ML20027E778

Responds to Rl Amsden Re Mid-Coast Health Research Group Allegation That Detailed LER Info No Longer Available at Lpdr.No Changes Made to LER Submittal or Distribution.Lers on File at Lpdr

ML20027E778
Person / Time
Site:	Maine Yankee
Issue date:	10/29/1982
From:	Dircks W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:	Cohen W SENATE
Shared Package
ML20027A912	List: ML20027A911 ML20027E778
References
NUDOCS 8211160135
Download: ML20027E778 (12)

Text

.,w e

T ps Ft U

qq p.g eq gg

.r M,,

W 4

7 q-V 4

'g

.I OCT 2 915a2 The Honorable William S. Cohen United States Senate Washington, DC 20510

Dear Senator Cohen:

This is in response to Ms. Rebecca L. Amsden's letter of October 4,1982, regarding concerns expressed by Ms. Maria Holt of Bath, Maine, whose organi-zation, the Mid-Coast Health Research Group, is interested in monitoring the Licensee Event Reports (LERs) prepared for events that occur at the Maine Yankee Atomic Power Station in Wiscasset, Maine. Ms. Holt indicated that she needed access to the detailed information contained in the LERs, and thought that because of a recent modification in the format of a monthly sumary of LERs, this information was no longer available at the Wiscasset Public Library, the Nuclear Regulatory Commission's (NRC's)

Local Public Document Room (LPDR) for Maine Yankee.

There has been no change in the format and procedures for licensees reporting individual LERs, and this infomation continues to be made available for inspection and copying at the Wiscasset Public Library. The only recent change involved the refomatting of the monthly summary of LERs, not the LER submittal or distribution.

In this regard, seven new LERs or followup reports to previously identified LERs concerning Maine Yankee have been received since August 1982, and we have confimed that these reports are on file at the Library. Copies are enclosed for your infomation. Also enclosed are copies of NRC Regulatory Guide 1.16 " Reporting of Operating Information--Appendix A, Technical Specifications, and NUREG-0161, Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File, Revision 1," which describe in detail 'the current procedures for LER reporting.

For your infomation, the NRC has under consideration revisions to the LER reporting procedure. On May 6, 1982, a proposed rule was published in the Federal Register entitled, Licensee Event Report System" (copy enclosed).

The proposed rule would revise and codify the existing LER system; however, licensees would still be required to submit detailed reports on significant operating events. The NRC is now reviewing the responses received on the proposed rule during the public coment period which ended in July 1982.

8211160135 821029 i

PDR ADOCK 05000309 H

PDR 4

DATEk eo a8o-329 2

sacgosy aie no 80, suc o2fo_

OFFICIAL RECORD COPY _ _ __,,_

l s

n

.m 7

m,

• V

()

f, ~ ~

Q y

f 2-

v.*

TheHonorableWjliamS. Cohen United States Senate Washington, DC 20S10

Dear Senator Cohen:

regarding concerns exphss. Rebecca L. Amsden's letter of October 4,1982, This is in response t Ms ed by Ms. Maria Holt of Bath, Maine, whose organi-zation, the Mid-Coast hec 1th Research Group, is interested in monitoring the Licensee Event Reports (L Rs) prepared for events that occur at the Maine Yankee Atomic Power Stati(on in Wiscasset, Maine.Ms. Holt indicated the needed access to the deta11std infomation contained in the LERs, and thought that because of a recent modification in the LER femat, this information was no longer available at the Wi'scasset Public Library, the Nuclear Regulatory Comission's (NRC's) local Pub c Document Room (LPDR) for Maine Yankee.

There has been no change in NRC's, procedures for reporting LERs, and this infomstion continues to be made available for inspection and copying at the Wiscasset Public Library.

In this regard, seven new LERs or followup reports to previously identified LERs concerning Maine Yankee have been received since August 1982, and we have confimed that these reports are on file at the Library.

Copies are enclosed for your information. Also enclosed are copies of NRC Regulatory Guide 1.16, Reporting of Operating for Preparation of Data Entry Sheets for\\ cations, and NUREG-0161. Instructions Infomation--Appendix A, Technical Specifi Licensee Event Report (LER) File, Revision 1, which describe in detail the current procedures for LER reporting.

The NRC is now considering revisions to the\\

LER format, and on May 6, 1982, published in the Federal Register for public*Coment a proposed rule entitled

" Licensee Event Report System" (copy enclosed)l The proposed rule would revise and codify the existing LRR system, which is a oluntary reporting system in which nuclear power plant licensees provide ta concerning reactor component failure ever.ts experienced by licensee In the proposed rule, 3

the Comission endorsed the Institute for Nuclear ower Operations' plan to assume responsibility for management of the exi ting equivalent industry program, the Nuclear Plant Reliability Data System. \\The proposed rule would provide the NRC with the most efficient system to gather data on the operation of nuclear power reactors in order to evaluate the saf ty of selected systems of these reactors.

• "'c4

'****4 DATEf;...............l....................

oc romu m no co-cw me OFFICIAL R'ZCORD COPY

• " "8 ]

e.

y y

l

=-

.,_ ; ~

o The Honorable William S. Cohen If Ms. Holt has difficulty locating any of the LERs at the Wiscasset Public Library, she may telephone Ms. Jona Souder, Chief of NRC's Local Public Document Room Branch, toll free on 800-638-8081.

Sincerely, b) T. A. Rehm 4 William J. Dircks h Execytive Director for Operations

Enclosures:

1.

LERs (7) 2.

Regulatory Guide 1.16 3.

NUREG-0161 4.

May 6, 1982, FR Notice Distribution SECY-82-1002 (3)

EDO 12373 EDO Rdg CA PNorry (2)

HDenton GCunningham LUnderwood JRoe WDircks PDR D

W'

}

<j3

'/A.........

...DD: ADM D:ADM

E EDV45)

..A.D.M....

. A..E..O. D...A

...R..:.A..D.F

... D.. :.

onict cu:uar)

Ber:km JMF MSpringe PGNor JRo

.VfdOIiFcks,,,,,,,

.......j.3.........

10p[/82 J/

(2

.1U/ey/5f....,

1..............

10/ /82

......J... 7/ 82 10/

om) 0/25/82 82

• " '*8o-32 e24 sac ronw sie'iio<eoi nnew o24o OFFICIAL RECOFiD COPY

ENCLOSURE 1

..+ ^ %,

/

\\

{UAl0(

MH(( ' 'u.'

PriV..

.;;,p e stlt N.

2,Ip,x a 2 7tu s

4 h

-t. mm.. ri s,7%

\\

2fs7.xh24321 IH-82-157 August 11, 1982 l

thited States Nuclear kquiatzw Carinission Office of Inspection and Enforossrumt 11cgion I 631 Park Avenuo King of Prussia, Pennsylvania 19406 Attention: Mr. Ibnald C. Haynes - Director 4

lieference a)

License No. DPR-36 (Docket No. 50-309)

Dear Sir:

sub M : Maine Yankee Reportable Ocozzence No. 82-021/01T-0 Picase find enclosed the Licensee Event Report for hine Yankee in ortable Occurrence No. 82-021/01T-0. This event dass not represent m

a violatlan of Tednical Specifications, but is reportable under the requirenents of 'Dednical Specificatica 5.9.1.6.I.

l We trust this infocustion will he satisfactory. Should additional l

informtion be required, pleAuse feel free to contact us.

Wry truly p urs, MMNE YM53E ATGGC PGER CCNWelf twi [.

/

E& tin C.1800d Plant Manager l

IXM/va Enclosures

.S208230302-830011 PDM ADOCK 03000309 S

PDR

.A Yo

'LIC.E NSE E L VE NT HE POR I

.1HO

+ia.i~ro ' < u u"'to~o

'o-i lg

'. J ". _. ". : > H 11 J.OI o' 01 I o lo M I o lo 1 - Mi o IQt.: 11iiIti1l@l......,

1 F)to l'> 10 10 I o l 3I o I 9 l@l o 171.> l 9 l a l 2 IQI o l 81111 I 812 l@

l'.

!L

. o e n o,,.[i N[i. tts h l

Nrun; a revtew of C.E. owners gmup traininq mterial on control rod drop cuitblinemi 1

--. bf. wittwring personnel it was discovered that the incmase in planar radial peakinal L-L (1x to local Xt.ncn burnout in core areas way from a dropped rod had not been i

. If ] l n,

previousl/ cmsidered. With an irretrievable dropped control rod the increase in I

I fhIpl7nAradialpeakingduetoXenonburnoutatfourhoursresultsinapeaknearly

'Ihe increased radial peaking could I

y,, ti>uble the initial preciicted increase in peak.

l m- ]qi{tyiued on attached page) 80 COYP vatvt 4.

9 4.'

s At:5f

( A 658

.4 tiiDi 5b140004 COveo%1%f CODE

%g4004 SveCoct l Rl Bj@ W@ W@ IX lX lX IX lX IX l@ [Z_J@ [ZJ @

_j_j 8t h esso %

OCCUR 8 l %CE REPO*41 SEO,vi%ftA4 coo't im o

. oa f ~o 9..

l812 l

{--J lo 1211 I

[gj i of 11 pt

[--d L9J

//

23 J4 26 JP 75 29

. JS 32 NPRD4 PRsWE COMP-COUPONt41 A f7.ACMut 47 5.m,DOWN SU neeTTED FORW sue.

SupPtstR UA%uFACTURER

',l o s t C F

%,, tst s

%'4A%f VtfMOD

.*OUnb

[1 F)l.x_J G Lz_J @

tz_JO t o 10 lo I

ly_J@

LN,j@

(Z_j@

12 19 19 19 l @

'A.%

. te.%

n

>s o

ao as az e

a e

~

'i CES.64ipt,0N At D CONNECTIVE ACTIONS h e

'A h situaticn is to ensure that the increase in planar radial nankino folicwina a I

1 dmpped rod cbes not result in violaticm of the specified aerwotable fus=1 dr.aicm

-] i 1inits. To aw-vlish this requires ensuring that reactor power is reduced in I

gi fh[ sufficient time to counter the long term increase in naaking due to Xenon burnout I

l if the rod sixxild prove to be irretrievable in the short term. Ohtil quantification 1 l t (Cc R'nW cn attached page) es L2.J@i "otificatica fro" **==rin@

$.L

Or smsvatus @ EEERT o.scoven, ossCaieres 1

.,w4 1

I LEJO Io I9 I716L l

i

'3 toCafioo.asi.sse@

, Ja,, %,

@j

......u..

,. -. t i e.

. Ov, o,.C r...,,

l NA j

NA

!, I.. I LZ J G i.i_JGI

.... s.o...osv n N t

,'#t t.e. 4 #,*T,0.e j

_1_J l o 1 o'.6 haIol@lz'@l NA

,N s,'.'.%,'.f.

5

,a v.....O~ @

j T1 I o I o I o l@l NA

-saceasoato saos11,

~ '

d)

.......t.....<

con noocn osoooso NA S

PDR l

. l.1 [lij61 "ac use onty l

l Z [_*.ij$l NA l

l l l l 1 l l l 11 I I l}

.o s Jmes E. Brinkler (207) 882-6321 g

..i.v, o. poi ano.

l i

1 IIR f82-021/01-T Page 2 l

INI2rr IESGIPTICN AND PICBASIE CXNSEQWNCES (Cant'd) lead to violation of the specified acceptable fuel design limits if either the rod is not retrieved Witiously or reactor power is not raamad within a reasonable period of time. Since the variations in planar radial peaking are related to Xenon redistrLh*irn sufficient time exists for Jve action. 'Ihere was no effect on the health and safety of the ptblic.

