ML20203J552

FOIA Request for Documents Re Info on Maine Yankee Nuclear Power Plant in Wiscasset,Maine & Problems Experienced W/Cable Sys

ML20203J552
Person / Time
Site:	Maine Yankee
Issue date:	08/16/1997
From:	Dorr D MCTEAGUE, HIGBEE, LIBNER & REITMAN
To:	NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML20203J544	List: IA-97-320, Final Response to FOIA Request for Documents.Forwards App a Records Already Available in PDR ML20203J538 ML20203J552
References
FOIA-97-320 NUDOCS 9712220009
Download: ML20203J552 (68)

Text

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Catwatt C Duet N tat, wteNG R 5,u,amest L Jcmentow August 16, 1997 Director, Div of Freedom of Information Office of Administration U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dear Sirst Please consider this to be a federal Freedom of Information Act request per 10 C.F.p. 59.23(b). We are requesting information on the Maine Yankee nuclear power plant in Wiscasset, Maine and problems it han experienced with its cable systems. See attached Portland Proon Herald newspaper articles from 3/8/97 and 6/14/97 as well ac several pages from your agency's Maine Yankee Inspection Repurt 96-13, dated January 15, 1997. Your report notes " cable separation" problems while the newspaper refers to " improperly crossed cables" and "how cables have been routed". Specifically, we are requesting information from NRC records, inspection reports or Maine Yankee generated documents waich address which subcontractors, if any, are responsible for the planning and installation of any of the variously identified cable problems. This includes the most recontly discovered cable problems in December 1996 and forward, as well as cable problems which had been identified in earlier years. If any matter in this letter is not clear, please call me so that I may provide additional clarification. Please note that we are willing to incur immediate costs of up to $200.00 for the processing of our request if you determine that it is necessary under your fee policy. We appreciate your expeditious handling of this urgent request. Sincerely, 6% Dale Derr Taw Librarian 9712220009 971215 l PDR FOIA I DORR97-320 PDR __t______---_-

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• A letter noens that an assessment of risks at the NRCs regimai otra in Penns>+

N plant was ahered to make conditions appear bcuer,

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.S. Attorney's off ce in Port-Ily 1UX TUltKil Ur.:on of Concerned Scientists, a land is already engaged in a cri-Stag Writer Washingtontased nudcar wakh-minal investigation prompted by dog group. After reviewing the similar muegations made in 1995 of l The Maine Yankee nudear plant matenal, une group contacted the wwngdoing involving Maine Yan-is once again the target of anocy-Nuclear Regulatory Commission kee. *Ihat case centers on computer maus charges that engineers nowm tale Thurschy. ccdes used to ensure that Maine playeu past safety prublems. "We haven't been able to confirm Yankee operates #Arely. Federal nudcar argubtors Mon-or discount the allegations," said Scrend said the latest aucp,ations day are expected to receive hve David Lochbaum, the watchdog alsu would be forwarded to the US notebooks said to contain evidence grvup's nuclear safety engineer. Attomey, if the NRC found any of wwngdoing i.: Irrw r.afety risks W NRC also was tying to evidence of wrongdobig. were evatusted in 1992 at Wee decide hiday if the chary,es were Maine Yankee has been closed Yankee. vabd and how significant they rnight since December,when an electrical The documents come from an be. Inspection found some improperty unnamed source who presented the

• lt's too soon to tell," said Diane infonnation sato last month to the Serenci, a spot.cswoman for the Pleast set YANKII,'Page 4D each other. The whistleblower nuclear plant in Per$nsyhania in A'_ "

' y y asserted that some of these nssess-1979. Inents were altered to make condi- 'Ihe new allegations center on a ContinucJfium l' age ifl tions look better than they should pmcess used by safety regulators to

have, set spendmg and maintenance prt crossed cables. Company officials Spokeswomen for both Yankee crities in a nuclear, plant. The recentlyannounced that theyintend Atomic and Maine Yankee said pmcess asks three basm maeshons:

to make the shutdown ;ermanent if P2y Umy were reviewing Die What can go wrong? Ilow hkely is it a buyer cannot be found for the charges and couldn't make any that a given problem will occur? 2, car-old plant. spec fic comments at this time, -- Mat s um possH wtcome? 'eco Energy Co., an energy who-Lochbaum said tiuat these and lesaler, has expressed interest in Wletter writeralso refers to the other issues raised by the whisdeb-buying the plant. On Thursday, a sirnilar charges made anonymously lower didn't by themselves seem to delegation of ernployees and local to the Union of Concemed Sdentista pose a serious threat Uut combined legislators was in Washington to in 1995.The 1995 charges stated that with the possible inadequacy of Yankee Atomic and Maine Yankee seek congressional support for such Maine Yankee's coolant syt.lem, as a g3]e, purposely skewed computer code alleged in 1995, the situation could The latest allegations of umngdo. calculaGons and that Mame Yankee be serious. And he wonder if Yan-used Umse calculations in 1989 to ing came in a two page letter that kee Atomic may have perfonned acrompanied the notebooks. The justify generat6ng more power than faulty analyses of other safety sys-charges deal with the way Yankee it otherwim would have been tems at hta!.ne Yankee. Atomic Electric Co. of Ilotton, Mass, allowed to produce. an engineering finn and longtime 'the 1995 allegations are serious, consultant to Maine Yankee, pn> because they call into question how IOR l_ INKS to information on piued assessments that measure the plant would have perfonned in Maine Yankee, see (l'e Press risks at the plant based on how the kind of lossof<volant accioent licrald's World Wide Web site: vanous safety systems interact with that crippled the Tlure Mile Island nwpontand.com e

N heS.f 4)d .~, Maine YanheTEEhs ~ to its work force to correct problems = Many of the jobs will Afaine Yankcc has pay in the $40,000 to 0 0'000 ' " 0' j,gggggg 39 gg workforce tran. 11y I:DWAltD D. MUltfilY And late utst month, federal regu-Sta]J WHrr' lators told plant omeials thy found WISCASSE.T Maine Yankee is 16 app:urrt safety violabons, indud-continuing to txost its work forte ing a design flaw Dial could render whileit entends with ongoing prvb-t e ' de 1 i lems and ter scrutiny from federal regu tors. regulators are to meet wRh Maine Yankee o!!icials next week to dis-1he plant announced IMday that cuss the apparrnt volations, which it will add another 63 posidons, txmsting the number of full time antld rrsult in fines totaling mil-bons of dollars, workers to an all Ume high of $50, in addibon to maintenance and over the next six months. Most of ci gineenng, Maine Yankee said it is the new jobs will be in engineering adding jobs in acrounting, fmancial and maintenance, two areas in services, training and technical sup-which problems have plagued port Many of the jobs will pay Maine T ankee in recent months between $40,000 and $50,000, said ke t i wo lo I to p1 t. on prvduchon costs, but that ended Most of the new worters willjoln last yearafter the plant unmvered a temporary employees and outside series of potentially dangerous contructors tryire to cormet a back-design ilaw:; or opcrating Ig of rnairttchgp ombiena, sne prublems. said. 1he plant then said it would shift 1he goal,11rown added, ts a its focus from low <ust to excellence morv

• pro-acuve" work force that in operations.

6 will identify and wrwet problems Maine Yankee has not pmdueM snoner and preven'. a tacklog. power since December while lhe company also has 49 vacan-workers review how cables have 'es thmughovt the plant, Browti been suuted thruuch the putnt, (md said. . the shutdown is.iow expected to The number is high compami extend into summer for an carber-with trcent years, she r. aid, but than-planned replacement of leaky tellects the after+frects of a hinng fuel rtxis irreze and employment study and a The plant has pmduced electricity changeover in managernent that just nine of the last 26 months. took place last year. l s. e t

r;, a.m., w.,$n 6 6, - r,er,-*mnw ' McIne Yankee Inspection Report 96-13 1 Selected _Broorts Index l News and Infrumgion l NRC Home Pane l E-mail January 15,1997 Mr. Charles D. Frinje President Maine Yankee AtomicPower Company 329 Bath Road Brunswick, Maine 04011

SUBJECT:

NRC INTEGRATED INSPECTION REPORT $0 '.w9/96-13

Dear Mr. Frizzle:

t On December 7,1996, the NRC completed an inspection at your Maine Yankee reactor facility. hhe results of that inspection were discussed with Mr. R. Blackmore, and others of your staff at an exit treting held on December 20,1996. The enclosed report presents the results of that inspection. During the 6 week period covered by this inspection period, your conduct of activitics at the Maine Yankee facilities was well focused safety. Your staff demonstrated excellent safety perspective when a plant shutdown was hiitiated upon discovery of cable separation problems with the reactor trip manual pushbuttons. In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its eaclosure will be placed in the NRC Public Document Room. Sincerely, Original signed by: Richard Conte, Chief Projects Hranch No. 5 Division ofReactor Projects Docket No: 50-309 1.icense No: DRP-36

Enclosure:

NRC Inspection Report No. 50-309/96-13 U. S. NUCLEAR REGULATORY COMMISSION REGION 1 of22 08/lIS71602:06 ._ 2.

