ML20202J262
| ML20202J262 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/03/1985 |
| From: | Lieberman J NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Axelrad J NRC |
| Shared Package | |
| ML20202H992 | List: |
| References | |
| FOIA-86-244 NUDOCS 8607170050 | |
| Download: ML20202J262 (326) | |
Text
{{#Wiki_filter:. . .
. July 3, 1985 i
Ncte to Jane Axelrad Director
- Enforcement Staff FEFMI INVESTIGAf!ON REPCRT (3-84-021)
The subject Report was referred to Region III by 0! for consideration on June 14, 1985. .
%~
The Report docunents instances of forgery by a contractor QC supervisor at l the Ferr.i facility. . l 9 The incividual is now employed at the Pilgrim facility in Region I in a responsible position. Region I should be made aware of this matter. Also, the matter raises ccnsiderations similar to those raised in the florth Anna matter.
/ I
/
/
James Lieberman, Director and Chief Counsel Regional Operations and Enforcement Office of the Executive Legal Director cc: J. Gutierrez, RI i R. Berson, RIII Distribution l ROED rdg ROED sub Lieberman chron ' Kcefling chron ELD rdg SB/KC/LC info l 8607170050 860709 PDR FOIA PUNTENN86-244 PDR j
- i
- 0 ELD /- '
/ 0 ELD : : : : :
- _ - _/ -
- Ho 1in)d..:-__\_(
sb :Li an : : : :
- 7/3/85 :7/3/85 : : : : :
. S3G
. t .
h'. k Deholt . Edison- _ , Date: April 2, 1985 VP-85-0078 To: F. E. Agosti S. H. Leach W. F. Colbert R. S. Lenart
.. W. Dutton W. J. McCarthy, Jr.
- 3. K'. Earle S. H. Noetzel 7 ,
W. J. Fahrner G. R. Overbeck E. P. Griffing J. L. Piana ! C. M. Heidel L. J. Simpkin W. R. Holland G M. Trahey S. J. Latone A. Vance From: W. H. Jens h.
Subject:
Minutes of Meeting iuh the Nuclear Regulatory Commission, April 1, 1985 Attendees NRC Region III Detroit Edison P. M. Byron C. M. Heidel J. G. Keppler W. H. Jens C. E. Norelius W. J. McCarthy, Jr. Purpose The purpose of the meeting was to discuss with Region III the critical period between fuel loading and 5% power. Mr. Keppler i did most of the talking except for a few remarks by Mr. Norelius. General
- 1. Fermi-2 is a good looking plant. It is one of the best in Region III. ,
- 2. We should be proud of the plant. We were encouraged to keep up the good housekeeping.
- 3. The NRC feels we are doing a good job in maintaining a well informed and involved senior management up to the CEO.
- 4. Region III wants us to succeed and will help us as much as possible by watching us carefully pointing out need for improvement as we go through startup.
Relationships with Region III l 1. Keep Region III well informed of activities and problems at Fermi-2. l
. a - F. E. AgoOti, Ct 01 April 2, 1985 VP-85-0078
- Page 2
- 2. Region III will give us almost 24-hour inspection cover-age until 5% power. They will also observe all tests beyond 5% power.
- 3. of particular importance in the next three months is how well we deal with problems.
- a. Do we act promptly.
- b. Do we get at root cause or it it a bandaid solution.
- c. Do we take' prompt corrective action.
- 4. Region III will tell us where we need to improve the minute they sense a problem that we do not properly handle.
- 5. Nick Chrissotimos will be here every two weeks. He is the key NRC inspector in obtaining a good report card prior to 5% power.
- 6. Region III will call a management meeting if they detect trouble.
- 7. Sensitive issues to the Region are:
- a. Personnel errors.
- b. Repetitive equipment problems.
- c. Scrams.
- 8. Misaligned safety systems going in and out of technical specification surveillances is where they predict we will get caught. The penalty in making an error can be severe. :
Mode changes are also a potential trap on system alignments (valve and electrical). If we have an opportunity, we should I l practice conducting alignments with mode changes.
- 9. Operating shift changes without complete knowledge of system status can also trap us if we are not careful.
- 10. Each operating shift should quickly pick up changing con-ditions in the plant. This is commonly referred to as
" attention to detail".
- 11. The NRC will be particularly severe in their enforcement if control room indicators indicated a problem or a pre- l cursor of a problem and if those indicators were ignored by the operating shift.
F. E. Agosti, st el April 2, 1985 VP-85-0078 - Page 3
- 12. Edison was encouraged to take a stronger position with the NRC on inspection issues especially those which can be easily defended. We must choose our battles carefully, however. I.e., don't pick issues like fire protection.
Advice
- 1. Communication is the key to avoid trouble. Be certain that those that need to know understand the status of systems; i.e., PN-21 status and operability status.
- 2. Technical specifications are complicated, and it will take i
great care to avoid being caught.
- 3. Interpret the technical specifications conservatively.
4
- 4. Proceed cautiously and don't cut corners.
Enforcement - Philosophy
- 1. More use will be made by the Region of the Confirmatory Action Letter (CAL). A CAL provides both parties a mutual understanding of the problem and the commitment by the licensee to solve the problem.
- 2. Missing a Limiting Condition of Operation (LCO) will auto-matically require an enforcement board in the Region (Davis, Norelius, enforcement specialist, lawyer).
- 3. A Level III noncompliance will require an enforcement con- ,
ference. Edison will know at the conference or shortly thereafter, but before it is published, the extent of the penalty. . l
- 4. Fines are generally determined in Washington based on the l j Region's recommendation. l
- 5. Fines will be mitigated if our performance is good; i.e.,
if it is the first offense.
- 6. Fines can also be-mitigated with a good analysis and pre-sentations at the enforcement conference. This presenta-i tion should cover .
1
- a. A clear understanding of the problem,
- b. A good analysis of the safety significance.
- c. A good analysis of root cause.
F. E. Agosti, et 01 April 2, 1985 VP-85-0078 - Page 4 I i
- d. Good, prompt corrective action which in the past has l been demonstrated to be effective. '
t Mr. Keppler will send us a copy of a presentation by Kewaunee which he feels is a good model. {
- 7. If a fine is assessed, it does not automatically mean a low SALP rating; i.e., if it is an isolated event.
i i
. 8. Good performance (SALP) will lead to less inspection by a factor of 10 to 50.
Full Power License i 1. Region III will delay us from receiving a full power license .f if in their opinion we are,not ready.
- 2. We will have a mini-SALP before 54 power. It will include training, housekeeping and control room discipline.
- 3. NRR and Region III (Norelius) will both make presentations to the Commissioners.
, 4. Edison will probably be asked to make a brief statement at
, the Commission meeting. We should address problems brought up by the NRR and the Region in our brief statement. Anticipated issues are fire protection, drawings, Quality i Assurance, and operating performance. Other Observations
- 1. Except for Callaway, the plants 800 MW and larger have poor j performance. Even Callaway had six scrams in 1985, all due to secondary (BOP) problems.
l 2. NTOL plants are in most trouble because of new technical specifications. The NRC has an effort underway to change
, technical specifications, but this will take some time and will not be of much help to us soon.
l 3. Both Commissioners Palladino and Asselstide will visit the j plant before 5% power. } 4. Commissioners Zech and Bernthal were impressed with the l plant. We should try to do as well with Commissioners ] Palladino and Asselstine.
! i
- 5. Mr. Keppler made one observation that bothered him. We seem.
j to not have a unified approach at Detroit Edsion. i i a. There appears to be a division between operations and engineering.
- - F. E. AgOcti, at 01 April 2, 1985 VP-85-0078 Page 5 )
- b. A lot of stops and starts occurred in regard to the drawing issue. Who was in charge? Were we getting the facts from those doing the work? The NRC observed that the numbers changed a lot during the resolution !
of the problem.
- c. The NRC has the impression that we were pulling in different directions,
- d. On one occasion, a disagreement between the plant and
. engineering surfaced in the presence of the NRC.
- e. Another observation the NPC made was in regard to closing of open items. The NRC was told we were ready, and in many cases when the NRC examined the issue, the item was not ready for closure. They felt that perhaps one group was not responding as they should to another group.
Messrs. McCarthy and Heidel indicated that changes would be made to effect a unified approach. ) WHJ:r P
. s l
I l l l
.__ ___. __ ,_ - -._ ~ - , _ , _ . __ - . . . . . - - - - _ _ - - ,
1 i Fermi 2 Readiness Briefing for Commissioner Asselstine July 1,1985 Opening Remarks NnC-W.J. McCarthy, Jr. Presentation by W.H.Jens Misson Statement Business Goal
- NuclearSafety l
Strategy A-Controlof Resources
- Organization i
S rategy ad N Follow
- Unque Featuresof Fermi 2 a
We
-l . . l Fermi 2 Readiness Briefing for Commissioner Asselstine (cont'd.) July 1,1985 Strategy C - Maintain High Or olity Work Force
- Start Expenence
- Training Strategy D-Communication
- Senior Management
- l'm Ready
- SAFETEAM*
Strategy E-High Standards
*INPO
+NUMARC
- Excellence Objectives Readiness for FullPower Management Philosophy Future Needs
Mission Statement The purpose of Nuclear Operations is to manage the Company's nuclear facility to produce electrical energy in a safe and economic manner, emphasizing the health and safety . of employes and the Public, and fulfilling regulatory and contractual requirements and commitments. I. - 1 l 4
as , 1 Business Goal , To Operate Fermi 2With Excellence
- Excellence in Safety
- Excellence in Economy
- Excellence in the Eyes of Our Peers 1
==
, r ,
Nuclear Safety Organization .
' Board of 4 Directors l
Chairman of Nuclear the Board and % Review . Chief Executive Comml: tee Officer i President and Chief Operating Officer I We President ---- Nuclear Safety _ Nuclear 4 Review Group Operations I Manager Nuclear Operations I I I I I General Director . Assistant Manager Assistant Manager Nuclear A=alatant Manager Nuclear Regulation and W Operations Compliance Production Services Engineering independent On-Site Safety a Review --> Engir.;;.i rs Organization Function j I !
i, ! ;i i1 s t u t a S p u o r _ G e c 2 a w8 e9 l P i 1, i n v5 es e1 r a re t R eDub d t ymt eo c f es o e cgr aDienP S d eedn t r e a ai zMr e l en9ad r t cglr aeh uOHC N *+*
n o r , ec . i i t e nso s t is g p o e n nAt .n d n Er cl ha t d m o t e a eu eTs n a n l cyn n C i r e u go o
- p N rC it a
p S u .el
,no l u
u r cEt n r n6 0 g o r e I c y, si o 2 R e m v aC : e G r o eBl c n,a r, e FyL c g w ,rrl ei e ga i e t n ot gn0 eSiao e2 inn v aFst ,oicop: l f a e n rM c f e t l un ne sd x i R 03swd 1 yl aor
- l
- s a n o si AR ae rserti E r o Gtna d al np t a P asm e m me-CB Pe e -s c/
l r w . f et n l uedn o at xn e yM i N c EAC n - SiEe vy ea a se r ssr en n r . oa 9 a ee r rG Lr ebbm l o u r Ypm x r l c ee m mJ SM i l t aEia h uMM- -- toc N * * *
- _ i ,
.1 l: ! ; .I O ;
Corporate Strategic Plan > MajorStrategy A Maintain Total Control of Resources to Operate, Maintain and Modify the Plant. -_____._________A___ _ _ _ __ --_. _
o h Nuclear Operations June,1985 Vice President
- Nuclear Operations Manager i Nuclear Operations i
i l I I eneml Director Assistant Manager Assistant Manager Assistant Manager "* " Nuclear Production Regulation & Compliasi. q Nuclear Engineering S e i l I I Superintendent M nt a e t - - Director _ Architect / N r _ _ N r Operations & Modification Assurance ensing Engineer Security Training
~
Nuclear Director Director Director Safety Radiological - Nuclear Human Resources Fiscal'& Materials Review Assessor Engineering & Admin. Support - ~ Management Group Services
- Supervisor of Director ., Projects Computer Nuclear Service & -- Production 1
Information Administration Systems i 1 ) ~
' T' l
Nuclear Operations Management Plan l REGULATORY REQUIREMENTS CORPORATE DOCUMENTS AND COMMITMENTS - General Orders (includes FSAR and Tech. Routine Instructions Specifications Administrative Letters I m OPERATIONAL QUALITY . NUCLEAR OPERATIONS , ASSURANCE POLICIES DIRECTIVES (34) (31) m
}
QUALITY ASSURANCE ; NUCLEAR OPERATIONS PROGRAM REQUIREMENTS gg PROGRAM DESCRIPTIONS (39) i l l l organizational No interface req'd? es INTERFACING PROCEDURES (59)
. m
~
IMPLEMENTING ! PROCEDURES (3,784)
- e WORK INSTRUCTIONS WORK PROCEDURES
i < i l 1 i k Corporate Strategic Plan l l Major Strategy B Lead, Not Follow, the industry, the Nuclear Regulatory Commission (NRC) and institute of Nuclear Power Operations (INPO) in the introduction of NewTechnology and Methods to improve the Safe and Economical Operation of the Plant. i i l
5
, e 9
- 8 6 9 mn1 mot gPoR rmo ala r 2 odf l s i r ed o ie z et r mP r wlay on et i o lp p u einl v C p S F e e r f R m Emd n e e o er t g k s Po w
. s cn as ple is inr o e
r er mip e St an u i e ocD t ar io t pCn s r xe es nis a eE xdrPt n i oeHemVVc l F g aA amtpeGskk ndRF al en eieA u t ad r l Ln aoms Qi ea50 t l i r T 3142 q eeA i mRUDla23 i ph uH u nOS HR - - D- - U * * * * *
- i ' !! :i, 1 l
. J. . Operating Experience Review Program Events as Reported by NRC, INPO and Vendor Documents
- Program Formalized in 1972
- Comprehensive Program Actively involves and Informs Personnel Who Needed to Know by Participation. TPaining, and Retraining
- Over 2500 Documented Events from the Industry Were Revewed. Resulting in About 5% Desgn and 12% Procedure Changes at Fermi 2.
4 Unique Features of Fermi 2(cont.)
.
- Safety Review Task Force -Initiated Two Weeks After TM1
- Back Up Electrical Feeds to Circulation Pumps and GeneralService Water Pumps
- Low Level Radvieste Storage Facihty
- Third Remote Shutdown Panel
- Stan@y Food Water System (Motor Driven Pump)
- Combustion Turtunes Backup Power Supply b
4 1 1 i r i j i I 1 i i e 4 l Safety items , i Ttwee Mile l
! Safety Review Island
. Task Force NUREG 0737 - Completed 93 42 l 7
! Deferred 1 Remaining 4 0
- Total , 104 ,
43 I i t i 1 1 0
- i W
L s -i. 1 3
1 1 1 I .
. .~ $
o f u,. I a n
.] .
.I 5 '
' il11!) 1 l8l"1111Il
........ In l 4
4 l 9 _ _ . - ~ _ _ _ _ _ , _ . . _ _
4 Fitness for Duty
. Drug screen Background kwesagation
- Menesota hPhasicinventory(MMPI)
- BehavioralRehab4ty
- Onentahon
. o Unique Features of Fermi 2(Cont.)
- Knowledgeable Organization
- Chief Executwo Officer
- President
- Vice President at Site
- Integrated Organization
- Essenhal Support / Functional Noods at Site
- Design and Construction Expertise Trans.tioned to Operating Organization
- Permanent Facihhes for All Support Organization Personnel
. E=: " "; Uncontested Hearings
- SAFETEAR8"-Irwesbgahons of Concoms
- I'm Anody Program
I i i l J 'l Corporate Strategic Plan l MajorStrategy C i Maintain aVery High QualityWork i Force. 1 i 4 a { l 1 i I
l I J 4 i i 4 i Fermi 2 NuclearOperations ! January 1985 4 Experience Levelsin Years 4 . Fermi 2 Rmlltery Commercial Total Total Average orgenkation . Nuc. Nuc. * & Other Nuc. Other Experience Expertence , Vice Pnesadent and Staff (11) 72 17 48 196 333 30 Nuclear Ppwtarenri(172) 1,094 418 71 658 2.241 13 Nucteer erg 1 ' .ii(73)
- 829 38 15s 301 1,323 10 l NariaarQueBayAssurance(153) 261 41 176 297 775 5 i
NucieerTraining(39) 101 138 95 72 406 10 Totes (448) 2,357 as2 54s 1,524 s,078 15.2 l Above done per ANSIN18.F1971 I 1 i 1 4 6
Fermi 2 Management l TotalDEco Total Nuclear Other ] PosMion Indivkluel Degree En, "_ _e (Yrs.) Emperience (Yrs.) Emportence (Yrs.) Chanman ofIhe Board and Chief Executive Officer W.J. McCarthy, Jr. B.S.E. 22 22 Presulent and Chief l Operating Officer C.M. Heedel B.S.E. 38 8 , Vice Presedent - l Nuclear Operations W.H.Jens B.S.E., M.S.E., PhD (M.E.) 21 36 1 Manager- Nuclear
- Operassons F.E. Agosti B.S.E. 28 6 Assistant _ 7 -
Nuclear Production R.S. Lenari B.S.E. 24 13 Assessant Manager-j Regulation & Comphance E.P. Griffing BS., M.S., M.B. A. 8 22 Assessant Manager-q Nuclear Engmeeting S.H. Noetzel B.S.M.E. 31 to Supenntendent - Operassons G.R.Overbeck B.S. 7 15 4
' ~
unaarann. J D. Leman B.S. 5 22 Dwector - >=4==r j Engmeenng W.F. Colbert B.S.E. 38 25 General Supervisor- , ) Nucteer Safety and Plant Engwooenng LJ. Sempkin B.S.E., M.S.E. 3I e General Dwector-Nuclear Operahans Services J.L Piana B.A. 18 4 3 j Dwector- ' j Nucteer Tramung S.J. Lasone B.B.A. 33 4 i Dw.ctor- t Nucteer Security S.H. Leach A.S. 33 6 19 Dhector - >-*==r 1 QuainyAssurance G.M. Trahey B.S.E. 4 21 [* Dwector-Licensing T.Randazzo B.S., M.B.A., J.D. 14 14 f 1
6 Fermi 2 Nuclear Operations Experience Levelsin Years Ferm12 Military Commercial Total Total Average Job Title Nuclear Nuclear & Other Nuc. Other Experience Experience Supt.-Operations (1) 7 9 4 20 20 Supt. Maint. & Mods. (1) 5 22 27 27 Asst.to Supt.Operat~ms (1) 8 20 28 28 Had Chem. Engr 1Supr. (5) 16 17 7 24 64 13 Genl. Supr. Chem. (1) 2 9 11 11 Chemet / Chem. Engr. (2) 8. 3 12 23 12 Gent. Supt Health Physcs(1) 3 7 6 6 22 22 Operations Engr.(1) 8 to 18 18 FuelHandhng Supr.(1) 19 16 35 35 Stwit Supr.(7) 61 31 13 27 132 19 Asst. Shift Supv. (6) 36 31 25 92 15 Supeneng Oper.(38) 132 233 10 90 465 12 Mamienance Engr.(3) 18 12 30 10 Mamienance Foreman (15) 64 18 4 187 273 18 Tech. Engr. (1) 8 9 17 17 Tech. Support Engr.(2) 29 8 26 63 32 Others** (87) 845 64 7 168 1,084 12 Totals (172) 1,269 418 84 633 2,404 19 Above data per ANSI N18.1-1971
" Indicates Remamder of Plant Staff Other Than Clerical Statt
8 i l 1 Accumulative Training , Number TotalWeeks l Trained FormalTechnical i Training Licensed Operators 52 2453 weeks Non-Licensed Operators 48 720weoks ShiftTechnical Advisors 5 216 weeks Health Physics 23 288 weeks
- Chemists 9 131 weeks i l MamtenanceJoumeymen 114 371 weeks I& CTechnicians 12 204 weeks Fue Watch /Bngade 426 87 weeks Secunty 115 864 weeks
- QualityAssurance 130 7 weeks RERP 567 89 weeks LicensedOperatorBarr% 47 423 weeks i
Summahon: 6,104 mornseeks of Irameng apprommates 117 man-years. l f i
, I
4 l l l INPO Training Accreditation Schedule Grenspl Licensed operasors-InmaiTranng INFO Reviewing ticensedoperasors-naq -=-1. Nonhcensed Operators Shift Technscal Advisors Group N Instruments and Cormols December 1985 ChemiseryTechnicians . Heakh PhymesTechncans Group s ElectncalMaintonence May1986 MechancalManeenance Management.TechncalStaN AllDeemt Edson Sutsuttais Ase:
- Commeted toINPO by End of1986.