CWSE IESOtIPTIO4 AND CONECTIVE ACTIGIS (Cont'd) of the effect of long tem Xencm redistribution can be per*===d; the p ui.i course of action, therefoto, is to require an immadimea power rmadian following a rod drop. 'this action is as conservative as current C.E. Sectmical fpecificaticns for similar plants.

n'='adiate w ctive action was to revise the rod drop pMg (EP-2-21) to require initiation of a power r=A*h socin that power is reduomo to less than 70% within one hour after the dropped rod event. An attempt to withdr=* the drop 5md rod will not amenence till x=ar+rw pcuer has been reduced below 704. If i

the &w d rod cannot be retrieved within two hours after the dropped mod e

event, then a reacter sh***= will crammence and the plant is to be in a hot shutdown condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

~

Ieng tara corrective action was to initiate a stu% by angina = ring p(ersonnel to de++mine m Wa time a12cuence during whicts cperatien a continue at a re rnd power level with a duopped rod = tan 11 grad front its pagAas well a

as rarmemdations for the required rets~ of pouer x=A*ian and maximas pouer I

level for -T-a L= with a decyped rod. This - -y--- i== stW ie on~ going..

rot and is act=431=4 to be ocuplate prior to adedttal of apse:.7 solond' analysis. Mxtifimeirm to Tactuial W'4M aa= will also be pungomed as -

j i

~

6 t - %,.N yJ,;,. - -

part of cycle 7 edsulttal.

..c - :7 m.,.

g-

~

s s

+

• l 3

0

' e j

,t 1

-]

. ?.

75.,

F 4

u t.

_w:-

lM M i ATOMIC POWER 00MPARS e un No. 2. non 3270 hawt. Mairw 0457M g,

207 M424321 w

r August 13, 1982 I

MN-82-160 a

United States Nuclear Regulatory Commission 4

Directorate of Regulatory Operations Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 i.

References a) 1.icense No. DPR-36 (Docket No. 50-309) p

~.

. >.+

e Dear Sir A'

Subject:

Maine Yankee Reportable Occurrence #82-022/03L-O

-.4, Reportable occurrence No. 82-022/03I<4. This event does not

~

'.{

Please find enclosed Licanoes Event _Beport for Maine Yemkee i

~s j

represent a violation of Taekie=1 Specificettene but is reportable l'

under the requirements of Techsteal specificaties 5.9.1.7.

~

f We trust this informattom wil1 be satisfactory. Should " '

l additional informaties be required, please feel free to contact A

l D

, 7y,

us.

e 7

• i Very truly yours.'

. W.f

. w

,4,

.' J,

~

I M&lNE YAIEER AftBEIC CSFAET:

p

(_

e 1::.

Edwin C. Wood -

r-m

.6,,J

[.7 >'~ "(.

Flant Manager w

y..

- y _,... r p'.

".. ^ " 'l #

~ - " '

ECW/va

_3.g : '.-

~.

?

+

Enclosures 7

,(

r h

O O

PM j

0

- - - - ~

v'w,-9

m.'

1.lCENSEE EVE NT RE POH I c

f

[

f,

• {

(PL t A%t e Hj%109 1 v Ft AL L Hi QueHL p aNo OHV AleuN.

• 3

.l.'... _L '

L '_jQ_1 'd -l " h I". l o I" l il J Di. ' l 1 '.l '..i l@l I

IG,

]

'1EL" l ; I o! "I "I + I" J._'iFJLJ.>L11d..-l / Cl "I k l ' l il 81 ' if)

" ~

~

'......., *: ';. ;' "., f

' ' ' ~ "

3 1. A d 5 N. -t *;pg ~ t at c,.n..ra.il p l_m..y rat lon. wh ile SericI inA.roi. i m. wneh1y sur-I i

v i : 1.iu. e t e. t i n e. _tt he aut omat is bu transter switch ABT) for is low pressure l

, i L._._____.

in)cct ion.otor operated stop valve (l.S I -M-l l ) it was discovered th.it althoughj 3,!

...?.tv_.

__...~

t he Ah! performed it% intended s.ifety function, transferring power source from normal l

]

the return from alternate power to g

}

t q alternate power in t he required t iene f rame.

accomplished within tiac frame specified in the procedure.

l 7

,.___n~f.at power was not sub equent retenting of the ABT was. perf ormed with satisf actory results.

Surveillanceq

_. tinued on attached page)

(con

~

....e

..m.

.a v,u ww

..,m%, %, eou

s..u,a sm

]

I t In 10 L,,nJ@ L,,AJO I a i r l i l ^ I V l x IG L.w. JO L,zj @

si uut % t a A6 OLCUR Al '.C l,

8048f841 e.i b e90%

t.t%'.4aa sit PO** * %O U104 evet

%Q I s I.' l L-J loi212i L.c.J I nl il pt.

L.J U

'O,,

'A

/.

JS 28

.4 J9 38 32 cQa8POs t%?

AT1ACssWt47 espot04 pghwg (5,ap.

WA%ufACThes(m e

s%e.J*

• .et. 9 Mco%

eaet Mr

s. e SugereT1to f amw g,46 SupptIER gt ett eeOy.e b 1.2JC.L.r.J O LI_l @

LIJO

,I o Io I o I o I

p. @

L.,21@

L.2JJ@la 11 lo 19 0

• • .e.

a e,%

4_ :t :a u.airtios A%o comarcTivt Actsow h determined that fatture I

] i M ter an invest igation by plant eneineerine nernonnel it m.

the ABT to transfer poieer supply within specified time frame was due to the i

g, ot A,:ast at tine delay relay. The apparent cause of the relay failure was sticking con-g g

ta(ts.

The suboptimal Agastat time delay relay was a model 2400 and an investigationg gg g,will be performed to determine other safety related applications where model 2400 g

v_-i.anues on attacneo pay)

~..'....

o,

...,v. @

m,a.r oo,=,r o

c.,. vouca.,v o

s v o cow Sar'*iliaac' T***

I x^

l L.2.J@l J LJ.J@ l o I 9 I a l@l

,1 LocAfemeOrftEL M wt.6.

e i

~/s e.g. g ais

.googpagt Qe AC f tytev NA NA

,L et=,,% qt is* W at5

.*e. I e f.Pe 4 SL s*.*TSO%

l

] I o f c l n)@L,L'@l x^

... w.

.% m-. i s

m......cs@

I

]lOfofolh.2 NA S200230194-82o21'2, o

. r' mO.!..'.r'"" O pon anocn osooo3o 8

l 3.L.il@l u

=

.s NRO 'J5E mtv

, '".,' 'l... 9 @

1 11ll11Il11l1l{

i U l ijbl VA

=s James E. Brinkler (207) 882-6321

{

..avt '>' Pat rawin

d LER 782-022/03L-0 Page 2 1

EVENT DESCRIPTION AND PROBABil: CONSEQUENCES (Cont'd) testing of the other two LSI stop valve power supply transfer was satisfactory. Since the transfer device did perform its intended safety function there was no effect on public health or J

safety.

i CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (Cont'd) relays are used. All the existing time delay relays that are used on the three LSI motor operated stop valves will be replaced with the currently available electronically controlled relays..

It is anticipated that the new relays will be installed prior to plant restart following next refueling outage.

i

[

e D

5

't

_{

.e

.,,*,9 m. f F

,m e

4 I

9

~. _

f N

S MAME HRlWE Atom /CPOWERCOMP.4RS *

? *'t>U It V1) 2 N w a w i.. W n. u.trJ %

O i

August 20, 1982

(

644-82-166 l'

United States Nuclear Regulatory Camaission Directorate of Regulatory Operations Region I 631 Park Avefue King of Prussia, Pennsylvania 19403

Reference:

License No. OPR-36 (Docket No..T-309)

Dear Sir:

7

Subject:

Maine Yankee Reportable Occurrence 82-24/01T-O Pursuant to the requirements of Techrlical Specification 5.9.l.'6.1, the Maine Yankee Atomic Power Company hereby submits the followin0 report.

An investigation of LPSI pump tPSH requirements during a double ended cold leg LOCA injection phase with one LPSI pop inoperable reveals that, after amroximately eleven mirutes into the translant, the puup may operate in a Under these conditions, et pump run cut, the mode precluded in the FSAR.

required PPSH may momentarily exceed available DPSH, causing a reduction in flow and a correspondingly lower required IPSH. Discussions with the pump marufacturer and architect engineer verify this mode of operation as perfectly acceptable and raises no concem for safety. The floe rates to the RCS under these cittunstances are always well above what is required by the accident analysis. This infotination is being reported to identify a LPSI pump mode of operation not in acx:ordance with the description in the FSNt.

Very truly yours, MAIPE YANKEE ATOMIC POIER C0pFANY N

[W (dwin C. Wood % 9 5 E

Plant Manager l

l l

ECW/v1

y a

o j

r i

t I

M AllllOllPOW[liC0lI1PAllUe RR No. 2,ikn 3270 g,

Wiwaw 1, Slain

• O 457M 207-MM24321

. i 3

• t

g August 31. 1982

_g 4

MN-82-168

}i II t'nited States Nuclear Regulatory Cosenteston Directorate of Regulatcry Operations

}j Region !

611 Park Avenue

's King of Prunsta. Pennsylvania 19405 f

References a) License No. DPR-36 (Docket No. 50-309)

J IAar Sirt 1

Subject:

Maine Yankee Reportable Occurrence #82-023/017-0 7

j

i Please find enclosed Licensee Event Report for Maine Yankee j

keportable occurrence No. 82-023/017-0. 1his event does not represent a violatlos of Technical Specifications but is reportable under the:.

j requirements of Technical specification 5.9.1.6.1.

l We trust this information will be satisfactory. Should additional 1

informatton be required. please feel free to contact us.

j Very truly yours.

. -l l

MAINF YANKEE ATONIC F0WER COMPANY h

(* / tt$.

g Edwta C. Wood

),

Plant Manager

]:

1:tv/hb '

)

Fnelonure 1

~

.)

7.

0 3

C209130018 820031 g

post ADOCn O W Q s

,tw

h,esi. nee m u

r tre LICENSEE EVENT REPORT i*s. ' a v. a i '>

• L.1 1

1*I I

1 irt<*5E *a'~, ca rves ati. c:iovi Eo i~rona.atc~.

g [ s ; t. i n l y g r l jgi o l o l - j o l o l o j o l 0 l-I n l n lgp li l i li l Igj l~....~g I

s

..,...m...

.... s s........

o <.,

E

-";.",' @l n I s I o I o I o l 1 l o I 9 l(Tjl n I a I i I 8 l 8 l 2 l@lo I 8 13 I i I 8 l 2 l@

e. t. : t.e s..etiem a t, enonAsi a c ENcts gj [ in r.11 ewing data and annumptions f or the Maine Yaniree Cycle 6 Main Steam Line Break i y ( (MSI.8) Analyhin against operating procedures and tlw Technical Specifications, in i

g greparation f or perf orming cycle 7 analynen, it was realized that the full range of l

y[ Reactor Cool. ant System cold Leg temperature (Tc) was not taken into account. The j

g.j l An.it ynia did not, therefore, take into account the potential increase in moderator j

g Ldef ert_ reactivity addition if Tc in higher than the Tc programmed value, which it

T~l I could be when temperature is used to control reactivity.

(Continued on attached page)

.o C

CtPM V.agg 5tJ.A L,".1

. * *. ' t V C A @f CODI COUPON (%T 000(

$wgCQQg gygCOgg

. ^.04 Of 4s4

. 8 L,,ZJG L,ZJ @

3 17121 0 L,,*J @ l,.^_J G I 21 zl zl zl zl 1

(Kfva hg Nct segroot M( y,5.oM s.t.o.ut %.,.s A.

o

.o coo.

,m o

Oc....

i al 21 t-J lo 12121 L,cJ l of 11 7

-: L-d LOJ 2

2.

n u

n n

z.

i.,

U.'. ? *. '. 3.

.,' "#4, T.W.X'

^4'M13'

,o".,*.