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.-,.ew,., _.- --, mew.gi,m Communications with NRC staff was well done and very timely. Mainterwits There was generally good performance by maintenue personnel during the conduct of repair and testing activities. Engineering support of maintenance ma, as analysis to for unreviewed safety questions was very good. The operations department initiative to model the testing of the auxiliary feedwater pump full flow test on the statio*: simulator prior to actual test perfonnance indicated an excellent safety perspective. Maine Yankee properly responded to the failure of the senice water pumps gland cooling check valves during testing by increasing the frequency of testing which in tum identified the design problem. This corrective action appears to have been timely and comprehensive. Operators properly followed TS actions statements. Mzine Yankee personnel properly perfonned suive!ilance tuts. The testing of the emergency diesel generator EDG-1 A was completed well. The operator in the diesel generator room performed the task in an excellent manner and was very knowledgeable of the procedure requirements. All equipment was observed to function propedy observation and the testing was completed satisfactory. The testing of the diesel fire pump was also completed well. There was good engineering involvement. The PED involvement demonstrated the increased attention to attempt to resolve long standing problems with the diesel fire pump. The nuclear plant operator demonstrated an excellent understanding of the past problems with the diesel fire pump and closely monitored the pump's performance during the test period. The revised Work Control Process procedure was appropriate to enable maintenance sections to provide better work controls. All sections of the maintenance department contributed in the revision process to ensure that the completed document will meet all the departmental needs. EDE nctiing i Engineers continued to provide excellent supput to the plant. Identification of cable separation issues reflected good engineering efforts. Ilowever, it also revealed that therehd been some weaknesses in the past that caused Wproblerns to exist. Good efforts and appropriate actions were taken to ensure that safety related equipment and structures in the turbine building would not be adversely afTected by a design basis llEL13 or flooding. Engineering department personnel provided good suppor1 to the plant such as with the efforts to correct the problems with the senice water pump gland cooling check valves. They properly conducted testing of the original valves in a proactive manner outside the system and identified the valve clearance problem. Engineering personnel properly developed and implemented the EDCR for the Containment Spray building heating and ventilation unit, ilV-7, in a well controlled and safe manner. EIELSuppen While the few unschedului radioactive releases that occurred were minor in nature, they indicated that Maine Yankee needs to perform more extensive review of the events to determine a root cause and provide adegaate conective action to prevent recurrence. 3 of 22 08/l1/97 16 S2.16

.\\,creerrsoFN=,oriv=y96tsJe= bap//wwwarciovCPAlreporta/=y9613.htra ~ 0" E8 Miscellaneous Engineering Issues 13 E8.1 Cold Weather Operations (Update, URI 50-309/96-08-02 and 96-08-04) 13 E8.2 Replacement ofIfea'ing and Ventilating Unit, IIV 714 IV. Plant Support 15 R1 Radiological Protection and Chemistry (RP&C) Controls 15 RI.1 Unscheduled Radioactive Gaseous Releases 15 RI.2 Ilot Particle Exposure to Security Personnel (URI 50 309/96-13-03) 16 V, Management Meetings 17 X1 Exit Meeting Summary 17 PARTIAL LIST OF PERSONS CONTACTED 18 INSPECTION PROCEDURES USED 19 ITEMS OPENED, CLOSED, AND DISCUSSED 19 LIST OF ACRONYMS USED 20 EtD91L[htaib SWUmary of Plant Status Maine Yankee began this inspection period at 90% power. The station reduced power to 80% on October 29, November 5, November 23 and December 2,1996. for backwashing the main condensers, waterbox cleaning or mussel control and returned to 90% power by the next day. On December 5.1996, at 9:45 pm a olant shutdown __ was cornmenced due to the manual reactor trin pushbuttons being declared inoperable because ofinadequate cable separation. Reactor power was less than 2% (flot Standby) on December 6,1996 at 1:30 a.m. and the reactor was made subcritical(Ilot shutdown) at 2:21 a.m. The plant was in llot Shutdown condition at the close of the inspection period. L0nstions - 01 Conduct of Operations 01.1 (isneral Commentt(.1707) 7 - Using Inspection procedure 71707, the inspectors condeaed reviews of ongoing plant operations. Operators performed all observed tasks to be in accordance wiin approved station procedures and done by a staff with a very good safety perspective. Prompt action was taken when (hot shutdown condition) after engineering $ of 22 08/Ii/9716S2:20

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MAINE YANKEE ATOMIC POWER COMPANY AFPRCVED FOR RELEASE Unit No.1. S & W J. O. No.115:50 e FOR GENE /Jil. FABRsCATION Ven ftrM V 4 L.O M d N ULY l $' $.,A 3 u7 / - t '""~ (F. r. '/@ AT.ON Pro s t D. C. Rl'.'. o C:uio. Na DT.A' - Ni 0.eerevien g gMWM"y.glggs sen' Cest n

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R3r, 3 g J.0.No. 11$)0 June 23, 1969 ~ MYS-15k6 Revised August 20, it)69 Revised November 17,1969, S P E C1 F1C ATI O N von CoffrROL BCARDS JtR MADE YANKEE ATCMIC PCWER STATION ~. MAINE YANKEE ATOMIC POWER COMPANY WISCASSET, MAINE. g@O. SELLER - WOLFE & MANN MFC. CO. PURCHASE ORDE NO. Mr-127 REVISIONS REV.O REY.1 REV.2 REV.3 Frepared By Ip r v11 N Project Engineer Approval g j g[ .h Equipment Specialist Review h Quality Assurance Review .d* A-M , ~

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IQ.,. ' 6. t R-1 Solderless copper ring type lugs of the pirallel indent or compression type, approved by the f.ngineers, shall be utilized for an vire terminatic :- Except as specified belov, an internal viring shan be furnished by the Seller and shall be 7-strand No. Ih AVG copper, minimum, with 31 mils insulation of gray, che=icany cross-linked, fined polyethylene, General Electric Yulkene, SI-57275 Thermocouple lead vire, coaxial cable 'and prefabricated cabling for the elsetro-hydraulic governer and reheater control valve insert panels vin be provided and instaued by the Purchaser. be provided for this viring. No term.inal blocks need M-1 Virinz shall be neatly laced or run in suitable virevays. If vire-vays are used, viring holes shall be gro= meted. If metal support clamps are used, actual centact betveen insulation and clamp shall be prevented by plast cleats or tape. All vire shan be per=anently marked with the wire number where they conneet to ter=inal blocks. Pover'or control virinz shan be adequately separated from lov energy'sirnal virina. The latter shan be run as shielded tvisted pairs vith the shielding carried te a terminal ad.ireent to those of the tvisted l pair. The shielding shan be insulated to prevent inadvertent grounding. I'j R-1 Sigma instruments and the CEDS centrol inse:1; panel vill be provided complete with plug and connecting cable. This cable shan be ter=inated on ter=inal blocks including the shield, if any. V Viring for redundant safeguards, controls and instrumentation shan have special consi6 ration. No tvo signal or control channels (for exa=ple - A, 3, C or D) shan,be connected to the same terminal block nor shan they be run in the same viring harness. There shs.11, at an times, be physical separation between channels. f Viring panels for terminal blocks or other devices where required within the boards shan be arranged for clear access to all devices and viring on the instrument and control panels.~ Viring between shippine sections shan be terminated on terminal blocks at the ends of each section for field connection. Control svitch viria.t shan have sufficient slack to pemit removal of the evitch from the panel vithout re=oving the viring. This includes R-1 viring between the control svitch and associated indicating lights which vin not be removed. Viremeld or equivalent shan be previded ter chart drives, where i .g.s id O Purchaser's viring avav frem the beards vil'. be.*To.12 AVG, 7-strand copper with 1,000 v polyethylene insulatien and No.16 AVG, 7-strand cepper signal vire unless othervise ncted. ,b a 4 N

c .; ~ :.,..e... z. e...~. T.1 C-74 k lC((h I I J.0.5e.115M 1 20, 1970 sers-ap57 Revised J U 370 FOR NAIII YAlgGlE A2tMIC POWER STRION ' \\,,. unr= r*== mucC powan==ANY VDCASSET. MAZEE STONE & WEBSTn n GINEERING CORPORATION 30620N, MASSACNUSETTS O 8

llG-Sg i AGA y 1 I 3.0. No. u$50 Mrs-2957 1. GDrtRA,L' 'his document is a summation of instructions and advice issued by Maine Yankee Atanic Power company to stone & Webster I:ngineering Corporation in conference and informally on severp.1 occasions. Its purpose is to define the criteria necessary to identify ahd separate electrical embles within the Maine Yankee Atomic Power Station. This procedum shonid be read and funy understood before any cable is instaned. This document smst be used with the constructiou drawings, esble schedules, duet loading schedules and try loading schedulee. Where ptys-ical separation is required for safety related cables, the cable schedules vin indicate the power bus, the battery and the vital bus numbers. _All ,O p

==faty reinted _ eAles in one_ raceway aball be identitied with one designa-Wg l i tien. De one line diagrats win indicate the safety related circuits. Not au circuits connected to emergency buses are safety related. nected to these buses if possible, but such circuits front)oth.,, buses a h _ occupy t e same trar section if necess.ag ne same philosophy applies LCEll ( to nonsafety related circuits conne:ted to the station batteries. 2. Du rasuoBS 2.1 Raesvay - An exposed rigid metal conduit, a camerete encased plastic or metal duct, an unbarriered cable tray or a section of a barriered tray. 2.2 Safety Related Circuits and Cabits - The circuita and cables associated with the hgineered Safeguard Systems and Reseter Protective System of a nuclear fueled generating station that are provided for the specific purpose of preventing major accidents or mitigating the consequences of major accidents. 3. Mry!0DSOFAm.nEar2CAyION. Safety related cables viu be identified et their terminations by means of renow tags bearing the cable designation. Nonsafety reisted ( tables vin be similarly identified by white tags. Trays will be identified by numbered decals applied at intervsis alcos their routes. Rese numbers win correspond to those given on the construction drawings. 9 e

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l J.O. No. 11550 N!5-8957 2. i k. nuaQLi 0F MA MTAINING SEPARATION \\ b.1 In separate esposed rigid metal eendait fallsvfag separat,e routes where praetteal k.8 Za separate eonerste emessed plastie or metal duets in the sans duet bank t h.3 4 In separate emble trars with boksestal separstlan. The tray sides are considered adeguate barriers { k.h Za separate sable 'crars separated vertically by solid r trar sovers. 1 k.5 In separate stasie barriered sections of the 'same tray 5. SEPARATION NE250D5 31 Alternatine current cables Safety related embles originating from k,160 v bus No. 5 or from k80 v bus No. 7 and its associated actor control centers shall be se from safety related eables originating from k.160 v bus No. 6 or from k80 v bus No. 8 and its associated motor control centers. be by means of methodNos. h.1, I t, k.3, k.k. or k.5 Sepa*ation may .origiasting from bus 6 or bus 8. respecti,vely.from bus 5 and their associated motor control senters may beEensafety re section with safety related embles, if meeessary. placed in the same tray 52 Direct C-. set Cables. . bus and from each bus to its respective vital bus inverte one battery s methods h.1, ystem from another.