- Requesd by 2 Years Ahor Commercial Operation.
L , . Fermi 2 NRC Licenses
- Mw4aar PMm Staff 6
- NucteerTraining Staff 3
- Shift Personnel
*SRO
- NucioerShiR Superwsors 6
- Nucteer Assetant Shift Superwoors 6
- ShinOperamonal Adwsors 5
- NucteerSuperwsingOperators 3 t
*RO
- NucteerSuperweing Operators 21
- SR(>Hosencted to FuelHandEng
- Nucteer FuelHandEng Superwoor 1
- Operamons Staff 1 Total 52 I
__ y --_ m - - - . - - - _, w . o.a. m o. .w.. o.
~~
P P 1 1 0l l!!!I!!II
~
i D O
y m a r o n r e t n a nllookcw t n F l o ole l Bnh hd eue il s e eei t a a ndiicc s e cS c oa ws oo oe r r nn nu t t r c sq a ere us nLL e BDMMB PDS i _ r _ e p s s s s x k keks ek k e ss k s ek s E he t ge ee eek e ek ee t n nw 6wew ee w we aL1e5 w8 ww 4622 44 w l 1 224 P g r i nb e 558o11 t t a m5 01 6 r u 3 1 eN p O l . a
- s t
n n n a e o i c m i t a e c J n r e n h- a f l e r r oes v e e c m e f t a en p ir Sge r e Tro t p ab r psf der e u eO p x c e anlaag ncEn S n Es yn c O o ah a i gl s n egneer ndt n t ot oe i sicnoh ai n P ee i i n sin or ot t nfiad nrn ra ai d t t t i r l c setrT e dd eah a ip e eM daea PloxC AHMCO RR - e .
4 Monroe County Community College Cooperative Program
- Programs Consest of
- CompanyTraining Courses
- TraditionalCogogo Courses
- Participant Gwen College Credit for Nuclear Operations Courses
- Programs Designed to Upgrade Slugs
- Programs Coordinated with Local Fturyear Unwersstees
- Wayne seass universey
- unwerseyorTosedo e SevenCoursosin Cunent Program
4 Corporate Strategic Plan MajorStrategy D Maintain a High Level of Both Internal and ExtemalCommunication to Ensure Continued Support.
-._ _ _ _ _ _ _ _ _ _ _J
O P t 6 m NE I 1.u.!
.E Eis
#1 is ji ps
~
gal
=j4.
< a. s E
F ? g e
.m
e . j :.,. ,.. - , f . .[ f': .. g ., v . v ~ . . j . r. f:o, V'.'-;.'-Q. t ,
- M' .,.e . r &l
...' ..#1 .; f ,A'y '
- y
,./. .
.Yh L ,- y-
' ;; $' . , .l _
g.^ [; #R" W.,
. ^
~g' t"
. . . .,.'.: .i' . . % ' .. _ . ".?. , h.
- 7. .
. '~ -
?'; 7
.N Q g$e-n W ._ :. W. f .
.s .A .
?A 'l 7,'-
c t l a ; :: . h ~ . . . .
- f. ..
.: R '.
f'L.
-Ny%~w~.m*%
~
;: . R
?' :l$g?f ..-
.. _:-,>s '. .. -~ - .
,j.,-
f[?gxJ. p .p .v
.% j-
.l e.. .
],.. 1 .
4., m.*. Q:- j%' 2WO*> - . W
), .
h , %f4
.4
- 3. .> .-
&, .w,4*:.v.fy,g%(*%..," - .
e - '. .b. -u gs y
,? y }r
]:, . e :; .
Nm~m~ Qu". ' a t, N i _:. - g?. S .+.
. % .'ga. ' p;f* z u, $;# ;'
v-
;p
.;{):- ; S i
h
.. ' f ,.
%u.. - ,
'2 '
x
;(
?
'- - ~
a Mb-d. s %. O _
, . . j}4hm':..i I: ,, ~.:. :*"
- . - . ^
e- , " 4.
'. y: i
.:_a. p ,. . ~ s - . ' ' . ,.'I : .. .'6
., 's? .
?. ;. w. : " y v . ,*
,;p *:: . h_
-.+ . ' p[ .
?f, %}d.. , . . . : ,. -l. ,> ' . . '- '
- 4. - _
3qh l\;4
- ) 9. .-s. .
f' ; -
?.'y ' .
4,e ,e a[. Q
~-
- , - . . f*
N
. ; .Q:..e Mm FC Q E~
7 - N [;
. ,,ts: w, L- ;
' . . Y.
.s 3 Y
7 r~ 3 ;- ' W..g
^. a1 s; x.
,.- ..., ~ [' Y. ?syy ,dr. :. %
gf-
.'_7 q
- g 7
- v. . ,...*- - ,*j,;L; : ,.'
~ '
;y .:'=;fp, - . ' ,. .
.s 'v A
{' -
?'- s.
=. - ;.- :ks-a g> P
..l ;
;-<:.' , ' .,.cf. ....
dD2S j- ,.t ; ;:
' . Q,s. - ;. -
.' ., &. j. , * .* . . . ;'..;G,';y:h.
'f :..h?.w :: m' ., ' .'hV,'
jr . : n _
&- }.,<.@ _G .
OEe
.?. $
r 5 .
. s..T',f$ hl . : c. .,
&. Q;, 9;4, c,"%s. d. :
.. '7 l..q e' .-
3
-.1 c
_ -_f _c
/ _
bo y. G
. ;%~ [*. A.
; g'R.'Q+ . .g ' . 'p..
OD';
- g; . w. w.l': k R47 i..:
- y$Mg 1
?':
7} cEt
?, f. vQ w' A-i' .
- (
g
--i .
- h. wr
&[j;: ..f' 'i X
e
~
p/ cg' Oc9wn 3 4'- * [' . , ' - r k t' {Q' 's
.Y Q
."m.
l
. : (& ~.i.qSi .%
).;,
t
./
s.n n e-
- wy .
k / Ywsa-- g
. sr.
b . r
~
; f ,. e
%,'i:g, ldnf \ f. &he,k%Q 'p' w.y' ,
q i
?:;:
.;.t r .
'. . j : .
v. i i <.,- - y. 5 o,- N y. .:' ..T
, , sa1-.'^ .
s g .'f ?[;,,'>+. _ Q'; ,.RW4%oy : . .&}f
?.? _ ..
". ,? *. ::Ns ., .
l .V
. ; +
k a y ;',e.>. , . y . 9. *?%lqa:
~
. i.:,:
- g ?lp:. .,.r.: a,b' h
!j U'T' l +e.m.M:q$g'. 4 ,
n e.,
, j; .~
. , s.
- &P.s : ,
, '* ' , " . q s [
Fermi 2 SAFETEAM'" Status Report (6/21/85)
. Investigations Completed Concerns Class Received Closed in Review UnderInvestigation Nuclear Safety 1&2 757 740 5 12*
Management 3 363 360 2 1 Industrial Safety 4 175 173 1 1 Misc. Security,(etc.) 5 179 178 1 0 No Concerns 0 394 394 0 0 Totals 1,868 1,845 9 14 Total People Through Safeteam 5,700
*All Safety items Were Investigated and Replied to at the Time of Fuel Load O
t Corporate Strategic Plan MajorStrategy E Maintain High Standards of . Performance for Human and Capital Resources.
INPO Visits October,1982- Assistance Findings: Improve Licensed Operator Training improve Radiological Protection 6 Good Practices ' 51 Recommendations September,1983 - Assistance Findings: Coordination of Testing & Turnovers Need improvement improve Development and implementation of Operating Procedures 6 Good Practices 35 Recommendations Completed all but 8% of resulting action plan for both Assistance Visits. INPO Evaluation - Plant and Corporate Scheduled for October,1985 O 9
r en c ia e ecP t l b 90 ~0 9 c arn m 1 1 nPo u - a i N mdt r oA c oo s fGe r e v poi epa t hNi t n i tI gyI g nbC. n itdR ne 6 io s era 0 1 g meM v s O n m e eoUm pCNt e e l ig t v r o ni n msy i i t d n l at e iab s a eo Pe imd na e i nM t i i t n nta er iC o orc gr i mle t cFI m ofo d e u dr epi n C elpnsyMAA e R t nmo t i iU ion t gR. A eiC l ri M me eB e r t UN t eo0 Di1 t r2 lpli d a m l n-U l n oro t oA N I mWU TF MO
1985 Excellence Objectives 1985 Expected
- Dernonstrate Corporate Support-Senior Management Trips to Fermi 2 for Nuclear Operations Meetings . . . . . . . . 130
- Operate the Plant with the Number of Licensee Event Reporis (LER'S) Better Than the Other NRC Region lli Boiling Water Reactors at the Same Levelof Maturation . . . . . . . . . . . . . . . . . . . . . . . 80
- Meet the INPO Guidelines on Training Accreditation of Programs . . . . . . . . . . . 4
- Control Exposure to Employe(Man /
Rem)to Reduce the Concern of Health Risk . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90
- Protect the Environment and Be a Good Corporate Citizen by Havmg No Unmonitored Release of Potentiall Radioactive Materials . . . . . . . . .y..... 0
1l l , y B i ar it e r C i n O P t a N i n I g a i n s z t M i l i r o p o t U e t e s R sc nr oe t n mn ici t e ae rl l cf ef pO E v s ge sn e n )e w oc v t n oc it ni e rx I du i t e a a ve PEnnc d s ivmR nd laaet sr e i t r sxn gf eeDoe a eP crEer cuiof dPao n c f u i o n in f i gTiecae et h r i s e n wCe- ie r i nt g n a t r a nCPVMine v op ioSP t l
- - - - R(eN Ex SC * * *
- Industry Experience Updating
- Required Reading
- Urgent Required Reading Must Be Read Prior to Assuming Shift
- RequiredReading-InformationThatisImporIant to Operators. Issuedon a Weekly Baus
- Weekly Classroom Review of Industry Reports (SOER. SER, Sll, LER, DER) Dunng Requalification Program
e Significant Programs to Maintain Continued Excellence (cont.)
- INPO Evaluations
- Initiate Plant Performance Program Before CommercialOperation
- Emergency Exercises
- Licensed Operator Requalification Using Fermi Specific Simulator
- INPO Accreditation of Training Programs .
- Encourage Operating Personnel to Get College Degrees
- Site Professional Appearance Standards
Surveill:nces System Operability and Temporary Procedures I I
- Conditional TechnicalSpec.
Compliance Releases , o PreepTe On-site Review " C $ons and Deficiency : Organization and NRC Open Reports items Start-up Tests and Restraint RadWical Prde Workitems ( Recommend Advancing to g' Region lli Plant Superintendent I nse Recommend gssuepogP # 'g3ce e Vice President Nwk NRR Operations I
, Approval T
~ Supe L Readiness for Full Power License i Execute Power Ascension
- License Conditions Criticality
- Accessibilityof Safety-relatedValves
- BWR Cpcrating Experience on Shift
- Interim Procedures for Altemate Shutdown y
O
- F,
s e r u d e c o r P S) r dg T e nn r G ait s o S t w s r e t a we ( g r o o oT imiv gin nn p P oo l e ipar l i R e Drd l
% ey C oR mT m 5 yF iH v
i m aro a r e St slido i nb ei t n g n ht s st dy s n os in g o r O otal ece l t i l pgcSs ee nmMeP di n n i i t ab ao bt mnA gh t i H L,P ts S r si aeagt nLn oc e a mt nna
- r i dn r aooeTeiu Co mrse etnD t l r P nCsl l d
o ctF dd B u moe a ppe o oi n e r e eReteaiyiMipGmmR l t eRc c r nt PySSg aa e s or el o a n b nt DpdA meutgmetydSSa st e uenTTk e noreoqoaef ataGGe r l f f a i c C FC L P C G E S S S S L L *
- i i
* * * * *
- a * *
- O I
i !i e. (
4 i Fire Protection 3L Panel Installed 5/02/85 Hydrostatic Test Completed 5/31/85 Conduit 90% installed at 7/01/85 Expected Completion Fire Doors 7/03/85 Fire Detectors 7/07/85 Cables Pulled 3L Panel 9/30/85 Procedures, License Amendment SubmitIaland Training Completion 9/30/85 3L Panel 9/30/85 6 _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . ___ 9 _ -_ _ _ _ _ - - _ _
Equipment Qualification Submittal Mechanical 100% OualifMMJ at March 1984 Electrical At July 1,1985 Qualified Components @ Submittal 850 Qualified by Evaluation 210 Qualified Components Since Submittal 214 Justified forInterim Operation 136 Total 1,410 Action Plan R ..saining Tests 7 Relocations O Replacements 129 TotalRemaining 136 MaterialReceipts 35 Implementation Schedule July Ibru Sept. '85 58 Oct. thru Nov. '85 78 Total 136 h
i !i P i f o e g t o i ar g ef o r n y v n id s ro Ao ni e e t nt a oa t c el s ir t a u o r ngu rD P a e u r r R e T Da ,e f o r pR eY c e tuAe n e b r Sc e n c naFn ot e iS iO rnie r v
. en pi o a t
z o ore r f dp p i e s Ee xd p gnd ex n aa e sE
- yl t A ign a r u / r r e uBy r
- h t su es d e z eOT e in w e is su t
- P dR ydogeB md an eI ns l
t a i sl nM Eei nv l Te dun n 2 Ar t l rI rRWongd ola swe aet t ero P a, pheedPi r e m eol c s nr TPcs a gs i t tu S r s BNF t ai e chtx N unl ne O u id a Te- ae mtsiu ie t EN- S TG S * * *
- _ i l i. 1 ;l1 ii,t , 1 l : i ' t e
J
F rmi 2 - Stcrtup T:st Phase Power Hi togram Reactor < Thermal l Power l 10 0 % - l (100%) (95%)
"- ~
Q (% @ [ 90% - 80%- (750I) 7M-(65%) 60%- - (58%) @@ 50% - . (50%) (48%) (45%) 'q p 40%- l : k' (' Ch 40%) 30% - Initial
- Synchronization s. ..
20%- j 425 % ) (20%) Initial - 10% . Criticality Lic s it+ 5% - - - - - - - -
%) @ @ b b 0% 01 4 9 14 20 25 3233 3940 50 51 5J Test
, Condition g,, (4) Warranty Fuel Open Test Test Test Test Test Run Load Fuel Vessel Condition Condition Condition Condition Condition Snubber Test .
Load Testing Heat-Up (1) (2) (3) (5) (6) Inspections i Weeks A Shutdown from Outside C Recirc. Pump Trip "A" E F.W. Pump Trip G MSIVisolation
'ird Room D Recirc. Pump Trip "B" F SRV Discharge Test H Generator Load B Loss of Offsite Power Reject (
Management Philosophy
- Do it Conectly, Safely and Carefully
- integrate The Site Organization
- Operating Authonty - Plant Management
- Actneve Excellencein Operation 2
e 9 9
iI 1l' e d-, t n .- e , e e , i s c
+-
fi a e E f ba'e cesa a e: f a fb i e t l g n DD gn Ota i S n o dD e a n d e i wn ne t t o e ;.u pm r n r. m o me i eg g ig t r o wn oEC i ha gn N pdl ua E 2 n a n acs. rM o i Mg a i gimThd ola e m r t ci nl yf i F e t aw r a oC d ntviU i n s e n r ao*dn d h . o D Ria t et a et e ioehh n C e ei aM n d t t Ndat at h e eR P o t t i el izi e e ed seta - r s a u p po a m oncl li ungd t or meoo mA v cu eo rt u CO R C CtonA F
- I e * * *
, ,1 ! l
4 .r --- - - .a , -- . - - - _ - ,1 . --, l C ' G CL Q. 4 - l o
- . . . - . -- - -,-.. _. ~ -. - - ..--,,..- . -. - - , . --, --.----. .-
9 Fermi 2 i Newport, Michigan i The Fermi 2 nuclear power plant is located on an 1,120 acre site along the western shore of Lake Erie in Frenchtown Township, Monroe County, Michigan. A 17 percent ownership interest in Fermi 2 is held by Wolverine Power Supply Cooperative, Inc., Boyne City, Michigan. Construction of Fermi 2 started in October 1969 with the first concrete pour in October 1970. The Station is a single Boiling Water
- Reactor with a total output of 1,154 megawatts. After completion, the power from this unit could provide service to a city with a population of approximately 1,000,000 people.
The Containment Building that houses the nuclear reactor has about i 12,900 tons of reinforcement bars within the concrete walls. The Containment Building is 155 feet above ground with walls that range. from 18 to 36 inches thick up to the refueling floor. Fermi 2's cooling towers are 400 feet high.