'"d'l'.iS7

.J *fe,'i,..

c

~

bl)(~2)lz.._lO Lz_lO L.zlO "I ol of o@f of p@

(", J O l.z J @

,,v Iz 19 IS l'.,l@

' Ac*.f 8)(*.t.HsPf 6cN A%o cO8tHECvlVE aCrlOats 21 1 11 the M. tine Yankee Cycle 6 Main Steam Line Break (MSLB) Analysis as8umes that the g

y [ p..tential omderator reactivity addition following a MSLB from any power level is j

limited to the portion of the moderator defect curve below the reactor coolant g

mg

.e.crage tseperature associated with operation at the programmed cold leg temperature g yl g titi for that power Icvel. The Analysis did not take into (Continued on attached pagg) i

".. c' '

o,

.,,.,o @

OJ W'.i.

n.wovi, o.,c.

r.o., @

.~-

T [t,,J @ l 01 91 % l NA j

Q Transient Analysis Group RevTew l

".. s,o..c.,s... @ ~

ix.,,o..aA.,@

@ Ldj O t..,z)GI x^

l I

NA l

..........,..s i., s......, @

I I o f o I of)L7)@l NA l

m>

.......". @ N A l

9 I o f o f 0181

)

m,

.;,.....n...g 2 (! j@jl NA l

l 8209130023 B20031 PDR ADOCK 05000309

._1_ I bjbl NA S

PDR I - l 1 1 1 1 1 1 1 I I I I l.i

n-u N

1 Pcge 2 LER 82-023-01/T-0 1

EVENT DESCRIPT10Il AND PRosABLs CONSEQUEN GS (Con't) 1

.5

~

The reactor was operated such that sufficient available scram reactivity was c1 ways available to prevent a retura_to power following a worst case MSLB cccident. There was no effect on;the public health or safety.

c

.,y I

. 4

~~I CAUSE DESCRIPTICII AllD CORRECTIVs ACT10005 YCom'tN' 3

...I-c:

cecount the poteettal increase la moderator defect reactivity addition if Tc I

is higher than the Tc programmed value. ubich.it could be when temperature j

~

is used to control reactivity. To assure adequate shutdows margia in the ti

~

current operatias cycle, the affected operating procedure has been modified Ij power level associated with the higher Tc la the normal Tc program.,,The full

~ }f such that CEA insertion will.he restricted to the FDIL corresponding to the range of Tc, allowed by Technical' Specification 3.10.F. will be takes into l:

cecount in subsequent safety analyses. -

f,

~

_p t

_g e-e e

f

_a

~

A

^

.r'

~

y

._' *g

, =.1 - '

3 s

. s

~

~-

d wg, g.

3

. - i; 3-

~

• 7 s

4 O

4=,

k t

f p

a' I

g*

g 5

g g,

p y

q f

M 5

--4 g

l. ' ~~ s, % :.25s it. ;;, i *.:,5. E jd,

'+

g c

l'

\\

M M j Ai?7hC P0GiilCClWAM e stu N.,.u.fu,x 3270 Win awe 1, Staine 0157h

\\ g, s

207-hM2#.321

~e September 2, 1982 MN-82-167 l'nited States Nuclear Regulatory Commission Directorate of Regulatory operations Region. I 9

631 Park Avenue ji King of Prussia, Pennsylvania 19406

-l References a) License No. DPR-36 (Docket No. 50-309) i j'.

Dear Sir:

i

Subject:

Maine Tankee Reportable occurrence 82-024/01T-0

_ 5;.

Please find enclosed Licensee Event Report for Maine Yankee 9

U Reportable occurrence No. 82-024/01T-0. This event does not represent

)

a violation of Technical Specifications but is reportable under the '

j requirements of Technical Specification 5.9.1.6.1.

~

We trust this information will be satisfactory. Should additional

}

inform.ition be required, please feel free to contact us.

].:

3 Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY i

f-b L*th Edwin C. Wood

]

Plant Manager ECV/hb Enclosure 4

P B209130074 820902 PDR ADOCK 03000309 p@

E PDh

rm LICENSEE EVENT REPORT costnoi stoca l.

l l

l lI l

tet Ast ronNT on ryrs ALL cteueres supoemarecess R IM I E l M] Y lP ] l j@l 0 l 0l-lo 10 lo 10 l ol-b 10 l@l4 l 111 l Ill l@l,, i.4i l

l t.s. v.....,.

i.

i.

ocv.54 o t-1, 2

uctwt nP. m

i u s

• '*'",' $1015 I o 10 I o 13 I o 19 Tjlo I e I 119 I e l*> l@ln I e In I 9 I a I e l@

a tu 68 DQcatT 8.veseta M

Su t% t esi DA f t 8.

76 MCPORT DAf t no i 9 e *ei DF R84ePTION AN PRC3 ASLE Co8tsEOutNCES g ; During a rev uw of LPSI Pump H requirements occasioned by concerns 3

g i raised by LER 82-019/01T-0, further calculations indicated that durina i

~

g, the injection phase of a large double ended LOCA with one LPSI pump in-l 'g

...~

y

, operable, after approximately eleven minutes into the transient, the g

g 1 pump might operate in a mode inconsistent' with the descriotinn in e ha

'l z:

2

@ l FSAR.

Section 6.2.11.13' of the FSAR states that the minimum available 1.}

.,./

1,. -

m l NPSH for the LPSI PMs during ' safety iniection mode of operation f ens 'ilse -

cour vatve svstiu catas cause +

COO 4 CODE'

.SueC008 CondPOseE88T C0061 as ar $8 SveCODE y

I s l E.lh d,, h~ lM' ' h I PIU IM lP l X l Xl@

mo>.

seousieviat u occua m.t -

asPo=T' aavisics:

6t a no IVIt ytan

~ setPORf endL' *

• C ', '

- CODE Tvr5

~ ~ - -

se0.

.i

.6 2

2 34

-35 arand raast cour.

consposes=v i

~

o~

. Attaesesserf cP.n tc7ptasir Seeur?lE'

., Y eeQuas suonoffre s roman nus.

sumptean name.veActunen e

ac.eo utuo.e.

m war r

v.

aci Eofol~o I

@f W ~ W@: I a12 I sis l@

L,:Z.J@L2_l@

en o,.

as -

e..

[]$ sg........

<n e z.(,:{$,grggl.

,}. ~

.,.j

~.

caust otscneetoow Awoconnectiva AcTicises g l Review of previous analysis 'of LPSI oump WPSR reoniremant s ennAnc+.A

1J l

w g.;yM;;:s giq:;p M.g g:

g;yg ; f. -,fa,r+ hme I ]

EI in response to the concerns raised by LER 82-019/01'F-0 n-e aA m c..!-c.:n -. & L W :.k Mf G K =5,~

in:. l ? ';

1 As a if g l analysis of LPSI p M performance'under fullEruntout conditionsi y ~. ~ v r :,

.e cy:ngy.

,g.y m?z f

g 1 result of the analysis, no'significa;nt effect on'LPSI D M nerformance ij cm.,,n s..... n 3,.w

~

is expected and no further action' on this issue is.c + ;txt: ~ '

expected.

(con't)

I E,I

...s

...,. _ ~,,

= 4 Sta

%#CWER OfteEM 5fAfts SIseC0VfRY 0

'~

DIMM'v N

^

' ~ l' u@sTras En'iinestin<a anoo, nevrrw I E LEJ@loISi70 NA'

,.?,,,,,, ca, v.,

LOCA79080 0F stELEmet eef Lt A$t 08 ptttASE A480uest OF Activity I

1 I

==

E.L,a]

L. 7J@L._

==

=

• t #%O%%4 L E nPO5umES

%uwet a t vPE OGSC84ePTIOne l

y I oIoIol@ L2J @l w^

i.

o u

=

• 1 R* fl%*st t 04JV#ItS Nuveise DE SCAIPriU'e na I

E. I ol o I ol@l u

=

f D F AcetIT V D AV AC i,(Pe L(Y.5 08 084

(,$ %C94P f fvPt

]'M NA t E.....o 6 WNK ONb g j. u,'"""g 8

pon l

l 1 ll 11 t i ll Ii li

,e

-ai Robert H. Nelson nus h !l

-m---

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (Con't) following a major loss-of-coolant accident always exceed i

that required by the pumps.

Under these conditions, at

• i run out, required NPSH may exceed available NPSN.

Both I

the pump vendor and architect engineer. concur that under y

these conditions the pump will continus to operate with j

flow limited to approximately 5900 gym due to minor n

cavitation and resultant loss of head.

The accident f

analysis requires 5000 gym under these circumstances.

l!

No significant flow chugging is expected.

There was no l'

effect on the health and safety of the public.

2/;

f.

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (Con't)

Work on actions set forth in NRC Confirmatory Action Letter 82-20, NRC response to LER 982-019-01T-0, is continuing.

1

l n

~

~

l l

1 i

li 1

I i

i

' i

+

i i

a AIDMPOWERColl1PAllo e RR No. 2, nax 3270 1

Wiscanet. Maine 0457M 207-882-6321 september 10, 1982 101-82-178 l

United States Nuclear Regulatory Commission Directorate of Regulatory Operations Reston I i

631 Park Avenue King of Prussia, Pennsylvania 19406 i

References a) License No. DPR-36 (Docket No. 50-309)

Dear Sire J.

Subject:

Maine Tankee, Reportable,0ccurrence #82-025/03L-0 Figase find enclosed Licemens Event Report for Maia= Yankee Reportable occurrence No. 82-025/03L-0. This event does not represent

~

a violation of Taehaient Specifications but is reportable mader the requirements of Technical specification 5.9.1.7.b. ~

We truet this information will be satisfactory.- 'Should additiemal information be required, please feel free,to.'costact me._

A.'.

.Very t y years.-

MMME YANEII ATWEEC 20WER COMPARY b

~

Edwin C. Wood Plant Manager EOisvw Enclosure 0

S N

pt

..... m.w 2..~ -

a

.-:,+ce : ;

,;_i e

e Maine Yankee Reportable occurrence #82-025/03L-0 EvntT DESCRIPT10It MD PROBABLE CollSEQUENCES CONT.

2

..r out of service for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> therefore there was no effect as the public health or 7

,..2:

catety.

~ $,,

". 'J

-;6 2

- a CAUSE DESCRIFFIM MD CORESCTIVE ACTIONS CENT.

.. 4,,

found satisfactory.-

79 osamined by plaat quality control personnel and was -

..< :,.3;

.y 4.,

.z.. A

=,%

-Z

. -Q,fi

'd4

..l M.'. ?*. 5 x

.- ~

M.h,.1

. p.1j, f y

- %.. ~(;'4 3

[*.L =, *'.,

ne 5

$4 *

,Y

~ l,;C& *

. g. s}'

~

1..

.; w. >

~

.g. 2 _

' 4,2y!. * '13

'4

~

. ;,.w : 7

..g$c ;/

.. g s, -

... i... '

~

..l

- ? ' L 4_Ry [.*(^3

- w g l,.,.

4 ::

- w.

Qj %'* * '. ' ' {

)

(,'%-

. ~.

A.,

e.

-,- r

• .g

.=

a..

• g

=

• i.

4 j

=

s s

.-i.*e

' o.

8 b

Y L

e*

h i

s 3

.e

. Op g.

y.

-(

e w

>.; g u ~ n...e m,; p g %, g. p;.z Q.,.

. -. g, v.,' y.. ',.,,

.u M'.

sese

,j

" % ~.; &.3 W.Scyty 9:,esenn. 2 M.n 5; DdNCLOSURE

. -. c r, :..,

,;?; -

e u

. ~, ~.,. -..,.

W..'" + w v e e c.

Proposed Ruleswsc.pv.~Yge.-... w:

I WN ~ '. ~,*

> wmm.m.Wr,.; %f'1{r y:-4,'n%nkg.W'. vst.'J. NUsei '7 : :. :,.~.

-' r F P.y u -,.

.: n.s c c 2-IM

~

. 5 2." / -

.'f I!j

^

.>a.

.m1 Thursday,n.y e 1982-Ma

, s.

U

• IMqN '. fs5 WC'M th*"% T*

1. s v :p.m.m.,.:.:n[(% n: j% mM&.

. y&s o

~.

..w u f..O r$:. a.s.

t=:,'. ^

)f d

~-

Yd?.? W'.("'.' * ' p...W,. "

. '..C'3*1 ' ' I'revious difBculties =-

s * ~m, - '...w

,,.Y.,. ',l 4.,;.' 9ih..?,,*:,y.39 &. '"b).?.%.?).'