eparated, 4 2, k 3, k.k, er k 5 Separation may be asiatained by means of shall be separated asserting to the bus fres which they another. No two safety rela be run in the same raceway. ted tireaits from different battery buses shall i

methods h.1, k.2,. k.3, k.k or 4 5.Separatica may be maintained by means of L-It is preferred that the same separation of nonsafety related cir-enits be maintained in the same manner if pes:itle, hat these etreuit.s placed is the same tray section with safety related circuits, if ne ::sary. ..n.. -, - - - ~, - - - ~,._,-.tL, --,n.,- ...-...,._--....,---.,,.-.-<-a-.---,-

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J.0. No. 11550 Mrs-2957 3. 5 3 centrol cables..c.. Circuit breakers connected to k,160 Y bus No. 5 and to 480 v bus No. 7 receive their control power from station battery No.1. Circuit breakers ootmected to k,160 v bus No. 6 and to 480 v bus No. 8 reeeive their mostrol power from station battery No. 3. Safety relatei oontrol cables originating from battery No.1 shall be, separated from safety related esatrol embles 4riginating from battery Bo. 3. k.k or k.5.Sephrstion shall be preferably by means of method Nos. k.1, k.2, k.3, Safety related control cables originating fron.netor controllers annaected to k80 Y bus No. T shall be separated from safety related control, embles originating from actor controllers connected to k80 v bus No. 8. Separation may be by means of method Nos. k.1, k.~2, k.3, k.k. or k.5. It is preferred that like separation be maintained for nonsafety related control cables associated with the smargency altenating current k buses or the battery buses but this is not essential vbu it beoones impractical. Nomsafety related ocatrol embles may be placed in the same tray with safety related cables. 5.k Instrumentation cables All instrumentation cables associated with vital buses shall be separated, each vital bus from the other. No cable associated with one vital bus shall be placed in the same raceway with a cable associated with another vital bus. k.5. Separation any be by means of method Noe. k.1, k.2, k.3, k.k. or with safety related instrument cables.Nonsafety related instrument cables may 5 5 L eeuter and Alarm cables Computer input and output signals and alarm signals are not essential to plant safety and need not have separation. 5.6 Lishtine Cables i No sysIcial separation is required except for the direct current supplies to the energency circuits. In this instance, separation is desirable but not essential. Refer to section 5 2. t \\ S

i V L. _ = 9 { 22C- % i R. f. G. 4 t J.0, No. 11550 h 2957 k. 5 7 Deadea cables ~~ . meet no speetal separation. cables used in area radiation asaitaring have detector No 1 with.5.1 vith 6. 3 with 7, aat k with 8.cablev used be separates ame tram another. Each group shall Liso be grouped and separated one from the ether groups of emblesc tion sha31 he by means of method Bos. k.1 and h.2, szca Separa-follow the same. routing and raceways shall be ferrous. pt that they mar servloe need no sFecial separation.Incon detectors are not safety reist 4 f G e I.' e e e 9 e T 4 4 9 4 0 we t 6 e x. .f

Y .stDNt &. cttlitA ENGINtt!.it.*,[::ro:Afl0 ,g vy tot BhEncidoy-3 (4 ones.) z U-76 EJSurevisc-3 (3 cnce.) g (, /C, f RCC"--inge-!E-iiiccasset-2 (ene.) J70ibbens-Conb.Eng.,Inc. (Vindcor)-3 (y encs.) h e. sp6e 4: ?.>r g, ;, ..y..... ,...,' s Mr. B. B. Bee! clay July 27, 1970 Project Engineer Maine Yn:-l:ca Atomic Power Compcny J.0.!!c. 11550 IflS-3276 Ensintering Offics Turnpihn Rond-(Routa 9).. Westboro, Massachusetts

01581,

' Dear Sir C }E-127 MAIN CCTTROL BOARDS MAI13 ?!.152". ATC"TC Pct..T.R ST!.? ION Enclosed a.re four copies cf notes of' Conference hold at The Volfe & Mann lifg. Co. en July *15,1970. .. Hinny cuantinne annnarnine the m3 ectrien1 board varc resolvad. ~ cnd vs 'cgact to rat- . tiring diagrcus with cur et --cnts cc prc= iced. Prcductics cf this bocrd, alrecdy stcrted, should precced without di.fficulty., Questions concerning precurement of device: by Volfo & M ri for tha left section or tho scin bocrd (referred to es vero resolved. Wo hevo since forwarded decvings Panel "t.")4'2-67, h, 70, and 70.'., c d ogect to hevo dimen-for Ite=c 60 C. siens of the talep ens handcat seen. Iac.: of this infor=ctier chould not be a nc.jor problem. Prcduction is scheduled to stcet July 24. We hnvo cinca learned thtt the best chipping premica Wolfo & censiderins overtino cad curte.iled vecctions Mann can ncke,for tho electrical beard end Janut.ry 25 for the in December 8 Icft &d of the nnin betrd. Energiccticn of the stction bucas frcm tnc 115 kv lines 'cy Docenber 1 is, he if shop, inposcible. thereferc Ship ente could be cdvcnced by throa vae tecte vars waived and perfor:ed on tho job. Va bolieve this cheuld b censidered. 6 O

L 3,....,.. ca.. excicaugweaann %y /' A&+ 5 IRB 2 July 27, 1970 No premise can be given for shipment of the nuclear section i l of the cain borrd until Wolfe & 1:a.*ut have becono acqucinted with the centants cf the severcl C.E. dravin;;c cyplying to i, back-of-board. C.E.-supplied devices. These dravings aro i ^ all stamped "Prel4*-4e y" and are not. entirely cocrdinated With C.E. equipnent lists thich shc.ald be updated. Also, we lack certified cutout drawin s for ceny of the speciel itens in C.E.'s supply, and unlese ve receive these soon, delay of the senter section can be expected as well. We are reissbg all our arrangement sketches and natorial lists applying to the main beard to incorporate all changes and additions made since the last issue. When these are in your hands, we urge that an early nesting, including C.E., be held, so that each iten en the board can be reviewed. l .g p- ' Beemune of ':he incertance of 'm4ntaining redundant channel . cat;cn ana s vs car.nos, w.u.a samacence, term s un Wolfe e Mann ccn confirm our + suggestsd locatica cf ter= W i blechs in the nucle:r section. It appe:rs therefero, that ductuerk in this vicinity of the control roo,m must remain unfinished for several weeks to cc=e. L 6 Yours.very trulv. \\ .H. T. Dickson-Senior Electrien1 Engineer l Enclosures navu 1 i i 4 e 1 I ~ P R f '4 m.. m.

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• MEMOR ANDU M

[ g g: 7 To DAR .. August ?$,1970 s 1.14 ~==>a= FM yDB FILE ECN WIMO ~ ~ ~. - SU:: JECT MELTDIG AT S & W TO DISCUSS CABLE SGEDUI.ES I went to S & W on August 19, 1970, with the view of deter::ining the accuracy of the cable schedules drawn up by S & W. I came away feeling,co.nfident that S & W hadithe procedures and documentation necessary to assure.mo that the reliability I was looking for did indeed exist. The following represented S & W: H. T. DLekson E. E. E1muts (Chief Designer) L. Frey (Site C/C Digineer) Mr. Dmts began by outidning the procedures by which raceways were assigned to a particular service, for exar:ple, tray B for 6900 V and h160 V power cables, tray Ca for train "A" control cablest tray Cb for train "B" centrol cables, etc. (The tray assigr.ments are shoun in S & W dfMng Sf-D2DTE, and'F). With this infomation at hand the designer knous exactly which trays he may and nay not use for a particular cable, this astres that the desired seraration between different types c2 cable is aluay,s maintained. Information telling the designer the precise service of a cable is obtained from the one line diagrams (which indicate all safety related circuits by an asterisk) and from a column in the cable schedule (which gives the train designation). In the case of reactor protective system channele the cable designation itself contains informatien that indient,es the channel to which it belongs. A procedure has been set up with S & W site by which site requests eles.rance from Doston engineering in writing before they pull any cables. On receiving this list S & W Boston checks out each cable in the list to make sure the routing shown in the cable schedule is still correct and that it satisfies the cable ,4a separation criteria. They check if site has the correct revision of the schedule I and t. so indicate on their reply any reference to other dravings that may give spe.id instructions pertaining to that cable (such as spacing requirements etc.). In the course of assigning mutes to cables the designers keep track of tray thermal and phy.dcal loadii 7hermal leading is controlled by not permitting l more than one layer of power ( cable in a tray. If this is ever exceeded then 5 the designer must make a detailed analysis of the cables in that tray to astre that another layer can be added without oppiociable effect on the temperature rise of the cables. Tray physical loading is also recorded at predetemined sections throughout the plant, and at request S & W can determine the cables at any desired section in the plant. / Ve Nn discussed the raroblem of redundant cables crossing at intersections of ,barriered trays. S & W have a method (shoun in drawing FF.-Jaf, rev:.sion 5) by which crossings are made without violkting the cable separation criteria. f i \\. e e

i k s g'. l 21s. 9c / i /t E F, 7 DAN I,. l /. hge a 1 Assuet 25,1770 1 l i We also discussed items such as their basis for power cable soloction, documan- ~ tation of cable pullins tensions and minima band radius. Cables are selected /' *.';' d .aecordLag to IPC% and 5 6 V standards which supposedly contain all the desired infomation. Mf.nimma band radLus is specified in some cases (drawing F5 38D). W. DLokoon wi13, look into documenting something that will'oover all cables. Cable riiing tensions are indicated in NYS-2300 - Instructions for, Handling and Zhstallation of Tower Cable. ) Mr. Dickson is preparing a letter to us outlining all the procedures followed by 8 & W in preparing ard. checking the cable sche &tles. . v. oct JW 388 d2 DEV 4. x.)wM g a 1 8,3 O e 2 d e e L 9 e e 9 a ? e i I ,8 ~... --....,,_....___m...._ g

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F R.G 0. 8 \\ NOTES OF CONFERENCE ,i toston, Massachuset ts 3 September 1970 Those present: Maine Yankee Stone 8 Webster P. R. Selhumeur H. T. Olckson F. D. Saxter E. E. Elmuts

8. 8. Seckley Atomic Energy Commission E. M. Howard R. F. Helshmsn Reglon i Compilance Pu rpose:

