ML20134L995

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Forwards Microfiche of 850612 Submittal Re Annual Rept of Facility Changes & Relief & Safety Valve Failures & Changes
ML20134L995
Person / Time
Site: Maine Yankee
Issue date: 07/18/1985
From: Whittier G
Maine Yankee
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
6204L-RMN, GDW-85-204, MN-85-138, NUDOCS 8509030497
Download: ML20134L995 (1)
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EDISON DRIVE MAIRE HARHEE ATOMICPOWERCOMPARUe suausra,urluE oaa3e (207) 623-3521 O

July 18, 1985 MN-85-138 GDW-85-204 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator

References:

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

( b) M(APCo. to USNRC Letter dated 06/12/85 (MN-85-ll6)

Subject:

Microfiche of the Annual Report of Facility Changes and Relief and Safety Valve Failures and Challenges Gentlemen:

Enclosed please find a master microfiche of our submittal noted in Reference (b).

Very truly yours, MAINE YANKEE ATOMIC POWER COWANY G. D. Whittier, Manager Nuclear Engineering & Licensing s GDW/plb

Enclosure:

cc: Mr. Edward J. Butcher, Jr.

Mr. Cornelius F. Holden 8509030497 850718 PDR ADOCK 05000309 R PDR fick

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631 :ss Aven_e King of Pruss;a, ^e~.s;.h a'ia 19406 A::er. icn:  ::. Tnomas E. Murley, ;e; ions. ACT,inistrator F.eferences: .a) _icense No. OPR-36 (Doc <et No. 50-309)

Suoject: Annual Report of Facility C anges anc fielief and Safety valve Failures anc Challenges Gentlemen:

In accorca ce witn 10 CFR 50.59, atta:ne:: clease fino a report containing a brief descri:: ion of the facility carnges ecmpleted at tne Maine Yankee Atomic Power C:many plant curing 1964 In lieu of 39 copies required by 10 CFR 50.59, a master microfiche of tnis su mittal will be provided under separate cover.

There were no relief and safety valve failures or challenges during 1984.

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Very truly yours, MAItE YAtKEE ATOMIC P0iER COWANY hhW G. D. Whittier, Manager Nuclear Engineering & Licensing GDw/ojp Attachments: Amual Report of Facility Changes (91 Pages) cc: Mr. James R. Miller Mr. Cornelius F. Holden Mr. James Taylor, Director, I & E Washington 57841.-FWS

va:sc ..s.cc a u e,: . ,u croa.s, I'GX TO DESIC, n:-:23ES C: 4'Li!E: :N Ich DA 25-61 Rercate EV-1 and 2 :e ief Lines c '" nry ,'ent S ack PA 27-82 Auxiliary Steam r:c ,r: 33a.3:n y , ;,.;

PA 35-52 C-A1A, 9, i C After: :le: 0: air N ;i'itati:n PA 3-83 Refurcisnment of :efueli^; 'G: . e PA 4-83 Circdiating eater 5:a;nless Ste d Per:ac P! sing Replacement ,

with PVC Ploing PA 11-63 Containment %rge Exnaast Room ;30iatic9 Sniela Door PA 14-G3 Hycr:;en Purity Instrumentatic e:la:e ent PA 18-83 SFP Ceep Sec Filter Timer PA 22-63 Staff BJilding Jncervoltage Tri:

PA 23-83 Uninterruotable Po er Sucaly *.o FEACO PA 25-83 Reactor Trip / Turbine Trip Reduncancy PA 27-93 Indeoendent Operation of Containment Sum Pumos PA 28-83 NNS Instrumentation Multiplexer PA 30-83 Alarm for TCB-9 or RPS Panel PA 33-S3 Separation of well Water and Domestic water Systems PDCR 11-82 Replacement of Containment Electrical Penetration E-2 and E-11 PIER 15-82 Replacement of Safaety Related Limitorque Motors PDCR 22-82 Manual Operator for MS-T-163

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PCER 4-83 Emergency MCC Feeder Remote Indicator Lights PDCR 5-83 Limitoroue Motor Splice Upgrade PDCR 6-83 Modification of Housing Interlocks - tPSI, LPSI, and Containment Spray Pungs PDCR 7-83 Personnel Airlock 0-Ring Retention Modification EOCR 79-36 Ground Detection System for DC and Vital-AC Busses EDCR 80-50 Grid Undervoltage Protection EOCP 81-11 Mitigation of Harsh Envirornent i

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L va st = asa ct 4 :- c *ca t a revaas-EDCR 51-18 ReplaceTent of Safety a e :a:ec Te: na; S;ocks EDCR S2-31 Decris Screens fc: 2cotairent Air 5 :. an: carge Exnaast Lines i

EDCR S3-09 Accendix R Mccift:3tions EDCR 63-18 Feecaater Sprinc Cans ECCR 83-20 Pressurizer Safety Relief salve ; icing v:dification EDCR 83-22 'i?-D2 Suoport uccificatic.s ETR 53-24 Capa::llity of Main Steam miring t0 H0ld n: iter EDCR 83-28 Concensate Surge Tank Sys:em ELER 83-29 Auxiliary Feedaater Syste- Modifications EDCR 83-32 Inadecuate Cr-a Cooling M:nitoring System ECCR 83-500 Isopnase Bus upgrade EDCR 83-501 Containment Hi Range Rad Manitor Cable Swap EECR 83-5(4 Elimination of "lSH" Interlock EDCR 83-509 Main Steam Non-Return talves Vacuum Assist System EDCR 83-512 Motor Oriven Feed Pump Recirculation System EDCR 83-513 Main Turbine /P-2C Trip Interlock E,ypass EDCR 83-514 ICI Cable Upgrade EDCR S3-515 AFW Seismic Upgrade EDCR 83-517 Condenstate Overboard Disenarge Line Check Valve EDCR 83-518 Steam Generator Chem Feed Line Penetration Isolation

'ECER 83-519 Feedwater Pipe Arrangement Modification EDCR 83-520 Removal of' AFW-1 Internals E[CR 83-527 MSR Tube Bundle Replacement EOCR 83-529 Modification to Reactor vessel Closure Head Lift Rig ECCR 83-530 Waste Oil Pung - Trip on High Tank Level CDCR 83-531 Auto Close of FW-M-336 on P-2C Trip

MasNE V ANNEC a Tc w : 00 4 tR COvsa%

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ECCR 83-533 Ad::ition of an !r Sar: L. 'ut.c, Near :L,tairent Personnel Hatto EDCR 83-534 Traveling aate: Screen ..::: sic- N ;;3ation I m rove ents EDCR 84-02 Qualified Level Tra s-itters f or :entai wnt Samp Indication EDCR 84-04 Performa- >

Instrumentati: up; race ECCR 84-06 Reroute Scavenging Vent tt Ulrst Doint Heaters EDCR 84-08 m alfication to Stea- Generate: Prinry vanaay Gasket Retainer Plates EOCR 84-09 Less of 115</ voltage Alar-ECCR 84-10 P-2C Low Suction Pressure Trip Tine Delay EDCR 84-13 Containment Personnel Haten Irrrovements ECCR 84-14 Charging System Flow Restrictcr for LTCP Concerns EDCR 84-15 Steam Generator Wet Lay-up Recirculation System Taps EDCR 84-16 Main and Auxiliary Feeonater arid Main Steam Isolation Bypass Annunciation EDCR 84-19 Steam Dtsnp Controller Output Test Feature EDCR 84-20 Main Steam Quality Measurement EDCR 84-21 Condensate /FW/CW Instrumentation Upgrade ECCR 84-23 PORV Block Valve Motor Operator Replacement EDCR 84-24 Feplace Tenperature Switches on C-5A & B EDCR 84-26 First Point Heater Vent Recairs EDCR 84-27 H.P. Turbine Moisture P:"e-Separation EDCR 84-28 Jib Crane Mounting Reactor Containment El. 46' EDCR 84-30 S/G Separator Can Replacement EDCR 84-31 Addition of Locking Device to Polar Crane EDCR 84-32 Loose Parts / Thermal Shield Monitoring System Upgrade ECCR 84-36 Steam Oenerator Secondary Hanmole Cover Thermowell EDCR 84-38 Check Valve Installation in Water Treatment Line EDCR 84-39 S/G Secondary Hanmole RTO's 5669L-FWS

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ECCR P4-ll H.F. Containment ParaTeters Relocation I,

ECCR 64-12 HI, Wice Range Log Recorcer Reclacewnt 5669L-FWS

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. a-51 installec a crcss-esaneet lir.e, cance; ting tne relief lines from the evascrators, EV-! ana EV-2, aitn ine line leasing from the Slowdown Tank, T<-15, to tne primar;. vent Stack. Tne ner"al disenarge froT. the evacorator relief valves, shoulo an overcressurizaticn concition occur, is to TK-18. The ne. cross-connect line provices an alterna e floapatn so tnst tne Slowdown Tanx can ce isolated for maintenance or inspections and any disenarge from tne 4

evaporators during tnis period wi.11 be directed to the Vent Stack. This cesign enange was imolemented to ensure proper safety for tnase personnel performing tank maintenance.

t The system modified is non-nuclear safety class. This modification does not alter the function of the avaporator relief line nor does it alter the function or operability of any other existing plant system. Additionally, ,

this plant alteration does not create an unreviewed safety question as defined by 10 CFR 50.59.