.k

~

4, management by a committee and

~

supptzasexrAnv mronesAnosc TNs secdon of tie FEDERAI. REGISTER

" 'S 't"W'*#*W"" ! ~ ~t

i

%: funding from severalindependent

- 4:

Background ~L " dear Plant ReliabiHty contans noeces to,the snabac of the..

it poposed leeuence of wee arid'* '

• M..ne present No aganizaHas.Fmeer,wieINPOtioisin

- N ti i program for the reporting of reifahility : focusingupon a utility s ar Data (NPRD)Systemis avohmtary. 3

,,pianons. The purpose of these nosome A

Hon ts to grve Heressed persons en '.u c,

data. On January 30,1980 (45 FR 6793b NPRDS eni-opportanay to peridpate in,the nde ti na of N

?

mewng ptor.tz,the adopcon of,_the shal and plant audit activities,thelev idBWa-Mpaupdeerh-&iP # I

. _.,..,. - of Proposed RM ~= Mag (ANPRM) that ndee..,,7.7. e,r pe. W ;;...-5

. quallty add quannty of NPRDS day ^ ' 7

.j,., :',;, described the NPRD System and invited j

a g shouldsigniacandylacmase.MnaDy,

' 5 E,..

. m.

x m

public comments on an NRCplan ta '.

NUCt. EAR REGULATORY were received in respoose to the,.,,..a..the Comminalon will co make it mandat"Y. Forty fourletters

' ~ ' ' ' - ' '. ; *.....

. ', acHve role b ee dm!OP' ment of an.

COMad.tSS.I_ON s n.-h,., N" :r w effective NPRDS by participating in an AN.PRM.%ese comments generaDycppoM mag NPRDS mandat

. 4

., '..j -

.1.y,;,.,3,...g to CFR.Pa.rt 50. ;; w...

a..

ss Padag. by periodicaHy assessing the quality an

r.mt, m.....c.q o... +

...' NPRDS, andby assuring the timely p.

,y,u g. quantity ofinformation produced by e d be ma Ucensee Event Report Systern.

twy

..'.-. :n.... w -. 0,#.g avaHabHityof theinfamatintothe '

A twcy:NuclearRegulatory...uf, 4. decided thet the reporting of operational

,f

[.' expedence dateneededmajorrevision, iNRQTay 1

Commiasion.. g.g.,.: pts N.

E.

~ Aciioic'ProNed ruf[9%

• 1 i however,makes the %mmission..

r Integrated OperationalExpertar= ' -:

cautious. Problems wSInot be resolved ;

~

sowuAnvin's Nul. lear RegulatoryCommission(NRC)is considering ~. '.1; Reporting (IOER) System.%sIOER " System would have com 4,

i cmendingits regulations to require the. and made mandatory the existing INPO and the NRC are weII aware of the, ~

7 reporting of operational experience at problems and are prepared to worki 0

. nuclear power plants by estabushing the, Ucensee Even' Rhport (LER) system and the NPRD System. SECY B0-507 8 e

Ucensee Event Report (LER) system, discusses the IOER System.. ~ tv c _ together in a cooperatfve effort to assure- '.

p successful re&rection of NPRDS.IfIn -

He proposed rule would codify existing.

~

As a result of the Commission's,,, the future though.if becomes clear that i

LER reporting requirements and '

approval of the rrmem pt of anIOER 4

. the essential NRC needs for reliability establish a single set of requirements System. the NRC published another ANPRM on January 15,1981(46 FR-data are not forthcoming from NPRDS, '

C that would apply to aD operating nuclear the %mmf=mioncouldconsider power plants.no proposed rule would 354t).nis ANPRM explained why the

. resumption of theIOERS rulmaMng,

[

r

. apply only to licensees of commercial NRC needed operational experience

~ nuclear power plants,'and not to '

data, and described the deficiencies In' and make mandatory the reporting of

[

licensees of research reactors, fuel the existing LER and NPPD systems. ~

reHabiHty data. ~

[

processing facilities, or byproduct On June 8,1981. the Institute of. _ -

.h fee, ab dem is a Ukdbod

- I processing or utilization facilities.

that,intha future.NPRDS under INPO

[{

1 that,because o ts as an '

cirection can meet the NRC's need for oaTr: ne comment period expires JolY ' active user ofNPRDS data.INPO would reliability data, there is no longer a need e

6,1982. Comments recalved after this o

assume responsiblity for management.

at eis time Wroceed wie 6e IOERS.

p date wi!! be considered if it is practical - -

Hence,the coIIection of detailed y

and fnndinF of NPRDS.Further INPO

~

to do so, but assurance of consideration decided to develop criteria that would, i f

ificant

.be usedinits management audits of. h. technical descriptions o sig i

cannot be given except as to comments.

filed on or before this date.

,e

.s rul-aMng to mochfy and codify the

. me be utilitie m the adequacy ~

m m m. v,,.

existing LER reporting requirements and m

Allintensted persons who g

desire to submit written commenta or. M & WMpldd~hy.

to assure rnnaistency with 10 CFR Sa72, 1

Aponesstr.s:

. ~

o' ous! ""de NPRDS ""M. ' ". covenng the immediate notification of --

suggestions in cnnnectionwith thisproposed rule should send them to th ' -. had y

g g

gg

. =i-a*=nt events.

~:.c : - m d

were the inahility of a committee..

Consequently, the' Commission has Secretary of the Commlas!on.U.S 4

managnnent structure to provide the directed the NRC staff to:

s *.-

p

'(1) Defer rulemaking that would -

A asMngto D.

tte t!on ner-= mary tM=1 duection and alow-le. vel of participatim by the utihties.

Docketing and Service Branch, Copies of establish the Integrated Operational' J

7 %e-mi' manta and actions by-

. Experience Reporting System (IOERS):

d y be 2.

c11d e

ent Room'at INPO provide a basis for confidence.". '. (2) Develop a proposed rule tha L

- cxamine that these two d*N(-nries wH1 be Q.

1717 H Street.NW Waagon D.C.;.

bdFa -vampfe.centrahtmg the would modify and codify the existing

.Commis n's Ucensee Event Report (LER) reporting a

r manasement and fnnding of NPRDS,

' requirements and would assure Frederick J. Hebdon Of!!ce for Analyals. ' withinINPO abould overcome the.

b ron runTHen wronsaations coef7ACT.

consistency with10 CFR 5072 which A==--*

m m laWein covers the immediate reporting of -

Cs

,y'

~

f*-

- and Evaluation of Operahnal Date.

-'C'P'" **" N T $ *g*w % 4 (3) Prepare this preposed LER rule:

, l significant events:

Ni U.S. Nuclear Regulatory Commission, h

Washington. D.C. 20555: telephone (301) 492-4489 D.C man i_

-Q*; Q;

.. a t:. 'p%

~

t e

, ' Federal Register / Vcl. 47, No. 88 / Thursday, May a,'isa2./ Proposed Rules

(...

19544 stenthaau %e letters did'not specify ' ~ e,eappucab0fty of the event.no NRC's

.a.

a. e s.

~

(4) Endorse the Institute of Nuclear, -

witat constituted an event of major -e

-concern with simply extending the time Power Operations (INPO) plan to.

L S assumeresponsibilityforthe -

. *safetysignificance.One of theletters ' ' for submission of a written report la the l.

also encouraged the NRC to eliminate W ' pot.netal for, or the appearance of, e,

h r management, funding, and !=rhnt<=1.

the duplication between the List systess' ' transfer of responsibility for evaluation M-direction of the Nuclear Plant Reliability and the NPRD system, and between the ~ 7 f the event to the ResidentInspector, o

d':

Data System (NPRDS):._

LER system and other NRC si,vu4Nb bade for this transfer would be the ~

(5) Coordinate closely with INPO to,

Mc W

- =aint=t m duplication between the LER requhements (e.g.,10 CFR 50J2). T i C written inspection report of,the event by

/

Allof the commants received were 7,. E the ~ ' ~

whichin many cases.m 4 and the NPRDS systems and between -

writtenwellin advance of any 7o -

subsequent NRC and INPO analysis of e reviewed by the staff and wereW C wouldconsidered

'-% pubuc' record of the event by the O s dl'.

[$7 NPRDS data:

. u " J.. q -...

P'roposed LER rule.*;p,9.;lt TD L,oensee.%e NRC considers promgM (6) Encourage INPO to assure that the 7dF.' evaluatiosi of an event and~ reporting of.

I.E NPRDS receives, processes, and oy,,,g,fr y Lfg'g,i.,fb?h'f

-y

'~mes.r the results of the evaluation hnportantin disseminates the reliability data needed

. If the proposed LER mle beco. -

order to provide ~ assurance for continued W",-

byindustry and theNRC to support effective, the LER wiH be a detaHed

. ~

4 e

safe operation of the plant after an' g

ina. f event.De decision for selecting th f".I '

probabilistic risk and reliability. ', '

narrative description of safety..

reporung Hme and

-'k="1== wH1b MN sesessment programs; and ;

significant events.By describ 9 "",

(7) Closely monitor the procoss of',

detailthe event and the pl

--.s

-based on an evaluadon d the W,~O.C, t '. '

' INPO's ent of the NPRDS and'.

basis for the careful a corrective action.it will rovide the -N.. alternatives.hNRC sp=<#<=Mw

.d afterINPO over the system, q of more. 9..... requests pubile coenment on the above

.'o b.

provide the Commissiop withW-rsemiannnat status reports on thel!C

. serious events that mighto serious accidents.lf the NRC staff Je -

.It should be noted that i 50J2,e. -

%alternauves.

W Mh F

effectiveness ofINPO.managemen of. -

e LM NPRDStoNRCneeds..+ w. s[-

I"gtha the

.. Notification of Significant Events,Uf NPRDS and the responsiveness.of g deci

]t.S.

establishes the requirements for the -.- -

08staffrna t &e11 e s immediate reporting (l.a., by telephone)

See SECY 81-494 a for additional,-

,g ado

[i -

of significant events.Many of the _...

' event and descri,be the results of that -

criteria contained in 5 5053 are al=Ilar

details. -

!., G On October 6,1981, tid NRC...

. h Ec u s e l I N,...

.an LER y '

because of the different purposes served

• gg,,,,,.

.s.,,

- to the cr!teria in 5 50J2.However.l. -

f,gj published an ANPRM (46 FR 49134) that, p

deferred the IOER system and sought ;

those events or conditions that meet one b the two systems, and since 3 sa321s

j. 7,

. public ccmment on the, scope and -

or more of the criteria containedia :...

ady in use, the Commissionhaskept

p.7<

content of the IIR system. Six comment i 50JMaj.h criteda are based M, aI 5032 and I 50J3 as separate >

~

,y letters were received in response to this pdmaruy on &e natum course, and requirements. %e Commlesion plan,.,.s. to

, d.

ANPRM. m

..c N.

-consequences of the event.Derefore. '

continue to workio ensure ccasistency N

y, One le~tter strongly opposed the NRC's - events that meet the criteria should be -

between tha two rules and to previder b',

plantodefertheIOERSrulema% -

reported regardless of the plant. o~ '4.. clearidentification of differenr==,&

However, this opposition appears to be. operating mode orpowerlevel, and e.:

between telep~ hone and written.... 3..

q.g.;;

due. In part, to a misconception that the-regardless of the significance of the ' _. ~

~

reportmg requirements.%ese efforts "

g J.;.

. NRChad proposed to turn over the.- -

,am-nts, systems or structures. C-

'gnvolved. In trying to develop criteria for. may result in combining the existin q_7 4 INPO responsibility for the management NPRD system and the LER, system.*Ihe,. the idenuficanon of avents rep g;

and technical direction of both the -

single final rule. A combined rule could t

1!y..

