ML19291G038

Forwards Compilation of Preliminary Info Re 820125 Steam Generator Tube Rupture Event,Consisting of Chronology of Notification,Reactor Sequence of Events,Radiological Considerations & Other Documentation

ML19291G038
Person / Time
Site:	Ginna
Issue date:	02/03/1982
From:	Mills W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8202250372
Download: ML19291G038 (19)

Text

{{#Wiki_filter:. Y-7-t-+~ s -lE FILE'CORY y C[y/ FEB 3 1962 smrt ku \\ H _2 M Ls ( Q ' o-9w j -\\ ~ J ,/j!! Q* u. Q>'i Q G W M t> MEMORANDUM FOR: E. L. Jordan, ret or, Division of Engineering and Quality Assurance, IE FROM: W. R. m l h, Acting Chief Events Analysis hanch, Division of Engineering and Quality Assurance, IE

SUBJECT:

STEAM GENERATOR TUBE RUPTURE AT GINNA ON JANUARY 25, 1982 This memorandum provides a compilation of preliminary information concerning the steam generator tube rupture event at Ginna on January 25, 1982. 1. Chronology of Notification - The times and methods by which notifications were made are shown in Enclosure 1. The more salient features of the notifications show that: (1) the licensee called the NRC Operations Center via the direct telephone line within approximately 8 minutes of the first indications of steam generator tube failure and 5 minutes of the resulting reactor trip; (2) the direct telephone line from the site was continuously manned by a licensee employee or the NRC resident inspector until a controlled cooldown was assured; (3) the NRC Regional Office was notified immediately after the licensee called the NRC Operations Center; and (4) the Regional and Headquarters Offices manned their response centers in a timely manner after which the Region dispatched a team to the site. 2. Reactor Sequence of Events - Preliminary information on the equipment performance and plant staff response to the steam generator tube rupture is described in Enclosure 2. 3. Radiological Considerations - Preliminary information on the radiological chronology and discussions of radioactive releases are provided in. 4. Other Documentation - Copies of the PN's are provided in Enclosure 4 for convenience. The preliminary information presented in these enclosures was compiled during and shortly after the event. It has been informally distributed to various CONTACT: I. Villaiva, IE 49-24865 o'"cr> 8202250372 820203 om) IE ADOCK 05000244 CF """""'*"*'""C" 2* OFFICIAL RECORD COPY a usceo maa

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FEB 3 1982 E. L. Jordan NRC personnel. This information will be supplemented by the results of ongoing NRC evaluations. W. R. Mills, Acting Chief Events Analysis Branch Division of Engineering and Quality Assurance, IE

Enclosures:

As stated cc/w enclosures: R. C. DeYoung. IE R. W. Starostecki, RI J. H. Sniezek, IE T. T. Martin, RI H. R. Denton, NRR G. H. Smith, RI E. G. Case, NRR R. C. Lewis, RII D. G. Eisenhut, NRR J. 01shinski, RII R. H. Vollmer NRR J. Stohr, RII R. J. Mattson, NRR R. L. Spessard, RIII J. J. Kramer, NRR C. E. Norelius, RIII S. H. Hanauer. NRR J. Hind, RIII V. Stello, DEDROGR J. E. Gagliardo, RIV C. Michelson, AE0D J. Crews, RV J. Heltemes, AEOD G. Spencer, RV J. R. Shea, IP J. D. LaFleur, IP W. Kerr, SP J. G. Davis, NMSS R. A. Purple, NRR T. M. Novak, NRR G. Lainas, NRR T. A. Ippolito, NRR R. B. Minogue, RES D. Ross, RES R. C. Haynes, RI J. P. O'Reilly, RII J. G. Keppler, RIII J. T. Collins, RIV R. H. Engelken, RV [ omer > EAB:DE&QA:IEkEA$l:DE&,QA:I,E $"* "' f lV.il.l AlN A ,.W .l. ).S. " ' > 2/.1./.82.:.jr. ,2/.. 18 2,.,, unc rons aio no sw uncu c240 OFFICIAL RECOFsD COPY