This meeting was called by the AEC Olvision of Compliance to review: Stone & Webster engineering procedures related to power and control cables. Olscussion: Compliance has written to DAL stating that our statements that "lEEE 279 will be observed" and that "barriered trays constitute separate raceways" are in confilet. Compliance does not believe that barriered trays are acceptable. They are leaving it to DRL to make a determination. ' Mr. ' Ole'kson described that bas is for sizing _ pcaver cables _. These are cons T eered to, be #5AWG and larger. Stone & Webs ter uses the folicwing assumptions: Motor current for name plate full load plus 15% service factor 100% load factor soplicable duct bank configuration e use IPCEA empacity tables for these assumptions use next larger AWG size conductor pcaver cables placed in one layer only unless specIal review approves mui t e pie _ layers or reduced spacing. The tools used in scheduling cables were shcun and their use was demonstrated including: Job memoranda giving cable sizes to be used cable tray loading sheets tray section diagrams cable schedules marked (*) one-line diagrams. l e

f s. E 16 - 74 .ukf 8 .g. Notes Of Conference loston, Massachusetts $ September IS70 Compliance was told that the cables in a raceway sould be identifled f rom the document 6 lis ted above. At some point Stone & Webster will be asked to issue the trey loading sheets so that spot checks in the field can be made. Mr. Howard kept repeating that they were looking for evidence that tialne Yankee was being built to better practice than conventional plants and conenercial standards which he lumped together. He feels the IPCEA tables are not conservative and constitute marginal design. N Mr. Howard read a fair portion of the Stone & Webster electrl-cal job book and their book of engineering memoranda. In closing he said he had no problem with the system for Maine Yankee. On a new job a ha would expect to see written engineering pro;4dures covering the design tasks. The lack of formall'y ' others him but he will accept it o on, Maine Yankee. ~ Theclosingremarkswerebrief.ly'discussedby$.T.Dickson ~ and B. 8. Backley with H. V. Aedgate after the meeting. 888:sek G' O a 9 y e

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7 a M.95, l .THZ WOLFE AND MANN MANUl'/sCTUR!NG COfAPANY bY b 'b. k POWER CONTROL. SINCE 1922 Fra # NO sason sin!tfs. DAttuer.L IAAMW:D titit inn t.t.tl30 22.4 - 94, September 17, 1970 lMF 9A Stone & Webster Engineering Corp. P.O. Box 2325 Boston, Mascachusetts 02107 Attention: Mr. H. T. Dickson Senior Electrical Engineer

Subject:

Maine Yankee Atomic Power Sta. Stone '& Webster P.O. MY-127 Our S.O. 15630-A, B, C t 1563] Gentlemen: After reviewing the revisad single line drawings and criteria for identification e.no separati,on of electrical cables forwarded with your letter of Septenbcr 8, 1970, Wolfe & Mann initiated c. conference call to your engineering office to clarify your requirements. The fellowing personnel participated: Mr. H. T. Dickson ) Stone & Webster Mr. D. Morash ) Mr. L. L, Bopst, Jr.) goyge g Mann Mr. G..T. Bailey ) After a general discussion in, regard to wiring separation, Stone & Webster engineora advi' sed the following: 1. The document id3ntified " Criteria for Identification and separation of E3ectrical Cable" is primarily for field use, but was sent to Wolfe & Hann for our gen-eral information. 2. In Section 1, Paragraph 3, it is noted that it would be desirable to maintain caparation for non-safety related circuits from emergenc; buses and station b a t t e r i e s,,_lY, o l f e & Mann has been instructed that'it _is not necessary to Sena ate any non-safety related .g_ircuits. (' D s

l l e. .e 2 Lc -94 Stone & Webster Enginuaring. Corp. per p ( Page 2 l 4 September 17, 1970 f,gg ^ Soction 3, Paragraph 1, lists methods of identify-I h W 3. ing safety related circuitr and non-safety related W circuits. No identification Js required by W&P. y -w 4. Section 4 is not applicable. 5. Section5.1, Paragraph 1,definessej>arationof alternating current safety related circuits orig-inating from 4 }N bus 5 or 480 v. bus 7 and buses d 3 \\{ 6 and 8. The only circuitry we could find on the i p k [ main electrical' board was for a few voltmeters,Wolfo&Mannwas'if "y ammeters and ammeter. switches. advised'hatthesemetersdidnotfrequiresepra-Ih_ 2 tion. y as=== 4 p 6. Section 5.6, interior lighting will not require separation. 7. Wolfe & Mann was advised that " Train A" only meant . Battery 1, bus 5, and bu's 7 wiring and Train B" only meant Battery 3, bus 6, and bus 8 wiring.- 8. Wolfo & Mann pointed out that a few synchronizing switches were identified as being critical.' The ? ii h i i .gn v w r na on any sync ron z ng switches which is to be separated is that which will be interlocked witn a control _switsh in a critical circuit. In summary, it was decided that the wiring diagrams sub-mitted with Uolfe & Eann's letter of September 14, 1970, moet the necessary requirements, and no further action is required on,the part of.Wolfe & Mann. Mr. Dickson then pointed out that A_erminal block layout drawines o'n, Stone & Webster needed the combustion Engineer-Jng ~% Ile said she pouring of the floor of the con- - trol room uns being held pending this intormation, anci that it was needed as soon as possible. Ile elso indicated that Mr. Don Pidretti of Combustion Engineering was recep-tive to the idea of coming to Wolfe & Mann to discuss the design of the racks. We are receptive to this suggestion, and will advise Mr. Dickson when we are ready for this dis-cussion. Yours very truly, TIIE WOLFE & M7.NM F'. CO. ,,lY Mk l G. T.. Bailey # Project Engincor GTB/jd cc-- T. A. Maquire SM: D. C.,Cahl I. R. shoou B. De:-k12v Im! na vnhoe P. rj. H w i r.v 7, y, u _.,.

g.f Mr. B. B. Bockle) . W stbora

• Maine Yankoo Atocic,Pcwor Co pany Q.N - y f Q. ;,.,. '... g ',.

j~. , _y Q - J.O.No. 11550

nYs-3587.

E.IES OF CONFERUCE MAINE YANKEE ATOMIC PO GR STATION Ev1d in the offiie of Stone & Webster Engineering Corporation Bostor, Massachusetts September 29, 1970 Present fort Maine Yankee Atomic Power Compan'y Mr. N'. Baxter Stone & Webster Engineering Corporation - Messrs. E.E. Elmuts H.T. Dickson ~ The purpose of this conference was to discuss apparent errors in cable schedules detected by Maine Yankee. Many of these were shown not to be errors but a result of confusion or mis-understanding owing to one of the following:

1.

• Assignoent of different functions or services to the same tray number but in separate areas of the plant.

2. Unawareness of tray loading schedule key plans not yet issued and consequent reference to the wrong ' a&.. tray sections. M As a solution to No.1, Mr..Baxter suggested that tray.s. be renumbered so that each fune' ion had a. recognizable tray number regardless of tray location. Mr. Baxter instructed ' Stone & Webster by telephone the following day to disregard this suggestion. No. 2 vill be clarified by a new issue of loading schedules. Some errors pointed cut hy Mr. Baxter were real and admitted by Stone & Webster. Most of these were in routing redundant circuits in the same tray section. However, all of these errors were in cables not yet released for pulling. When these cables are verified for pulling a final check will be made. O 4 1 g -4 n.

n c -u . ~ g .gGF 4B \\ ~. '. .6. .7,' 'N In at least one instance No.12 instead of No.10,as agreed. ammeter leads were scheduled as This will be corr.ected. In the beginning be pla'ced in the,same tray with power cable.it was intended that no control grossed and tray space he~ scarce,' control cables wereAs design' pro-placed with power cab.le sparated from them with a barrier.

.v 1 By telephone the follow c

ry. ' Mr 7,w Fi a,. Baxtor instructed Stor.e & Webster that to satit i i must not occu,py the mate . power and control cable. e ff. Tontrol cable was defined as any cable, excluding ins; sw tion cable not producing appreciable heat and cou) loads such as valve motors ;./ Noisting apparatus or No.12;n.a.1.s pow vice which is not' loaded to x.. than 50 percent of its capacity. .~.. Sep'uration of redundant circuits in a transitio'n between ~. horizontal trays and vertical risers will be acccmplishad "?, by sheet metal dividers placed af ter all cables are pulled. ,,, hose will be designed on the job site to suit each condition. .m ..e 9 g M' @ O g e s g. Y .o e t

G,. A c!.f ' *; ;f-u g.. y. s e, t,e v i - (Lc F k ., 1 t 9 ,7 wme l REPORT OF CONFERENCE -February 4,J1971-1., MATM-COMTROL BOARD - PANEL B - W/M S.O. '15630-B i Wolfe &- Mann presented Stoise & Webster with one (1) marked . print each of Dwgs. E-2200E, sheet 10, Rev. O, and E-220SE, 1. Thace drawings show changos and/or - e o' Sheet 14, REv. 1. " ' * * * - additions made by Wolfe & Mann'since previous submittal hand-delivered by our Mr. Lee-Bopst. Those_ were reviewed by Stone & Webster, who advised the - 'g ~ fo11owing2 7 F - ) ' Terminal Block "S" cannot be relocated, as Stone-A Webster has already planned their cable runs based 'a on existing location.. ~. - Added wiring to Terminal Block "U" is acceptable. b) Stonc t. Wr.b her rn :ue.itad.that.Panelboards DP/CE1 and 24

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DP/CE2 be relocated to Panel C. Stone & Webster advised that the connections to Panelboard . 3. Wolfe & Mann it-to -DP/ PAC'are shown on their elementary. review the'se to rake sure th wiring diagrams. l._ The followin'g CE drawings were presented to Wolfe & Mannv 4. .' D-44G7-414-211, Rev. 00. 1 - ' D-4467-412-350, Sh. 2, Rev. 02 D-4467-412-142, Rev. 02 -D-4467-414-461, Rev.:03 E-4467-412-25,0,-Rev. 02. Although.the diode relocation, as-discuscod betwoon -NOTE: and Mr. Larry Lambert of Combustion

• our Mr. Sid Kat:

/ Engineering, has not bocn incorporated on Dwg..D-44G7 as shown on Wolfe & Mann's drawings. submitted to Combustion Engineering was. satisfactory. 4 N ^ e t s ' ~ ' .s ~ s .m,..,,

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^* WMMC ~ Report of_ Conference - Page.: 2

5.

