ML19220A907

Forwards Utils Comments Re Administrative Controls Tech Specs Forwarded Aug 1977.Requests Formal Reply to Comments, Giving Basis for Rejection

ML19220A907
Person / Time
Site:	Crane
Issue date:	10/07/1977
From:	Herbein J Metropolitan Edison Co
To:	Varga S Office of Nuclear Reactor Regulation
References
GQL-1323, NUDOCS 7904250082
Download: ML19220A907 (34)

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6.1.1 The Unit Superintendent shall be res;cnsible for everall '-d ' '-'

c;eration and shall delegate in writing the succession to this responsi-bility during his absence.

S.2 ORGANIZATICM C.:: SITE war"I' l O N for ':7"he offsite organi:ation of the Cor: orate Technical Sup;crt Staff 5.2.1 T

. =anagement and technical sup;crt shall be as shewn en

.igure 6.2-1.

te l e-1 l C P4

_ -.... --.=S3;--

ST'AR~TI C N 5.2.2 The :. '. organization shall be as shewn en Figure 5.2-1 and:

a.

Each en duty snift shall be cc= posed of at least the minimum shift crew c:= position shown in Taole 6.2-1.

b.

At least ene licensed 0:erator shall be in the centrol r:c when fuel is in the reactor.

c.

At least two licensed 0;erators shall be pre:ent in the l

control rec-during reac::r startus, scheduled react:r shutd:wn

}

and curing recovery frc: reactor trips.

I d.

An individual cualified in radiation protection precedura-shall be en site when fuel is in the reactor.

e.

All CCRE ALTERATICMS shall be directly supervised ' y either a licensed Senice React:r Opera::r or Senice Reactor C; era::r Limited to Fuel Handling sho has no other concurren: responsi-bilities during this operation.

ST/7T1'O N f.

Affire Brigade of at least 5 members shall be maintained ensi:e a all times.

This excludes 3 ma::ers of the minimum shif t crew nect sary for safe shutd:wn of the al =4 and any psescr el s

required for a:her essential functions duringla fire emergency.

().N 17-i

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7

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.vrLICn2,e.unr:.5 L.. sg.:-

e C^'T "~~'Y 1, 2, 3 & 4' 5&6

^

SCL 1

1*

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1 Non-Licensed 2

I

• Coes net in:lude the licensed Senior Reacter Operator er Senior F.ea:: r C; erat:r Limited to Fuel Handling, supert i:"ng CCF.E

,.,,...,. -.. 1 5.

.. i :..u i w.

! Shift crew ccmposition may be less than the minimum requirements f r a peri d of time n:t to e.xceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in ceder to accc.nedate t.ex;ected absence of en duty snift crew mem:ers provided immedia e acti:n is taken :: restare the shif t crew compcsi tisa t: wlcnin tne cinimum requirements Of Table 6.2-1.

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positions, excepc for the

)

• ).1.1

=. h ~...... " = r c #.

ualificaticns of A"SI '412.1-1971' fcq.cc ;2rabi'h shall meet or exceed s

Superviser of Radia:icn Fratectica.:.4 Chemistr I'

the qualificaticns of Replatory Guide 1.8, September 1975.

a 1

O A I NI NG l /&6(,,'I'Q k I (cM l 5. A

(

- n.e s A retraining and replacement training prcgram fen the q

Training

~

5.4.1 staff shall be maintained under tne direc:icn of th l

f and A;cendix A* of 10 CTO. Part 55.

'f Sectica 5.5 cf ANS~ N13.1-1971, Dt 2.cccre.R-6 C N ER.ATt OW"TRM N M c.

i A training :regr2c(for the Fire Brigaie shall be maintained under

.,... ::- and shall meet or

.a.2 the directica of the ".

. ~ ~ _

exceed the ruuirements of Sectica 27 cf the NF'A Code-1975.

I i.

c h, r 6 y

c. 5 : :.l r.. rl e o,

.<w a.

.n. e. Cr...u. r. t. r.r ( =. c..r.- )

.i-u r c...,. m,. a 2

--e s

p,.a., r.

..3 a

r a.i :... _. C,. i The Plant C;eratiens Re/iew Cc=ittee {FGRC) shall function to Superintendent en all catters related to n.: clear safety.

5. 5.1.1 advise the Uni rcv:c.e.i.c..;

Tne Plan: C;erations Review Committee shall be composed of the:

5. 5.1. 2 Uni'. c -ar'ov.= d=... A

.[.y, y g3-

<p,,:, y /;q. : =pte,u,,q g u.