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e CRITICAL OPERATIONAL EVENTS AT NRC OC GINNA EVENT 1/25-26/82 0933 Shift Supervisor at Ginna called NRC HQ with a Notification of to Unusual Event. Ginna decided to keep line open. 0937 0938 HD0 established telecon with Ginna and Region I, then notified IE and NRR personnel. 0949 HD0 notified FEMA. 0952 Region I began to mobilize personnel at their IRC. 0953 IE, Region I, and Ginna CR and TSC personnel join in telephone conference. 1030 OC activiated after licensee declaration of Alert.

Response

personnel selected. 1035 Chairman's Office notified. 1035 Selected response personnel called to report to OC. Key personnel to notified in Public Affairs, State Programs, NMSS. 1055 1040 Executive Team and Operations Team personnel begin to arrive at 0C. 1045 Licensee declared Site Area Emergency. 1100 Haynes in conference call with Executive Team. 1125 Chairman arrived at 0C, then fully manned. 1125 Other agencies notified: DOE, HHS, EPA, White House Situation to Room. 1150

' 1130 NRC Region I and FEMA personnel leave for site. 1145 Additional NRC offices notified: Commissioners (through Chairman's to office), Security, Congressional Affairs. 1205 11g5 g3g Chairman briefed Governor Carey. 1520 NRC released DOE personnel (RAT at Brookhaven and ARMS at Andrews AFB) being held in standby. 1525 Chairman appointed EDO as Acting Director and left OC. Region I team, under Haynes, arrived at TSC. 1700 After briefing with Acting Director, Haynes appointed Director of Site Operations with full authority; Headquarters team established to support DSO. 1710 Governor Carey, Chairman and other Commissioners, and other to agencies notified of transfer of authority to DSO. 1740 2015 Licensee downgraded status to Alert; Headquarters support team on midnight shift reduced. January 26 1115 Licensee ended emergency status and entered recovery mode. 1500 EOF deactivated. 1600 NRC response retured to Normal mode but personnel remained at Ginna. Headquarters confirmed status with personnel in TSC. 1625 Final status calls made to Chairman, other Commissioners, and to other Federal agencies contacted by Headquarters during the response. 1700

r GINNA JANUARY 25, 1982 STEAM GENERATOR TUBE RUPTURE EVENT SEQUENCE OF EVENTS (TIMES E.S.T.) JANUARY 25: 0925 Charging Pump Speed Alarm; "B" Steam Generator (SG) level alarm; Steam flow - feedwater flow to SG-B mismatch; Steam jet air ejector (SJAE) radiation monitor alarm ; low pressurizer . pressure (2170 psig). 0928 Reactor trip on low pressure; Automatic safety injection (SI) actuated; Containment isolated. 0929 Pressurizer level offscale low; Reactor Coolant System (RCS) pressure approximately 1200 psig. 0933 Both reactor coolant pumps (RCPs) manually tripped. 0940 Main steam isolation valve for SG-B manually closed following indication of RCS leakage into SG-B (increasing level and pressure in SG-B). 0953 SG-A pressure 540 psig and level 76%; SG-B pressure 825 psig and level 89%. Plant being cooled by dumping steam from SG-A to main condensor while relying on natural circulation in loop "A". Subcooling being m61ntained at about 70*F; SI pumps on. 0957 SI circuitry reset; Instrument air for controlling containment isolation valves restored. 1000 Radiation level at SJAE reading 15000 counts and trending down. Was full scale 5 to 10 minutes previously.