.s e
Fermi 2 Project Status - Estimated Quantities Quantity item Unit Current Estimate Civil Concrete Cu. Ft. 324,000 StructuralSteel Tons 12,700 Penetration Seals-Mech. Each 10,700 Piping Large Bore Pipe UnealFeet 218,000 . Large Bore Hangers Each 15,100 Small Bore Pipe Lineal Feet 120,000 l Small Bore Hangers Each 13,400 Whip Restraints Each 183 Electrical Terminations Each 294,000 Wire and Cable LinealFeet 8,650,000 Conduit Lineal Feet 944,000 Tray LinealFeet 71,000 Calibratible Instruments Each 18,250
Fermi 2 Milestones Activity / Description Date Complete Construction Permet Appiocation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4/69 , First "O" Concrete. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10/70 Construction Permit issued . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9/72 install Reactor Pressure Vessel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10/74 Shutdown of Construction on Fermi 2 . . . . . . . . . . . . . . . . . . . . . . . . 11/74 Resumption of Construction on Fermi 2. . . . . . . . . . . . . . . . . . . . . . . . 2/77 ; Energize Power Block . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6/81 NRC Approved Safety Evaluation Report (SER). . . . . . . . . . . . . . . . . . 7/81 Fermex 82 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2/82 Reactor Pressure Vessel (RPV) Hydro Completed . . . . . . . . . . . . . . . . 7/82 First "O" Preoperational test. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8/82 t e
9 t. Fermi 2 Milestones (Cont) Activity / Description Date Complete ASLB Ruled in Favor of Fermi 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10/82 Flow induced Vibration Test (FIVT) Completed . . . . . . . . . . . . . . . . . 12/82 22 NRC Licensed Operators . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7/83 19 NRC Licensed Operators . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12/83 23 Consecutive Starts and Stops on All Four Diesel Generators Completed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6/84 i Fermex '84 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6/84 ECCS Complete . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9/84 SCILRT Complete . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11/84 PCf LRT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12/84 Load Fuel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/85 52 NRC Licensed Operators to Date . . . . . . . . . . . . . . . . . . . . . . . . . . 5/85 Synchronize Turtune Generator to Grid. . . . . . . . . . . . . . . . . . . . . Est. 7/85 Commercial Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Est.10/85 FERMEX '85 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Est.10/85 Complete Erwironmental Qualifications . . . . . . . . . . . . . . . . . . . . Est.11/85 100% Power (Test Condition 6). . . . . . . . . . . . . . . . . . . . . . . . . . . Est 2/86 Warranty Run . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Est. 4/86 e 1 I w Y 1
e
. Fermi 2 Premature Criticality Event of July 2.1985 32DLngry of Findings The findings with regard to the cause of the premature criticality event of July 2,1985 have been stanmarized by identifying the root cause, several significant contributing causes and other significant findings ROOT CAU.SE o Ocerator Error - Failure to follow procedures / control rod withdrawl pull sheets.
SIGNIFICAE_fDN32fDTING CAUSES i o Eajhtr_e._tohAtely Manare Controlltoom Ac.t.iyltjes During Critical Plant EYDlutions. Neither the Nuclear Shift Supervisor or Nuclear Assistant Shift Supervisor was in the "at controls area" during the rod pulls. o Failure _.T.o_Daera.tt.b_. Trained - Operators are trained to pull control rods and concurrently monitor neutron monitoring. In this case, operator was using STA In Training to monitor / observe neutron monitoring for him to speed up process
- 83
i kp Failure To Train As Oncratina - Operator was trained using control rod pull
. sheets, which pulled group three (3) rods to position forty-eight (48) in one sequence, where as control rod pull sheets in control rod had group three (3) rods in " reduced notch worth" sequences.
o Failure To Use Plant Hardware (Rod Worth Minimizer) To Fullest Potential - Rod Worth Minimizer (mai) was not " loaded" to enforce group 3 and 4 rod pulls in accordance with the pull sheets. It was " loaded" to meet the
" dropped rod accident" only for all groups, which meant groups 3 and 4 only had positions 00 and 48 " loaded" in the RWM.
o Poor Human Factored Pull Sheets - Control Rod pull sheets layout between groups 1-2 and 3-4 are in configuration and appearance identical and can ) mislead operator. o Failure Of " Shift Team" To Resognize And/Or Perform Their Assigned Functions - Personnel on shift who should have known about the event and/or by being more vigilant in the responsibilities to prevent its occurrence were not in several cases f nvolved prior, during, or after the event. Qther Sienifisaat_Eipiirga o Failure to Maintain Adecuate Logs - Neither the NSS, NASS or the NSO logs made mention of the event. Event was noted in Reactor Engineers log and subsequently lined out. A Deviation Event Report (DER) however, was written to record the event 4 l
e ,- o Eailprs_.ts_Stoo and Evalypt.c_psy.10 tion - TM on-the-spot cvaluation was
. done poorly and in haste, with limited input prior to proceeding. Only the NSS, the NSO conducting the rod pulls, and the STA In Training reviewed the event and did so in haste o Failure To Proper 1v Turnover Function At Shift Turnoyer - The two (2) operators failed to stop the evolution long enough for the off-going operator to communicate where he was in pull sequence and what was coming up ar.41 the on-coming operator to review with the off-going operator and others the entire evolution of bringing the plant critical and becoming familiar with the procedure and significant steps in the procedure.
RSL/ 7/20/85 1 4 l l l l
- e OUTLINE FOR MEETING WITH NRC ON 7-23-85 ROD PULL EVENT 7-2-C5 I. INTRODUCTION & PURPOSE OF MEETING II. FERMI C OPERATIONS III.. DESCRIPTION OF EVENT A. THE EVENT B. ROD PULL SHEETS C. SRM CHARTS D. SHIFT COMPLEMENT & THEIR LOCATION IV. DEVIATIONS A. IMPROPER ROD PULLS - OPERATOR ERROR B. FAILURE TO RECOGNIZE EVENT & TO STOP, EVALUATE,
& DOCUMENT BEFORE PROCEEDING ON V. SAFETY SIGNIFICANCE OF THE EVENT A. SIGNIFICANT PROCEDURE VIOLATION & NOT SAFETY CONCERN B. PLANT WAS IN PROCESS OF STARTUP
) C. NO SCRAM OCCURRED, PERIOD 114 SEC., MAX. SRM COUNT - i WAS 6 X 10 3 , NO INDICATION ON IRM*S D. NOT OUTSIDE DESIGN BASIS OR IN AN UNANALYZED CONDITION AT ANY TIME E. NO TECH. SPEC VIOLATIONS - VI. REPORTABILITY CONSIDERATIONS A. DER EVALUATION B. 50.7C AND 50.73 REVIEW VII. ROOT CAUSES & CONTRIBUTING FACTORS A. FOR ROD PULL ERROR B. FOR FAILURE TO RECOGNIZE SIGNIFICANCE OF THIS EVENT
& TO STOP, EVALUATE & DOCUMENT VIII. CORRECTIVE ACTIONS IX. RODWORTH MINIMIZER DISCUSSION X.
SUMMARY
, CONCLUSIONS, L LESSONS LEARNED l t- . 34
, \
l r.a .
, j
- . l I t ..-
9o .
) . FERMI 2 OPERATIONS DATE TIME
^
- .. ~.
4-9-85 SHUTDOWN MARGIN TEST f .
~
- 6-21-85 FIRST STARTUP CRITICAL AT 0519
. 62bS-85 MANUAL SCRAM AFTER CRD PUMP TRIP 1418 POWER < 1 % PRESSURE 140 PSIG 6-29-95 SECCND STARTUP CRITICAL AT 1109 7-1-35 SCRAM FROM FALSE REACTOR WATER LEVEL 3 1432 SENSING LINE VALVING ERROR
/
~
POWER < 2% PRESSURE 140 PSIG
'7-1-85 THIRD STARTUP PREMATURE CRITICAL AT 2359 7-2-85 CRITICAL AT 0050 7-5-85 SCRAM FROM REACTOR WATER LEVEL 3 1531 MAIN BYPASS VALVE PROBLEM POWER < 4 % PRESSURE 630 PSIG 7-6-85 FOURT)1 STARTUP CRITICAL AT 0107 7-9-85 SCRAM FROM REACTOR WATER LEVEL 3 2301 MAIN BYPASS VALVES IN MANUAL 4
~- POWER < 5% PRESSURE 955 PSIG 7-10-85 FIFTH STARTUP 0935 4 %
-~w
IMPROPER ROD PULL EVENT EVENTS OCCURRED ON THE 3RD SHIFT 7-1-85 AND THE iST SHIFT 7-2-85 TIME SEC 2220 50 RO ON 3RD SHIFT STARTED PULLING RODS 2314 52 RO ON 3RD SHIFT COMPLETED STEP 37 OF ROD PULLS 2316 03 RO ON 1ST SHIFT STARTED PULLING RODS PER STEP 38 (HE HAD PREVIOUSLY ODSERVED PULL OF SOME PREVIOUS RODS AND SOME TURNOVER OF INFO HAD TRANSPIRED) 2320 STARTED SHIFT TURNOVER MEETING 2326 10 F'.EIVED A SPURIOUS RWM BLOCK 2300 COMPLETED SHIFT TURNOVER MEETING 2335 04 RWM BLOCK CLEARED BY REINITIALIZING 2336 02 CONTINUED PULLING ROD 22-31 AS PER STEP 44 J N 2340 50 ROD 02-05 WAS PULLED BEYOND 04 TO 48 WHICH WAS gy START OF ROD PULL ERROR U
't' N[kf 2059 08 COMPLETED COUPLING CHECK OF 18-51 (11TH ROD 4 ( WITHDRAWN IN ERROR) RO & STAIT NOTICED CONTINUED INCREASE IN SRM COUNT AND RO NOTICED THE ROD PULL 5 ERROR 2359 33 RO STARTED INSERTING ROD 18-51 AND ASMED STAIT TO GO GET THE NSS 0014 14 ALL ELEVEN RODS PREVIOUSLY PULLED INCORRECTLY WERE NOW BACK AT NOTCH 04 0014 49 STARTED PULLING 10-43 AS PER STEP 57. SNE & STA HAD VERIFIED PROPER ROD POSITIONS USING OD-7 OPTION 4
L
Rav. 4
~
EF-2 ROD SEQUENCE CHECKOFF SHEET
% TART DATE 7'(' I TIME 222l SEQUENCE B-1 PACE 1 of 72 SIGNATURE '
APPROVED BY: 3 S//3fg-N53785'O Reac M n dfeer/Date RODS FULLY WITHDRAWN
' FULL OUT LIGHT ILLUtilNATED AND STEP
- ROD FROM/TO ALL RODS POSITION 48 IS ROD COUPLING VERIFIED /l FINAL P05TTTON INDICATED ON THE OVERTRAVEL LIGHT l VERIFIED 4-ROD DISPLAY (1) EXTINGUISHED (2)!
l (INITIAL) (YES/NO) (YES/NO) { i RSCS-CROUP 1 RW.-CROUP 1 I
-1 22-55 00-48 l *[8 l' V1E'S V6 1 2 14-47 00-48 M If5 70 3 06-39 100-48 E0 l [6b l 4 06-23 100-48 b y65 l YD l 5 14-15 00-48 M$ l N1 VD I 6 22-07 00-48 l MU '
u6 I l 7 38-07 00-48 I b YO V65 I 8 46-15 00-48 [b b v65 l 9 54-23 00-48 [b l Vl1 v/3 I 10 54-39 00-48 .I/3 ' F 65 l I _11 46-47 00-48 l M 1 1//1 1 /($ I 12 38-55 00-48 M i VB5 k/d 13 30-47 '00-48 h [I Vh I 14 22-39 I00-48 8J f'/5 l 15 l14-31 00-48 h M l Vr> l 98 l 16 22-23 00-48 1 d> V(7 //6 1 17 30-15 00-48 l kI I//6 1 18 38-23 00-48 h h h80 1 19 46-31 00-48 h __ N 20 38-39 00-48 I/N - 21 30-31 00-48 -
//
i * (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.7 (2) IF NO, SEE TECHNICAL SPECITICATION 3.1.3.6 Ant- A 5 r @ /0 1) D 55 O 14 Fu 44. e4.5- , t
- _ _ , M
l
'.' EF-2 ROD SEQUENCE CHECK 0FF SHEET
' SEQUENCE B-1 PAGE 2 of 72 APPROVED BY: nw _ [j/My-Reactor IfWe r /Da_t e 1 l R065 FDEEY v1TBDPJNN 1 FULL OUT LILTT - I . ILLUMINATED AND STEP ROD FROM/TO ALL RODS POSITION 48 IS ROD COUPLING VERIFIED /l ' l FINAE'P65ITTON INDICATED ON THE OVERTRAVEL LICHT l VERIFIED EXTINGUISHED (2) ) (INITIAL) 4-ROD DISPLAY (3)l (YES/NO) (YES/NO) l I i RSCS-CROUP 2 RW-CROUP 2 M 22 114-55 00-48 WV Wo I 23 106-47 00-48 b '
#4
/
Wh I i I 24 106-15 00-48 l i h V6s Vf5 I 25 14-07 00-48 l 1 i/ 6 VU l 26 t.6-07 00-48 l /II l' 6 27 54-15 00-48 b I 28 54-47 00-48 - 1 O I 29 46-55 00-48 [b c9 h(# I 30 30-55 00-48 b ' 02 M'.) 31 ! 06-31 00-48 1 h I e f(> EN I 1 32 30-07 00-48 [O F(J EU~ l 33 54-31 00-48 I'N VD t/ I 34 I46-39 00-48 I (3 YO I 35 38-47 00-48 I h - VS I 36 22-47 00-48 Yb I 37 14-39 100-48 [h 56 Yi l l 38 14-23 00-48 "' l I I 39 122-15 00-48 I 40 38-15 00-48 i
~
41 _46-23 00-48 2 I 42 38-31 00-48 43 30-39 00-48 0 (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.7 (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6 3A2.
~ ~
cre. , ET-2 ROD SEQUENCE CHECK 0FF SHEET SEQUENCE _B-1 PAGE 3 of 72 APPROVED BY' ; 8/gg-njheer/Da t e leacto l RODS FULLY WITHDRAWN FULL OUT LICHT
ILLUMINATED AND STEP '. ROD FROM/TO ALL RODS POSITION 48 IS ROD COUPLING VERIFIED /l FINA N ITTON INDICATED ON DIE OVERTRAVEL LIGHT VERIFIED EXTINGUISHED (2) ,
(INITIAL) 4-ROD DISPLAY (})I (YES/NO) (YES/NO) l RSCS-CROUP 2 RW.-CP.0UP 2 44 22-31 100-48 N l Neh l I > 45 30-23 00-48 UU Lb a YM I i y i I l i i i I i i i I I I I i i I l I I I i 1 1 I l I u I I I I i i l I l l l 1 I I i i i l l I l i l i i i i i I
- ! I i i i I
I I I I i i i l ; l 1 i ' i ! l I i l i i l l l l I i I I I i l ( (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.7 - (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6 9A3 -
- EF-2 ROD SEQUENCE CNECKOFF SHEET SEQUENCE B-1 PAGE 4 of 72 APPROVED BY: _p [/J3/fg Reactor Engineer /Date i
RODS FULLY WITHDRAWN FULL OUT LICHI - ILLUMINATED AND ALL RODS POSITION 48 IS ROD COUPLING VERIFIED [ STEP' ROD FROM/TO OVERTRAVEL LIGHT ' FINAIPo3HTON INDICATED ON THE a, EXTINGUISHED (2) i VERIFIED 4-ROD DISPLAY (g )l l (YES/NO) (YES/NO) (INITIAL) l i
' f l RSCS-CROUP 3 RW.-CROUP 3 K
46 102-35 100-04 f/4
~
'[ / C l
'47 02-19 00-04 l Un U ~ ~1 '[d ' Q[T l C' l 48 l10-11 100-04 I [(/d I 49 118-03 100-04 (J/ Yd ib fN ( l
@ Y l 50 34-03 00-04 I t// th [7 51 58-27 100-04 Ld[_ d M Nt -r 1 52 58-43 00-04 /. if._ WN M [N r i 53 50-51 00-04 tc'/ (MY .- 1L*- E M y' c. ~( l 54 142-59 00-04 f t'f_ #
j' v / h/ < _1 55 26-59 100-04 t .'d I 1
~ T I l 56 ._18-51 00-04 f t'f. iM l'.- i.
~
l 57 10-43 00-04 d l4'4 . I i 58 10-27 00-04 / (8/d 1 59 18-19 00-04 / (A/ M l 60 26-11 00-04 i (A)( , j 61 42-11 00-04 MK _ 62 50-19 100-04 /. R/I l A/g 63 50-35 00-04 / I 64 42-43 00-04 A/K
~
65 34-51 00-04 Nf I NE 66 26-43 00-04 67 18-35 00-04 h/d
. (1) IF NO, SEE TECHNICAL SPECl[ICATION 3.1.3.7 (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6
.<rcr b -S(,. -/ebS guwb 7e y$
74g.gl Lt. -//ScS-fah R W (es-c.ccf. f0S/fscAf 3A4
H -. -
..,~.
, " .!. g - . . -
e
, s, f. g.. n
', . .s; ... . .
s ; . ~ . Cps . . . - . .
.i . s i.a.- t. .
, ,. l e -
si a it s s 104 a 108 sx s to
-Jj,s -
.,.g e 13-A L5el 26-S9 FRoM ya-4
.. -{:>,'\
. .- . ;';- . . . ty . .y .4- .-
.; y.
, gg . .
. ~ . .
' ' ' 18-51 FRon 2 1 - 2.,
t
. .T *-
II' .' '. . c a. _.,, .I A ' 8 [ w h
~
'. j2.-A $ N l t- C) FRon 4 5 - 3. n.
. . .... i .
r
.. l . .'. ,.
y , . lg _s . . _) , q -* .' . Y = 114 Me s .
~ '
r t . 9 .
. (PS *
- t. ..
@' s 1 : s 10 s 108 s f03 's 108 s 1C ll- F O*. 18-Si FR M 38-9F x = sl- G ab*,h, Q m , h \ 18-58 F Rom 36-38 1
.c .
i 1 . . ' ~ -
, ,,_ y g.gga\ i s g pg,n 3 , _ , ,,
uM.Qd sees
' j[ ..
2= l t _e. it r 3,.3 , 8 - -
's - ,. \
' f .p -
e i j
). . . . . - .
g;75 .' g r. /) was n-1 i. l g
~ ; t- .- . y ,3 ,,,,,,.i -/ ,.,, a ,, d a S . e , , , .,/
v 11. i*
, < wo s dw 'n .
. CPS -
'r . r l
10 4 s s to - stot.* s 105. . s los ggff,g g);tQg( ig.ft Men 72-3o s \ 7 i.. j
$A/t 1. 6t .M. *
(,
/ -
,t A Q;Qa\ \ t - 51 F R ors 0 * - 2. 3.
', - ~.
;. \ , . ,..
~
c
)n N 1
[ , a
,e.' r.
c 7
*.'s - .
r .. . y J., .- ' e ..
. . m- ,
... .=. . .
'.. .. : /o-A v3ttkir a \
1 . .,z
. 5. .
ts , . 2 .
,, CPS 10 A g,&g,agR
., I ,
- 10 4 s1' s'io r.
1 (df. s* l 1orf s Idt
. . o.
's n
- J * . - * ,
.. . . =
3 81
p-. 1 1 . s 16 ' s 'it S Kij)
's esp' .s [*P s _CiP
.ys 1.::- - ..~,-
a
- r. .
~ 1 ,'.
.v
\ . t
. e.
s :.t . ..
$~kf .C/D.k. :.
i , t .
~)
s*
. .:. 5 -
l * .- g, -,;,, . ls ... .
- g ..
,. g:
i ! . .s e . .; . . b.,;hil.' @7Nl Ef
. . s.. . .
- 5. .
2 . e . . - s 9; . iss' . x l
- c .. . ' , - .
- r. :- .
.. _ _. }- ,
i
'. /. -. .. g l
1, K, & $f ';Tf( }, gu.f. ~ 4
's: : '. .s. \ ,
. .? ' >
t
.. ' . ,.- CPS . ,; ,
.e i,o , 'E i . l i
1
~
o' aI 3 10: s 10 ' 5 108- 5 108,
's .108'- s _10_8 l
- 1 7.1..' 03 ',
<! . .t.e /.2 3 i } . r-r
' v;- -
I T
- g. . . . . . /f-5 / . '/ F h 2E
- t l . s :.
g_ -
- 7. %
1 1,
. s' t- - .