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3/ 5: -eacer 4, _. :2 in :'.ve; tne a::itien of a ne. ac<ilier, steam su::1y line from the

~2" 11ef sal'.e line fer ".SR's A 4 9 to tne exis:ing auxiliary steam haa0er.

7,e neal. ins:al'.e: e ir , line incorr.::stes a e- :: essure control valve anien is con::allec tn:cza s lit rangin; aitn - e esisiti,e auxiliary steam sa:aly .alve to alloa -: tur01 e exnaus steam :: sanolv all vie r t t xiliary stea., demanos aoove accraximately e5-024 clant ::.er level. This ecdification aas installed tc increase plant out;_t oy acorcri ately 125: <w (assuming auxiliary steam fica of 60,003 lom/Hr. and hign :: essure turoine efficiency of 81%).

All co.mponents of tnis oesign change are classified as non-nuclear safety class. This alteration does not involve any unrevieaec sa'ety question as cefinec by 10 CFR 50.59.

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.,  :, anc : ; ' e .- ~ ~ . . - . ;n i gion 34 .' .-E2 re ;.ed tre scle 010 c;eratec cc,. salv .s # 39 t9e service and instra'en: dir co Uressor afteraccier; and replaced tne? .ith Dall float traps 2,0 lese ;a.:;es. - is enan;e .as to e.lo slow steae. crainin; of tne system aitn eininal air loss ana to alica visual verification of concensate level, T,is cnange =as to a system anien is non-nue; ear safety class. This I

a'.teration does not constitute an unrevie e: safety question as defined by 10 j CFR 50.59.

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.a e..s c. . .' .' .i s* y a nd s;ee: of c?erati:n ; ring refueling.

ve nanical imprc.erents were made to faci.ita:e Taintenance, im;reve ce::nta-i ation of n;ist assemoly shim ;;ates. a:0ed a vieaing ainco=, a new electronic based c0n'.rci console, genera; re',rcisnment of me structure, new receanle TV camera system, and state-of- ne. art m0tcr drives. This alteration "0es not involve an tinrevieaec sa'aty Ouestion as Oefined by 10 CFR 50.59.

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'nis s'.teration invches replacin; tne existi g scheoale 10 stainless steel cipi,g on tne circulating water Acertaa Sy;te witn ov^ cising. 7ne change aas necessitatec cy corrosion of tne stainless cicing.

rne cir ulating water Mertap System is ncn-nu ' ear safety class. Tne reciacewn; of tne pi;ing did not affect tne Operation of any otner plant system. Therefore, tnis alteration coes not involve an unreviewed safety question as defined oy 10 CFR 50.59.

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- r e . 0.5 '. ;*.e SJui. ;3!. #ee puTO anC CC:M 3i1 Pent curge ex9aJst rooms were int e rCO', .;;t e: Ov an 00e* ?3ssagea3y. ~ i"Ce tne Containment at30sDnere essentil.., este905 int: tne purge root t".r .39 ine ve9til501Cn du0t work UO

One .::atic, of tne first isolation .a1.es, Sc A-3 anc c, ra:iation levels in this area 'f.lcaing an accicent Oca'. s e tne Dam rco- inaccessible.

"caever, the reno room mast remain a:cessiale as varicus post a:01 cent valving scerati:ns are serf ar.ne: frar, tnis area, i.e., aligning RCS not leg injection,

,yeragen recomoing, ana contairment our;e/nycrogen control systems.

PA-11-63 installed a slicing radiation shield ocar to isolate the auxiliary feed pamo room from tne containment purge exhaust room following an accident to ensure that tne hacitaDility of tnis area is maintained.

This plant alteration does not adversely affect existing plant systems or components. The snield door was inrtalled solely to provide radiation protection for personnel in tne unlikely event of a major acetcent. Since the coor is large in size and is located in an area near existing safety class equipment, tne door was seismically nounted to ensure that a failure does not occur, wnich could damage vital station components. This alteration does not constitute an unreviewed safety questinn as defined in 10 CFR 50.57.

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_.,...-n, 4,2:a..z *urity ' :_r v :3:ic- :erlacement P . - -: 'a e0 tne 0::50lete, techaa.i;51 *y : ;en ?Jrity meter for the main genera :: . a state-c'-tne-art electrcnic system. This enhanced aintal a:.. y anc rc '.iacility as we'l as im:rovin; coeration.

ine ;enera :: nycro en monitoring syster is non-L: lear safety class. The acility to nonitor gererator fill gas was enhancer, no other plant systems

.ere affected. There' re, tnis enange cces not ir.volve an unreviewed safety caestion as cefined oy 10 CFR 50.59.

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rL-55, 51, S2). inis timer ,<eers a rur .; :ota' of filter usage time to c.

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crtions of tne filter. No cont cl function is prJvi ed by tre timer.

Nereiere, this enange coes not involve an u .:evie.ec safety caestion as

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... :ing feecer Crea' <er when bus 3 uncerv:ltage accurs. Tne cre3<er aill Oe re Osed after tne voltage has been restore 0. Inis eliTinates u ,ecessary Icac: *9en voltage is low. This plant )

alteration 0:es not in/Olve a7 unreviene: Safety CJestion as defined by j

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cl-E' : .an;ec tn. :: er sa 0;y for t e : an ps;ing sjs*.e?. to a more re;ia ;e suoply tc assure continuec ope:ation anc asaliaci.ity. By enanging

a cif'crent oatters-cacked inverter : er suo;;y, crevi:; sly encountered er interruptions aue to bas s=it:ning caring c ta;es wi;; be eliminated.

7nis s' teration coes not involve an unresieae: sa'e y cuest;un as defined by r.eR ,v.

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. -5? i .;rc.e0 tre re;iaDility of tur:19 trip in the event of a reactor trip.

'nis enange pro. ices for a se:arate and ince encent means of tripping One rsi- turcine on CE3v bus uncerva; age. Tnis :hange aces not involve an unrev'.eaed safety caestion as definec by 10 CrR 50.59.

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p. . ;-1.2 : 1 E. It is now possiale for contre; room operators to run either
:U 3am saics as desirec. Tne 10 ;evel c;r auto-stc: ' unction remains ini x , as coes tne ma.,ual overrice of :ne 10 :e.e' pamp catout. This enange es .at invo've an unrevie.ec safety ::aestion at :efined cy 10 CrF< 50.59.

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..:.cleser s .- ' i stalle; a ren::ely c:erate; si; 31 se;e:to- in containment with its

v.rc; u-i: in :ne control roce.. Inis alicas ore of sixty four input signals
ce ele:te #:r monitoring. using c,;, one ca:;e and electrical renetrati:,. :: is not to te usac for con:rci si;nals nor 'or safety class instru en ::ica. It is not to te usea 'cr cen in;oas;y Sonittred NNS instrumentation, ncr 'cr any signal inportant co ; .. Oceration or safety.

Tne multi:lexer is non-nuclear sa'ety class and is mounted away from any safety class equipm.ent. Tnis alteration coes not involve an unreviewed safety question as definec in 10 CDR 50.59.