• CE D'wg. E-44 G7-412-350, Rev. 02, has been revised, and now' shows Power Supply X20, which is mounted in panels rer;erved for-CD equipment.

The (11) Power Supplies previously shown a,s part of Stone & i.'obster, Item 4AA 255 are not required. 6. The four (4). Power Supplies shown on CE drawings and received by Wolfo '& Mann are not listed on the Stono & Webster equipment list. There are required, and if possible, they should be added by Wolfe & Mann. O e t .G.T. Dailey ~ xmb ,e f e 9 = g g g e G O g 4 e .w

MEMORANDUM 115 - 9 (, : /tc5 g# To DLN ' Fr.bruary 19, 1971 ~ E 1.15 ~ ~ ~ - ' = ynog OTD ystg ECD: HI 29/71 aafs>tcT TRIP TO WOLFE A!TD !RW TO IISPECT 3 SE=C:t OF !E IMDi 00!!TP.0L BOARD The inspection of the B Section of the E main entrol board at Wolfe and I! ann indicates that nore direction and r'd=Was regarding cable separation is needed by Wolfe and :hnn before the 1: iring is started in the C Section.. Ibst of the safety chsanel viring vill be located in the C Section of the main control board.

• he natal work for this section is presently being fabricated and no uiring has been done. Although Section 3 contains a mininal anount of reactor protective instru.entation, some of the observations made in this

~ pection cones..ing separation are as follows: ,A.. Mde range instrcnentation, which are protective channels, do not have cable separation but they are all run'together'in one cable harness. B. Color coding is used on the Tavg-Tret recorders. These are not protec-tive instrumentaticn, but are strictly fren the reactor control systen. It is the intention of Wolfe and linn to run all four reactor protective channels in one co.. on tray without ar.y dividars and maintaining a separation of tuo inches between cables in these trays. In a meeting of Jr.nuary 6, between CE, S & W and Wolfe and P. ann, a minier.:n of two inch physical separation was agreed uperd but if these four channels r.:n together in o'ne tray, it is dcubt-ful that they will be acceptable to the AEC. O ror the saxe of c=,rertson, scrarate e=ciosed c.etas race =axs for each chi==e1 vere used to obtain cha.nel separation at Pa111sades. h' hen these leads left the enclosed tray and uere within close pro:P.ity of one annther, they were enclosed in netal jac:cet. Then separate channels were ro.c.ed to neters in approxinately the same location (1/2 inch apart) the cables vero kept apart b-/ nylon separators. Pc rer r.:pplies for the separate channets uere lu.ated in indicator netal be:ces. r CE has stated at the Janua.7 8,1971 neeting with S & W and Wolfe and Linn that they are not satisfied with the se;antion as propoced by S & W and *, believe they are justified in their concern. It is recor. ended that a rt.presentative of IE be present at all futura neet-ings concerning the rW control board. t GTD/snm j cet B33 3 Jpy e e a y \\ ( ~!

l'. t e 22y-yg : gap x, s wmMc,i REPORT OF CONFERENCE E: February. 23, 1971-a PLACE: Offices of Wolfe & Mann i Baltimore, Maryland 1 Combustion PRESENT: Stone & Webster Maine Yankee Enaineerine Wolfe s' Mi Carl Pabler Bruce Beckley Jim Veirs Geo. Bailt .1 Doug Morash George Doud Ed Brown Bob,Listor PURPOSI: To review propened method of wiring separation for "O"'Section l O

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Wolfe & Mann. presented,one (1) set of "C" Section mechanical drawings to each company. 2hese were then used to discuss _ method of uf rine separatien 4 It was agreed that the plastic' troughs and routing of wiring, as proposed by Wolfe & Mann for the rear and top' sections, was satisfa: tory. It was also agreed that critical wiring could be routed with non-critical iring. Maine Yankee w w ration planned for the,as not satisfied with the 2-inch sepa ~ front section of the board. It was proposed that the front horizontal wire trough be increased in size and barriered into four.'t) sections. This trough would then be used fo: four (4) critical wiring channels instead of for common wiring. Maine Ytnkee also advised that flexible armored cable is to bre _ used to protect and isolate the_ wiring to the reactor p-in pushbuttons. An extra contact block I Fatso to be added to these buttons in order to obtain more physical clearance yetween the critical. wires. This change will have to be made in the field, as both the "A" and "B" Sections of Main Control Bbard have been completed by Wolfe & Mann. buttons are on the j'C" Section. No reactor trip I j I l t j x l 2

_7 7 2/2.Gj.*14 g M t., z.

• /,

-Q. MC Report of Conference - 2/23/72. - Page 2 / .s ife & Mann advised that fabrication had progressed to the p' int where the trough systems have already*been made. o and proposed changes would increase cost of board. Both Maine Yankee and stone s Webstar concurred with this state-ment, but wanted assurance this change wou'ld not affect delivery. Wolfe s Mann then determined this work could be performed in time to catch up with the job and not'further affect delivery. - ~.. O George T. Bailey TO i \\ 'O g 6 g. g 0 4 I oI l .t i, g e a

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h~ 2 Z. 4 - W - acf 13 Ta,,l DiH Februarr 25. 1971 ~..- FnoM OTD Fit.g ECD: MT 31/71 SusJECT MEETING ON SEPARATION REC.UIRSTE!TS_OF !E MAIN CONT.E' BOARD AT WOLFE AND MANN GI, Those present: Stone and Websi,er Maine Tankee Combustion Ihgineering J. Viers C. Pobler .B. B. Beckley E. Brown D. Morash

• 0. T. Dowd This meeting was held to resolve cable separation problems in the MI

-main control board. The specific problens are described in more detail. in a man.) from the writer to DAR on February 19, 1971, ECD: MY 29/71. I The B Section of the main control board is scheduled to be shipped by March 5, 1971. No changes win be rade on this section at this time, so

• Q that shipnent win not be delayed.

On both the A Section (treviously shipped) and the 3 Section, four batteries are brought to two reactor trip buttons located next to each other on the benchboard. Ar=or covering trin be umed in the field to enclose the cables frop t.he trip buttens to the ~ termination on the physicany secarated teminal_ blocks. This will prol vide some separata.on. l The C Section of the nain control board tdn be changed as follows: l A. Be intention of Wolfe'and Mann to run four different channels of the reactor protective system together in one tray with tuo inch separation has been changed so that a deeper tray trill be instaned with netal barriers in the tray. This will provide more adequate separation for each cf the four channels. The cables trill exit from the bottom of this tray and will be routed to the particular instrunents on the front l l of the main control board maintaining m Amn separation, mis tray J wi n be covered. B. "At the reacter trip reset buttons, four batterias are tdthin close proxirdty of each other. On this wiring, armor covering win be used from the individual reset buttons out to the physically separated l teminal strips. C C. Color coding tdn be used on the vitki buses. If this vital bus goes to a_ channel other than a pr.otective channel, the color coding idll _not be continued on the signal leads in that channeJ.. 7 D. Engineered safeguard cables will not be color coded, but the nylon cable clamps on the haranestes will be color coded according to channels. ~ E. _A vital bus, a d-c surely and/or a reactor vretective system channel,- trill be allotted in the sr.e channel of the ditidad trsz as long as l-they are comparacle c!nr.nels. // 7 l \\ l s

714-q 6 .- DAR l REF g Faga 2 l 1 February 25,1971* ' F. Protective system channels running fron'the front of the main control

• board to the rear of the main control board will go into separate plastic troughs, across the top of the MCB and down to,the protected reactor systan channel areas. Vital buses, batteries or protective' Shannels which must run oor. ween sections or the HCB will be run through raceways on the top of the mais contF61YaTEWch are physie2T17

~ separated. Wolfe and Mann is looking into the constmetion of this divided tray which will be inserted in the C Section of the main control board. Diey feel that this will not delay the deliver date of the main control board (which 'is now Jiuto 17 1971) but we will know for certain within the next three or four days. We have achieved reasonable separation within the main control board although in sone areas it does not approach that within the Pa111sades h. board. However, to have achieved any further separation at this tine would have caused a further delay in the de11ve:7 of the C Section which Projects feels is not acceptable. GTD/s=n ect JDV BBB e O e 4 S ,8 e ~

..,r. \\ = ^ ~ m.% K /M. ~ s y 4 T,HE WOLFE AND MANN MA'4UFACTURitd3 COMPANY IY MY.6 < 9, ) .,I. ,, e POWER CONTROL GINCE 1922 som ano sesson stattis, SALT wont. wranA=3 rias sast; ass 4eco March.1, 1971 i c 5m.b & m Stone & Webr er Engineering Corp. kk P. O.. Box 2325 Boston, Massachusetts 02107 g $ b d. - Attention: Mr. H. T. Dickson Senior Electrical Engineer di, g// y-S.*bj ect: Maine Yankee Atomic Power Station

• Q Main Control Board Panel "C" Combustion Engineering Equipment Your J.O. 11550; P.O. MY-127 Our S.O. 15630-C & 15933 l

Gentlemens s Enclosed are tour (4) copieschourxeper of Cc #a-- - A nted February 23, 1971. In reference to this report, we have the following comments: l i 1. We hav3 reviewed wiring on the " Bench" Section of the Main Control Board, and f'.nd that except for pushbuttons i located in the Reactivity Section, all wiring is either j for "A" or "C" circuits. Consequently, we recommend that the frent herizontal_ wire _ trough be barr,iered into three

13) sections instead of four _ (4), as outlined in refer _

enced cJnference report. 3'his trough would then contain "_A" and "C" circuits and common wiring. (Refer to marked print D-6510, enclosed. ) Reactivity wiring for "B" and "D" circuits would be run in n exible armorea cable. ~ '2.' In addition to the above, we also propose to run conduit in the vertical troughs required to maintain separation. 3. Discriminate use will ra made of flexible armored cab 1e and/or conduit on the vertical portion ~of Main control Board where we believe it is necessary. 7-4 2 l r

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• ' Stone & Webster Engineering Corp.