2 t t:/ s .S.R.O .
,* .t-'-
- SN. .f. I '(' I .(Ct'
/)< . .
'b'
-(J,[g. . ').
3 d /0 'l@
- ~
'
- if S)
UI T ' . . , .'
,e / 2 , .
._ CPS '
9 @J s 'l " s 10 s IC 2 5 108' s 10 8 5' 10s s tos . 1 . 1 >
'/t 9 I ,
I. a 2 /s. '36
. r -
l .,. ;J. IM
.,2c fc M .
I - I . o, C. agj s ..
... . . n.
.g 1 .' > o
.x ..r u
z
~
- .. . t.
l l j ;
- l$ d;l Ic 3 )
1 s i : 2 i i D
.;.. .. CPS .
.. .-1 ..* .
~ . , . .
- 10? s I s 10 ', * 's ,c e s los a 108 - 3 IO'8 ' s#108
.. ' '. v .
- f. ' 'r
; ./g . g . Qg -
%**g z -
l g* . ,. *. .. e .,- c _,< a
,... , ,s... 4. < . j .e.- . . - .
c . .. . . . 4 L e.
', * *: \' -. ,[. I. 'O ' Ig j *
.- ,. . ,i -s .= *.. '
.~.. . . . . .,,.
.a ' % < ,. ? s,; *
.9
- a. .
. s'. >;*.C
. < i s,. . . ' '.d
. s*g, * ; . . .
. a. .
,see s -
1 i. - m-m
.. ,,, t
f SHIFT COMPLEMENT NIGHT OF EVENT 1+ NSS NUCLEAR SHIFT SUPERVISOR SRO 2+ NASS NUCLEAR ASSISTANT SHIFT SUPERVISOR SRO NSO(5) NUCLEAR SUPERVISING OPERATOR 3+# IN CHARGE OF CONTROL ROOM SRO
. 4+# AT MAIN CONTROL (603) PANEL RO 5+ PATROL RO 6 RADWASTE RO 7 TAGGING CENTER (NON-LICENSED) 8 NPPO NUCLEAR POWER PLANT OPERATOR (NON-LICENSED) 9 NPPO NUCLEAR POWER PLANT OPERATOR (NON-LICENSED) 10+# SOA SHIFT OPERATIONS ADVISOR SRO 11+# STA SHIFT TECHNICAL ADVISOR (NON-LICENSED) 12+# STAIT SHIFT TECH. ADVISOR IN TRAINING (NON-LICENSED) 13+ SNE SHIFT NUCLEAR ENGINEER (RX. ENGR.) (NON-LICENSED) 14+ LSTPE LEAD STARTUP TEST PHASE ENGR. (NON-LICENSED) 15+ GESTQ GE STARTUP SHIFT ENGINEER 16 CHEM. TECH -
17 H.P. TECH. OTHERS SUCH AS ISC TECHS. AND MAINTENANCE CRAFT.
+ DENOTES IN CONTROL ROOM AT TIME OF EVENT # DENOTES IN "AT CONTROLS AREA" AT TIME OF EVENT n
s . 1 . , i .: . l x =- a -@ ,,
-t
.I
[I O
" M. ~
mU U3
-. -c wg S-
=' g 5 -** g= -
- . = .- o m .U C
oco,
,v, ,-
VK -
?
ao MI7 6 0s '% s ets o, o
\g 9A s
\N\\\ \ N O N N\
'N \ \\ \ N, N s
_z , NN \\ N I
. , l\ \\\N _
l 's \ A ~. CONTRcts RC \ 5 sg NN\ 4 \ \ \ N,N '
' s-
' , \\ s , N N ' s.
sN\ .x N ' . s s x s\x. . sN \ \ 's . s sysN - N ll N \ . [ 905 \\ . b B
\ . NN s
. 5@ @'N '
Got s N N 7
""g ..
D \ \\s -
\' h
. 602 y h1AlW \
c CONSDLE)
=
s 603 _ ! D ? .- l LEGEN O' $ NSO Cf Console SOA GJ) GE $70 043085 @ NSS QS NSO Alml . - '
, @ NASS * (OSTA SNE}
$TPE)
@ Nso-1,cu p @STA1T @ LSTPE !
DEVIATIONS o IMPROPER ROD PULL
- o INATTENTION TO DETAIL I o FAILURE TO FOLLOW ROD PULL PROCEDURE NOTE: THE OPERATOR AND STA IN TRAINING DID DO A GOOD JOB IN RECOGNIZING AN INCREASING SRM COUNT RATE AND THE
, ' OPERATOR EXPEDITIOUSLY INSERTED ROD TO TERMINATE THE EVENT o FAILURE TO RECOGNIZE THE SIGNIFICANCE OF THE EVENT SO AS TO STOP, EVALUATE AND DOCUMENT BEFORE PROCEG0itHE ON o PERSONNEL IN "AT CONTROLS AREA" FAILED TO RECOGNIZE OR PURSUE THE EVENT o CERTAIN PERSONNEL AWARE OF A SUSPECTED CRITICAL DID NOT PURSUE o WHEN DISCOVERY OF ROD PULL ERROR WAS RECOGNIZED, APPROPRIATE PERSONNEL DID NOT GET INVOLVED IN THE EVALUATION TO DETERMINE THE DETAILS OF THE EVENT o BECAUSE OF ABOVE, DER HAD INCORRECT AND MISSLEADING INFO ON IT o EVENT WAS NOT LOGGED IN NSS LOG OR NSO LOG o FAILURE OF STAFF TO RESPOND o STAFF DID NOT EXPEDITIOUSLY EVALUATE THE EVENT TO DETERMINE THAT PREMATURE CRITICAL HAD BEEN REACHED o THE EXACT STATUS OF THE EVENT EVALUATION SHOULD HAVE BEEN BETTER COMMUNICATED TO NRC m 6P- - . _ _ - - - . - - - -
SAFETY SIGNIFICANCE OF THE EVENT THE EVENT: ELEVEN GROUP 3 CONTROL RODS WERE PULLED TO POSITION 48 INSTEAD OF POSITION 04 AS PER PULL SHEETS AND A PRE-MATURE CRITICAL WAS ACHIEVED. s o SIGNIFICANT PROCEDURE VIOLATION o NOT A SAFETY CONCERN. PLANT WAS IN PROCESS OF START-UP AND APPROPRIATE NEUTRON MONITORING INSTRUMENTATION OPERABLE AND BEING OBSERVED o NO SCRAM. 114 SECOND PERIOD. MAX. COUNT ON SRM'S WAS 6 X 10 8 . NO INDICATION ON IRM'S o NOT GUTSIDE' DESIGN BASIS OR IN AN UNANALYZED CONDITION AT ANY TIME o NO TECHNICAL PECIFICATION VIOLATIONS b ( W 9 l . . . l } e 4
, EVENT EVALUATION SEQUENCE I
DATE TIME
< 7-1-85 2359 REACTOR OPERATOR (RO) AND STA-II.-TRAINING j -
(STAIT) RECOGNIZED PROBLEM. RO STARTED INSERTING RODS TO PROPER POSITION. RO l REDUESTED STAIT TO CONTACT NUCLEAR SHIFT SUPERVISOR (NSS). STAIT ALSO INFORMED STATION NUCLEAR ENGR.(SNE) OF EVENT. 7-2-85 *0005 NSS WENT TO RO AT CONSOLE, NOTICED THAT RODS WERE BEING INSERTED, AND THAT SRM*S WERE DRAWING VERTICAL LINES. (CONSTANT COUNT RATE) ) j, 7-2-85 0005 NSS TALKED TO SNE AND STAIT. NSS DECIDED TO REACTOR HAD NOT GONE CRITICAL. BY THIS TIME 0015 RODS WERE BACK TO CORRECT POSITION AND HAD BEEN i VERIFIED BY STA, SNE AND RO. 7-2-85 0015 NSS CALLED OPS ENGR. AND INFORMED OPS ENGR. i 6 GROUP 3 RODS HAD BEEN PULLED TO 48 OUT OF SEQUENCE, THAT THE REACTOR DID NQT GO CRITICAL AND THAT THEY HAD BEEN RETURNED TO THEIR PROPER j POSITION. OPS ENGR STATED THAT A DER SHOULD BE j PREPARED AND IT CAN BE DISCUSSED IN THE MORNING 7-2-85 1200 DER WAS DISCUSSED AT CARB MEETING AND . EVALUATION WAS ASSIGNED TO REACTOR ENGINEERING j I 7-3-85 1600 MEETING HELD TO DISCUSS PRELIMINARY EVALUATION I RESULTS. SRM CHARTS REVIEWED AND DISCUSSED. j DETERMINATION OF CRITICAL WAS NOT AGREED UPON AND FURTHER EVALUATION WAS REQUESTED. 4 ASS *T. SUPT. AND OPS ENGR. NOTIFIED RESIDENT 4 INSPECTOR OF THE EVENT AND STATUS OF EVALUATION
%g <
g gr 7-4-85 SNE CALLED ASS *T. SUPT. AT HOME AND STATED l hf RESULTS OF HIS FURTHER EVALUATION INDICATED
- g. REACTOR HAD REACHED CRITICAL. IT WAS STATED S THAT A MEETING WOULD BE HELD THE NEXT DAY.
j h" p 7-5-85 1600 MEETING WAS HELD TO REVIEW LATEST EVALUATION DATA. AGREEMENT WAS REACHED THAT REACTOR HAD i b, BEEN CRITICAL AT A PERIOD OF 114 SECONDS. i 7-6-85 EVALUATION DATA WAS TURNED OVER TO ADVISOR TO ' SUPT. FOR INTERVIEWING CNT PERSONNEL, DETERMINE ROOT CAUSES AND RECOMMEND NECESSARY CORRECTIVE-ACTIONS 7-15-85 ASS *T. SUPT. DISCUSSED THE EVENT WITH SE,NIOR RESIDENT INSPECTOR I . 7-
REPORTABILITY o CONSIDERED 50.72 (b) (1) (ii) & 50.73 (a) (2) (ii) ANY EVENT OR CONDITION DURING OPERATION THAT RESULTS IN THE CONDITION OF THE NUCLEAR POWER PLANT, INCLUDING ITS PRINCIPAL SAFETY BARRIERS BEING SERIOUSLY DEGRADED; OR RESULTS IN THE NUCLEAR POWER PLANT BEING: (A) IN AN UNANALYZED CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY; (B) IN A CONDITION THAT IS OUTSIDE THE DESIGN BASIS OF THE PLANT; OR (C) IN A CONDITION NOT COVERED BY THE PLANT'S OPERATING AND EMERGENCY PROCEDURES. o THE NUCLEAR SHIFT SUPERVISOR DECIDED THAT THE EVENT WAS NQT A 50.72 ONE (1) HOUR OR FOUR (1) HOUR REPORT o THE CORRECTIVE ACTION REVIEW DOARD (CARB) CONCURRED WITH THE NUCLEAR SHIFT SUPERVISOR *S DETERMINATION AND ALSO DECIDED THAT THE EVENT WAS NQT 50.73 REPORTABLE. o IT WAS DECIDED THAT-THE RESIDENT INSPECTOR SHOULD BE INFORMED OF THE EVENT. o WE NOW RECOGNIZE FURTHER CONVERSATION WITH REGION III WOULD HAVE BEEN APPROPRIATE. ROOT CAUSES OF THE DEVIATIONS ROOT CAUSES FOR IMPROPER ROD PULL OPERATOR ERROR o DDERATOR HAD BEEN TRAINED AT SIMULATOR USING PULL SHEETS THAT WITHDRAW GROUP 3 RODS TO 48 IN ONE STEP INSTEAD OF THE REDUCED NOTCH WORTH SEDUENCE TO BE USED AT FERMI 2 o THE ROD PULL SHEET DESIGN & APPEARANCE FOR GROUP 3 RODS ARE THE SAME AS GROUPS 1 & 2 RODS. THE WORDS " RODS FULLY WITHDRAWN" IN THE UPPER RIGHT HAND CORNER AND THE BLANKS FOR VERIFYING RODS FULLY WITHDRAWN INDICATIONS MAY LEAD ONE TO BELIEVE THE RODS ARE TO BE FULLY WITHDRAWN. o THE RODS WERE BEING PULLED AT TOO RAPID OF RATE FOR AN OPERATORS FIRST REAL REACTOR STARTUP. THE STAIT HELPING BY WATCHING THE SRM CHARTS ALSO CONTrf!EUTES TO FAST PULLS. o THE OPERATOR DID NOT REVIEW AND UNDERSTAND THE PULL SHEETS PRIOR TO SETTING DOWN AT THE CONSOLE TO FULL RODS. NOTE: ALTHOUGH NOT A ROOT CAUSE FOR THE OPERATOR ERROR EVENT THE RWM LEING PROGRAMMED TO PROVIDE SOME RESTRAINTS OR ENFORCEMENT OF REDUCED NOTCH WORTH WOULD HAVE PREVENTED THIS EVENT. _9 .
i ! [ - , l I ! i i ROOT CAUSES FOR FAILURE OF SHIFT PERSONNEL' TO RECOGNIZE THE EVENT AND ITS SIGNIFICANCE SO AS TO STOP, EVALUATE AND i DOCUMENT BEFORE PROCEEDHVG o NEITHER THE NUCLEAR SHIFT SUPERVISOR OR THE NUCLEAR ASS *T. SHIFT SUPERVISOR WERE IN THE "AT CONTROLS AREA" DURING THE ROD PULLS. o VARIOUS OTHER ON-SHIFT-PERSONNEL IN THE CONTROL ROOM DID NOT DEVOTE NECCESSARY ATTENTION TO THIS "FIRST" STARTUP FOR SOME OF THE CREW. (ONLY 3RD PLANT STARTUP) e THE SOA, THE STA, AND THE NSO IN CHARGE OF THE CONTROL ROOM SHOULD HAVE BEEN MORE VIGILANT IN RECOGN12iNG THE-
, EVENT AND AIDING IN PROPER EVALUATION OF THE EVENT.
j o THE NSS SHOULD HAVE REQUESTED ASSISTANCE FROM AVAILABLE RESOURCES 1 I o ROD FULLS SHOULD HAVE BEEN TERMINATED SO THAT CHARTS COULD BE ROLLED BACK AND PERSONNEL RESOURCES USED FOR EVALUATION. l I l
- IO .-
~ .
ROOT CAUSES FOR FAILURE OF STAFF TO EXPEDITIOUSLY EVALUATE THE EVENT AND INFORM APPROPRIATE PERSONNEL o TOO MUCH TIME AND EFFORT WAS BEING DEVOTED TO MEETINGS AND COMPLETING COMMITMENTS FOR PLANT FULL POWER LICENSE o STAFF DID NOT RECOGNIZE THE IMPORTANCE OF PROMPTLY ADDRESSING AND EVALUATING ROD PULL ERRORS E5 FECIAL.V II 201 TICALIT'i MACHED Q
-lI -
~ ,
l l CORRECTIVE ACTIONS l REMEDIAL o A SECOND QUALIFIED PERSON IS VERIFYING GROUP 3 & 4 ROD PULLS pg g yggs -
.o N/A IS BEING ENTERED IN " RODS FULLY WITHDRAWN" COLUMN BY REACTOR ENGR. IF RODS ARE NOT TO BE FULLY WITHDRAWN t
o CURRENT " FERMI 2" PULL SHEETS ARE NOW BEING USED AT SIMULATOR FOR TRAINING v PLANNED ACTIONS TO PREVENT RECLIRRENCE OF THE ROD PULL ERROR ( a REVIEW THE FORMAT AND LAYOUT OF THE ROD F'ULL SHEETS FOR {'f HUMAN FACTORS CONSIDERATION. MODIFY AS APPROPRIATE. e, o ASSURE THAT THE ROD PULL SHEETS ARE UNDERSTOOD BY THOSE b,l' USING THEM. PROVIDE A COVER SHEET OR INSTRUCTION WITH PULL SHEETS INCLUDING INITIALS OR SIGNATURE TO DOCUMENT THIS UNDERSTANDING OR PROVIDE ANOTHER SUITABLE MEANS TO ACCOMPLISH THE SAME OBJECTIVE. d y ,,p o OPERATE OR PULL RODS AS TRAINED. DO NOT PULL TOO FAST. Q h DO NOT PULL RODS DURING SHIFT CHANGE OR UNTIL APPROPRIATE f PERSONNEL ARE READY. (REF. 7-9-8,5 MEMO NP-85-804 ITEM 2)
$ g )o AGSURE LICENSED OPERATORS ARE TRAINED AND UNDERSTAND THE 6 INTENT AND PURPOSE OF REDUCED NOTCH WORTH PULL CONCEPT &
% THE IMPLEMENTING PULL SHEETS. -
( o ASSURE LICENSED OPERATORS UNDERSTAND THE RWM AND THE PROTECTION AND RESTRAINTS THAT IT PROVIDES AND DOES NOT hgf' rg PROVIDE o ASSURE THAT ALL LICENSED OPERATORS AND APPROPRIATE ' SUPPORT PERSONNEL ARE AWARE OF THIS EVENT AND ITS SIGNIFICANCE 9 (VIDEO TAPE OF THE EVENT HAS BEEN MADE & IS BEING SHOWN.
; A MORE EXTENSIVE VIDEO TAPING OF THE REENACTMENT OF THE EVENT AT THE SIMULA10R IS PLANNED WITH A GOAL OF 8-0-05)
. / CONSIDER MODIFYING RWM PROGRAM TO INCLUDE SOME REDUCED X(o NOTCH WORTH CONTROL RESTRAINTS. MODIFY IF FEASIBLE.
~ m2 -
l
. L 1
l CORRECTIVE ACTIONS PLANNED ACTIONS TO PREVENT RECURRENCE IN REGARDS TO FAILURE
, TO RECOGNIZE THE SIGNIFICANCE OF THE EVENT SO AS TO STOP, EVALUATE AND DOCUMENT BEFORE PROCEEDING ON o REVIEW SHIFT PERSONNEL RESPONSIBILITIES AND MAKE CHANGES
- AS REQUIRED TO ASSURE PROPER MANAGEMENT OF CRITICAL CONTROL ROOM ACTIVITIES. (REF. 7-19-85 MEMO NP-85-804 ITEM 1) o ASSURE THAT THE ROLE OF THE SOA AND STA IS UNDERSTOOD AND BEING PROPERLY FOLLOWED. ENCOURAGE NSS AND NASS TO USE THESE PERSONNEL AS WELL AS OTHER QUALIFIED PERSONNEL ON SHIFT. (REF. 7-19-85 MEMO NP-85-804 ITEM 3) o ASSURE THAT THE SNE TAKES AN ACTIVE ROLE IN ROD PULLS /-
INSERTIONS AND THE EVALUATIONS OF UNPLANNED REACTIVITY CHANGES o IMPROVE LOG BOOK ENTRIES AND ASSURE EVENTS SUCH AS THIS EVENT ARE LOGGED. (REF. 7-19-85 MEMO NP-05-03) o REVIEW SHIFT TURNOVER PROCEDURES TO ASSURE THEY ARE ACCEPTABLE FOR THE OPERATIONS MODE OF THIS PLANT l
~
i ' 4
'ELIMINARY NOTIFICATION OF EVEN 'R UNUSUAL OCCURRENCE--PNO-III-f 58 Date 1 5. l iis preliminary notificaticn constitutes EARLY notice of events of POSSIBLE safFtyTr . iblic interest significance. The information is as initially received without veri-pM' . ' ' caticn or evaluation, and is basically all that is known by the staff an this date. icility: Detroit Edison Company Licensee Emergency Classification: Fermi 2 Nuclear Plant Notification of an Unusual Event Newport, MI 48166 Alert - Site Area Emergency Docket no: 50-341 General Emergency C Not Applicable . ibject: INADVERTENT CRITICALITY s.1ulv 15, 1985, the licensee reported to the Senior Resident Inspector that an agn.. ering analysis of reactor startup activities on July 2,1985, had determined 1at the reactor had been brought critical at that time without the shift supervisor talizing that criticality had been achieved. (Fermi 2 had its initial criticality on 2ne 21, 1985.)