- LERs,the Commission has concentrated ~. have three elements:(1) One d-===*

W 1 -%_.,

writer also appears to have erroneously - on as conse@nces d me eyed as &e - : devoted 'to prompt notifications whi assumed that the NRC would notlonger measure of signiBeanm %erefore,&eC Tdo not require a written report: (al sw-;

re i

.M analyze or evaluate data from either the reportingcriteriaingeneraldonot&-M.*T second element % :.Lgprompt,::Tw LER system or the NPRD System. 'a a specifically address classes of initiating notifications which also require m e.*-o

@A@14 Twoletters forwarded copies of '

events or causes of the event.For ":=.'

k!,

papers or reports that dlscussed the -.

. example, there is no requirement that aB2. written report: and (3) a' third d===ne-l1 R.;

collection, analysis, and evaluation of :

operator errors be reported.However, c. encompassing events which do notm require a prompt notificationbut for'.:.'

e many reportable events will have been - ' which a wntten report is required. An.

- fe. j LER data.One report, prepared in m: ~

. November 1979 by EG&G in Idaho Falls,

,h!:li.

had already been reviewed by the stafL initiated by operator errorst :..,.e, e[I Alternat'fve'would be to process another He proposed rule as presently &.

,'ritten requires that the holder of an 5,.

revision to I 5032 and the final I 5033 :

ne other report was preparedin

,r-

} 6,N 8 December 1979 and described potential operating license for a nuclear powerh in a combinedpackage'which czone,c p f industry uses of the LERs, including verF l t h ll b it LER within 30 as references the requirements in the two.

TQ

. generalrecommendations forimproving

.p an s a su m andays after:the discovery of a'reportableg.j rules.~%ese c y.i --

the LERs.. 3.J.-,rf,.--Je f.;, -.y

. event.%e NRC has not yet determined.3ad=Infatrative, and the revised I snJ2.

%e remaining three letters, whida.,. the appropriate Eme.ne attematives e-I: would notbe significantly marMhd nor

.. [t

• t-

~

~ decision to defer the IOERS rulemalring,' ~ days.If the timsIfor submitting a writtaa

...y

~

1.~wouldit bepublished again inrpublic. -

were from utilities, endorsed the NRC. under consideration are either yk e

T report was ext-nded to 30 days then a'.~.T~ JiiihdorsIn'g~th p'M

.+ N >

Eachletter encouraged the NRC to.

e' reduce the overalllevel of LER reporting summary report transmitted byM FI' ' Commisalon has noted that the ACRS7

',, f, 3[.

r telegraph or facsimile within a few; days " saldi.y v. -

S

,;,ge ;,sj,&$ DE""e"m.a*""2'JsO2E4:gg(G

. by limiting the LER scope to only.those occurrences that are of major safetF.,. k. of the event may be.reciuired.Such agi Q ~,f9, l %*;.

,(

';ri:Od e'****f*.;Wrt, continued operation orretuni SOM g; publication for--

thougk1 a 1, L D=:=nsat Roma et inr H Street. NW. Washste.

t

.T e.;.., operation, a.y.omments'en1he genedo&sabesg

w. 1

< 3r M. -.

_ t!!, A-sin my.1--

nd c :,~. w <:ww w..~ -

w

.. L p. nc ruas..>

s 3-

.b ' <R. ' M.

.P,Q ;. ~

..=;.9,g.f.,,24...

w M n

(,.gy,.E6 J ' 4r.*;, 2;Me[m.,

0. u s..7. & W rC h

.?

e. - - *

...e

u. y 4.

~ K. & y e=; Q 7.1,.*. b ]?*.**; 1*fty q.'s--9,.QQ,.Ch'y?.*r.4.

... :x,..

j,N.

?

,-.C

-C, nf,.Q:;uWQ+-g%

d

.R...

J

t.-f. ;W-

. y = :. y.. _. r c.~..c

.g.g3;,..-

D.'Qf g }p } g g. m % D,.O.2.;;lb.>%;:: j.Q fjl'~ g. y.. g nl [ M (( RQ.QQ-

p{,..-... ;,.,, ~,,,:ideral Register f..w..#,7,N,,,.y/ - y b ),3}'*/.1 9. f,. .@,,-(, f M b j e,:<. (,'. W.:x w..,3 a.,3 ;,.... Proposed Ru!ssi *

• i,4,,i9545 ">'..

. 3.., s. g w -e.... 4.".;j/;...... . ' T.. Y'",* y, May 8,3,o 3.,/.. ,o. e.. w,g Vol 4

o. 88 'Murs 982 j sJ " < 63%Ma

~. the consequences of an ceddent. While' 4 p. -r. ..,,,..v.~ a... R revealwaysin which the Propeesd Ru!* i... ?.. ; *- ,.M'-Paragraph-by Parsgraph Explanation of - ,M v...., the LER Rule ' w..nd.hy.d.i: i ' f 50.73(a}{1) epplies to actual demanda-5g f ESF. I 50.73(a)(2).,, ('i { .! ' abould be resteed, and even perhapa ;> c.y..-4rg-gg*gg gg q.t.for actuation o an6 ?, covers an event where a M replad.we do not believe,its publication J^ k d(s., should be delayed until a more advanced,,. 4 ;7 _ systemis devsloped.1Htimata goals for such Y pr' possd rule are explained ' intended functi6n because of one or souldhave failed to perform its ' ff 4 o o sydam bdude tm'er reporting, analy'sia, - ~* ' : a x; bl2M. '. more personnel errors; equipm~ent ' * .,end evaluation of humsn eners and computar,,g 75.,gg7.;#,~;p rre,7 -. Any event resu ,.y si,.e.e u4 A i; t software errors and harhepe the devebpment .~of a system for more a!!ectfvefy identifytag.- -- automatic actuation or the need for actuation. ' analys s procedural deficle'ndes.He event ' (ESFI,.u PC"'** ang systema interactions .3,.. of any Engineered Safety Feature . should be reported regardless of the E a.%e Commission supports'the *&*,G (RPSL Actuation of an ESP., tion, ? Including the Reactor Protec wwng the.. .; situation, or condition that caused the I.> f, s b[" # proposed rule and and anticipates.h[. RPS, that results f ? ' structure or system to be unavailable. 2 substantialimprovements fromit.%e ' gdh"'i"8 'd 'EI.need

e. His paragraph does notinclude those,

.i, g W :'" ~"M*;:W. cases where a system or component la m, Commission recognizes that the LER ..- be rep ~orted."~ /2" N s .. s *1' d 7 W "' } ' system needs revision to make reporting. His paragraph is intended to capture

• remobed fro

~ ~ ~ c:. tes or E more consistent among licensees, to stop [,d e . bapproved procedure, and inordance'with th 'i {. th2 reporting of unimportant events, and'. premise that the ESFs are provided to.a. ed u.c r.. c,...

• a

. " to provide better data on significant M

sh[ SpecBeadmJorexampl_e Me M

• cysnts.no Commlnsion ' agrees with the ACRS comments that this Propos'ed Rule fecg,tntand,t o

1) 11 mee tem ves part of a system from; ~* ser ce to perfonn mWenance, d the s ,. 3 is a natural evolution in the state-of-the

• work properly whencalledupon,and(2) TechnicalSMcations pen g

~- ~~ b h II d' crt in operationc! experience datagathering." N d W: (." /%. the should not e c a engeunne . p[ 8 -7 both in events where an ESF was '-needed to mitigate the consequen Comments are solicited at this tinie. ' Umit 8pecMeOn the Teclznical. Lt 3,, I-for Commission consideration prior to" - an event (whether or not the equipment Specifications, the action need not be pt 31 Issuance of the final rule, on the " l ~ - feasibility and desirability of improving performed properly), and events where.: reported under this criterion.If, y-t the overall desfgn of the dats reporting ~ an ESF operated unnecessarily... ' - however, the licensee takes a -7,,. qj - system, the characteristics of such an ' . Operation of an ESF as part of a. component out of service or returns a l li U resources required tti develop'it,~and the ' plinned test or operationa evo ut on component to service'in a manner.. 4 . Improved system, the time and --P ' need not be reported. However, if during resulting in a configuration at the system p. ., the test or evolution.the ESF actuates in itted by the plant's s j ~ utility of doing so. Ainore serviceabledata system would have at least two ' " a way that is n level that is not perm d Technical Specifications, the event

, p Procedure, that actuation should be. _

should be reported. In addition, if, while dimensions, one which can be used to - reported.For exampfe,if the normal.7 f i the - { , reactor shutdown procedure requires 7. the componentis out o serv ce,.llcense v support case studies of sp'ecific events end a second which will support that the controlrods be inserted by a have prevented the system from - g ~ ~ ~ j multivariate, multi-case analyses. - manual reactor trip, the reactor trip need ' performing its Intended function (e.g., '

M I

a Specifically,the Commissgonis. - not be reported. Iloweveriff conditions the licensee finds a set of relays that is rf - J ^ 2 ~ . develop during the shutdown that require an automatic reactor trip, the.3 wiredincorrectly),that conditio interested in receiving comments on a be reported..; ' fh'h C .y, L more diversilled system that would - make the LER even a more useful tool' - reactor trip should be reported.The fact ~ thatthe safety analysis assumes that an r %e lic'ense'e may use eitgineering~ " ~ ' E s for the analysis of operational 'ESF will actuate automatically during an. Judgment to decide if a failure or~ I, .y cxperience. Of particular interest would be potential improvement to aid in the. - event does not el!minate the need to-,.7 operator action that dia:. bled one train" s' enalysis of trends and patterns that may report that actuation. Actuationsthat, of a safety system and mighthave,but ' I need not be reported are those initiated' ~ did not, affect the redundant division. : h Identify precursors of major incidents. ' constitutes ait event thatfcould ' - for reasons ofher than to mitigate thejrconsequence,s of an ev {7 For example, the Commission believes-h y. that a more diversified operational data - ~ - function.If ai:omponent fails by an e discretion of the plant operatorsfas part 0 apparently random mechantam it ma'y.. ~ % I'., gathering system might involve reportin8 & '. ~ rather than relying on a narrative,ent.1. of a planned proceduie) ~J s t, r data recorded directly from the ev c... ;. Section 503(s)(2) requires reporting. not be reportable even if the. . - El description of the event.Withincreased, oft j.j:.g,g { Q.g.;,,.. ;f.;. functionally redundant c ~ 'l f emphasis on techniques of reporting and.,,wintanciof pmannderror,' -i i. fall by the same mechanism.To be..' re V % 1 equipment fairm. W-, vietation or - discovery of des!gn. enalysis, fabrication,X condition where there is a reasonable -Vil 4 storage of event data, the technical.? s'- record associated with the event would doubt that the ftmetionally redundant ..I. constructica or proceduralInadequancies '.'. that alone could t the fnintiment of tha. division would remain operationaluntil ' '. ' ! y be enhariced with a corresponding it completes its safety function. For '. W. - A*p potential for increasing the effectiveness j,'Y ' example;if a pump fails because of r . of the use of statistical techn! ues to,g.-. W ; t. (!) Shut down the're' actor and maintaln it in - eed i M system would permit the use of more,6 ; J s san shutdown cond identify trends and patterns ?- D, ; _ operational experience. Such'a' data.' ' -(11) Remove residualheath v.~.i.5 : W - Judgment indicates th e N A c (till Control tLe release _ of radioactive ' ',1 - functionally redundant pump would - {

y. ' sophisticated statisticalprocedurea to Identify signals that may be present only. material.{.4,.7

,g.,,,%Is paragraph is also based on the have also failed before it completed its - safety function, then the failure is 8 M~ in the aggregate and are essential to the assumption that safety-related systems g.understandingof accidentprecursor and structures are intended to mitigate - reportable. f m r , conditions. _e C k, e ~ [i lr ~

WC'

'D. --~ u_.f

j Federal Regb /Yol.'47. No. 88 / h-iday. May 8,1962 / Prt.p,i.ed Rules - a 5 2 [ j9548 'T--! n'=1 Specifications should be . W Secuan 50.73(a)(3) requires reporting Finally,thelicenseemayuse - reported.Jn addition,if a conditionthat ' ,9 /.O of:~.~.. - u. a :,.,, engineering judgment to decide when as would have aquimd a plant shutdown. [ OPerato(a acdon constitutas a,. / .Agy,,,;it caused by a falfpre,fedt, nonconservativeinterd=pendantw Any. exists for a period of time longer than condition.or action that demonstrates a,~ . time an operator operates a component l- .thatpermittedby theTeA= leal 4' W'. - p

• • /. with esesotialstrucanres.-raaaetsse ~

he could annrelvably operate au the ; ' C _ -htionsltt shcold be reported N.* @\\ nonconservativeInterde. '---associated functionaly redundant comp'onents [1.a.,.evenif the conditionwas not disc he cordd casats an undesirable.4',,,C.l. . ' and the con - istilafter the aBowsNe timebed '< . T. systems. Eswatial structures. -. +... and systems are those needed to-e;..,. Interdependence).However.Jocan cevent to be mportable the operato 1 ' 3'-9 *,T,,'[,'aj,*,'d una. d 71aaDy.~1he He====e annat report.ii T . c.1)Remos,midealbeet:M M.L '. - - actuaBy operate or attsunpt to operste >. components in more than one division d events arhere an Aedom Statsunan h M (1111Contmlthe release af =Anaarelse. y, ~,mnimin. din a Uminag ConditionM ' n es .testal. n.. -;,,.,e.g.- n.y a safdy eydem, and 6e neeltd&ef.,; Oper 6aelsnotaset.ParanAoticaEr - H ? -e E *f. 'theintentof this peregraph isto;. actionmostbe undesirable from the " - Sam er===t that gives thelicensee L4 '-' ' ~ ah=r==tives {es., repair a apaciSc,.. ^ identify those events where a single - Per*P.ective of protecting the health and. e

Qg.

