ML20054A048
| ML20054A048 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Arkansas Nuclear |
| Issue date: | 07/06/1981 |
| From: | ORGANIZATION FOR ECONOMIC COOPERATION & DEVELOPMENT |
| To: | |
| Shared Package | |
| ML19240B432 | List: |
| References | |
| FOIA-81-380 NUDOCS 8204150245 | |
| Download: ML20054A048 (2) | |
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El. 6 1991 No IRS 42 RESTRICTED DIFFUSION RESTREINTE Date of Receipt 23rd June 1981 Date de Rsception Name of nuclear power station Arkansas Nuclear One Nom de la centrale Unit No. 1 (U.S.A.)
Date of incident 1
10th May 1980 Date de l' incident Type of reactor PWR Type de reacteur Authorized electrical power 850 MWe+
Niveau de puissance electrique autorisd First commercial operation December 1974+
Date de mise en service
- dded by NEA Secretariat.
a 8204150245 811109 PDR FOIA I
CONNOR 81-380 PDR l
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DAILY HIGHLIGHT May 13 1980
_ Arkansas Nuclear One, Unit No.1 - Saturday, May 10, 1980 f
At 1:45. a.m., CDT, the pump seal for primary reactor coolant pump C experienced i
.a leak that eventually released approximately 50,000 gallons of reactor coolant water.into the containment. A leak of approximately 12 gpm was discovered while 1 ' the operators were performing the normal procedure for. leakage rate determin Technical Specifications require shutdown if that reactor coolant system leaka is greater than 10 gpm. As the reactor was being brought to a normal controlled
' shutdown, the leakage rate increased Ontil, when the reactor coolant pump secured (shut off at 3:00 a.m.)., the leakage was 200 - 300 gpm. The reactor twas tripped at 2:50 a.m.
High. pressure injection was manually used for make up. coolant by opera. ting and ced'ures wer,e,used.to control, throttling charging, pumps. Pressu The small break LOCA the transihnt.
' to"c6ntrol make' 6plbolarit.,Mirg'ih' tFlsa~t0 ration was at lease 100*F af all-~ 7 were ui times.
Decay heat removal was initiated by the RRR pumps at 9:00 a.m.
In order to bring the reactor to a cold shutdown and therefore atmospheric pressure'
,the operators closed the core flood tank isolation valves.
These valves are required by Technical ' Specifications to be locked open during power operation.
To do this, the power to the operation of these valves is removed by locking -
open the breakers wh' nish power to the valves. These breakers are located inside the r
..en t. Therefore, to provide power to these valves in order. that they cc.d be closed by the operators, two men entered the con-
. tainment to unlock and operate the breakers.
4 1/2 minutes and each received approximately 50 mr doseThey were in the conta The. field of radiation was 400 to 1000 mr/hr which is consistant with the amcun.t expected for the reactor coolant which was discharged.
The operators initially attempted to open the nitrogen vent valves on the core flood tanks.
The vent valve for one tank oper'ated but the valve to the other
. tank did not operate.
The operators chose instead to close the core flood tank isolation valves.
~
l It will be two to three weeks to repair the pump seals and clean up the contain-l ment for normal operations.
NRR is continuing to review both the details of the reactor coolant pump seal at ANO-1 and the lockout of power inside containment to emergency equipment for all reactors.
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PRELIMINARY NOTIFICATION May 12, 1980 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-IV-80-21 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public inten2s_t sionificance. The infonr.ation presented is as initially receivec without verification or evaluation and is basically all tnat is known by IE staff on this cate.
FACILITY: Arkansas Power and Light Company Arkansas Nuclear One - Unit 1 (50-313)
SUBJECT:
REACTOR COOLANT PUMP SEAL FAILURE At 1:45 a.m. CST on May 10, 1980, the seal of the "C" Reactor Coolant Pump (RCP) failed resulting in excessive leakage to the Reactor Building sump. The Unit load was rapidly reduced from 86% of full power and the turbine was taken off the line at 2:47 a.m. CST. At 2:48 a.m. CST the "C" RCP was secured and the leak rate increased rignificantly. The reactor was tripped at 2:50 a.m.
CST from 10% of full power and the standby High Pressure Injection pumps are manually started at 2:51 a.m. CST. The RCS was then cooled down and depressurized. The decay heat removal system was placed in operation at 9:00 a.m. CST. There was no offsite release of radioactive material, but the Reactor Building sump contains about 50,000 to 60,000 gallons of water. The
, initial masurements indicates that the Reactor Building atmosphere contains about 3,000 curies, primarily Xenon-133. Offsite environmental samples detected no activity levels above background. At 8:00 a.m. CST on May 12, 1980, the RCS is depressurized with temperature at about 1220F, and the seal leakage is.1 gpm.