,r i,

. =..

C,.r' Supervisor c-C; era:1cns T G c 9 m t A, u p ?c R. ~.'

j

.s..w.

e,,=r/ia 9,.

1. . " > i..o,., r.,

4-o d

d'.

Unit Electrical Engineer J,

s Uni:.echanical Engineer M

3-r ~'

o,.,

._s a c :.,,1,,. a a_ r E

Uni' Instrument and Centrol Enginee N th;,

.,/..

v.

I.

.3 l.t, n l.

=

i 5f[Y.

Su ;arvisor of Radiation Pro ecticn anc Cnemistr'v >U N. 6%

[

2 4 i M F E.2-$ /rSS IGN G D.3y 'Ti4 5 g

S,:rrie s y

h ll designa e the Chair an and the ' lice ine Uni-Su;9:intendent s aa:cng the cecbers of the Plant C;erations Re'/iek C ee.

t.

Chairman it:=

I

.J E.

u.

.m u t :_ :. m. -:,s

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c.1 i a 1.e.m.. 2.

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Chair an to serve.cn a-tec;crary 52 sis; however, no more than tNo t

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10 C.i w f 5.5.1.4 The FORC shall meet at least once per calendar =cnt.i and as convened by the Chair an or his desicnated alternate.

., n c :,, M

-.~

5.5.1.5 A qu rum cf the PORC shall c:nsist of the Chairman or his designated alterna*e and four =ecters including alternates.

n:_.q:n. tSI I, I i 1=2

- e m

6.5.1.5 The Plant Cperatiens Review C =ittee shall be responsible fer:

a.

Review of 1) all precedures required by Specificati n 5.5 and changes there:0, 2) any other pr:p sed precedures cr changes thereta as dater nined by the Unit Superintendent to affect nuclear safe y.

b.

Revie4 of all prep: sed tests and experiments that affect nuciaar safety.

c.

Review of ali propcsed changes to Appendix "A" Technical Specificati:ns.

UNIT d.

Review cf all proposed changes or ::difica:icns :: ;'

-t syste-.s or equipmen: tnat affect nuclear safety.

Investig2:icn of all violations of the Technical 5:ecificati:ns e.

including the preparation and femarding cf re:Or:s c:vering evaluati:n and rec:=enda:icns to prevent recurrence t: :ne

.,..._ T_..

. _ _-1 Station Superintendent and the {:..;....

...a 6cacRic0N K q{gca (30rn A tTTEE C RC.) CHpngm;J _3

% : _' ~T~ ".

5 f.

Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the C: mis

.t.

ONiT-MtLEAM g.

Revi ew o f 5_.. ' ' :, cperaticns to detect potential [ safety ha: arts.

h.

Perfor ance of s:ecial reEs, investications or analyses and reports thereen as recuested by the

.n

_x

Tb c O M'i % xR ig Tfl.c:L-iT-Tu.... ' -

^ :

b

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. I.i,t 5,,..,l. C u~.., i r.u,.

it l5 RESPCNSI5ILITY (Continued)

• L e.

5.5.l.6 a.

Review of the h Security Plan and i=;lementinc precedures and shall submi t rec:= ended ch.nces t,n, c.._ ~ :,...,..,,... _h,: ".,

i.

oi Ogi.. w,.:u.tu.

_.-. i e

..,.,5 o M..u me,.o 'i--

i Mb TH':. S A-T I o N Review of the Emergency Plan and ic;1ecenting precedures and F

shall submit rec:= ended changes to the %=c. _-

- m :c j.

~.

N : ', 'i R i. t.Wr Sje.a. u n.CE vi"),p.c 7sg:.

r--

1

/

S. TAT 1od S.O R:f.iM'IE m qT-g..... s t

..._..r The Plant Operati:ns Review Cc=ittee shall:

)

5.5.1.7 the Unit Superintendent in writing, approval er disapproval of items c:nsidered under 6.5.1.6(a) thr ugh (d)

Rec:=end ::

a.

abve.

i ith regard to whether er not J

Render deter--inatiens in writ ng w(a) through (e) abcve c:n-..

5.

eech item ccasidered under 5.5.1.5 g g,

. C.f.Ud dM,0#

f 5titutes an unreviewed safety cuestion.

11,

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p r,.n.,,s r...,, n2, :andthe"e.. h...'"'

