL REQUIREga 24 @ l'M fA l Y lK l R l 1 f@[0 l 0 l-l 0 l 0 l 0 ) 0 l 0 INFoRMATIONI i 7 9 LICEN5EE CODE to 45 d5 UCENSE NUMSER l lg 25 26 LICENSE TYPE JO 57 CAT SS [o E i s"'u'RC LLj@l0 l 5 l 0 } O l 0 l 0 l 2 l 9l@l 0 l 8 l1 l 3 l 7l 9 ]@l 0 l 9 l 1l 2 I 8 60 63 7l9l@ 00CKET NUM8E R 68 69 EVENT CATE 74 75 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h REPORT DATE 80 1During testing, while performing leak rate surveillance on VD-TV-20 o 2 lei [akage past the upstream isolation valves resulted in abandonme a 3 i l o 4 e; [ testing. It has been more than 24 months since a leak test has bee i 1leted on the valve as required by T.S. 4.6.1.2.d. This is the first i o s [t of this nature associated with this test. eveni o e, This event did not effect th _ PiTO Le ability of the trip valve to perform its intended function i

no adverse effect upon the public health or safety o,

7 89 resulted. 'I E CCCE SUSC E 80 o a [S l Dl@ [E l@ y@ lV l AlL l V JE l X l@ U8COC'E COMPONENT CODE SU E V 3 @@ J@ 9 10 11 12 13 ggfgo EVENTvEAR SEQUENTi4L 18 19 20 @ y(j$ l 719l l- --J l 012 l0 l y l0 l 3J LL_j l---J W a REPOR T NO. OCCURRENCE REPORT CODE REVISION TYPE No. ,23 22 23 24 2G 27 28 29 JO 31 J2 h' JJ[x_J@Lx_J@ W@ 10l@ l010l010 l [N_J@ [N j@ [_A_j@ l M l 1l 2 l Ol@ TxN A 7 CN ONP NT MfT d HOURS 'se TN FOR 8. SuP L1 MAN FACTURER 34 25 36 37 CAUSE DESCRIPTION AND CCARECTIVE ACTIONS 40 48 42 43 g lThe root ca6se of this event 44 47 is leakage by the seat of one or more of th g te upstream isolation valves. The trip valve will be tested dur i [down s,cheduled for 9/8/79 when the pressure across the isolation va j [is lower. Future leak testing will be scheduled for refueling o es i i p t ch is well within the 24 month time intervals required by T.S. 8 9 i STA S %PCWER E [h[j@ [0 l 9 l 9 l@l OTHER STA TUS 80 Ot Rv N/A l LAj@[ While performing Survei DISCOVERY DESCRIPTION ' A!riviTy Co'3 TENT i2 n ance l 44 <s 4s REttesEo or aELEasE AMOUNT on ACTiviTv @ ItoCATioN or REtEAsE @ LTJ Lz.]@ LZ_J@l ~ 80 N/A I N/A PEnsoNNEt ExPosOES i I l g l 0 l0 l 0 l@[Zj@[oEsCRiPTioN@ NuMsER TvPE N/A PERsoNNEobu'n'ils l eEsCRiPTioN@ uuvsER 0 Le_Lo_ Lo_J@l N/A '*9 11 12 -d j TYFE DES 7 ~ [Z_.j@[ CR PT ON 80 N/A 3 30 l ]135U DESCRIPTf0N 0 LtOF @l 80 N/A 4 9 10 J 11tillfillilli NAME oF PREPARER. 83 3 68 69

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ML20002C898

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ML20002C898

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