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-- .jicle alar- as reen a e: tc tne c?S :-1:cring panel to incicate the  !

c:ening of T:5-9 s tie trea<er f or 'C-14 i E . Tnis alarm sneala make the l c era:::s a.are ;,at :ne t=0 m.ctcr-ceneratcr sets could ce operating in a I no .-syncnronous :ce. inis enange 1*cr;ves t e ionitoring ca;;acility for j

i. :::an elt.:tr. cal eaairment. It c;es n:: i sclve an unrevie ed safety 1

c_estion as cefinec cy 10 CFR 50.59.

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' ell aater and C:~.esti: aater systens. As a result, ea:n afstet is naa totally cedicated to serving a S:ecific plant site water

ecaire er.t. Tne C:cestic water sa; lies flushes, s"caers, wasn basins anc 19e atl. 3:er suc; lies all the pota::le water fixtures.

soth of tne aa*.er systems affecte Dy tnis PL are non nuclear safety Class.

Tnis Onan;es coes not involve an unrevieaed safety question as cefined by 10 CFR 50.59.

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ve: rations for tre control elenent cri.c 3ranisn fans =ere replaced s nce i j carts are ns lar;er avallaole for tne ;re.iously installed penetrations. The i ne cenetratic s are eauivalent reciacerent c' an existing component. This enange caes not in. ive an onrevieaed Safety cuestion as defined Dy 10 CFR

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c- casign cr.a9;e inv31.ed tne m0 Or re;13:ement of six sa'ety related Limit :;ae actcr C;.3rators. The six rcters aere replacec .ith radiation l

{ exposare-;aalified direct re::lacements as cart of Maine Yankee's Commitment to environmental cualification of safety relate; electrical ecui;: rent per I&E Salletin 79-015.

Tnis mocification ci:: not involve an unreviewed sa'ety question as defined by 10 CFR 50.59.

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. 'G T-163 to prosice manual caerati,g cacaci'.ity. 95-T-163 is a CIL'5:AS, air oceratec isolation valve to

e t r;i e criven au 111ary feed.ater ;u r ( TDA~P) . :gring a total station
lac : , MS-T-;C .1-. renain open fcr an esti,s:eo ':ar naars (until the air accuNiator ledes ,nessur6) . witn tnc Tanual na^ca" eel tha valve can be caenec and sceam can ce fed to the TN o , snaald the need arise. Steam press re for the ~3A m can ce regulatec oy tne hanawheel on US o-168 located aann stream from 45-T-163.

The nanc *1 eel will normally be in tne neutral position anc locked. Thus the normal functon of the valve will not be altered. This change does not involve an unreviewed safety g;estion as per 10 CFR 50.59.

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c cer: rsuc ~72icr_n Lig"ts

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contrel ccarc. inese lig-ts incicate tne pcsitions of tne feeder Dreakers f r:e n;sses 7 and 9 to NC 's 7A, 75, el., 65. This trovides useful indicati0n of NCC reasiness status in tne cont:ci room.

Sa'ety class parts were Inis enange does involve a safety class systen.

utilized anc seismic ac:e:tacility of co conent mounting nas been assured. j Tnis enange does not inv vie an unrevie.ed sa'ety cuestion aa defined by IC CFR 50.59.

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...; .:li:es :: s: e _imi::ra ce c;erators were reclace: with environmentally

all .e: s ll:es. inis :nange is a cirect repla:ement of existing eculpment ai:n
  • n:tiona;.. es ..aier: out envircn entall., cas;ifiec eculoment. This al e:ation coes r:: in . :. . :: an unrevie ec saf et caestion as defined by 10 CrR

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p  :->

.. i :ne :: anin; : ___

. 9 5:, _P5; anc a rcs cotaince : :2 encer :I4 6 -? tne nousi,; interlock fer :ne nigh pressure safety injection

( :5: . .:. pressure sa'e* , injection (;;E:), anc containne, spray pumo (C P )

r3.e :ee acaifiec :; a.;o the use of a ;rcan tru:.< in an inoperaole cump caci:.e aitnaat disrli g its respe::i.e scare cana. Aeloca:ing and replacing

ne i'terlock s.: .cn a.;o.s tne spare u e te c erate if tne A or E pur.0 cuoicle nas a grounc track anc tne eleva:i,g meenanism is rackea up. This PCCR i croves tne reliaci:,ity of the +5:, LPSI, and containnent soray pump power suoplies and, tnerefore, does not involve an unrevie ed safety cuestion as cefined by 10 CFR 50.59.

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va sr va u arc e:c -c.sc. os.cs ,

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'ica
icn .wolvec :ne acciti:_n of 3,12' fille: . ire on tne cater edge a' :u :.ri^; grco.'es c, : e inner aan cu:er 00::s of :ne personnel airlock.

rme aire ...; n21: t,e c-:. gs in cla:e . ore fir-1. anc :nas reca:e

. .o .,_.,,.a-s,..

L, s :n3nge increase: tne :ellatility and recace: :ne ainter.ance on the persanre; air lock. The airlock is a Safety Class 2 contain ent isolation be.,ca ry . This mo:ificati:n did not involve an unrevie-ed safety cuestion as cefine: in 10 CrR 50.59.

5669L-FWS i

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  • A N
  • E E A T C A* C s. O W E R C o v e A n, y

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  • Crc,. '_ : t e;t .cn 5. stem ' ~ X = ; .i:a; A; Basses 4 .:p irr: an:e ;;rcan: cetection syste a3s installe: uncer EOCR 79-36 in the

' ?.S D: cus. Tre syste .ill ce activate; and evaluatec Defere a similar systen is insta;1ec in tne safety class Desses. This 00es not involve an crevie-ec safety c estion as cefined oy 10 CrR 50.59.

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u* se -as u o 4 :,u.: .o c cou.is, E T. 9 c'c.

Cria uncerv:'ta;e -: .e:tien

' u ; : nan;e u;; race tne uncervaltage :::c;e: tion for .:.'E valt safeguard t sses. 'ne sys;e: =111 alarm on 10. volta;e. Coincicent witn SIAS, the bus

_11 ce s.: he 03 tre e ergency ciese;s. r nis enan;e ::es not involve an unrevieae: safety cuestion as cefinec cy 1: :r, 50.59.

O E9L-FWS

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I vi. igation of cr- E ',i: anment t

4 iE L.;r.in No. U-T.5 rea; ires tnat a nip energy line creak (HELe) outside contaimen cust not rescit in an envircoment capable of causing failure of cafety :;sts electri:al c;iprent.

EDC; el-11 mocifiec tnree nign energy oiping systems. Ne modi'ication provices aatomatic isolation of tne auxiliary steam, clowcoan, and letdown systens anen a hign amoient temerature is sensed by tne Air Tencerature wonitoring System (ATM5). The ATMS ooserves the ambient temperature at various :lant locations and initiates a trip signal to close isolation valves following a H3.0, tnereDy, ensuring the harsh envirCnment is short term and

{

j operability of vital electrical equipment is not compromised. .

1 The modifications performed on the letcown ano olowdown systems are safety class 1 and 2, respectively, and tne auxiliary steam system enanges are non-nuclear safety class. Tnis change igroves the reliability of both safety related and non-safety related systems. This change does not create an unreviewed safety question as defined by 10 CFR 50.59.

4 56691.-Fw5 ,

wast y ANMEE A -V:C PC WER t Ov8 aNv

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...e~nt af Sa'e: . k ..;;e; er-!nal 3;oc.<s I .E. ;_. .eti ~3-C' 5, "E . ircreenta'. Lalification of Class 1E E:;ipmenta, re: ires taa; 2.. eauipmnt in safety relate: systems sAject to narsn environments :s cualifie: to tnat e,virennent. rme safety-related terminal cle:<s insice tne ;eac*.0: Contaiment lac.<eJ an. cualification c::uNrntation an: aere res'.a:ed aitn aeianuller-tf or ensiren : . tally qualified terminal clo c.<s . Tnis ccification does not preseiit an unreviewed safety cuestion as cefime: in lo ~'R 50. 59.

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.: .tssei c<.' - 1 :: "cnitor

_C; :; -.' i stalled a cc73x cual 40 in a t"er caell on the Reactcr head.