The licensee plans to process the sump water starting today and to corrnence a Reactor Building purge later this week. After the Reactor Building purge, the licensee will disassemble and inspect / repair the four RCP seals.
Reactor startup is scheduled for June 2,1980.
The resident inspector is on site, A Region IV MP was dispatched on May 10, 1980 and is on site.
The licensee has made a press release. Region IV (Texas) does not plan to make a press release. The HQ Duty Officer was notified of the initial step change in the RCP seal leakage at 2:28 a.m. CST and again at 4:14 a.m. CST of the significant increase by plant operations personnel on May 10, 1980. The Region IV Duty Officer was notified at 3:40 a.m. CST by the HQ Uuty Officer on May 10, 1980.
The Arkansas Nuclear One, Unit 1, is a B1W pressurized water raartnr.
Contact:
T. F. Westeman, 334-2841 A ao -
90S YgS-
t PRELIMINARYNOTIFICATION
,)I May.13, 1980 PRELIMINARY NOTIFICATION OF EVENT OR UNU5UAL OCCURRENCE -- PNO-IV-80-21A This preliminary notification constitutes EARLY notice of_ events of P055tBLE
~
safety or oublic interest significance. The infomation presenteo is las.
in_itially received without verification _ or evaluation and is basically all that is known by IE staff on this date.
FACILITY: Arkansas Power and Light Company Arkansas Nuclear One, Unit 1 (50-313)
SUBJECT:
REACTOR COOLANT PVMP SEAL FAILURE (Supplemental. Infomation)
~
The licensee comenced processing the approxirately 50,000 to 60,000 gallons of water in the containmnt at 6:10 p.m. CST on May 12, 1980. ~All but 5,000 gallons are planned to be returned to the Borated Water Storage Tank.
This water would then be used.for reactor coolant make up.
The remaining 5,000 gallons will be later processed as liquid waste. At 12:00 n.n.
- CST, May 13, 1980, 23,000 gallons had been processed.
The licensee had planned to comrence a. purge of the Reactor Building at 12:00 n.n CST, May 13, 1980; however, pending ongoing discussions between the State of Arkansas and AP&L, the purge had been held up. The latest gas sample taken on May 12, 1980, indicates approximately 2840 curies are contained within the Reactor Building.
There have been only minimal radioactive' releases associated with two containment entries; a ruptured diaphragm on the waste collecting system, however, the associate relief valve didn't lift; sampling activities; and other nonral waste processing activities. The weekly release for the period of May 6 - May 13, 1980 was 78 curies Xe133 This is considered to average for a week's operation.
The EPA has a sampling van on-site to monitor the environment during the Peactor Building purse. The State of Arkansas has been working with the EPA personnel.
The update is current as of 2:00 p.m. CST, May 13, 1980.
The Arkansas Nuclear One Unit 1, is a B&W pressurized water reactor.
Contact:
T. F. Westeman, 334-2781; G. L. Madsen, 334-2781 A
Distribution:
Transmitted H St. M/h _
4 Cnaiman Ahearne Comissioner Hencrie
- 5. J. Chilk, SECY f
Comissioner Gilinsky Cohmissioner Bradford j}I C. C. Ka=4 re r, 'n )
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Comissioner Kennedy ACR5 (For Distributic D
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IE:X005 <t a A (IE:HQDi di W. J. Dircks, E00 H. R. Denton v
,'g C. Michelson, EDO R. J. Mattson, NRR 55 B1dg.
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J. J. Fouchard, PA D. Vassallo, NRR J. G. Davis, hMSS I /
q N. M. Haller, MPA D. Eisenhut. NRR R. Budnitz, RES i
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R. G. Ryan, OSP J. J. Cumings. OIA (MAIL)
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FRELIHlhARY NOTiFit.kTI A
PP.ELIMINARY NOTIFICATION Hay 14, 1980 PREL!HIhRY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-IV-80-21B This_ oreliminary notification constitutes EARLY n_otice of events of POSSIBLE sarety or ouolle interest sienificance. Ine infonration presented is as initially receIiveo witnout verification or evaluation and is basically all that is known by It staff on_ this date.
FACILITY: Arkansas Power and Light Company
~
Arkansas Nuclear One, Unit 1 (50-313)
SUBJECT:
REACTOR COOLANT PUMP SEAL FAILURE (Supplemental Information)
At 5:07 COT, May 13, 1980, a purge of the ANO, Unit 1. Reactor Building was initiated. The purge will take 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> to complete.
