ML19220C949

Forwards Questions & Answers as Backup for 790410 Congressional Hearing Re TMI Incident

ML19220C949
Person / Time
Site:	Crane
Issue date:	04/10/1979
From:	NRC OFFICE OF POLICY EVALUATIONS (OPE)
To:	Gilinsky V, Hendrie J, Kennedy R NRC COMMISSION (OCM)
References
NUDOCS 7905160092
Download: ML19220C949 (18)

Text

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50-320 4/10/79 QUESTIONS ATiD ATlSilERS ?REPARED BY OPE AS BACKUP FOR SENATOR HART'S CONGRESSIONAL HEARING APRIL 10 118 onctua

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15. Anticipation of hydrogen bubble proble:

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i. International (export) implica icns (4 Q's & A's) f 118 206

. How might the events and the cutcome have been changed if an ;RC resident inspector had been pr^senc?

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.The auxiliary feedacter pump discharge valves were closed for two weeks crior to and into the accident while the reactor was operating.

It is very likely that an NRC resident inspector would have noted this situation and insisted on immediate correction.

If the situation had bnen corrected the accident might have been avoided or, at least, had' greatly reduced ccnsequences.

Ir addition, a resident inspector expects to be contacted and to respond i : ediately to licensee events.

If such contact had been made, l;RC wculd have had a highly qualified reactcr cperations inspe: tor en site much earlier ir the unfolding events rather than at about iC a.m cn " arch 23 (ahen MRC's Regicn I response car arrived at the site).

Nevertheless, the presence of a resident inspe: tor in the control rocm at the time of the accident r:ight not have affected the initial phase of the i

accident.

The NRC inspector would not be responsible for cperatcr actions --

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Me:ropolitar. Edison is responsible for operating the Three Mile Island plant.

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..nat orovision does t'?.* have to see tntt license re:uire en:s--such as

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b' hen non-ccmoliance with regulations is identified 0..

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1:nat is ?PC's chilcsochv cor.cerninc decendence on coera:Or.4ud: ment in safety-cri.ical oceraticr.s.such as coera tion of ECCS?

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It must be emphasized that althcugh ope ator judgment is relied on for safe operation of a nuclear power plant, this dces no; mean that safety devices do not cperatzuntil the operator acts.

Many critical actions, such as initiating emergency core cco,ilng, are tax. en autc aticaii;r wnen certain sensors detect potentially hazardous conditions.

The operatcr can manually Overrisve certain or. these automatic acticns it, ror exampie, t.ne information at hand indicates to the oper: tor that the initiatinc sigr.al is spurious.

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,e which time a renewal must be applied. for.

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': hat crecautiorarv action is 'mC takinc at the other Eacccck L '.-li l cc x nuclear facilitiet?

By April 1, NRC's Office of Inspection and Enforcement transmitted a bulletin (IE Bulletin 79-05) to all utilities with an opera:ing Sabcock

& ',!ilc x pressurized water reactor.

The eight operating B&W reactors are Arkansas ' Unit 1, Crystal River Unit 3, Davis Besse Unit 1, Cconee Units 1, 2, 3, Rancho Seco, and Three Mile Island Unit 1.)

The bulletin requested that each utility immediately review its facilities and procedures in light of the Three Mile Isl'and event to preclude a similar event.

Utilities have 10 days to submit to NRC detailed results of their reviews of the Bulletin's seven items.

Also, en April 1 NRC dispatched an inspector to three sites with operating 3LU reactors:

Crystal River (Fla.), Davis Besse (Ohio), and Rancho Seco (Calif.).

(Resident inspectors had previously been assigned to the other two sites.)

In addition to the usual resident inspectcr duties, these inspectors are required to assure that licensees are conscientiously fulfilling the Bulletin's provisions.

They will also keep licensees informed of the details of the Three Mile Island accident.

Currently NRC is inspecting these reactors during every operating shift.

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r The NRC has initiated a generic review of all B&W reactors to determine whether there are any inherent design flaws.

This investigation includes NRC licensing offices and varicus licensing boards and panels.

118 210

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4, Oc you anticipate that',Feactor.,ill te operational acain?

If so, when?

What steps must. be done to restore it to operacing capacity?

It is too early to even consider whether the reactor will or will not be restcred to cperation.

The Commissicn's inves;igation shculd be completed and

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The tcst expensive phase is

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l}y d ?,.H 7 9 What are respective roles cf GRC and 5: ate and local goverrments relating to radiological emergency situatiens?_

s NRC has no statutory authority to require State and local goverr.ments to devise or to test radiological emergency response plans.