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""..".'."..=l5.'.#.. < u'"r.= '. 1' n.='.'d =. n,.,

.i Superintende-:

" .4=.=.n '..a.

r'ORP shall have res nsibility for d'.'2'.:.=.'_'..=."...

c, c_: d'.i..%' " '

h vever, the Unit Su:erintenden

u. y.

resciuti:n cf such disagreennts cursuant to 5.l.1 abcve.

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l T*.'?;"T:0?! (Ccc:inued) i i

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c.

Chr.istry and radicchemistry i

i

'I I

]

d.

Metallurgy j

l e.

Instn::entation and centrol

[

tl i

l f.

Radiolcgical safety I

I g.

Mechanical and electrical engineering h.

Cuality assurance practices i

l 1. _,, _ -...

.,1

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-:..m

,6 b. 5. 2. 2.

• h e C.T55 S H ALL EE COM Fos E B O F T K ii.

C,EMER ; 504 REV [EW COMM t'TTEE f;N D TM E OPEAA-TI ON,!-L II l

QQ A LPl

.%509 /r4C,E $T/-F~;

i cL. T R G.

C, r_..sER,v7 i o N REv tEw ccMM 17 TEE I

I (C-7Ad ) SH ALL COMS!sT C 3 A T L E / C I-NWE-l!

M E M B E R_5 14 0.Lubi H C-7 7 M F-C H /rt EMMi l

APPOIN.TE-D 1M /4 /T'/M 6

/Sy W/i:.

V/CE 7

(A S E 5 I h 5 h ) ' ~ - Q 9 tJ &,g,4 7; 9,q, (3;t C M St.,7 gQS hl M&Y rdLE Appoin7212> i=/ecx tJiTHin THE V

C0t? PoRrLrL cit.GA+1I 2a-TtoAl OR PnCm h

SXT= R ll4L SO u,2 c_ ; 5, "W F_

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ll coever wa. es v&ws s net ; iso /u l

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T K G. o:Emn o.4 A-L QuGLm/ Assu,E4.vc5 re,f; I

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6. 5. 2.

9 1 4 A ccc C 4.v etE, oj ; T y r y 3 oQA Ptes.

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K.

cach.._- mr..cer an,. alternate shall ha ce an academ.c degree in an engineering or ;nysical science field; and in addition, shall have a

-inimum of five years-of techncial experience, of which a minime.m of three

~

years shall be in one or more of the areas specified in 5.5.2.1.

I l

d7',

2nd.N. SUD\\TCil O F T i% E.

C Q /4 STM F 5 MLL.

65 QU frL t T--i Et IN frCOOADh4CE W t'T K 7 M G_

O CD A PL M,

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w All alcernate m abers shall be ap;cint2d in writing by the 55 l

,!,h5.2.'- to serva en a te.;crary basis; hcs.=ver, no acre tnan tao al:er_

!j-a:es sh2ll pa.Mici;1te as voting members in 49 activities at any cne l

tim e.

(q Q j er em -

3 i

r-;---

W $m s u a

,.. h,,

/-

I w s s i-;w

's~~ t A

l5.5.2.5 Consultant shall be utilized as da:e :ined by the ~~: ::.. _.

u - o m_.

.X

r. c.275 ~

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-w l., g._,<;,

f C,.i$ ~l'

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The 4; shalll,m/

GM eet at least cnce per calendar quar:cr during the 6.5.2.6 initial year of 2 _

., operation folicwing fuel loading and at leas cn,ce per six cenths thereafter.

/ gRC C

CUCRL'M C M-7 6.5.2.7 A quorum of-F+5-sha}1 consist 'of the Directcr or his designated alternate and at least 4 4:99 members including alternates. No more : nan a minority of the quorum shall have line responsibility for egeration cf th e '-: ^b b41 i w#

REIT E1 b$C 5.5.2.8 The f44WE shall review:

The safety evaluations for 1) changes to precedures, equipment a.

or systems and 2) tests or experiments c=npletec under the prevision of Section 50.59, 10 CFR, to verify that sucn acticrs did not ccnstitute an unreviewed safety question, b.

Prepcsed tests or exceriments shich involve an unreviewed safety l

quescien as defined in Secticq 50.59, 10 CFR.

.mihts wnicha w olve ar a p id sa h y

Propos. :: s or exca

--.1cn as

.. ' '.. in SecOcr T59,10M C_ /[.

Proposed changes to Technical Specifications or this Operating License.

I

'liolattens of codes, regulations, crders, Technical 5:ecifica-o tions, license requirements, or of internal precedures er instruc-tiens having nuclear sa fety significance.