March 1, 1971 Page 2 ./.

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) These recommendations are.being made based on our interpreta tion of Haine Yankee's prefe'ences. Any increased cost would r .be covered by Wolfe s Mann engineering change order and in-voiced to customer. .s May we please have your comments on the above by March 12, 1971. l Q Yours very truly, I .THE.WOLFE & MANN MEG. CO. George T. Bailey Project Engineer GTB/rmb . Enclosure cc-Mr. F. D. Handley Mr. G. L. Koch 6 l t g 9 a C ) g 4 O ,g. e G e g 8 9 Y.

72.6 - W - Rap /r ra DAH May 11, 1971 gy 1,1g l OTD FILE ECD: MY 73/71 (fnoM l s, SusJECT TRIP TO WOLFE AND tuNN / 4 )

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At the request of S & W, I went to look at' Sect' ion "C" of the Mf main control board to insure that the separation criteria was being followed. Since a meeting of February 23, 1971, between Wolfe and Mann, Maine Yankee, S & W, and CE the separation criteria has been fonowed quite closely by Wolfe and P. ann. Two areas were discovered where there was a discrepancy in the separation and these were as follows: A. Semi-Vital Bus Wiring This viring was color coded ar.l. separated the 'same as the vital buses. This carrie s _secaration one sten further than was recuired but can be left as it is with one exception. Valves which suing between tvo buses must be re-_ move d, _f. rop _t_he AeparAt_eA,gr_ougi.ng_p f_Ae. ti_ _ vital _b_uy e s_an4Jpple d_bo th se _, parately from these buses and sep. rate from each other. S & W has been notified and they will nake a deter.:ination as to whether the modification will be made at Wolfe and Fann or at the Maine Yanitee sita B. Seoaration* MY requirements as to t?ie, separation between cables on the SLgna instrunent g (U protective channels uas unclear to Uolfe and Fann. Y.ese cables have not yet been run but Wolfe and I~ ann has been advised that extre.ne care must be used in the routing of the ca' ales. If trerer seraratien cannot be achieved _ they vill be protected with an armour sleeve. The comJ.lon date of the '"C" Section is still firm and should be : hipped to tt site th.aiddle of June. 4 OTD/s=m cc: JDV BBB 6 k e W 9 9 6 g 6 g e L y (, e __1

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'T.J.! r.it; JDV-La:st W 3" #11' Mr. J. F. Gibbons, Project Manager + Combustion Engineering, Incorporated TechFilf _7 s,wp 1000 Prospect Hill Road Windsor, Connecticut 06095 Dear Sir Cable Setaration r You have raised the question about cable separation of various circuits. Please refer to FSAR Section 8.3 7.7. Since the earliest day of this l project we have said we would maintain geparation as recuired,in_secer-dance with u.:.,279._ And to the best of our checking and auditing we are. Separation criteria for Maine Tankee are based upon the use of separate raceways. A barriered tray sectien r n"=+A +"+ = = a separate _ raceway. Therefore, a single tray with three barriers constitutes four raceways. We have further maintaine4 that safeguards and non-safeguards functions may share the same raceway. ,Thi's separatien-criteria a 7rtd Ito ia'ck ~~ and panel arrangements too. M These matters have recently been revieued by AEC DRL and DRS representa-tives at the site and found to be acceptable for this project. We appic iate your concern and observations but believe we are in conformance with our license application in all areas. L very truly yours, ct Bnice B. Bockley Project Engineer BBB/sek cc: JVALongcor i () JRSantry ( \\ EJSur:wiec ))l JBRandazza i, ~

- - - - - - - - ~ - - - ~~ ~ tor.rovrmrivv m Y 7 C - 44, REF I3 TO DAM June 1,1971 MI 1.15 F=oM GTD F1L.E ECD: Mr 76/71 ( SusJECT TRIP TO WLFE AND MANN '.. Those present .f...- .' Stone and Webster

,

. _ Wolfe and Mann Maine Tankee C. Pabler

0. T. D w d.

G. Bailey D. Morash ' P. Belhumeur On Wednesday, May 26, 1971, I went to Wolfe and kann'with Stone and Webster to resolve.come questions on separation concerning the Sigma., instruments on the C Section of the main control board. The major ites was that concerning the separation of the wiring of the 214 Sigma instruments in the protective system. Due to the close proximity of these instruments it had previously been suggested that _to achieve the_ Aecessary separation it night he necessary to use an amour mieeve over the__ .11_gma cable. It is evident, ho.iever, that the armour sleeving would stress the Sigma connector to such an extent that it could damage the connector. Specific routing of the cable tras agreed uren obtaining the meximum separation fo ssible.- ~ The C Section of the main control board is scheduled to be shipped the week i of June 1. t OTD/snm i cc: JDV 3 i I = .. + (., p 'l

}

9

I 4 z zc _ y f, _ R&^ f 7 -J.o.No. 11550 Revised May 24, 1971 810ME & WEBSTDt ENGINEnt.tEG 00MPQRAT2DN ND125 0F TELEPE)ME CONVERSATIDN ELINE IANEEE ATOMIC POWER STAIIDR

Jgjg, Check d!7/

Time /d Inod a* Y if this is a deviation Call Date Outgoing from specifications or New [Q 8dtbr of Haine Indes dr a ings u d s ud epios to

• below.

of Combustio, Engineering ' 'and heIOMuhof Stone & Webster 4 90elila (Sh-l Meworandum A4. /37 subsset /i t N.> u~ se.* bLYItr> no $/tl7/ 'D l'cle.1 m b o belhot-$, l rsnr 2.s.7.r a & b h orn e.attJ s.4 C h .9-r-p A nt a k ws 'Mn An- ~ L t c.b u in h M. ~ .Y I q,.) Sign'ature d "7 Copy tos C. A. C4co c!y(wl:et.uci) X WL% der - M.Y-We.sfWo % 'JVAlongeor I 'WCWoodman RHStone LMPerry

1. NRCilbert 1

WJLKennedy _ GWDelaney DJDonnellan \\ DIMattson 'DKFeldtaose DSRoberts MScheibner HTDickson T

• EEDelandson T flD L0Tse/ X CCPebler i

\\ HAP.cters DHDavis AKBoghessian

• DGens,Jr.

LKatler EPIrainer Milsen RMCampbell 'S W -.nnu X 'OSurrecozf-3 __,,_ JAF,opip g(Miss) y

- ~ ~ [. 3MD .l 2 1 c, - %. 'yyy TRIP REPORT i l Nf,C,J,: MAINE TANEEE ATCHIC Post CCEPANT, WISCASSET, MAINE g JULT 12-13,1971 ' PURPOSE CP VISIT: To audit SIM Q.C. activities N1ative'to electrical, l instrianantation and controls. i i m m m T m S: STONE & WEBSTER . MAINE TANKEE ") . L. Frey . F. Belhuineur

3. Baranow g3, A review of the cable separation in tho' cable vault room was made by Mr. Frey and me with t.he following results.

1. Located within a box type enclosure at the floor level of the cable ~ vault roca tre numerous white tagged 1ND series cables. This'scries of cables are part of the reactor protective system and should be identified with yellow tags and should ncaive 1005 SfB quality control surveillance. 2. There are two cables identified as 105PL-79 which is a yellow designated. g cable that crosses a gnen secticn with no barrier provided. a 4 (3 Cable 120FL-193. (green) tray chb which er.tws sleeve 215. This cable lies ~. in close proxamity to a redundant system (.*ellow) and should be provided with, adequate separation. -~ P. Tray *Ca in the cable vault room has.caS'les that exceed the height of the h 7 f;;3 e tray. This condition is in dire:t conflict with the 5th paragraph on pages 8-11 of the FSAR and must be resolved. \\-

• Located below the pnssuriser an the pressurizer heater cables that '

are left unsupported..The weight of the cable is held by the crimp lug tied to the heater element. Mr. Goodie has been infomed of the condition for corrective action. Mr. Frey is aware of all items identified above and will take necessary corrective action. I audited the records relative to 13. cable changes documented through a telecon dated 7/1/71 between Mr.. A. McKin and Mr. C. Gregites. All records were found in satisfactory order. . Located in the cable spreading room are cables 120PL-80, 86, 92,155, 81, 87,'93, 156 and 157. These cables an control and power cables going through J common sleeves to the switchgear. These are typical examples of cables in areas y 'e y in which inte M

• g exist. This is in conflict with paragraph 8 3 7.5 of the g;

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TRIP RDORT 2 JULT 12-13, 1971 FSAR which states that cost rol 'and power cables remain separated. Jankee Iloctrical Engineering Section should advise of the resolution to this condition. ')o c A f, 't E A

.Wct, Paul R. Belh5setir "

~* Quality Assurance hf wr PRE jmb ~ c co s. WPJ v0K .g tus / 333 un JBR F. Bendtsen R. Prouty S. Baranow F. Baldwin 9 8 6 4 e e e y.g ~- as e s 9 g 4 O~ e e' g e s

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• ..f N. R. Gilbert, Project Engineer Stone & Webster Engineering Corp.