There were numenaus discussions throughout the day between Arkansas Power and Light Ccapany (AP&L), the Governor of Arkansas and his staff, the NRC, members of the State Health Board, and the State Departnant of Health. Although Dr. Robert Young of the Arkansas Department of Health had verbally requested that the purge be delayed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and had indicated that legal action would be taken if AP&L did not comply, no written order or similar document had been received by AP&L as of 8:00 a.m. CDT,May 14, 1980. Dr. Fred Smith, Chairman of the State Health Board had contactesi Lim Bie tn.i.ur 6i IE Revion IV during the day, He indicated that he had been recuested by Dr. Young to convene the State Health Board. He later indicated to AP&L that based on discussions with the NRC and AP&L he saw no reason to convene the Board and that he was satisfied with the actions being taken by the licensee. The AP&L Company also had infonned the Director of IE Region IV that during l
fcur separate conversations with the Governor of Arkansas, that they were never asked to not purge, only that they should contact Dr. Young.
Tne AP&L Company also indicated that AP&L had contacted the State Attorney l
l General and he had informed them that in response to the Governor's request for advice, that he intended to infonn the Governor that the state had l
r, gno case or basis for issuance of an order.
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c' The EPA sampling van remains on-site to monitor the environment during the Y
Reactor Building purge.
In addition, there are 45 NRC environmntal radiation Q
r'enitoring stations (Thennoluminescent Dosinnters) placed (since g
December 1979) in concentric rings around the site.
I G The release calculations indicate, based on worst case atnenspheric conditions 4
and continued occupancy, that the maximum site boundary dose would be 2.4 mR.
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There has been 37,377 gallens of water processed fro:n the Reactor Building sump as of a:00 a.m. CDT, May 14, 1990.
This update is current as of 10:30 a.m. CDT, May 14, 1980.
The Arkansas Nuclear One, Unit 1, is a B&W pressurized water reactor.
l
Contact:
T. F. Wes terman, 334-2781; G. L. Madsen, 334-2781
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... z C7a PPILIMINARY NOTIFICATION S_,md.mam May 16, 1980 PRELIMINARY KOTIFICATION OF EVEfT OR Uf' USUAL OCCURRENCE -- PNO-IV-80-21C This preliminary notification constitutes EARLY notice of events of POSSIBLE safcty or public interest sienificance. The inforration presented is as initially receivec without veritication or evaluation and is basically all that is known by lE staff on this date.
FACILITY _: Arkansas Power and Light Company Arkansas Nuclear One, Unit 1 (50-313)
SUBJECT:
REACTOR COOLANT PUMPS SEAL FAILURE (Supplemental Infonnation)
The ' purge of the ANO, Unit 1, Reactor Building was officially completed at 2:15 p.m.
CDT, Kay 15, 1980. The building fans were left on to continue to ventilate the Reactor Building.
The EPA officials on site have indicated that they did not detect any radiation were detected which ranged-from 1:5X10-gduring the pur In 4 of 8 offsite samples take levels offsite during!ge purge.
to by AP&L traces of Xe 5.7X10-g2 pc/cc The limits of detectibility for the AP&L monitoring equipment is 3 to 5 X 10-12 pc/cc. The EPA and Arkansas State Health Officials were onsite on May 15, 1980 and observed a reanalysis of the May 12, 1980 grab sa=ple taken from the Reactor Building. The EPA and Arkansas State Health Officials indicated satisfaction with the AP&L Company sampling and analysis technique. The Resident Inspector was present during the reanalysis.
The final total for the water removed from the Reactor Butiding is 59,700 gallons.
Decontamination of the Reactor Building floor and Reactor. Coolant Pump Cavity
.is scheduled to commence today (May 16,1980).
Initial seal replacement / repair is planned to start May 18, 1980. The returned to power operation is planned for June 3,1980.
This update is current as of 9:30 a.m. CDT, May 16, 1980.
~
The Arkansas Nuclear One Unit 1, is a B&W pressurized water reactor.
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Contact:
T. F. Westennan, 334-2781; G. L. Madsen, 334-2781.
I l M Distribution _:
Transmitted H St.
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Chairran Ahearne Comissioner Hendrie S. J. Chilk SECY Comissioner Gilinsky Comissioner Bradford C.. C. Kamerer, CA Comissioner Kennedy ACRS (For Distribution) l 3
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Transmitted: MNBB P. Bldg.
IE:X005 (IE:HQDist.
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W.- J. Dircks, EDO H. R. Denton C. Michelson, EDO R. J. Mattson, NRR SS B1dg.