; ring the reactor startup on July 2, a reactor operator moved 11 control rods in Group 3 to le full out position. The operator failed to follow licensee procedures in moving the ads--they were moved to the full out position, instead of being moved 1 steps, in accordance with the procedure. The reactor operator noticed the power evel increasing faster than hc anticipated, and he promptly returned the 11 rods to the ally inserted position.
he shift supervisor then reviewed the operator's actions, and determined that the reactor ad not gone critical. Startup activities then resumed using the step-by-step procedure, and citicality was achieved consistent with the expected estimated c itical position. ive days after the incident, a reactor engineer concluded that the reactor had , n fact gone critical during the initial Group 3 rod movements. egion III (Chicago).was notified of the inadvertent criticality at 1:30 p.m., CDT). July 15, 1985. The licensee has initiated an investigation of the criticality ncident. An NRC technical specialist has been dispatched to review the ircumstances of the incident. The Office of Nuclear Reactor Regulation has een informed. Region III is also reviewing the time lapse between the event, the etermination of criticality, and its being reported to the NRC. he plant is currently operating at 2 per cent power, he State of Michigan will be informed. his information is cur ent as of 7 a.m., July 16, 1985. ' ONTACT: ssotimos E. r nman . FTS 388-5716 FTS 388-5518
- t. P MNBBf.00 Phillips h E/W M h Willste h.~.13 QCairman'Palladino EDO NRR IE NMSS om. Roberts PA OIA RES om. Asselstine MPA AEOD lom. B:;rnthal ELD AirRightsh3 MAIL:
om. Zsch" ' SP INPO MD ADM:DMB @CY + ~ > / / NSAC . 9 DOT: Tran's Only $RS "* d . o
LIMINARY h0TIFICATION OF (VEN1 OR U; USUAL OCCURRENCE--PNO-III-85-58A Date s prelicinary notification etn itutes EARLY notice 6f events o. POSSIBLE saMy iWF lic intersst significance. The infomation is as initially received without veri-A /e/e4/ s tion cr evaluation, and is basically all that is known by the staff on this date. # l ility: Detroit Edison Company Licensee Emergency Classification: I Ferr.i 2 Nuclear Power Plant Notification of an Unusual Event ' Newport, MI 48166 Alert - Site Area Emergency Docket No: 50-341 XX General Emergency Not Applicable [ f;ct: INADVERTENT CRITICALITY (UPDATE) July 16, 1985, Region III (Chicago) issued a Confirmatory Action Letter to Detroit Edison ipany, documenting the company's comitment to restrict the power level of Femi 2 to ar cent, pending completion of an evaluation of the July 2,1985, inadvertent critic 0 ., ident. Also to be addressed as part of the evaluation are Reactor Operator training and operability of the Rod Worth minimiz'er. The licensee must seek authorization from the ional Administrator before exceeding the 5 per cent power level. licensee team investigating the incident is being headed by the company president. The Resident Inspecter and a Region III specialist are evaluating the incident and the ensee's actions. Licensee officials will meet with Region III management on p 23, 1985, to review the circumstances of the incident and the licensee's evaluation.
' plant is currently operating at a power level of 2 per cent. . State of Michigan will be informed.
s information is cur ent as of 11:30 a.m., July 17, 1985. _~ iTACT: llN.'Chri Y h .. sotimos $4.W E. Greenman FT5 388-5716 FTS 388-5518 s iTRIBUTION: 9:5b
- 5t.]M.' MNBB).2.$ Phillips. /.'/A. E/W /. 0 g[ Wi11ste/.'/[
iirman Palladino ED0 NRR IE NMSS
- n. Roberts PA OIA RES
- n. Asselstine MPA AEOD
- n. Bernthal : ELD AirRightsI.'90 MAIL:
- n. Zech SP INPO ADM:DMB
- Y NSAC g),QDOT
- [ Trans Only t5 Applicable Resident Site /7t/O-Regions I]M,111.36. IV j.'3D, V_/73J Licensee (CorporateOffice))ZdI Rev, 07/06/84 fy_Q Sf'C / ' Q ,
, i ..
l l FERiil 2 PRESEf4TATION TO NRC REGION 3 PREF %TURE CRITICALITY OF JULY 2, 1985 JULY 23, 1985 87
~~~
b 1 4 PRESENTAT lord OUTL INE
- 1. INTRODUCTION i
iI. FERMI 2 OPEPAT10145 111. DESCRIPTION OF EVENT IV. DEVIATI0llS V. SAFETY SIGNIFICAt4CE OF THE EVENT VI. REPORTABILITY CONSIDERATIONS
; Vll. ROOT CAUSES AND CONTRIBUTING CAUSES VIIl. CORRECTIVE ACT10NS i'
IX. ROD WORTH MINIMl2ER DISCUSSION 1 X. TRAINil4G XI. SUt41ARY, C0tlCLUSIOtlS AtlD LESSONS LEARNED F 1 ! r I i 1 s ,
. . _ . . _ _ _ . ~ . _ _ ._ _.
I 4-II. FERMI 2 OPERATI0lis DATE ( TIME 04-09-85 SHUTDOWN MARGIN TEST f 06-21-85 FIRST STARTUP CRITICAL AT 0519
, 06-28-85 MAflUAL SCRAM AFTER CRD PUMP TRIP 1418 i POWER < 1% PRESSURE 140 PSIG
) 06-29-85 SECOND STARTUP CRITICAL AT 1109 { 07-01-85 SCRAM FROM FALSE REACTOR WATER LEVEL 3 1432 SENSING LINE VALVING ERROR i POWER < 2% PRESSURE 140 PSIG 07-01-85 THIED STAP. TUP PREMATURE CRITICAL AT 2359 } 07-02-85 CRITICAL.AT 0050 07-05-85 SCRAM FROM REACTOR WATER LEVEL 3 1 1531 j lIAlH BYPASS VALVE PROBLEM I POWER < 4% PRESSURE 630 PSIG f j 07-06-85 FuuhrH SIARTUP CRITICAL AT 0107 i ) 07-09-85 SCRAM FROM REACTOR WATER LEVEL-3 2301
\ -
MAIN BYPASS VALVES IN MANUAL j POWER < 5% PRESSURE 955 PSIG l 07-10-85 FIFTH STARTUP 0935 i
- i t
e
1 j .. -. i i 1 III. DESCRIPTION OF EVENT ! i } i il ; ! i I i. i i A. THE EVENT U i
?
B. Roo PULL SHEETS AND CORE PLAll . C. sri 4 CHARTS : i D. SHIFT COMPLEMENT [ 1 3 1 1 A i a
# [
d 4 k { 4 1 1 1 i t 4 i k i i
.,._.-,,_,,,~__-..,_,-_-.m.._,,--_.,-,.,_.._..,__.,...-.,,.._,_,__._,,,-,.,,,,__,#_., . _ . - , . . . . . _ _ . - - - , . -
_ _ _ . 4 - -.._ _ _ - L-. t . < I A. THE EVENT i IMPROPER ROD PULL EVEFE EVENTS OCCURRED ON THE 3RD SHIFT 07-01-85 AtJD THE IST SHIFT 07-02-85. j TIME SEC 2220 50 R0 ON 3RD SHIFT STARTED PULLING RODS i 2314 52 R0 ON 3RD SHIFT COMPLETED STEP 37 0F rod PULLS 2316 03 R0 Ou IST SHIFT STARTED PULLING RODS PER STEP 38 i (HE HAD PREVIOUSLY OBSERVED PULL OF SOME PREVIOUS RODS AND SOME TURNOVER OF INFO HAD TRAflSPlRED)
; 2320 STARTED SHIFT TURNOVER MEETING l 2326 10 RECElVED A SPURIOUS RWM BLOCK I 2330 COMPLETED SHIFT TURNOVER MEETING 2335 04 RWM BLOCK CLEARED BY REINITIALIZING
, 2336 02 CONTINUED PULLING ROD 22-31 AS PER STEP 44 I 2340 50 ROD 02-35 WAS PULLED BEYOf10 04 TO 48 WHICH MAS START OF ROD PULL ERROR l 2359 08 COMPLETED COUPLING CHECK OF 18-51 (llTH ROD WITHDRAWN IN ERROR). RO AND STAIT NOTICED CollTINUED INCREASE IN SRM COUllT AND RO NOTICED THE 1
- .CD ;'ULL CRROR 2359 33 RO STARTED INSERTING ROD 18-51 AND ASKED STAIT To G0 GET THE NSS 0014 14 ALL ELEVEN RO3S PREVIOUSLY PULLED INCORRECTLY WERE
- ' !!OM BACK AT NOTCH 04 j 0014 49 STARTED PULLING 10-43 AS PER STEP 57. Sf1E AND STA HAD VERIFIED PROPER ROD POSITIONS USING 00-7 OPTION J
=
4 4 e l l i9 s ,1 X X 7 - - "Sm A SRmB 6 a X X X X 5 z i X X X s X .. smo X X" sm c X 1 X X X 5 .
; 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 EF - 2 Core Map GROUP - 1 l
l,
i
- e S
X X X X X i X X. X "scM A X X .
" sam 8 X X X X X X X X X 1
i X X X X X X X . X' X X . SbtD X X . SAM C X X ! X X X X X X X X X X X X _J 1 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 i i EF - 2 Core Map Gh0UPS - 1 & 2
ge. . x x ns X X X X X h ' X . X X 17 ~ j y [ y
-e y y
+ X X X X X X X
- s X X X X X LX X X X X X 1
7 _ hf f l l 3
'X X. X X X X X
, y ,
-cy y
,. c y
s - X X X X X X X 1 iX X X 7 [ [ 3 02 06 X X' . 10 14 18 22 26 30 34 38 42 46 50 54 SE EF - 2 Core Map GROUPS L 2 & 3
8 ' s9 - X X X X-p5 X X X X X b1 X X X X X X \7 -
'f ~l seAf f l f f' s" B X X X X X'X X X r3 9
X X X X X X X s X X X X X X X X 1 X X X X X X X ;' 7 l l l l l l l ll X X y- X X Xy- X X 3 X X 'X X X X XX e s X X X X X X X i XX X X X X 7 [ s - 02 06 10 14 18 X X X X 22 26 30 34 38 42 46 50 54 58 i l EF - 2 Core Map GROUPS 1, 2, 3 & 4 EF-2 ROD SEQUENCE CHECKOTF.8HEET
~#'
START DATE TIMK 2238 SEQUENCE B-1 PAGE 1 of 72 SIGNATURE ' N5S/MO APPROVED BY: Ga J~ % 8//Jfg-ngftreer/5 ate ' RODS FULLY WITHDIEVR l FULL OUT LIGii'I l
]LLUMINATED AND l STEP' ' ROD TROM/TO ALL RODS POSITION 48 IS ROD CX)UPLING Vr.RIFIED/l i FINAL N TITON INDICATED ON THE OVERTRAVEL LIGHT l
, VERIFIED EXTINGUISHED (2) (INITIAL) 4-ROD DISPLAY (3 )l (YES/NO) (YES/NO) { l RSCS-CROUP 1 RW.-CROUP 1 l _1 22-55 00-48 I */8 FIPS Ve5 1 2 14-47 00-48 M FPS 70 3 06-39 00-48 @ IO l I 4 06-23 00-48 b h y65 YO I 5 14-15 00-48 M$ YE5 Vf} 6 22-07 00-48 b I 8 15 uM 7 38-07 00-48 l l Y 83 V65 1 8 46-15 00-48 b b V65 l 9 54-23 100-48 [D V/1 Ul3 10 54-39 00-48 .M 1
&' 65 11 46-47 00-48 l -
VU /[3 ! 12 38-55 00-48 I Ff5 t/(3 13 30-47 00-48 h ' [I Eh 1 14 22-39 00-48 M Eh l 15 14-31 00-48 l VD l FO 16 22-23 C0-48 h V(7 /b 17 30-15 00-48 I/II I 18 38-23 00-48 [ ' I 19 46-31 00-48 h 20
- 38-39 00-48 Il -
21 30-31 00-48 h- h// J * (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.7 (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6
@ Ap1)ruscesa Fu40d<r Fe n A ' C 5' :
3A\ t -
~
. . . B. ROD PULL SHEETS e EF-2 ROD SEQUENCE CHECKCFF SHEET 8EQUENCE S-1 PACE 2 sf 72 APPROVED BY: _ 13f3-R5DDDEEY7TTRERAW FULL OUT LIERT '*
ILLUMINATED AND . STEF ROD FROM/TO ALL RODS POSITION 48 IS ROD COUPLINC VERIFIED / FINAE7b31TTON INDICATED ON THE OVERTRAVEL LICHT VERIFIED EXTINCUISHED (2) v (INITIAL _) 4-ROD DISPLAY (1)l (YES/NO) (YES/NO) i RSCS-CROUP 2 RW.-CROUP 2 l M 22 14-55 00-48 W5 W'> l
'23 06-47 00-48 h v(4 YO 24 06-15 00-48 M I F4$ Vf5 25 14-07 00-48 /6 1/ O I 26 46-07 00-48 kb 16 27 54-15 00-48 28 54-47 00-48 - 0 29 46-55 00-48 [b FI) hM 30 30-55 00-48 h fP W.2 31 06-31 00-48 h MS IN l 32 30-07 00-48 [h FN O 33 54-31 00-48 M /(7 L/
34 46-39 00-48 (I b 35 38-47 100-48 l .h I/O I 36 22-47 00-48 h Yb
._37 14-39 00-48 [N 55 I l 38 14-91 00-48 I I 00-48 i 39 22-15 I 40 38-15 00-48 b '
41 . 46-23 00-48 P N - 42 38-31 00-48 [ - 43 30-39 00-48 , (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.7 (2) IF MO, SEE TECHNICAL SPECIFICATIOP 3.1.3.6 30E _.- - _ - . _.
. .. . B. R0D PULL SHEETS EF-2 ROD SEQUENCE CHECK 0FF SHEET SEQUENCE 3-1 _ PACE 3 et 72 AFFROVED BY: g.
ROD M l M HDRAWN FULL OUT LIDWT - I
- ILLUMINATED AND !
STEF *. ROD TROM/TO ALL RODS POSITION 48 IS ROD COUPLING VERIFIEDA l FINAE P651TTON INDICATED ON THE OVERTRAVEL LIGHT VERIFIED EXIINGUISHED (2) (INITIAL) 4-ROD DISPLAY (3)l (YES/NO) __ (YES/NO) l RSCS-CROUP 2 R'iM-CROUP 2 44 22-31 00-48 bl \ ' %/ p}hg__ __ 'ft$ 1 45 30-23 00-48 UY hbh Nd 1 I I I I f 1 I l l I I I I I I i ll l l I I l l l , l 1 (1) IF NO. SEE TECHNICAL SPECIFICATION 3.1.3.7 - (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6 - 3A3
,, . EF-2 ROD S'E. hut'All Ull'LkOfY"ShfET SEQUENCE S-1 PAGE 4 of 73 APPROVED BY: _
g (/jg/g eactor ngineer/Date ROD 5 FULLY WITHDRIUN FULL 007 LITHY , 3LLUMINATED AND ALL RODS POSITION 48 IS ROD COUPLINC VERIFIED [ STEP ,. ROD FROM/TO OVERTRAVEL LICHT 4 FINAL PD311 TON INDICATED ON THE VERIFIED EXTINGUISHED (2) , 4-ROD DISPLAY (g)l (YES/NO) l (INITIAL) (YES/NO)
' s RSCS-CROUP 3 RW.-CROUP 3 K
46 02-35 00-04 C/( '[ 7 7C 47 02-19 00-04 Un U l 'ffb' V[ T I 48 10-11 00-04 164 I NA f' l 49 18-03 00-04 f.J/ h!b NI7 7 I I 50 34-03 00-04 t,T d- NT i F 51 58-27 00-04 14/(_ N i M 't i 52 58-43 00-04 /. s/_ &JI 'rN !b r 53 50-51 00-04 te'/ (Md CD. it*. aC
#^
54 42-59 00-04 It'/_ M y's ( 55 26-59 00-04 t .t' 'b I N( l I I ~ T 1 56 __18-51 00-04 fv4 WE- i 57 10-43 00-04 l4'I .
)
l 58 10-27 00-04 ]/ (i/M I 59 18-19 00-04 / (df 1 60 26-11 00-04 / 4)( 61 42-11 00-04 A/K U 62 50-19 00-04 / #,/X' 63 50-35 00-04 / A/g 64 42-43 00-04 M4 ' I 65 34-51 00-04 Nf -
~
66 26-43 00-04 NK 67 18-35 00-04 d #f (1) IF NO, SEE TECHNICAL SPECIFICATION 3.1'3.7 (2) IF NO, SEE TECHNICAL SPECIFICATION 3.1.3.6 ..
. tar, yt, -SC ~/ebs Auwb 7c 16 yge.J ci -isson-rab 77.'
W (trtest.fbs/fnAl 3M
b.
~
; ?,' ,- S. ' .*, u it 4 A C. SRM' Charts ^
- .. ~ t'A7s }-
. .t .
.: ,,.- . ces . . . - .
.l. .
- t. o t.yi. (.e. ..
t .
- u io 3ia.sm- n 108 s1; 15-A Lsad 26-s i FRom va-y t
i . . . ,.
. .y,s S,\ +-
g
.. m. . .
enon
?.-
. .e. .
. 12,- g .Tw f Is-so u . 2, 3:,.( '
.! - .. ." 's . ,
s r
. l2.-A l'M e- si Fae s 4 * - 2 =_
c , '
,3 q. -
t . T = fry e s. g o.r (PS
- od s I : s no a 108 s ros -s soa 's tcr ll.r g,Med is -s s FRon Br-et .
==n s!- G o Kh .Q w b r\ 18-58 F CDM 36 3 v .
OfQur\ is-ce
.~ . -
, ,g.y pgan 3 2 . y t,,
x:tI-c.u%Q,samL ss-Te FRan S o - 3 s. 9 . , ts
'- I s~
I . ... > a ; . P '. * :- .
/) was n:.i i .~ l
.y. g . e f f. .
