ML20055D657

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Forwards Info Requested on 860703 Visit to Plant
ML20055D657
Person / Time
Site: Rancho Seco
Issue date: 07/14/1986
From: Kellie F
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20055C226 List:
References
FOIA-90-76 FWK-86-364, NUDOCS 9007090250
Download: ML20055D657 (175)
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t FWK 86-364 July 14, 1986 h!((I:

ROBERT G MARSH DIRECTOR OFFICE OF INVESTIGATIONS NUCLEAR REGULATORY COMMISSION REGION V 1450 MARIA LANE WAENUT CREEK CA 94596 Attached is the information requested on you visit to Rancho Seco on July 3, 1986.

Attachment

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FRED W KELLIE RADIATION PROTECTION SUPERINTENDENT l

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'87 claim

"" m by NRC O

CO The conclualons are the first in t-cetion that the commlenten contt l-ered SMUD's settons a dellbers e cover up rather then negilgence et4

COVCT, bed judgment.

'The actions by $ MUD were wi' b fut and intentionally eencealed rp.

t By Steve wiegend ego giiv,,,ieenes to the envitou and Deus Dempster ment from the NRC and the pubite see stati f rHere by false recorde and reports? ti e

$0 >tte document concluded. *E06-Rancho Seco managers deliber.

dence and testimony collected dtt-ntely f alsified documents to cover up ing this investigation demonstratis the release of redlotetive water that the entire ($ MUD) chtin di from the pter.t in IDH ond 1985, ac-command... participated in or h0d cording to e previnuely confidentint knowledge of the repetitive creation federallnvestigative report-of fotne records and made telet fr-The 1337 Nuclear Reavininty ports in the NRC on recurring ocO-Commtenton report also concluded ggongy that managers at the nuclear plant The report was released by flie ntdered radioattivity tests to be NRC itst menth under the Freedern modifled to that the results would be of inf ormstlon Act to a law firm rep occeptable, and that the actions recenting a group of Rancho Seco

'were nimed at preventing the dis-nelghbors who are sving SMUD in

,ti1c't from losing more money be.

Superior Court over the redtstion e-ce0se of plant problems.

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In adattion, the report Seys the in June 1983. when the issue filet

$geramento Municipal Utility Dis

  • carne to light t SMUD spokesman trlet modllled the pinnt's design said *there never was any intention

, ithout NRC knowledge rather than to deceive aftyond Whal We hl 'e w

i

. follow estabilthed procedures to here is a d!!!srence of epiriton on

'hdtp dest with the large etnovnts el

,ggg ggggggggggg g ggdloggttvg fe.

I contaminated weler.

),gge'e "The conclusions In the October o,neral manager David Boggs,on IW9f report by the NRC's investige.

the iob less then a year. sold Thu'1-tive arm back up ellesntions made day he was previously unewtre of b7)ther NRC employeesin legg that 4p, r,porg,

$ MUD cut times for sampling Iluulti

  • ' Almost all of the people involvrd t

dlscharges in half to leeten the prob.

in that are gone and none of tht m i

ability that radioactive materint 3re in line management poelliota,,

    • uld show up.

4td said. That is not how the curront i

  • mbnegement does businem. I will never personally do businean like that, nor will I allow ll to be done as

'longasI am general manager?

,"7he NRC fined $ MUD 8100.t00 N,lksf January for f alling to controllhe

.r'plense of radioactive water 18 in l, 'l)

See SECO, page lit i

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i Seco George A.Cowntd,hent mentger (entleued from page 81 by the NMC nna wete not discovestd Ciny Cieck near the plant from 1983 until n surprise IDA0 inspeellon by at the time,enuld not be reached for in 1986. The amounts releened were the federni ngency.

comment, lie was firpd ently lett deemed no danger to human health NRC Investigators also concluded year efter the NRC ddmanded it.nt that plant mannucts f ailed tu report $ MUD tertify it had fdll conf 6dente hy lioth the NRC and SMUD, and the the relense nt redtonttive waste end in those who may haver htd 60me re-U.S. niinrney's nflice decided lost yent not to pursue criminni prosecu-changed test procedures to create sponsthllity for the releases.

re69tt6 thht falsely showed the waste Ronald J. Rodi nguet' former anste-

tion, Dul a letter finm NRC sesionalad-wus not contaminated.

tant general manger sold he was ministratur J6ck Martin that accom-1he leport told that Rtncho Seco never twere of any nient in fake panied the nollte of the fine might not have been Allowed to oper. leets or misleed the N1 C. Rodrigues, ennleined nn suggestinn that federal nie until the d!stharges were who left SMllD in Illi andlennwa afficists thought the stilons had stopped.

nuclear industry consultant, sold he been deliberale and not a result of

  • ll it believed that the intent of recalled 16 thing to Cornrd about the

$ MUD mnnagement was to deceive lesse at the time.

negligence.

NRC spokesman Greg Cook seld the HflC and pubilC that Rancho $4-

  • l 86ked him to meks sure that ev.

j the report was withheld while the Co was not esperlenting design end erything thel's dont l( done proper.

Josinte Department studied possible operoling pleblems until such time ly," Rodrigues sold.*later he (Cow.

prnserullon nr.d that the Freedom of that the ptent had been ellowed to the Intent of Information Act request by the law restert,* the report sold, "end the tid) entlefied me thtlically sound, the action was Iechtl item of Triedman,CollerJ 4i Poewsli necessary corrective nellons t' auld 1here wasn't any intent to vlotale involves Justice Department docu-be theit undertaken while Rancho the procedures.

i ments as well es NRC reports.

Reco was in nperetton (nelling elec.

ACCording to the report. when tricity), rather than taking CorreC-

"I. Ster on when Ileft AMUD, they Rancho Seto managere were faced live actions while shut down (pur. (NRC) seemed to imply there was a with unexpectedly large 8 mounts of chnsing elecirleily)."

delibertte move tolfelelly docu.

contaminated water in the early The reference in restart involved ments. But from myiconversations 1960s, they modified the plent's de-a shutdown prior to the cae lhel tide. with people, that sure wasn't the in-al n Isther than folinw accepted,but lined Reneho Seco for more than tent.lf the NRC really felt somebody more expenelve, procedures. The twn years.- from Dec. 20,1965,to was fatallying documents they would li have done something $ bout it."

modifications were gver opproved March 30,19 Bit.

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Nuclear Page 1 of 2

$ACRAMENTO BEE l

June 9.1986 Page D1

.O SMUD rates begin to worry industry 1

Sy los litettbeers tween $ MUD and other utilities, *eur competitive Seehalf triser strength in attracung a new manufacturing enter.

l i

)

prise will be setteusly eroded,' the consultant

said, i N A COUNTY THAT long has wooed new jobs sacramento's energy problems stem from the i

with its abundance of cheap energy, the grow, lag cost of an errant nuclear power plant is kin, giant Rancho Seco nuclear power plant, which currently produces aero power but mega baad.

eling the first sparks of concera among bustness aches for everybody down the line. The SMUD i

and industry leaders.

Sacramento's rising industrial and commercial plant, with a long history c,f abutdowns, has been sale since Dec. 26, when an electrical problem electric rates still are below those charged in oth, and operator errors led to a severe overcooling of a

er major Californla communiues and many cluas the reactor. lt is not espected to restart for at least scross the nat6cn. But the vital volts, upon which another sit months.

the area's jobs and profits depend, are more cost,

- ly now due to nuclear woes. And major customers With SMUD buying replacement pov'er, and un-of the Sacramento Wualcipal Utility D6str6ct say able to sell millions of dollars of surplus pwer

,they are not obliv60us to the growlag dont en the from the 'Rench' to another uultry, $M UD's reve-espense side of the ledger, eues drop and customer electric rates rise. The

'You're like the homeowner in that you feellike latest rate increase totals nearly 10 percent, be-one of the reasons you moved into an area was to ginning July 1. A slipping date for restarting the beve the advantage of SMUD, and you see that ad. plant is raising the possibility of at least a tempo-vantage is basically d6tappeartag," sold Don rary M percent rate bike thead. Additional rate Owens, vice president of informauon resource locreases are prod 6cted if the plant sever runs management fof Sacramento banou Cal Gas Corp., again, which distributes propane gas throughout the U.S.

. And as if the plant weren't in enough trouble To be sure, heltber Cal Gas not other major $ac. technically, pollucal troubles also loom: A citi-ramento County businesses contacted said they seas' group is collecting signatures for a proposed beve yet been seriously hurt by ristag electric ballet leluauve to permanenUy abut down the costs, and some gave high marks to publicly run plant, which is SMUD's major asset.

$ MUD for its management and soliability of aer.

SMUD staff have said that even after the July I Vice to date. But many business persons and offi-rate increase, industrial and commercial.11ectric clats acknowledged that there are quiet but grow. rates will run 60 to 60 percent lower than those of lag economic coticerns over future costs and Pacific Gas and Electric Co. SMUD residential reliability of SMUD electric service, rates will run oaty 30 to 30 percent lower than

' Historically, our now. cost electr6 cal power and MM.

Feliability of its availability has been a major fac.

%mparatively speaking, the rates are still tor in our ability to recruit new industri' enter.

ph, out natutally we're concerned about the prtse to the Sacramento County area,'said Alan bibh percentage of this area's needs ibat should be Ewen, a management consultant and former el. coming out of Rancho Seco, and aren't,'said Ste-rector of the Sacramento Area Commerce and phen Huffman, director of planning and admints-Trade Organlaauon.

To the extent that the cost of power narrows be-4 ea. Ae -

n

Pace 2 of 2 tration for the California Almond rete bike was lev 6td against all cus.

Some local businesses already Grosers Eschange, which markets tomers, after one member dropped have cut eleetne costs by taking en.

I its products undirt the Blue D4amond a plan for a seven month,25 percent ergy conservation measures or in.

label.

surcharge for business and a 3 pet. malling cogeneration devices that "That's naturally a long-term con.

cent boost for residential customers. create electricity Independently of i

cart; will they be able to furnish it Kehoe said the across-theboard SMUD ianos. $ome local energy man-(electncityl on a reliable basis as lacrease is fairer than a bisher sur. agement f6rms amid they are saving they beve?* amid Huffman, who ad, charge against commerenal and in.

building owners significant sums b) 4ed that $ MUD's service to the es.

dustnal customers."That would be a inmatting energy effic6ent lighting estant,e has been highly re16able.

Pretty buvy hit, and a pretty,I sup.

"Obviously we don't have any con-The Sacramento plant of the pose. dangerous precedent to take trol over out $ MUD rates, so every i

Campbell $oup Co which employes with respect to rate. making by month that otr electncity bill in-l.600 workers year round, sino is one SMUD? be sald, adding that custom-creases we're searchms for ways me i

of the largest $ MUD electric custom.

ers abound there the Rancho Seco een possibly offset those? said Cal burden equally.

Gas' Owens. *We've looked at em.

ers, The plant must remain competi.

'When we set the Ranch back on ploying energy management compa.

tive with other food plants across the line and operating in a healthy man. ales... blatoncally where we've run Mation. *and a plant that is not com.

a r. It is 3060s to help stabillae the lato an office a senes of eight bulbs.

,petitive could expenence a reduc.

estes? sa6d SMUD board member now we've cut that back to five

'tlon in its manufacturieg scheduley Paul Carr, bulbs?

gid spokesperson ceae 76erney, Carr said the nuclear plant trou.

Consultant Ewen, who says the

  • Increases in the cost of utilities bles haven't weakened $scremento's continually rising industrial power edd to the burden of maletalaing an solid busteens climate = with elec. rates are
  • alarming? called for officient operstlett. $ MUD rate ln.

tric rates stilllower than other utill. greater public discussion of the poo creases have created to major prot >

ties

  • but it is at that point in ume er lesue's affect on local business

.lerns for us ao far, but we are always acw I think that businesses are sud industry, including the avaltabil-

,toncerned about rising costs? Tier.

looking a little more carefully at the try of adequate power reserves for ney said, county because of it?

future growth.

Acknooledging growing business New businesses continue to enove "We no longer know when we are poneerns, the Sacramento Metropol.

Into the $acramento area, and John going to have Rancho Seco, and it no Itan Chamber of Commerceplans Roberts, esecutive director of the longer can be classified as reltable soon to establish a speelal commit.

Sacramento Area Commerce and power? be said. *Indeed, that hap-ae rganlaauon, asM wisidus MAS H H has to be decommlnsioned fee to look at Rancho Seco economic conunW um Wn 6 87 as a d sucensfulinutaWF issues, said esecuuve director Mike Seward.

Proval when they compare SMUD's Ewen said at least one major busi-e mes o n amas M me aus MenHH 2 Sacramnto shn The chamber, he said* wants to man an enW.

was dWckr at $2 bas ph.

Mudy ** hat essetty will ha n in

""* 48"U" p

got ynt coH con'Ws

% they eM MginMag m W con-terms of cost if Rancho Se o goes back on line, and what would ha r,

if the whole situation blew up a7d' acrewed down as tight as you can, cerned a little bit, but I would say let's say on the November ballot is and your budget is done for aert that the serious aspen +' this frem 8 ""

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  • sue,if people voted to close it down *

""r" cent - that's the other side of point beve not rew t.eu. talked 10 pe Seu.ard - like other officials -

the coln? he said.

about? be said, quickly stresses that Sacramento electric rates remain well below those offered by many other utilities and that companies recognize 'It still is cheaper to do business here thanit is literally in any other.Tnajor com.

munity in California and a lot of oth.

er communtues in the U.S?

But the chamber dl*ector also ac.

knowledges. *There is a concern among the business community,,,

% e are,ltke the rest of the communi.

ty, particularly concerned about the problems that have happened with Runcho Seco?

$ MUD board members say they are trying hard to keep rate htkas to a niinimum, and are hopeful that better pnce stabiltry will return af.

ter Rancho $eco comes back on line.

  • l'm very concerned that our very favorable rates and attendant attrac.

tion for jobs not be hurt? said board member John Kehoe.

The board's July 1, p.33 percent

Sacramento Bee 6/13/86 1

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retsh_iactorems to the".-

  • W and M p :T<' M$[*.The MRC ing'ted that trainingi r""")

,,g, i

t"'."s,*."e."e2'Eliic'e*."fe ".*4eJ !"J.w, "elnllew:have started sees tr i

llll"'~e."e's~erio,ees

,,es,..

.d Y 8 hat.se eseidy is [.

,,1 ty.

YtrWehg.7g*6

.e}

med see en persommei who condr 985. mancheesece54ectm. seeerthe crier

.. Pt'M n.ebons med ; yetti kne practice driets med a thag.

l

, m.. -

amewpl in any esser,ency, we-1

. -- =

w,-

ne

...ao. how sertees pre. But, he -

Hereed Fire' Department the.

i i

  • eded.'Whe he seene pcese, sederessy srades dral uefore fece FWe Acadesey as est "O p T ggerf-hp. h W S M q-n.irq polets. Ist July'-1985.g _ _.,

_y -

2, 3efringements 18sthere de Reacho sece has been Idle'stacej pleet.efRdels resnosed the; ensore feelereA 2s. when en electrices smearese,. 8eec7 e'I'8pment.soch as l

lokeep such as emef-tien and operatorerrors caused a

_inetsee kits.ifte n these

. Seecy Plee.eles that do not, vere.,.s_

^"__ ; of the seclear re. ' costlosed te It'it thens i

pahow the Ibcation

.fPst old Onctet*,'The.5 federal MRC bas.wknetteegelpmestgasseered, @

e

[.",

  • evertente years of sneenge.[J.deresWeecalcolate* The egency eEs seed thof was s' start-up piss wt!ct r

.n'ed _ QM,thet esmeent et L

f.,c.

e hertpos. et the pient. -.and operatieme! shortceaningsd'sessouses released darlag n, l

m,

- r anesear accidem were out i

'#%'37

[. r:e)Ime,gd the leape,cties; thef.. sed ".of Ilmlee.d vetee.*, ',

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NRC steps upp6tbf?Se60watgrrsbases

,,. J

., he pouctee, Regislatory Commtesten hoe W

, -lt

~

  • t Met

. s' M

- U,S ggg l

no,,e.,o sec.,,,,c.ee,,se r.

o e.e,,isas technical specifications.-

~

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4 noe seen poemstsee vaas-en-se. Pogo A29.

,' Cy Tom Harris The NRC has agreed with SMUD that the ;

%*0bvioegly,-i 3jA ty,g'tse e.

j/ /<J3 gThomasselO pf*

r

,e

.s w

Bee statt Wrteer discharges did not reach levels dangerous inj NRC criterte. Wd wMI cer4t*W~.m to y

i neighbors of the plant, about 25 miles souths.

$ heirs.,

abid, k, gy

<g,b l u,, v,

ies

  • The Nuclear Regulatory Commission staff east of SacremeMo.

~ ** "P I-Evert % h

' ' ~ ~

~~ y 'j "

has begun a high-level investigation of what it

.g But in the process of its inquiry NRC inspeep taused amore then ein M, den cs.Hs " apparent errors and, failures'* In how SMUD handles life release of radioactive.

tors discovered that the apparent change in.",

II! reno uf redlettes to someone Nving st ed i

measuring radioactivity levels was done "to fa;,

boundaries.The NRClimit to protect seej t

waste water from Rancho Seco nuclear power i cilMate the release of potentseny contaminst

  • pubHc is See miellrems, and anomer esforced J l

plant.

ed Hquid to the environment.-

.by the EnConmental Protection Agesecy is 25. '

t One of the problems, NRC spokesman Greg

  • The report says the agency was subsequenf{.

t The specific Mems which me NRC is perse.

w 1 Cook said Thursday in Walnut Creek, is with ly told of at least one lastance where a 2,900m ing, ;^i....., from en maannounced Inspec ~

i the Sacr:.mer.to Munkipal Utility District's second count revealed the presence of radios.

Non of the piset Dec. 26 following a long4erm g)

) anipulation of radioactive sempHng methods activity, but that the lechnician was ordered le(

$eidown,Inchsde-

' in an effort to legitimize the discharge of con- ) coset ageln fof.onlyl3,996 seconds. ThM e

  • The appeng violence 'g N ' S - ~.,

'J y.

l l faminated water threatening to overloed on-

. shorter coeM did act reveel any radioet'tivity,M Timits designed to protect M M"3 s

I Fallere to replett feath I'h') '

site storage tanks.

l -

M the contaminated water was released into ofthe pleet.

s~

I s

That is the most serious one 'of the issues *. Clay Creek.9. y,;p,'ci,. 4 "

T-I \\

~

f

/ d i

' measured la me W '*', ',,

levolved in the current review," Cook sold. **, Two seperale discharges'cNe'd by the NRD"*

T i

~:

l

., 9

.g.,e g, c,,,y,ggg, g,,

SMUD's practice he said, was to count radio. 4 levolved 150.767 gallons and 85.956 asilons;

(

imNs for 1985*

vJ M.

activitylevels soquicklythatitwould nederre.*J.taleted with radioactive ceshmt 134, cest'em

. p g,?*g i

'** 1.'*-

i amfeff,,,,, @ /

port actual concentrations in discharges to ti

  • 3 137 and cobeM 60.

y

.c l cy Clay Creek, which flows off the plant site to i #e: Sech. compounds have already,contaminet- *

, gg'..

pubik property.

d the creek,its sedinnent, fish, frogs and other -

g p,,"

(

  • r " d.d-F.4.,i l
  • It appears that they Intentionally altered j

j

.and have been transferred to adM M

I i

y.

l their sempling methodology." Cook seld. It is

, cent farm fleidt, where cattle graae and crops.1 g,g "9" i

,.,,q.,.4 t

'**88E; f ~,_

l setting a high level of attention, here and in ;

h

, are raised

[

, While the N q.pg p iRCsacksewledges'that tge%

  • SMUD hes. ;, y.p y+y N /

l headquarters.".

Aa NRC repert details how utility managers ; westes are longlived - ceslum 137 takes 39 3

,,me dem..;.c;gew, fgg i

g,,4

)f*EIY FTporting all Indications of contament ordered staffers to measure the radioactivity Mentlefly %,W, deser and re== Ins pe.

rears to lose hel c'*** *f 980*ctivhwmehmutung u f

J k

f #e Seven such of ligold effluent for only 1,000 seconds rather a, -

- -p t.'e.

a.

s tion and implenienting better sempnag 3

g23, than the required 2.000 seconds, knowing that
  1. 8 "8I --

" ~ ~

ods.,..

p j

It would underreport the actual values and al-keskBg. h Mr

" Some3clenhs W@,espatch,%pb N-Th( M'h MW W

low the appearance of compliance. -

7g. ;j. ~

l The discovery came while NRC i.,~. i; utfe levels d radoecHvhy andAietatalajeet,,

Whhq f

j /i.

~m2 l

were prepering a final report on the impact of vpoMFe hassamuffecy y

F' f

tethele d teld':. J A ;. 7 problems from 1980 to 1984 with Hquid dis.

S s nee g.Among mose ere rce& J,.4.W*

1.,',.,

/-

  • i charges that were made with incorrect dilu-theMwith the 1 were told to follow o,% sick count practice Det";

dnetramferof tien calcialetions.-

rders.They sold the ulott.

.Med water mrough ^.

- - n s

s. There never was hy Intention'to deceive

. x.y systems Mk votion for the citenge in counting time

, Du hoses and unprotected plastic pipeg, said ettlity spokesman Brad Thomas..*stemened from the excessive 'laventory of,g# JMquent transfer of water from the anyone,"hed a definillon of what radioactive

  • W3 pic pleM wMer and the licensee's public' state -

We ngeld weste p

E ' ** If8"me@nt. YF systents fer glWeler was agd stuck with that definition. Our ment that they would not rete ase any addition- -

i I

e edennMion of no radioactivity is not being able al Hgeld r;f* ci;w effhsents."

L i

4, i 4*'

j kdetect M. tesing techniques outlined in our SMUD's Thopias sold. *EvNd tNeth we*!

pal J..

...m i

made a change la me count Mme, we feel we I were still on the conservative side and met aN

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5 P We dienstices age,*gountMhtd ettper*

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asyming omer then 1

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NRC pr.obg,targstLJ$,

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'wastewat& dom in M

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c.: '

. >.M O... % %.'. a :.:;

. % WW <'"ii' K."fe6'. U i

  • B'y John Johnson '.

2-Bee Washington Bureau

  • ir.: tid #.".41.'** V '- 1 t'
  • .\\eg.gr. o *.

1 Q Y*

itles in the handlins p 'radioactlyc..wastew,0f rr.i.

.* n.s *.r.

WASHlf,4GTON,:A; ederalinvestigation pgul a er'at -the '-

Rancho Seco nuclear. power plant is focusing on s,everal. :

current"an'd f6rir.idr~ialgh ranking utility officia)pTacc6ry (

ing to. sources fam)ilar with.the,casg.,, of 43f..:.:.,

e

-},

These, sources say Nuclear Kegulato,ry.Commissio

..vestigators feel (bey haveia'*yery;yla'bj$ case th 'in 9

strong enough to refer to'the Departmbpt of Justice for.

1 possible prosecution.

?'..'

Distiict, operator of Rancho'Seco, Ither'Wdr,lp,,all!tlieTn

..q T

)

. ?They say officials'of.the Sacram

'Munic

,i mishandling of low level radioactive M10 stew &ter@ I%

in or had knowledge of policy. decisions that led to

[ idated into a creek near the plant... ':*t1Ji.+ih w c.:.

i

' Federal documents indicate that plant,have been the' -$1sc

' tween 1980 and 1985 caused what may

. greates,t radiation exposure ever to human beings living f near a mklear power plant that was continuing to oper,

' ' ate. Rbgular testing of wastewater discharges,at U.S. nui '

clear power plants began in 10'/8. -

.. r u,?

7:

Two,fisWfrohi'a'cbnta'minated dre6k"floWijii from,o

,e.

.I separate. private studies estimated that pe I

satfii's e:

RanchESeco s.it.e Eou. ld have been e.xp,6. pied.t.o'.u_p to.s.:

47 m.

2

s...,

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ki$ d.t $e4 4 e

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. = - -

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a ha.,a-o.e e,, u, s., t !