2.

Significant operating abncrmalities or deviations frcn normal and expectad performance of.f a e equipment that affect r.uclear l

s a fety.

U.4. -

sa

( /g'.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

C All recc ni:ed indications of an unanticipated c'eficiency in 5

scme aspect of design or operation of,[ safety related st.uctu. es,

i

~

systems, or ccapenents, ggetgjj(

T /.

Reports and meetings minutes of the PCRC.

l l

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c-o

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t ii v c..

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vr ry q s a?

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5.5.2.9 The _.,...___

... - d_..

... :.-.- s h211 conduct audi ts tc rations with the Ccerating Cuality AI:ur-verify ccmpliance of '

ance plan, including verificition of ccm,>iiance with applicable internal rules and precedures; federal regulations and C: rating License previsicns; training qualificatiens; and performance of the cperating staf f.

These audits shall encc= ass:

e

\\_)M.t\\

a.

The confomance of f;U'., operation to previsions contained within thc Technical 5;:ecifications and applicable licenset conditions at least once per 12 conths.

S'i%Ti c N The[perfemance, training and qualificaticas of the entire b.

.- staff at. least once per 12 centhc.

.1

.\\

\\

V H. \\._,

The result /of actions taken to cc.- act deficiencias cccur-ing c.

in".,'

'.- equipment, structures, systems or method of cpera-tien that affect nuclear safety at least once per 6 months.

PLAH C PGL'~rt k b The performanye,of all activities required by thejCuali:y d.

Assurance

.,- - tc meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e.

The ~

. Emergency plan and implementing procedures at least cnce per 24 conths.

f.

Th e 'N : "

. Security plan and implementing precedures at least once per 24 cenths.

j g.

The L

Fire protection prograrf and !=pinenting precedures at least once per 24 months.

h.

An indeper. dent fire ;rotection and loss prevention inspection ano audit shall he perfomed annually utiliain-

'*"er quali fi ed effsite licensee personnel or an out: ice fire protaction fir:.

i.

An inspection and audit of the fire protection and less l

preventien progran shall be performed by an cutside qualified i

fire censultant at intervals no greater than 3 years.

,i e-VN,l'I j.

Any other area o f # -

'. cperation considared apprcpriate by the CTSS ce the !Pnager-Generation C;;r::ica:.J

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J 5.7 Safety LIMIT VICLATICN 6.7.1 The follcuing actions shall be taken in the event a safety Limit is' violated:

\\)MtT~

.TM a.

the

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.- sn,all me pl aced in at leas..,

y.....,s-.( wi 1n w e nu s im =u heu r-s, b.

The 5Faty Limit viciation shall be re;cr:ed to the Cc=ission, the Staticn Sucerintendent and to the :' _ _;..

5:

Q R C, C g t g tvi g d within 2? hcurs.

c.

A Safety Limit Violaticn Repcrt Gall be prepared. The repor:

shall be reviewed by the plant Operaticns Review Cc=ittae.

This report shall describe / (1) applicable circumstances pre g '3' ceding the violatien, (2) effects of the viola:icn upcn ^

~,

ccm;cnents, systems, or structures, and (3) corrective actica taken to prevent recurrence. E Ch.alD uI g

d.

The Safety Limit Vici.atien Recort shall be submitted tc the Cc=ission, the 'T::'"and the Staticn Superintendent within 14 days of the violatica.

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3

ritten prccedures shall be established, implemented and 2i.tained

,5.5.1 covering the activities referenced belcw:

The applicable procedures recc= ended in Appendix "A"

of a.

Regula: cry Guide 1.33, November,1972.

b.

Refueling operaticns.

Surveillance and test activities of safety r> lated equipment.

c.

d.

Security Plan implementation.

e.

Emergency plan implementation.