.g J .-- '
t~ ' . .. . n 3 w m,1r.:. a ,, d .a s tr. o;, 4 1' f,e w s de 'h . CPS , 70 4 s ato: s 10 0 s'ios. - a ios . d 17-//-6 h) tided it -ri sRon 22-3 1 s _i
$p.f'A.@-
I , . ,'. .. l . it ; d;% m\ I t - si FRan 0 * - 2 ^2.
~
. .. . \. , ..- z. .
1
- ... ,.- , }. ; '. .; .. i.; ..
- ;. - m-fo-s usttkira\
'i. I,; .
- r.'
.7 b
. c. .
; . . u ,
#0~A A La3d CPS- :.
c; ,. :. . . I'. l E0d U 1 n'4- I LI I r id. ' s 10T' O tI'. . . g' .. 13 _ _ - __ _ _ _
c
..... ~;. .
. s ,, . , .,
.. . r. u ... ., ,
3 .,s,. 4
- 5.t .
skt, .C/6 j,;.
'l
... . : C. SRM Charts
. s .
. . h, . . . .. , .
..r .
... .. . ... r.-
-n.
,4., ., .,i, r.
h ' C .l -
.. .y , .. s.
~ . -
L. _ , '. / .
,, 1 .. , ,. . ...
.- s ,,
.. "a
- w. . .- .
- e,. ." d .i- .
.] ,
.-,[c . 11 .;
.i: : .. iv.y \
L z);p:s.g.p,_ {
.... n. s.
\ ,
]'
CPS .
.. .,o' (. i. 5 V -
s tr
- s 10 's10P s 10'- a lot '810* '
.[... .
l si_
- ' .s e -t I . ,2 L. f..s .' 02. .
, ., .<.- . s. .
I
. . /05 / .v E h 21
.~
.+..
q 3,
/. .
s..c:1 u
- ~
- ./ S. ,r .
t t 5/,1 1A 0
.. _(&Il< '
-(31 rel}
'.t. i s) 3e h '/6 E- '
g it a 36 43 3-
~ '-
h b. . e
'Sf" s 10 s IC '
s 103 ~ 8 10, 8 s' los stos. L ' '/( '2] d'3 d
- 3 ).
' : .. IE..5), .2c fe .dk -
. l
;- i
. 21:
- 3. ~..,.
- o. ;
. s ,2 o
. 1
~ -- .__
.o
.' ' o u
.. . o
- _ z I '* . < e e.
. S, . .i.
\ 1 [
. g. . ~;; .
. 2 /c 33 v
) * ,: - e.- l , CPS . h5 *
' sl 1034 108
. 8 Id T * 's C 3 d IOs . s 108 ,
5 .
'. u ., ..%.
s . ..
.r-p a .. . '.
..- . 7 r.; -
.jg . . ;f ,
(c gg -
.. ..;... 7.
..s m...
s.
, ... .. . . ., . .,.. . ; s ,. .
.,s .
.' . ~ <
- ... . . . .o :'
v.e.,s :.:
, ..:. < .- -, , . - (.
- r. ,. s
';,; t,e r~: >
. . .~ .., -
<f ,
'.g , ,5 ; ~y .;.. '; .- g- [ q 14
'yz
.5,, s
,. e.
O d D. SHIFT COMPLEMENT NIGHT OF EVENT 1+ NSS NUCLEAR SHIFT SUPERVISOR SR0 2+ NASS NUCLEAR ASSISTANT SHIFT SUPERvlSOR SR0 NSOCS) NUCLEAR SUPERVisi!4G OPERATOR 3+# IN CHARGE OF CollTROL ROOra SRO 4+# AT MAIN CONTROL (603) PAf4EL R0 5+ PATROL RO 6 RADWASTE RO 7 TAGGiliG CEt4TER (NON-LICENSED) 8 IPPO NUCLEAR POWER PLANT OPERATOR (N0il-L ICEtJSED) 9 (PPO NUCLEAR POWER PLANT OPERATOR (NON-LICENSED) 10+# SOA SHIFT OPEl:ATl0f15 ADVISOR SR0 11+# STA SHIFT TECHNICAL ADVISOR (N0fi-LICENSED) 12+# STAIT SHIFT TECH. ADvlSOR lti TRAlfilNG (NON-L ICEllSED) 13+# SNE SHIFT NUC. Ef4GR. (RX El4GINEER) (NON-LICENSED) 14+ LSTPE LEAD STARTUP TEST PHASE ENGINEER (Nott-L ICENSED) 15+ GEST 0 GE STARTUP SHIFT ENGINEER 16 CHEM. TECHillC I AN 17 HEALTH PHYSICS TECHNICIAN OTHERS SUCH AS l&C TECHNICIAf15 AND MAINTENANCE CRAFT j i
+ Dell 0TES IN CONTROL ROOM AT TIME OF EVEt4T l
# DENOTES IN "AT C0rlTROLS AREA" AT TIME OF EVENT i
e i - 15-l l
~
'Do SHTIT COMPLEMENT LOCATION IN CONTROL ROOM
_ l 3
=
[ , u
- f
,b -
3
- ).,
("
,i e .
,m
.gg pt "v.
..g e 4~
- s 5 B g g '
5 -
=
>Yn
/f
[___ $ l--- O asi 's ; ars 306 s *or 9, , .NNNN'N~ Ns , g
.NN \\ NNNs gsN '6
' NNxN .I N l\ NNNN .
f, e N N \ N A7. )er#c' h RC
' s s s xN 4 N N N NN s\
sNN . N's'(Ng s , s N N 's f- A s s xNN N.- -
,y N\N ssx xN \ '
N N , - GOS . gN, == I NN -- N' 6 01 s\ N s,
@ @' s' y N .g N
"$E N\N -
D = Es3 804 \' bx s 6oa E l ,1 - i u. f $1AlW ~; CONSDLE
$ q .
603 . - D ' .. [7 L EGUVO - '
@ NSO ClCnns0l9 $0A & GE STO
@ NSO M '*l. SNE) u m , @D
, NASS NSS ' %)Srn .
srps) D3 NSO-irsCh g &STA1T @ LSTPE, y.. . . . . . ~ . . . , - - . . . . . : e. -
._ _ _ __ _ _..__=_ __, _
D 4 IV. DEVIATIOlJS A. IMPI'oPER Roo PULLS - OPERATOR ERRon I , i B. FAILURE TO: RECOGNIZE EVEllT To STOP To EVALUATE To DoCUf1ENT BEFORE PROCESSING 4 C. FAILURE OF STAFF To RESPOND l l i 1
- I l i l
IV. DEVIATIONS A. IMPROPER ROD PULL 0 INATTENTION TO DETAll 0 FAILURE TO FOLLOW ROD PULL PROCEDURE NOTE: THE OPERATOR AND STA IN TRAINING DID DO A GOOD JOB IN RECOGNIZING AN INCREASING SRhl COUf4T RATE AND THE OPERATOR EXPEDITIOUSLY INSERTED ROD TO TERMINATE THE EVEtlT B. FAILURE TO RECOGt41ZE THE SIGillFICANCE OF THE EVEllT SO AS TO STOP, EVALUATE Af4D DOCUMENT BEFORE PROCEEDING 0 PERS0tlNEL IN "AT C011TROLS AREA" FAILED TO RECOGNIZE OR PURSUE THE EVENT 0 CERTAIN PERS0tillEL AWARE OF A SUSPECTED CRITICAL DID fl0T PURSUE O WHEN DISCOVERY OF, ROD PULL ERROR WAS RECOGNIZED, AFPROPRIATE PERS0!!NEL DID I40T GET INVOLVED IN THE EVALUATlott TO DETERMif1E THE DETAILS OF THE EVENT 0 BECAUSE OF ABOVE, DER HAD INCORRECT Af4D MISLEADING INFORMATION Oil IT 0 EVEliT WAS NOT LOGGED IN NSS LOG OR HSO LOG C. FAILURE OF STAFF TO RESPOND O STAFF DID t40T EXPEDITIOUSLY EVALUATE THE EVENT TO DETERMINE THAT PREMATURE CRITICAL HAD BEEN REACHED 0 THE EXACT STATUS OF THE EVENT EVALUATION SHOULD HAVE BEEN BETTER COMMUNICATED TO NRC
V. SAFETY SIGfilFICANCE OF THE EVEf4T THE EVENT: ELEVEN GROUP 3 C0fJTROL RODS WERE PULLED TO POSITION 48
~
INSTEAD OF POSITl0f4 04 AS PER PULL SHEETS AfJD A PREMATURE CRITICAL WAS ACHIEVED. A. SIGillFICAllT PROCEDURE VIOLATIOfJ. B. NOT A SAFETY CONCERN. PLANT WAS IN PROCESS OF STARTUP Af1D APPROPRIATE NEUTRON M0filTORING INSTRUMENTATION OPERABLE AND BEING OBSERVED. C. NO SCRM4. 114 SEC0!4D PERIOD. MAXIMUM COUNT ON SRiIS WAS i " '" . "? :2 ' CAT 10ft ON IPJ.ls . D. NOT OUTSIDE DESIGN BASIS OR lil AN UNANALYZED CollDITION AT Arsv T e ts: E. NO TECHNICAL SPECIFICATIOli V10LAT10!1S. l l l
. . - - - - . - . . . - . . .. - . .. ~ .
. i P
i 2 i f VI. REPORTABILITY CONSIDERATIOfJS : I i
- A. DEVIATION EVENT REPORT (DER) EVALUATION I j B. 50.72 AND 50.73 REVIEW 4
I t I l 1 1 I i i 4 4 i i i 4 4 h I i , I . _ , . , . . - _ _ _ - - . . . . _ . _ . . . . . . 3_...___, . _ . _ . . . _ _ , . _ . ._ __.m . , . . . . . . . _ , . . . _ . 7.__,_,. ,, _. ..;____..._...-_-..
A. DEVIATION EVEflT REPORT EVALUATION SEQUEllCE 07-01-85 2359 REACTOR OPERATOR (RO) AND STA-IN-TRAINING (STAIT) RECOGtJIZED PROBLEM. R0 STARTED INSERTING RODS TO PROPER POSITION, R0 REQUESTED STAIT TO C0f4 TACT flUCLEAR SHIFT SUPERVISOR (NSS), STAIT ALSO If4 FORMED STATION fluCLEAR ENGlfiEER (Sl1E) 0F EVENT. a 07-02-85~035 NSS WEllT TO RO AT CONSOLE, NOTICED THAT RODS WERE BEING INSERTED, AND THAT SRMS WERE
~
DRAWING VERTICAL Lif4ES (C0flSTANT COUNT RATE). 07-02-85 0005 NSS TALKED TO SNE AND STAIT. NSS DECIDED TO REACTOR HAD NOT GONE CRITICAL. BY THIS TIME 0015 RODS WERE BACK TO CORRECT POSITION AND HAD BEEN VERIFIED BY STA, SNE AND RO. 07-02-85 0015 NSS CALLED OPS ENGR AND INFORMED OPS ENGR 6 GROUP 3 RODS HAD BEEF 1 PULLED TO 48 OUT OF SEQUENCE, THAT THE REACTOR DID MQI G0 CRITICAL AND THAT THEY HAD BEEN RETURNED TO THEIR PuuPER POSITION. OPS ENGR STATED THAT A DER SHOULD BE PREPARED AIJD IT CAN BE DISCUSSED ll1 THE MORNING. 07-02-85 1233 DER WAS DISCUSSED AT CARB MEETit1G AND EVALUATIOfJ WAS ASSIGNED TO REACTOR ENGINEERif1G 07-03-85 1000
, MEETil1G HELD TO DISCUSS PRELIMINARY EVALUAT10ft RESULTS. SR'l CHARTS REVIEWED AND DISCUSSED.
DETERMINATIOf4 0F CRITICAL WAS NOT AGREED UPON Af1D FURTHER EVALUATl0ll WAS REQUESTED. 1 I
y (
- ASSISTANT SUPERINTENDENT AND OPS ENGINEER ;
NOTIFIED RESIDENT lNSPECTOR OF THE EVENT AND STATUS OF EVALUATION. 07-04-85 SNE CALLED ASST. SUPT. AT HOME Af4D STATED RESULTS OF HIS FURTHER EVALUATION INDICATED REACTOR HAD REACHED CRITICAL. IT WAS STATED ; THAT A MEETifJG WOULD BE HELD THE tJEXT DAY. i 07-05-85 1600 f.lEETING WAS HELD TO REVIEW LATEST EVALUATION DATA. AGREEMENT WAS REACHED THAT REACTOR HAD BEEN CRITICAL AT A PERIOD OF 114 SECONDS. 07-06-85 EVALUATION DATA WAS TURNED OVER TO ADVISOR TO SUPERINTENDENT FOR INVERVIEWING OF PERSONNEL, DETERMINE ROOT CAUSES AND RECOMMEND NECESSARY CORRECTIVE ACTIONS. 07-15-85 ASSISTANT SUPErslNTENDENT DISCUSSED THE EVENT WITH SENIOR RESIDENT INSPECTOR. O
B. REPORTABILITY O COI4SIDERED 50.72 (B)(1)(ll) & 50.73 (A)(2)(II) At4Y EVENT OR CollDITION DURING OPERATl0f1 THAT RESULTS If1 THE CONDITION OF THE NUCLEAR POWER PLAf1T, INCLUDING ITS PRINCIPAL SAFETY BARRIERS BElf1G SERIOUSLY DEGRADED: OR
~
RESULTS lil THE UUCLEAR POWER PLANT BElf4G: (A) lil Afl UNAtlALYZED C011DlT10N THAT SiGNIFiCANTLY COMPROMISES PLAtlT SAFETY: (B) IN A CONDITION THAT IS OUTSIDE THE DESIGtJ BASIS UF THE PLANT: OR (C) lll A CONDITION NOT COVERED BY THE PLANT'S OPERATING AND EMERGENCY PROCEDURES. O THE NUCLEAR SHIFT SUPERVISOR DECIDED THAT THE EVEllT WAS HQI A 53.72 ONE (1) HOUR OR FOUR (4) HOUR REP 0dT 0 THE CORRECTIVE ACTION REVIEW BOARD (CARB) C0r1 CURRED WITH THE UUCLEAR SHIFT SUPERVISOR'S DETERMillATION AND ALSO DEC!DED T!!AT THE EVEllT WAS RQI 50.73 REPORTABLE. O lT WAS DECIDED THAT THE RESIDENT INSPECTOR SHOULD BE
~
INFORMED OF THE EVENT. O WE fl0W RECOGNIZE FURTHER CONVERSATION WITH REGION Ill WOULD HAVE BEEN APPROPRIATE.
-P3-
i l l l VII. Root CAUSES Af1D CollTRIBUToRY CAUSES o DEVIATiolls e. A. l FOR Roo PULL ERROR B. FOR FAILURE To o RECOGril2E SIGtJIFICAf1CE o To STOP o To EVALUATE o To DoCUt4Ef4T j C. FOR FAILURE OF STAFF To EXPEDlTE REVIEll l \ 1 e
)
t
% t 4
Vll. Root CAUSES OF THE DEVIATIONS A. FOR IMPROPER ROD PULL OPERATOR ERR 0a 0 FAILURE TO ADEQUATELY MANAGE CONTROL ROOM ACTIVITIES DURING IMPORTANT PLAf4T ACTIVITIES 0 THE RODS WERE BEING PULLED AT TOO RAP ID A RATE FOR Afl OPERATORS' FIRST REAL REACTOR STAfsTUP. THE SHIFT TECHNICAL AovlSOR IN TRAlfilNG (STAIT) HELPING BY WATCHlf4G THE SRL1 CHARTS ALSO C0f4 TRIBUTES TO FAST PULLS. O THE OPERATOR DID NOT REVIEW AND Uf4DERSTAf1D THE PULL SHEETS PRIOR TO SITTING DOWil AT THE CONSOLE TO PULL RODS. O FAILURE TO PROPERLY TURF 40VER FUNCTION AT SHIFT TURNOVER. 1 NOTE ALTHOUGH NOT A ROOT CAUSE FOR THE OPERATOR ERROR EVENT, THE Rtti BElf4G PROGRAMMED TO PROVIDE SOME RESTRAINTS OR Ef4FORCEMEf1T OF REDUCED NOTCH WORTH WOULD HAVE PREVENTED THIS l EVENT. 1 l l l l
a
)
0 FAILURE TO OPERATE AS TRAINED / FAILURE TO TRAIN AS OPERATING 0 THE RODS WERE BEING PULLED AT TOO RAPID A RATE. 0 OPERATOR HAD BEEN TRAINED AT SIMULATOR USING PULL SHEETS THAT WITHDRAW GROUP 3 RODS TO 40 IN ONE STEP INSTEAD OF THE REDUCED NOTCH WORTH SEQUENCE TO BE USED AT FERMI 2 0 POOR HUMAN FACTORED PULL SHEETS 0 THE ROD PULL SHEET DESIGN A14D APPEARANCE FOR GROUP 3 RODS ARE THE SAME AS GROUPS l AND 2 Ruus. THE WORDS " RODS FULLY WITHDRAWN" IN THE UPPER RIGHT HAND CORNER AND THE BLANKS FOR VERIFYING RODS FULLY WITHDRAWN INDICATIONS MAY LEAD GNE TO BELIEVE THE RODS ARE TO BE FULLY WITHDRAWN. e i
- - - ^~'
- I l
B. ROOT CAUSES FOR FAILURE TO O RECOGNIZE THE EVENT AND ITS SIGNIFICANCE O TO STOP O TO EVALUATE O TO DOCUMENT O FAILURE TO ADEQUATELY MAf1 AGE C0f4 TROL ROOM ACTIVITIES DURif4G CRITICAL PLANT ACTIVITIES 0 NEITHER THE NUCLEAR SHIFT SUPERVISOR OR THE NUCLEAR ASSISTANT SHIFT SUPERVISOR WERE IN THE "AT CONTROLS AREA" DURING THE ROD PULLS. O VARIOUS OTHER Off-SHIFT PERSONNEL IN THE CONTROL ROOM DID NOT DEVOTE NECESSARY ATTEf4T10N TO THIS "FIRST" STARTUP FOR SOME OF THE PERSONNEL. (Of4LY 3RD PLANT STARTUP) 0 THE SOA, THE STA, AND THE NSO IN CHARGE OF THE CONTROL. ROOM SHOULD HAVE BEEN MORE VIGILAf1T If4 RECOGNIZlNG THE EVENT AND AIDING IN PROPER EVALUATl0fl 0F THE EVENT. O THE NSS SHOULD HAVE REQUESTED ASSISTANCE FROM AVAILABLE RESOURCES. O ROD PULLS SHOULD HAVE BEEN TERMINATED SO THAT CHARTS COULD BE ROLLED BACK AND PERSOf4NEL RESOURCES USED FOR EVALUATION.
~ . ~ , .