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,*A key elemast af the lovestigation b

,. CO,

m i,.",,

"' -'a =a'a-a= 5~

F f

that they failed to keep records and O f procedures. La some cases, the pinnt apparsa0y,did set l

Costlawed from page Al

. know how enuch redlauon it was releasing because gyaf i

millirems per year of radiation. A millirem is a measure-not monitoring the discharges closely enough.

meet of rsdlistion.

r

  • f'he end effect is, they were fortunate
  • the probles nat is nearly tu lee as high as the Ilmit of 25 millitems w.isn't worse, said NRC inspector Yubas. *These guys l

adopted by the Environmental Protection Agency for the

, ere not doing it right."

w protection of public health, though it is still f ar f hort of, knowlagly withheld damaging taformation from Additionally, there is evidence that plaat operators the NRC publbc bealth standard of 600 milltrema.,

trl don't habw of any other nuclear plants thal had ', erament. $

i eene calculated doses.* aald Dr. Frsak Conael, director,.

  • For irstance, plant operators reported la public doce..

of the Dirtstoa of Radiation Protection for tte NRC., snents that there were no releases of fissign products la SMllD mever was cited for violarlag als standard, how,, the first half of 1985, despite evidence la the esottsry, I

eeef, because it could sever be proved that anyone 10 Peaks had been found on Juee (,3, add 17. ace 9fdtng to gested auch a done.

records. '

v:NRC regional laspector Greg Yuhas andtlId health NRC documents show that sa ese of those daysi a and safety significance of this esposure was not great, plant, official called the NRC to ask for an esplanaUon of mainly because the arco around Rancho Seco,25 miles a key regulatloa.De official was told the peaks must be southeast of Sacramento,65 sparsely populated.

N recorded and repotted.

ne long-running. highly secret NRC Investigation lato. Despue thla,they ware act.

dtancho Seco's waste releases from 1980 through 1985 ts ; ' A review of pubile documents and laterviews with uald to be nearly complete. Sourges familiar wHb lt said those lavolved in the lovestigauon reveal the fonowing-hey expect the agency to refer the case to the Depart.

la March 1985, control room operstors were told met nent of Justice inr possible prosecution under statutes radiation peaks bad been measured and that wastewater agulating the withholding of information from the gov. could not be released, SMllD tad earlier namounced its arnment, or making material false statements.

Intentiom to not dlacharge say radioacUvity to the cavl.

, t.ess severe actions could be to impose floes on the ronment, according to the NRf.

+8stty something that could be attractive because some The issue was flaatly reported to the,NRC in March Bey p? vers in the waste release acuvitics are po longer 1986, touchlag off a full. blown inspect 6on of the last.La i

' vita Rando Seco.

  • ' turn, that led Ao the curTent laeulty by the nigh Of-Asked stut the accusations, SMllD spokesman prad' flee of Investlantions, wb6ae job to to pursue allegauotsc Thomas said: *.%1IJD has cooperated with the NRC'in of wrongdoing.?.'
  • 3 very step of t1 h Inquiry and will continue tofdo so. We Accordirag to the account la a Mae g,'t)Stlaspectica o

lo not feel thei t was any latent to deceive seyone by* the water ceutd be released if so }inahs"were fou report, a 1et for chemistry and radiaUon',amistant enid' inybody."

t 1

l

  • What we're talking about is dumping low level, counting for 1,000 acconds. "Som,ellechnicfnas stated

' caste,* said ont source close to Rancho Seco. *At best _ they did r.ot believe this was the correct action,bovever, it's a case of) aillful non. reporting, in lemis of egre. ' they did what they were totd,* ace 6tilag to the'doce.

j niousness. it sht and be a 10 (ou a scale of one to 10).*

. ment on feht with the NRC in Washington. ' matter ws6

. !. a,

i Another sou ce caHtd the case *very Vlable* to terms he J une traspectloc report 40tes Rat 4

if its chare of being brought to trial, s!! hough that de-brought to she at!ention of licensee management in the etslon ts up 9 the Justke Department.

contert of a violation... and that management had con.

It tr sill' not certain which Individuals will be blamed cluded no violation occurred *

%J

' or me uste rek.ve nwileles. Investigators are believed ne report does not identify the managers who re-

@qv' found evidence of widespread errors, combloed,,ceived the report.,,,,,,,,,,,,,;.

/

ot d failure of soruc wellIntentioned workers to com-he utilley. bas coled that altering the 1ountimig tleie' l iunicate their rntsf)vire about what was going on to the did not spet'DcaUy vlotate the plant's tachalcal spectn.

ouC f6clats declined io comment for fear of

& pna 2e @@ opmnonM me fa.

ca w

jeopardizing the ca.se. lim.e knowledgeable about it de-cility: Dose agw:lfksuore requira plant operators to be cribe a Ullitty desperate to keep its plant running in the able to detect radia00c down to e @ecifled, et'remely ace of a chronk prob 1cm wita leaks and troubleso:nc ' mggyg,eggee.ng,,,g,,,

s g*.

i

  • However,9%ett is evidence that tetility offbetah Laew adiatlos test results.

i The test results showed peat.S-rneasurab!c amousts, at the time the alftration was 8,nade that the specificg.

i

- of rudistion in plant wastematet that, while not postag gtions.were not adequate for ;#aacho Sece. Dwt it be-

,iny immediate t*areat to hornan health,'vl6 lated the cause, Un!!ke cuany other plahtt RaMho Seto is not on company's promise nr4 to releme any rudioactive waste, the coast and thus cannot deperu' on the Ma to dilute its J

l Officials finally released the coratnralnated water into wastewater, Dny Clay Creek near the piant eher chanElng the waY he NRC documer ts dhicuss a ssem[ffsm then ?,t$eb me radiation was mettsured. Instend of counttry radta-etsing liealth Pi,ysicist Ed Bredley describlag *hu i

l Qon levels for the standard L000.necarufs, the countin3 awareness, begi;ir. tug in January 1986,I. inst the ents 7a5 done for 1.000 setorwis.

(detection systern) may not be adequale to assure cem-y NRC doevuLe. cts state that Ranc30 Seco fesangement p!!ance* With reguleucas. *The mem6ttaduct, demstbed Jmentional'y changed the counting fimes *(u facilit. ate his efforts to evaluate the issue (and),tb9 lack of snau-o pc release of Ilquid as necennary to e titeve operatlo, ant "agement support.*

. eitraints* - to keep the plant rurming.

Another PIRC source giald mere kas been

  • conceal-Souren sam WW inknnH MD @M Maa-Y' eat of information that they bad some Jignli'cnnt ope Wary IM bat even M hhc measMnW9t PD' j

n ut enal problent De whole mellve is to keep running..r. cedure did not guaraMee comp? lance with feastal

~. Asine from altering the way the redloacuvity was re,ulations. According to a re!!able accout% officitia sp-Seasund, lees!!ptors are 6csttialzing the prectice of a.ny further study cf the hsue for fear it wcaid re.

P ysing fire bmes to fromfer wastew. ster for proceelag wal shgrtepmlngs in the ;/. ant's wastewater prticedurea, j

and ruimse into the creek. If that makeshini nstem hed It appears that officials Anew evec %efore then Ikst Mt'ed, the NRC.uld in vts inspeitton report, Otere cwld' their specificatlons were innittquate. And there h evt.

I"~

@ve been *nn unroritrolled :! case of radioactive mtkei. 'dence tent (tmy '.rted to prett et theonselves against it i I

'L-

~

hal to the surface waters?

ture violations' of federal regulettuas'deshsg with

} "Dey imlI a duty to report this,*ltid one source.

rt d'. allen esposure by drullog an escape clattse, '

3 i-

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us.=uctaan AconT couminio=

asc. mas uniti=a moonsu E'a'....'

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1450 MMtIA 1 ate, SUITE 210 Cif V FACSIMILE TRANSMITTAL I.T.Y.

REQUEST N CREEK CA f,,.,,,r. 6.

1sb 2d /957 O **

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_t mo ene.mst atso m P.cssess68 Posoma muassaa osaarssef som e. nome enemose

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4 NRC asks 39co r#> -official: Whom EF "do you trust?

ht.0 :

By Doug Dempster act meet a later NRC Standard bee Stof t wrlier MJ/T7 which $ MUD committed itself to meet in 1884.

Federsi regulators want Ranebo

  • We're asking them to comment Seco chief Carl Andogatal to supu* directly en those ladividuals -

late whether be sult trusts any re-whether they have confidence in mainlag plant management those ladividuals and why,* ex.

personnel who may beve been re-plataed Cook.

sponalble for radioactive releasse Thomse has laststed repeatedly that are alleged to have violated reg, that SMUD did not inland to deceive utations up to legs.

anyons.

-f to a strongly worded memo,Joka The NRC has conceded that the s

IL Marua, regional administrotor of discharges did not violate health the U.S. Nucidar Regulatory Com-standards la the sparsely populated misalon, told Andogntal to submit area but claims that SMUD vtaleted the informatloa by Jan. 88, promisse not to release radioactive Plant spokesman Brad Thomas waste.

L sold Andogatal will answer by thea.

Meanwhile, plant startup has been Domes said be could not asumate delayed from mid January to pobru-how many manager 9 the NRC wants try, largely because of nagging vt.

Andognint to vouch for. There have brauen and testing problems with been major staff shahe upe durteg the plant's giant standby generators.

the two years the plant hea been out Andognial said this week that g

of service, particularly since Andog-even without headaches caused by alnl took over the lagging restart ef-the generstors, a delay totalmg 80ur gg fort last May, weeka was necessary to catch up on g

De Bee reported in Detober Akat paper work that must be submitted the NRC has submitted a cast to the NRC.

s-En against one or more effnetals of the Top NRC offletals last tall metad is Sacramento Muntelpal Utility Dis-that while SMUD has made stridesin g

trict to the U.S. Justlee Department attitude,managernent and hardware r

for possible presseuuoa.

changes during the two year startop p

Neither the NRC nor the U.S. al-effort, they will not cut short the p

torney's offnes la Sacramento would time the agency staff aseds to re.

=

comment onthat Wednesday, view voluminous reports that SMUD F

Martie said in hit letter that, provides almost daily.

E based on a lege NRC laspectica, "That general concers remains

  • k-SMUD management permitted an Cook said Wednesday.

snauthorised connecties between he plant cannot be started up.sn-two water storage systems that could til the five. member NRC gives ep-beve al60wed radioactive material to proval.

escapeinto the environment.

to addition, Martlp said technl-etans had been told by enaabgement to cut la half - from 8J minutes to 17 miautes - the Ome itsed to ana-s=

lyse samplas from Cley Creek,

=l; where SMUD dumps its wastewater.

The shorter time, bkttle warned.

could lesses the possibility that re-dioactivity would show up la esces

=5 of NRC standarets - even if the tim-

=

tts had been s 1:eded. Previousty, P-the NRC contea ed that gMUD me-n alpulated sampitas methods to de-L eelve regulatom.

b NRC spokesman Greg Cook sand E

the lower count time met techalcal E

specificanons written when the plant g

was built to tse early 1970s but did Dif-lb w oo-c. ;

g SMUD psnalty e.m l g 4 C' -

4 fo' r water is

o. sal"3:It

@b. JM -5 e

l V L4 i,

NRC punishment for radioactive waste water could ' affect license i my ANNs Ngusa

/*V3//57 wmv Q(,*.en ampMper pendem anidany,yy y y

"***** *e8e ** umu I

he' Nuclear 'ResWatory Osambden said Wednesday at wul take memos agalast

' *" t,ast year, to NBC.need SMUD Nft,006 hr vietations etsammhg Gua as evensab:

sMUD ser saleasetag reenaeuw waaie

.cator at Ranche asse eartag test.. '..

, las sneldent met samt dews memote een, la a two yeam ap he remainsthest.

leser 'te me

. 4 eek said t o Baera,mm.ete af

'Uttty Distrlet, he h esasemed that tederal aponey said M te dotarsunag "thee. ' "there are people that wem tevolved te.

these lastaamat met am sem there." *.

estant et.ma 'estersonant motion ta'ba takes,lorduetes what acties if any she he regdatary assaey wasta to,lms he takes wie supon to ynur, besses,." Wd "what has happened met would pNeiste Sigsod by NRC Repenal Administrator. esos miase tren hoppealas agnia."-

Jets 8. ntartta, the letter resdres SafUD Ceek refused to comment se b mitaalt wittig st days.......

an asseauseat of nporte tho' matter has teen turmid what ted to the eer to the UA. Department of

..

  • lt Mes Aels Jetlee let peestde frieslaal prese-

. A n d ;. ;nt to austear.eddei Casi suusa.

latth and een als whomer he' hat " fun

  • SMUD spokemana trad Womas la he' asement pareassel who were,pneemt man.

Aald SMUD hee trod as workers er m heen, leveNedis thess matters." ayhave.

over the talebandung.

heIfRC's poneng acusa stems'tross

.a sut he aald Andegaial, who teek as tevest4gethm'inte discharges by StfUD sever the Ranche Sese restant pro.

of low 4evel radieneen waste waner sein Aram la Juss, has inade changes in

.Iley Clay coesk.. t ptet manasement ans procedures.

tDe kmutisette'sweeaned.that.6eshG

.. Mon management changes am einen at Raoebe Sese ethanged to w6y. antkdpated, Thomas makt.

eley ameasured releases et weste water Of Um la Manche Sees emplerus from the pleet,'.allowleg esetestve ; the NRC geseuemed thmingits loves.

tigetien. at least seven stul wert at assuntoaf." l., tele!sts week, p,

! g, g o

la addinea, plant mastgen permitted

.Two et the remainlag workere -

me usiet a am base and stammepipes'to

! Steven Redeker and Fted EeDie -

esassa two water storage eyelene at the-s meses o.

4

.o' sek seted that the NRC later..

plaat.,

Aseerdag to the NIK"4 letter",'the prM viewed the workere, but that dose em em med

  • in n eamed and mus.
  • met eneaa they were levolved la the perted pe44twiny fer disoberge et redlese.

gue,name,rmusm.

evity te mm esversemenL" A9c Osak eaued the apparent viele.

.EnfUD has adentiped ate 2005 relea....

ses at

. upas "a very eartees matter." SW

' vedinastive water hele CRey Creek'essese'

he added mat R le sattely the lemus ed feden) goldeLhas. Bewever, se health

.wW anast the restart af aanche and estety luatte were violated, SMUD 3,,e,

' 4tfUD bepen to have Wee plaat osatande.

NRC spokesman Ores, ceek eald

pieducing power trylate February.

..Anar its hveeugation le sempleta.

} Cesk amid the NRC is teely to lemus hasues er vietaties. no aposer's laterdi entortement actica wul be e.nnouseed then.

,,,,,,,em ma M6 olo-I%

'"""" D

\\

N,.

M g/tQ & tf.7,y..:^ seq *..-...m.f C.,, m,

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a te mese,m,,a,t wac tcvenem

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M e. c. ' r' W.~.:

h4

[

Q

  • g W ne n

. PS Y'

me n a reasessue u nt u an as, i

i elated met plant officials seted wnu-J (Elly or latentlosel

$e h

g7 O

Wielensesof regungens.ly to hide (W v(

In 26s casa.

the lavestigettve office is said to

%#v.

/

b45 V

have t 618h segree of teafleette l.y,.e..ma.a Set wit!fulne no ua 3sswas,levolved.

ne ma a vese.reia m * = = a;,,,1 y

.gt..

e.e e e e=tema..d i

.to cau=4 am 3,

sud 3,wA,,y commi ies s iusee.<

W6.auerWas e Se,gQy,,g m a h o w.a c u ar u. nty ern.

h=8*,3,HINGTON - De Musear e im.upues.e4 t

bus lasenters A ama ma t=

a ofgami ain ome tLaa.but had hvuupuc there kaa been euc,eme, a it.

= c=e.#,,as burnu

eu sea mue= ga,,,,.nas sent mue..an me ncais e,,m,an.

an=ua===5.=enm.,n,,e, d

case 3013 te (to Jusute Depart.

,s. e,eanea eu. ne dg w.se,er.

ed m,=m woid m.m.e uvo.e,a 1

'v.s. nwan== e,,,,,,,,,

wha move a y.w.pime '.

1 ble Pfwecution, mune.4 men.

r,.inc dee 1

any triminal wnagn..

any.. -

though me wefe##P '",4,,

m.de W neum mr gg tavestigstlet reperledIY I#*-

were set seasidered termg,, g, etag? Th m es '

t esiv.,eversi rom n a arm -

actshbors arwa4%W Plant at emid.*but we teve se waitand see?

h m

ins,e. demrmiad n= =,,,

e,n,.e five,et,e,ter be,,s,d h,at oupervtory egglegaig at me plantWH-Bee,geweter)me 4.oroek empid b4Ve '

about se levesu3stiva affice's flu,

of using fire beets 2 trthB eN c 0,,ed w,,,ta,e4 an suspected of meanpulattag #-

.epes at the niesse et rednesetive,'

,g gap M e Need.dow enmes lum.'

ke w'as uscentrolled' release eid.

'wasteweter..

elescuve motor %1;ta,8.e yerhoe fore me board met puWiely wie;

.,The ease was dell,vered to UI'.AA*

Suremente Municipal Uutify Dio.

ters?

The high4eielggMUD,

  • sia...

trlet off6clais sa Oct le to tevtew efDeivld L'EvTTRfliie IUa. cts-Ranebe gece's pro i

mente vieta Se

.fwe weetB.

50es, wh6th looWinto snlopuens W accordlag to mese lar wle me.

gelserste wrongdelng such as tylag starttagisreneur. pees towere re.

The reafter was h=W ont of Inquiry.

6 er misleedlag government neu e' i

offbeats wire to NAC refuest to

' tors, tes eseducted'the NRC's ledg.

tervlee nearty two years ap duttag:

discus the mar.or, and Levi sela. *t-yy, Yne revtewbfeceses en the an everteoling leendest eat esmoi l

decline to commeat" 08 wheter te -

ocuens of othc1&ls who me la maa.

teared could have demaged me re.-

i has received such s'ese. But'ene agement pasideas la vtMeus pgg actor vemest itself. Thouga It turnedi i

u.cwiedgesele spurge said me MM tenartment.

out that was sent e earless threst) heugh a sumber of mese gr,

,the, sceldest ultimately espesed eerk-was thand.delwrw? and mat po.,

y gg,,,g,pgg,g,,,,,g,,,g,g tenualvlonattensinvolve*maalpanal ?

Sted my me ortginal tmsopuca.

the preceduru to meet Geir eseda?.

ve slace left la erempmg Mr*

There beve been alleptions that.

heul of Se that$nanapsment tun.

man'a'gemenUn~atNe'rtento ese 5

~

Ranche Seto Personnel change 6"'

  • nse et two* are, tale le sbu be,sa ;

clude me plant should.De metatah:1

, g,g,,

their precedures several years ago me payren.

,,,,,,. y,.,,g,, q for mealtering realausa la weste-A referralto Juance is a senes M*

Adding furner, uncertstafy. Pactf. t ties by the NRC.4stitdoet ut es-nc Oes and Electric Co. has made s ?

see SECO. beak page, Alt w n prosecutlev 91) N #Ve 88Nk II.

takeover We for SMUD.andsevers! * -

vttilus around Se eeuntry art sud d has referred M f9PGto 4W88,fd to be laterested in maag Mr me

  • I recent yests.1M igve88#U '

I ebmined Went ceevleteak Anemer

$btVD claam handleit.eetfttlea of the ne SeC n com we wtimmely #t" 1

for prosecution bdustie which h-n m nt sigas, ne w m r. p ut es e.1 4,

ae eineiess.en tst siir er i e* *e restart earl e a se,i. Lacatyear.The minu NRC staff and SMVD. betweet Centleved from...

f,,'

g efflee's lavestigstery stDis la lesd*

m.o.

page A 4

water releases to evold detecties of mony before Congress < *.

officals lead. l peale* La redloacthiry whic6 that The NRC ls as:d to have felt for furter weight to this concim!sa.

be steve defined levels set by tee some ume mat it nad a powerfu

'At h p ulelen W tH m e g.

ease at Ranebe Sece. Doe searce eus-the NRC stoff achnowledged matets-NRC.

, L 1 * ' M

Citif Wilco 8. $ree'ldes' of the

' side me NRC called it strong and as-altlant program sad besa made m.

t soar said Meadgy sat it Asemed ward restart and tatt the restart 3 MUD board, sold Monday might

  • .,...s*

age NRC bas set told es want is go-echedule presented by 3 MUD ap. -

p, eared realisuc.* esy me sus'ates, lag en' and he was nM aware tnat the case had heta turud ever to the blet were released by 24 NRC Justice Department; He es!d be had gg g

hursuant to e request by a reporter.

am been contacted parsonally obeut e 5 MUD schedule propeees to be-31a nettir the investigation, see wasn't sure what the telal ramLficadoes might y 7/ h January ns up the reactor la mid.

At tee NRCpubile moeungoct. lg, to if me case were prosecuted, W1;ces said the enacrepanctes la commissleners espressed uttsfac.

L gee wtg me ambitious program of moniterlag tse wastewater were ac-c7g cleantog up bee the plant and as tas!!v ettected and reported by f*yggAyf I

ss.l,D personnel and that utility offt-manastment. They added, however, cais consadored $st the lasus was that they want furter ev6dence of

'Just a queston of bc7 the calcula.

.'stabliltf witnia SMUD, whica has tiens were done? We said me men 6-been hampered by internal diesea.

torlag precedures ' heve been sten, as a proceneluen le adowmg changee since tbt discrepancies the uclear power plaat to get back i

were onscovered.9 h 4 -

(soportuen.

11is unclear what effect te leffe-l (Chb this process. s Radtty Wiu have se tiptive office' N.(M.ooe ug*

tM6 -o40 - l @ I

~

_ _, _.. - - - - - - ~ * ' ~ ^ ' " ' ~

qs":'?"

a+ Al LK U!I!!$!!I og!r$lp,!!r![p!i

{ ij; ki illif

"'II*"gi"

.E$I!!!d@l!!)/

u-e i s!I!!!lli

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T } UlI 11i gi Pii Q 's.1, i{lI!!l1191 t

it!

.. A Dc gi>ll}'

j!I A ema h

! ! ! ! ! lI k i N i i l

Og7'"

?

i ini i

g y1 i

if

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@ Mi f 91 I

g6 31hisliHijg!

O

,(

,n

.w-an.

sue-~---~~a.--~.~.no.

n.-

-a..wa+...

-me

-.s.=

, s. mm n.a-s -s-ra mx a aas

-a mn. a mes a m. wa. - a..

.a s..ax-s.+~.a.a-a s a s, 4

Y R!!!i]II'll!p113 I

i ll

}

l%if8 @ka$u

ma,im v

~

l SMUD board president d

~

~

W'C@X quits, cites, divisiveness, h ~. penet ere,ete eso.gh Jo.,eee. rom,e,..,

m

.esee e _ e. e.ed emer.

.re,ddes, <or,es.oe,de, 1

" " 4" gy systems he new homes he aap Wiscos deptered the atl80ty's senet g

recent rete lacrease of an everage of

.t t Wiken's decidea-a esso St.

g9/

w Aeg,

- * '""Y so e h gne apt are if 8 percent. which was _Q 3 to 4 per-I 2e on a 3-2 vese, es he 8FDeeg L f

ese seen Wete' cestage potets *htgher thee It ereded to be* end casepteleed obset Cttff Wtteet, president of the seeks om heard defeuerettoes to se-leWer k the NRC. See med he W SMUD heard of 4treders, reelped ketenew W w the Aug. Il letter to the hope test Teesday. haemeen sewmi %

Secrementees witt have es seech in-hoe'd mesnhers for tweMug "evi-WDcos etse spectAmsty criticlEEd g

formattee as poultite betere ment directors Jake Kehoe med Fd Stee-Jone s voce ce e messere test womad a

58ventsL*

i rve had It wth 35 me pellikst loff for artthe to the U1 Modeer ekwar the secteer poemt -

4 Regeledery 8 m===ammann to regnent a reatpenflon k efsee9ee ammedletesy. heartagto Secressenes ehest wheft-N' N The seere apre we cae ese to this

! eeseelgens sold Wticos.whose Seeme e$ensneetty em answersag canceres t

  • $ thtak N's en esfesteeste Beal 9er er readers such as et SBSUfFs IdBe l

Mf WEpeat slee C995tland shout the notegrity of the peast, the (h.

" Maedctiet Uttilly Dis-bewer aff we*B oft be." Ketboe said.

trect) and the cessessestyr seed vice seeWea.oex.peSe All WeeSetectrute h h e, W8Bces completoed GBust the treter 6

I i

was em SasuD seetlesery moeten w I

idet likeit was a boarddeetsloe.