, b i faDure or smup of fsDares affedt m,. safeyof 6epuhucasown. ~ ". ' redundantorindependentportions of. anbe fumtionaDy Ma=<I= ayes,two component oeachieve hot ahuistawmWJ' ' < 4 ( within u bours), the AcBoo Statament as - W ar .a. safety-related systems.%ese events Pumps in ddferent trains) or not :W ? i ametJf eitheralkrnative is meet (e.3, they - ? ' '-+ canidentifypreviouslyunrecognizedf d d t( the mmmoncausefauures andsystems,\\ I'""*'.a=#yre un an eg, aussponent ja apaired or the plant is in ~ ~ $3 interactions.To be reportable,the evang _. Operator correctly stops a pump in' DataA" and.i M. i O b dischargnalwtaTrain%"heog to coupy withaSury.mann, n y x F 4 '.' ' umsthave had thepo+=ntimitoneultin f. hh the inability of more than one train ce. mistakenly shuts the ymnp discharge ' Requirement need not be reported as an. 15t,butabouldbe tabulatedinM c. valveinTrain~B7. w q ' . e M channelof theaffectedsystemto; e. Sectica sa7 Map) aquires mportig *. Monthly Operating Rego 1.; t;M - ~ performitsintendedfunctionc,, ..,;*M.' ~ J,. Section 50.73(aX5) requires repo$ ' - Anonconservativeinterdepaadaa4s. 0.*". forwhichplantTechnical. Q 8 "V 3 -3 'en. ' ' e. t.. 7:. '- '* ! W * "' C ' S 'N ons that pmduus a negative (La.,- "Aqreventthatresultsinthe==cf.,?, fe.,

• Any event

/ - nnnmnaervative) synergism which Spedfications tequire shutdown ct tbe, M pE causes a reductionin the abGitynfa. g nuclear power pient se for whida a ptamt 41 pourplantnotbeingina ___ _ ~.,.,.. d system to perform its intended safety - Techn1ont Specifica.u.Act. ion Statsenest In conditloo er that assults in an ama nalysed y 7 ~ tion & C.. -... el.TI D ~ condidonthMstenhady function orcauses a systesa to perform

• • t g

.x %1s paragraphis simHarto;,'. '." 'I A. '. !NT 3 an action which ne8ativelyaffects the.. l 50.73{a)(1).However,inthis paragraph - p1 mat safety."W * -i '9 ',~ _. pub!!c health and safety, s. h. 'In addition, the Commissionis.It the s'hutdownis a mermal shutdown v f., %e intent of this'paragraphis C - capturethose,ventswhere thepla#*i: - lacre'asingly concemed about the effect i e h requiredbytheTechnica! An: automaticwasinan 611=dorunanalyzedr .e of aloss ordegradationof whathad.: J Specifications ratherthan' smodition. Far n==ple, small voids lui 9.t i beenpreviously assumed tobe non-T 1essentialInputs to safety systems.3 7. reactortrip %yk thosti eventswhere thelicensee is - -- ~ the reactorcore whidshave.been.hy %erefore, this paragraph also lndindesi ) those cases where a service'arlaputL-', vequhed to shut down theplantbecaus a--- "=3 ahown through analysis net.. J which is necessary for Gie reliable er..' It'cannatmeet th'e' requirements of the 1 UA.tobesafaW-':al#a-a'needmothep - j purpose of thisparagrapP.4,*shutdowd".'\\.-re 'long term operation of a safety systemhp ^ TechnicalSpeciBeations.For the %: 't lost or degraded.Ihss or degradation of .j ]y j., Technica1 Spec!!ications regoire that2he. _ad ~ ~ these services or inputs are not W.,, reportableif they do nctdegrade the ? ' h shutdownias deHnedintheStandardk*}j.i rculation ~.aman .-Ir O.. operation of the safety system.The" d faunre need'not be reported if it aWets ) 1f Se":.; g . **portablelIn Addition, velding hi S 4 Y'- ?. TedhnicalSpec1Beations.' condition 1s correctedbeforeth p.. onlyinputs to systems that are not.- g needed for safety.: '.M; ! 4: , hed-[j_. limitforreachinghotshutdown,Se %srronesissindicationca t This paragraph alsoincludes '.P-" ,h,,a e-eventneednotbe reported.ggg 'Itsboddbe r=*A.however.5:st eperatortomisunderstand trueg > 'discoveryofnonconservative5'> ' "; L [., conditionof the.351antisalso5:R.R interdependence in which theinitisting 2 the paragraph 1xmirs."(a)gy event fat g. anoontroBe8 condition and'shoddbby". - event is causaDy liniced to 6e faDure of 3 aragraphyf@,.Q %ejrb,rntY[a."' e' = whichplantTsanWt- -- g3.I l' one division (e.g,trein)of a safety MnN'-.. requhe shutdownL* *"( ls$t pi,, $ft1he 1"[,e system regnhed to adtigate that ds for = 6 added).'Iberefore,1Ep. err.p lh* k f' M'a=aa=(msfuse engineerlagMN ~ , initiatingevent. Itis justas sedacommon cause failure to precipitate a-Q~incIndes e.ents ' and experience to deta=ning wbtherind - mnoontroBedesGn n=1yzed....dd.h ni' ? d g_- demand fora safety system and fallone. ~ the s h hli(y$. of its divisions as it is to fa11the pia E ' bedahse oficonarrian that 5 L q redunannt divisions butnot trigger the'D[,Taantrif Mpaanc.eth aina g.cf" 4 i(perugraph spply toinlanrvariatio Q.: ~ individualparameters, or 16 problenis O 46 [a) didnot re'mgniza untillater @1.'_ 4 'initiatingevent.If anunacoeptableh, event is madaled as (t) an initiatings-s that the situation rialatal theT=4=le= 5 singlepieces of equipmeniV. =i g-event, (2) a fallme af ch=11=t= d safsty

• Specificatione and, therufere,did ast
• Af arg thne* tee se niore~ safety-uslutse h

[ y; i division A.and(3)afalhaw,of M-%W shut down:orMWJ7EWW

==q==="tsisEkslyto% a 2 ofservloe.. ,.m, two ofTa'ar.fetydivisionB,thenany.y- -(b)didnotreczyntseuntRlater. lenit/f5ytdvlat sin @ttni;. 0, (-;. chall' ~ .aee wsn maus a..a.x._. 4 i, e orm.moent even=es caat se c6 aidon es,i.d an, e {.' sa a didnotshut down.M e-4orpotentiall occarnasdases. % us. g. c a= atthe ad,,.- Toregnaie,,,,,j,9,g,,,g,p',:grd.,e.s. da a t, y 'and are v.s. - sar m..n.eest,oo,3dp,,h ; Ln.acommoninreportahie.ym-vrms aun.siis,.p-pyas ~.,yy$g.hh.kIdi$g g,.y h ' '.

2.,

y wc.m:h..'n ym. m,y. m; 9 %a.g.p,.,. r r c.u-mns ~ w w w

s. ; _.... v.w.

gg s.-.... r.

[ i^[^hhj*Eh.d b 9."$-).['.Q W. 7::~r. ~.~m,r r~-7.r w n -.,, m E y ;k I.

• N '.5YY

( b 'e -t-G~M'dh 7eder'ai-R2giste// VolM No 88 / Th' 5diyI Nay' h19827.PropM5diale's'DW5 V u ~.. ~ J situation in which two or more often 'P'afrooms an'd bnMfngs'that subsequent " componen 7 .. : - r.. .u. e m ;.. ... e< : ... n.: . w...... < unrelated. safety-related compone6ts ' ** ; evaluation determines were f! need not be reported. f:@-41.i.n. ' ' operator errors or violations o & :,. % 'are formally out-of-service. Technically. , this is an unanalyzed condition.J TM:' 5 Section 50J3(a)(8) requires reportingld be ~JQ. ' ch corrective action taken on'pf=nned as a ".. -g .j67 nbo.14,'e'efnnenIreleadE' ' result of the event.nis paragraph is.. -Intend h t h . ; How2ver, t ese even s s ou . reported only if they involve p.u?'M. I, . functionally related components orif :. fi glno quantity ofradioactive materials in.. brief description of the event so they a / - J i J liquid or gaseous efDuents released from the 'can find events ofinterest. *d.i. P hs. 5 tiey reflect significantly comprcanised atte exceeds the hmits speci5ed in the p pie.nt s:fety.,. O rw c.v : m6 U t. TechalcalSpecifications. ".myv'.l..MT Section 5dS3(b)(2) requires that tho' 'I r o . Ptrally, this paragraph also includes -

• (U) The quantity of radios.-talve m&ials. licensee include in tiie LER a clear,M.., #b s

mfc{, ! specific narrativa statement of exactly 3 ' material (e.g., metallurgical, chemical) p* 4,- contained in a liquid or storage tank problune that cause abnormal 1--ik umits,,s, ,ydg

so that renden not f=mmar with the d*/,7 ' {

degradation of fuel cladding, Reactor q.;i.tu!MOespAEMEM~cto Bje,c S',..t.