The Commission's regulaticns recogni7e the States' authority and responsibility to rescord to emercency situations within their jurisdictions.

NRC policy provides for guidance for the States in developing radiological emerc. enc.y response plans.

NRC conducts training courses for State and local personnel engaged in

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emerge'ncy respense actiyities and evaluates State eme gency plans against a check list of 70 essential elements.

Through a Federal assistance program NRC cnd c her Federal agencies make reccmmendations for improvement.

NRC also exercises a lead agency role in a Federal interagency program which provides guidance and assistance to State and local governments in developing and testing their radioicgical emergency response capabilities.

NRC has been able to work cc:perativelf with the States in reviewinc : heir plans and capabilities.

Thus f ar, NRC has concerred in theemergency response plans of 11 States.*

(Pennsylvania is not among them.)

Facility cperators view emergency acticns to prctect public health and safety cutside a facility's boundaries as the responsibility of State and local L

t-I governments.

Under NRC regulations (10 CFR Part 50, Appendix E) licensees are i

recuired, as part of the NRC-approved licensee emergency plan, to have pro-cedures in place for notifying local, State and Federal cfficials and agencies in the event of an emergency.

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'Ca ifcrnia, Connec!1 Cut, Ce11 ware, Ficrica, Nev, Cersey, New York, Washington, Sou:n Carolina, Kansas, Alabama, Icwa.

On ;nat basis did the Governor cf Pennsylvania reccamend evacuation of pregnant wcmen and children cut to 5,5.i l e c ?

On Friday, March 30, folic.ving a release of radioactivity frc: the Three Mile Island piant, Governor Thornburgh of Pennsylvania recc mended the evacuation cf pre-schccl children and pregnant wcren withir 5 miles of the plant.

The Governor's press office reported a reading of 1200 nillirems per hour at the 4

plant vent frca which the gases escaped.

This is 20 percent higher than the level at which the EPA protective action cuides call for protective action.

(One rem vinole bcdy, dose if received in :ne hcur would trigter a protective response under E?A cuidar.ce.

At 5 rem projected dese, respcnse..'ould be d :& L,. 6 a.

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assess the magnitude of the accident to make reccr endations to State and a

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'r.' hat actions should ;;RC take in the future tc avoid ccn us ng disseminatica f

i of informiticn to the ceneral public concerninc the possibility of ev:cuation?

Under current arrangements, any recc c.endation for evacuation would ccme f rc. the licensee to State end local authorities.

In the ca,se of Three P.iie Island, i RC made recerrtendations to the Governcr, thus by-passing

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clarified on the basis of this experienco.

I# in the future I;RC inttnds

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k 8 2,U Gi cen the risks of a ccre meltdc.un er a hydrogen expicsion, :hy.-;ere nc evacuation plans put inta effect?

The State informs us that evacuation plans were in readir.ess.

Had the experts invcived judged a ccre maltdc*,.n,iculd cc:ur during the course of the accident or that a hydrogen exmlosion could occur if certain changes e

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an evacuation would have in the plant's operations were purpcsely made,b been crcered by the State.

The decision would have been Gcverncr Thcenburgh's.

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The States surrounding Pennsylvania have also dor.e monitoring cn their c.in.

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". "s _ l r n d. e.

.. a a

...n..

.v n...a.rn_.s r, a j a,.. ;. m. 3

-. m. ]

4.. r..

'. " - n. d.

,* a a

, o

o.. c. o r. -...,_j s

,.y a

.v s

v

ransferred through pices to storage tanks outside the reactor con ainment C u h.

c, ". c_.r '. ". '. *. i n o #.

a ", c i. / o_ " ". ' d. i c a. '. i v _'

2. ' e u'.."

" o i l l.' ", o_

'.r c....

-r ", l v" 4ina.

s

.s s or 3

i the overficw of tanks released radioactive cases to *he atmosphere.

While a number cf employees at tne site received more than r:utir.e cccupational l' ds_s r.v'.

a_,-, o. ' r

's o h >. ". o.

b _' o_, a d = n : a. ^. ' ' c " - ".. '..

.R a.d i a *. i o n c

s oxs3>"s. n,

+ ' a.

c. + n_ o.v - n. s_ f a.d. l. e.. n. ] e.na_r. ~...s..

lr n r r,. 'i. - n.. 2.. 4 e n b u, *, a 1 s.