~ r . JANUARY 25 (Continued) 1003 SG-A level reading 100% on narrow range and 400" on wide range meters. 1004 l Charging pumps restarted; RCS pressure 1300 psig; Pressurizer flevel 18%. 1007 Pressurizer power operated relief valve (PORV) manually cycled to reduce RCS pressure per Station Procedures to reduce leak rate; Pressurizer level 10%. 1008 Pressurizer PORY manually cycled again. 1009 Pressurizer PORV manually opened, unable to shut PORV; Pressurizet pressure dropped from 1300 to 800 psig; Pressur-izer level increasing; Pressurizer Relief Tank (PRT) high temperature clarm; Pressurizer PORV Block valve shut. Pressurizer level offscale high. First indication of a steam bubble in the Reactor Vessel Head. 1010 SI pumps increase RCS pressure to 1300 psig. 1018 Incore thermocouples indicate 458 degrees. 1025 SG-B atmospheric relief (PORV) manually isolated as a precaution. 1 031 Reactor Vessel Head temperature 525* (by thermocouple). . 1040 SG-B code safeties lifting (setpoint 1085 psig); Safety Injection pumps secured to reseat safeties; all charging pumps operating. _ Reactor Coolant Pump seal return relief lifted as a result of 1050 earlier containment isolation; Seal return relief discharged to the PRT.

"~" 4 ' JANUARY 25 (Continued) 1057-PRT rupture discs rupturgd releasing RCS water to the "A" containment Sump. 1115 One Safety Injection Pump started; SG-B safeties lifted; RCS pressure at 1035 psig. 1129 "A" Reactor Coolant Pump restarted. 1200 Bubble drawn in Pressurizer; Pressurizer level at 80%. 1205 Established normal letdown. 1230 Cooling down at 2 degrees per hour by dumping steam from SG-A through the atmospheric PORV (condenser lost - SJAE not functional); RCS Press =923 psig. 1400 Containment Sump "A" at 9.3 feet (approximately 8000 gal); PRT at 92%. 1700 NRC Region.I Incident Response Team onsite. 1840 Reestablished level in SG-B. Plant cooling down via single loop circulation dumping steam from SG-A to atmosphere. SG-B being cooled by feeding AFW and bleeding via the ruptured tube (s) to the RCS. JANUARY 26 0705 RHR initiated with "A" Reactor Coolant Pump running to promote backflow circulation through the "B" loop; RCS pressure 280 psig. RCS temperature 330' (TC and core thermocouples agree), tiaintaining temperature and pressure from about 0705 to 1200 (no net cooling) to degass RCS.

. JANUARY 26 (Continued) 1300 Sometime between 1200 and 1300 RCS cooldown started at a rate of approximately 50 F per hour, after which cooldown rate was lowered to about 30"F per hour. Graphsplottfingthepreliminarydatareceivedat the NRC response center are appended hereto.

Incore Head A Loop B Loop Thermo Thermo Col d Cold RCS Pressurizer A S/G A S/G Couple Couple Leg Leg Press. Level Press. Level B S/G Time F F F F psig psig Press. 0626 341 344 297 50 85 48 321 0650 338 342 285 51 82 46 31 0 0726 327 331 278 37 70 51 307 i. 0805 330 326 275 50 69 54 302 0833 326 330 276 35 69 53 301 0856 326 329 262 36 69 53 294 0924 326 330 257 36 69 52 289 0953 326 330 259 30 69 51 285 1028 326 331 254 30 70 50 282 1058 325 329 248 32 68 50 277 1307 297 299 225 37 58 46 254 1357 267 270 234 41 46 44 252 1459 240 243 201 38 35 43 240

Incore Head A Loop B Loop Thermo Thermo Col d Cold RCS Pressurizer A S/G A S/G Couple Couple Leg Leg Press. Level Press. Level B S/G Time F F F F psig psig Press. 0933 540 1300 1005 492 476 345 1300 18 100 1009 480 350 1050 1018 458 460 360 1023 100 + 1032 450 525 1360 1043 450 790 1048 525 800 1054 450 529 936 1105 525 1035 31 0 1115 450 1020 1150 408 41 6 405 984 100 + 207 872 1159 400 1006 195 1200 395 400 380 1006 100 + 195 870 1203 98 1225 974 60 184 1227 370 375 923 62 131 1231 374 374 923 67 110 854 1255 371 369 374 944 67 131 1307 368 373 922 67 130 1332 368 368 373 877 56 130 1355 367 371 835 47 130 860 1425 3 61 361 729 52 120 7 51 1448 361 362 364 709 51