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~ i J ACMINISTRATI'!E CONTRO'_5 STARTUp rep 0RT (Continued) 6.9.1.2 Etartup reports shall be submitted within (1) 90 days felicwing completion of the startup test program, (2) 90 days fcilcwing resumptica or c:mrencement of cercercial power operation, or (3) 9 c:ntns felicwing initial criticality, whichever is earliest. If the Startup Report d:e3 not cover all three events (i.e., initial criticality, c:=pleti:n of startup test program, and resumptien or c:=mencement of cermercial pcwer cperatien), supelementary reports shall be submitted at least every three m:nths.until all three events have been c:=pieted. E ANNUAL GPERATING rep 0RT 5.9.1. 3 Routine operating reports covering the operati:n of the unit curing the previous calendar year shall be submitted prior to March I o-The initial report shall be submitted prior to Mar:n 1 Of eacn year. the year folicwing initial criticality. 6.9.1. 4 The annual cperating reports shall provide a comprencnsive suntary of the cperating ex erience gained during the year, even th ugh scre repetitien of previously reported information may be i' valved. References in the annual operating report to previously submitted re;;rts shall be clear. 5.9.1. 5 Each annual cperating report shall include: Lj g iT' a. A narrative summary of cperating experience during the re;;rt period relating to safe operati:n of the f:f' t., including safety-related maintenance not c:vered in 6.9.1.5.b.5 belcw. For each cutage or forced reducti:n in power :l of ever twen:y b. percent of RATED THERMAL PCWER where the reduction extends for greater than four hours: gg go E.15 lmb HOC' E.M?,0TM - -1/ A s i ngl e s u:mi ttal may be made.fo r ;.._: : ' pl ; _ - '. : :_ t '.... The subnittal should combine th:se secticns th:: are c:rmen tc 2d1' units at :he-3teter. 6 ;Ty -~2/ The term "f ced reducticn in power" is defined as the occurrence of ailure or othe,r conditicn which requires that the 1 cad a :=;- en th-Je reduced for corrective a:ticn imrediately cr up :: and inci .g the very next weekend. Note that rcuti.e creventive maintenan.s, surveillance and calibration activities requiring p:wer reducticn3 are not covered by this section. i <p;n q(... LcJ (( Tu. :::-_.7.L. T.(L.'"nD - UNIT 2 6-13 r. v a ' ~. '.P, 2

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n. > 5 i...> i n 1

o n,.,,,r l O :.,......- - a c; 3.. (uon nue i ii t e r i t u n:. . i s e 1. The proxirate cause and tha s. item and major c:::enent ~ involved (if the cutage er fcrced reducticn in pcwer involved ecuipr.ent malfunction); l 2. A brler discuss 1c-cr (cr r.ference : reports cr.) an.y reportable cc urrences pertaining tc the cutage er pcwer reducti:n; 3. Ccrrective acticn taken to reduce the prcbability of I r =..u r e r...=, i #. a -a.. -. i a '..a, .r r 4. Operating time icst as a result of the cutage cr pcwer, reduction (for scheduled. or forced cutages,rl use the generator off-line neurs; for f:rced recucti:ns in pcwer, use the appr ximate duration of cperatica at reduced ;cwer); 5. A descriptien cf cajar safety-related corrective main-tenance perfor ed curing the cutage or power reducti:n, including the system and cc penent involved and iden-i fica- + : c a. c '. u5 a. c.. d. ' i e l

n. =.."..=... i v i '.v, di...= ". ~. 3

'm"..=.lc-r3 5 s r of the autage or pcwer reducticn; and n re;;r Or an single release or. racicaccivity cr .c. d i w.'5 '.".=. rad.i.='.'.... =. x,., m- - ". =_ s,. =.c '. #. 4 c.= l l,y = s w c. = * =d. cutace which ac :unts for c:re than.V. of the all wabla J.rs-E~v21ues. 8d G xa: au.s s 2.s.u l a. "...... n c-...u = 1 " 's i s o '. * " = n u.." =.- 2. - .s.. i. c., 4 a n utility and other pers:nnel (including c:ntract:rs) receiving exposures graater tnan 100 nrem/yr and their assc:iated man rem expcsure accerning to war'< and jcb functicns,'- e.g., reactor cp= -etiens and surveillance, inservice inscaction, routine maintenar.ce, special naintenance (describe maintenar.ce), waste processing, and refueling. The dose assig-.ent :: v a. i v-"s ""e ej-f ". -. "... s...=. v b =. a_ s "m... = ' = s "u = s =_ d ~..,. -ka. a.s m5= cc.u~..e..=. c '. ' c -.. ~~.. =... -.j i... 3~.~ ~, ~., m c -....= c.=. " i s d =. #. i n =_ d w, ee . : 3... r,_,, c.,, r m_ o... a.... w.... . 2,. e_ s. x...,.. ,.... am_ a u .i .. w e.._...s=.-,".=_#..~. c - ~.. =... '. ". = =. i v~.. i....= ^.= 'm ='i j-c. u., '. ' a r. " i r. 'i.s '. ~.., t h e v a-e n e n w ee'< e r.d. }:.