Kehoe said clerecet steff seest j

have gdched the stageoery. f just i

streed to costem the tener heseed.

^A has served he se acting deel do either wtInde met time, the power to repiece the 983messweet Socransente Cseety Board of Super-acclear pessW if 588UD dendes so A few days earlier.a board analortty s,

71stingof the letter was poor.Wti-la giving up the pert 4ttee. $8094-visors has 30 ders to some a succtsp-seH e portion of it.

l had rejected seedlagsuch a Reger.

cepectty for I4 moneert Wilcos subenttled a letter of reeg-ces west on.becease Iteache Seco ts eneset direder's jeA>.Wtkest else cit-ser. ff met heard does not act, mere seemen, het e SMUD speheswomme i

very etmeeto reisert and thecffort ed me setese rose servense, voted for wist he e speast etecnen.

The soccessor, who wita serve refowd to reveal its ceseents.

j by Kehoe.Sanetettmed Koemder The three were swayed by staff througpt 1999, erneut live Im Ward 4 Kehoe seed the letter, whkh was isla m, a handa 11ge glemt weg dent le late 1985. The closere has espleestfees that shewing the in-whkt lectodes nee 44 ef Satressesso read to hise, noted that se shut dowe efter en evescoelleg fed-crease as WHeen wested could Comesy snest of Breedway between board seemberswere trytogto pnftN-teigesed a settes of rete tecresurs stretch SBSUD Remecesse ten tibet N me Serranneste River and SHgitway cite iTunes et a tisme ween she othry tohoy sepIncement power, was tryingen bringehe necIcar pt,ef 3

Reptding the selection of a per-setWit have trouble horroutet amon-pp-i Wtkest, first elected le 1982, we*

tieck es line and regate teseiscial ste-Q meneet steneret semanger-detstyed ey to aseef greet.

reelected to Iges and etsoserwd as me,ty, i

setore tites a semelte beyond the Aug.

Director AseTayterfeinedWteces m

le vattes agudent the tervense be-beere president ist 1985.

" UC'" '*I#

i y

9, I target date - Wtkor coseptelmed. cause it west etehele a tiestet dis-le his Mrst term.WIBret e/ bwe % mech h eeman j

"We eieve e closed sesdom, esed tie-

/'

fore it's over nosectody is cataegme comet rete to hamme,hotds per hesic SBRUD ces pcteettet homes by sethseg two or mne beerd mnebers, met y

senedia med directadog wetet we es. <genottfles of electrictey, lovetter-poet or set of Reache Seco. het re_

the heard has " lost sigpit of the jot j

owneed atttIttes such as Perific Oes ceived Istate geppert. Other dirwfests mM nwds to be dose to peereme)e j

Cwssed

  • and Electric Co. have had such dis-keve slece s.1..w" the idee, and
    • '"#*L "#" ****I "I

b Searces trove sold S. Deved Free-in June. 5800D eshed etettlies and

  1. 8"'N

'S' armen, former cthettman of the Tese-counts severst years.

Under the state law that goverws oteners soserbereit efters spegere Valley Aomority and energy cegtesser-owned ettNtses, such as Waltwa etso broke ground by sus-Kehoe speceleted that etteer fac-lors la Wdron's dechion snay have l

edwtser 00 three presidents. has hece offered the jeto. thesnem and me di-ShfUD.the other toer direders have gestistg ion Jely that SMUD seet hids been fannify illness and a fare f i

rectors Itave decreed comuneet. Wit-60 days to appalet Wilter's Mecces-from botta utility med see-esitefy liefe Lethem, a 26-year SMUD ser or call e spectet electies. If they soerces ter up to 400 senespeweets of Elk Grove tissioness.

..O 34 Ihe becreaseene See. TesseJoAMay *a, TSer

  • e pharges of 'mproper Seco visits probed Jetta Joltases perled the accident involvtag sa overly rapid cords to obscure GBe fact that certain crucist coef down of the seector vesect has kept the plant cables were lacerrectly routed threagh a fue dan-r esessurees set of service for 16 eioetts so far.

ger asse. This case also began as am laquiry..

N' womhte 8

With a new managem est team revamping Cook said that he (guld act discuss detaits of p,

~Y~

I 0*

N keEher'ptsat presatses have prompted hopeful of bringleg the plant bach in service Ibis by tee Offste en ImW:"9"~~ Thf ef15

  • mer-

.}

t g

g,,

sees sense,metamm et poteetlany criedmet behavser.

l

- fan.

vestW at the power pteet.

An offletal at Rancho Seco sam he was encer-such en the sessifytag et decoments and sytag to i

TJte Nuclear Regulatory Coenmission con-tale what circumstances the NRC was research-regulators Many of their cases have eventuaNy Mooday that what they called an *henguiry* leg la its inquiry. The official salat the only been prosecuted by the Department of Jesske.

hE been opened as a result of the attegattoes.The lecident levolvsag unmisthorized visits that secur6 A source who asked met to be ideatiNed said the

$E.ident. which occurred tn 1935. ls believed to in-ty efficials were aware of levolved ao ledividaist latreder case is "being taken serleesty.* But he l

1styecharges that plant off6cials who did not have being allowed oc the site by a person who ao long-added that se Ser lavestigators have act escov-ered wreegleseg scrises enough to be alorsned.

-ac sethertty to do so approved visMs to the facill-er had authority do50.

Admintitratively speakleg. on lastulry is one The receit signancast case moder review by the Q.

CSetts a charge is potentially goeriestas becauw step below a tut > blown lastsligation, but NMC Offece of Inveshgations coeceras a report that J

are strict rules latended to prevent unau-spokesneae Greg Cook la Waleet Creek said tacse stility managers ordered staffers to measure the people frosa entering a nuclear power isn't a great deal of Jefference, except th.d'an tw raessoactivity of thstsid effhsent for only 1,000 sec-plast, which contains some of the most dangerous vestigption is larger scale and rmeRs in a larEer onds rather thar. the rettelred 2.000 seceeds. That smeant the theel readiaC woesid under-report the equipment tesed by private industry. if true. It also report.*

roekt underscore ettstated concerns about deft-la esecy cases. ao lagelry results in se lovestl-IcVel of coa 8===eameian la the geler beleg Risshed clencies in paM operating procedores at the Sac-galice after scrutley, as le the case of De poeca-from endte eterage tanks inte Clay Crect, which rassento Municipat lMittty District's Rancho Seco. tially more serious allegations that SMtJD flows eft Rancho Seco grounds isto publie proper-Some NRC officials la Washlagles had otten la off&ciats saaelpulated radioactive sampflag to ty.

~

the past charactertred Rancho Seco as one of the make thefr retenses of contamleased water con-Radicoctive contamta= net have tafected the

- t nat oa's problem plants, even before an over cool-ferra to regelrefacets creek, fish, frogs med adpscent farse fields. The t

" lang accident on Dec. 26 t985. One of the most se-That lavestigettoe is selH umder way, as is an in-NRC sold. however. the level of contaminaisess is c'iylous;tacidents la the post-Three Stile islasd vestigation late the possible falsification of re-not serious enough to threnden hissmaa heath.

LC

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i CounterfeitValves Found at Diablo, 2

2ndNuclearPlant

  1. #" ***'"'* *'"**' " ".* ~

~

~

~

c g r a a n =,s VALVES: Counterfeits Found at 2 Plants-c" r,mes st.11 w,ue WASHINGTON-The Nuclear

  • Centlemed from Fage3 Nevertheless in ~ the ' case of whether'they were'used in safety-Regidatory Commission said Toes-9 WY.

valves alone, the NRC said plants' related systents.

i day that counterfeit valves have In addition to DiabloCanyon, the suele as Diablo Canyon may be.

At thnes during Tuesday's hear-been found in at least two nescicar NRC said counterfeit valves were using as vaany as 40.000 valves in ' jng, NRC Chamman Londo.2ech '

plants,includingtheDiabloCanyon escovered at Co_..c.s Power safety and non-safety systems.. seemed irritatd m star'sneen- '

)

faelhty nearSanLuis0bispo.

Co's Palisades nuclear plant near Given the large number of cosape-bers who kept palating out that-Pacific Cas & Dectric notified Kalamazoo.Ifich..wheretheagen. nics that sett valves to nuclear 'someof thepartshadbeenfoundin i

the NRCin April that it had found cy said it,had identitled.about 65 *- plants, some sources said they fearE non-safety relatM p**h far I

60 counterfeit 2-inch valves in use valves that cordained parts that: that counterfeiters sney have see-as I*m concerned"he add,"every-l at Diablo Canyon in systems that were believed tobeconsnterfeit.

were not related to plant safety,

. Tine NRC said it still is trying to cessfctly Infiltrated nuclear plants ~ thing in a naclear power plant with theirpredoctsona widescale.

inwntressafety."

agency officials'said at, a public determine the extent of the prob-1 The labelson thevalves found at.'

  • ggg gg, hearing into the counterfeiting.

Iem. "I can't imagine this coeld r.~ Diablo Canyon indicated that they

. Investigations of the use of coun-problem. The valves first came to only be Mmited to two isolated were made by Henry Yogt Machine '

the utility's attention after they enretsmstances" said a high-rank-Co.of Imstsville, Ky.,but company, terfeit parts, according to Winiam i

startedicaking.

.mg NRC efficial who requested efficials confirrwed that.they were..Hutcisinson of the NRC's Office of I

Officials said the counterfeit anonyndty.

, ' counterfeit. PG&E bought the '

I valves that weredescovereddid not

. vaIves from an' e' disclosed 90stetstorsSelded o

endanger the public.but they add-3,,,,,,,pg,,g,,,,,,

SouthernCaliforniadistributor. -

Since Jtdy, the NRC has raaded ed thatsuch devicescouldconceiv.

The discovery of,the valves Is

'the NRC.last summer warned le ditlerent distributors of circun '

ably pose a safety problem if found the latest in a recent series of owners of the nation's,110 rimelear breakers that One agency alleges to be in widespread use in the disclosure's involving counterfeit plants. to beware of counterfeit nation's nuclearpowerfacilities.

material at nuclear plants around -. valves. Last FViday, the cormes-. sold coun'erfen or fauky W sment to nuclear plants. All of the Cook said it would be" extremely the nation. 'lisesday's public hear-sion sent a special notice to utHRies' conipanies are in W Cahfor-i unlikely" that failure of the coun-ing was held to announce, the

.astung them to be on the lookout g

terfelt valves would here caused results of the NRC's first-five for. counterfeit valves like those h NR W N the release of dangerous radiation,,

months ofinvestigations into other recently found at the Palisades -tics and Space Administration and

~

counterfeit parts that have beeni plantin Blichigan. -

but similar valves also are tased as

=,

l part of the plant safety system that found, l'icluding circut breakers.

Like these at Diable Canyon.the ave I

i cools reactor fuelgrith waterin an pipes, fittings boltsandscrews.

. counterfest valvent at the Palisades.

.down count ters i

Flease see VALVE 5, Page 3g The agency said it has not turned. plant were found when they start-t upanyexasspiesofsafety 22J..o - ed to leak. The valves were sold

    • 7 caused by these parts. I don't with labels that said they were, into commeressi jetliners and the

~ 'E***

    • *N 88 think we.are close to... any manufactured by' Masceellen-l Idangerousi cliffs ** said Brian Dresser Co., a Norwood, Mass -

Crjenes, spokesman for the. corn-company that said the valves were C. U Crouch W h l

miesson's Office of Nuclear Reactosf rebuntcounterfeits. ~ '

. ConsumersPowerCo.did notsay.. t.se Angesse and-spoug l

Regulation.

-I

- freneW e

-em 5

Of FILE REVfEW t

T0:

Q6-R4-c/o DATE OF REVIEW:

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/98'6 CASE AGENT: //fM#.S REVIEWER:

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o
O SLHMARY OF INTERVIEh' TRANSCRIPT OF ROBERT /.. DIETERICH CASE

5-86-010 I

Robert A. DIETERICH, Assistant to the Department Manager in Nuclear Licensing for the Sacramento Municipal Utility District (SMUD), was interviewed on March 25, 1987, by philip V. Joukoff and Owen C. Shackleton Jr., investigators, Office of Investigations, regarding q

DIETERICH's knowledge of SMUD's management and operations of the Liquid Effluents Release Program at the Rancho Seco Nuclear Generating Station (Rancho Seco).

DIETERICH began his employment with SMUD in 1970 as an Associete Nuclear Engineer.

He rose up through SMUD to a Supervising i

Engineer it, the Fall of 1981 supervising the areas of licensing, j

environmental ectivities and the As low As Reasonably Achievable Program j

(ALARA),

in 19EE, he was moved out of the Nuclear Engineering Department l

and was reclassified Manager o' the Nuclear Licensing Department.

in the sunmer of 1986, the Management Assistance Corporation (MAC) came in to I

tr. anate e performe.nce improverent progran. MAC brought in an individual i

te renage the Nuclear Licensing Department.. DIETERICH was made an assistant to that manager (pp 1-8).

Re information listed below is a summary of the interview transcript.

f I

Special Report 84-07 1.

DIETERICH read Special Report 84-07, dated September 27, 1984, at the time it was generated (p 9).

l 2.

He did not know who was the author of the report. He assumed it was Ronald COLUMBO, head of the Regulatory Compliance Group at Rancho Secc.

This group has the responsibility for all reporting activities te Reaion V. speciel reports like this and licensee event reports, etc (pp 9-10).

I

<-.Y, i

m n.<, c. ~

?,

DICTET:L4 hii-no input into this report (p 10).

Scurces of Contarcination of the Seconcary System 1.

Steam generator tube leaks are the major source of contamination in the secondary system of the plant (p 12).

2.

DIETERICH did not recall any other sources of contamination for the secondary system (p 12).

Temporary PVC Line from the Demineralized Reactor Coolant Storage Tank (DRCST) te the Regene~ rate Holdup Tank (RHUT) 1.

They have always had a problem with tritate water (p 13).

?.

The intentirn was te evaporate as much of the tritate water as possible if there was an excess (pp 12-13).

l 3.

Under the circunstances, he believed this water was discharged. He was r.et sure of the exact discharge path, but it was discharged from-the plar.t (p 14).

4 He does not know when the PVC connecting 1dnes wers installed between the DRCST and the RHUT canks (p 16).

5.

He did not know of Iny f orma'i notification by SMUD to the NRC advising them of tne installation of the PVC ifnes, He fel.*,the NRC 4esident Ins,ector should have been aware of the lines and could tossibly hat e Seeti ' informed (p 16).

6.

In his opir. ion, the Commission should have been advised of this no'li' i :o t i on m: roviac water from the DRCST tank to the RHUT tanh u n t'c

'O frn R Sc,.

1A_:'

S-36-010 2

3 7

The Eegulittory Corpliance group within Nuclear Operations had the-repnrtina responsitdiity (p lE),

8.

He is not familiar with the history of this modification, Et does not know how many times it has been used (pp 19-20).

9.

There has been some discussion within the Plant Review Committee and within the Management Safety Review Committee. He thinks it was more in terms of plastic cipe is not an appro9riate method to transport radioactive material around "d.e titt, that-it should be steel pipe and done with a permanent modification rather than a T

temporehy lash-up (p EC ),

[

1C. He believes the responsibility for the modification wou',d lie within the Nut: lear Operations Department (p 20),

11, iie dons not know who tne individual was that initiated the work or ms respcnsible for letting the verk happer (p 20).

Pret'ler, sith Parcho Seco Beino a Dry 5ijg 1.

There are several' problems with kancho Seco beint 2 dry site.

Not all are. related to ridioactivity (p 21).

~2.

~ They ars. limited to discherge; not,iust radioactive discharges but various other solids and dissolveo matter in the water (p 21).

/

3,.

Blowdown frcm the coolinn towern has to be diluted in order to discharge it from the site and meet various state requirements I

(p 21).

4.

Orr of the problems they did rot foresee was the build-up of tritium,

'i cy made " c' wri tnar,t te in ru:lic te not discharge radicactive -

Ti n,' W

+.r d4 rbarra Y tiun certe e'ly d

licu m fror tho :m n

5-06-010 3

f withir the license Timits but ilotlwithin their commitmer.t to the roblic (y EI).

1 I

5.

He did not: know what r.ontrols were imposed to insure that water mi transfer ed.between ORCST and RHUT tanks was properly sampled for radioactivity s'p 22).

6.

LE knows that once they realized they nad a problem that somehow the

.y

.f radiatiin a'id chemistry protection people did do sampling or

[

~

performed ~cale.lations to make sure that Tech Spec 3.17.2 were not l_

exceeced(p22)..

7 Concerning the t e?tast of water: from the RHUT tanks, he knows that

thc Chemistry and Rat lation Protection people would do an analysis and. determiile what the rele.tse level would be. They would then obtain perm'lssio1 of the shift super 'iscr to make that' release f

(pp 23-24).

r F.

He did net know whether or net the water in the DECST was v.onitored for rf tica:1.ivity prior to being transferred to one of the itHUT ta nk s.

he knous the water in the RHUT tanks was sampled before release from tbc site (p 24').

Pethod of Samplina RHUT Water Before Reh ase

?L 1

He was aware that the Radiation Protect'on personnei did sample the RHJT water before a release was made,.ralculation was inade to deterniine f f Tech Spec 3.17.2 would have been complied with, and then it was determined if the release was accep:able (pp 25 26).

~

s-2.

He did noc have any direct knowledge w1Hther or iot relesset made frcm the plant during the time frare after Special Report 84-07 were in cons?> ant.e with 10 CFR 50, Appertfit. 1, as reauired pu.suant to Tech ica'. Specificatier 3.17.2.

ht knew there is some que tion about the releases being in compliance with Appendix I and this hu

' 5 -8 f>- 010 4

m-

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4 i

4:

in de witb thL scrsitivity or the mininur level of derettability cf -

some of the sattple; thpt were made (p 28),

- He 5 as no responsibility to assure that Action Item No. ? was

(

3.

1 implemented n si,ated in Speciai Report 84-77 (p 29).

4.

tie assumes dilution of liquids would occur in the retentien basin before release from the plant (p 29).

E.

He was familiar with the report written by Mr. BRADLEY regarding the lower limits of detection. He does not have any tech.11 cal ccgnizance of the contents cf it (np 31-32).

6.

In his position with the Distr-ict in the late NS5 time fram? he would not have been irnolved with the activities that Nr. f!PADLEY t;es disco r ing in his drrf t report (p 3I').

7 He is aware by hearsay and @at f.e hes read of the. count time'used ta measure radictier f ron liquid ef fluents at Rancho Seco.

He is cware that there was a 2,000 second count time, whir.h was subs *quently changed to a 1.,000 second time (pp 32-33).

6.

It is all hearsay and his understanding only -- that it was determined that a 1,000 second count time was acce pable, and 't c

would provide the sensitivity to detect compliance; but, yet, was low enough that we could make dincharges wf thout alarming the public of excessive releases.from the site.

It is his understanding f ron' what he heard that Fred KELLIE authorized the lowering of the count time (p 33).

9.

Neither he or any individuals under his direction would be involved in the reporting of radioactivity in the effluents (p 37).

H r-m fer:iliar e the reporting by the Lawrence Livermore Nationti

'scretory (LLta) c' cesium 157 ir, oownstrean sediment at levels not enticipated (p 39).

5-86-010 5

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NRC REGULA10RY REQUIREMENTS

.l 10'CFR 36a Technical SpFCIfications required demonstrating adherence to 10 CFR 20,106 and 10 CrR 50 Appendix !

limi ts.

l

- Semi Anrual Effluent Reports are required reporting the amount of liquid effluents released to the environment

- All information which allows NRC to estimate the maximum annual radiation doses shall be reported in the semi annual reports.

LIO CFR 20,106 The EPA standard for NVclear Plant Operations - 40 CFR 190/ annual dose of less than 25 mrew to an individual-snall not be exceeded by effluent releases to the public.

If the cause of the excess releases-is temporary and corrective action has been taken, a variance f or continued operation can be granted by NRC, 10 CFR 50. App?ndix !

Requires the estimated annual dose from radioactive material released in liquid effluents not to exceed 3 mrem to the body and 10 mrem to any organ,

- The licensee is required to establish a surveillance and monitoring program in order to provide data on liquid relear.es.

. The licensee is required to identify changes in the unrestricted areas -in order to permit modifications-to the monitoring programs that estimate doses to individuals l10 CFR 20.405 Requires licensee to file a report to the Region within 30 days if releases of radionuclides are in excess of the EPA standard of 40 CFR 190.

- The report should describe the cause of the excess releases and corrective action taken and

- the extent of exposure to the individual, 10 CFR'50.71 Requires the licensee to annually. Update the Final Safety Analysis Report so that the NRC is aware of changes made to the facility.

10.CFR 50.59 Requires the licensee to make a safety evaluation for proposed changes to the facility as described in the Final Safety Analysis Report when the change involves L

an unreviewed safety question.

1 5

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RANCHO SECO LIQUID EFFLUENTS PROGRAM g'

Backaround f.Y j

,,j March / April 1984:

'SMUD's ODCM found to be in error by affactor of 25, impacting on effluent releases since 1980.

May 1984:

SMUD filed a Special Report with the NRC based on the ODCM error. 'The report indicated:

The maximum calculated dose for 1963 for all pathways was 108 mrem.

A WBC of an individual living in the effluent pathway for the 1st quarter of 1984 was 12 mren, thus the limits of 40 CFR 190 were not exceeded.

The cause of the radioactive releases was due to a primary to secondary steam generator tube leak.

Region V requests NRR to confirm SMUD's May 1984 report in order to determine whether a variance for continued operation.is necessary.

In July, Region V disclosed that the irrigated food pathway parameter was not included in the calculations for the data in the SMUD May report.

SMUD did not inform NRC that the land use parameter was omitted.

July 1984:

The Rancho Seco RETS are implemented.

September; 1984:

NRR reports that the SMUD May report data does not support SMUD's assumptions.-

NRR states that 10 CFR 50, Appendix I dose objectives and the 40 CFR 190 limits have been exceeded, and there is no apparent justification for granting a variance for continued operation.

SMUD issues Special Report 84-07 for the first eight months of 1984, stating that SMUD had exceeded 40 CFR 190 limits with calculated annual doses from liquid effluent being 185 mrem to the body and 253 mrem to the organ.

The source of the problem, the primary to secondary steam generator tube leaks, had been resolved, and the pathway of the releases to the environment was through the RHUTS via the secondary system.

9

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Near term corrective action included instructions to the Chemistry and Radiation Protection managers te sample the RHUT and control the releases so that they were in conformance with Appendix I, Tech Spec limits.

Rancho Seco was limiting their discharges so that 10 CFR 50, Appendix I limits were not to be exceeded and a variance for continued operation would not be necessa ry.

November 1984:

NRR notifies SMUD that a variance for continued operation-is not needed because of SMUD's commitments in the-September 1984 Special Report 84-07 not to exceed the limits of 40 CFR 190 and because the near term corrective actions that had been implemented.

Fall 1984:

Pierre OUBRE, SMUD's Plant Manager for Rancho'Seco, makes a public statement that the plant will not make any

. liquid releases containing radioactivity.

April /May 1986:

Region V Inspection Report 86/15 indicates that the radioactivity released in Rancho Seco's liquid effluents in 1985 violated Appendix I Tech Spec dose objectives.

Rancho-Seco's Radioloaical and Environmental Technical Specifications l

May 1979:

Rancho Seco's draft RETS was sent to NRR with the word "not" in the bases of the Tech Spec 4.21.1.

Insertion of the word not indicates-that the levels-of radioactive

-materials in bodies of water outside the site will "not" result in exposure within the design objectives of 10 CFR 50, Appendix 1.

The word not was inserted because Rancho Seco was a dry' site and'the design of the plant exceeded the ALARA Appendix I provisions designed to comply with Appendix 1.

July 1984:

Rancho Seco's RETS became effective with the word not remaining in the bases of Tech Spec 4.21.1.

Modificetion to Rancho Seco's Primary Water System

. Inspection Report 86/15 revealed that from December 1982 to March 1986, a-modification from the Class I DRCST, in the form of a PVC pipe and hose to the RHUT, allowed water to be transferred from the primary system via the DRCST to-the RHUT, for release to the environment.

L

-- The modification was'not reported in FSAR updates, as required, showing L

a different routing of the primary watar and its release to the l

environment.