4 Incore Head A Loop B Loop Thermo Thermo Col d Cold RCS Pressurizer A S/G A S/G Couple Couple Leg Leg Press. Level Press. Level B S/G Time F

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F psig psig Press. 1520 360 364 679 50 117 700 1539 358 629 46 115 650 1600 358 357 360 609 51 112 633 1857 355 357 486 54 105 521 1928 353 356 476 47 103 49 505 1958 354 356 449 57 108 35 493 2026 352 356 459 53 1 03 39 4 91 2056 351 353 457 45 99 43 479 2220 345 349 438 55 93 23 472 2249 343 346 434 56 89 31 476 2322 339 342 41 3 56 81 32 453 2351 339 342 393 53 84 42 426 0021 339 345 362 60 84 41 411 0049 339 345 362 51 86 47 398 0116 339 346 370 44 89 43 383 0149 344 347 350 56 90 35 371 0219 344 347 346 66 91 32 364 0253 342 346 334 57 87 37 357 0328 341 345 326 56 85 43 350 0352 340 344 319 58 83 47 343 0421 340 345 31 8 54 86 44 342 0458 341 344 309 51 85 46 334 0526 341 344 303 50 85 47 330 0554 340 ~ 343 3 01 51 84 49 324

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[ I i RAD CHRON0 LOGY January 25 1015 Environmental measurements team sent out by licensee. 1044 Environmental team reports 10 - 12 mR/hr at Training Center - believed to be peak dose rate. 1045 Site emergency declared. 1058 Met conditions - wind from 330 at 20 mph (gusting winds). 1106 Environmental team reports 1.2 mR/r at 1 mile SSE of plant. 1115 Containment radiation level - 6.7 mR/hr (normal level 2.5 mR/hr) (approx) 1115 Environmental team reports 0.8 mR/hr at 1 mile SE of plant (believed to be same location as 1106 reading). 1130 Plant began steam dump to atmosphere from steam generator A. (approx) 1200 Environ. team reports 0.2 mR/hr at Training Center. 1200 Environ. team reports 3 mR/hr near plant to the South (under or (approx) in visible steam cloud). 1200 Met conditions - wind from 317 at 11 mph. 1250 Environ. team reports. background dose rates at Training Center. 1250 o Containment radiation level - 7.8 mR/hr. (approx) o Area monitors in auxiliary b1dg. reading normal ( 10 mR/hr). o Containment air monitor reads 13,000 cpm (5000 cpm - normal). o Environ. team reports all dose rates levels at background out to 1 mile. o Degassed primary coolant sample analyzed - 2250 ppm - boron 0.32 uCi/gm - gross degassed activity I-131 Dose Equivalent 2.5(-2) 1-131 - 7.6 (-3) uCi/gm I-132 - 1.1 (-1) uCi/gm I-133 - 8.8 (-2) uCi/gm I-134 - 4.1 (-2) uCi/gm I-135 - 3.3 (-2) uCi/gm o Secondary water sample ("B") steam generator) 1-131 - 2.0 (-3) 1-132 - 3.9 (-2) 1-133 - 2.3 (-2) 1-134 - 2.2 (-2)

,n<.-,., 1 I-135 - 2.5 (-2) o Detectable levels of radioiodine in snow at 500 - 600 ft. from plant. 1310 Results of snow sample taken near Training Center. (Sample taken at 1210; analyzed at 1310 hrs.). This believed to be the highest reading N{CORRECTEDFORDECAY 1345 o Environ. team reports no airborne activity offsite, o Main steam line reading 30 mR/hr. o Turbine building reading 3-4 mR/hr. o Highest offsite deposition on snow (beyond location of earlier 12 nR/hr) reported about 10,000 cpm. o Met Conditions: wind from 250, 10 mph, stable conditions. Sf40W SAMPLE A!1ALYSIS ISOTOPE uCi/ LITER

• I-131 0.04 1-132 0.24 I-133 0.35 I-134 0.06 I-135 0.47 Mo-99 0.006(??)
• uCi per liter of melted liquid 1539 Reading taken onsite east of Training Center parking lot shows 0.7 mr/hr at waist level and 5000 cpm at 1 inch above ground due to deposition.