P. O. Box 2325 Bosto$ Massachusetts 02107 /Cy'

Dear Sir:

4 ~ # %.. Cable Schedules l Enclosed are "the minutes of the meeting held September 1,1971 with the AEC in Bethesda, Maryland..Tou are requested to implement the agreements which these minutes docunent. The power cables which probably l need rerouting are listed on the attached page. If it is shown that l their present routing does not conflict with the criteria expressed in l the minutes, please advise us and we will review the rect.11rement to l reroute these cables. N you have questions on these new requirements, please call me. ,o Yery truly yours, L s) Bruce B. Beckley Project Engineer EBB /dtm CC: J. F. Gibbons ,, J. B. Ravizzza E. J. Surowiec 'F. A. Bendtsen J. R. Santry J. A. Ritsher R. Lowenstein L. B. ,a g g =' a 9 ,1 0 / e ? S

r \\ 4 &~~.,j [ a Horss Or coryEnEscE v p g..; c z ;... e pathsada, Maryland ' September 1, 1971 = ,' * ? ' ' ' i Those Present: AEC .. Mr CE D. E Cratchfield W. P. Johnson P. L. Barkoski O. D. Parr G. C. Andrognhi A. Facano 'D. 1. Hansen R. F. Heishman

• P. S. Littlefield E Dunenfeld
• T. R. Hencey D. F. Sull.ivan
• J. E. Frad=="

O. Ferrel J. B. Randazza J. D. LeBlano s B. 3. Beckley -/ ?.7

• 5/2h g

aj9 . ~. OFFICE MEMOR ANDUM to 1. Tray Dividers and sides.wil.1 be to i av a. Further overf41'4 = is to t r=ow av I m tc 1 k M (C B 6 l b. Protection will be given te c power cables which cross be this is provided by the arn or 1257 DC cables local pre cablesabovethecr.ossig) affoidid bf theYoYeFof t1 purposes of this requiremez

1. 1/0 AWJ.

c. Certair ncin-safeguards h801 vays with both A train and All such cables will be re) vide arn ccmon path betwe

removed from the trays 1.f -

1 the raceway. L.3 d. Cartain redundant non-safo; i safeguards motor control e already.been scheduled may share the raceway with a a or collectively share the : guar (L cable., In other vor guard cables must get away .with an engineered safeguards cable. [ Any cables scheduled from new on which are supplied from emergency power buses will riot be run with cables from the alternate emergency source. These agreements were reached between DFS, ODP, REH, and BEB. 9 9

7 '_.___ __. _

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2 2C ~ % - fs' r;F zy t sons or coura zuca pathesda, Maryland 8eptember 1, 1971 Ibose Presents gg .g g,' -D. M. Crutohfield W. P. Johnson F. L Barkoski. 4

0. D. Parr G. C. Andrognini A. Facano D. A. Hansen L F. Esishman *-

P. 3. Littlefield L Dunenfeld + T. L Nonosy i D. F. Sunivan

• J. L Fredsan O.,Ferrel J. B. Randassa J. D. LeBlanc L 3. Beckley

...sm ' 8/9 1., Tray Dividers and sides win be extended where trays are overfined. ~,, a. Further overf49147 is to be avoided if possible.' b. Protection win be riven to safeguards cables above and below large power cables which cross between trays.~ In the case or jaWeiblesi snis is pror:Ided by the armor on the li160r cable. For large h80v AC or 1257 DC cables local protection will be required for safeguards cables above the crossing cable which is equivalent to the protection + afforded by the cover of the tray below to the cables below. Zar Durposto of this requirement, large cables v4 D be those larger than J1/0 AWJ. L e. Certair non-safeguards h80r cables have been determined to share race-ways v2 :a co-Ja A train and 3 train cables in the course of their route. D such cables viu be replaced or rerouted so that ther do not tro- -v:.de arrr common path between trains. The discarded cables need not be

• removea trem the trays if this could cauge damage to other cables in the raceway, d..* Certain redundant non-safeguards loads are supplied from engineered i

safeguards motor control centers. The redundant cables which have already been scheduled may be run in comnon raceways. They may also share the raceway with a safeguard cable;,but they may not iniividually ~ or'conectively share the raceways assigned to the redundant safe-i_ guard cable. In other words, at least one of the redundant non-safe-guard cables' must-get away from its MCC without sha'-ing the raceway Nith an engineered-safeguards cable. Ag cables scheduled from now on which are suerlied from emerrency _ power bumen winnot ce run with cables from the alternate emerrencv soured. - These agreements were reached Detween DF5, ODF, Eni, and BBB. G ij O g -J

____ _ _m - .~ -76. t t c -9 c /%S r 't } / Fage 2 NOTES OF C017ERINCE September 1, 27/1 /. r ' Y..,.. n / DAH described the hardware associated with the symetric off set. trip. +. *' As soon as possibly we should discuss with D. Sullivan the interconne':tions .between t.his circuitry and the reacter trip logic. We should try to do this on September 9, A.M. ' 3. f TechEical' Speci.fications were discussed 'and any needed corrections will be made.

• '. 15. DiO will r.=

eview our position on reactor icte;nals seismic reanaly=is and l., S the depth of discussion desired by. the ACRS on transients without a scram. s. --~ Power Cables To Be Rarented' f t The following cables appear to require rettuting ofer a portion of their route in acco:: dance with Notes of Conference of September 1,1971. fM,). 4. Cable No. SE Drawing Ih9PL1 107J 253PL1 107J . 128PL17 107BA 138PL28 107BG 138PL30 107BG 138PL32 107BG 138PLhD 107B0 138PL71 1073H 138PL96) 107BJ .s. 97) 138PL102 107BJ 103 138P1120) 107BJ y,i 121) s ,.183PL2 107DE 183PI50.., 107DF 1h0PL1). 1070 2) 138 [ 10730 128PL26)' 10731 27) 138PL22) 107BG 23) / 138PL 107BH 138PL7h) 107BH 75) g a 4

i..

'TE. 't 't. C - 14 b,' 2 D3 30TE5 CF CONFEREN.CE Septemberi,1971 .........45 4. '..e r . y... ?. r *. <*c g ne,% .,,.. ?.. .Dekte so. ~- varuos .. gras a >... s 109. ..i. Y'.... .-)$L:.i. '~ ......4 .f ; - 133pu3o , 373g ..., i: f... .. 131 J g r.. .s .. s. .s .1287uo. . 107sg ',,, 11 1 y? > h l. J'. 128P m 107ss W. t' '.i '. 7e .r. 6 pp3... s t .~ .... ~'. .r ... dh. s s .. ) v 6 .m g g e. .8 ,,g . O . gg R .8 5. 8 O p e -G

'g. u [ h G O MOf l m s... A _ --ly p,,,.. -e l ENCLOSUpE No.1 7 g, .7 g, e, (2 is F 2] MAINE YANKEY ATOMIC POWER COMPANY .6 2 l }- MAINE YANKEY ATOMIC POWER STATION - DOCKET NO. 50-309 ' ~ ' ' h* f SEPTEMBER 1.1971 d 3, z l fc Susanarv 1' 1 ~ '" ; 7.. T

• t A meeting w/k held with Naine Yankee to discuss the latest (8/20/71) f draft of the proposed Tech Specs for the Maine Yankee Station and to

. gj , by C0 and D. Sullivan of DRS. hoe items included the use of metal y. resolve several items identified at the 8/26/71 visit to the plant f (y 6 * (A1) dividers in cable trays, the u*se of covers on trays, flash protection .s for 480 volt power cables that cross over trays of redundant ESF cables 4.- f. in the vault, and non-safety re'ated ca'bles that pass from one wireway of l ' engineered safety features cable to another wireway,containf.sg the redundant aj engineered safety features cables (tray hopping).- ) ( f

• I...

Datoils lg,{ As a result'of this meeting, the Tech Specs are about 90-957. completed.

., j there are a few changes,to be made; Maine Yankee has to revise portions s

of several sections and one or~ two sections are avatting the results of i analyses being performed by combustion Engirieering. By the end of September, the Tech Specs should be e'ssentially complete, [. We discursed with Maine Yankee th( items raised by D.' Sullivan, (DP,5) and .y l,,,,, 4 i C0 during their recent visit (8/26/71) to the pla.nt. The PSAR restes l-and we accepted, that divided cable trays could os used throughout the plant to separate redundant engineered safety feature cabling. However, i in some 1., cations, especially in the cable vault, the trays are so loaded that the cables extend above the sides of the tray and the cable tray l dividers (barriers). In respo'ase to our concern, Maine Yankaa streed ,Lt.fgend the height of the barriers and the eides of the affected trays to maintain the intended separation._ Ibey also agreed to provide metal covers on all horizontal trays Located in t!ie vault. In some instances, e

t power cables crosa wireways (cable trays) containing redundant safety

-l channels. All 4160 volt power cable is armored so that this practice is acceptable for these cables, however, the 480 voit cable has no protection 4 T o.ther than the normal insulation. Maine Yankee has agreed to provide some 7 y , form of flash protection (probably an asbestos wrap) for.the 480 volt g, t, ;, " cables where., they cross wireways containing redundant safety feature <p-cabling. It was also noted, that there are ntanerous cases where non-safety l 4 9 4 9 6 f a

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-w-p s u n w' -svg GJ e __.m ,. of ,1 19 2 TE Z.26-7C A n c F. L t. 9 reisted cables are common to redt.ndant protectica system cabling. Maine ~ Yankee agreed to reroute all such cables that are never cables of 480 and M*her voltaea and the high current carryins de power cables so cast they would not jeopardine redundant safety feature cabling, subject to confirmation that the above changes have been performed satisfactorily, we consider all of these ite.ms resol.ved. 4 3 9 le 4 4 74 a p

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r t. p b 2 C' 9d ncs;; z3 o n -4 -J.0.Ho. H 550 MT5-4835 30225 0F CO WERE C Matte Trp ATCMIC PO*1ER STATION - Bald in the Construction Office 'of Stone & Webster Ingineering Corporation Wiseasset, Haine, September 14,1M1 Present for

• Haine Yankee Atomic Power Cempa:g (MI)

Messrs. F.D.Baxter V.Litiere (CIP) Stone & Uebster Engineering Corporation (S&W) Messrs. C. A.Coody W.Roettger C.Gregitis D.R. Whitney J.D. Bailey A.HeKim E.T.Dickson - This was an unscheduled meeting caued to discuss certain apparent violations of electrical cable separation criteria. The list of cables to be rerouted given in.the Note: of Conference in Bethesda, ' September 3,1W1, was discussed. 3"W pointed ont that in some instances trays.in the us: protected cable tray room carried no safety related, oables and-need not have been provided with a barrier.*' The removal of the barrisr would elimiLate an apparsat' cable hopping free one section of tray to the other. This procedure is acceptable to HI provided there is no probability ,' W' of adding safety related embles in the future. h 1 % Q. c. A 6 p.4 %. % h J E M " 4Q \\d _1*h, =_m,_m_ i.7 ?* g= %",g g n="rr_r_ y,,._i V -- ..-i ^ a= = =_ S&W will review all 45) % :;over cable n uting for possible similar viqlatiens. The tonoving violations of previously established cable separation criteria hkve been noted: . Floor sleeves beneath motor control centers in the switchgear 1. roca contain both never and control _n).2.g. Because of the limited number of sleeves in a sman space it was not practical to separate control frem power., Separation is not maintained in the wire space within iibe motor centrol center * - and because of the zramber of noter contreuers in a vertical stack, it is not practical to do this.,Eeeause of the ~ .e 4 actica74ty of separating control from power 1.n the " floor _ _ sleeves, the insu.ugtr6h was accepted ~aTbiEltI S l. q: gnc g 4 .m .o s. ~.~sv.wa,,e -ne w-, w,, - -.-

