ML19290A093
| ML19290A093 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 11/21/1978 |
| From: | Morck J METROPOLITAN EDISON CO. |
| To: | |
| References | |
| TM-0961, TM-961, NUDOCS 7910010497 | |
| Download: ML19290A093 (17) | |
Text
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e TMI DOCUMENTS DOCUMENT NO:
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1' OF DOCUMENT PROVT.DED BT COPY MADE ON METROPOLrrAN. EDISON COMPANY. i Supervisor, Doct= ent Control, h"AC 222.1 001.
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WORK REQUEST APPROVAL TMI Nulcaar Station Unit No.
b Work Request No.
bO95 W.0/ Account c -
N' NPRO Fonn lleq'd Priority
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ltems 1 through 5 completed by cri;inatar,
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1.
System:
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Comoonent(nIma & nSber) 3.
Describe malfunction and cause of nulfunction (if known) er modification desigd.
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Oriainator: J 0aterTime:
5.
Oriainator's Sucervisor's Sianature' N[ ((6I
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Does work represent a change or modification to an existin; system or component?
If yes, an approved change modification is required per AP 1021.
C/M No.
Yes No 7a. Oces work require an RWP Yes No /.
7b. Is an approved procedure required to minimize personnel expcsure.
Yes No /
Ba. Is work on a QC component as dafined in GP 1008.
Yes No 8b. If 83 is yes does work have an effect on Nuclear Safety? If 8b is yes, PORC reviewed Superintendent approved procedure must be t. sid.
Yes__ No 9.
Agreemant that a PORC reviewed, Superintendent approved proccoce is not required for tf fs work becau:e it has no effect on nuclear safety.
(Applies only if 83 is Yes and 8b is No).
/
/
Unit Superintendent Date 10a. Is the system on the Environmental Impact list in AP 1026 Yes N
10b. If,10a is Yes,is an approved procedure required to limit environn ental irnpact.
Yes No 10c. A;reement that 10b is No. (Requirad only if pa is Yps).
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Unit Superintendan'6 Supervisor of Operations Date 11.
Plant status or prerequisite conditiens required for work.
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12 Um, s anc Precautians o
a) Personnel b) EqJipment GPU TEST e e~,oement OC O 1/ k.l.
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- 13. Post !3aintenance Testing reamred and Acceptance Crittna. g.1 14.
Estimatad manhours to parf orm ic5: E IC N
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- 15. Maintenance Foreman Aigned:
- 17. Supervisor of !.8sntana.1ct approval to commence work:, ",
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Date N/ t /? *
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- 18. Shitt Foreman Date hpf* IN \\js aceroval ta ecmmence work I
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( !<cf dnitialif Shif t Foreman Tapag AscMation No.
Radetson Work Perm.t No.
signature is not required
- 19. Comments on werk partermed:
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- j Retest mar acceptance enteria Yes No Work Performd ':v dare/ time Work Reviewed. Maintenance Foreman's Stgnaturs fjj~/)[
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Date
- 20. Wo,rA completad and cornpcnent alignad f or testing.
l \\ l.?/O le.itial if 3.F. signature is not required.
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- 21. Tasting completed and component retessa 1 or normM
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. si e is not required.
sn.e Foreman i s,sname oat.
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Cuabry Conrrnt Department review of work and testm eted (QC work only).
s-.ac e a o.. e Na oc oeparemane care 23 Supervisor of Maintenance Werk re::uest and procedure'aregemplete end signsd of f as required. Change / modification f crm has been siened t.fi as required Machinery histcrh.1try Eds-bee 'm'ade,li required.
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. AP 10017 Three Mie Island Nuclear Station SIDE 1
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Special Operating Procedure SOP No. 2 - 7 9 -001
( 1ure 1001-8
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- 2. Purpose ua.io
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- 3. Attach procsdure tdhis form written ac::srding /c the fadowing format.
A.
Umitationsand Precautions
- 1. NuefeatSafety
- 2. EnvironmentsiSafety
- 3. PersonnelSafety 4.
Equipment Protection B.
Prerequisites C.
Procedure
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- 5. O uration cf SD P ' sn.a n. a sea,- e.a so e.v. erom in..eem e.e.
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(a) SOP will be cancelled by incorporation into existing or new permanent procedure submitted by O
(b) SOPis notvalid after MhA.
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- 6. (a) is the procedure Nucf eer Safety R eisted?
If "yes", complete N ucteer Safety Evaluation. er,2., em. e.,m>
Yesk NoO (b) Does tt:e procedure affect Environmental Protection?