Ia 3 J. J. Fouchard, PA D. Vassallo, NRR J. G. Davis, N.455 N. M. Haller, MPA D. Eisenhut, NRR R. Budnitz, RES R. G. Ryan, OSP J. J. Cumings, OIA R. Minogue, SD IE:X005 RI RI!
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AUG 2 71981 No. IRS 53 RESTRICTED DIFFUSION RESTREINTE Date of Receipt 20th August 1981 Date de R6ception Name of nuclear power station San Onofre 1 (United Nom de la centrale States)
Date of incident 17th July 1981 Date de l' incident Type of reactor PWR*
Type de r6acteur Authorized electrical power 430 N,1e (net)*
Niveau de puissance 61ectrique autorisd First commercial operation January 1968*
Date de mise en service
- added by NEA Secretariat 1
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rr.itlMNARY KOTIFICATION OF EVEh*T OR UMUSUAL CCCUF.REHOE--F*:0-Y: 51-W-.
Octe:
July 19,1521 This orelimine.ry notification constitutes EAo.LY notice of e.ents of PDS5] ELE safety er n interest sienificence.
The infomation oresented is r i ni ti e. l l y receive:: withcut verifi er evaluation end i s ba s i c a lly a_l l t ha t is known by IE statt on :n_11ca te.
Facility:
Scr.ithern Californie Edison C:r pany San Onofre Nuclear Generating Station Unit No.1 San Clemnte, California Docket No. 50-206 5"3 JECT:
CJ.SE005 LRSTE DECAY TANK FAILUR FROM APPARENT HYOROGEN IGNITION The licensee informed the HRC Duty Officer via the ENS pb,r,e line of the f ailure of (
ca'. ecus este decey tank in the radioactive waste treatment system et approxicately 9:25 p.m. (PDT) en July 17,1c>31.
The contents of the FO3-cubic foot tank. acoroximately 0.o m in ur ouble gas, were released to the Auxiliary Building and subsequently discharge to the envirornent via the building ventilatien exhaust system.
Ventilation exhaust ronitors shosed rc evidence of radioactivity release.
Subsequent surveys inside the Auxiliary Building and externally to the site be,undary revseled no radioectivity levels acove nomal background.
At the time of the tank failure, a planned release of the tank's centents, which was to h:ve cccurred over e period cf approximately 6 rainutes, was in progress. Difficulty,
.dever, h:d been experienced in e:;tablishing ficv from the tank through a doc str-:.m crycgenic charccal absorption unit.
" Rumbling and banging" sounds wre reported by plant cperators followed by the activation of an auxiliary building fire alarm.
It is restulated by the licensee that hydrogen and oxygen within the tank were ignited by a preheater unit located upstrea:n of the cryogenic unit.
En.ination of the waste decay tank which failed revealed evidence of drage to an apprcxinately 14-inch ranway.
Bolts on the aanway showed evidence of their yielding under internal tank pressure allowing the excape of the grsecus contents via the manway.
Charrhg of paint on or edjacent to 'the runwy was also harved as well as slight ceformtion (wid crack) to a steel reinforcement ring at the point where the rzrir y a
extentien (approximately 14-inch pipe) joins the tank's shell.
No other dyldence of damage to the tank was observed.
~
l
. Persennel responding to the auxiliary building fire alar:n reported slight haze and l
the cdct of s. eke upon entry into the building.
No actual fire ws in evidence, hwever, the surface of the tenk was reported "too hot to touch."
CC4iTACT:
J. L. Crews, 453-3735 D. M. Sternberg. 463-3737 Distribution:
Transmitted H St.
Che irman Pal ladino Ccrraissioner Ahearne S. J..Chilk. SECY Cmr:issioner Gilinsky Co:missioner Bradford C. C. Kanr:erer. CA Transmitted:
-ACRS (For Distnibution)
MiBB:
AI!:
P. BLDG:
IE:"TAS (IE:HQ Dist.
W. J. Dircks. EDO C.W.Kerr, SP H. R. Denton, NRR C. Michelson, AE00 R. H. Vollmer, NRR MIL:
J. J. Fouchard. ?A T. E. Murley. HRR
- S.'Ebbin H. M. !! aller. HPA R. J. Mattson, imil
'IE:TAS
- 44. K. Shaper. ELD D. Eisenhut, NRR Docu,ent'Mgt. Dr.
8/449W"y[
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S. H. Hanauer NRR
.(For POR/LPOR) l willste gldg.