C. FOR FAILURE OF STAFF TO EXPEDITIOUSLY EVALUATE THE EVENT AllD INFORt.1 APPROPRIATE PERSONf1EL 0 flUCH TIME AND EFFORT WAS BEING DEVOTED TO MEETINGS AND COMPLETING COMMITMENTS FOR PLANT FULL POWER LICEtJSE. O STAFF DID f10T RECOGNIZE THE IMPORTAIJCE OF PROMPTLY ADDRESSif1G AND EVALUATING ROD PULL ERRORS. I l
Vill, CORRECTIVE ACTIONS A. REMEDIAL 0 A SECOND QUALIFIED PERSON IS VERIFYING GROUP 3 AllD 4 ROD PULLS , SCHEDULE: DollE (filGHT ORDEi:: 7-3-85, 1348 HOURS) 0 N/A IS BEING ENTERED IN " RODS FULLY WITHDRAWil" COLUMN BY REACTOR ENG INEEi! IF RODS Ai!E il0T TO BE FULLY WITHDRAWN. SCHEDULE: DONE O CURRENT " FERMI 2" PULL SHEETS ARE NOW BEING USED AT SIMULATOR FOR TRAINING. SCHEDULE: DONE B. PLANNED ACTIONS TO PREVEllT RECURRENCE OF THE ROD PULL ERROR 0 REVIEW THE FORMAT AND LAYOUT OF THE ROD PULL SHEETS FOR HUMAN FACTORS CONSIDERATION. MODIFY AS t APPROPRIATE. SCHEDULE: 8-15-85 0 ASSul!E THAT THE ROD PULL SHEETS ARE UllDEi: STOOD BY THOSE USING THEM. PROVIDE A COVER SHEET OR INSTRUCTION WITH PULL SHEETS INCLUDING INITIALS OR SIGNATURE TO DOCUMENT THIS UNDERSTANDING OR PROVIDE ANOTHER SUITABLE MEANS TO ACCOMPLISH THE SAME OBJECTIVE. i f SCHEDULE: 8-15-85 I l
i O OPERATE OR PULL RODS AS TRAINED. DO NOT PULL T00 FAST. SCHEDULE: 00f1E (REF. 7-20-85 met 10 OP-85-210) 0 DO NOT PULL RODS DURif4G SHIFT CHANGE OR UNTIL APPROPRIATE PERSONf1EL ARE READY. (REF. 7-9-85 MEMO fP-85-804, ITEM 2). O ASSURE LICENSED OPERATORS ARE TRAlf1ED AND
~
UfJDERSTAND THE INTEfJT AND PURPOSE OF REDUCED f40TCH l WORTH PULL CONCEPT AND THE lbFLEMEf4TifJG PULL SHEETS. SCHEDULE: D0flE AfJD IN PROGRESS 0 ASSURE LICEl4 SED OPERATORS UNDERSTAND THE Rift AND PROTECTIOfJ AND RESTRAINTS THAT IT PROVIDES AND DOES NOT PROVIDE. SCHEDULE: WITH REQUAL 0 ASSURE THAT ALL LICENSED OPERATORS AND APPROPRIATE SUPPORT PERSONNEL ARE AWARE OF THIS EVENT-AND ITS SIGNIFICANCE. VIDEO TAPE OF THE EVENT SCHEDULE: 00f1E O A MORE EXTEf1SIVE VIDEO TAPING OF THE REENACTf'ENT OF THE EVENT AT THE SlfiULATOR IS PLAllNED. SCHEDULE: 8-8-85 0 CONSIDER MODIFYING Rlil PROGRAM TO INCLUDE SOME
~
1 REDUCED NOTCH WORTH CONTROL RESTRAINTS. SCHEDULE: 8-15-85 I
( _ .
- a s. -
-C. PLANNED ACTIONS TO PREVENT RECURRENCE IN REGARDS T0 t
? FAILURE TO RECOGNIZE THE SIGNIFICANCE OF THE EVENT SO AS TO STOP, EVALUATE AND DOCUMENT BEFORE PROCEEDING.
- O REVIEW SHIFT PERSONNEL RESPONSIBILITIES AND MAKE CHANGES AS REQUIRED TO ASSURE PROPER MANAGEMENT OF ;
l CRITICAL CONTROL ROOM ACTIVITIES. . SCHEDULE: DONE (REF. 7-19-85 MEMO NP-85-804 ITEM 1) O ASSURE THAT THE ROLE OF THE SOA AND STA IS j UNDERSTOOD AND BEING PROPERLY FOLLOWED. ENCOURAGE
- NSS AND NASS TO USE THESE PERSONNEL AS WELL AS 1
OTHER QUALIFIED PERSONNEL ON SHIFT. I ' SCHEDULE: DONE (REF. 7-29-85 MEMO NP-85-804 ITEM 3) 1 0. ASSURE THAT THE SHE TAKES AN ACTIVE ROLE IN ROD PULLS / INSERTIONS AND THE EVALUATIONS OF UNPLANNED I REACTIVITY CHANGES 1 !; SCHEDULE: DONE (REF. 7-20-85 MEMO OP-85-209) u inenove Lud UOOK ENTRIES AND ASSURE EVENTS SUCH AS THIS EVENT ARE LOGGED. SCHEDULE: DONE (REF. 7-19-85 MEMO NP-85-803)
- u ncvitu aniti TURNOVER PROCEDURES TO ASSURE THEY ARE ACCEPTABLE FOR THE CURRENT MODE OF OPERATION.
t SCHEDULE: 8-13-85 4 1 o .
I n .. , I i IX. Roo 1loRTH MINif4fZER I l Discussioti i e s O e 1 J . . _
<...i l l
1 . l l X. TRA l f4 l NG A. SPECIFIC EVEt4T B. Roo WORTH IilNIMlZE!! C. SIMULATon TRAINif1G VS. PLAtlT 1
< i . .. .
X. TRAlflING 1 A. SPECIFIC EVErlT 0 SHORT VIDEO OF EVENT (ALL SHIFTS) O LONG VIDEO, AS DONE vs. AS SHOULD BE O GIVE THIS PRESEllTATIOff TO OTHERS IN flUCLEAR OPERATIONS . B. Roo WORTH filNIM1ZER 0 If4tED l ATE If1F0i: MAT 10ll 0 SHIFT BillEF ING 0 VIDEO TAPE O CURREllT ACTION O NEW LESS0ft PLAft U blMULATOR DEMONSTRATION C. SIMULATOR TRAlfilNG Vs. PLANT 0 SIMULATOR AUDIT - NO FINDir4GS 00f1E JULY 18-20, 1985 O CollTINUE TO AUDIT 10% PER M0!!TH OF ALL OPERATIO!! PROCEDURES AT SIMULATOR 0 REVIEW LESS0t4 PLANS 00f4E JULY 18-20, 1985 -
4 h (14 . e XI. SUf1 MARY O C0f1CLUS10fJS o LESSOf4S LEARflED e I
O d % er:n voc e<s vs - b- I/J4/W " Yer- c.f RJf2m3 e -
% L/
/- SeJ- 4 %.'kn l-q,;ts u.l <;,-44, r,,,s, Osems&a%~.l 4
- 2 -
Q~1 70/2 (s o.,.ys,f , ,qc, L / -
'l 21-(W d 2% g#
gm <4 .L e.cs a s 7a 49s < - G } tysv V 9-I <> l.1 P Il< } Pr r Grp - Ge ~- su- h1 sa x m .L, C6ce 4) nha s -s ~rcLvs. ye h -
'rmy -
Ge -b
.shp ,e /f- c bah,Cl 3. Z c' a L - ,
- 20 9- cai L.- ,
. U < >~ an, .
38 g '.
' ~
ORAD!; PRESENTATION OUTLINE ( . l
*a s .
'3 A,*
- x. % ',.. .. ,.
FERMI 2 PRESENTATION TO NRC REGION III REACTOR OPERATIONS IWROVEMENT PLAN SEPTEMBER 10, 1985 i l
+h
=
OUTLINE I. INTRODUCTION I1- FERMI 2 CURRENT STATUS III. IMPROVEMENT Pl.AN IV. MONITORING V. SlM MRY APO CONCLUSIONS 1 l l j _1_
~
l
- l. INTRODUCTION O DETR01T EDISON C0bNITMENT 0 RECOGNIZED NEED FOR IMPROVEMENT 0 REACTOR OPERATION lbPROVEMENT PLAN I
i l m.u.F:.. m 4 + =.c ^,g+1.:=. m - ,=,.g
,7
_ . o .x . Es - . ZM" ._ . _._ .u .:_
$ ~. '-2.a
'. ^. . .. $. .d. .. 74d. bMI' '". 'I - WUWo.j$ *4t_ _t
_T ~_~
.c
">1 "N t* --s 7 .. _ _ . MsN'_
- u -
^ -
i3 ' t I
! u.
%. Q.
- P:s '
Ii. FERMI 2 CURPfNT STATUS 0 OPERATIONS SINCE JULY 2, 1985 0 TEST PROGRAM 0 SCHEDULE 4 _3_ O , .,. ,e -- a , - -. -
, _ 1 1I. EEENI 2 CURRENT STATUS I 0 OPERATIONS SINCE JULY 2, 1985 l
0 REACTOR RESTARTED AUGUST 10, 1985 AND SEPTEMBER 1985 o CURRENTLY OPERATING AT LESS THAN 5% 1 o LOW POWER TESTING - ALMOST COMPLETED SCRAM TIME Af0 CRD FRICTION RCIC.' HOT CST INJECTION (PARTIAL REPEAT) SELECTED PROCESS TEMPERATURES / WATER LEVEL (PARTIAL REPEAT) LPRM FLUX RESPONSE (PARTIAL REPEAT) 0 TESTING PROGRAM / SCHEDULE o START POWEP, ASCENSION TO TEST C0f0lTl0N I - SEPTEMBER 1985 (MAXIMUM 20% POE R) o BEGIN FALL OUTAGE - OCTOBER 1985 l 0 RESTART REACTOR - NOVEMBER 1985 1
-4 -
l
- ' >G A__
___ _'3 ggtgy _3 __ _ . ~ . e g ,,3__a .- -. y . ._. . , .,ms , u-. i
l
?%'ch
; :,,ka $\-
6
.a l $ W
- h. . " _ __ l III. IW ROVEMENT PLAN 0 INTRODUCTION O PURPOSE 0 OBJECTIVES I
i 0 CORRECTIVE ACTIONS J 1
i . L ,
?).1,.h h - ,
0 !:. x <- 1Ii. IWROVEMENT PLAN 1 0 INTRODUCTION O PLANT PERFORMANCE o CO WIRMATORY ACTION LETTER (CAL) o INST 1TtHE OF NUCLEAR POM R-OPERATIONS (lPO) o MANAGEMENT ANALYSIS CORPORATION (MAC) o SELF INSPECTION o SHORT TERM, PRIOR TO EXCEEDING 5% POWER lWLEMENTED ACTION COWLETED OR PART OF CONTINUING PROGRAM o LONG TERM, AFTER EXCEEDING 5% POER IWLEMENTED BEFORE OR AFTER EXCEEDING 5% POWER WILL NOT BE COMPLETED UNTIL AFTER EXCEEDING 5% POWER 1
. _. . __. .- _ - _ . - _ ~ . _ .
i
\
s ]kh .:r cahi
,. ; I 0 SIPMARY OF CONCERNS / REC 0lSElOATIONS i
iWUT: NRC -1 IPO - 2
- MAC -3 l DECO - 4
- o MANAGEENT SLPPORT i
SHORT LONG
- IWUT ITEM TERM TERM 1 COWLETE CAL ITEMS X 1 INTEGRATE SOAs AND STAS INTO SHIFT- X 1,4 COMPLETE 5% SU TESTING X
! 1-4 TEAM BUILDING X 2 SINGLE INTEGRATED SCHEDULE X 1-4 CLARIFY RESPONSIBILITIES OF ADVISORS X 1,2,4 CLARIFY NSS a NASS RESPONSIBILITIES X 2 REVIEW USE OF STAR LIST 11-1-85 l 1-4 IWROVE CLOSURE OF EDPs 12-1-85 2,4 j IMPROVE RWCU PERFORMANCE X 11-1-85 ! 2 REACTOR ENGINEERING PRE-PLANNING 12-1-85 1 2 REACTOR ENGINEERING RESOURCES j >20% POER 12-1-85 l 1,4 IW ROVE PM PROGRAM 6-1-86 1 LOSS OF MAIhTENANCE EXPERTISE X 11-1-85 ll 1,4 1,3,4 REVIEW IWO REC 0lflEf0ATl0NS X X l l IWROVE WORK ORDER, TAGGING, i EQUIPMENT STATUS X 12-15-85 4 REDUCE NUMBER OF EERs AND EDPs X X , 1-4 SUPERINTEf0ENT-OPERAT10NS OVERSIGHT OF CONTROL ROOM X l I . l
1 o MANAGEMENT SLPPORT (CONTINUED) SHORT LONG IrFUT ITEM TERM TERM 3,4 1!0EPENDENT REVIEWS X 4 PLANT MANAGEMENT PARTICIPATE IN TURNOVERS X 4 PLANT MANAGEMENT REVIEW SHIFT ACTIVITIES X 4 TRAINING ON ROUTINE OPERATION X 4 2,4 STAFF MEETING NEW FORMAT X 4 ONSHIFT TRAININ ON CHANGES X 4 INTEGRATE PM IN SCHEDULE AND PRIORITY SYSTEM X 4' REDUCE LITE ANNUNCIATORS X 4 ESTABLISH SHIFT ENGINEERING TECHNICIAN 12-1-85 l 4 3 . _ . _ . _
- - - . , - , . .- . _ - . - - - _ _ - - - - - - - _ _ _ - _ ~ . . - _ _ . -
=- . - ._ -
? til'
.'. . .L O SHIFT MANAGEMENT SHORT LONG t INPUT ITEM TERM TERM 1-4 IW ROVE EQUIPMENT STATUS SYSTEM X X 1,4 IWROVE SHORT TERM LCO TRACKING X 2,4 INVOLVE NSS IN DAILY PLANNING X 1-4 MANAGEMENT OF CONTROL ROOM X 4 WDRK ORDER CLOSURE X i 1-4 " DOT" SYSTEM X 11-1-85 l 1 IMPROVE "OUT OF SPECIFICATION LOG" X 1 IWROVE NSO AND NSS LOGS X
! 1,2,4 MANDATE BRIEFINGS ON TESTING X
! 2,4 CONSOLIDATE SHIFT TURNOVERS Af0 BRIEFINGS X I 1,2,4 NSS STATUS MEETINGS X
- 2 UTILIZE INTEGRATED SCHEDULE X 4 MARK CONTROL ROOM CHARTS X
! 2 STARTUP SHIFT COORDINATOR X 4 NASS IN CONTROL ROOM X 1-4 ADDIT 10NAL AND CLARIFICATION OF { RESPONSIBILITIES OF ADVISORS X 1,4 NSS PARTICIPATE IN SIGNIFICANT ACTIVITIES X 4 NSS DETERMINES PRIORITY Af0 WDRKLOAD X X 4 IWROVE NIGHT ORDER ENTRIES X 1,4 SOA, STA a GE SHIFT ENGINEER ATTEf0
- TURNOVER MEETING X 1 4 STRESS SEATER USE OF OPERATIONAL
- COMMUNICATION MANUAL 12-1-86
- 4 MAINTAIN ROUTINE SURVEILLANCE BACKLOG LESS THAN 5 X r
_9_
i
,x h t ,
;s :j ' . , n 0 ADMINISTRATIVE IW ROVEMENTS SHORT LONG IWUT ITEM TERM TERM 1 It0EPENDENT VERIFICATION >100 MR/HR X X 1 COMMUNICATION DURING SURVEILLANCE X X 1,2,4 IWROVE TEMPORARY CHANGE TO PROCEDURES X 1-4 INCORPORATE PLANT CHANGES INTO TRAINING 12-1-85 1 IMPROVE METHOD OF REVISING MAINTENANCE PROCEDURES 12-1-85 1,4 lMPROVE MAINTENANCE WRK PACKAGE PREPARAT10N X 10-1-86 I
l 5
[. l t i II. IMPROVEMENT PLAN (CONT lNUED) O PURPOSE o PURPOSE IS TO DEVELOP SHORT TERM AND LONG TERM ACT10N/IWLEMEMAT10N PLAN TO IMPROVE PLANT OPERATION -t 0 OBJECTIVES o PROVIDE GREATER MANAGEMEM SUPPORT OF OPERATIONS
< o IMPROVE SHIFT MANAGEMENT o PROVIDE IMPROVED ADMINISTRATIVE SYSTEMS
...,::%) e n- -
.J 2 ,, ..b l
l1I. IMPROVEMENT PLAN (CONT lNUED) O CORRECTIVE ACT10N - SHORT TERM iWROVEMENTS o MANAGEMENT SLPPORT COWIRMATORY ACT10N LETTER CAL-R IIl-85-10 ITEM 1. PRESENTATION TO REGION III STAFF ON EVALUATION OF THE JULY 1 AND 2 CRITICALITY EVENT, INCLUDING CORRECTIVE ACTION - COW LETED ITEM 2. TRAINING OF LICENSED OPERATORS ON 1 APPLICABLE R00 MANIPULATION PROCEDURES 1 - COMPLETED j ITEM 3. PRESENTAT10N OF EVENT EVALUAT10N RESULTS TO LICENSED OPERATIONS j i PERSONNEL - COWLETED ITEM 4. R00 M RTH MINIMlZER PROGRAM MODIFICATIONS - COWLETED i ITEM 5. SIMULATOR PROGRAM VS. PLANT PROCEDURE REVIEW Am VERIFICATION - COMPLETED ITEM 6. APPROVAL TO EXCEED 5% POE R LEVEL - SUBJECT OF THIS MEETING OPERATIONS SUPERINTENDENT OVERSIGHT OF CONTROL ROOM OPERATIONS
O CORRECTIVE ACTION - SHORT TERM IWROVEMENTS (CONTINUED) ADVISOR TO THE ASSISTANT MANANGER - NUCLEAR PRODUCTION AfD REGULATION APO COWLIANCE STAFF SURVEILLANCE OF CONTROL ROOM OPERATIONS 4 If0EPENDENT REVIEWS IPPO OBSERVATIONS MAC ASSESSMENT KT (PROBLEM SOLVING) TASK FORCE ASSISTANT MANAGER - NUCLEAR PRODUCTION AND/0R SLPERINTEf0ENT - OPERATIONS REVIEW RESPONSIBILITIES IN ONE-ON-0NE SESSIONS WITH NSS, NASS, SOA INCUMBENTS. REVIEW WILL COVER: COMf4JNICAT10NS AT ALL LEVELS C0f0VCT OF BRIEFINGS RELAT10NSHIPS BETEEN POSITIONS ADHEREfCE TO PROCEDURES ATTENTION TO DETAll INVESTIGATION OF ANOMALIES CONSEQUENCES OF ERRORS PLANT SAFETY CONCERNS ACCOUNTABILITIES OF THE POSITION (COULD EXTEf0 BEY 0f0 5% POER LIMIT) SUPERINTENDENT - OPERATIONS PERIODICALLY PARTICIPATE IN SHIFT TURNOVER PROCESS AND PROVIDE CRITIQUES TO NSS
O CORRECTIVE ACTION - SHORT TERM lhPROVEMENT (COMINUED) OPERATIONS ENGINEER FOLLOW AND REVIEW PERFORMANCE 0F SHIFT ACTIVITIES AGAINST ESTABLISHED PLAN STAFF STATUS MEETING - NEW FORMAT TECHNICAL ENGINEER STAFF MORE CLOSELY SCREEN AND EVALUATE ENGINEERING EVALUATION REQUEST (EERs) Af0 ENGINEERING DESIGN PACKAGES (EDPs), OBJECTIVE, REDUCE CHANGES ' INTEGRATE PREVENTIVE MAINTENANCE (PM) WORK INTO DAILY / WEEKLY WRK PLAN AND INCREASE PRIORITY ON PM WORK PACKAGES 4 l i _ - . , . , - - - . . - , . , . . , , - - - - ,w - - - - ----
O CORRECilVE ACTION - SHORT TERM iWHOVEMENTS (CONTINUED) o SHIFT MANAEMENT i WILL C0f0VCT BRIEFINGS FOLLOWING TURNOVER AND REVIEW LPCOMING SHIFT ACTIVITIES 1 - WILL PARTICIPATE IN SIGNIFICANT REACTOR OR PLANT EVOLUTIONS WILL PARTICIPATE IN PLANNING MEETINGS WHEN ON DAY SHIFT LOG BOOK UPGRADE PROGRAM l NUCLEAR ASSISTANT SHIFT SUPERVISOR ASSIGffiENT TO j THE CONTROL ROOM i 1 WILL MANDATE BRIEFINGS ON TEST ACTIVITIES i WILL PROVIDE FULL TIME DIRECTION OF CONTROL ROOM ACTIVITIES IWROVE EQUIPMENT STATUSING
" DOT" SYSTEM IWROVEMENTS
- (PARTIAL UPGRADE BEFORE EXCEEDING 5%)
TRACKING LIMITING C0f0lTl0NS OF OPERATIONS OTHER EQUIPMENT STATUS FEATURES , OUT OF SPECIFICATION LOG ) PLANNING / STATUS MEETINGS l NEW PLANNING / STATUS MEETINGS WITH NSS AT 1330 HOURS, 1800 HOURS, 0001 HOURS AND 0600 HOURS i CONTROL PLANT WORK - NSS DETERMINES PRIORITY AND WRK LOAD (IN PROCRESS)
~
O CORRECTIVE ACT10N - SHORT TERM iWROVEMENTS (CONTINUED) o ADVISORS SHIFT OPERATIONS ADVISOR
- MORE INVOLVED IN DETAIL OPERATION SHIFT TECHNICAL ADVISOR WILL PROVIDE FOCUS ON IDENTIFYING Ato RESOLVING CONTROL ROOM, PARTICULARY ANNUNCIATORS, 1N ADDIT 10N TO NORMAL DUTIES REACTOR ENGINEER WILL INCREASE PARTICIPATION IN REACTOR OPERATIONS APO WILL CLOSELY FOLLOW, ANALYZE ABO REVIEW SIGNIFICANT REACTOR EVOLUTIONS i
l . l .