Direct reading at junction of Lake Road and road to plant shows 0.1 mR/hr. 1606 Met conditions are as follows: wind from 265 at 4.5 mph at the 33 ft. level neutral conditions, light snow, temp. 13.5 F. 1630 Rad monitoring Van from Region I departs for Site. ETA about 8 hrs. 1705 All offsite dose rates reading background levels. -c Rad levels in plant are normal. "A" Steam Gen. reading 1x10 uCi/ml icdine activity. Slight' contamination reported in water puddles in Turbine Bldg.

(3 ~ f. ' 2004 Met data from tower LEVEL TEMP. WIND SPEED WIND DIREC. 33 ft. level 14 F 14.5 mph 261 150 ft. level 13.2 F 18.2 mph 248 250 ft. level 13.2 F 0(?) 245 2015 Status changed from Site Emergency to Alert. 2310 No significant offsite readings. Ginna estimates that for a maximum of 14 minutes, they exceeded their instantaneous release rate by a factor of 9.6 times. This estimate is incomplete, because it does not include steam lost subsequently from the "B" loop. January 26 0105 Met data from tower: Neutral Stability LEVEL TEMP. WIllD SPEED WIf4D DIREC. 33 ft 14.7'F 8.5 mph 402 (??) 150 ft 14.0 F 25.5 mph 319 250 ft 13.7 F 28.0 mph 308 0405 HP Status Update (no releases offsite. Normal readings in-plant). 0705 HP Status Update (no releases offsite, normal readings in-plant). Largest activity from a smear (wipe) sample on an automobile in o on-site parking lot - 17,000 DPM/100 cm (A typical, surface contamination allowable level is about 1000 DPM/100 cm~ in the plant). o Licensee is performing calculations to estimate total release and arrive at estimate of integrated dose offsite. o NRC RAD specialists performing independent calculations for offsite dose assessment.