• only the quantity of radioact we materials hr. -deta!!s of a particular plant can

. Cool:nt System pressure boundary, or ;,,. --M f, Sectf on 50J3(s)(6) requires reporting" sase,ous waste transferred froin the primary C 1. un . thm cont'ainment. N: W.n]t ai,,' coolant system'to the seasons redweste hf should emphasize h vi6 a management system exceeds the limits 9 resonded, and how systems,' ' ~"9d.P. ,n!)..e4.,A L'q,,.t;.Aph: d i l- ~ -W ...l'Any act of nIur's, denfor'a'ct bypersonneL that expwy threatens the safety ! spaiB . of the cuclear power gJeat or alte personnel I" %!s paragraph is intended to capturem h b je ~ ,, in thiperformance of datfee necessary for the an event that causes the controlled 7 'P -. s ould not e covere d release of a significant amou(of'

• i ' f.detaE Characteristics of a plant that are i

, saf2 operstion of the plant or the security of 'of ' radioactive material to offsite areas.7.' ' unique'and that infl,u 4 ?cYsa I nm ant"is based on the plant's 1 described.ne licensee should also ",[; = c or a pt d abo u F c - ' viol:nce that are not substantiated by the - . Techn! cal Specification limits for the' 43 describe the event froni th6 perspective 2 L - !!am. se.e. need n,ot be. reported.".' '.; ~.~..k.- L release of radioactive material, of theoperator(e.g.,whattheoperator ~ ' '

Section 50.73(a)(8)(111) refers cinly to'heTechnicalSpecificatio

. %is paragra h is intended to capture. , hoss events w ere there is a clear j. t antity of '... ". misunderstood)..~ ;~ ' *.':N.MW,. t ' amdition, or natural phenomenon, and,.l applies directly to the'. radioactive materialin the gase + '1 Section 50.73(b)(3) re'qifres'tfidthe'7 %- threat to the plant from an act,..,5 - b j where the threat or damage challenges .radwaste managementsystem. Itis: f d* . the ebility o( the plant to continue t . Intended to ca ture those events where" ','and potential sa ety consequences an '... N " - '.; f, b q dt radioactive material from-implications of the event.nis~ , operste in a safe manner (including the the reactor coolant system approaches ' '.' assessme '~ orderly shutdown and maintenance of ' ~ ~ ' require'an assesment of whether the k k ,shutdow u.onglitions).ne {Icensee

should decide if a phenomenon actually radwaste management system.nesa

. incident would have been more sevde ' ~, : l t I . thre:tened the plant. For example, a events are frequently indicative of.- under re'asonable and credible mintr brush fire in a rentote area of the significant fuel cladding failures. ) ., p..' alternative conditions, such as power 3,y,j g F s , sits that was quickly controUed by fire

. Section 50.73(a)[9] requires reporting I

fighting personnel and, as a result, did. og y ; g,. ' .,,,a ,, an event occurred while the plant was at not present a threat to the plant should ,,Any event for which the.-quantity! :.15% power and &e same event cow 3 not be reported. However, a major forest radioactive materials released during an have occurred while the plant was at,, ^} 7 fire Ittge-scale Good, or mafor unplanned offsite release is more than t curie- ' eaEhquake that resents a clear' threat f radioactive matuialin liquid emnents,. 'y power, and, as a nsuh,6e :,,' - ? r - consequenceswouldhavebeen I to the plant shou d be teported. more than 150 curies of noble gas in gaseous., Tconsiderably more serious, the licensee-I . His paragraph is also intended to . effluents.or more than0.05 curies of. ' capture acts by site persdnnel and acts, radiolod!ne in gaseous ef!Iuents.",'.J $:,j J. should assess those conse9uences. a n licensee desenbe in the LER any,.. - . j( 'S i h tthe, by personnel offsite that threatened or .~%!s pa'ragraphis intend' ed to capture. ' - Section 50.73(b)(4) requ res t a have actually damaged the' plant.The - those events that cause an unplanned or. corrective actions planned as a result of - licensee mut dhcide if the act actuaDyA, uncontrolled release of a significant . the event eahown atee time 6e. , M*W. Q - 7 ',Ws subanitted,inchding achons to ~.. threatened the plant. For exampTe am unt dradioacuve material to oEshe -s y i I threats of violence that are not - anas. reduce the piobability of similar events ' substantiated by the licensee need'not a ' Section 50.73(b) describes the format be reported (e g., bomb threats need not , occurring in the futurp.His is not to say fl ' be reporld if the licensee does not find ', and content of the ER.It requires that ;<,, that for every ev

g

. 6e Bcensee pnpare 6e En ' evidence that an attempt was made to sufficient depth so that knowledgeable _mustbe 100% assurance that the event g A will never occur again.Many events are n Section 50.73(a)(7] requires.g,Q.., a ' readers conversant with the design of. comm 'sctually plant a bomb). F- ' rep li ? ', throughout the life of the plant. ;,'... -....; D ~ v. m 3,.

• y. not familiar with the, details of a

,g, _ m g g s, w s. h t I'. ' However,if an eveat occurs that particular plant, can understnd the'scomptete event (Ld., the c e - fr I

1. Any radioactive release that requires the-s svacuatfon of a room or building.U 'W <

' ' corrective actions should be described.- 'd In. plant releases should beieported if' event.'the plant status before the event / After the initial LER is submitted, only L ' and the sequence of occurrences during "substantialcorrective achim needbe ' ~ ' th2y require evacuation of rooms or ~, buildings con *ing systams important. the event)..., Q:.ief.,2: x m.- . Section 50.74 (b)(3) requires that the.. - reported as a supplementalLER., ) to safety or rooms or buildings which Section 50.73(c) authorizes the NRC licenses provide a brief abstract describing the majar occurrences during. staff to require the licensee to submit ~' may require access for any test. 7 mzintenance, or conduct of emergency. the event, including aD actual : - specific supplementalinformation and g procedures. Precautionary evacuations - r t s t l' w. -Y

1-1 Federal RMr / Vd. 47.No'. as / En, day, May e,1982 / Proposed Rules .i ( .,19548 _ - proposedregulationsa!!actelectricp - Canadssionis M--N =ER for the timing dtheenreports,%ese e I Z Y assessments beyond that required by~. aHin== that are dornin==* in their : 2 alternatives are discussedlathe ce 5033(b).Sadainformation anny be respedive service areas and thstown <. Statament of Considerstenandert tr 1; ' rlequired if the staff ands abat J. b and operata undear n'if==tian fedlities OVERVIEW OFMRSYSTDQ after.: supplemental material is necessary for, licensed under sections los and 104b d ?(the discovery d the event.no Eceass t completeunderstandingden ally theAnanicEnergyActofia54.asA, :. - 5 ofthef. w'" he arnaaA===*= clad (y and Y ahaBsepart sapuest., land NW,. complex or sign *=nt event.Wheaa - I.' moddy pr==ardly existing acHha*1ay '. plantmade ' tinfar==Senis' l I L i requestforsad b-shoddurf madeinwdting, the dthat/t,-

?.'

submit the requested information and.- . new, i=f bant econounctmpedes R:. structure, system,ar r===g-= h ' initia'112R within the time peded ei-t ~ thesekana=es.nor are theBr==== 4.1 'I1 "' ' asses==ent as a supplement to ther,4 i P report: M d # ' e M, W 6.4 ' t within the definition of =maM besinessee. } -l ^' -In*=====1erS P specified by the staff. Usamily a written. set forthin section 3'of heSmsE ".W.i (1) Any event needforW.. e J report will act he required in less thaa 15 days from the date of receipt by the'.,,Iu,ina== Act.1s rr M P 832.or withla*/% a=*a==*te actuation i " dSafety:n. , theSmallBusiness Size Standardsact 6;! actuation of a licenseeof theletterrequestingthe f c.r* a

-7 Informatien.i --$.bW 'RC 7 C. IIst oI5ubladsjn19 CFRPa'rt30 ;y. Protection System 3)i e v-c...

Section soJ3(f)sives the N ,.i L*1 ^" W. ' i revention. Intergovernmentalrs!Mf se'quenos dadag J .e"= tesdis partof theprep Executive Director for Operations thav7. _, n k,. examptions to the reportinge.t W, hj _~.? Antitrust,osanswa infor== flan Firs % fruenan 1 l er 7., - authodty to grant case by<ase h i -d d " "requhements cont =laadintheMR'. M Nuclearpowerplants an8 reactors l.?.h;-fT merm .;, /. ' O Wr;vpW', 'aystem.%Is exemption could be used io.. Penalty.Padiatf an protection. Reactor.d; repost 3h' siting criterla. Reporting regulrements.J-ae r manna set out h theT ~ limit the mnartian of certaindataIn W- $ j%. or discoveryetdetIgri.'analysia ~~~.' 3 those cases where full participation.4-wouldbeundulyamruitbecauseofa.. ~ j Forpre==h and ^ 4'- plant's unique circumst=ne==. J'.e_.? . Energy Act n!1954, as amanrbri &ai. inadequacies ht alone could prevent b .; j ~ ~ ' _ Energy Reorga nle= tion Act of 1974, as 9 amenaarf and secuan 55s of 21tle5el e . the fulfmment of 6e safety functiond % .Section.m73(g) states that the t.r i [ <' reporting requirements contained in the UnitedStates Coda.natimishereby structures ne systema thst are needed * - - p., requirements in all nuclear power plant giventhatadoption of as following.1. '. to ;.---r wgy.a i.s,. A. ,8 5073 replace the reporting f.v.J 10 Shut downhtesctor and' M, (n TeAnle=1 S;edricatichs that ar* ; ).-? amendmegts to10CFR Part30Is.wU maintahltina safe shutdo@lF i e, contemplatad 2..:-.4'O- .' !.S #'- -l conditicac" N ' 0h- ^ #?% % j { associated with" Reportable.,.. Mh@ f -?'.- Occurrences" %e reportlag.,*,. PART50--DOMESTIC 1.1CENSINGOFJPRODUCT3O .r. .c, requirements superseded by 3 5073 are <1 those rentained in theTechnIcal :.... ? '".: ' -- ~ J 'v r Specificatlan sect!ans that are usually. FAC1UTIE3;* iE ?" ^ '('o.'. mataridi-'- imtNa"used by's fallarsi[# 8 ~ (3)An[ev .ginsthority citition fw"Part5 fault tand!!!'on.'waction1 hat W7 p titled" Prompt Notification with Wdtten c .t to read as fo3ows:e : f.:...,/- ;. a d 2m-.~. M N'7i Followgf'and"ThirtyDay Written m., A h os. u t. u z. n a.2se. interdependance associatedwlfhE*8 ~

.y Reports.%e reporting awmr.ments.h 68 Stat. 936. 937. 948,953,954. 955,950. as !# amended (a USC 21 M,.

thathavebeen superseded are also,, i describedinRegulatoryGuide's.18'.. W mrumums.-

• 4'--# -

1244. 22ee le UAC son. sou. see).=1===',-2:33.zoobem.201.zaz g Revision 4.*'Repo of Operattag.L N. lLg InformaUon--Appen ATeAnle=1. _ - - - - = - - etherwisemated. W n vry-O ? <gg;@-s g. e, v.t p* dlte % ; f ay 'N. - S Specification". Paragraph 7.? Reportable. o..- a Sedan 5038 duo 1:sedin'dersec/tzt.se.c. Teactoran Stat.spicUAC214Sedoim aaso.eam p [Q Shut down 9.. hg . Occurrences" - ?.. i * '^/. '. a*: ig*- alsoissuedundersec.1st.asstat.sse,misP Crna '" v; r g y, N PaperworkReduction Ad h====%. am aa=atouscme.sewo ssa< toe-JL so.tatieased anderser.ut essent Q UQRannovetes!dualheaW2-Aswqeredby se prwidons'dae" USC224 c. ..W w-J N;mstad ly IRQContml&eideau d&lb. b# PaperworkReduc6an Acid 1980{ Pub.c Fmans purpms d sec.223.MRatm.$[- med L I. En).Be NRChu made a - W. Yi[4) Any eventforwhldipladt g 9 - preuminarydeterminauonhttheseW - k u = - a ia- - 7a gakkk.13. .ast. rst 5=h i= mP=== d proposed regulations do not hnposemal f.S a,e ed.nd.r a 1 ! t or.

• . ad-d-,-eve-eeerias. -Infermanoncollectionbedan/m= r, amendedteUAc2xntte:ssso h.