If "yes", complete Environmental Evaluation. csi
.t e r.,ms............... YesO No%Q (c) Does the procedure affect radiation exposure to personnel?................... YesO NoK nora: se.n
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- 7. Reviewand Aocroval Approved - Shift Supervisor
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- 8. SOP is Cancelled
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" EVALUATION" N001 Three Mile Island Nuclest Statien SIDE 2 SDP No.2-b (
Figure 1001-8 Nuclear Safety / Environmental impact Evaluation i
- 1. Title
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2.
Nuclear Safety Evaluation i
Does this SOP:
- (a) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety?............................... yesd no 8""
- (b) create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report?........................... yesO nor
- (c) reduce the margin of safety as defined in the basis for any technical specification?..... yesO noY Details af Evaluation es.
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3.! nvironmentalimoact Evaluation
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Does this SOP:
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(a) possibly involve a significant environmental impact?.................... yesO noO t?.................... yes O no O
- (b) have a significant adver et on the e r
- (c) involve a significant [nviroimental r at*=r or uestion not previously reviewed and evaluated by the N H.C.-
...................... Yes O no O Details of Evaluation
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Evaluation By O aili'--------
- N OT E: If ens que.rions a. yes *. the ch. age rhvet r.co.
N.R.C. approwd.
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Review (PCaC, or eneu.non is reauir.4 one, wn.n r.au ted dv to. session succ.nt.ndent/unri suc. int.ne.at. it en, i is nw.
the PORC must conse.t of two off+te Es.)
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Off site M.moer:
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Approval p
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6.3.3 PERNRMANCE EVALUATION A u components of the reactor coolant system have been designed and fabricated to ensure their high integrity and thereby =4a4 4'e the possibility of their failure.
The reactor coolant system, the safety factors used in its design, and the special provisions taken in its fabrication to ensure quality are described in Chapter 5.
However, in the event of a reactor coolant system piping failure, emergency core cooling is provided to ensure that the core vin be cooled and will not lose its geometric configuration. This emergency core cooling standby safety feature is provided by the core flooding system and two independent, full-capacity emergency core cooling trains of equipment.
The basic design objective of the emergency core cooling system (ECCS) is to ter-minate the temperature transient and thus =aintain core geometry in the event of a loss-of-coolant accident. To evaluate the loss-of-coolant accident, analyses were performed for breaks in the hot and cold leg piping. The m w4- ~ break size in each pipe.-as equivalent to the double-ended rupture of that pipe.
High-Pressure Iniection System One of the HPI (makeup) pumps is in operation during normal plant conditions, fur-nishing nor=al makeup to the reactor coolant system, and a positive static head of water ensures that au pipe lines are fined with coolant. Upon receipt of an engineered safety feature actuation signal, one of the evo remaining HPI pu=ps is actuated.
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Fo noving a loss of coolant accident (LOCA), the safety features equipment will be automatically actuated by a signal from the Safety Features Actuation System (SFAS).
The building isolation valves MU-V2A/3, HU-V376, MU-V18, MU-V25 and MU-V377 close, halting all normal flow into the pretsurizar. Normal seal return flow out of the reactor building is stopped while flow into the RC pu=p seals is continued at a re-duced rate. The outlet path is through the seals into the RC system. The sun 1-mf Indrogen to the mnka"*
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Man grade sole A valves in the hydrogen rging line. The high pressure injection G. ms MU-V16A/3/C anc a in tne sa eup lines to tne Icur reactor coolant pu=p dis-charge lines open, as do the suction valves DH-VSA/B in the lines from the Sorated Water Storage (BWST) to the =akeup pumps. The HPI system valves are designed to open within 10 seconds after receiving an actuation signal.
An ESFA signal vill ensure that only two pu=ps are operating; one for drawing suc-tion from the makeup tank (makeup header) and one from the BWST (BWST header). One pump is always alignad to the BWST and this pump will automaticany recei.. et SFAS signal. The system 1)gic assures that there is one (and only one) pump running on the makeup header in :he fonowing mnner af ter an ESFAS:
a) If only one pu=p is running in the makeup header, that pu=p v111
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continue te run upon receipt of an ESTA signal.