FOR FGER REACTORS ONLY:
P.EGIOML OrffCES:
PO/1/ M O J. G. Davis.'H".SS tGAC Cc m. No. (415) 056-66 l
/
R. B. Minocue, RES INPO Ccera. No. (415) 952-67 PRELIMINARY ROTIFICATION
MO-V:B1-%\\
(Cont.) July 19, 1551 The tirbome radioactivity released during the occurrence was well within the NRC lim-It is estir.ated that the gaseous release through the auxiliary building ventiletion exhaust stack occurred over a ' period 'of 20 to 30 minutes - well in excess of the previously planret period of controlled release.
r A cor.bustible mixture of oxygen and hydrogen in t'.0 decay tank apparently resulted frce cross ecanunication between the plant's instrement/ service air and nitrogen sys tems.
The Itcensee has identified 9 valves where nitrogen backup to instrument or service air exists.
These have all been isolated to prevent further air inlazkage into the plant's nitrogen syste.. pending an engoing investigation into the occurrence.
All liquid and gasecus tanks in the plant which utilize a nitrogen cover gas have been str. pled and purged with nitrogen to reduce oxygen content to less than 3 percent.
Followp. Post-purge, sampling is currently in progress, with plans for edditional purging as saf::ple results indicete a need.
The Sen Onofra Unit 1 was shut down at the time of the occurrence, having been taken off line early on the morning of July 17 for repairs to one of the plant's diesel generators dar. aged by a fire on July 14.
(see Daily Report and PHO-V:81-39, cated
.7/15/81.) The plant is' expected to remain shutdown for at least four weeks for these repairs.
The fiRC resident inspector responded to the site and the Region V Incident Response Center (IRC) was nianned on a standby basis following notification of the cccurrence.
This mode of response continued until approximately 2:00 a.m. on the r.orning of
- July 18,1981.
The licensee has issued a press release covering the occurrence.
There has been only brief media coverage of the event.
~
Region Y (San Francisco) received notification of this occurrence frcrn the H Adquarters l
Duty Officer at approximately 10:30 p.m. on July 17, 1981.
The information is current as of 12:00 neon on July 19, 1981.
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, \\ \\f FRELIMINARY N0!IFICATION U
FRELIMINARY NOTIFICATION OF EVENT OP. UNUSUAL.0CCURRENCE--PNO-V:81-39A Date: July 21, 1981 This oreliminary notification constitutes EARLY notice of events of POSSIBLE safety or nobl interest sicnifiTance.
The info'r nation presented "1s as initially received witnout verificI or evaluat_i_o,n and is basEaily al'1 tna,t is known by !E staVf on this date.
Facility: Southern California Edison Company San Onofre Nuclear Generating Station Unit No.1 San Clemente. California Docket No. 50-205
Subject:
GASEOUS WASTE DECAY TANK FAILURE FROM APPARENT HYDROGEN IGNITION Subsequent information on this event has revealed that the ventilation exhaust monitors did record a step rise in reading from a background reading of 1,500 counts per second-(cps) to 12,000 cps.
The reading then decayed off exponentially to background in 30 minutes.
The Final Safety Analysis Report fur this faciliLy analyses ~ the environmental consequences uf a weste gas tank accident resolting in the discharge of 20,000 curies of noble gases.
In that case, a dose less than.01 rem would be received by an individual in an unrestrictec area.
Thus, the 8.8 curies discharged in this event would give a dose less than.004 mrem to an individual in an unrestricted area.
Additional media interest is not expected.
Neither the licensee nor the NRC plans to.
issue a news release.
Region V (San Francisco) received this notification update uf this occurrence from the Resident Inspecter at 10:00 a.m. on 7/20/81. This information is current as of 2:00 p.m.
on 7/20/81 a
CONTACT:
A. Chaffee, 463-3746 T. Young, 463-3853 1
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Distribution:
Transmitted H St.
Chairnan Palladino Ccanissioner Ahearne S. J. Chilk, SECY Commissioner Gilinsky Co rnissioner Bradford C. C. Kammerer, CA
.1 Transmitted:
ACRS (For Distribution) l.,
MNBB:
AR:
P. BLDG:
IE: TAS (IE:HQ Dfst.)
W. J. Dircks, EDO G.W.Kerr F H. R. Denton, NRR l
C. Michelson, AEOD R. H. Vollmer, NRR MAIL:
l J. J. Fouchard, PA T. E. Murle'y,.NRR
- S.
Ebbin N. M. Haller, MPA R. J. Ma'ttson, NRR IE:TAS H. K. Shapar ELD D. Eisenhut, NRR.
Document Mgt. Br.
$.Ji. Hanauer. NRR (For PDR/LPDR) '
- hhistedd !.
FOR POWER REACTORS ONLY:
- f. G. Devis td(SS NSAC Comn. No. (415) 851 T57 REGIONAL OFFICES: --
M. B. Minonu; IEES INPO Cormi. No. (415) 952-6724