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~z 2. C - cit ao n - 2. 2 In sone instances, it was necessa'ry to. install a barrier . within a floor sleeve to separate.a green from a yellow cable. Because of space and physical limitations, it was not practical to drill another sleeve. Since the barrier within the sleeve is at least as good as a barrier in a trey, this installation was accepted as built. m Although the foregoing violations have been accepted, they are to be con-sidered exceptions and not standard practice. Previously estabidshed criteria shall govern whenever at all possible. ] I 1 Qg) r e 9 9 9 e O e 6 p=

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2: C ~, 1 g (b. ~ ~ se MPJ.CR A NDUM l? 6E % f FRS October 26, 1971 l To . /,Q.. DAH .1 ECD MT 108/71 prnow pg Sum >rcT M ROOTM AT MADE T.ANTJ2 ,.'..ll.,..'..?:'.. o, ,,, 1. Cki Detober ih,1971, you requested clarification o't the recent agreement which Mr made with the AEC sta.ft in regard to the rcmtir.g of cables (tray-hopping). S & W has been applying the corrective measures o_nly to tera 2 eables, and not to control or instrumentation cables. This ~1s the correct intarpretation. The main concern in trayhopping is that a short, circuit f.tult could cause a heating effect in a cable, and if this cable were routed through two trays of redund*nt cables, the heating effect could conceivably disable two retindant circuits. Theratore, the trayhopping s'estrictions are applied to cables which can generate a heating effect; nuely, power cables and 1ATEe d=c Cables. Instrementation Cables and control cables Are used in ~~ circuits which ci.n be.short-circuited without much heat generation and 4 therefore can trayhop without the da.nger of disabling other circuits. Fi. Hansen, Section Head Electrical and Control Derign Section~ DAH/ : n . ces JDV BBB WB 4 ? s g ~ ~ ..v

W ( ~ e a c-h md l MF: 2 s-l TRIP REPORT PLACE: MAINE TANKEE ATOMIC POWER CCHPANT, WISCASSE% MAINE DATE: APRIL 13-114,1972 PURPOSE OF VISIT: To assist in the electrical and instrumentation audit which was carried out by the AE0 Compliance Inspectors. THOSE CONTACTED: STORE & WEBSTER MAINE TANKEE .AEC L. Frey F. Bendtsen b.M.Howard S. Baranow R. Luce R. Maishman J. Haseltine P. Belhumeur RESULTS: A. Mr. L. Frey assisted Mr. Howard during his first day of audit at the site. Ora area inspected was the cable vault room. Mr. Howard noted that some cablas were left unsupported and also the cables came in contact with the metal tray covers that, in some cases, had sharp edges. Mr. Frey is avan as to thi location or tha ochlea $n question and is to take all necessary corrective measures. B. The second day of the audit was devoted to inspecting the containment pressure sensors and associated components. Mr. Howard thoroughly checked the separation of the cables to the sensors and found all conditiona satisfactory. '"h e instrument tubing to the sensors were traced from penetration 61 and 63 to the sensors with the following results. Mr.'Howard commented that lines A and B crossed linen C and D and we'n all within inches of each other which are located directly below the penetration outside of the containment. C. The_ Division of Reactor Licensine (DRL) had instructed AEC Compliance t.o check the safety injection and _other switches located on the==4n control bokrd for proper separation. Mr. Howard found factory installed wires Eii'boETind'B~ Train redundant" switches entering a common barrier channel. He requested that Tankee review the condition and assure ourselves that proper separation exists f for all wires going from the switches (recirculation, core spray and safety ( injection) to the relays located on the back side of the main control roe t panel ksection "C". l D. Mr. Heishman has closed out his outstanding item 'of==v4=n= physical and thermal cable tray loading criteria. U s. l0

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F. z zc-u o TRIP REPORf t ' APRIL 13-1h 1972 PAGE 2 Adf 2 I ~ E. After the conclusion of the AEC audit, the writer inspected the repairing of the electrical penetration (Mfgrg. D.O. O'Brien) with the following results. Upon reviewing the re the work in progress, pair procedure prepared by D'. G. O'Brien and inapecting it was evident to the writer that the repair program was insufficient in that the breakdown of the insulation between the 19 conductor No.12 wires 'was not being considered in the repair procedure. Four of the penetrations had alnady been repaired by the use of the procedure. Stone & Webster Quality Codrol Section has issued a Non-Confomance and Deviation Report and all work on the penetrations has been halted pending a review by Stone and Webster and Tankee Engineering. It appears that potting the connectors and other measures should asaure us of an acceptable and reliable condition. F. Baxter of Mr and H. Dickson of Stone & Webster have since reviewed the penetration problem on h/18/72 and a procedure is being prepared by Stone & Weoster which vill be reviewed by Iankee.*or approval of the repair 29 D. O. O'Brien penetrations. The fc11cving are items hat either require follow-up action or are for information purposes. 1. Cables in cable vault room. 2. Contaiment pressure instrument thbing. F 5 7 3 Main control board "C" section separation, gg s

h. Penistration repair.

wmL Paul R. Belhumeur Quality Assurance Engineer TRB jmb cc WPJ F. Bendtsan IJDi S. Baranov TMS F. Baldwin WJM J. Randazza EDT E. Surowiec C0B J. Hase1 tine JWS N. Gilbert WEP JD7 DAH u 4 e O W e e

zu -u (p. j MEMPRANDUM ggp g ,, 3 ;. 7,,;, n 2. FnoM P. R. Belhumeur pg suancT SAFETT/Nolf-3AFETT CABLE ROOTING AND INTE!DCCIDO Attached you will find Stoos & Webster Memomndum No. 22h. ' It is aquested that you. review the memoran6an and advise this department as to the acceptability of the condition identified in the meno. nnt44

l Paul R. Belhumeur Quality As'aurance hwin=er,

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1. ~ TSh; page 7-1, Instrumentation,and i control, Introduction, para, beginning

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STO E & WE8 STER ENGINEERING CORP'. M. Y. ATOMIC POWER COMPANY '* ! " h ','.. . J' '. tA P. O. BOX 368 WISCASSET, MAINE ,N. ' N Haech 1, 1972 ,.1...l. OUALITY CONTROL MEMORANDUM NO. 224 s,.. TO F. B. Baldwin Atte.. tion: N. R. Gilbertl /H. T. Dickson TROM

5. W.

Baranow

SUBJECT:

SAFCTY,'NON-SAFETY CABLE ()," ROUTING AND INTERMIXING

References:

1.. TSkR, page 7-1, Instrut entation and l Control, " Introduction, para, beginning with."The engineered safeguards.......".

2. Letter B. B. Beckley to N. R. Gilbert 9/2/71, MYB-2172, Attachment Notes of Conference, para. Ic and Id. -{' There are several groups of cables, with cables of both safety and non-safety related kind, routed through separate redundant cable tray sections, cables of each group that are routed together through a common single conduit. (See attached skotch) Cables of each group with trays are: Unnumbered [. Conduit gables Tray gn_d_ cables Trav res fes Pr$ Pes 1. 107PLl6, 4i C5a ll4PLl7, 44 C5b 45 Pps P ei 2. 107PL 1, C5a ll4PL23, 51 C5b 4* P P y J. 128PL90,lO7PLil6 C5a 138PL66 C5b VIsl C C C 4 107PL118,128PL93 C6a 138PL69 C6b c C 5 107PL29' C14a 114PL32 C14b C C C /6 107PL149 Cl4a ll4PL115, 149 C14b No vM P P /p* lO7PLl47 C11a ll4PL113 C11b viol f3 As P ets 8 138PLll Clla, 128PLll Cllb 9. And others g,

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3/4/971:15 PMNS xMaine Yankee Cable Separation TIMELINE n m Draft General Design Crite:ta IEEE 384 issued 'GeneralDesign CritedaIssued PSAR Submitted 10CFR50 Appendix A Appendix R issued Draft IEEE 279 IEEE 279 Issued TMl Start installation of TMI Mods Construction Permit Issued PSAR 10CFR50 Appv'd Appendix B Compliance with Appendix B s. I FSAR FSAR Approved Submittad Low Power Liceese Full Power Ucense l 1937 l 1968 1969 l 1970 1971 l 1972 l 1973 l 1974 l 1975 l 1976 l 1977 l 1978 l 1979 l 1980 l 1981 l 1982 l 1983 l 1984 l 1985 l -g-.. ..j toco44 p.s + S/2 l SWEC MY3-2957 Cable ID & Separa!!on Spec Addendum ,SWEC MYS-2957 Cable 10 & SeparaHon Spec SWEC MYS-1546 Control Board Spec SWEC MYS-1110 5.000 & 8,000 Volt Cable Spec YAEC-1163 Cable installadon Recommendg'on DRAFT DRAET Pap-4 ora

~ Maine Yankee Cable Separation TIMELINE 3/4/971:15 PM IEEE 384 Rev.1 Issued FSAR Rev.12 's.omplete InstaRallon of TMI Mods CAL 1-96-015 LER 96-038 Cable Separation i t 4, 'b k# 8) 1986 l 1961 l 1968 l 1989 l 1990 l 1991 1992 1993 1994 l 1995 l 1996 1997 l 1 STD ELEC-1 TE 226-96 Cable Separation Criteda Rev. 4 l TE 239-95 Cable Separation Maledals STD-ELEC-1 Rev. 3 l [ STD-ELEC-1 Rev. 8 STD-ELEC-1 Rev.2 STD-ELEC-1 Rev. 7 STD-ELEC-1 ,MYC-464 Cable Separation A.Wysis for Apperdx R Rev.1 STD-ELEC-1 Rev. 6 STD-ELEC-1 Rev 0 STD-ELEC-1 Rev. 5 DRAFT 1 DRAET rap 'or2 l ,}}