] c f c. ] - r..

• e. i. s 4*+

a -

m s

.n si.

m r

o y

io o

o a

v.

s_

.s.-.

.n. e,, ].

<n o.X ga..-ce C :.

jn.s4..i.s 3]s o

..rre_

• n. 3.,.

3 e

.,Ctu 4. 0 i

. r.,, n n.. 3 sc e

2

..i...

w i.

l ;. :. s.s, h

I18 2l9

-.*jsn,.

2

.c2e n>

In c h. 3. -. n.

cvs a

e + -i.

a

.:..., v L....) -. a. c.

i.. 2

.w

,a.

ar-wsw n

v.

a nf.

. i.

a 5....

u.

C. n e.

a.. a. 'i s e.nnn9

.s T.. j e c,, a. s 'w i ^v.m.

an r4iv "a.

e n. # - '.. d a. d.

+o ir6.= e -.~= w h 2 '.

.c - ^ ^ "w l.a '. i '/ n.

...2..n_-

n+

sgv.

s.

r.w os s

e v

we do not have all the relevant infcrmaticn at h2nd.

'ne kn0w that during

• he course of the T.'M accident there were oeriods wher, the core ccolir.g was m ar o. i n a l.

.i there hau been no effective coo 3.inc. or tne core ter an a pre-7, j

e ci2ble ler.gth of time, a T.eltdown cculd have resulted.

Since there is evidence

.2

.c m. n. i w. i +. j.n. : occurro.d

... n. r - r.e

s. ; 3,2 e.,... 2 c n. s. jw j e.

n e e e 4. x ] n.

+ws.

.a.,..

+w

-c

.~

sa.

curing cr.e of the snart periods when core ccoling apseered to oc insufficient,

~.,.,,

c. -

+

.. s

1. y. r. 2 j e.

1 4.

... j,, g 1 s.

,.m,,

i.

s..-3

3..g p,

. ji a_

2

p.., c.

3 i

2 s

4.. e., '.

e. }, W W j..

f...., p g a '. n. c, +.

+ ' a.

e. a. n. 4. 2 1 [ g r.

. n. i +. s v... -.,. 2 r>

c arn.-

-r6 ps..

.rn s

.s s.

+

m-js,

'..".a. n a. r i. o " n h a. n.., '. s - r o.

- u n o.' c ' "s " h 'i c.

,,.r>2 e, rJ

. c. d. 4. r. '. s". a e m. >.- '.

.r u-.

c v a. 3 s. l.

.t '. '.. i i a b"s v" i n.

.h a. d F

a. /. 0.2 ^ " n '

. h a.

r, i..... #,, a - o.

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ca a

w gu 3

+ - n.

c..- - o.,g.

si.e 12..na

. +', en.rn.. n.

.,-3 s.

u un

._-a_s.

.. 2 r. a.

4... a. 4. o c.. u l.1 c.,

s-e o x s '. =. d.

1. c r

.a r.".

a

.,-a r i u'.hl e.

'.'.~.~a, i

' '. i-l '. 's. i.v '. n m".

- n i ' d

e. r:

e"e1s '

m n m, ". o.

i s

g ev.

.s s e

a..3. '.. o...

p. o w. o. n,

50 h,J" b l.> di.d er'. 2 s.

'..".)'e s

....d ' '. 1' v n.>.. ~, s.. - n.

o r.

1 c

- s e

.. ~,>. n a'

. a i '. a *s l n.

'u o c c r *.

• c l i '+

c'.n u~"sp ^u' e n.

'. a c '. ' n,

's.", a_

~.,a.. =. ~. p. r.a.

o e e i b, l 1' '.;.

o.

o o

s g

w..

s

., c.

.. 3,i

s. n n d.$ -)

4 4. s 'w - - a. s. d o.r a. d 'wo v.ha e

1. . #. i c. i c..r *

1. . o r

a. m.. o..r e '..n ". y' w v >..u.=.. i r. r.

o v

i ww.

v.

e av sw 3

of the nearb" pcculation.

P

)\\0 bud f

- l a-

,,,,...,.nn_ m,-sin _i-a r.. i r.

'.... h. e.r=____.~.

" n

.c o l.'..

2.. #. ^. '. n = ' c. '. w. =... '.

n.. o_ -. j...

r.

a.

s.

s Answer:

."o, it was not.,

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118 2c

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