Carlin;; aas accac to connect the RTD tn:cogn ;cntainment penetrations and lance: cn termi'al alc ks in the vain Co trol Board. N e caules, ccnnectors an: cual ;TO are all Class lE. Future ECCRs .ill utilize 071s modification to provice tne actua' indications fc: R.V. Hea: te ac:sture on the pain Control Boarc. Inis modification did not involve an unrevie ec safety q.estion as cefinec in 10 CFR 50.59.

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"' N E ' A N a C C A TC uiC DO W E R C owraNv c_ ..i . . .

.. , 'n  : n aio:c ': .: *g.. r 1 ;.:ge Ev.naast Lines I J.T. ins:a'.;ec cerris scree's in tv> cc-:ain e- curge s.031y and ei ::;st ; iring systers ta :: event :ne reste ::ssici'.ity of decris being blown int: tne DJrce liner. :ari~ a LC event. Tnis cerris could orevent the isc.ation ulves f rce fully clocing an: consec.ent;> 'siling to seal the annin ent Building snoul: cn-line our;e te i cre;:ess ::in:icent ita a Less of Ccolant Accicent.

Tnis cesign :nange is saf ety class 2 as the ou ge su::ly cecris screen is attached to the containment pressure t,cendary. The aceration of the purge supply and exnaust system is not affected oy tne cha ge. This EDCR does not constitute an unreviewed safety question as defined in 10 CFR 50.59.

O SM9L-FWS

waiNE v asact a y0M8C POWER COMPANY l

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EDC i 53-t M , E , a ^

Annencis R v:Sifi:ati:ns

-is cesign cran;e corsisted of nocificatic^s te meet Maine YaNee's crit ent to the rea;irements of 10 CF,7 50 Opendix 9. These modifications i.:1uce: t,e ro llo ing: 1

1. ine installation of an alternate s tcoan po er suaaly consisting of a 230 KV diesel generator, a 480V n:ter control center, ano 125V DC station battery and battery enarger, and a 2KVA inverter.
2. The installation of an alternate shutdown canel to replace the existing steam generator emergency panel in the Auxiliary Feedwater Pum Room.
3. The installation of all necessary process, instrumentation to develop the necessary parameters for the Alternate Shutdown Panel.
4. The installation of all necessary alternate pung and valve control circuits to allow control from the Alternate Shutdown Panel.
5. The installation of all necessary fire barrier material to separate normal and alternate shutdown system.

This modification did not involve an unreviewed safety guestion as defined in 10 CFR 50.59.

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I i: 4 ~. 33-15 ins c.,ec ine recla:enent SN/or resetting of six spring cans on the

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tr.r ee 'eecaater lines i.' tne c.3in stear valve house. Tne supports affected by trit cesign nange are ;;cated .Ithin the Safety C;6ss 2 bouncaries on the fee:aater lines. Tne accificatic tc tne six su;;;rts aas perfcr9ed to ensure nat tne suoports aill serve their inte,ded functic, ni .hout jeccardizing the cicir; system. Tnerefore, tnis cesign change does not involve an unrevie.ed safety cuestion as define:: of 10 CFR 50.59.

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-: u .;e: . z e:: Safety Re;ief s a. . . .;; ,; "o ification Ine 9, c aac :-eir inlet picing are Safet, c; ass 1. The modification

' 11';ed floa naracteristics nic7 icoreved stacility and thus incroved reliirility c' tre SRV's. inis mo:irication cid not involve an unrevie.ed safety cuestion as cefined ir 10 CFR 50.59.

mis mccification involved minimizing tne ;eng n of tne SRv inlet piping.

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i_:.' . , 2 i '. c h e tne ':Jificati;m Of Ses e:31 SJ0000tS C' 59' aral different safety C. ass Sy sters. ese modifi;ations are a result of analysis performed 1

.s.,,, c :...is o e . . . .

r

E 5...stin 79-C^ "33Serlate Flexibility Using Concrete Ex 3nsion :.rncr s" .

r-is cesign :na,ge ensures tnat tne mocif le: supports are ca:1 le of

er'orm.ing tneir intence
function. 7nis enange coes not invo;se an unre vicaec safety cuesti:n as define: oy 10 C R 50.59.

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i 9 i va sr a -tt s cu ;eratecoweas, i r: c - -

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. c...t. of "ar' ne3- i:.n; tc m;; aate:

_~._ . .acan ca:atility ':: A:pencix R conti;erations necessitates flowing

. ate:

.n tne steam generscrs to tne concenser via tne main steam piping.

t P.is cesign :nanae noc.'ie: three sua:crts en the main steam piping and two s.::::ts c , tne a rcssneric steam cam .ine in crcer f : tne main steam lines to +:e:;ately su;:::t static water leading. nis enange aces not involve an

.nrevie ed safety queston as cefined by 10 75 .50.59.

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_ 5669L-Fws - - - - - . ~ . - _ _ . _ - _ _ - _ _ . - _ __ _ __

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

MatNEwa%4EEATCw40* .N E st C O v P A N v EJ.R d7-13 i T

Ccncensate : m r < 2. stem EX, e!-;5 adced a CcNersate Surge ta%, 74-12:, to serve as surge volume for

,e w: .cary plant c .,censate cake;p and s::ill syste :. Tnis function was cerferred by tne Dai! but reennical Specification :evisions require that the

.Lasi ce isolatec f rom '.Ns systems cring clant co er c:eration. The exclusive -

foncticn of tne Casi, caring plant : wer operation, will ce to orovice storage ca:a:ity for ne safety class emergency feec.ater system.

EDCR 83-28 incluces a ,120,000 gallon stainless steel tank .ith concrete f founcation (ic:ated outcocrs),10" concensate oi::ing to ccaneet to existing j secondary concensate makeuo header, steam injection for tank heating, tank level . monitors, nign/ low level alaras, tencerature moniter, and required heat tracing. The new equipment is NNS but the tank is seismically designed to protect nearcy safety class pumps.

This modification igroves the safety design of the plant. This change does not involve an unreviewed safety Question as defined by 10 CFR 50.59.

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    • .c-a.n.n me..c.ce...s.
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r:r > ree:.3:er S. _ - :ifica:ians

. .: azi.;n c .a 2 ::ifie :ne Emrgency Frea ster s stem by a: ding an accitien a . isolatic, val.e in Jacn feea li e. Tne ne. .alves au:cmatically

se =~en a 10- cremre condition in tne valve-asse:iated steam generator is

.ense:. T e asso:icted E er;ency reecaster contro.'. salve also isolates on the a ,e 10. pressure signal. T ,e *.c valve isolation c arcs against a single a::ive failure caring 5'G oeoressurl:ation c aused by a main steam line break.

Tne val es will autenatically reopen upon restoration of S/G pressure.

Tne mocifications :erformed are safety class 3. This design enange enhances nuclear plant safety anc coes not constitute an unrevi ed safety cuestion as cefined in 10 CFR 50.59.

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w. c....u...,c:ar.~,..y

. ' T- .;:

- i '. rer...e; ~..

- an; PT-;;3 . : _ _:izer ;ressure chan.mels (M.5)

..; _4' :-25 0 psi; ;rtit Je trr ; .:t r = c'-;0.' an: 37-105, as part of a

vrizati:n Protection (LT3p)

_:r.rai t: ac::ess Lc Te cocrature v.fr;r

.:stians. Tne sic a's from these tr ar:-itters aere ea:n connecte: to their res:ecti.e contro'icr. The contro.e: set::i.: am ::: cess indication are cc: care: in crcer to a:tuate the POR.s i' :ne crc:ess is a::ve the setpoint.

7,e LTDP system is armed in tr.e varia ;r are:sare set:: int relief ;csition unser a:7.inistrative centrol. Tne t.o trains, ea:n naving a controller, rc:ess indication and separate digital setpoint indi:ation, orovice two in epen:ent trains to pre:1 Joe electrical failure from interrupting the correct actuation. Poaer for each train is from independent power sources.

Alarns are retaineo for the purpose of ensuring t9e proper arming and cisarming of the LTOP system.

l 1 1

This nodification did not involve an unreviewed safety question as cefined in 1 10 CFR 50.59. l I

l 5669L-FwS ._________ _ _

v4 s e - * *. . t r v: v e c w c a cc ..s.

t' .i - s .'