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O 9 ~ m..n... Le i r.- i t 1: C,o,,. o,,.., S .m ru 4 A IVAL GFjRATI*tG REFORT (Continued) T Small ex;csures desimeter, TLD, or film bad;a miasurements. totalling less than 2C". of the indivicual total doce need In the aggregate, at least SC" of the not be act unted for. total' whole body dese received frca external scurces shall be assigned to specific major werk functions. Indications of failed fuel resulting frem irradiated fuel exz.,inatier.s, including eddy current tests, ultrasenic tests, d. or visual examinati:ns cc pleted during the report pericd. In addition, the Anrual 0perating Report shall include the folicwing infor-ation on aircraft =cvements at the Harrisburg e. International Airport: The total nutter of aircraft ::vements (takeoffs and Harrisburg International Airport for 1. landir.;s) at tha the previous tnelve-conth.pericd. I The ::t21 numbar of covements of aircraft larger than 200,C^0 00unds, based en a current percentage estica:e 2. provided by the airp:r: manager. I t L 'T j O. P7f p.e 6 -- 5-A-1 -2 's t..,D - U.'ti T 7 c ,7 :.::. t.* f r. a

n.. t d I 5 i xm t. :.- -.,, u-., nCLs. . m.. .o- ..CNTMLY GPFRATING rep 0RT Routine reccrts of Operating statistics and shutdown ex er'ence 5.9.l.6 shall be submitted en a monthly basis to the Office of Inspecticn and

20555, Enforcement, U.S. f'. lear Regulatory C =issien, Washingt:n, D.C.

with a cc:y to the Regional Office.'e+. ~~... '... i.- ".-:.. ..... a _; a. .......~....,.,. ;. nem-, a c .- ~.,. \\ ... u Ii .:.c;,.... OCcn R:.,dC:- aime.: en s The RE. 0RTA3LE CCCURRENCES cf Specificatiens 5.9.1.S and 5.g.l.g, 0 including carrective ac icns and measures to prevent recturrence, shall be 5.g.l.7 Supplemental reports may be requirtd to fully describe reported to the NRC. final resolution of cccurrence..In case af c rrected or su a licensee 2 vent report shall be cc. pleted and reference shall be made to the criginal report date.

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r. o a ou The types of events listed belcw shall be reported within 24 h:urs by telechene and confirmed by telegraph, mailgram, or fe.~" mile 5.g.l.S transnissien to the Director of the Regional Office, or his des enate day fcil: wing the event, with a wri-ten M2 1, no later than the first workin: The written folicwup reper: s,all- ~~"--~6T'i~f up repe r: w1:ni n# ~ include, as a minimum, a ccc:leted cc:y of a licensee event report farm. gM' .wr 1 s...,,il

w. s L,, a, _

w 7, 2. __,. 4. n....m. 2,.;. ...... 11 con., ev3.n. r,,. .s s e mented, as needed, by additi:nal nar-a:ive caterial to provide c mplete ...n r. ho-e x.y-_ m-... o, ,.1 ,. os.sur..,...a .- gs.o.Lut iWM me. KP.Qv ptuocT5 r d G.wLA:t:rq G vh's /, /. . w..

1.,

=.v.n v. 4 .w. =, p 6., 2.1 n,m, ..2... W. ,voT:_f, S De S.t . a: lure of the reector protecticn systam or other systems ~ to lhiting safety syste1 settings to initia a the 4 _u h '- A.9 ? W a. 'I subjec: w., '.4.....= a r.~- u< '.. =. d. -=. =.. r 3.r u :. r. ,,.,...,.. j y. e. n o .4. ....y

s...

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1. . i a. d 4

s,vs'.=a s =. r.'.'. g i a- '. ". a * * ".".. i v- ', l S r = ". i '. '. ". = ~.'. ^.. s c ~. '. = 4.1 u -=. w. to complate tne required protective function. o Operation of the ' unit or affected systems when any para eter b. or c:eraticn subject to a limiting conditica for cperati:n is less conserva:ive than the least c nservative as:ect of the e s *.= k i i s "..ad. i.". '.. ".. = ' =. e. o".. 4. c.2 'i 3 :n. 1 t. g c -, d. 4. * '. n

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s..