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.5-86-010 2

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No safety evaluation was conducted on the modification.

With the release of primary water to the environment, the DRCST should have been sampled for radioactivity.

Water from.the DRCST was transferred to the RHUT, where it was diluted with service system water before sample water was taken for analysis.

The modification conflicts with the information reported in the September 1984-Special. Report 84-07 regarding the source of liquid effluents, the implemented short term corrective action to control, through sanpling and management, the release of radioactive effluents

.and the commitment not to exceed the 10 CFR 50, Appendix I dose objectives.

KELLIE and MAN 0FSKY stated they were neither aware of Special Report 84-07 nor the commitment required of them to control liquid effluents so that releases would not exceed the Appendix ! dose objectives.

COWARD, the Reactor Operators and KELLIE had direct responsibilities over the control of primary and secondary water.

The information on the modification was obtained by happenstance by Region V.

Alteration of Rancho Seco's Radionuclide Analysis Counting Time r

In early 1985, Chemistry and Radiation Technicians were instructed by KELLIE, MAN 0FSKY and WILSON to lower the analysis counting time from 2000 to 1000 seconds to preclude detecting peaks of radioactivity.

If radioactive peaks were detected, the RHUT water could not be released because of SMUD's commitment not to release to the environment liquid effluents containing radioactivity.

One of the first occurrences of the lowered counting time occurred in March 1985.

MIXA notified a Reactor Operator in the Control Room that peaks had been-identified and that the water could not be released.

. Shortly thereafter, KELLIE instructed MIXA to recount at 1000 seconds and release the water if no peaks were identified.

The CRPT's felt uncomfortable lowering the counting time because they were reporting to the Reactor Operators that there was no radioactivity when they. knew otherwise.

The CRPT's were told by KELLIE, MANOFSKY and WILSON that NRC was aware of the count time alteration and as long as Ranche Seco's LLD's were met, the counting time could be lowered.

1 In June 1985, KELLIE was told by YUHAS that any peaks, including those below the plant's LLD, had to be reported in the Semi Annual Effluent Report.

l l

l 5-86-010 3

f s

In December 1985 BRADLEY was told by MIXA that the counting times were being altered. BRADLEY informs POWERS and RODRIGUEZ. As a result, COWARD consults with KELLIE and then states that as long ts the counting time is within Rancho Seco's LLD, it can be lowered.

In March 1986, BRADLEY informed NRR, as an aside, about the alteration of counting time.

This information led to the initiation of Inspection 86/15.

The Insufficiency of Rancho Seco's Lower Limits of Detection Technical Specification in January 1985, BRADLEY realized that Rancho Seco's Technical Specification reeuiring a LLD capability of SE-7 did not assure compliance with Appendix !

dose objectives because the plant is a dry site and has no river or ocean dilution capability.

POWERS and RODRIGUEZ ere informed by BRADLEY about the LLD issue in January 1985.

POWERS does not want BRADLEY to study the matter because it micht expose deficiencies in the effluent progrcm. RODRIGUEZ agreed with 6RADLEY's suggestion to not publish his LLD study until af ter startup and resolution of the high point vent brake.

The study was furnished to POWERS in July 1985, and he disagreed with BRADLEY's assertion that Rancho Seco's LLD was insufficient for compliance with Appendix ! dose objectives.

POWERS takes no further action on the matter.

COLOMBO and KELLIE were not aware of the LLD issue until after BRADLEY issued his draft study in October 1985.

SMUD's 1985 Semi Annual Report of September 1985, reported no releases of radioactivity in liquid effluents. The report stated that extensive work and a concerted effort had been extended to comply with Appendix !.

o dose objectives.

In December 1985, BRADLEY informed YUHAS that LLNL's downstream pathway analysis detected cesium at concentrations that are unusually high for a plant with no radioactive liquid releases.

BRADLEY also informed YUHAS about the insufficiency of Rancho Seco's LLD.

In December 1985, Region V informed NRR that Rancho Seco's LLD cannot assure compliance with Appendix ! limits.

SMUD's 1985 Semi Annual Report of March 1986 reported no releases of radioactivity in liquid effluents.

5-86-010 4

4 SMllD's Acknowledgement of Effluent Release program Errors in April 1966, NRR informed SMUD that the Steff assessrent of the contamination of the environment of liquid releases for the years 1980-1984 was significant but that the ORNL whole body count analysis indicated that the 40 CFR 190 limit was not exceeded, NRR also informed that they were reviewing SMUD's radiological effluent program to determine if SMUD management practices are adequate to insure compliance with 10 CFR 50, Appendix ! and 40 CFR 190.

In June 1986, SMUD's Special Report 86-08 acknowledges that the 1985 annual dose objective of Appendix ! was exceeded due to strict reliance on Rancho Seco's LLD values and the release of liquid effluents in Quentities not contemplett-d.

In July 1986, SMUD acknowledged violations contained in Inspection Report 86/15 regarding monitoring procedures, modifications without 10 CFR 50,59 reviews, the alteration of counting times and not reporting detected radionuclide peaks.

1 N

1 5-86-010 5

CASE NUMBER:

5 86-010 DATE OPENEN June 23, 1986 STATUS:

CLOSED CASE AGENT:

MARSH CLOSED:

October 16, 1987 ATS NO.:

RY 86-A-0048 TITLE:

RANCHO SECO - Falsification of Test Records and Semi Annual Reports Concerning the Release of Radioactive Effluents ALLEGATION:

Tests and reports concerning the release of radioactive effluents at Rancho Seco were knowingly f alsified in an effort to conceal radioactive contamination released to the environment and improper plant modification.

PRIORITY:

HIGH, Referred to 00J.

FINDlHGS/RESOLTS:

This investigation revealed that SMUD officials had submitted three required reperts to the NRC that appear to contain material false statements concerning:

(1) plant configuration and pathvays of release of radioactive nuclides; (2) that radioactive releases were not made to the environment when in fact radioactive releases were made that exceeded Appendix ! limits; and (3) chenistry testing procedures were altered when radioactive nuclides were detected so as to create a chemistry 109 that appeared that no detectable nuclides were present when in fact they were known.

Also, it was determined that several SMUD and Rancho Seco management officials were knowledgeable of the falsity of the reports and gave instructions concerning the alteration hahrs s

n ra nager, Nuclear. # 88-Ahew Director, Nuclear Engineering.f s'to

,206#v 'h eW dM.

gg g%s7 Director, Nuclear Operations

  • gPlant Manager 44s,mews

[,I Q25 jp,g, ks//7 Superintendent for Radiation Protectiog

.g This matter was referred to D0J on October 20, 1987.

Responsible managers have been relieved of their positions of authority by SMUD.

An AUSA from the Eastern District t

of California, Sacramento, California, and an l

Environmental Crimes Special Prosecutor from Los Angeles, California, are working together in making prosecutorial '

decisions on this case.

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LIMll.. DISTR 1BUT10N -- NOT FOR PUBLIC

.SCLOSURC

_ INVESTIGATION STATUS RECORD Case No.:

5-06-010 Facility:

Rancho Seco Opened:

86/06/23 Docket No.: 50-312 Assigned To: Marsh Priority:

High

Subject:

Violation of SMUD Managers in the Control of Radioactive Effluents Remarks:

UG 86/12/29 i

Category:

SS (falsestatement/swornstatement)

DR (drugs)

M WR (falsestatement/ written)

MA (misedministration)

UY OM (falsestatement/ omission)

M LC (licenseconditions)

OR (false statement / oral)

AE Atomic Energy Act)

IH (intinidation & harassnent)

MS miscellaneous)

Status:

08/01/08:

ROI under DOJ evaluation.

08/31/88:

ROI under 00J evaluation, 9/23/08:

Declination by D0J on 9/23/00, Closed: 87/10/16 1ssued:

87/10/16 Referral:

87/10/16 Statute:

D0J Action:

Evaluation XXX Declination Prosecution / Grand Jury Prosecution / Plea Indictment /Pending Trial Indictment / Sealed Trial Conviction Acquittal 1

LIMITED DISTRIBUTION -- NOT FOR PUBLIC DISCLOSURE WITHOUT 01 APPROVAL

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BRIEFING TO NRC Comission 3.

INTRODUCTION TheOfficeofInvestigationsiscurrentlyinvestigating(

matters that could be related to Rancho Seco restart decisions.

A.

Case No. S-86-010 Concerns Releases of Radioactive Liquids Effluents from Ranch Seco, conspiracy to fabricate records showing no radioactive liquid effluents were released when in fact they were released in quantitie's that exceeded Appendix ! limits.

This investigation focussed on SMUD and Rancho Seco managers and supervisors and the apparent intent behind their actions,

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Iwouldliketo(iscusstheInvestigationconcerningreleasesofradioactive liquid effluentsi I believe the activities of SMUD and Rancho Seco managers that wil'1 be' revealed in that discussion will be relevant to our discussions about the El.sctric Cable matter.

4 1

0S 5

1

Title:

Rancho Seco - Material False Statements Conspiracy to Conceal the Presence of Radioactive Nuclides in Liquid Effluentf. Released to the Environment, and Violation's of 10 CFR 50 RequiremeAts to Limit Radioactivity Exposure to As Low as Reasonably Achte.vable (ALARA)

Case No.

5-86-010 Initiated: June 13, 1986 - Request from Region V Administrator

Purpose:

Liquid Radioactivo releases, were made to the environment that exceeded Appendix 1 Limits.

Semiannual Liquid Effluent Reports to the NRC stated no Radioactive Liquid releases exceeded Appendix 1 Limits.

The superintendent of Radiation Protection and Plant Manager Findings:

gave instructions through Chem / Rad Supervisors to Chem / Rad Technitions to reduce the counting time for detection of radiocctive nuclides.

Chem / Rad records were created showing that no radioactive nuclides were detected when in fact radiation was present at

,/

levels that would have precluded releases to the environment.

A Plant modification was made that created a pathway for Mh f'/

ry,A radioactive water stored in the DRCST to be released to the

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PC environment through the RHUTs.

(Violated 50.59 Requirement.) 7-Evidence shows that during 1985 the Licensee regularly transferred radioactive water from the DRCST to the RHUT and then released it to the environment after a special report issued to NRC in September 84 stated that no releases in excess i'

of Appendix 1 Limits would be made and no operating variance would be necessary.

There appears to have been a conspiracy transending the SMUD Organization from the SMUD Assistant General Manager Nuclear through the Rancho Seco Plant Manager and Radiation Protection superintendent to the Chem / Rad supervisors to created a record that declared no radioactivity was released to the environment and that the plant was not experiencing difficulties in l

dispositioning excess radioactive water, j

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The intent of the actions was initiated by financial conditions t

created by the poor operating performance of Rancho Seco.

The principal SMUD and Rancho Seco employees involved were as j

follows:

1.

Ronald RODRIQUZ Assistant General Manager 2.

Piere OUBRE' Manager Nuclear Operators

-- 3. Roger POWERS Manager Nuclear Engineering

-- 4. George COWARD Plant Manager

- 5.

Fred KELLIE Su>erintendent Radiation

>rotection

- 6.

Manofski arid Wilson Chem / Rad Supervisors

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BRIEF

SUMMARY

OF RANCHO SECO MAJOR PROBLER~ HISTORY COMMERCIAL OPERATION APRIL 1975 LP TURBINE BLADE AND MAIN JUNE 1975 4

GENERATOR FAILURES (7-1/2 Mos.)

REACTOR VESSEL SURVEILLANCE APRIL 1976 i

HOLDER INSPECTIONS (6 Mos.)

HIGH PRESSURE INJECTION NOZZLE APRIL 1982 AND AUXILIARY FEEDWATER HEADER PROBLEMS (5 Mos.)

FIVE STEAM GENERATOR TUBE LEAK 1982 - 1984 OUTAGES (6 Mos.)

HYDROGEN EXPLOSION IN GENERATOR MARCH 1984 EXCITER (I Mo.)

PIPE SUPPORT REEVALUATION JULY 1985 (3 Mos.)

REACTOR TRIP AND COOLDOWN DUE OCTOBER 1985 TO FEED OSCILLATION REACTOR TRIP AND COOLDOWN DUE DECEMBER 1985 TO LOSS OF ICS POWER PRESSURIZER HEATER BURNOUT DUE NOVEMBER 1986 TO OPERATOR ERROR i

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GE0 GRAPHICAL MAKEUP CALIFORNIA HAWAII ARIZONA ALASKA OREGON NEVADA WASilINGTON PACIFIC TRUST TERRITORIES

  • GUAM (6 LICENSEES)

AMERICAN. SAM 0A (1 LICENSEE)

  • AGREEMENT STATES 1

l NUMBER AND TYPES OF LICENSEES 6

POWER REACTOR SITES 11 OPERATING POWER REACTORS 0

POWER REACTORS IN CONSTRUCTION 1

P0WERREACTORINSHUTDOWN(HUMBOLDTBAY) 16 RESEARCH AND TEST REACTORS 11 - OPERATIONAL L

4 - SHUTDOWN 1 - DECOMMISSIONING 4

FUEL FACILITIES (G.A. TECHNOLOGIES, l

ADVANCED NUCLEAR FUELS, I

G.E. VALLECITOS, A.I. ROCKWELL INTERNATIONAL) 321 BYPRODUCT MATERIALS LICENSEES t

l'

REGION V RESPONSIBILITIES 4

INSPECTIONS POWER REACTORS RESEARCH AND TEST REACTORS MATERIALS FUEL FACILITIES LICENSING ACTIVITIES MATERIALS REACTOR OPERATORS OPERATING REACTOR LICENSING ACTIONS I

EMERGEl4CY PREPAREDNESS PLAN CHANGES l

10 CFR 50.54 AND 10 CFR 70.32 SAFEGUARDS LICENSING ACTIONS RESPONDING TO INCIDENTS EMERGENCY RESPONSE AUGMENTEDINSPECTIONTEAMS(AIT)

ENFORCEMENT ACTIVITIES STATE LIAIS0N AND STATE INSPECTION ACTIVITIES PUBLICAFFAIRS(REGIONAL)

OI REGION V FIELD OFFICE 1

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BRIEF

SUMMARY

OF RANCHO SECO MAJOR PROBLEM HISTORY COMMERCIAL OPERATION APRIL 1975 LP TURBINE BLADE AND MAIN JUNE 1975 GENERATOR FAILURES (7-1/2 Mos.)

REACTOR VESSEL SURVEILLANCE APRIL 1976 HOLDER INSPECTIONS (6 Mos.)

HIGH PRESSURE INJECTION N0ZZLE APRIL 1982 AND AUXILIARY FEEDWATER HEADER PROBLEMS (5 Mos.)

FIVE STEAM GENERATOR TUBE LEAK 1982 - 1984 OUTAGES (6 Mos.)

HYDROGEN EXPLOSION IN GENERATOR MARCH 1984 EXCITER (1 Mo.)

PIPE SUPPORT REEVALUATION JULY 1985 (3 Mos.)

REACTOR TRIP AND COOLDOWN DUE OCTOBER 1985 TO FEED OSCILLATION REACTOR TRIP AND COOLDOWN DUE DECEMBER 1985 TO LOSS OF ICS POWER PRESSURIZER HEATER BURNOUT DUE NOVEMBER 1986 TO OPERATOR ERROR l

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RANCHO SECO Designed as a zero ' liquid release plant.

Beginning in 1980 chronic steam generator tube leaks resulted in the release of small quantities of liquid radioactive effluent.

The licensee used NRC computer codes to project potential publi c e::posure.

In late 1983, the licensee identified that they had incorrectly used a dilution factor of 25 in the model projecting dose.

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4 Investigation by the licensee and NRC f ound the ef[luent water had been used to create a public exposure pathway.

i Radioactive materials were measured in fish, soil, and water used to irrigate pasture lands.

(20 pCi/g)

When Appendin I T.S.

were innplemented in 1984, the licensee acknowledged a potential exposure pathway that could result in a total body oose of 184 mrem.

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The licensee presented actions taken to assuri f eiture releases would meet the Appendi:: I dose objectives.

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A Investigations performed by the licensee.and NRC identified real people who received e::posure mostly through - the consumption of fish.

NRC estimated the mai:imum real 4

individual could have received a dose of about 47 mrem based on recall of consump ti on.

However, a license whole body count was adequate-to demonstrate that the individual did not e:-:ceed the EPA 40 CFR 199 value of 25 mrem per year.

i The whole' body count estimate was that the individual did not receive more than 6 mrem.

t In view of the licensee's stated corrective actions, NRC 1

found no need to issue a variance.

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' licensee had, in part, failed to follow thrcugh on ' U-mir-

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commitment to assure comp 1iance with Appendi= Ie Inspectors found the licensee had manipulated effluetht sample x;

y coun t i ng. t i ti.es to facilitate the release of liquid radioactive waste.

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Although the projected dose consequences were small (approx.

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f 4 mrem for 1985) the indications of a l l aci: Of responsible i

management are being tal:en very seriously and is the subject i

of-an ongoing OI i nvestigation.

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SIZE AND ORGANIZATIONAL STRUCTURE REGIONAi ADMINISTRATOR JACK MARTIN DEPUTY REGIONAL ADMINISTRATOR 800 FAULKEM8ERRY SENIOR REACTOR ENGINEER JESS CREWS REGIONAL ATTORitEY (VACANT)

L _-

PUBLIC AFFAIRS Ehf0RCEMENT OFFICER GREG COOK AL JOHNSON I

i DIVISION Of REACTOR SAFETY AhD DIVISION OF RESOUREE MANAGEMENT I

DIVISION OF RADIATION SAFETY AND PROJECTS AND ADMINISTRATION SAFEGUARDS DIRECTOR - DENNIS KIRSCH I

OIRECTOR - KATh1EEN liAMILL DIRECTOR.- ROSS SCARANO DEP, DIFECTOR - AL CF4FFEE 3

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STATE AGREEMENT OFFICER l

STATE LIAISON OFFICER i

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Sf2E SP/LLEST REGION

  • FY-86

- 114

  • FY-87

- 107

  • FY-88

- 102

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w RANCHO SECO 4

Designed as a. =ero ' liquid release pl ant.

Beginning in 1980 chronic steam generator tube leaks.

resulted in the release of small quantities of liquid radioactive effluent.

1 i

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The licensee used NRC computer codes to project potential publi c e>:posure.

In late 1983, the icensee identified that they had incorrectly used a dilution factor of 25 in-the model projecting dose.

So I

Investigation by the licensee and NRC found the effluent water had been used to create a public exposure pathway.

Radioactive materials were measured in fish, soil, and water used to irrigate pasture lands.

(20 pCi/g)

When Appendix I T.S.

were implemented in 1984, the licensee aci:nowledged a potenti al e::posure pathway that could result in a total body dose of 184 mrem.

~

The licensee presented actions taken to assure future releases would meet the Appendi:: I dose objectives.

O, e

20

Investigations performed by the_ licensee and NRC identified l

r eal people _who received _ exposure mostly through the_

consumption of fish.

NRC estimated the ma::imum real

~

individual could have received a dose of about 47 mrem based on recall of consumption.

However, a license whole body count was adequate to demonstrate that the individual did not e::ceed the EPA 40 CFR 190 value of 25 mrem per year.

'T he whole body count estimate was that the individual.did not receive more than 6 mrem.

In view of the licensee's stated corrective actions, NRC found no need to issue a' variance.

21 I

A f f ol l ow-tip-i nspecti on in the. spring-of 1986 found the 1icensee had, in part fai1ed to fol1ow through.on their 3

commitment to assure compli arice wi th Appendi::

I.

2 Inspectors found the licensee had manipulated effluent sample counting times to facilitate the release of liquid radioacti ve waste.

Although the projected dose consequences were small

( appro::.

4 mrem for.1985) the indications of a lack-of responsible management are being taken very seriously and is the subject of an on00ing DI investigation.

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_ ;[ gj gl}j jg 3 !,l lj if 11 + I 3,t s a s 2 : is i s E V N P- = i 3 E E. ==an = ( e L !j 4 GASEOUS EF FLUENT NUCLE AR POWER PLANT / [ b f- }pgg Q W LIOUID E F F LUEN'T I i s s I k l. y=.=., l Is i \\' P O '4 't, t o.,,n j ( g 1 ire.d.n... l f e ( iI'!'.*t ~ FUEL TRANSPORT l i' sho,,,,,, g ( )!!!&,.,,f& re ~ u %~qeeceav gw oa ~ caecee %s ~ +/ \\ g ....f %(,z. l ~ .r _ _E, ,. /.k _ m._____ -my_ DD k -l J The drawing above shows many of the possible pathways for radiation exposure to a member of the general public. 10-6 i 4 I .x 1 s Figure Ill.1 1 PROJECTED' DOSE TO MAXIMUM EXPOSED INDIVIDUAL (mrem /yr) RANCHO SECO NUCLEAR FACILITY ~ .4 _ - /A W f %,"Y i n;_ 97s IF hhT 'T)f.1{'. '.' 's,1]if[ ' ' 0 0 p .0 .qu $l E== .q Swl gBa hing_ NNx wo [o n s;; g 10.2- %s C g = h h. M s , i b @.... J j,, se \\ttigetton 9 g ,k. r k{ )w x,,_ ,k 1 7' s% 'N dWj9E? ~ ew e RANCHO SECO In.8 02/24/B6 l l W / L-RADIOACTIVE WASTE i l l' GASEOUS EFFLUENT NUCLEAR POWER PLANT ~ NM $ LIQUID EFFLUENT [s.w;p r - ej

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== 4 4_ TRANSPORT DISPOSAL l + This section discusses the sources, handling and ultimate disposal of radioactive wastes generated by Nuclear Power Plant operations. 10-1 s I e ( ALPHA o l L I Alpha radiation is a particle made up of two protons and two' neutrons. Alphas are low speed, low penetrating particles which can only travel one l-or two inches in air. Alphas are easily shielded (stopped) by thin sheets of paper or the body's outer layer of skin. Alphas are considered to be an " internal hazard" due to their ability to cause a large number L of ionizations in a small area if the radioactive atom can get inside the L body. Outside the body, alphas present little or no hazard. I l l 3-7 l - _--..-_~. e t-h BETA ( e Betas are high speed, high penetrating particles which are usually nega-tively charged. About 1/1800 the mass of a proton or neutron, the beta can easily penetrate the skin and is considered both an " internal" and an " external" hazard. Betas are best shielded by thick metals and plastics. 4 3-8 ~ l i

h GAMMA

( Gamma radiation is electromagnetic energy (no mass, no charge) similar in many respects to visable light (but f ar more energetic). Gammas can travel thousands of feet in air and can easily pass through the human

body, Gammas are best shielded by very dense materials such as lead, concrete, and uranium.