.. ' . _. ate Ccre L' c .:: Ir; System 2  := Lataraticn 'oni: cts were installed. Taey ;;cvice indication of the e.ar;! :o saturation at tnree places in the Reactor Coolant System (RCS) - the

e. ;,e reactc: vessel neac, anc tne S/G tuce region (c's sice). This EOCR res n:t involve an unresie.ec safety cuestic . as ce'i .ec ey 10 CFR 50.59.

l 5669L-FWS

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socn asc ..s  ;; a n I

.;e: E _.: :.63-530 tne is0; nase bus syste 00!ted g:Cunding strarc aere

e:..s;ec Cy aelced laninatec expancanle sna,ts. This enance recuc.es yearly

.sintena :e and coes not involve a*. cnresieaed sa'ety auestion as defined by

. < .we7-

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, ~ - -; sa ;e ;3: ec-;t;: :c;e cenetration Saas EC; '3-5:. '. .t : tne nig7 range ra:iation n:-itar cables from triasial renetrations, tc coaxial ;enetraticns, anien a e correct for tne ca:le type.

Ymis : a .;e in :cves tne rellatility of inst cents important in tne unlikely event of a sericas a:cicent. Safety class, environ entally cualified parts

.ere uset. This cha*ge coes not involve an unrevie-ed safety question as cefine: ::y 10 CFR 50.59.

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vANC.AN4FC a ;v : pCof4COV*aNv I l

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:eric 4 D;; EJ-f:5 cermanently elirinatec an interlcek in t*e Control Element Drive
c
::: System =qicn nac reen temorar;.ly Ce-activatea since 1980. This i all =s a four steo variability in snutcom- ro group ::sition to slow guide tuCe wear.

Tne CD:5 is non-nuclear safety class. Te:nnical spe:j fications allow the chr.ge, and four years experience assured its functionality. This enange ooes not inv:lve .in unrevie-ed safety cuestion as defined by 10 CFR 50 59 . .

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  • 0 A+ C a c .s t r. cgwpa%,

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'n. _ca - 'm Re turn . c . e - c u _- issist System

  • ,is . in e invalse; accing a line fro . tne ain tendenser : the top of each rain steam ncn ret _rn valve. The vacuan from the concenser , olds tne non return valves c en curing ic. stean fica conditi:ns. This reduces l fluttering" of tre valves ano a'.so allo s tne main steam system to be used for ce:ay heat rem: val.

This enange does not involve an unreviewed safety cuestion as cefined in 10 l CFR 50.59.

5669L-Fws

va- ,* .tr a ev.: o:wtuc v..s, 5 .~l 0' "'.~

- : .r- rer: .- ;-:; : lat.:n System r_.2 1: Increa- ec '. e re: rc;;stic, fica ca:acilities fcr actn motor

Ir i . e- ain fee: Outps (0-2A 5 E}. The criginal recirculation systems did not Orcvice ace 0aate p; c flo. 3 rin; recirc ;1ation 0:eration. Previous meas.rements of ; ump pressure pulsations nave indicated that P-2A & 8 experiencac aviation caring coeration 1. ne re:ircu'ation ~0:e.

. This cavitating flo. concition nas contricuted to sesere pana inpe';er eye camage ano nign pum; vi rations. Increasing the recirculation fic= ca ability to 4000 g n will reduce pump internal recirculation anc inlet vane .:cvitation, and c cvide the capability to operate for increased periods of time on i 1

recirculation without risking severe pume damage. l l

This enange does not constitute an unreviewed safety question as defined in 10 CFR 50.59.

I 5669L-FWS

wa sr -as r r c .: p:. ace:2 ..s, Eita .

"li-rr ine ':-2C 'ri. *r- .ir:- Sy: ass

~~.: E. insta.'e: a -ey lock by: ass saitch en t,e nain control t ] aid.

. The c.1-- 'ay oe usec to c: Feat the coin:10ence tri: ' unctions ret.een the main t_ : ne an tne turoine 0:iven feecp. O, c-2^. An annunciator has been ins:alled to alarn :ne cypast function. Tnis :na,;e allo s plant startup on

ns :ertine criven feecoum hen the main turtine '.s tri; ec. Tne coincidence tri: circuits bet een tne main turoine anc ?-2 are oy.:at:;s: under acc.inistrative control itn the key lock sait:n. Inis alteration does not constitute an unrevie.ec safety question as cefined by 10 0 R 50.59.

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i:.:: 5 3-: .. i,s:f...:: ne., c;a ifiec co.'e cets 'c: seven core locations, in

.nica e. cetect::s aitn cua.i'iec care exit :nerno:ceples were installed.

f p,is ensu:es tna cat'es 'c: these core locations insice tne containment will remain oceraole in :ne unli<ely event of a LOCA.inis change affects a safety class ;E :ys:em. -c.ever, tnis 12 an ucerade of :ne environmental cualit:ca:icn of :ne components .i n no functional cna,;e. Tnis enange does not involve an u revei ed safety c estion as cefined by 10 CFR 50.59.

5669L-FWS

vi e* :c e ;v.: ac.sr.cov-is,

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e :+:.; : a ,co . . ;.e: :ne ,::ification of eristn; suppcr:s anc addition

. me. s.rr:::s ' . tre e;e:tric Energen y Feecaater cumcs recirculation lines s' : c er E a ciriac also, s e Onec4 valve -as ad:e: to t s c:eam-cri.en A:W punc recirculation line, rne ene < valve mill serve as : e seismic pressure councary oetween tne seismic electric-ctiven Era punc recirealation cipin; and the non-seismic turoine-criven AFn pu o piping.

Die AFa system operation was not affec ea Dy this enange. This change does not invcive an unreviewec safety question as defined in 10 CFR 50.59.

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v c.s r v os s ti Arc v.: PC W E R C OveQNy

. .I ;'< u; sr -. s' ,.

, ~ " C J:' .2:e dver:C.ir ;;s; ..: :5 _ ; e Ze; < .' = vl e s 7ge in.J1.e: ". 0 i"<!3.'3ti n C 5 6" Check valve in the Condensate

.- 2 0 erroar .ine -t.ich ties into tne service ater disonarge header. This >

elic.inates tne cassici'.ity of introcacir.; sea.ater, anc hence, chicrices into 1 the concenser if an isciation valve is ina::vertantly lef t open.  :

i Tne car.censate system is oco-nuclear safety cisss. Tnis enange dic not involve an unravie e: safety question as cefined in 10 CFR 50.59.

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va so asart a :- :4 t u c a ..s.

7 I ' M' ,C .i .ti w6 . G.

e-ratai e,elica. re :..me Oc'etration Isolation u: .ip :na ;e involad the cuttin; an: caccing of 3 small core pices on notn sites cf a Ocntair. ment penetration. Since tne lines ere no longer

_ti;izea, tnis esign enange proviced 'c: a mans of per .anently modifying the penetration suen that annual IST pe etration testing is not required. This

na ;e ::es not ins lse an unrevie-ed safety Caestion as ce'ined by 10 CCR 50.59.

h 5669L-FWS

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  • 0v C m; a t e ;Oweg g, 1

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Eit':- (;-$1' ru':C o d'. e: =1:e 4:A*.; C ~ ' ':: fiCation EO'N d?-5:- re::a:e: se:::ans c< t a xai., feec ster piping ane steam generator l

irlet ne :le thcrtal sice.es. Tne 1./G no::le t9ermal sleeves were replaced as

ney .ere s11;ntly ceformed da:ing the 1953 ater nammer event and the piping i was replaced as a precautionary measure. Tne fee:aater pipe configuration was l
nanced in order to mini-ize tne namder of welce: joints in the horizontal f

pipe sections adjacent to tne S/G inlet no::les. -,ien previously experienced  :

i tnermal stress cra:xing.

s This modification is safety class 2. The new pipe configuration does not i adsersely affect the operation of tne feedwater system. This EOCR does not present an unreviewed safety questien as defined in 10 CFR 50.59.

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    • NE v oN= E t a cv.c P0n ce ccveas,

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) ;e o.a'. ;f ;/ a-1 1-ter- als i

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- P.e Casi :rosices condensate stcrage for tne suction s;; ply to the auxiliary f eec p s anc if *-1 is a gate valve whien isolates tne DaST from the suction neacer feeding tne auxiliary feec pumps. Single failure of tnis valve in the closec ::sition acia prevent operation of the auxiliary feed system during an

! r e gency. Tnerefore, EXA 83-520, essentially eli.mi ates A%-1 by removing t .e valve internals (disc) and hand *neel tnus mocifyin; tne auxiliary feed system to satisfy single failure criteria.