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i. t. J e ACPI tISTU,TI'!~ CCFRCLS l Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady stata conditiens d. .~ during pcwer cperaticn greater than er equal to 1% ak/k; a i calculated reactivity balance i'ndicating a SH tiens; short-term reactivity increases that ccrrespond to su:cri tical, nan a secen s or, it s a react:r period or. less t.an unplanned reactivity it:sertien cccurrence of any unplanned criticality. Failure er calfunction of cne or more cc=ponents which preven or could prevent, by i.tself, the fulfillment e. n t ~ in the S ~ W A g Personnel errce er precedural inadequacy which prevents o prevent, by itself, the fulfillcent c* the functional require-f. ments of systems required to c:pe witn accidents analyzed in 'g the.t:::*. pg,p, q, a Conditiens arising frc= natural cr man 7 ade events that, as a f direct result of the event recuire M shutd wn, operation g. of safety systems, cr cther protective measures required by technical specificaticns. Errers disc:vered in the transient er accident analyses er in F5/d the methcds used for such analyses as desc h. that have or could have parmitted reacter cperation in a canner K_._ less c:nserative than assumed in the avaNes / ]./ rM l I t ~ i Perfer ance of structures, systams, er cccccy. s that requires remedial act.cn cr ccrrective measures 00jrevent cperaticn 1. in a mar.er less conservative than assuced in tne accicen:or tec ,,, 3 j c!M analyses in tne ?. + _. _. _, __ 2 life of ccnditiens not s duri nc.r.J ;.r. -n -ehi i/d tions bases; or discover ~y specifically ccnsidered in the h_g. technical specifications that require remedi unsafe condition. -n --

h.., _,,;,.,.(,, 3... -,1 s. r exit

,.. i i 3 :.1 The ty;es of events listed beicw shall be the subject of wr ini. t 6. 9.1.9 Fice within thirty days Of

reports to the Directcr cf the Regicral G i

l ~ r ~ s, ,. e. - m n. 'l t:' * (" m A.-17

m...e..r_:_

'i n. : ' 5 LOO - U ttIT ~ i

l J 4 _i...a,. a e w. /: C u, ,...u,.5 Occurrence of the event. The written report anall incNde, as a minimum, a completed c:py of a licensee even repcrt for. Infamaticn provided on the licensee event report form snall be suNiemented, as needed, by additional narrative inaterial to crevide cc.;plete. explanation of the circumstances surrounding the event. TH F. 6AM tTc<ty NOT=5. 8:Qor.t a.wec a. Reactor protecticn syste ar engineered safety feature instru-ment settings which are fcund to be less conservative than these established by tne technical specificaticns but which do not pre /ent the fulfillment of the functicnal requirements of affected systams. b. Conditiens leading to cperation in a degraisd mcde pemitted by a limiting ccccitica for 0;:eratien orpa-a shutd quired by a limiting c:ndition far operatiorh y g*wn re-g c. Cbserved ir. adequacies in the implementaticn of administrativa or procedural centrais which threaten to cause reduction of degree of redundancy provided in reactor protectica systems or engineered safety feature systems. d. Ab :cr71 degradation of systems other than those specified in 6.9.1.5.c above designed t: c ntain radicactive cateri'al ., e w_,. u. m.

e...... =

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c

m..::.....r

.:_:. e d. 3-5.9.2 Special rep:r:s shall be submitted to the Director of the Cffice '

Of :.specticn and Erf:r:emen Regicnal Office within the time period s;ecified for each re::rt. These repcrts shall'he submitted covering One activites iden:ified belcw pursuan: to the requirements of the ap-Ol':able reference specification: a. ECC5 Actuaticn, Scecifications 3.5.2 and 3.5.3. b. Incterable Seismic fionitoring Instrumentation, Specification

3..3.2.

c. Inc erable itetecrological Monit ring Instrumentatien, 5:ecifi-cation .3.. oa tT2.e c.T. V E. R _ _ Cir_ t.] ,. M C.,. I v-g L e b t-t m., 5 h'~ - 4. ..,f .Ic., l 9 P c. m O t c. -. c_. ...c -. 5 4' c~.4. p u,.. o, n y. s. ..,n,,7. . i. =. 1, r c. r It r t C l Tiba'- -2 fTH.EE'iILEISLA.';D-U: LIT 2 6-13 g,1 - M AUG'.7 EU

i ~ .I t ~ L 2

r. r.n.. i e &.3 ; M r* 6 1 e,.