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~ g S PT. APPROVAL d) Nuclear
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- 13. Post Maintenacce Tesung required and Acceptance Ciitaria.,1'...w.;hu um, f
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Estimated manhours to perf arm job: E IC M T t/ U
- 15. Maintenar ca Foreman Assigned; h4YvCS
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- 17. Supervisor of Mzintenance ascroval to ccmmeace wcrk: ' l. '4 d + -
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Date e/.I 2./' '. -
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- 18. Shitt Foreman's aoproval to commence acrk
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Cate NM7/W l STE AyPRgyAL,m.uq Initialif Shif t
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Foreman Ta99ng 4,pMatecp No.
Radration Wo a Perrmt No.
j signature is net required
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C ; mments on work perf ormer f77t.$?rG T.31t. PeCM D)t,, TG W.4d)f4t,P LE $D CT;nR., b ~. T=*9/[,,
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Retest met acceptance criteria.
Yes No Werk Performed by dare/ptne Work Review =d - Maintenancs Foramin's Si>:natura NTLloQy Os VO C-!b b
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- 20. Work completfd and component aligned for testing.
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" sa.# Foreman -o'.an +ure ox.
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T; sting complete.1 and compo.a.ent r:ia3:id f or normal use.
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/ Date Qua! ty Centrni Decartinent review of work and testing} completed (QC work only).
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Date 23 Superwsor of Maintenance work request and procedure are ccmplete and signed ofI a: required. Change /medification f arm has been s:mted nff as req 3tred. Machinery history entry has been ma.de if requ;ted.
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WORK REGUEST APPPOVAL i
TMI Nulcear Station Unit No.
Work Request No.
b W.01 Account. : ?
e ?. */ _ NpRD Form Reg'd Priority 1
Items 1 throuah 5 comolated by cri::nator Al 1.
System:
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Comoonent (rkma & Number)Fch <- 1 3. Descrit:e malfur.ction and cause of n.alfunction gif known) or modificati2n desired. ( \\.-o . E-d y,,e t ' 2.. u,ws 1 4 sh / -7'g o p 0%- AQTG;
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00 Tll&lN% Fh9 00~ kCT Gels $=20 nr Qy. LiJDFR - 4. Oricinator: N/ Date/Tima: '/./ Z/. Y i~ 7 5. Oriainator's Sucervisor's Sienature dh)'7/&Lc,d- _- I '/ 6. Does work represent a change or modification to 'an existing system or component? If yes, an approved change modification is required per AP 1021. C/M No. Yes No / 7a. Does work require an RWP Yes No 7b. Is an approved procedure requ' ired to minimize personnal exposure. Yes No Ba. Is work on a QC c::mponent as defined in GP 1008. Yes Nc 8b. If Sa is yes does work have an effect on Nuclear Safety? If 8b is yes, PO R C reviened Superintendant approved procedure must be used. ,Y,es No 9. Agreement that a PORC reviewed,Superir.tendent approved procedure is not required fcr this work because 't has no effect on nuclear safety. (Applies only if Sa is Yes and 8b is 'Jo). / /\\ !1 l ' Unit Superintendent Date 10a. Is the system on the Environmenta! Impact list in AP 1026 Yes No 10b. If 10a is Yes,is an approved procedure required to limit environmantal impact. Yes <' N o 10c. Agreement that lab it No. (Required only if 103 is Yas). 3 Unit Superintendent / Supervisor of Operations Date 11. P! ant status or prerequisite conditions required for work. (),,z... n i e.a. . /:.. :.n ~ /
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L ... - ~....+ _.w . ~. w ....._a.. _a m..,. + ~ ~ THREE MILE ISLAND STATION gf77 APPLICATTON FOR APPARATUS TO BE TAKEN OUT OF SERVICE ENCLOSURE I l DATE / - 7 / ~7 9 CONTROLNO.~~bd AI UNIT NO. T M -f~ L I APPARATUS DESIRED N w J A, c.e u /. r*v a eu r/< s JefDAY j FRCH Oer# a PM' OATE J. ry -7 7 19 _. UNTIl d,- A PM OATE 19 _ AM OAY W':RK REQUEST NO. PERSON INITIATING APPLICATION C S u 4 4 n. - WORK TO BE CONE
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'. o e *L, f fl-(J SI,I i nN L/AJ ~ k EQUIPMENT /PERSCNNEL HAZARDS SWITCHES / VALVES NECESSARY _(One Line For Each Cevice) t* % c-M& W M _k gr y - rj.1 y r f I r. In ! s }}, - y pf-W r. a. y w -tj-2 n 6 ~ e. t' hv -9/ -f a __On h &MM Mv - t/ - A 4 8 ~ n. ~ 9 7 -,, - 1 I a. Ap.,. t/.- t$ ( da-w BLs EBY u.,-v-yr sT /)W e, - 0Lt w-u' /-t[ s i i y J RADIATICN WCRK PERMIT REQUIRED YES NO ALL CF ABOVE FORM TO BE CCSPLETED BY TAG REQUESTOR ABOVE TAGCING APPROVAL: APPROVED CEPT. FOREMAN APPROVED C-w SHIFT FCREMAN SIGNED EW CONTR0f. RCCM CPERATCR GO TO ENCLCSURE I AP 1C02 REY. II (CCD) FOR " CLEARANCE CCNTROL". APPROVAL FCR CPERATICN 2-S-79 GC0o DAIE TIME SMiri (OREMAN I6.0 2221 012 t i u m -ummassums __ _..., m ""'"~~"'W mim** . ~. _.