Note: X-rays are similar to gammas but are produced by changes in electron position rather than nuclear decay or fission. t 1-9 t 3 i. l e ) \\ NEUTRON t \\ Neutron radiation is the high speed, high energy neutrons emitted by nuclear fission and by the decay of some radioactive atoms. Neutrons can travel hundreds-of feet in the air, can easily penetrate the human body and are best shielded by materials such as water, polyethylene and concrete. e 3-10 i I s HALF LIFE w E \\. m IN 7 HAL'U!! !EE!** ., g oo THE RA010 ACTIVITY of i t THE MA TERIAL nab N ,,wr, m an w n' \\ t N.,. t o<o x.5 0 o< .'.... <.2s = .y, +yg,a-~ 4.st <, 0 4 e v s- ........... p............ /............ I I l l ,c 1 2 3 4 5 s 7 ( TIME The rate of nuclear decay is measured in " half lives." The half life of ~ -any radioactive material is the length of time necessary for one half of the atoms of that material to decay to some other material. Half lives range from millionths of a second (for highly radioactive fission products) to millions of years (for long lived materials such as l' naturally occurring uranium). l l l 3-5 MATERIAL RADIATION HALF LIFE Krypton-85 Beta 10 years '~ Gamma Strontium 90 Beta 28 years lodine 131 Beta 8 days Gamma Cesium 137 Beta 30 years g Gamma Carbon-14 Beta 5770 years Zinc-65 Beta 245 days Gamma Cobalt-60 Beta 5 years. Gamma Iron 59 Beta 45 days Gamma Tritium Beta 12 years (Hydrogen-3) L Above is a partial list of-radioactive materials produced either by fis-sion (fission products) or neutron absorption (activation products). 'These materials are of particular interest because of: l 1. Their relatively long half-lives ~ 2. Their relative abundance in the reactor (or) 3. Their ability to chemically interact in biological systems i 5-7 f[g>& Rf Cg}'eg 8 UNITED STATES 3 y, NUCLEAR REGULATORY COMMISSION e l 5 (%,%,,*..... */ i 0FFICE OF INVESTIGATIONS - REGION V V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 CASE CHRONOLOGY TITLE: BANolo SECO - Potential Willful Violation by SMUD Managers in the Control of Liquid Radioactive Effluents PAGE 1 0F lDate ope l Investigator l' NU'05-86-010 l Date Opened 6/23/86 g.3 o DATE CASE CHECK OFF LIST 1. Obtain a Case, Inquiry or Assist to an Inspection file number from the 6/23/86 appropriate log book completing the required entries. 2. Investigation Status Record (NRC Form 305) facsimiled to 01:HQ within 6/23/86 24 hours from opening the case. 3. Send a copy of the Allegation Data Form (NRC Form 307) to 01:HQ. 6/23/86 4 Route a copy of the Allegation Data Form (NRC Form 307) to the Region V ATS Of fice Coordinator. 6/23/86 5. Route a copy of the Allegation Data Form (NRC Form 307) to the Allegation Data Form Transmittal file with a handwritten notation of the date the 6/23/86 form was sent to 01:HQ with your initials. 6 File the original of the Allegation Data Form (NRC Form 307) in the 6/23/86 investigative file. RV-86-A-0048 7. Case Assignment Card prepared and filed. 6/23/86 8. Mark pertinent name and data with yellow highlighter for indexing. N/A 9. Prepare index cards and file, 1 6/23/86 10 Confidential Source stamp and Official Use Only stamps applied when j N/A required. b ACTIVITY 6/13/86 REQUEST FOR INVESTIGATION: RFI-RV-86-010 (EyH ra r r 1 1 6/23/86 OI INVESTIGATIVE IDG SHEET 2 i 6/23/86 INVESTIGATION STATUS REOORD (ISR) 3 6/23/86 OIMIS DATA ENTRY FDRM 4 l L/M = letter or Memo TC = Telephone Call INSP = Inspection ACTIVITY CODES ISR = Investigation Status Record MTG = Meeting INV = Investigation REP = Report Issued a_ 0 i ~F ICIAL USE ONLY DO N0T DISCL0SE JD l ...c g f.h kl C.g 4 8 'o UNITt0 SVATES' [.;. ( '[,i NUCLEAR REGULATORY COMMiuSION 3g'd,Y,g! 0FFICE OF INVESTIGATI0fl5 - REGION V %.y 1450 Marie Lane, Suite 210 4.,,,,* Walnut Creet, California 94596 CASE CHRONOLOGY CONTINUATION SHEET ' "

  • d5-86-010 f f.,.

PAGE 2 0F / / 0 / / DATE ACTIVITY SEP; AL 6/6/86 AILDGATICN DATA INPUT SIM,T R Undated SACRA 4WIO BEE ARTICLE: NRC STEPS UP PROBP OF SLTO hWPPR DrTFA4"4 r -6/20/86 NOTICE _Qf_SJGNIFICANT MEETING: ON INSPECTION REPORT 50-312/86-15 7 6/25/86 REOUEST FOR IhVESTIGATION RESPONSE 'IO MARTIN PRCN MARSil A 7/14/86 KELLIE 'IO MARSH: INFORMATION REQUESTED FROM VISIT ON 7/3/86 4 7/18/86 l MARSH 70 ifARD: REQUEST FOR INFO. [6.M 6TT N) I 1n 7/23/86-l PEREZ 'IO MEEFS RANCHO SECO OUITAGE DATES 11 G/11/86 ! ASHLEY 10 MARSH: RE LETTER OF 7/18/86 12 7/1/86 OI FILE REVIN 13 ,0/21/86 OI FILE REVIN 14 8/22/86 h'ARD 70 SMUD EMPIDYEES: NCTTIFICATION OF NRC IhVESTIGATION 15 9/30/06 lh"aRD 70 WASH: RESPONSE 'IO OI'S RDCUEST FOR ADDITIONAL INFO. OF LIQUID i EFFLUENTS FROM RANCHO SECO 16 -11/17/86 tOI FILE REVIEW 17 um s tarr.to 12/2/86 IWARD TO MARSit: INFO FROM 7/18/86 REOUEST OF INFO FROM SMUD(EXPANDING VOL IT 18 12/3/86 ATTENDEES AT MEETING OF 12/3/86 AT RANCHO SECO 19 12/10/86 l NOTES OF M. CILLIS ON REVIEW OF SMUD 12/2/86 REPLY, REQUEST FOR ADDITIONAL INFORMATION 20 19/4/86 INVERTTCATIVF TNTERVIEW OF MICHAEL CILIIS (. U flin;f 21 COURT REPORTER TAPES FOR INVESTIGATIVE INTERVIEW nctdllArwrime. 21n 12/9/86 WORK ORDER NO. NRC 401-530 FOR COURT REPORTER 22 12/24/86 MEFRS TO WARD; REOUEST FOR ADDITLONAL INFORMATION [ f%W6 Y l ~1 9 't '12/29/86'

EEKS TO FILE: UPGRADE ON INQUIRY TO INVESTIGATION 24
12/16/86 MARTIN TO MARSH
PRIORITY OF INVESTIGATIONS 2j 1/5/87 WARD TO ASHLEY, CRANSTON & LANGER: ONGOING OI INVESTIGATION 26 l 1/13/87 COURT REPORTER WORK ORDER NO NRC-401-571 27 1/15/87 IRANSCRIPT OF INTERVIEU OF YUHAS

[E 4t E(bE T i d (EXPANDING VOL. I) 28 1/15/87 IAPES TO INTERVIEW 0F YUHAS 28a 1/6/87 TORK ORDER NRC 401-561 COURT REPORTER 29 0FFt;Cl1"A[l/;USE ONLY D0 N0T DISCL0SE 3 [p ancu 'o UNITED STATES g g g NUCLEAR REGULATORY COMMISSION -a ' l OFFICE OF INVESTIGATIONS - REGION V / 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 CASE CHRONOLOGY CONTINUATION SHEET File No. THIS PAGE COVERS ACTIVITY PAGE 3 0F 5-86-010 FROM: / / T0: / / SE L DATE ACTIVITY 1/20/87 INVESTIGATIVE INTERVIEW OF YUHAS VOLUME IIf t~Y Wr e>LI L'I) EXPANDING FOLDER 30 1/26/87 INVESTIGATIVE INTERVIEW OF ED BRADLEY EXPANDING FOLDER 31 1/26/87 TAPES OF INTERVIEW OF BRADLEY [WhlbH 6) MANILLA ENVELOPE 31a 1/5/87 WARD TO MARSH: CLARIFICATION OF DECEMBER 2, 1986 RESPONSE 32 1/23/87 COURT REPORTER WORK ORDER NRC-401-583 33 1/28/87 NRC TRANSMITTAL RECEIPT OF 1/26/87 COURT REPORTING REPORT 34 2/19/87 WARD TO MARSH: RESPONSE TO 12/24/86 REQUEST FOR ADDITIONA hTON11Tb 35 2/25/87 STATEMENT OF GUS C. LAINAS ( f% H r &'T Hl MANILLA ENVELOPE 36 3/26/85 .. BRADLEY'S PERFORMANCE EVALUATION REPORTS FOR 1984, 1983, 1982 37 7/11/83 3RADLEY TO MSRC MEMBERS: RADIOLOGICAL PROTECTION AND ALARA TRANS. MEMO 38 7/5/83 1RADLEY TO KEILMAN: ATTACHMENT TO MEMO 38 38a 7/6/83 3RADLEY TO KEILMAS: ATTACHMENT TO MEMO 38 38b L7/7/83 mADLEY TO KEILMAN: ATTACHMENT 3 TO MEMO 38 38c (12/9/86 3I FILE PEVIEW 39 ! l/21/87 l11 INVESTIGATIVE WORK PLAN 40 1/21/87 11 FILE REVIEW 41 3/3/87 31 FILE REVIEW 42 3/4/87 3I INVESTIGATIVE WORK PLAN 43 3/25/87 LNVESTIGATIVE INTERVIEW NRC TRANSMITTAL RECEIPT 44 '/26/87 ENVESTIGATIVE INTERVIEW NRC TRANSMITTAL RECEIPT 45 _ 3/19/87 RC-WORK ORDER NO. NRC-401-662 FOR COURT REPORTER ,, tf l 3/31/87 CANTER TO MEEKS: FORWARDING INFORMATION REQUESTED ON 3/25 & 3/31/87 47 l 4/1/87 NRC 401-681 WORR ORDER FOR COURT REPORTER AR 1'4/1/87 NRC WORK ORDER 401-680 FOR COURT REPORTER lA l4/6/87 RECEIPT OF APRIL 3, 1987 TRANSCRIPT 50 4/9/87 RECEIPT OF APRIL 7, 1987 TRANSCRIPT S1 4/1/87 NRC WORK ORDFR NO. NRC-401-681 FOR COURT Rl' PORTING SERVICES 52 UNDATED INDIVIDUALS CONCERNS 53 6/5/87 TELECON D'ANGELO, SCHAEFFER TO JOUKOFF: BEE ASLE TO LOCATE SMUD EMPLOYEES 54 -IETERVIEWED BY OI:RV PERSONNEL 0FFIC1AL tl C E" J oI L Y 00 NOT DISCLOSE h P fuc9 ^ g UNITED STATES [g g NUCLEAR REGULATORY COMMISSION Y u 0FFICE OF INVESTIGATIONS - REGION V / 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 CASE CHRONOLOGY CONTINUATION SHEET File No. THIS PAGE COVERS ACTIVITY PAGE " 0F 5-86-010 FROM: / / T0: / / DATE ACTIVITY SE L UNDATED CASE CHRONOLOGY _,,3 5 UNDATED INVESTIGATORS NOTES AS OF 5/21/87 MANILLA FOLDER ,,56 3/24/87 SUFDiARY OF INTERVIEW TRANSCRIPT OF MANOFSKY 5 7,,_,,,,_ 3/25/87 SUbD!ARY OF INTEKVIEW TRANSCRIPT OF_DJETERI.,0]L SR 3/24/87 INVESTIGATIVE INTERVIEW OF WILLIAM A.., WILSON [frH: e>rT kEXPANDING FOLDER 59 3/24/87 INVESTIGATIVE INTERVIEW OF STEPHEN C j!ANOFFKYIMr ertrMEXPANDING FOLDER 60 _3/24/87 INVESTIGATIVE INTERVIEW OF R. PIERRL OUBRE [6/oro p 931 EXPANDING FOLDER 61 ) 3/24/87 INVESTIGATIVE INTERV.tEW OF GEORGE A. COWARD [fy' yM %) EXPANDING FOLDER ,62 3/24/87 INVESTIGATIVE INTERVIEW OF FRED W. KELLIE [evfft4 7 C) b E_XPANDING FOLDEP63 3/24/87 INVESTIGATIVE INTERVIEW OF ROGER I. MILLER [q.v.Iiy bi7'M ) EXPANDING FOLDER 64 ) 3/25/87 INVESTIGATIVE INTERVIEW OF RONALD C. LAWRENCE _ ' EXPANDING FOLDER 65 L 3/25/87 INVESTIGATIVE INTERVIEW OF HARVEY LEE CANTER , EXPANDING FOLDER 66 INVE3HC,ATIVE INTERVIEW OF LEE REILMAN (fxHMMT 2.0) EXPANDING FOLDER 67 3/25/87 A _3/25/87 INVESTIGATIVE INTERVIEW 0F ROBERT A. DIETERICH EXPANDING FOLDER 68 3/25/87 INVESTIGATIVE INTERVIEW OF ROGER L. POWERS (fyp t Gd 2d EXPANDING FOLDER 69 i-4/3/87 INVESTIGATIVE INTERVIEW OF RONALD WAYNE COLOMBO [fyHaenhEXPANDING FOLDER 70 l 4/7/87 INVESTIGATIVE INTERVIEK OF RONALD A. RODRIGUEZ (fysudT ydEXPANDING FOLDER 71 j l 3/25/87 TAPES OF INTERVIEWS WITil: P.0UBRE, H. CANTER. L.KEILMAN, R.DIETRICH, R. MILLER. G. COWARD, R. COLOMBO, R. POWERS, R.LAWRENC E. F.KELLI E, R. RODRIGUE7.. S. MANOFSKY 72~ l (IN EXPANDING VOLUME 4) l'5/13/87 ARTICLE " CHARGES OF IMPROPER SECO VISITS PROBED" M 7/16/87 CIY.LIS TO MARSH: OI INOUIRY. ALLEGATION REOUEST RFI-RV-86-010[ Erne f 13 3 7A 7/26/87 MILL 1:R TO MEEKS: INSISTING ON RFCEIVING COPY OF STATEMENT FOR REVIEW 75 l7/30/87 MARSHETO MILLER: RESPONSE TO 7/26/87 LETTER 76 '1/9/87 REPORT OF INTERVIEW WITH YUHAS [tr yk n, 4 l_/ ) EXPANDING VOL.,,111 7 7_ _ 1/15/87 SUFDIARY OF INTERVIEW TRANSCRIPT WITH YUHAS EXPAUDING VOL. III _J_8 !l/20/87 SUFDIARY OF INTERVIEW TRANSCRIPT WITH YUHAS EXPANDING VOL. III 79 ~ l1/26/87 SUFDfARY OF INTERVIEW TRANSCRIPT WITH BRADLEY EXPADING VOL. III SO . ~. _ _. i

1/26/87 REPORT OF INTERVIEW WITH HAMPTON yy, f5. p)

EXYANDING VOL. III 81 , -.memam 0FFICIAL USE ONLY 00 NOT DISCL05E eOteg jo UNITED STATES g g NUCLEAR REGULATORY COMMISSION E ~! 0FFICE OF INVESTIGATIONS - REGION V / 1450 Maria Lane, Suite 210 %.,v Walnut Creek, Cali fornia 94596 CASE CHRONOLOGY CONTINUATION SHEET File No. THIS PAGE CCVERS ACTIVITY PAGE 5 0F 5-86-0!0 ! ROM: / / 10: / / + maammmisessa mammmmmmmmmmmena l mammmune SERIAL DAls ACTIVITY NO. 1/26/87' REPORT Of_ INTERVIEW WITH HOWARD [fpWIeiET'l@ EXPANDING VOL. III 82 1/26/87 REPOR'l 0F INTERVIEW WITH LEINWANDER (LfHI.NtT 2id EXPANDING VOL. III 83-

l/26/87 REPORT OF INTERVIEW WITM PARTRIDGE

({vn 3 m t T 1 *'d EXPANDING VOL. III S4 '3/24/87 SU)BRRY OF INTERVIEW TRANSCRIPT WITH COWARD EXPANDING VOL, III 85 3/24/87 _ SU) DIARY OF INTEP,. VIEW TRANSCRIPT WITH,RELLIE EXPANDING VOL. III 86 '3/24/87

SUMMARY

OF INTERVIEW TRANSCRIPT WITH MILLER EXPANDING VOL. III _J7 3/25/87 SUFDIARY OF INTERVIEW TiMASCRIFT WITH POWERS EXPANDING VOL. III 89 4/3/87 SU} DIARY OF INTERVIEW TRANSCRIPT WITH COLOMBO EXPANDIEq.XQL J I 80 ,4]7/87 S_USDtARY OF INTERVIEW TRANSCRIPT WITH RODRIGUEZ EXPA@EG yQL. III 90 8/17/87 LAWRENCE TO MARSH: REQUEST COPY OF INTERVIEW TRANSCRIPT 91 >3/18/87 RODRIGUE"4 TO MARSH: P.EQUEST COPY OF INTERVIEW TRANSCRIPT 9? l' UNDATED RELLIE TO MARSH: REQUEST TOR ff0_P7 0F INTERVIEW TRANSCRIPT 93 8/25/87 .:ANTER TO MARSH: REQUEST FOR COPI OF INTERVIEW TRANSCRIPT 94 l8/11/87 MIXA TO MARSH: RIOUEST FOR COPY OF INTERVIE.7 TRANSCRIPT 95 '8/10/87 COLOMBO TO MARSH: REQUEST TOR COPY OF INTERVIEW ' TRANSCRIPT 96 I8/11/87 KEILMAN TO MARSH: REQUEST FOR COPY OF INTERVIEW TRANSCRIPT 97 8/28/87 MARSH TO LAWRENCE: IC RECEIVE TEANSCRIPT AT CLOSE OF INVESTIGATION 98 i8/28/87 MARSH TO RODRIGUE2: TO P.ECEIVE TRANbCR.tPT AT CLOSE OF INV_ESTICATION 99 l8/28/87 MARSH TO KELLIE TO RICEIVE TRANSCRIPT AT CLOSE OF INVESTIGATION 100 8/28/87 MARSH TO CANTER: TO YtECEIFE TRANSCRIPT AT CLOSE OF INVESTIGATION 101 1 8/_28/.87 MAPSH TO MIX _A.:_ TC RECE1VE TRANSCRIPT AT CLOSE OF INVEST.IGATION 102 z8/28/87 MARSH TO COL 3MB0: TO REC 7.IVE TRANSCRIPT AT CLOSE OF INVESTIGATION 103 l-8/28/87 MARSH TO REIT.MAM: TO RECEIVE TRANSCRIPT AT CLOSE OF INVESTIGATION 104 1l8/18/37 COWARD TO MARSH REQUEST FOR COPY OF INTERVIEW TRANSCRIPT 105 8/22/87 WILSON TO MARSH: REQUEST FOR COPY OF INTERVIEW TRANSCRIPT 106 i 9/2/87 MARSH 2L_q,0 WARD: TO RECEIVE IBANSCRIPT AT CLOSE OF INVFRTTCATTON 107 ,3/2/87 MARSH TO W715 %,; TO RECUVE TRANS2,IfT AT CLOSE OF INVERT],jlATTOM 10R ,8/14/87 FAULKENBERRY TO MARSH: 01 INVESTIGATIONS IMPACTING RESTART 109 9/2/87 SACRAMENTO UNION-SKID BOARD CHIEF ABRUPTLY QUITS 110 M Yd\\"*. 0FFICIAL 0SE ONLY DO NOT ULSCL0SE

.8p naai,% UNMED STATES 4 ! "~ NUCLEAR REGULATORY COMMISSION. n 5 -f 0FFICE OF INVESTIGATIONS - REGION V S 1450 Maria Lane, Suite 210 %,,,,, / Walnut Cren, Cal'.fornia 94596 CASE CHRONOLOGY CONTINUATION SHEET \\ File No. THIS PAGE COVERS ACTIVITY PAGE OF 5-86-010 FROM: / / T0: / / 6 ~ m SE L DATE ACTIVITY II1 9/3/87 MARTIN TO MARSH: REPORTING I_HE STATUS OF PEFDTfG INVESTICATIQSR 10/16/6_[ REPORT OF INVESTIGAT'fqN CLOSED + EXHIBITS EXPANDING IV 112 10/15/87 HAYES 70_p RTIN: TRMS U Q L LETTER FORWARDING ROI EXPANDING IV . LLL,_ 10/16/87 HAYES TO TOENSING: FORWARDING ROI TO DOJ FILE 6 EXPANDING IV 1 1/. E M $ 3 k k -- b M M A6 Y S!dlWO It/hlY/ MMC b4L;.,. i hi.uc. d_ d/ 1A1S 4_.ww/ &&'h A4E' A d/ l }$ by/beku ys /_q' ?, l AnwD AfP mml L Rec A Iw a s 's ii //lO bg____,Qw + W Ef)7 /bMu/ b !) tA bulA&_ fY/ c v , _,10/M,/87 STE1.LO TO DISTRIBUTION: TRANSMITTAL MEMO OF 5-86-010 115 h,O/27/07 BEE ARIICLE: US ATTORNEY REPORTEDLY CONSIDERS SECO CHARGES 116 I9/27/84: SPECIAL REFORT 84-07 EXHIBIT 2

9/15/84 LTR LAINAS '10 RODRIGUEZ
CALCUALTED DOSES IN EXCESS OF 10CFR EHXIBIT 3 12/16/85 MEMO LRADLEY TO POWERS: 10CFR50, APPENDIX I SOURCE TERM DEFIITION EXHIBIT 6 S-86-010 SPECIAL REPORT 86-08, PRELIMINARY CALCULATED DOSE TO THE PUBLIC EXCEEDING THE NUMERICAL DESIGN OBJECTIVES OF 10CFR50 APPENDIX EXHIBIT S 12/31/85 LTR, POWERS THRU COWARD TO RELLIE: CEP COUNTING OF COMPOSITE MONTHLY SAMPLES EXHIBIT 7 l 6/6/86 NRC INSPECTION REPORT 50-312/86-15 EXHIBIT 9 6/6/86 SMUD INTERNAL MRMO: TELEPHONE CONTACT OF KELLIE WITH YUHAS

, EXHIBIT 10 1/26/87 REPORT OF INTERVIEW WITH MIXA EXHIBIT 22 ,3/20/85 CHEMICAL / RADIATION LOG EXHIBIT 23 l9/26/85 LTR, RODRIGUEZ TO MARTIN: SEMIANNUAL EFFLUENT RELEASE REPORT EXHIBIT 36 l3/3/86 LTR, RO,DRICUEZ TO MARTIN: RANCHO SECO SEMIANNUAL RADIOACTIVE l EFFLUENT RELEASE REPORT EXHIBIT 37 11/12/87 MEMO: SCARANO TO MARSH: REPORTING OF RADIOACTIVE EFFLUENTS RELEASED FROM liANCHO SECO NUCLEAR GENERATING STATION ENVELOPE 117 11/27/87 VARRH TO FLYNN! NRC O?PTCT AT Or MFAT.TH & RAFFTY urun iin 1 12/23/87-MARTIN TO ANDOGNINI: REQUEST FOR INFORMATION 119 =- 0FFICIAL USE ONLY - 00 NOT DISCL0SE

groug# r? * ~ 0 UNITED STATES f,,g NUCLEAR REGULATORY COMMISSION 'a 0FFICE OF INVESTIGATIONS - REGION V / 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 ,,,g CASE CHRONOLOGY CONTINUATION SHEET File No.. THIS PAGE COVERS ACTIVITY PAGE OF 5-86-010 FROM: / / TO: / / 7 SE 'DhTE ACT.IVITY 120 ,j,ll4 f_8_Z,,,y RECORDS TRANSFER (SMUD) TO NRC OIX 329 12/2/87 _ BEE ARTICLE: NRC ASKS SECA 0FFICIAL: WHOM DO YOU TRUST 7 121 SMUE PENALTY LOR _ WATER DISPOSAL: NRC PUNISRMENT FOR RADI0 ACTIVE O '12/3)/87 UN10N ARTICLE: 122 WASTE WATER COULD AFFECT LICENSE /22/84 MINER TO RODRIGUE7.: AMDMEMENT 53. FACJLITY OPERAT MG,TTPFNRF VQL I 121 4jl25/88 ANDOGNINI TO MA1(TIN: RESPONSE TO 12/23/87 LTR 104 l10/8/87 ANDOGNINI TO MARTIN: RESPONSE REVISED TO APPARENT VIOLATIONS IDENTIFIED IN '125 NRC INSPECTION REPORT NO. 86-15

2/.12/88 INFO REC'D FROM RV ON ACTIONS TAKEN ON SPECIFIC INDIVI_ DUALS 126

?/17/88 MARSH TO YUHAS: MEETING WITH AUSA 2/26/88 127 4/20/88 E ARANO TO MARSH: RANCHO SECO EFFLUENTS RELEASE AMENDWNTA Vnf T -for -9/23/88 T. Flynn, U.S.DQ7/Sacranento-declinina prosecutio:15-EG 01n 12; l9/28/88 MARSH 'IO MARTIN: D17 DDCLINATION OF PROSEn1 TION, INFORMATICN CONCERNING 130_, 12/9/88 SECY B_B-339: PROPOSED NCfrICE OF VIOLATION AND PROPOSED IMPOSITJON OF CIVIL i PENAL 7"I CONCERNIN3 COMPLUtNCE WI7H 10 CFR PART 50, APPDQJX T. BY SACRAMERIO MUNICIPLE UTILIT'I DISTRICT (EA 86-110) 131 VOL. I in 3/14/89 PPgDONqr's 'to pmpc?q FOR TRANSCRIPTS OF INTERVIES (MULTIPLE) 133 PRESS Pn FASE - PROPOSES $100,000 FINE 1 f17fpo 134 ,2/6/89 FDRNING REPORT 3/21/89 RDCORDS - 70 DE RUIURNED (JOHN VINQUIST) VOL. I 135 4/27/89 FOIA 89-A HUNT 10 pmn 136 117 3/20/89 MDD, MARSH TO HUNT, EDIA 89-A-07 INVENIORY OF PERDS t MULTIPLE LTR FRCH MARSH 20 FULTIPLE ADDPMAW9 TRANSMITTING INTERVIEWS 138 l 00 NOT DISCLOSE OFFICIAL USE ONLY