MadddraplantTeAnima.,s.* U. S tis not.,, M pored regnistions w1H oeeerthelees'C e M aimisase ureisemedemieress.2eu. 4 ~m mua,ementandsaa etrord.M@M.J; stat,see,as - A A 4 d. .a.- r t enbmitted to the OfBee of ss samusammsessan.==.=a5 Astyagwant thdate e. Ma! s ys consideration et the reportirig. WON.. am ass esmeedumdersacesenseamma. .,; w eatnbein,wa y .s k r> .,e dueeping.orinr-manonosnea.;.m dinu3c==.y ; d.pp;p.x:qp.Wganeddfyse R. onfroBed randition or that resulti q".. ;, requirement..'. %WW9"'V 2.JAnewi2J3Yi'aild'sdt c

• i

. <..e :es Eg } t., r (S) Anyadofnatura,wigd eractby h' r-4==ne with iheResu!=tir m 4.8nJ8 ?-fJe..E.ghpwt.SyeQnneesczneholdk%,3 per.-=a tha 7 4 at no may f .n ;,;.(aja,orta c. 'y,mmyAd f tsan.susc.eas(b)$.?.,plamellv-==)shalladfasta-an opers tin 5 'll. thecannala lan'herebycertifiesthat r s-=., j} '2/ 1=6a= willnot. Af ei necessary for the safe opeastian af theb per-ma==*ad have a sh.am4W Ev,ent Rapost(150foranyseemdas 7.these prTa=ad a.g: wri&@imb ;plaat,er the securityof spe econornic impad on a substantia 12.tT, type da=rvi*mmt in shie .F

==tertd.;tadadins netmacesadpeq e tad to 1 ~. M+ W. iMMY,=,'.W@i,cd~.w'* %gish

g..m.w-4; *C.d.e

' fl 'namberof sma11 entities.nese W94so 68M:;;;f.;-%.M 3." .f*M:&y A.. y ,A

l. Q t'

... : :... :.6 p. ~ 1,2 a.M.@d.sTs % s R gf-d .W..: N > a..h .1. e n-g.m.m . n.,. m m.

... m,. _ . ~ %. g{ .j..i.- Vol. 47. No. as ] 'Ibursday,Way a,1982 / Proposed' Rul:s ' ' M19 AM..... C */ Federal Emelster .,.. z.,.: ~ ..,,.,. ~... ~.,.

$l T i

'.; l

..a ,..... :. :... + s a. w J abatase er attempted M-Y 5:ents f J' (A)IEEE Std Pam/P805A/-i-[-M....@,20tCstaffmayre n=== to : .-w.~.. C r -t submit spedfic additionalinformatione Rara====Al Pr=ctfr== EarUnique.U-and assessments beyond est required. ~ *..y.d 0 of violence thet are not substantiated by-pahe licensee need not be reported.,d' 7 3 den thahan Plants and RelafedFacGinse-Prinefples and D g -- '=ii-V4' staff finds that such supplemen . byparagraph(b)of thissection,if the'. e ~. f req (7) Any radioactive release that.c-r.uires the evamstion of a roose or.3. ".s < (p j kru..brildios.. +.;...M.j s. 4.W1-L%i c. Practim derSystemi (8) Any radioective afDua qlW.owhere-lRn f.MFEMMM ' Farm== C Wm.N ywrv2.MG or=Ign. g h; 'W *. - (1) N quantity of radiondive CM.N (Q These publiations have beenV ~ L approvedinr1=.- hby 7 matedals in liquid or gaseous ah==#= by the Directorof the F.sderal . ', req estedInformaHon'and essessment ' NA M.. reisesed from the site exceeds the limits ' A notim of any A= a= made to the e., nee a su^pplement to tee initial LER within.d2 d 7'. speciSed in the Technical'.,.9.dng ;n -maineist by referenos wilL3 the Mmeperiod spirdSedby the staff:- 1 'J.:t. 4 s..R i h". Speciflations..,y W pysyy. ep ,. e,.- Copias may be obtained frcan the,a,f74g',s IN#88 M**2; T2',$., N *. m:(ii) & quantity of =diaarlhe > g be published b the Federal Register.. 5 C - storage =nir exceeds the limits specihd 'InaHhda c.f Electricaland Electronicsg f; lerial metained in a liquid er gas,. e. - Engineers, United Engineering Centark-NRC-XXX_ n i' ' in theT=Anhf Speciacations. m.;*.i D.. "fali) With respect to balling water" 7~ 345 East 47th Street, New York,N.Y 20017. A copyla avaDahle forinspection. O==J-=fonis enn=Maring. alternatives g: f Y 4 resctors only, the quantity of redimactive at the Cranmission's Public Document /.,, for the timing of then reporta. These. - r.n ' materials la gaseoas wanas transferred. - Room.1717HStreetNW, Washington :,'. altej

v. t ~

D. from the primary coolant system to the. D.C. and at the Office of thaFederal i'- <I" gaseous radwaste management systma... E. Register's infonnation cen'=r. '

- U ' OVERVIEW CF'IEELER SYSTEM)'.'.

e2.ce;eds tlw Emits specificila tim ance the discovery of the event cbvered Technical SpeclBations.W "-,h' y s n #0.*Jhe func6m of the compment oc. " "' 1 . (9) Any event for which the rpantih. For failures of =amaa=n'= wi& multipl*.in the report.%4 LERm ,5 a * :.M i systemin whidt the failure occurred. "... W<a az m . submitted.to-.. g.e. - 8ppropnate NRCReginal, m g. r. M s.; c , < an==i curie ofr=dfaardwe matenalin. - list of systeam or semnda cf radioactive matadals r=b==ad dering - I"netin==. the ihn=*e shah laclude a, J - y.- C. af aaa d offalta m!4aseis more that were also affected.... UC_"Se.;. dfuncHonaDyradaaeah. ]y-] than J; i Uquld.mu..,+a-more than no cunes d For each faned-. t-Dt own.inWnM to Part 2D d als

• yy noble 8as in gaseous efDnents, or more compnnenta insta!!ad in the plant. ". '

' Chaptes; and'. ?$',-??Jf ~;. 1 1 [ .n Ihan 045 curies of radioMa= la- ~

i. :i nmes byb E'1. lacluding the degree of dimsity an.d$gy yp, Didsetar[ Divislo"n'ofTechnical M5l rams elHunts (b) Contents.h 15s.

T Inton==sk= and Document Control. U.S. I . s J.-N..their avanabnity during the eventc. _. !WOperatoracdons &ataffect - *' O, h! sM Report must contain: i, - (1) Abrief abstract des'cribing the - &a caru d&e mnt. including e sc ? Wash.ington.D.C. 20555..F.M a 1.- Me)@be ofsufBelent quality to ?. inajor occurrences during the event...,' operator erram,,,m.--- I dabiandes - ~. Jep%%e i includ aH t orbo&,&amotrash &e eme I -g fdums at contn u d the eveni - itxMntmnaticaDy and mannally . ' pennitlegible @dsc:fon and-." - -l copies must M ~~ and any signihant corrective act. taken or planned to prevent recu.rrence. ' initiated safety tem uses..~ micrographic processing.. ' %~ ion - model '~ . (x)%e man MD8t@iME U mwrin'enreynesb-f (2) A clear. specific, narrative . '. number (or o&er idenuncade) deach P .p, component that faned dudag the event. from a heen=== indoding adequata - 1. 7, . description of what occurred so that. knowledgeable readars conversant with:(x0h number and types dworkers' exposed and the dosereceivedbyeacha justfButam.ar attheinitiada o -. L ;, - NRCstaff,the Exacn8ve Director for the dMgn of commercialnudear power plants but not fammar with the detans, worker as a directresult ofa reportable Operadoes may, by aletter to the of a particular plant can understand th* event that results in a total occupational licensee, grant exemptiona to the - L,. '. f-complete event.h narrative that exceed five manrem.%e' -* ' % porting requirementa under this' ~ N ~ < '- - - ". i Yes--.. M -'NP 2: licedsee neednotinclude exposures description shah Indude the foBowing. incurmd k cnrmcuve acHim and deaPi" sec6am.. a.@'* ----. C specific information:. ... + a. g .,. w - (i) Plant operating eanditions before. - up.... w,.,. -.. -m : ;. : ....i_of . mpiam an m . ~.= S Statnacha..M nces and g licat c ns (1 9 ." Reportable Cs..d as definedin' ' ~ E. /- ent ,systein.s bef,e the... **,,..... -of anycorr"ective -.s ~

4) A,-

' individual 1 ant'I'echnical ~' 7, .,7,; j c.. (Ili) Dales and appran==te times of 'ac(tions plarmed as a result af the event P ic.., m...,... event. s,. s (iv)W failure mode. mea =at== an of st=Har events ocx:arrag la the.fulnre. '. Datsi a t catie t,.,;,. - _, ,7, lacinding those to reduce the probabuityl JM; occurrences.', - f. 7.N.. ;... d 7-a - -- (5)%ename and telephone nu:nber d- \\ a personwithin the Beensee's. M'.; @f p saz. ~ s.'

Nacinar.

-'M',--. s-k ~ [ .Id i affect of each failed component.'. '. ". Nf U. System component function identiner "., organfradon who is knowledgeable N g, g--- b g l y,,,, j {. - 1 L. i 'Q . -(v) ne Energy Industry Identification, ? ?'g /.J: 7.., M; $ about the event and canprovide '? % C., , e ,Q J. cnd system rimme ofeach component or.., 'additionalinfannationu=-- L-J the $ 3"64?'88"*l85PE.,D'r m4a"'8=8? t ~ erstem refermd to in theIEt.no {g-Energy Industry Idene-= tion System ls event and the planfs diarartad=5cs. - - ~........ - '.~ sanma coce?sm*ur,.. :.Q :... M..? l%G (c)Supplemen.to!inf. ormution.h.. -...:.,.... n.s ,', /,.i.p Q.4.L. =,-: .~ :,,:..x,a -2.,.y 9 p..y,..- y :. c. x,,g

• ga. g.;. j.y 3

y.,., q,z.:

defined kc -w. , n,. 3 ;. q *, 3.. .f f y,. #,. ~;*q ,y. y., .< ;. - J.. _, ;. t.:

,. l* ( b.

• w

-2 _' .'o', g* .,. y, ; .w e. ..?,, N. - a,- ' d c. ... <... ; s.

• . ~^, "

s, = t 8 *. .y 6 , ',=k'* ... ~. ~ * ~ -' ~

....'

*?

,,-e .\\ V

1. • mk

,,e hX Q l

• is.'

a t

• .-.-.si.

L T.%. .Q 4- '4% ' . y. - .A gn n r

l =,n o ACTION CONTROt DATES CONTROL NO. 1 rROu. yyjjj See. un'"c.no.m Wnitier L2373 c~ -~e ATE OF DOCUMENT I (Rebecca L. Amedes, Staff Assistant) i iNTcR,u Reny )g g { PREPARE FOR SIGNATURE TO. // b fe $c,,,,,,, \\ 3 hMI FILE LOCATION b / f /, @ EXECUTIVE GRECTOR / OTHER DESCRIPTION bLETTER O utuO O RceORr O OTHER SPECIAL INSTRUCTIONS OR REM ARKS t Ret th Maria Melt, fttd-Chast Meelth Reseerth Group for left re License Eveet Reports sa Mates Yankee ( ASssoNED f ' DATE INFORMATION ROUTING gg g __1 Doeten-J dift 4C. M CeWRj h LSederused , _. _. ~ - -.. - _ \\ ^ i ^ . j GC FORM 232 EXECUTIVE DIRECTOR FOR OPERATIONS (6 Jf0) PRINCIPAL CORRESPONDENCE CONTROL i

e m.m 1D02 J t n o. 10/7/82 uo. a NRC SECRETARIAT TO: O Commi on.r o... N Emec. Dir./Oper. Gen.Coune.1 M . Li.ison O sorcitor ._I Public Aff. irs O secret.ry Q' / O in ector & Auditor NF/d EP#F4 / #5 CMC Polley Ew.tuation incoming: IE p, . _ Maria olt To: rammarer o.,, 10/4/82 subiect: ran all nortinent info pertaining to or pre-nmenet in the Iironte Event ReDorts for the Maine Yankee m nlant Prop.r. reply for sign.ture of: O Ca.irm.n O Commi ioner O soo. ac. co sot. ex. secy...,e O si n.iur. biock omiti.o O O n.ium ori,in. of incomin.iin re.pon O '" di"*' *Y ' Suspense: Oct J!f I/ For.ppropri.te.ction O Forinform. tion Rec'd Off. EDO Date....... ;j g 4 3. p y i ....-cr. Time......m.h....... j..r ..m For the Commission: h4114a ' Send three (3) copies of reply to Secy Correspondence.nd Records Br.nch NRC FORM GM ACTION SLIP i..,}}