Tnis mocification inprm.. , the safety cesign of the plant. This change does not involve an unreviewed safety question as defined by 10 CFR 50.59.

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sf T . d ;_ un:le iep'.a:Fent

.e existing v5R tuOe bundles with "1.t :nsnge U.: 1<ec t^e replacement of c ticized ..:e Oc cles ano tne addition c' ;:erfc:ated plates in the inlet side of t,e ev: 9 car 's in :ne v5Rs e and D. Tnese mcdificaticns result in increased reliacility and efficiency.

rne *C9.s are in a non n lear safety class system. T,is enange did not involve an onrevie.ed safet/ asestion as defined in 10 CFR 50.59.

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5669L-FWS

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" * 'N E

  • A N n E E A TCu s C pow E r, cou pa % ,

EEG 51-5:9 te ;eacter '.esie. Cicsare Head Li't Rig Ert_ a e-59 rec; rec :ne .eavy lif t lineage cogenents that are utilized to atuen t's reactor vessci closure neac lif t rig to tne containment polar

crane. F.e replacement components were ucgraced to comply .itn Section 3.2 of J

l ANS! 14.6 - 1975, "A erican National Standard for Special Li' ting Devices for Snipoing Containers Weigning 10,000 Pounds (4,500 kg) or Mere for Nuclear i

vaterials", as cutlined in NJREG-612, " Control of Heavy Loacs at Nuclear Power Plants" .

The reactor vessel clcsure head lifting rig is not a safety related

! structure. The replacement components were designed, fabricated, and installed in accordance witn ANSI 14.6 - 1978, which encompasses and/or exceeds the design criteria and installation requirements of Maine Yankee's safety class structures. The replacement components were designed with a larger factor of safety tnan the original design. This change cces not i

involve an unresolved safety question as defined by 10 CFR 50.59. ,

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  • NE*ANmEEA'[VC40WLR CCypgNy

[ f,I- Ei-S3j u . . r arp - Tri; y' .-ig- Tan- Level EIW c'- Z I s*.li.lec a #. cat saiten c" t e aaste oil storage tan,<. This it:n ;rt.e ts :ne par; f rcr ;a.:pinc cil into a full tank, causing overflow.

s The aaste :11 tanx, pump anc new level switch are non-nuclear safety class.

This enange safe;caras against accidental tank overfica. T91s change does not invclve an anrevieaec safety caestion as defines by 10 "FR 50.59.

4 5&59L-FhS

ucis c -ss e r a-:v : =:<.cacovsas,

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t,L

- t: ;;;se :f re v-??: :n -<C Trip EL- :!-3E airec :r . tarts of re'3y 9?-FC .303 into tne Fn 4336 (P-2C Dis:na:;e valve) cent:c; circuit. Tne rela, energizes on F-2C trip and in tnis a :'.icatico closes tne cis narge valve. T .is prevents P-20 from being criven sa xaard oy ::ressure f rom -24, B, if its cisena ge check valve fails.

This Tnis ena,ga and a associatec eculament are non-nuclear safety class.

cesign prevents potential eculament dange. This change c:es not involve an unrevleaed safety q;estion as cefined by 10 CFR 50.59.

5669L-FWS

v. c , c . . v a , 0 s. : rawc. cov.a y c w:

k . r\ 2 -s 1_ s ,: ,

.-  :" an Air Su::1y Station Near

.: tain. ment ;ersonnel Maten r-is nc:ificatior, involve: tne accition cf a service air hose station near the I

.arsonne air locx. A nea run of la pipin; was tied .nto the existing air line running overnead.

rnis enang= affected a non-ne: lear safety class system anc did not involve an unrevie.e3 safety question as defined in IC CrR 50.59.

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5669L-Fws

o s s c a s. t r A*cu:c : :.* c a cev= sv E1; e?-t b

a,w i .; ac er Scree C:::Osio .gracation Itiprove ents EX; c ?-3M in ;urec several mocif t:ations ,*1ich aere aimed at reducing the level af periccic mair.tenance requ. rec for tne 'our traveling water screens
  • ni:n ser.e to remove ::eoris from tne plant i ta <e cc ling water. A new j elastomeri: uretnane coating material was selected to replace the historically ineffective citamastic coating. Cso, an incressed ccrrent cathodic ,

1 protection system aas acaec to all four intaxe tays tc crotect areas .eiich acre left uncoated or subje:ted to coating camage/ wear. In addition, a spare screen unit acacted for universal crive configuration was purchased to establish cuick change out capability and allow more flexible and less costly routine mainter.ance programs for tne screen units.

All aspects of nis cesign enange were classifiec as non nuclear safety related, and thus tne alterations outlined aDove do not involve any unreviewed safety Questien as defined by 10 CFR 50.59.

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EDCR 64-02 l l

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vm.itiec <; val Transmitter for :entainrent Sues Indication 1

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T7e leve; transmitters in the containment sumo have been replaced by envir:n entally qualified transmitters. They have a range of 0-10 feet and j indicate in tne control room. An existing system was uograded to assure l operacility uncer post accident conditions. This change aces not involve an unrevieaed safety ceustion as defined by 10 CrR 50.59.

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' **W E Y A NW EC A TCueC acW E R COMP A NY

! E;C9 24-04 Pe:fermance Instrger,tation upgrace Acditions'. instrumentation has ceen acced locally on the Moisture Separator Reneaters to monitor their performance. The information available from this new instrume:.tation, coup'.ed witn our existing instrumentation for the MSR System will enaole ; calculation of tne following, based on actual data for ea:n MSa:

1. Snell sice inlet conditions including pressure, flow and quality.

)

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2. Chevron pressure drop and moisture carryover.
3. Snell side tuce bundle pressure drop.
4. Snell outlet conditions including flow, pressure and temperature.
5. Reeater heat transfer to shell side fluid.

This modification did not involve an unreviewed safety question as defined in 10 CFR.50.39.

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5669L-FW5

vamevoucoarovic catacoupamy ECCR 64-06 3 era,te Ecs,enging vent to rirs: cr int reedaater Heaters Cha';es under EDCR %-26 allow tne crains 'ro? the MSR Scavenging Steam vent Concensor to ce autoe.atically routed to either the MSR snell (inlet) or to the first coint neaters. "lis modification cia not involve an unreviewed safety question as cefinec ir 10 CFR 50.59.

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5669L-FWS

I Ma a% E V ANM EE ATCulC PCW ER COppa%v EDCP 94-06 4

I

qi :ation to Steam Generator Primary vanway Narzles i

EDCR St.-05 instituted the use o? a mocified steam generator primary manway

! gasket retainer plate. Tne new plates allow gasket installation separately from tne primary man.ay covers. Tney previce easier and nore accurate positioning of the primary manway gaskets.

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Tne gasket retainer plates are non-nuclear safety class. Tne tappeo holes for the plate's positioning cap screws were located in the primary .anway flange,

< wnicn is safet's class 1. The modified components continued to comply with the appropriate design criteria. Thus, this modification does not increase the

probacility of an accident, equipment malfunction, or the occurrence of an l accident not previously evaluated. Therefore, this change aces not involve an unreviewed safety question as de'ined by 10 CFR 50.59.

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EDC A 61.-09 Loss of 115 Ki '.c;; age Alarm EDCR 84-09 upgra::ec tne alarm functions associated with the loss of 115 KV cf fsite pc.er supply. Tnis change installed an audible alarm in addition to tne visicle Panalarm scich annunciates after a ten second time delay to minimize nuisance alarms. The control room personnel are alerted by this alarm function to loss of reserve station power under all operating conditions, including problems with transformer x-14 when in the standby moce. This enange does not involve an unreviewed safety questicin as defined in 10 CFR 50.59.

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a wa'NE vas te arcuic Powce coucaw ECCR 64-10

'.L .ca Sucti0n Pre:sure Tri; Time Delay b

f EDC:

51.-10 nocifiec tne netnoc of initiation of a P-2C low suction pressure tric.