1 0FFICIAL USE ONLY t); CASE CHR0NOL0GY File Number: Date Opened: Opened by: 3-86-C/d to E.5 b N Cc b: Date Activity ' ~ /4.r/s > Mbv s/,R'#h .)/ b/e? f a/WK sdi o e &- juk; m &.dM X A A A u sa,A R 4.~ i , M nA% Aa M.Askos.Phr i/uhr ~.8A "aA.esA A. 2Ak ? Kw/e.k&. ib;/r?. fan af f.dL4L.l n -,.~ w ) e A J K e/ain AB J /MPA ikk7 /r%sts'-lz:;f* an 3D iz/ev/gs zhWo &% c., 9. W Ouh7 /M s-m %ht 6 i&K Mhp Fsb d W n %, ilyh? A 4 L w~fPA -x l: l i 1 t I Activity Codes L/M : Letter or Memo TC Telephone Call Insp: Inspector MTG : Meeting Inv: Investigation Rep : Report i 0FFZAL USE CNLY DO NOT DISCLOSE i ) a C %CLO-W35 = >

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oNice of lavest st ons CASS hsweth CA,. gony 09 p s04 yv 0. DelhATIN0 hl ACTO. t thDivspuat LeCf8sett 5-86-010 $ '.'EMis*CW&'"2 "...*,*n'.t h '' u' ' 0FFICE OT INVESTIGATIONS, REGION V v v...o. " RANC110 SECO - Potential Willful Violation by SMUD MARSH Mansters in the Control of Lieufd Rndioactive Effluentti statust w a . a m, w easeenni r December 31, 1987 Awaiting results of DOJ evaluation. [ January 30, 1988 Awaiting results of DOJ evaluation. February 29, 1988 Awaiting results of DOJ evaluation /\\' J / wa in r its of DOJ evaluation. April 29, 1988 Avaiting results of DOJ evaluation. A Dpi

l e teAC f oNM M5 is 42i U.5,I.UCLE AM C.tOVL&To3V Cosmi; ion INVESTIGATION STATUS RECORD i IN5frUCTICNS: The toem 4 to tw comp <eted whene.e's+pn ticant eet rty hen occereo reiet.w to a c4w or et teast ew'y M ocfi if no thener hei ecce'ee ceing t%e E cey resemeng ser od. ana cats No Cr.enpe" in the status toock 6.eep the orip nel with the cow foe end una e's copy to Hemosoners. o't.ce of invest. pet. ors C%. hvetl* Catt00m. j D8 e'Cl ^^ 0.cesnatiNG htseton i . shDiv'Dv t Lecthill a 5-86-010 ' #EUeUE'* "**"a'5'u OTTICE OT INVESTIGATIONS, REGION V v.vihosa a, os.'i m assic.hio to susaC' RANCHO SECO - Potential Willful Violation by SML'D MARSH innaters in the Control of Liould Radioactive Ef fluents siAsus are<<ry me. onsvorover e ever mcrosev June 30, 1987 I ROI in Draft ECD July 1987 July 30e 1987 ROI in Draft ECD October 1987 August 31, 1987 Tield Work in Progress ECD: October 1987 t l Saptember 30. 1987 4 No Change 1 Tield Work in Progress. ECD: October 1987 y CLOSED by ROI on 10/16/87. Sent to DOJ on 10/16/87. Aw2iting evaluation by DOJ. /C November 30, 1987 Awaiting results of DOJ evaluation. 1.

esRC FORM 306 U.S. educLE Am Rt GULatoRY Commit $loh I INVESTIGATION STATUS RECORD act3o 4 tn,i som i i,. cow.i.e.s. ..,.esemi.n.. iv..cer.a..i.i. i.. =a or et -si... x v it no e,e, n. ,.o u no is. s z.....no i.no i....a iao c.i. -e.o cw.n," in is. r..tvi a,ioci k.. is....ra.'..ia ihe c. v.=.no uno one copy to s.was.-i... on.c.. in.. i-,.i c.

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.i. ' o... ea,ico.. T o.o ima,mo miaeton i moiviosat uciasii 5-86-010 e. .eto. vuoin ,. 'f,','ll'" ' OFFICE OF INVESTIGATIONS. REGION V c.ssiosio to MEEKS Sv*>'C' RANCHO SECO - Potential Willful Violation by SMUD Managers in the Control of Licufd Radionetive ST ATUS ($p cefr cere..v a preo.. bret aserrerenf IffluentB 2/3/87 Additional information on the licensee's effluents program has been requested. Field work in the form of initial interviews has been initiated.- The ECD is moved up to March 1987 due to pending startup ratview by NRC staff. Resources Available' Yes March 1987 h ECD: 3/4/87 The licensee repiled during the reporting period to 01's December 1986 request for additional information. The 01 Director was also briefed on the status of the investigation during the reporting period. The scope of the investigation is increased in orr.r to determine the extent of SMUD management involvement in the liquid effluents program, it i s am i tiprtri t ha t intt-lu t u viewa will be cumpicted by tiw cud vi che reporting period and a Report of Investigation will be prepared. Also, a briefing of the Commission will be conducted at that time. The ECD is being changed to reficct the change in the scope of the investigation. ECD: April 15. 1987 4/2/87 Interviews of licensee employees centinues. A Report of Investigation will be issued during the reporting perio1. ECD: April 30, 1987 l l 5/1/87 No change Resources Availabic ECD: May 1987 l 5/29/87 i Report in draft. Resources Available . 4: j ECD: Changed to June 1987

. ~.... ~ .g WAC f oRM 306. U.8. NUCLE AR REGULATORY CoMMIS$loh INVESTIGATION STATUS RECORD g l#$1P.VCYlONI 7 ten eorm tt to be compiated whewee' sign.ficant setmty has occurred reistive to e case or et least every 30 cows. If no chease has occu red during the r & day espo*teg pe'66d. And.cate "ido Change" en the etetus block. Keep the Or60'nel with the (see file end send one copy 10 Headquarters. Q't.cf Of inve61*gattD64 +UMett C At t com. 08 e aCl \\ p 0 07t>Ataho RE ActDa 4 INDiv.0UAL LICt hle t g5-86-010 c.gggo,cn ] .,,,,,,,y,,'ut' OFFICE OF INVESTIGCIWStPIGION V v vitaDOR

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PRolO SDI - Poteltial k'illful Violation by mfd 3 _ SMUD Panaaers in the Control of Licogid Padioactive st Avus eson,a aere. ew awa, e one aernationi Effluents r 12/1/86 The licensee has ccripleted their response to OI:RV 7/84 requested infonmtion. '.the licensee will brief OI:IN on Deccnber 3, 1986 on their response. A Region V staff engineer has been assigned to assist in the OI review of the licensee response. An evaluation of the case status will be mde after that review. Pesources Available: 'les ECD: April 30, 1987 12/30/86 A review of information supplied by the licensee on planned and unplanned modifications to t.he effluent release program indicates a need to broaden the scope of this case. Consequently. this case has been upgraded to an investigation and field work, including interviews of individuale involved in the management of the effluents program, will commence during the upcot-ng reporting period. ECD: APRIL 30, 1987 c '.A RESOURCES AVAILABLE: Yes

ijc eom an "C'" INVESTIGATN)N STATUS RECORD 4 enuctiou:: ini, eorm. i be compm.o.*,n .ve.m.ny n.. co.a.i.i. t. e e .r ei i n..ev n e.v.. is no en.ne..ie.ecor,.o ou,.no in, 30 a y renomne p.,ioo. ino cei. No Che # n e natus blos* Keep the 0,ipinel with tne esse f>6e one send one oppy to Headuwarters. Office of investis.iions. ,gypts t a"1 go, OFf tCE ts 3FFICE OF INVESTIGATIONS:REI3 ION V. 5-86-010 CONST R UCTION e au l v.vtNDon N CintR amohio ro setCT PANCHO SEC) - PCrTENTIAL WIILFUL VIOLATICE BY SMUD N hmMAGERS IN THE 00tTTROL OF LIOU1D PADIOACTIVE DTLUENTE l ST ATUS (Specify dere. *Hf sevsest. 6rsef suerrerrapal OPENED: 6/23/86 Rcquest for Investigation v RFI-RV-86-010 received this date. Field work will begin on/or I about June 30, 1986. Region V has requested the inquiry to be cmpleted on July 20, 1986 in order to process timely enforcement action. July 20, 1986, k. PRIORITY: Normal ECD: 7/2/86 Field work was initiated during the week of June 30, 1986. It is anticipated that the scope of the investigation will be defined by July 20, 1986 in order to assist in the coordination of any escalated enforce:mnt action. Resources Available: Yes DCD: September 15,1986.Adk',(iN 3/4/86 Information was requested frm the licensee during the reporting period. 'Ihe information will assist in defining the investigative scope of the case. A reply is expected during the upcming reporting period. Resources Available: Yes September 1986 M M.__- ECD: 8/25/86 The licensee has requested an extension in the time to reply with an 01 reauest on details of the liquid effluent program. The reply is expected during the upcoming report period. At that timu initial interviews will be conducted and an investigative work-plan formulated. Due to the licensee's delay in replying to the 01 request for Information, a chance of the ECD will be made from September to October 31, 1986. 10/3/86 ~~r M V/x, RESOURCES AVAILABLE: Yes ECD: October 31, 1986 The Licensee's response on the Inquiries initial review is expected on or about December 1, 1986. The ECD for this Inquiry is changed. Resources Available: Yes ECD: January 1987 11/4/86 ECD in prior month should have indicated ECD of April 1987. Otherwise no change. ECD: April 30, 1987 (p.5 -% - Oto-OQ2)

SACRAMENTO MUNICIPAL UTILITY DISTRICT OFFICE MEMORANDUM To: L.R. Keilman DATE: July 5, 1983 E.W. Bradley rnout RECOMMENDATIONS TO FULFILL THE DISTRICTS COMMITMENT TO RADIOLOGICAL PROTECTION, EUBJECT: ALARA AND ENVIRONMENTAL SURVEILLANCE.

REFERENCE:

Regulatory Guide 8.8 Information relevant to ensuring that occupational radiation exposures at Nuclear Power Stations will be as low as is reasonably achievable. Regulatory Guide 8.10 Operating philosophy for maintaining occupational exposures as low as is reasonably achievable. NUREG-0731 Guidelines for Utility Management Structure and Technical Resources (Draft 1980) NUREG-0761 Radiation Protection Plans for Nuclear Power Recctor Licensees (Draft 1981) The following recommendations are the result of many conversations with various utility corporate health physicists, site radiation protection managers, emergency preparedness coordinators, and ALARA coordinators, and review of the various NRC guidance materials on the subject.

1. Have the Radiation Protection Manager report directly to the Manager of.

Nuclear Operations. R.G. 8.8 SectionC.1.b.(3) "The Radiation Protection Manager (RPM) (onsite) has a safety function and responsibility to both employees and management that can be best fulfilled if the individual is independent of station div-isions, such as operations, maintenance, or technical support, whose prime responsibility is continuity or improvement of station cperability. The RPM should-have direct recourse to responsible management personnel in order to resolve questions related to conduct of the Radiation Protection Program."

2. Separate the functional responsibilities of Radiation Pr'otection and Chemistry.

Allow the Radiation Protection Manager to concentrate his time and available resources in the areas of radiological health and safety and do not dilute his efforts with competing areas of responsibility. To my knowledge, the District is the only organization that still combines the two diciplines. Please review NUREG-0731 Figure 1 Representative Plant Organization. (attached) 5 Wo@O3'6e

y; 4.L L.R. Keilman July 5,1983

3. Remove the peripheral activities of the_ Nuclear Operations radiation protection group that are not associated with the day to day responsibilities 1

of personnel radiological protection. Transfer the quarterly, semi-annual, and annual reports from the Radiation Protection Manager to the Nuclear Engineering staff. Again allow the RPM to concentrate his efforts on the day to day health physics, personnel radiological safety program. Many utilities are already doing this and some go as=far as administering the monthly film badge program out of the corporate health physics group. I don't think we need to 90 that far. The current system worked very well when there were less than 100 people on site. This is no longer applicable.

4. Provide the Radiation Protection Manager adequate staff to fulfill his duties and responsibilities,
a. Add an additional Senior H.P. Tech, with responsibilities in the area of Personnel Dosimetry.

There is an increased emphasis on personnel dosimetry in general and beta dosimetry in particular by both the industry'and the NRC.

b. Add an additional Senior H.P. Tech with responsibilities in the area of ALARA.

The current perception within Nuclear OperStions is that they have no responsibilities in the area of ALARA. This perception makes the effort of the Nuclear Engineering ALARA staff almost futile. In reality the Nuclear Operation Health Physics staff has the greatestimpact on ALARA than any other single group in the District.

c. Add an additional Senior H.P. Tech. with responsibilities in the area-Radiation Dose Records Management.

This is necessary for two reasuns:

1. An adequate and accurate radiation dose records date base is the foundation for a credable ALARA program.
2. An extensive data base is necessary_if the District ever gets pulled into litigation involving radiation exposures.

L.R. Keilman' July 5, 1983

5. Demonstrate the District's Management commitment to radiological health and safety (Health Physics),
a. Have a Radiation Protection Manager report directly to the Manager of Nuclear Operations and seperate Chemistry from Health Physics.
b. Clearly establish that any member of the Health Physics staff has the re-sponsibility and authority to stop work or order a4 area evacuated (in accordance with approved procedures) when in their professional judgement.

the radiation conditions warrent such an action and such actions are con-sistent with plant safety. It should be clear that only radiation pro-tection management, the Plant Manager, or their designated representativt on backshifts can overrule such a stop-work order. NUREG-0761 Regulatory Guide 8.8 Regulatory Guide 8.10 There exists a perception throughout the Chem / Rad group and the contract H.P. Techs, that their job is in jeopardy if they initiate a stop work order. Whether or not this perception is true or false is not the issue. The issue is what is management's consnitment to change this perception?

c. Ir..tiate 24 hour Health Physics coverage at Rancho Seco.

NUREG-0761 "In addition, an individual qualified as a radiation protection technician (Senior Technician), as specified in Regulatory Guide 1.8, or a technician qualified in accordance with a qualification's program specif-i l 1ed in technical specifications shall be onsite where there is fuel onsite after initial operation." l The current requirements placed upon the Control Room Operators no longer l make it possible for these individuals to satify this guidance. ( To my knowledge, the District is the only organization without 24 hour i Health Physics coverage. l

d. Initiate a program to establish Health Physics operated access control l

points into and out of radiation controlled areas. Access control points will provide the following:

  • Reestablish the importance of the RWP program
  • Very effective ALARA tool in that l

-each-worker must understand the RWP i -each worker must know what task he is supposed to do and in what specific area of the plant -each worker will be properly prepared before entering a radiation controlled area

  • Prevent unneccessary entry of personnel and equipment
  • Prevent improper exit of personnel and equipment
  • Ensure a more accurate radiation records data base

+

L.R. Keilman July 5,1983

e. Have the engineering Health Physics group report directly to the Manager of Nuclear Engineering.

Regulatory Guide 8.8 NUREG-0731: NUREG-0761 Health Physics is an independent discipline just as Civil. Electrical, Nuclear, Licensing, or Mechanical Engineering are independent dis-ciplines all supporting a comon goal within the Nuclear Engineering ~ Department. To my knowledge, the District is the only organization that has Health Physics subservient to an engineering discipline. NUREG-0731(Figure 2, attached)goessofarastoplaceEnvironmental Health and Safety on an equal basis as Nuclear Operations, Nuclear Engineering, Quality Assurance, and Administrative Service. I think this is going a bit too far at the moment but should be considered in the future,

f. Add an individual knowledgeable of radiological safety to the MSRC.

Technical Specifications 6.5.2.1

6. Keep the emergency preparedness responsibility within the corporate. Health Physics group.

Health Physics professionals are dedicated to the health and safety of the employee and to the general public. Engineers are dedicated to the continued safe and reliable operation of a physical facility.

7. Designate a site Emergency Preparedness Coordinator.

The site needs to recognize it's continued comitmer)t to emergency prepared-ness by designating a full time coordinator. This would greatly improve the coordination efforts from the corporate planner. I would recommend that this individual be within Ron Colombo's group.

8. Keep a corporate ALA'M group.

Regulatory Guide 8.8 C.1.b (1) (a) 9.. Proposed ALARA review g0idelines Existing individual radiation exposure control (AP 305) 4100 mrem / week whole body normal adminstrative controls y100 mrem / week whole body individuals first line supervisor initialing their dosimeter card

  1. 300 mrem / week whole body review by radiation protection supervision

L l5 L.R. Keilman July 5,1983 >1000 mrem / quarter wnole body review by chairman of PRC >2000 mrem / quarter whole body individual appearing before chairman of PRC with ALARA representative present 2500 mrem / quarter whole body Rancho Seco maximum allow-able whole body exposures 3000 mrem / quarter whole body NRC limit with restrictions Proposed collective radiation exposure control 1 man-rem ALARA job preplanning meeting 10 man-rem review by ALARA comittee 5 0 100' man-rem review by MSRC 10.' Decide who will be responsible for Health Physics Training, and establish a formal Health Physics Technician training program. Regulatory Guide 8.8 Regulatory Guide. 8.10 NUREG-0761 The District has made many comitments for Emergency Preparedness Training and ALARA training. This training to date has been done by consultants. Will. the District continue to use consultants or hire full staff? Will this staff be within' Jack Mau's group or the Health Physics group?

11. Include a Health Physics review in the ECN/DCN process.

Regulatory Guide 8.8 C.1.d (1) I will not be the first individual to acknowledge that the current ECN/DCN process is time consuming, laborious, and frustrating, but this is not the fault of the Radiological Protection Program. To exclude Health Physics from the process due to the^combersome nature of the system is not a valid reason. The question is rather what will management do to imporve the ECN/DCN process, and then to include Health Physics just as the other engineer-ing disciplines are inc'" led. To create a set of ALARA design criteria I believe.is a compromi .o the overall District's comitment to Radiological Health and Safety.

Attachment:

NUREG-0731 Figures 1 & 2 ALARA Resource Material Summary ALARA Regulatory Guidance Sumary cc: 3rd floor files R. A. Dieterien G

i { l! n n t o o s i i i s h t t m n c c e ya 3 e es h ri r 1 t t n C t c e 0 o oa si t e l rr ri r t in nn I P e P c e n mh ai G g g a ec l g I i E na nn a l he P n R on oh n P CT E ia i c a lh tM t e M h a aT i i l d d a a a c R R i I n s h n c r a r e e i re T de dc oe nn ni t n l ai an ci I g h ag t n t c en nE ne RE e eT l ms m r ul us e ro rl g t r t o a st sr n nn nt a I o I n M C o N C O g I n T i A n l ia l r e i N r ao l c A T cs an G ii ca 4 rv inf 0 g t r ref l-ce tt a e ep cnt c l I N r a r l e eiS n A e n e ES l a a L g a g EM r P 1 a M a u n n s E e a t a s V r M n M A I u a T g t l e y A n P c t i T F a n i N l e a l E P t c n a S s n e u E s a t Q R A r n P u i l E s a e a R s M l r l c n A ( ao an o cs ca i y ii inf t t nv nef a i ar at a r l he hnt e a cp ciS p u eu ea O Q MS MM t e ro l t r c e e g r e a i c n s D r a gw o M ne e F i r h s tC t l y n a t o rt o i i ef t r t pi u a Oh e c r S t i e e S p s O f l f l o s s e t .c r ni o I i v pe kre R AS i e

DNREG- 0731'- -- ( Figure 2 ,2 REPRESENTATIVE UTILITY ORG4NIZATION President f Senior Vice President l Power Supply a l Vice President Nuc1 ear Power l' g Nuclear Power Technical Environmental Quality Administrative Generation Support Health & Safety Assurance Service l Plant Manager 1 Licensino Radiological Design-Trt.inino i Protection Construction 1 Plant Manager 2 Operational Environmental Operational Industrial Analysis Monitoring Quality Security Assurance Maintenance Systems Emergency Procurement Fire i Support Engineering Planning Protection Plant Tests - Design & Laboratory Audits Employee Procedures Modifications Services Security l

i RESOURCE MATERIAL

SUMMARY

The following documents are sources of information used by ALARA personnel to accomplish the goal of reducing radiation exposures 4 at Rancho Seco to ALARA. We are also using them to help in re-writing the ALARA manual and set up the ALARA training program. A brief description.of how each document relates to ALARA is included. =%. o l

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1 Regulatory Guide 8.19 - Operational Radiation Dose Assessment in LWR Power Plants - ~ Design Stage Man - Rem Estimates Part A, 2nd paragraph. describes the man-rem estimate as an important part of the on-going radiation protection design review for ALARA. Part B, 1st paragraph - states requirements for working knowledge of factors con-bributing to exposure, and methods and techniques to insure exposures ALARA. Part B 2n.1 paragraph - states what is to be evaluated, i.e. design, traffic patterns, r.aintenance, etc. Fart B, 3rd paragraph - states that principal benefits will arise from the preliminary design review, Part C, 2nd par'agraph - states dose assessment process should involve personnel trained in plant operation, shield design, system design, and health physics. Part C, after C.4 - discusses dose assessment for design changes, what elements to consider for a dose assessment, and that it is expected that further design changes and innovations will be implemented as a result of the dose assessment. NOTE: Even though this reg guide is directed primarily toward initial plant design, we use it as general guidance for making dose estimates for new de-signs and design changes to the existing plant. Regulatory Guide 8.27 - Radiation Portection Training Part "B" Proper training in radiation protection is an essential part of the ALARA program. C.2.2 Refresher training should reinforce awareness of individual's' responsibility to-maintain his exposure ALARA. C.2.3 Testing should determine a trainee's attitude toward the ALARA concept. .C.3.1.c Training objective should be to enable individuals to keep their exposures ALARA, and apply ALARA considerations in making decisions that affect the exposures of others. C.3.2.1 Each worker's training should be adequate enough so they may participate in and effective manner consistent with the ALARA principle. C.3.2.2. Emphasis should be placed on ALARA objectives, philosophy, and program implementation. C.3.2.3 Persons who work in or make decisions affecting work in restricted areas should be trained such that they appreciate the importance and the implementation of the ALARA program. C.3.2.6 Mock-ups of each piece of equipment on which high man-rem tasks are ' anticipated should be used so as to perform the work in accordance with the ALARA principle. Justification for mock-ups should be made on an ALARA basis, and'should be considered for every task where collective dose may exceed one man-rem, and even for lower man-rem tasks.

y -Regulatory Guide 8.29 - Instruction concerning risks from occupational radiation-exposure. Part B - states that training is an essential part of the ALARA program. Appendix, item 13 - NRC requires licensees to maintain exposures ALARA. Appendix, item 14 - spreading a given dose over a longer time period is not ALARA. Reducing it is. Appendix, item 15 - efforts should be made to reduce overall collective dose. Appendix, item 16 - using extra workers to reduce individual doses is not ALARA.- Reducing dose rates and/or time is. Appendix, item 28 - efforts should be made to keep internal exposures ALARA. NUREG - 0761 - Radiation Protection Plan (RPP) pg 4 - radiation protection policy should include management commitment to keep individual _and collective radiation exposures ALARA. pg 12 - Radiation Portection Engineering functions are outlined - temporary shielding, review procedures, ate, pg 16.- Corporate radiation r,rotection staff functions are outlined - ALARA, review design changes, etc. pg 21 - discusses ALARA cr, ordination - committee, ALARA coordinator pg 25 - what the ALARA program should entail for the RPP. pg 71 - sample method of job pre-planning for ALARA. AIF/NESP - 010 Potential benefits of reducing occupational radiation exposure. - examines how exposures limit personnel productivity - gives methodology for calculating economic consequences. - finds savings of up to several thousand dollars per man-rem saved - ALARA is cost beneficial. - overall risk of cancer reduced for general population is an undefined cest savings. ~ - recognizes that the bulk of exposure is due to maintenance activities - goes into detail, i.e. unproductive dose due to crew changes, critical path items, time elements, job planning, training costs, etc. - discusses determining what the potential benefits of dose reduction actions might be-training, number of personnel used, use of outside workers, etc. .gives designers some guidance to consider to help reduce exposures - gives some guidance on when mock-up training is beneficial.