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M r.,. / AP 1001 Three Mile Isl..d Nuclear Station SIDE 1 2"7I'~ 8 7 Special Operating Procedure S0P No l l Figure 1001-8 crrom sor too ino..) NOTE: instructions ano suicesi...e in AP 1001 must es fonowoo wnen comoseting Unit No. tnie form. /0/#/> 7 Date
- 1. Title 7Es 2.
Purpose cinciuoe purpos.of seen 5 (n +L a a k /L 4 & n an maa,a.2 a cze
- 3. Att ch procedurkto this form writteNaccidding to the follov,'-) format.
A. Limitations and Precautions
- 1. Nuclear Safety
- 2. Environmental Safety
[
- 3. PersonnelSafety 4.
Equipment Protection M B. Prerequisites C. Procedure /0!/ f!78 A. Generated by Y b M. H 4 /c _ - 4 Date i 5. D uration of SO P - sn.n es no sonow inan 90 asy. from the e.fective cate of tne sop or (a) or (b) beiow - wnicnever occur. f Wst. (a) SOP will be cancelled by incorporation into existing or new permanent procedure submi:ted by O (b) SOP is not valid after MV-V W C ALd7< ted.. S o e mein, cane.n.oi uin wi ckcum.sance. wn.cn n re.uit ijn 6. (a) is the procedure Nuclear Safety Related? If "yes", complete Nue: ear Safety Evaluation. (sio. 2 of ini. For->............. Y es E No O (b) Does the procedure aff ect Environmental Protection? If "yes", complete Environmental Evaluation. cside 2 of enie Formi...............YO No I (c) Does the procedure affect radiation exposure to personnel?................... YesO No$ NO,TE: if an answw. are "no", the change may be soproved by tne siift supervisor. If any que.tlons are an.**eo "ve. ine cnance mu. n3.porowed ny tn. station superint.no.ntiun t superintencent. e
- 7. Reviewand Accrot Reviewed - List memoer-IiiC contacted d b M9'"
g [- r/0h$ Ml$l? 37 %m 4/ahT / f Approved-Station Suparintendent/ Unit Superintend [ A-A g u
- 8. SOP is Cancelled
( i n 1 a sn.ft so en,s..,,snat,orem." (. ( L. I rui as 4-75
2.~. ?. L. \\ " EVALUATION" ~ AP 1001 } Three Mile Island Nuclear Station SIDE 2 SOP No. Z'76~h7 _ Figure 1001-8 Nuclear Safety / Environmental Impact Evaluation
- 1. Title Q
t
- 2. Nuclear Safety Evaluation Does this SOP:
- (a) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety?.................
........ yesO no E
- (b) create the possibility for an accident or m51 function of a different type than any evaluated previously in the safety analysis report?...
.................... yes O no F
- (c) reduce the margin of safety as defined in the tesis for any technical speci ication?....
yesO no? Details of Evaluation ie.. n v.nv to.o.v. oo t.on..,. no. att..n.co.t. n.:. ie c.au r.o.)Mn4 Sep hL h n 7a. ? 4 4 & cf Ma.4zJ,c2 A lb. Ach SW A W'U M :" f
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IW k valuation By G [.}}?i9ul ate to-19-79 3. EnvironmentalImcact Evaluation Does thisSOP: -h (a) possibly involve a signifi t environmen'iq impb?.................... yesO no O f. ffect on the envf onment?................... yee O no O
- (b) have a significant advet
- (c) involve a significan ironmentalf ma' " "
as. ion not previously reviewed and i ..................... yes O no O evaluated by the Details of Evaluation J X ~ Evalcation By Date
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