Tne cressure saitch was removed, and a new Sigma Meter-Relay inserted in an existing instrument loop. Relay alarm coints (2) drive an annunciator 1

anc a time celay relay. Tne relay trips P-2C if pressure stays low for 15 2 se cncs.

The enange provides new This equipment is non-nuclear safety class.

in ication and prevents nuisance trips. Tnis change does not involve an unreviewed safety question as defined by 10 CFR 50.59.

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M a *N E V A N N C E ATOV'C *OW E R COM pa %y 4

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tt. an r;
ters Contaivent 7atameters Relocation l

EXR SA-ll relocated several instrcents located on the Main Control Board

.at re;asure containment pressure, sum water level, nydrogen concentration a, Micn Range radiation to anotner locaticn in the safeguards section dealing

}-

.ith containment isolation. Tnis was done to logically group instruments of sinilar functionality to increase the effeciency and effectiveness of their t.se. Tne functions of eacn inoivicaal meter or instruwnt did not change, j only the location. These instrume'nts are Class 1E for post accident i

j xmitering. Tney were relocate.1 while retaining all of Class lE cnaracteristics such as channel separation, seismic mounting, etc.

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I' This modification did not involve an unreviewed safety question as defined in I 10 CFR 50.59. . ,

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ECOR G -12 ite r, Jact rs aide Range Lc; Recorder Replacement ECCil S-12 replacec a wide Range Log Pcwer siecorder with a computer driven CRT Trenc. Tne recorcer will be retained in another location until the CRT trend can De pro;ramed and any proclems worked out in order to satisfy Human j Tact::s criteria. Long term historical cata trending in nard copy will be rese;vec cefore'ocrietion of tne recorder removal. The new CRT will provide f

irroravec rnonitoring capacilities oy eliminating the Hut.an Engineering Def151encies in tne cnart recercer and not creating any ne. ones. The inputs necessary to drive tre CRT are generated by the plant process computer. This isolation feature retains the necessary class lE to NNS separation.

This modification did not involve an unreviewed safety question as defined in

,10 CFR 50.59.

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1 uaise y AN"EE ATOMIC POWER Coupa%v ECCR 84-13 Lon:ain ent Fersc .nel Haten Irorovements

-is aesign cnarge involve several mechanical enanges to the containnent ersonnel maten in orcer to irprove tne haten's overall reliability. The l  : anges are as fr.,1 lows:

. 1.' Installed new wear rir;s, with additional screws, on the inner door locking ring, i

?

2. Increased tne quantity of grease fittings on both locking rings, f 3. Replaced the wedges on both cocrs and locking rings.

4 Replaced the hinges (both doors) with an updated version of the hinge. .

5. Installed new adjustable locking pin holders.
6. Installed a system to provide the capability of testing between the o-rings of the inner door from outside of containment. This system is similar to the one installed for the outer door.

I The operation of the personnel hatch was not affected by this design change. . j This change does not involve an unreviewed safety question as defined by 10 CFR 50.59. .

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untNE y ANME E A'0wtC *OW E R CowPahr ,

r ELCR 84-14 l

^ ar;ing System Fica Restricter for LTT Concerns This enange ir.velve: tne installation of a multi-stage flow restricting orifice in tne c,er.ical and volume control system line. This orifice reduces tne ef fects of 1:a temerature overpressure transients when the RCS pressure is less than 430 psig by restricting the high pressure safety injection fice

0 200 gall 0n: cer -inute or less. At FCS pressures 210w 403 psig the flow restricter is va'.ve: in and the WSI valves are locke: out.

This modification did not involve an unreviewed safety question as defined in 10 CFR 50.59.

O

maine V ANM EE A T OMIC POW E R COMP ANv i

P EECR M-15 l

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, t t a. 2 eratcr net Lay-U;; .ecirculation System Taas 1 1

1 In creer to provide a mre efficient method of controlling steam generator

=ater enemistry during et lay-up, a recirculation system nas been designed

' 'cr each steam generatcr. This design change provided the pipe taps and root valves tnat will be used to connect the recirculation system to tne recirculation locps. ~5e ta s were installed on tne main steam lines and the cloaccan lines. Tnis ,ocification did not involve an unreviewed safety question as definec in 10 CFR 50.59.

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5669L-FWS

' o'en F E S T O MIC mow g R Cce - c M G 8 **C EDCR 64-16 Isolation vu n una Aoiliarf Feedaater at Main 5:

Eypa::s Annunciation iliary feedwater Inis cesign enange involved a change to the main anc iltry that provided an regulater valves steam cenerator 10 pressure trip ci

, .cn is in the bypass alarm directly from tne control switch whenever any u

! a bypass alarm from position. This modifiec tne old arrangement whien c-

) alarm whenever one of an auxiliary relay. Tnis design enange also provie i tne "CPEN" position tne excess flow check valve control switches are le' This modification wnicn also bypasses a low steam generator pressure :

ed in 10 CFR 50.59.

did not involve an unreviewewd safety Question as de' 8

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a s t a s c t a : v :c.  ; .s t a c c u pa % v E l ; 5-. :-

- .;T !c~tr:ller C t:st ~est Feature CI: s,-19 installe: an On-line :=St feature to tne steam camp control cir:;itry. ~nis nc. *est capaDility permits verification of the availability Of tne steam caTO signal from the steaT. cuTc controllers. This change ircr;ves tne rella:ility of the stear dump contrclier circuitry. This change c;es not in.:',ve ar anrevle-ec safety cuesti:n as defined by 10 CFR 50.59.

5669L-FWS

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" ,;- 5 ran av;..:. veasure,ent

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stesm sampling ric::'es nave been a:0ed to ea:n of three main steam lines to ce used to cotain sa ales of ~ain steam for testing ;urposes. These nc::les are locatec insice tne contai ce it ouilding, upstream of the main steam non-return valves. As such, tnis installation was cesigned, installed a .: teste: to nuclear sa'ety class I! re: aire ents. This nodification did not involve an unrevie-ed safety cuestic as cerinec in 10 CFR 50.59.

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5669L-FWS

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  • O %4 ) C PC .% [ Q C Q V D A % V E.; -2;

. x : sate /r n /;a : Mr - -. tic' .'.zrace nis cesi;;n cnange ::csicec for tre instal;ation of accitional instrumentation to .:.cre ef fectively monitor tne cerformance cf the circulating =ater and cencensate systems.

Tne mo:ifications consisted of the fo;10.ing installations:

1. Pitot tuce taps in the circulating aater inlet 1;nes and DP transmitters across the circulating water pumps to allow for accurate measurement of circulating water flow rates.
2. Circulating water discharge line thermocouples and conductivity probes to allow for accurate determination of disenarge water temperatures and water levels in the cischarge lines.
3. Parallel plate pressure devices in the ctodensers to provide for more representative turbine backpressure indication.
4. Thermowells on condensate punps discharge to be used to measure condensate punp discharge temperature.
5. OP cells downstream of the condensate header (connected to existing orifice plates) to be used to measure flow rate.

l This modification did not involve an unreviewed safety question as defined in 10 CFR 50.59.

5669L-FWS

v. ,ev.s.to.1.v,c. ,sca :.y .s. .

tt. e u - 2.2 e4 61::W .'31ve cor c;er n:: e:;1acerent inis cesip c .ance invcived tne replace.T.ent of tne existing DDRV block valve m::c: c:eratcrs it, icentical safety class lE environmentally qualified replacements. This enance was part of Maine Yan<ee's environmental cualificatic, program in response to IiE Bulletin 79-019. This nodification ci: not involve an unrevie ed safety question as cefined in 10 C R 50.59.

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v a s e. .as-ci.a+;..;oc t.: : , ,, , s ,

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- . 'e 'c%:- tun '..'.tc e C -5 0, & 6 EO: n - . replace ~ecn371 cal temceratu'e sait nes in the containment air compress : alarm circuits witn RID's and incicating controllers. This p c* ice: new incication, easec calibrat. ion ano slo ec setpoint crift. Die co presscrs and alares are non-nuclear safety class. New indication is provice: to ease fault ciagnosis. This ena,ge coes not involve an unreviewed safety cuestien as definea by 10 CFR 50.59.