i -. EPRI NP-1862 Occupational Radiation Exposure.(ORE) Reduction Technology Planning Study. - Discusses finding at utilities concerning computerized records management systems - capabilities, problems, data tracked, etc for use in an overall ALAPA program. - Discusses trends in ORE for plants, systems, components, work groups, etc. - Recommends exposure tracking by RWP's, job function, etc. - Recommends tracking exposure-significant activities. - Recomends evaluations and comparisons of similar activities at nuclear plants for ORE patterns. NOTE: We perform computerized records management functions on a Comodore micro computer with satisfactory results. We are working with Canberra to complete installation of software with more capability by tne end of the year. A mainframe computer with much greater storage capacity, versatility and functionality will re-place Commodore. AIF/NESP - 020 - Compendium of design features to reduce occupational radiation exposure at nuclear power plants. - Documents descriptions of design features that are in use or are planned at various facilities to keep exposures ALARA during installation, operation, and maintenance. - Discusses pipe routing and plant layout - zoning of areas, use of scale models, access for ISI, etc. - Discusses building layout, access platforms for certain equipment, equipment removal, access opening, etc. - Discusses equipment arrangement, separation of radioactive and non-radioactive l systems, filter maintenance, shield walls. - D'iscusses piping design - valves, flushing provisions, remote operators, remote operators, snap-on insulation, etc. - Discusses equipment design - tanks, materials, seals, filters, etc. - Discusses system design - decontamination facilities, ventilation systems, valve operating stations, etc. - Reactor systems design - control rod drive maintencnce, crud traps, etc. Rancho Seco ALARA Manu d L Provides guidance to all personnel for conduct of the ALARA program by means of-discussion and procedures. We are in the process of reviewing and re-writing the manual to make it easier to use and reference for various activities related to radiation exposure.

a. 4 i ALARA Regulatory Guidance Summary 10CFR 20.1 (c) e (c) In accordance with recommendations of the Federal Radiation t Council, approved by the President, persons engaged in activities under licenses issued by the Nuclear Regulatory Commission pursuant to he Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974 should, in addition to complying with the requirements set forth in this part, make every reasonable effort to L maintain radiation exposures, and releases of radioactive materials in effluents to unrestricted areas, as low as is' reasonably achievable. The term "as low as is reasonably achievable" means as' i-low as is reasonably achievable taking into account the state of technology, and the economics of improvements in relation to benefits to the public health and safety, and other socioetal and socioeconomic considerations, and in relation to the utilization of ~ l atomic energy in the public interest. Regulatory Guide 8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As. Low As Is Reasonably Achievable. In 1973, the ICRP (Ref. 3) stated: "Whilst the values proposed for maximum permissible doses are such as to involve e 'sk which is small compared to the other hazards df life, nevertheless, in view of the incomplete evidence on which the values are based, coupled with the, knowledge that-certain radiation l effects are' irreversible and cumulative, it is strongly recommended l' that every effort be made to reduce exposure to all types of ionizing radiation to the lowest possible level." Merely controlling the maximum dose to individuals is riot sufficient;- the collective dose to the group (measured in man-rems) also must be-kept as low as is reasonably achievable. Reasonably achievable" is i ) judged by considering the state of technology and the economics of improvements in relation to all the benefits from these improvements. Under the linear nonthreshold concept, resi:rict'ing the doses to individuals at a fraction of the applicable limit would be inappropriate if such action would result in:the exposure of more persons to radiation and would increase the total man-rem dose. The goals of the effort to maintain occupational radiation exposures ALARA are (1) to maintain the annual dose to individual station personnel as low as is reasonably achievable and (2) to keep the annual integrated (collective) dose to station personnel (i.e., the sum of annual doses (expressed in man-rems) to all station personnel) as low as is reasonably achievable. t m

e Attaining the following objectives to the extent practicable throughout the planning, designing, constructing, operation,

maintenance, and decommissioning cf an LWR station will be considered to provide. reasonable assurance that exposures of station personnel to radiation will be ALARA.

1. Program for Maintaining Station Personnel Radiation Doses ALARA To attain.the integrated effort needed to keep exposures of station personnel ALARA, each applicant and licensee should develop an ALARA program that reflects the efforts to be taken by the utility, nuclear steam supply system vendor, and architect-engineer to maintain radiation exposure ALARA in all phases of a r,tation's life.- This program should be in written form and should contain sections that cover the generally applicable guidance pres 9nted in this guide, as a rainimum, and more specific guidance n required to address the perticular LWR that is the subject of the licensing action. Th.is program may be combined with the station's radiation protection manual, safety analysis report, or other documents or submittals. It need not be an independent document. a. Establishment of a Program to Maintain Occupational Radiation Doses ALARA (1) A management policy for, and commitment to ensuring that the exposure of station personnel to radiation will be ALARA should be established. (2) The policy and commitment should be reflected in j I written administrative procedures and instructions for operations involving potential exposures of personnel to radiation and should be reflected in station design features. Instructions to designers, constructors, vendors, and station personnel specifying or reviewing st'ation featurcs, systems, or l equipment should reflect the goals and objectives to maintain occupational radiation exposures ALARA. b. Organization, Personnel, and Responsibilities (1) In view of the need for upper-level management support, responsibility and authority for. implementing the L program to maintain occupational radiation exposures, ALARA should be assigned to an individual (or committee) with~ organizational freedom to ensure development and L; implementation. -Responsibilities and authoritte.s should include: (a) Ensuring that a corporate program that integrates management philosophy and regulatory requirements is established l with specific goals and objectives for implementation included: l l (b) Ensuring that an effective measurement system is established and used to determine the degree of success achieved l by' station operations with regard to the program goals and specific objectives; p.

.g'__ t - i (c) Ensuring that the measurement system results are reviewed on a periodic-basis and that corrective actions are taken when attainment of the specific objectives appears to be jeopardized; (d) Ensuring that the authority for_providing procedures and practices by which the specific goals and objectives will be achieved is delegated;-and (e) -Ensuring that the resources needed to ar.hieve goals and objectives to maintain occupational radiation exposures ALARA are made available. (2) The. Plant Manager (Superintendent or equivalent) is responsible for all. aspects of station operation, including the onsite radiation protection program. Responsibilities of the Plant Manager with respect to a program to maintain occupational radiation exposures ALARA should include: -(a) Ensuring support from all station personnel; (b) Participating in the selection of specific goals and objectives for the station; (c) Supporting the onsite Radiation Protection Manager (RPM) in formulating and implementing a station-program in maintaining occupational radiation exposures ALARA; and (d) Expediting the collection and dissemination of data and information concerning the program to the corporate management. (3) The Radiation Protection Manager (RPM) (onsite) has a safety function and responsibility to both employees and management that can be best fulfilled if the individual is independent of station divisions, such as operations, maintenance, or technical support, whose prime-responsibility is continuity or improvement of station operability. The RPM should have direct recourse to responsible management personnel in order to resolve questions related to the conduct of the radiation protection program. (The specific responsibilities given here for the RPM are illustrative and not intended to be all-inclusive with respect to the ALARA program or effort. They do not include any of the respon:!bilities in areas other than ALARA efforts.) Responsibilities of the RPM with respect to a program'to-maintain occupational radiation exposures ALARA should include: (a) Participating in design reviews for fact'lities and equipment that can affect potential radiation exposures; l

t (b) Identifying locations, operations, and conditions that have the potential for. causing significant exposures to radiation; (c) Initiating and implementing an exposure control program;' (d) Developing plans, procedures, and methods for keeping radiation exposures of ~ station personnel ALARA; (e) Reviewing, commenting on, and recommending changed in job procedures to maintain exposures ALARA: (f) Participating in the development and approval of training programs related to work in radiation areas or involving radioactive materials; (g). Supervising the radiation surveillance program to maintain data on exposures of and doses to station personnel, by specific job functions and type of work; (h) Supervising the collection, analysis, and evaluation of data and information attained from radiological surveys and monitoring-activities; (1) Supervising, training, and qualifying the radiation protection staff of the station; and (j) Ensuring that adequate radiation protection coverage is provided for station personnel during all working hours. c. Training and Instruction A training program in the fundamentals of radiation protection and in station exposure control procedures should be established. It should include instructing all personnel whose duties require (1) working with radioactive materials, (2) entering radiation area, or (3) directing the activities of others who work with radioactive materials or enter radiation areas.. The training program also should include sufficient instruction in the biological effects of exposures to radiation to permit the individuals receiving the instruction to understand and evaluate the significance of radiation doses in terms of the potential risks. d. Review of New or Modified Designs-and Equipment Selection (1) Since several groups within a utility (e.g., maintenance, operations, radiation protection, technical support, engineering, and safety groups) are interested in station design and equipment selection, the utility should ensure that these groups are adequately represented in the review of the design of the facility and the selection of equipment. A coordinated effort by the several functional. 9

A groups within the utility is required to ensure that station features will permit the goals and objectives of the ALARA program to be achieved. Although the A/E and designers greatly influence stat on design features, utilities should not delegate all responsibilities.for st.tlon design review and equipment selection to the NSSS designer, vendor, or A/E. (2) Design ccacepts and station features should reflect consideration of the activities of station personnel (such as maintenance, refueling, inservice inspections, processing of radioactive wastes, decontamination, and decommissioning) that might be anticipated and that might lead to personnel exposure to. substantial sources of radiation. Radiation protection aspects of decommissioning should be factored into planning, designing, construction, and modification activities. Station design features should be provided to reduce the anticipated exposures of station personnel to these sources of radiation to the-extent practicable. (3) Specifications for equipment should reflect the objectives of the ALARA program, including considerations or reliability, serviceability, limitations of internal accumulations of radioactive material, and other features ~ addressed in this guide. Specifications for replacement equipment also should reflect modifications based on experience t gained from using the original equipment. 2. Facility and Eculpment Design Features G i Radiation sources within a nuclear power station differ appreciably with respect to location, intensity, and -characteristics. The magnitude of the dose rates that results L from these sources is dependent on many factors, include the t L facility and equipment design, layout, mode and length of operation, and radiation source strength and characteristics. l l a. Access Control of Radiation Areas b. Radiation Shields and Geometry c. Process Instrumentation and Controls d. Control of Airborne Contaminants and Gaseous Radiation 4 Sources e. Crud Control f. Isolation and Decontamination g. Radiation Monitoring systems h. Resin and. Sludge Treatment Systems-1. Other Features 3. Radiation Protection Program A substantial portion of the radiation dose to station personnel is received while they are performing services such as maintenance, refueling, and inspection in high radiation areas. The objectives that were-presented in regulatory position 2 can provide station design features conducive to an effective program to maintain occupational radiation exposures ALARA..

L w However, an effective program also requires station operational; considerations in terms of procedures, job planning, recordkeeping, special equipment, operating philosophy, and other support. This section deals with the manner in which the station administrative efforts can influence the variables of-'(1) the number of persons who' must. enter high radiation areas or contaminated areas. (2) the period of time the persons must remain in these area, and (3) the magnitude of the potential dose. l a. Preparation and Planning Before entering radiation areas where significant doses-could be received, station personnel should have tha-banefit of preparations and plans that can ensure the exposures are ALARA while the personnel are performing the services. Preparations.and plans should reflect the following considerations: (1) A staff member who is a specialist in ratllation protections can be assigned the responsibility for contributing to and coordinating ALARA efforts in support of operations that' could result in substantial. individual and collective dose levels. (2) To provide the basis for planning the activity, surveys can be performed to ascertain information with~ respect to radiation, contamination, airborne radioactive material, and mechanical difficulties that might be encountered while performing services. (3) Radiation surveys provided in conjunction with inspections or other activities can define the nature of the radiation fields and identify favorable locations where personnel may take advantuge of available shielding, distance, geometry, and other factors that L affect the magnitude of the dose rate or the portions of the body l-exposed to the radiation. L (4) Photographs of "as installed" equipment or components can l be valuable for planning purposes and can be augmented by additional photos taken during the surveys. (5) The existing radiation levels frequently can be reduced by draining, flushing, or other decontamination methods or by removing .and transporting the component to a lower radiation zone. (6) A preoperational br.lefing for personnel who will perform-services in a high radiation area can ensure that service personnel understand the tasks about to be performed, the information to be disseminated, and the special instructions to be presented. (7) A program can be implemented to provide access control and to limit exposures to those persons needed to perform the requir.ed services in the radiation areas. Such a program would address conditions that require a special work permit or other special procedures. l l -- , q; s, 79 ,~~- m j (8)? A iork permit form with an appropriate format can be useful-for rer.ording pertinent information concerning tasks to be performed in high radiation areas so that the information Is amenable to cross referencing and statistical analysis, a (9) Consideration of potential accident situations or unusuai w' occurrences (such as gross contamination leakage, pressure surges,- fires, cuts, punctures, or wounds) and contingency planning can reduce the potential for such occurrences and enhance the capability for coping with the situations expeditiously if they occur. (10) Portable or temporary shielding can reduce dose rate levels near " hot spots" and in the general area where the work is to be performed. (11) Portable or temporary ventilation systems or. contamination enclosures and expendable floor coverings can control the spread of contamination and limit the intake by workers through inhalation. (12) " Dry runs" on mockup equipment can be useful for training personnel, identifying problems that can be encountered-in'the actual-task-situation, and selecting and qualifying special tools and procedures'to reduce potential exposures of station personnel. (13) Adequate auxiliary lighting and a comfortable environment (e.g., vortex tube coolers for supplied air suits) can increase the efficiently of the work and thus reduce the time spent in the higher radiation zones. (14) Radiation monitoring instruments selected and made available in adequate quantities can permit accurate measurements and rapid evaluations of the radiation and contamination levels and changes in levels when they occur. (15) Performing work on some components inside disposable tents or for less complicated jobs, inside commercially availa'ble disposable clear plastic glove bags can limit the spread of contamination. (16) Careful scheduling of_ inspections and other tasks in high radiation areas can reduce exposures by permitting decay of radiation sources during the reactor shutdown period and by eliminating some repetitive surveys. b. Operations During operations in radiation areas, adequate supervision and radiation protection surveillance should be provided to ensure that the appropriate _ procedures are followed, that planned precautions are observed, and-that all potential radiation hazards that might develop or that might be recognized during the operation are addressed in a timely and appropriate manner l

kg( a, - m .? ; r y h - (1) Assigning a health physics (i.e. radiations safety or-radiation protection) technician the responsibility for providing radiation protection surveillance for each shift operating crew can i help ensure adequate radiation protection surveillance. _-(2) Personnel monitoring equipment such as direct-reading dosimeters, alarming dosimeters, and person:1 dose rate meters can be .used to provide early evaluation of doses to individuals and the assignment of those. doses to specific operations, 4 i (3) Communication systems between personnel in high radiation zones and personnel who are monitoring the operation in other _ locations can permit timely exchanges of information and avoid 1 unnecessary exposures to monitoring personnel. c. Postoperations Observations, experience. and data obtained during nonroutine operations in high radiation zones should be ascertained, recorded, and analyzed to identify deficiencies in the program and to provide the basis for revising procedures, modifying features, or making other adjustments that may reduce exposures during subsequent similar operations. 1 (1) Formal or informal postoperation debriefings of station personnel performing the services can provide valuable information concerning shortcomings in preoperations briefings, planning, procedures, special tools, and other factors that contributed to the cause of-doses received during the operation. l L (2) Dose data obtained during or subsequent to an operation can be recorded in a preselected manner as part of a " Radiation Work Permit" or similar program so that the da.ta are amenable to statistical analyses. (3) Information concerning the cause of component failures that resulted in the need for servicing in high radiation areas can provide a basis for revising specifications on replacement equipment or for other modifications that can improve the component reliability. (4) Information gained in operations can provide a basis for modifying equipment selection and design features of.new facilities. (5) Summaries of doses rece.tved by each category of maintenance . activity can be reviewed periodically by upper management to compare l the incremental reduction,of doses with the cost of station modifications that could be made. 4. Radiation Protection Facilities, Instrumentation, and Equipment l A radiation protection staff with facilities, instrumentation, and protective equipment adequate to permit the staff to function efficiently is an important element in achieving an effective program to maintain occupational radiation exposures ALARA. ac-

= - - - / l a. Counting Room b. Portable Instruments c. Personnel Monitoring Instrumentation d. Protective Equipment e. Support Facilities 1. Instrument calibration area 2. personnel decontamination area 3. equipment decontamination area 4. . change rooms 5. control stations 6. communication equipment 7. office space Regulatory Guide 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable Two basic conditions are considered necessary in any program for keeping occupational exposures as far below the specified limits as is reasonably achievable. 1. Management Commitment-The commitment made by licensee management to minimize exposures should provide clearly defined radiation protection responsibilities and an environment in which the radiation protection staff can do its job properly. There are several aspects to tnis commitment: a. Plant personnel should-be made aware of management's commitment to keep occupational exposures as low as is reasonably achievable, b. Management should periodically perform a formal audit to determine how exposures might be-lowered. c. The management should ensure that there is a well-supervised radiation protection capability with well-defined responsibilities. d. The management should see that plant workers receive sufficient training, e. The Radiation Safety Officer (RS0) should be given sufficient authority to enforce safe plant operation. f. Modifications to operating and maintenance procedures and to plant equipment and facilities should be made where they will substantially reduce exposures at a reasonable cost. 4 2. Vigliance by the RSO and the Radiation Protection Staff It should be the responsibility of the RSO and the radiation protection staff to conduct surveillance programs and invutigations to ensure that occupational exposures are as far below the.

specified limits as is reasonably achievable. Additionally, they should be vigilant in searching out new and better ways to perform all radiation jobs with less exposure. _There are several aspects to this responsibility, a. The RSO and.the radiation protection staff should know the origins of radiction exposures in the plant. b. The RSO and the radiation protection staff should look for ways to reduce exposures c. Adequate equipment and supplies for radiation protection work should be provided 9 'l 1-

I SACRAMENTO MUNICIPAL UTILITY DISTRICT OFFict McMoRANDUM To: L.R. Keilman oATri July 6, 1983 rnomi E.W. Bradley ousarcTi COMMENTS ON MEH0: A.S.1;0 HEN TO L.G. SCHWIEGER JUNE 17, 1983 REVIEW OF THE ALARA PROGRAM AND CURRENT FUNCTION II A I agree, the MSRC should take a more active role in the ALARA program. II B I agree, but this ambiguity also offers a challenge that can only be. met by an adequate radiation records date base, cost benefit analysis reports, documentation of training, documentation of applicable _ALARA activities, and a dedicated staff. II C I agree, no formal mechanism exists for an adequate or formal ALARA review. The success of the ALARA program to date has been due to an extremely dedicated staff keeping their eyes and ears open. II C1 The revision to.the ALARA policy statement is "on hold" until the MSRC discussions are complete. 11 C2 Dividing the plant and plant operations into twelve sectors is completely arbitrary and of no value. The ALARA committee should undertake and ALARA review of every major system in the plant. The current agenda is established by the Nuclear Operations Health Physicist and the Nuclear Engineering Health Physicist (ALARA). At times, the ALARA Committee diverges from it's proper role and into areas of a job preplanning meeting or a Chem / Rad staff meeting. Il C3 Adequate ALARA review is already available at the sitt level with Roger Miller being on the PRC. However, no capability currently exists on the MSRC. II C4 The PRC should play a more active role in the ALARA program. II C5 I agree. ALARA must be factored into the system to be effecitve. The management commitment on paper must be demonstrated by action. II C6 The PRC and MSRC.should be more involved in ALARA. II C7 Same comment as 11 C6. II C8 The ALARA group needs additional guidance and direction pertaining to the pre outage report. 11 C9 The comment relative to a permanent ALARA chairperson is invalid. N ) The Nuclear Operations Health Physicist is the ALARA chairperson */ / in the absence of the Nuclear Engineering Health Physicist (ALARA). ~

d L.R. Keilman ' July 6, 1983 11 C10 The ALARA employee suggestion program is still a viable program. The suggestions are currently being acted upon by either the Chem / Rad group or the ALARA staff directly. Very little assistance ever resulted from ALARA committee activities. 11 B1 The ALARA committee membership needs to be reevaluated, and direction given to the committee by MSRC. 11 B2 Selection of the Nuclear Engineering Health Physicist (ALARA) is being held up until the HSRC discussions are over. 11 B3 This has worked very well for the committee. 11 B4 1 do not feel attendance should be mandatory. 11 C Meeting frequency is currently adequate. 11 D1 Comment accepted. 11 D2 This part of the ALARA charter is very similar to the PRC charter, 11-D3 ALARA committee minutes should be treated similar to PRC minutes. -Ill In summary, I think the current success of ALARA has been done in spite of management support rather than with management support. The ALARA staff has had to jump into areas outside of their re-meetings, radiation dose records) goals (i.e. job preplanning sponsibility to accomplish ALARA and has had.to rely upon the communication's grapevine at the site to become aware of work requests, ECN's, and scheduling. ALARA should be thought of as part of the solution, not blamed for the problems, cc: 3rd Floor Files R.A. Dieterich s

SACRAMENTO MUNICIPAL UTILITY DISTRICT orreca MaMORA 11.8Qf nY.jp 7 s + j QD U M ss m's w70 vo: R J Rodriguez dam June 20, 1983 rnow: L G Schwieg sussect. ALARA - REVIEW BY A S COHEN I would like to have-the ALARA Comittee operation placed on the staff meeting agenda to discuss the recomendations of the attached report. Attachment cc: P Oubre' L Keilman k'., Y"'e-('j ] %- f+ (..., < jf (~ L L _/. m e :p p

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l.. SACRAh..NTO MUNICIPAL UTILIT. DISTRICT a omes usuoRANDUM vo L G Schwieger ears: June 17, 1983 ASCohenI S rnow: suester, REVIEW OF THE ALARA PROGRAM AND CURRENT FUNCTION

REFERENCE:

1. ALARA MANUAL - SMUD 2. ALARA COMMITTEE REPORTS - SPECIAL AND MONTHLY MEETINGS, 1981-1983 3. 0/. REPORT #83RO-086 DATED JUNE 9,1983 4. CHARTER FOR RANCHO SECO RADIATION EXPOSURE ALARA COMMITTEE DATED JUNE 1, 1981 1. INTRODUCTION At the request of the addressee, the writer conducted a review of the activities of the ALARA Committee within the framework of the ALARA program. This review had only one criterion; i.e., "Is ALARA meeting its commitment." To perform this review, the writer examined the published ALARA program as embodied in Ref. 1. For initial comparison, the original minutes, as published in 1981 were reviewed and compared with Ref. 1 and with the current meeting minutes; i.e., 1983 meetings contained in Ref. 2. The Quality Assurance Surveillance Report No. 83RO-086 audited the attendance in comparison with the ALARA charter contained in the ALARA manual. The charter, Ref. 4, issued June 1, 1981 differs from the Ref. I manual charter in that the latter, prepared March 1,1982 and issued circa May 27, 1982, adds an electrical engineer (Nuclear Engineering) and plant 1 maintenance representative (Nuclear Operations). Finally, the writer interviewed the acting chairman, Chemical and Radia-tion Supervisor / Health Physicist (Nuclear Operations) and Plant Engineer-ing Technician (Health Physics, Nuclear Engineering) who serves as committee secretary. This report attempts to remain objective although some of the actions taken by the committee and assigned supporters appears to be subjective. These appearances must be addressed to maximize potential benefits from the ALARA program. .t

June 17, 1983 -L G Schwieger ?

13. COMMITTEE CHARTER VERSUS PRACTICE A(1) Committee Designation This paragraph states that ALARA is a permanent subcomittee of. the MSRC and takes direction from it.