,-.~.C, 2 LL iI i 6.9 RE:0RTI.';G RECUI:EME'iTS (Continued) p,[. Seismic event analysis, Speci.fication 4.3.3.3.2. < 10

c..eCn o.D c..r : : h T. c..1

'.10.1 The failcwing records shall be retained for at least five years: U n.._. \\\\ a. Records and legs of '__.' '..- cperation ccvering tica interval at each pcwer level. b. Records and legs of principal mainten'ance activities, inscections, l repair and reclacement of principal items of equipment relatec to nuclear safety. l c. ALL REFCOTA3LE OCCURRE.';CES submitted to the Cc==ission. d. Reccrds of surveillance activities, ins;ecticns and calibraticns required by these Technical Scacifications. NOdLEM SAM [ REL/pTC e. Records of changes made t:30p2 rating Frecedures. A f. Records of radicactive shi;=ents. g. Records cf sealed scurce and fission detector leak tests and resuic:. h. Records cf a. mual physical inventcry of all sea 7 =d scurce material of record. 5.1C.2 The failcuing records shall be retained fer the duraticn af the r - Operating License: b, M t i a. Records and drawing changes reflecting facility de"gn modi fi-caticns made to systems and equipment described in cne Final Safety Analysis Report. b. Records of raw and irradiated fuel inventary, fuel transfers and assembly burnup histories, c~1 m 10 N. ~ c. Records of A._.' W radiation and con 2=inatica surveys. d. Records of radiation expcsure for.11 individu11; entering radiation control areas. e 9-q $ % e.q s o 43 ..; 0 7 0 s.10 7 0.r*.s*s U _ u-m I "e s * *I

. 'L q e

4. J L c. u

9 2 ,, u.u. r. y. T. c., :. 7 s."o :- CF'.;T..r' S Records nf gasecus and liquid radicactive materiel released to e. U>> I T the envircns. ' ~ 17 Records of transient of c~erational cycles for those f: ccmponents identified in Table 5.7-1. f. / Records of reactor tests and experiments. g. Reccrds cf training and qualification for current members of h. the s' =4 staff. Records of in-service inspecticns performed pursuant tc thess sTe?dcN .ecnnicai spect ricatiens. O R A F L.4 H i. s Records of Quality Assurance activities required by the fpr j. Reccrds of reviews performed for changes made to precedures 10 ecui; ment or reviews of tests and expericants pursuant to k. CFR 50.59. QRC l Recc-Is of meetings of the FORC and the (4LFt. i 1. I -.,....,, -.u a :... v. I ? 7..c. a rs.., 1 neu tn t.u.* rr d ccnsistent c.1 Precedures for perscrnel radiaticn protection shall be prepare cved, maintained wi-h the requirements rf 10 CFR Parc 20 and shall be appr diatica ex;csure. and adhered to for ali c;erations involving perscnnel ra i .,i a H.,.;,. D.... -,I...w,.

u. i m, t.

m.. ro In lieu cf the "centrol device" or " alarm signal" recui ed by hich paragraph 20.202(c)(2) of 10 CFR 20, each high radiacicn ar

> 5.12.1 !theintensityofradiationisICCOcrem/hrorlesss P e rmi c*. shall be contrclied by requiring issuance of a Radiaticn 'Jork Any individual er grcue of individuals permitcad to enter such a failcwing : shall be pecvided witn or accccpanied 17 cr.e or more of tne A radiation acnitoring device which continucusly indicates radiation dose rata in che area. a. ie 'healta Pnysics pe?scnnel shall be exempt from the R'i? issuance i

ection ment during the pc efccmance of their assigned peccecures for entry in

o high radiaticr areas.

n n 1 iy d 'g 13 I ' f>7 7 I

1. ~ ~'

f 5-20 l;! THREE MILE ISLA10 - U.!IT 2

A?!INISTCATIVE CCNT:CLS b. A radiation monitoring device which c:ntinuously integrates the radiation dose rate in the area and alarr.s when a preset inte-grated dose is received. Entry int such areas with this monitoring device may be made after the dcsa rate level in the area has besa established and personnel have been cade knowl-edgeabi e of them, c. An individual cualified in radiatica pr:tection procedures wn: is equipped with a radiation dose rate c:nitoring device. This individual shall be responsible f r providing positiva contr:1 cver the activities within the area and shall perf m periodic radia:icn surveillance at the frequency scecified by the facility Health Physicist in the P.adiation ' ork Pemi. J 5.12.2 The requiremnts of 6.12.1, above, shall also apply to each high radiaticn area in whic. the intensity of radiation is greater than 1000 cre:/hr. In additica, locked d: Ors shall be provided to prevent unauthcrized entry int: such areas and the keys shall be maintained ur.dar the administrative con rcl of the Shift Supervisor en duty and/cr

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