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a ._J _ u.... ,, m4mu CC5 8 3: 3U244-E20125 'Date: January 26, 1932 Cate: Janaary 27, 1932 PR9.1HW G!CC tTICN 3F EYLNT M UNU5UAL OCCUMENCE--Ph0-I-82-O?B'-* - --- 'digw.u CT!:IC ATION ;F EENT C4 Ua.J5 CAL CCCU!:RENCE-Fh0-I-82-C9C TMs reifrf r.a y noti'ication crastitutes E AU notice of events of FOSSIBLE safety e- }is ; e'iricary notifi:st'on constitutes EARLY netice of nents of POSSIBLE safety or i T, ;. ime est sige.f fi &cce.he evelta:lon, ar.d is basically all that is bewn by IE staf f on this date. -- .c ir Tre 4fo matier, is as ir.!!ially recelsed without veriff-v i'- irte'est significarce. Tne infcrmation is as initially received, wit,heut ge,rifj- ar evaluatten, aad ts basically all that is kr:wn by IE staff on thts rate.- -- Facil tty: R.C. Ginea Nacicar Power Plant Licensee Emergency Classification: racility: R. E. Sirna Nuclear Fewer Plant Licensee Emergency Clastificatinn: DN 50-214 Notification of Unusual Evm:t D't 50-244 Netification of Unusual Event Ontario Nes York X Alert Ontario, f4ew York Alert Site Area Erergency X Site Area Emergency __ General cmargeric;' General Ew'ergency tot Applicable Not Applicable subject: SitN4 CEMEPATOR T00E RUPTURE; SITE ENERGENCY "'bjeC* SIEM CENEUTOR TUBE RUPTURE; SITE EMERGENCY The Site Emergency was downgraded to an' Alert at 7:15 p.m., January 25, 1982, it 7:05 a.m. on January 26, 1982, the Residual Heat Removal System was pieced in service. 'he Itcensee devngraded the ' Alert' to the Recevery Mode" at 10:45 a.m. In accordance Cooldown of the Residual Heat Removal (kHR) syste.s began about 7:00 a.m.,,1anuary 26 flth the provisions of the emergency plan. The plant was placed in cold shutdown 1982. At A:00 a.m., the primtry system was at 2 N psig, 330 degress. One charging ude at 6:53 p.m. gmm, is operating. ihere is nomai let lewn ficw. "he containrent stag levet previously reported at 9.3 feet (8000 gal) has been t'sarter ccolact sameles indicate no fuel failu es. Surveys indicate no radiation levels fetermined to be in error. Actual level is 5.3 feet (about 1,900 gal). The initial above backgttrund. The NRC Radiological Messaremt. Van shculd arrive about 9.00 a.m., ievel reported was based on the higher of the two level indication channels. The ,1anuary 2(,, 1992, to independently check licensee sempics. at.er vreding channel was determined to be correct. A' backup response team from Region I has reinforced the onsite NRC contingent. 'he NRC Recicn I evaluation is continuing. CONTACT: KISTER ALLKI CONTACT: Kistar 468-1233 Allan 488-1340 430-1233 483-1240 0157R HUTION: 015TRIBUTION: H. S t._, MN38 Phillips _ _ EN W111ste_, Landow (Faud by pg) H. St. %3 Phillips EN W111ste Landow (Famed by HQ) Chairman Failadino EDO NRR IE NM55. 01A Chairman Fallac'Ino EDO NRR IE NMSS OIA Cerse. Gilinsky AE00 RES Corse. Gilinsk* AE00 RES Corra. Brsdford FA Air Rights MAIL: Conn. Bradford PA Air Rights Mall: Coem. Ahearne MPA SP INPO IE:TAS Cesa. Ahearne MN SP INPL1 IE:TA5 Cose. Roberts ELD NSAC ADM: Doc. Mgt. Sr. Co'am. Rooerts 'a LD NSAC ADM: ~~ ~~ ACR$ ACR5 ' ~ ~Occ. Ngt. Br. SECT Regional Offices TMI Resident Section 5ECY Regional Offices TMI Resident Section CA RI Resident Office CA RI Resident Office ^ 1 Fo,a 83 '- ~ ~ - ~ ~ ~ Re. I Form 83 N." January 5,1982) 'p+ (R ,anuary 5, 1982) 5 Destreyed previous edition i g\\ V g ith 3 m

1 I t ou c a e 4 DCS No: 80244-820125 DC5 No: 80244-820T25 Date: January 25, 1982 'cate: January 25, 1982 FRELIMINARY NCTIFICATION OF EVENT OR UNUSUAL OCCURRENCE-PNO-I-82-09A PRELIMINARY POTIFICATION OF EVENT OR UNU5UAL OCCURRENCE-PNG-I Og. This preliminary netification constitutes EARLY notice of events ef POSSIBLE safety or ~~' prelimicary notif tcation coestitutes EARLY retice of events of POSSIBLE safety or pen interest significance. The information is as inttially received without verf f t- .c interest significance. '. Ion or evaluation, and f s bastcally all that is knewn by IE staff on this dateThe information is as initially received without verifi-c or evaluation, and is basically all that is known by IE staf f on this date. C Facility: Ltcensee Emergency Classification: Factitty: R.E. Ginna Nuclear Power Plant Licensee Emergency Classification: R.E. G1nna Nuclear Power Plant Notification of Unusual Event DN 50-244 Nctif1 cation of Unusual Event