There'is no evidence that the MSRC has ever provided any direction to ALARA, including the charter. The direction appears to be an ALARA-Manage-ment agreement. B (II) Directive ~ Typical of government regulations, the title contains the ambiguous word " Reasonable," i.e., "... Reasonably achievable...." "...every reasonable effort..." This leaves little to " hang one's hat on!" C (Ill) Purpose Tne introductory paragraphs of this section of the charter define adequately the areas of ALARA responsibility and the method of performing the audit' and reviews called for. However, no mechanism is provided for the routine delivery, passage through, or other advising of events planned, occuring, or accomplished in areas wherein an ALARA contribution is indicated. In-actual practice, all ALARA efforts appear to be the result of ALARA members' unconventional gleaning. 1. " Review and maintain current ALARA Policy Statement..." This was done between the original charter, June 1, 1981, and issue of the ALARA manual, May.27, 1982. Another revision is now in process and has been since the first-of the year. Completion is currently scheduled to be accomplished after September 1983 but before January 1984. 2. "Itake recommendations on long term ALARA program planning and obtain MSRC' concurrence. Establish-goals... assist Nuclear Operations and Nuclear Engineering departments in implementing changes to meet these goals. Develop methodology and milestones for monitoring the success of meeting the established goals." The above is considered to be accomplished through the membership of departmer.t representatives on the comittee. There are apparently no' t' assigned areas of study for recommendations or any other organized ( approach. I-would recommend that the plant and plant operations be divided into twelve relatively equal sectors and that each sector be reviewed by ALARA committee members in their respective specialities. This would program at one a nonth. Every sector would then be reviewed annually. 3. " Review the Radiation Control Manual or any other procedure as referred Iiii ii i

l i L G Schwieger ~3-June 17, 1983 by the Plant Superintendent, the Plant Review Comittee, or the Chemi-cal and Radiation Supervisor as having a potential for exposing indi-viduals to radiation." W f147 Onn A "few" requests have been made. Alain, mbh N routinely be erocessed throuch ALAR'K T7 muu is sinteVTacnering to th~e pr hciple of ALARA. 4. "Upon a request by the Plant Review Comittee, provide a detailed revio, of proposed special or unusual tests, experiments, or procedures having a potential for exposing individuals to radiation." The answer and observations under paragraph 3 are equally applicable here. S. " Assure that an adequate ALARA review is performed on proposed changes or modifications to plant systems or equipment that have a potential for exposing individuals to radiation." g DI) \\N.MIb.f 'This can only be accomplished when SMUD management and/or MSRC make it mandatory that all such changes, modifications, etc. are routinely % g, ( y 9 p, ted t_hrough %EXRA. 1 b 6. "Upon a request by the Plant Review Comittee or Management Safety Review

'p ' 5 g pi Committee, provide an investigation of abnormal radiation exposures or y

overexposures and prepare a report covering evaluation and recomenda-tier.s to prevent recurrence." W g' L. A /if'fttRA. No rensest has been known to have been made in the two years existence Has plant health 6nd safety. handled all abnormal events? W l, b, Have there been nLo abnormal events? If the latter, it might be a good 1 PR item! 7. " Perform special reviews $nd investigations and produce reports as requested by the Chairman of the Management Safety Review Comit@tes." 4h j n.m kt -s By paragraphs 4, 5, 6, and 7. manAgeme has mad.e~ALARA subservient to virtually every other safety.Ir%iatio / hazard tgtouga. If this was the intent, it should not have been so obvious; i.e., under these paragraphs, no requests have been made of ALARA in its two year exist-ence. 8. 'frior to the start of any major planned outage, review applicable aspects and prepare a report ~ covering evaluation and recomendations for maint i taining radiation exposures ALARA. This report should be forwarded to the Chemistry and Radiation Supervisor, the Plant Superintendent, the l Manager of Nuclear Operations, Manager of Nuclear Engineering, and to the Chainnan of the Management Safety Review Committee for their appropriate action."

s L G Schwieger 4-June 17, 1983 5 For this outage, a number of items were presented, reviewed and 4 commented on. According to ALARA comittee officers, this was not en organized, planned review but a more haphazard presentation. No Teod-back is available of the reviews submitted. 9. " Copies of approved ALARA Comittee meeting minutes will be forwarded to MSRC Comittee members for infomation. At least semi-annually the ALARA Comittee will review radiation exposure documentation and prept.re and forward a report covering evaluation and recomendations for main-taining radiation exposures ALARA to the Management Safety Review Comit*,ee members. The ALARA Comittee chairman will subsequently meet with the MSRC Comittee to discuss details of the report." Monthly and special ALARA meeting minutes have been routinely forwarded to MSRC members. There is no record of rout Jineetings to discuss ,T resul.ts,..recomendatfom JLro ranmim itc u Tome conenent was made thet J (this si,tuation wat due_to the Tack of a ptrmanent ALARA chairperson. 10. " Actively pursue ALARA recomendations from employees. Review, respond I and follow-up on ALARA-related suggestions originating from the Employee ALARA Suggestion Program." The 1981 minutes show a number of suggestions originating from employees.. The 1983 minutes show none. The program must have succeeded and the entire facility is ALARA! Is it possible that the ALARA Employee Sugges-tion Program needs stimulating? The program needs review. B (1V) Membership 1. "The ALARA Committee shall be composed of the following personnel: Health Physici!,t ALARA) He41th Physicist D1 ant) Nuclear Engineer NuclearOperations) Civ" Engine.ey (M"@ Engin::Hng} MechanicalEngineer(NuclearEngineering)) Operations Supervisor Assistant (Day Shift Ocmd En;in;;r (Scle:- in;in::Mn; ) Added March 1 Plant Maintenance Represstative (Nuclear Operations ) 1982 to charter Safety Technician Principal Engineering Technician (Health Physics) Other members as the Chairman of the MSRC may appoint from time to time. The ALARA Comittee chairperson has the authority to request the attend-ance of specific representatives from the Nuclear Operations and. Nuclear Engineering Departments at Comittee meetings when he/she deems it neces-sary." w

c L G Schwieger June 17, 1983 The designation of membership by function recognizes a need for the d ALARA to have available certain recognized skills and disciplines on the Comittee. I meetings, the " personality cult" tyne of mamher. ,, b P, } S Q gnation ~ nis name designation 9s still used. 4 f Reference (3) shows thet several skills are seldom te

  • r represented.

If management is sincere 'n pursuing the objectives af Als Nwhy isn't attendence mawa y with an alternate designated 'f the ".icial repre-sentative cannot attend? The implication is that the mandatory attendance is c..,y for the monthly meeting. For special meetings, the Chairperson prepares the agenda and-invites those skills deemed required to properly address the agenda items. All designated members automatically receive copies of special meeting agenda but attendance of not involved members is not mandatory. At monthly meetings, mandatory to members, I would expect pr6gress i reports on all items covered at the special meetings. 2. "The Health Physicist (ALARA) shall serve as chairperson of the ALARA Committee. In his/her absence the Health Physicist (Plant) will serve ,t Q irperson. (No coment except why hasn't a new pennanent chairperson been appointty 3. "The Principal Engineering Technician (HP) shall serve as comittee secreta ry. In his/her absence, the chairperson will appoint another member of the committee to the secretary position." No comment. 4. "A quorum of the ALARA Comittee shall consist of the chairman and three vtting members." l The responsibilities of this comittee do not lend themselves to majority rule. No quorum should be required. Attendance as discussed above, should be mandatory. It should be the responsibility of each comittee i member to attend or make certain that an approved alternate attends. C(V) Meetino Frequency The ALARA Comittee shall meet a minimum of once per calendar month and more frequently as may be deemed appropriate by the ALARA chairperson." See above discussion. D (VI) Procedural Requirements 1. "The ALARA Chairperson will prepare an agenda for all announced meetings. . It is to be distributed to members prior to the meeting when time pennits." -r-e --e

J L G Schwieger 6-June 17, 1983 L "When time permits" should be eliminated. It diminishes the importance of ALARA. 2. "In the event that an emergency meeting of the Comittee is necessary l and a quorum cannot be gathered, it is permissible to canvass the members to obtain decisions on items requiring review." This should be used sparingly,if at all. As stated, Wrtually everything could cause an emergency meeting. 3. "The Comittee shall maintain written minutes of each meeting and copies shall be provided to the Chemistry and Radiation Supervisor, Plant Superintendent, the Manager of Nuclear Operations, Manager Nuclear Engineering and the Chairman of. the MSRC." This added reference to written minutes and distribution tends to support the opinion that the entire program Lone of lin urviq a.DQacking ,,_ sincerity or dedicat.i h Recipients of mTnutes must acknowledge tWe C ~ coment, reTMorce, enact or otherwise endorse the comittee's action. If the comittee's work is consistent and continuous., important, this reinforcement must be 111. CONCLUSIONS AND RECOMMENDATIONS To the question, "Is ALARA meeting its comitments," the answer must be YES. To this "YES" must be added "under the circumstances," or "but, they could do more." d o.....' N 4 9 N b Hl7 bI N 'I l These, an/, 'ther qualifications, come to mind as one reads the references. I < 3 ', J /' The battle in the wording of the referenced documents indicates an "eco" VLLaineere_ objectivity. This weakens to a sense of fr'ustration in 1983. O' . L. In recent meetings, a new sene of purpose is adopted. This analysis is ^ based on the use of certain words. /," {f y On the whole, the work done by the committet. Appears to be accepted by the j \\s/S,/,affected parties. The question arises as to htw much of the comittee w'ork Q.' should be routinely done by other departments. N t The charter of the ALARA comittee should be reduced by the elimination of .) Y, Y ambiguity and reinforcing the reviewing responsibility of the comittee. l I[, A new permanent chairperson should be appointed or the alternate chairper B role should be defined as having full chair powers when the chair is vacant.

  • f

+All documents involving radiation should routinely be routed through g p y 4-poee for review and coment. t 4gt Management and MSRC reviews and monitoring should be more ob i ,h ALARA committee. g,,Q, g f ~, . gly. f Q' ? ?~s o.o;[t, V ' ' w~as. f:1 ~AG ,f <e. t.M,

4..,.

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~. I' O L G Schwieger 7 June 17, 1983 s Formal periodic review of all ALARA comittee routine functions should be conducted and comented on to the comittee. Routine areas of study and evaluation should be established to provide ongoing responsible programs. I e l '*4 l l

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SACRAMENTO MUNICIPAL UTILITY DISTRICT g OFrict MEMORANDUM L.R. Ke11 man oAve, July 7, 1983 To,

rnou, E.W. Bradley
suoster, CHARTER FOR RANCHO SECO RADIATION EXPOSURE ALARA COMMITTEE (ALARA COMMITTEE)

I also have concern over the current ALARA comittee charter and agree that the charter needs to be significantly revised. The current charter crosses many areas of responsibility, is vague, and not well defined. However, before the ALARA comittee charter can be revised, the following groups responsibilities in the area of radiation protection must be clearly defined.

1. Nuclear Operation
2. Manager of Nuclear Operations
3. Radiation Protection Manager
4. Health Physics Technicians
5. Plant Operations
6. Maintenance
7. Scheduling
8. Training
9. First Line Supervisors
10. Nuclear Engineering
11. Manager of Nuclear Engineering
12. Corporate Health Physicist
13. PRC
14. MSRC
15. ALARA Staff
16. ALARA Comittee
17. Quality Assurance NUREG-0761 is a good place to start for defining the responsibilities of the various areas.

Regulatory Guide 8.10 is a very concise document and a good place to start in determining the possible role of an ALARA comittee. R.G. 8.10 C.1. "The comitment made by licensee management to minimize exposures should provide clearly defined radiation protection responsibili-ties and an environment in which the radiation protection staff can do it's job properly',' -The comitment is provided in the "ALARA Policy Statement". -Clearly, defined responsibilities between various areas needs to be i accomplished. 7 -Environment could be improved. R.G. 8.10 C.1.a " Plant personnel should be made aware of management's' comitment to keep occupational exposures as low as is reasonably achievable." 5 % CHOW 5 7c

L.R. Keilman July 7, 1983 .t Training responsibility R.G. 8.10 C.).b " Management should periodically perform e formal audit to determine how exposures might be lowered." - Q.A. responsibility. P..G. 8.10 C.1.c "The management should assure that there is a well-supervised radiation protection capability with well defined responsibili-ties." - Well-defined responsibilities need to be established. - Well-supervised radiation protection capability exists in the Chemistry, and Radiation Protection Superintendant, however, improvements could be made. R.G. 8.10 C.1.d "The management should see that plant workers receive sufficient training." - Training responsibility. R.G. 8.10 C.1.e "The Radiation Safety Officer (R$0) should be given sufficient authority to achieve safe plant operations." - I believe the authorf2y exists but the perception prevails that it does not exist. R.G. 8.10 C.1.f " Modifications to operating and maintenance procedures and to plant equipment and facilities should be made where they will sub-stantially reduce exposures at a reasonable cost." - Review of operating and maintenance procedures should be the responsibility of ALARA staff. - Modifications of operating and maintenance procedures should be the re-sponsibility of Nuclear Operations with proper review and approval by the PRC. - Review of plant equiment and facilities should be the responsibility of the ALARA committee. - The ALARA committee should report their findings and submit recommendations l to the MSRC. - The MSRC should act upon the recommendations and task the appropriate l department with the agreed upon action. R.G. 8.10 C.2. "It should be the responsibility of the RSO and the radiation protection staff to conduct surveillance programs and investiga-tions to ensure that occupational exposures are as far below the specified limits as is reasonably achievable. Additionally, they should be vigilant in search out new and better ways to perform all radiation jobs with less exposure." - Day to day activities are clearly the responsibility of the site Health Physics group. - Long range activities for reducing exposures is the responsibility of the ALARA staff and ALARA committee.

0 t L.R. Keilman July 7,1983 R.G. 8.10 C.2.a "The RSO and the radiation protections staff should know the origins of radiation exposures inthe plant." - The discussion in this section points to the need for an extensive radiation records data base. - It should be the responsibility of the site Health Physics group to establish this data base and keep it up dated. - It is the responsibility of the ALARA staff and ALARA comittee to analyze this data base. R.G. 8.10 C.2.b "The RSO and the radiation protection staff should look for ways to reduce exposures." - The day to day reduction activities are the responsibility of the site H.P. group. - The ALARA staff can assist the site H.P. group coming up with methods and procedures for reducing exposures. - Long term reduction activities are the responsibility of the ALARA comittee. R.G. 8.10 C.2.c " Adequate equipment and supplies for radiation protection work should be provided." ) - Site H.P. responsibility. With this background I will now coment on the ALARA comittee charter. CHARTER: The ALARA Comittee is established to perform review and evaluation of changes, events, and procedures to assure radiation exposure to individuais are minimized. COMMENT: I do not agree. The ALARA Committee should review and evaluate: - plant design - plant operations - plant surveillence and maintenance practices i - plant decomisioning The ALARA staff should review and evaluate, j - plant modifications l - events - procedures CHARTER: The ALARA Comittee shall perform audit and review furictions for maintaining radiation exposures ALARA in areas of planning, designing, constructing, operating, modifying, and decommissioning of the. Rancho Seco Nuclear Generating Station. Specifically, the nature of the business to be transacted is: COMMENT: The ALARA Committee should review and make recomendations to the MSRC. The Q.A. group should audit.

I 1 L.R. Keilman July 7, 1983 ( t CHARTER:

1. Review and maintain current the ALARA Policy Statement signed by Nuclear Operations, Generation Engineering, and i

SMUD management. l COMMENT: This is the responsibility of the ALARA staff, not a comittee. CHARTER:

2. Make recomendations on long-term ALARA program planning and obtain MSRC concurrence.

Establish goals and schedules to meet program requirements. Assist Nuclear Operation and Generation Engineering Departments in implementing changes to meet these goals. Develop methodology and milestones for monitoring the success of meeting the established goals. COMMENT: Make recomendations to the MSRC yes, it is not their respons-ibility to obtain concurrence. The MSRC can do with them as they may. Goals and schedules should come from the MSRC. Assistance should come.from ALARA staff. Methodology and mile-stones should come from the MSRC. CHARTER:

3. Review the Radiation Control Manual and any other procedures or changes thereto as referred by the Plant Superintendent, the Plant Review Comittee, or the Chemistry and Radiation Supervisor as having a potential for exposing individuals to radiation.

COMMENT! Repsonsibility of the ALARA staff. CHARTER:

4. Upon a request by the Plant Review Comitee, provide a de-tailed review of proposed special or unusual tests, ex-periments, or procedures having potential for exposing in-dividuals to radiation.

COMMENT: Disagree. ALARA comittee takes it's direction from the MSRC not the PRC. CHARTER:

5. Assure that an adequate ALARA review is performed on proposed changes or modifications to plant systems or equipment that have a potential for exposing individuals to radiation.

COMMENT: Disagree, this is the responsibility of the ALARA staff within l the ECN/DCN process. CHARTER:

6. Upon a request by the Plant Review Committee or Management l

Safety Review Comittee, provide an investigation of ab-normal radiation exposures or overexposures and prepare'a l report covering evaluation and recomendations to prevent recurrence. COMMENT: Disagree, this is the responsibility of the Station H'ealth Physicist. 9 4

4 L.R. Keilman July 7, 1983 [ CHARTER:

7. perform special reviews and investigations and produce re-ports as requested by the Chairman of the Management i

Safety Review Committee. COMMENT: Agree. CHARTER:

8. Prior to the start of any major planned outage, review applicable aspects and prepare' a report covering evaluation and recommendations for maintaining radiation exposures ALARA. This-report should be iforwarded to the Chemistry and Radiation Supervisor, the Plant Superintendent, the Manager of Nuclear Operations, Manager of Generation Engineering, and to the Management Safety Review Committee for their appropriati action.

COMMENT: This report is of questionable value. A discussion within the MSRC would be helpful before a decision is made or this re-quirement. The scope and purpose of this report must be better defined. CHARTER:

9. Copies of approved ALARA Committee meeting minutes will be forwarded to MSRC Committee members for information.

At least semi-annually the ALARA Committee will review radiation exposure documentation and prepare and forward a report cover-ing evaluation and recommendations for maintaining rsdiation exposures ALARA to the Management Safety Review Committee members. The ALARA Committee-chairman will subsequently meet with the MSRC Committee to discuss details of the report. j COMMENT: Meeting minutes are not necessary if the Committee generates l specific reports concerning long range ALARA recommendations. CHARTER:

10. Actively pursue ALARA recommendations from employees.

Review, respond, and follow-up on ALARA-related suggestions originating from the Employee ALARA Suggestion Program. COMMENT: Disagree, this is the responsibility of the ALARA staff. cc: 3rd Floor Files R.A. Dieterich

SACRAMENTO MUNICIPAL UTILITY DISTRICT orricE MEMoRANoVM oATE: July 11, 1093 vo ugo.t ugugges -,--~- ....Frm';li4Mpt:-?;~h~tMZ44 7.. s.c.= ~ rnom E. W. Bradley sueJECT: RADIOLOGlCAL PROTECTION AND ALARA Lee Kellman has Instructed me to distribute the attached three memos for your review and that the subject of Radiological Protection /ALARA be placed on the agenda for the next MSRC Meeting. Attachments: District memo EVB to LRK dated July 5,1983 Recommendations To Fulfill The District's Commitment to Radiological Protection, ALARA and Environmental Survelliance District memo EWB to LRK dated July 6, 1983 Comments on ASC to LGS memo dated June 17, 1983 Review of the ALARA Program and Current Function District memo EWB to LRK dated July 7,1983 Charter for Rancho Seco Radiation Exposure ALARA Committee (ALARA Committee) EWB:rb cc: R. W. Myers W. B. Rogers R.

l. Miller J. H.

Reese 3rd Floor Files 1 1 y A AC. N n-obf ?

l 01 !!iVESTIGATIVE LOG SHEET

Title:

PMmo SDI - Potential Willful File Number: d5-86-010 Violation by SKJD Panagers in the Contrc1 PEI-FEI-RV-66-010 of Licuid Radioactive Effluents. Als Number: w.nc.r nnan Investigator (s) Ims Date Assigned: JU:E 13, 1986 Date Reassigned: Licensec/ Company / Person / Incident: A11eger: ins SACPAMDTIO MLNICIPAL UTILITIES DISTRICT ConfidentiaIity Granted: Yes] No] Characterization: Inm w tion Report 16. SS/312/86-15 docu-ents possible disrecard or reckless indif forence bv S!t1D nnnacers in the control of licuid radioactive effluents. Date Opened as Inquiry: JlNE 23, 1986 Date Closed as an Inquiry: J. 29 9, C Date ROI mailed to 01:HQ: m /s /%7 Date Opened as a Case: e n ~._ Type of R01: Pending [ Closed { Date Case Closed: to /tb /O Dates of Pending R01s: Date ROI Received to/=(3/en by 01:RY: Date ROI @ Inquiry [ delivered to RV: to 49 /M Referred to DOJ: Yes @ No O oate Referred: to /a> /+ tocation: ~<eme 4e '] Date 00J gave a prosecutive opinion Declined ] Prosecution Additional Remarks: / n w o s. / / 2 7 9 - 9 /_ i/ H k d Ik D0ets'cl o n to[)o [41 An bbY h ' $v_ Am cet 4d by(MAMH 6WhD e+-W .,sw,g g gg

v....., yn.,, vi. n i r w,n 'TACIL1TY TYPE: cTNE0FCA ~ n ((PWR) POWER REACTOR / DOCKET # _50-312 (A) ASSIST NPWR) NON-POWER REACTOR /NAME E ((Q) INQUIRE VEND) YENDDR/ DOCKET #

1) INVESTIGATION MLIC) MATERIAL LICENSE /NAME OTH) OTHER

/NAME __

  • DATE OF RECEIPT: r /n /pr cTITLE: (Limit 100 Charaeters) PRC10 SDco - Potential Willful violation by swD Managers in the Control of Liquid Padioactive Effluents.

INVESTIGATOR'S INITI ALS: pay ' LEAD,n w CCASE ST ATUS: SOURCE F ALLEGATION: ~~(f OPEN LICENSEE xx TRANSFERRED VEllDOR CLOSED / ACTIVE CONTRACTOR (I CLOSED / INACTIVE 2 NRC 'cFIELO WORK STATUS: XX PENDING ENOR FIELD WORK IN PROGRESS AN0'lYM005 OTHER FIELD WORK IN ABEYANCE FIELD WORK COMPLETE TYPE.0F URONGDOING: (See Tl Table for Codes) DRAFT REPORT HEADQUARTER REVIEW (If OTHER: ) (FP) FINAL REPORT ISSUED DESCRIPTION: (Limit 500 Characters) Roquest for Investigation PII-RV-86-010 received this date. Field work will begin on/or about June 30, 1986. Region V has requested the inquiry to be completed on July 20, 1986 in order to process tinely enforcement action. COMMENTS / REMARKS: (Limit 500 Characters) e START DATE: Ju G 23, 1986 FIELD OFFICE NUMBER: 05-86-010 1 ESTIMATED COMPLETION DATE: JULY 20, 1986 l ACTUAL COMPLETION DATE: ZIP CODE: ALL RELATED CASES: REFERRAL: EDO (RS) REGION 5 ~ 1 HQ O!A ~ (R1) REGION 1 DOJ ~~ (R2) REGION 2 LAW INF ~ (R3) REGION 3 FBI \\f ~ (R4) REGION 4 OTHER J/)1 r 0 REQUIRED ELEMENT ~ , 3.g p s. sg -ot 0 - ocw(

E iP0fiSE/ STATUS TO RE0 VEST FOR If '571GA710N June 25, 1986 i TO: John B. P.artin, Rogional I&inistrator Pcgion V FROM: Pdert G. Marsh, Director office of Investigations Field Office, Pegion V REGION REQUEST NO.: Pri-RV-86-010 DATE OF REQUEST: June 13. 1906 Licensee / Vender / Applicant: sacramnto Municip31 titility nittract . Facility or Site tocation psnehn sem D0cket NO. Sn-312 License NO. Dpp-14 CASE INITIATED _:c:. CASE NO. 05-86-010 // Date Opened June 23, 1986 TYPE OF CASE: ItOUIRY Assist (A) Inquiry (Q) ECD stiv no.19ec Investigation (1) Case Priority High l Normal nz! Low CASE NOT INITIATED: REASON: COMMENTS: % e assigned priority is appropriate, however, an estimated empletion date of July 20, 1986 is unachievable. A preliminary D3 of Septerter 15, 1986 will be assigned for r.csolution of this matter. Every attempt will be made to determine the extent and' nature of the investigative scope by July 20, 1986. cc: J. Hunt 01:HQ 1 033 1 / ./j .;A Lb ' /' Q c,. RL-Q C' < C >'}}

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