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l Tne ::i;i a. car:

On 5:ee; <ent ci:;i'; f rv c' t e shel] sice of the first coi-: 'eet.ater neaters aas rep 12:ed with a stainless steel material to eli-inate erasien aac '.ea < ace problems. Pis mocification did not involve an i

i unrevie ed safety question as defined 1.1C CFR 50.59. 1 I

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Tus .nange ir.:;.ec : e accitic :f a sys e tnat crains off collectable j

, ecistare rom : e nig . pressure :_ : ire cu let nozzles anc pipes it into the 1

neater drait sys:e . 'nis was a:- ncl.she: ty installing ski r ers in each of j l

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the four turtine Outlets and pipi; lia.2ic .ater to tne heater crain tank.

Mo.sture recresa' impr:ses the effi:iency c' tne clant and recu:es the erosion 1

in tne crossuncer piping. j l

This enange affe:ts non-nuclear sa'ety class system, and does not involve an unreviewed safety question as defined in 10 CFR 50.59. ,

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Centsi n't Elevation 46' j

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s E -25 crevicea 'or tne installation of a ji: crane on tne structural steel trat sacacrts tne stcra;e plat'orm atove steam generator number three.

7 e EIR a;s prov; cec for a positive ancnora;e 'cr tne cavity seal ring and j aa lliary bridges stored on the plat'crns. The _ iib crane is rated for three tons.

i rne frame to .nien tne crane was mounted is safety class structural steel.

! ine structural steel frame was reanalyzed to incluce tne effect of the design i crane load, and mocified as appropriate to ensure continued compliance with the plant's safety class structural steel criteria. Tnis change does not involve an unreviewed safety cuestion as defined oy 10 CFR 50.59.

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- ts s -30 involved rerlacement o' 90 of 96 meisture separator cans with ne.

e nign cana:ity cans. To allo greater accessarility to the center region of l :ne steam generatcr, fcur original cans exten ing from the rsnway to the center region rer.ained. Due to tne possicility of overloacing, these original j cans .ere orificed. As a result of the height increate associated with the

! new cans, ne cryer drain lines with relocate: tenas were installed.

! Toese modifications did not affect the pressure boundary of tne steam i

generators and as sucn were assigned only a Q.A. related classification. This l design change does not involve an unreviewed safety ouestion as defined by 10 i

CFR 50.59.

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  • L E 4 *; Vic a; A t h coupA%,

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.. cf .c; king Cevi e : hlar Crane E'XR %-31 instal;ec a locking mechanism cn tne hook of the colar crane to

event tne rotatica of tne crane hook cn its tnrust cearing. The The

.m ccification invcivec only tne immediate cc.?.conents accat tne crane hook.

f modifications naa no effect on the strengtn of tne structural components, i

  • his crange coes not involve an unrevieaed safety Cuestion as defined by 10 CFR 50.59.

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. tt 'i%rnal 3- ie2 ".'i: rl' g System Upgrade I

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ri.e e. contin cus -c.'itering c9annels mye teen installed in this system j .nic, increases the syste sensitivity and monitoring ca acility. Tne upper

};h neac system consists of tnree m.agnetical.y mounted accelerometers while the i Ic er head system consists of two accelerometers attachec to the incore l instrumentation guice tutses. inis enange coes not involve an unreviewed i

t safe;y question as cefined by 10 CFR 50.59. l l

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i iniS 095199 CnY ' 'I .i;e2 fPr the irstallation of a 970 thermonell in eaCh l c' t.: stear gererator seconcary nanancle covers on steam generator E-;A.

r,ese tnermcaells ill re usea in conjunction with the RTO's installed under i

ECCR 64-39 to measure the temperature of tne coancomer water in S/G E-1A. l

.i Tnis informatica .ill re used to calculate tne steam cenerator recirculation rat.o.

Since tnese thermo ells are installed in the secondary sice coundary of tne 1

{ steam generator, they were designed, installed and tested to nuclear safety I l class II requirements. This modification did not involve an unreviewed safety i

!. question as defined in 10 CFR 50.59.

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vssevas-eea cv r -c .s t e ccu pa sy E'.C ; :.-36 s .c- .,..e ;csta.laric- i* *ater Treat ent Line ietnnical Scecificaticas reauire tnat the DnST be isolated from r4NS systems curing pc.e: cret ation and that tne DaST contain a minimum of 100,000 gallons. In crder to allow acdition of makeup water to the DwST during power c;eration and, at tne same time, preserve the safety class boundary, EDCR 5t.-36 ac s two ene:4 valves in tne concensate makeuo line at the safety class councary tnus provi ing a seismic councary an: satisfying sing.ie failure-criteria. This enange does not involve an unreviewed safety questiu. as defined by 10 CFR 50.59.

56&L-FWS

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a:sc as- - a r c ui wo s c e c o..s,

d ri 09-39 a'i 500
,'_::, 'ia c':le 4Cs EI ; s -39 19stalle: resista:nce teTerature cetectors (RDs) to monitor seconcary size temerawre in Staa ^enerator No.1. These RTDs were installe: in tnere:. ell; in the seccncary hancnole covers described under EDCR 84-36. Tnis change coes not involve an unreviewed safety question as defined
10 ^FR 50.59.

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".A9 6: :: ~ r s; :e: in Se : " A" SCB 3:acer re:;acemen: re .a:e: a c <isting non-lirear unit -ith a linear T,1; :

ne.
:s autout feecs tne co cuter an logs tne ;; er ca:pa: of tne plant to tre .: mter.

Inis ECCP-oces not invc;ve an un resie ec safety cuestion as cefine; ay 10 CFR 50.59.

  • 4 5669L-TwS

R M O ' N C

  • O N E L L O T ^j %* 6 0 P C .% F R C O M D A N ,

Eit.9 St.- ;

  • ..* 5 G i- as e r R ". : r_ts ter;ers;.re tramstitters ere i . stalled in ^e containment and connected to tnree i 22s c' : e sipal Eticlever installed under DA 28-83. This allows

< :nree ;cc cv. c;atina- RIDS to tse ecnitcred in the control room. Initially, RDs ere installec in tne stea generatcr secondary handnolds for use in cal:alatin; :ne stean generator recirculation ratio. Tnese trans.mitters ray te usec for otner RTDs in tne future. Tnis enange does not involve an j unrevienec safety cuestion as defineo by 10 CFR 50.59.

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r sun Pc:: it:si : F.c:lacement E.:A a  ; reclace: r e cri;inal "Y" type Strainer located in the suction line

' es:n s:reen aasn ; m .itn a casket tyce cuolex strainer. This new i s:Clati:9 all:as strainer casket removal anc cleaning .ithout interrupting t~e @!atiy. of the s0:0C0 wash pu?pS.

inis cesim enange nocifies a non-nuclear sa'ety class system. The reliacility anc availa:ility of the system alli be enhance: by this accification. This EDCR coes not create an unreviewed safety question as cerined in 10 CFR 50.59.

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.n cii :rtemic., re: .as ccnstructec at:ra :ne stes- criven teecpump (c.;C ) . T .e ci. resersair on P-20 nelas a sucstantial amount of oil. The functi: :' t .is terr is tc prevent spreading of oil, snould the reservoir rupture, tnus preventing camage by the oil, tne screac of fire, or the inace.:: ant overocar; cisc arge of oil. This enange is t: a ran-nuclear safety system. Inis :nange coes not does not constita:e an unrevieaec safety cuestion as cefinec by 10 CrR 50.59.

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. eter Occie 'er iS^ and E3~
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les ere irstallec '::, the main computer to the Tecnnical Suco :t Center at Emergen:y 0:eratin; racility. Tnts change provides the capaDility for these facili:les to ac-1::: actual plant conditions curing drills or in tne unlikely event of an a :aal accident. This change does not involve an unrevie.ed safety cues:i:n as defined by 10 r R 53.59.

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.c - ts %-5!. cel.'s ais p n i.:eJ to se,e al locatic.,s .ithin the plant 2r 'e a:aff builcing f:r the sinulator cc: uter root.. T.is cabling provice aness to :ne C.;ita; E:;eioment Corporation VAX r.omputer which is use: to stc:e data for maintenance and operations purp.ws. This cable Oermits a::essing tne '..'.x ccTuter systet, from terminals throughout the plant. Tnis change 00es not involve an unre<!eneo safety caestion as defined 4 in 10 CFR 50.59.

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