• DN 50-244 Alert Ontario, New York Alert Ontario New York 1

Site Area Emergency Y site Area Er'ergency General Emergency General Em-rgency Not Applic.able Not Applicable STEAM GENERATOR TUBE RUPTURE; SITE EMERGENCY Suldect:

Subject:

STEAM GENERATOR TUBE RUPTURE; SITE EMERGENCY About 2:15 p.m., the reactor coolant system (Rc5) was at about 822 pstg, 370, degrees. Baron sampling reported at 1:35 p.m. indicated 2250 ppm in the About 9:28 a.m., January 25, 1982, primary-to secondary leakage was indicated in Steae reactor coolant (RCS) and 1083 ppe in Steam Generator "B" (SG-B). A bubble Generator *B", and a reactor trip was initiated by low prfmary pressure. A Site Alert was drawn in the pressurtzer about 12:15 p.m., and pressurtter level was was declared and was upgraded to a Site Emergency at 10:50 a.m. An ENS report was made levelled out near 50 percent. Cooldown has been reduced to about 5 degrees-to the NRC about 9:35 a.m. The reartne ene sta-ent was tset.t.d. s f ts taJ=c61wn per hour. and coolant charging were used to maintain primary inventory. No excessive core temperatures appear to have cecurred. The pressucitee fodicated full. Natural circulation cooling using Steam Generator "A" was attempted, but its effectiveness was questioned Early in the event, a Power Operated Relief Valve (PORV) fatled open. The and a reactor coolant pump has been running in loop "A" since about 11:25 a.m. Pressurtzer Reitef Tank (PRT) rupture disc blew. The PORY block valve was shut. PRT Level was 92 percent at 2 p.m., and Containment Sump level was 9.3 At 12:50 p.m., the primary system was at 944 psig, core inlet temperature indicated ft. (about 8,000 gal.). 374 degrees, core thermocouple temperatures were about 371 degrees, and couldown was preceeding at about 48 degrees / hour. The NRC Region I Administrator and a response team are enroute to the site.

• The resident inspector monitored the event on site and continues to do so.

s, ;'that locatten has retureed to normal background.06 a.m., a 1.2 mR/hr reading was obtained about I mile south southeast of the The licensee issued a press release. An NRC press release is planned. The reported was 12 mR/hr at the information center; that location has also returned to -, ' ' Region I and Bethesda incident response centers are manned. The highest onsite reading normal background. There is no indication of a serious radiation hazard on or off the site. The NRC Region I Adminf strator and a response team are enroute to the site. The resident inspector monitored the event on site and continues to do so. The licensee issued a press release. An NRC press release is planned. The Region I and Bethesda incident response centers are manned. s M-n CONTACT: KISTER CONTACT: KISTER ALLAN 488-1233 -1340 $88-1233 488-1340 DISTRIBUTION: DISTRIBUTIJN: H 5t. MNEB Pht111ps E/W W111ste Landow Uared by HQ) H. St. MNBB Phillips E/W V1115te La dew (Famed by HQ1 Chairman Falladino EDO NRR IE NM55 OIA Chairman Palladino EDO NRR IE NM55 Comm. Gliinsky AE00 RES Comm. Giltnsky AE00 RES Com. Bradford PA Air Rights Malt-0 Comm. Aharne MPA SP INPO IE:Tks.. -- Comm. Bradford PA Air R1 hts MAIL

• Comm. Ahearne MPA SP N

M Coae. neberts ELD NSAC ADM:Occ. Mgt. Br. Comm. Roberts

ELD, 0oc Mgt 8r.

ACR$ ACRS 51CY Regional Offices ' TMI Resident Section SECY Regional Offices TI ent tion RJ Resident Office CA / Re 2.s 1 Corn 83 V V (Rev. Jeeuary 5,1982) \\ R. 4 I Forn 83 ' [/ a (RN. January 5,1982) V Destreyed previous edition Destroyed previous edition ksl v ,}}