h g/,Qg,YY,> 7 32 O CORRECTIVE ACT10N - SHORT TERM iWROVEMENTS (CONTINUED) o TRAINING 1 TRAINING DEPARTMENT WILL PREPARE AND C0f0UCT ADDITIONAL TRAINING EMPHASIZING NORMAL AND ROUTINE OPERATIONS SPECIFIC ADMINISTRATIVE PROCEDURES PLAKf REVISIONS IMO TRAINING - C0f0VCT ON-SHIFT TRAINING ON KEY /SIGNIFICANT PLANT OR PROCEDURAL CHANGES (IN PROGRESS) j e
, _ - ,. . . , , . ,,_ _ , . , n, _,- _ - - - - - - - _ _ - - + - - - - . . - - , -
!;*%' &; \
, e .
.9 i O CORRECTIVE ACT10N - SHORT TERM iWROVEMENTS (CONTINUED) o ADMINISTRATIVE IMPROVEMENTS IEEPEEENT VERIFICATION IN AREAS >100 MR/HR COMMJNICATION DURING SURVEILLANCE TEST (WILL EXTEW BEYOPO 5% LIMIT)
WORK ORDER, TAGGING AND EQUIPMENT STATUS CONTINUE TO WORK ON SIWLIFYING SYSTEM (IN PROGRESS) REDUCE OPEN MRK ORDER BACKLOG (IN PROGRESS) 4 REDUCE NUMBER OF LCOs (IN PROGRESS) REDUCE NLNBER OF LITE ANNUNCIATORS (lN PROGRESS) )
. . s.
1Ii. IMPROVEMENT PLAN (CONTINUED) n 4!.. . .k . . . . _. . .. O CORRECTIVE ACT10N - LONG TERM IMPROVEMENTS o PREVENTIVE MAINTENANCE PROGRAM INITIATE BACKLOGGING Af0 TRACKING OF PRIORITY 1 Af0 2 ORDERS NOT C0WLETED STATUS: COMPLETE 12-31-85 MONITOR: PERCENT COWLETION INITIATE CONSOLIDATION / IMPROVEMENT PROGRAM TASK GROUPING DELETION ABO COMBINING OF PM TASKS CONVERT TO NEW HARDWARE Ato SOFTWARE STATUS: COWLETE BY 6-1-86 MONITOR: PERCENT C0W LETION O PLANT REVISIONS INTO TRAINING ACCELERATE ENGINEERING DESIGN PACKAGE CLOSURE PROCESS STATUS: COWLETE 12-1-85 AUDIT OF TRAINING VERSUS PLANT OPERATING PROCEDURE STATUS: COMPLETED o MAINTENANCE PROCEDURES NEED CHANGES MODIFY ADMINISTRATIVE PROCEDURE (12.000.07) AND CONTROLS TO PERMIT ON THE JOB PROCEDURAL CHANGES 1 ON INITIAL AND SEC0f0 USE OF PROCEDURE STATUS: COMPLETE 12-1-85 MONITOR: REVIS10N TO ADMINISTRATIVE PROCEDURE 12.000.07 l l l
~
0 CORRECTIVE ACT10N - LONG TERM iWROVEMENTS (CONTINUED) o MAINTAINING OF MAINTENANCE EXPERTISE MUST REDUCE NLNBER OF PERSONNEL ON SITE STATUS: IN PROGRESS ATTEWTING TO HIRE SOME KEY CONTRACT PERSONNEL STATUS: IN PROGRESS, COW LETE 11-1-85 MONITOR: FILL EDIS0N C0WLEMENT SLOTS RETAIN KEY CONTRACT PERSONNEL UNTIL IN-HOUSE EXPERTISE ACQUIRED STATUS: CURRENTLY RETAIN KEY PERSONNEL, Ut0ER CONSTANT REVIEW o REVIEW IWO Fit 0lNGS APO BEGIN IWLEMENTATION SEE ATTACHED MATRIX (ATTAC WENT 1) h o WORK ORDER PACKAGE PREPARATION, TAGGING ABO EQUIPMENT STATUS SYSTEM USE OF "E" ORDER PROCESS CONTINUE TO ADJUST CURRENT SYSTEM TO IMPROVE EFFECTIVENESS (IN PROGRESS 1-86) STATUS: IN PROGRESS TO 3-1-86) MONITOR: FEEDBACK FROM NSS ON DELAYS, STAFFING STATUS MEETING INVESTIGATE OTHER METHODS Ato APPROACHES BECKl'EL SAN ONOFRE l STATUS: 9-15-85 TO 12-31-85 MAKE DECisl0N ON 3-1-86 AS TO BENEFITS OF ADAPTING COWLETELY NEW APPROACH
* - - - - - - , , - . , . - -. - , - - - .n-- . . - - ,., , . . -.,, - - ,,. - --. - e.--
) -:
IV. MONITORING 0 NUCLEAR PRODUCT 10N MONTHLY PROGRESS REPORT o EXAWLES OF ITEMS MONITORED o REVIEWED BY NUCLEAR OPERATIONS STAFF (VICE PRESIDENT Af0 MANAGER) 0 ADDITIONAL METHODS o CONTROL ROOM ACTIVITIES SUPERINTENDEU - OPERATIONS ADVISOR TO ASSISTANT MANAGER-NUCLEAR PRODUCTION o NSS SUPPORT FEEDBACK FROM NSS (SPEAK TO THEM DAILY) FEEDBACK FROM SUPERINTEl0ENT - OPERATIONS AND OPERATIONS ENGINEER o OPERATIONAL ASSURANCE MONTHLY REPORT PROCEDURE COMPLI ANCE MODULE SURVEILLANCE LER TREfolNG QUALITY SURVEILLANCE Flf0 LNG STATUS o TRACKING /TREtolNG LERs o QA TREF 0 ANALYSIS REPORT FINDINGS DERs BY CAUSE PROCEDURE COMPLIANCE
. ._ i
4j f._ b, .
?
V.
SUMMARY
Af0 CONCLUSIONS " O CURRENT STATUS SUlHARY o LOW POWER TESTING - COWLETED o COWIRMATORY ACTION LETTER - AGREED UPON ACTIONS COMPLETED o ADDIT 10NAL CORRECTIVE ACTIONS - IWLEMENTED o REACTOR OPERATIONS IMPROVEMENT PLAN - UNDERGOING lWLEMENTAT10N O CONCLUSIONS l 0 DECO MANAGEMENT C0FIDENT THAT ACTIONS TAKEN WILL PROVIDE THE CONTROLS NECESSARY TO ENSURE THAT OPERATIONS ARE PERFORMED WITH MINIMUM RISK o DECO MANAGEMENT WILL CLOSELY MONITOR Af0 EVALUATE PERFORMANCE ON'A CONTINUING BASIS o REGION lli APPROVAL TO EXCEED THE 5% POER LIMIT IS REQUESTED ! s 1
'A .
Iff0 RECOMMENDATIONS
SUMMARY
SHORT TERM LONG TERM TOTAL NUMBER TOTAL SCHEDULED CATEGORY NUMBER IMPLEMENTED NUMBER COMPLETION l GENERAL 5 5 0 0 i OPERATIONS 9 9* 1 12-1-85 i COMMUNICAT10N, PLANNING AND SCHEDULING 7 7 0 0 TECHNICAL 12-1-85 SUPPORT 3 3 3 11-1-85 11-1-85
*NSS, NASS, SOA INTERVIEW IN PROGRESS 4
4 ATTACHMENT 1.'
yen-o , ,-
- m. .
- .y
, ~ e., -
- ao aF 1 ~, ox ~, y .
uN- % C_c hs QEc C.so,oLt s 'e ,a b s , s -
- g m ),. . - ,-- 44 -4 LL<-
/ j, < r LH sk ~[ wyz -
CLees - so& % fa-> sk )w at)/ '7s ~ i-sb> -/ 24 > 7p /
%pw /}L.s 6 L cL .r -
J ,
- 1. .
'f//c/t.>
M a.m e ciyani?a kn TYd/e.
]aees C y e p p le,- ._ _ CCL _
12ey<*o,u$ Mlrrn'n, ._ (2. Sw] 4 0<.'.S . NRC . . . _ O y h Iy Seyin d 11A >n k .. G. blore It'a S . . . M R C. ._ _ __ _ _ t7m{cc. . pay,vi.cn)f~ela th,al1
.E. Seeen m an. .. .. _. .. .. . __ N R e
. . _ JeruI y Pa ul .~. PP. . . . -. . . . . - . .
G C .GJn'g kh .. O IM . _. $r:je'flLfet!M_40?_02?.
. L 13y<c<t N12c Ten <> farA'lJWA fernaE S S. DsA12 i - DE~e o ... JSirT//Jdmn' =5 ?uD_.
- i
$ .N *W 5 . . _ . - . . . . .
V.P. Nocih'z- @eMW . Z . f. .d > o e M u ..-. Alk/ABR -. Sediou lb, />'denxe $nL bt',ft)9 Nfo ~D, MC k .- .../l/SCf)O/EfC.. SeYmi-t.iPc),r7/y. r
.T%M 2M04h% .- . pets'.ctr.Edistw bi@. ,._CKGuutTD/21. o4Tdtk S . . . .i. . C . Less e c /%.,e,naJ andp s C.. .. AA,La, 4 Au'//1,- 1 L . Rcdae.d.i L P Gt2iFtsNG C . $7tzoaiTRMciti -. Assi. A14w.%sx.12squ$$$0W
( .. A.4 , N a.i o s t ~D e ith . r b- o.s.- J _.lder 0s.v y- .. . . . . .. B.W. STAPLETON NRc, . ._. . ENFoRCG. MENT SPEclAUST JA0 Sp2pSMA utt:Rs.u. Ar-swrts _ ._. 9%ut K-m<ts or+cEn .. 6b.d 44.6-p.,,f/Lc A% ,2.,t~/x AA . . . O m I g c_,u
- a. ,
n ,' *
** - .j/ , j,1 b(*"
,. ,, l MWV 6k%WrhMelnw ~hc %khet0S
W. C1 R .;
'[ C 4 ( L' l
a v/She S s n ' O:dth / A:Ju. s ahu f(d k oLAdD
/
Liem M&Lo% 1 H R.c G Mf ,%en4 Gar % h g 6 \ h' A~ f$.b-ef. p4p' ew,... dn40%4a/ _ t' W / y a & . .
T )? ,ff,d .
//E C-- ..
Di oA'o- . .- U L U 9 3 b. w s N A C- .. 0)ti.h- 13 RS S R B l.anc sm an _ p oe c. . . fryeJ- f % er_ (. H (.i.c.:. DAc .. . . ... . . . Co w a.?.'*
- 5. .~9 .
- a. . : - .. . -. .
1 TG l<~ .
^^* c- _. . . .
%-'-I" L,a.
. . . L, Osm mee.k . . . . -^! *2 c- - .. . -.
.o reim-- z. s c. . . - . . . . - . ._ .. . - . .. . - :- ..* ...=.. . . - 6 .
g g g g gg g,p g p g
. . 6. g 4 g y .
. . .m, g,
.h-..e. . . ,
. 6.
e .
., . u a --
e I S .
* ,'; - f r h w # ,.o Ww h& P*
,,DADm O s W
' l l
% PQ Pa atA FA w ,. w/ W m J y &-
Jc. ' - g 94 w. f +n a- w y %~ . N dM f -o M& e &
~
N.
-Am f' S& f g m a2* F&. W V
\
(P' f - WLctan G 4: J. r
+
h (1 3 t
~'
]Ir. 5t %ep n r3 w -
i A. ~ S h v,<fys- !
"b M 'f IJfLC (p k M*T-p V &W f>='- -
k*p yd S. Oze h .fmeAa(.Ae= , u .x,er 14I.c. (SYJ - W && _ c. Car mq /s,npy /fts
% Nu- r goAy .
/ dh hde "
R.E $ksea.xM
..G.K e /b, S ~&,y .. . L<s 5"lo
,' n w '" 9 x -
W-gs 0 A-V 4..&
/B4k 4'M
^'
Mf%=A 4 a~ OZ A cieh W. E. % L u -
^
w w new A o s --_ ,; n x l F
@ MMe~c-M h Mb H12 c . G.d. A he. oJLa-- a 64-
& f o y L n & .:shctct.g n 9 -$ - . m . .
F. N - w c As c.g w e a 5 y a s m e m E p2a* . h M Pm ODW at 37oo 3. daC N c.uyaW p
~
! - -w k
- .- a 4 4 y y p + e &.=a =n u ,=_ m -m
.:- ah w. ngn=-
W~ <w~p
=
u ___
._ p deel ; cc.., r. in- /e s,' wc el<. /
/kemi Jiems : J. fea Jegs beMd scieba.le m c<dag e R. 3L- Panel usovk coothOrat.'y _
- 3. Lacwkawg ort Ru)Cd. iss/sker: p d Iern.5 1/. Q e cnspeelsr prelletrL ns/ Gidag heeuee ces us<ka >y a c. add c.,che Gr & f <oedw 6 feetre pany R e>n 029 Syslen a Procedove s. 'f.ch Cet- eIandiness Mpeltm. dy QG pcce k e lon>7 sysden t. ~
Qc. urpek repeb c([ Hedcq OA recetoeb A cal.l 4.n exnsnaaS
, huksis ssQ 4/
tayes/c0 9t 4 ac oripede haD no{ efecn/n:en, ueensee tus delemad Ha/ ae a, e&c hrdd AMb md oryeab$4 tle cess zDio;9aA c~ase,y,yar >&s y a; m wemiee phas m ce<ss m /hy safx 4 ie - in Sp2k.
.5 Po(enkd eroflem Am(c> q us & ses seisxn eoe(aaIta1 of
. mad;h calems.
9
e AGEf0A , W-fp EQUIPMENT '. HISTORY PROBLEMS OTHER CAUSES CORRECTIVE ACTION SCHEDULE 1 8I7
9' s e EQUIPMENT l FOUR EMERGENCY DIESEL GENERATORS (EDG'S) TWO EMERGENCY DIESEL GENERATORS PER DIVISION DIVisl0N 1 - EDG 11 a 12 DIVISION 2 - EDG 13 a 14 4 BACKUP ON-SITE A.C. POWER SOURCE REDUNDANT POWER SOURCES FAIRBANKS MORSE DIESEL ENGINES NAVY 400 NUCLEAR PLANTS 49 OTHER ^ SURVEILLANCE TEST PROGRAM t
'm l
i 1 -
r .2 - r .%
,i 6 }I, ,i, S.& -WR OuCT 4 -
.- i" l T*' (t** I'< t L _. 3;.*- .:
e :. ~ ,. \ - AIR TO ' -- .?%r,'ef,-;,i
*NbEIi .+'i' U2 I
U'x CSE
.'\
~
~
- e ,.,
4:- ' W .. \ I %m--$ -.
/.
?E',i$1$
s,****=,**** P/ Q .',
. .I, Y
f, 1/
>:..,..ll ??h
' ,ii L
,[
l
'a r __[
a ,/h e I
'jT [ !
U
.J.t _ , 1( 1
;/
J l q .-
; N . AS FR3 .l i- a:
hzq f .h 33 m, - e, - Ty - - Q
~
C l ~ ,' ,
!' qv- :
es=2: Kr. :( '
,.s. G- ,
~
7 - . -yA+ ,;)
' * ^^~
.I
~'
U -<
... u -- ;
,t ic.st s y, ti 4.st.D.- -
S ' K.' C5 ,3 o r* -,.4,p ,,g / q'g .., Q -- r , 3
- e
\ --L u j . . . .'}.. - - _;
' ~ -{ _. .
L _--, ,1 \
- ' g' ji ,i h ~ b'\
^
l' - lp /i\l \
-Y '
~
i (" ' = * - ;
).)\$'
s I l ( l TURS".,$'JPERCHARGED l 8410 QR ENONE 12 CYL. CROSS SECTION
C* ( HISTORY ' 13 il, 3 N g 7 BUILT 1974 - 1977 INSIDE STORAGE 27p ou oA PERMANENT LOCATlON ONE ENGINE SOLD AND REPLACED (EDG 14)' 3" OIL SYSTEM MODIFICATION l i
- l a
l o O 4 L
= L
- - m
- 4. C C E 4 I L 4 33 g
~a C C M
O < DCOCxC - c L 2u Ou a h b t ". N b E c 4 W ee H
- 1.:
- c L U
=
L 4
# J W C E cc % e ,
C 4
< C:
cp W - W I - _
- .% c T,.$ C ei CO ,
C
= ?' > \ .c C E C.
D g =
"C - E ) -p
$: e N 5EC E' c.
J ; e C 2 o C C E a d m ~ o
' W
- c. .c.
3 --* < -, f l I E l M s 1 i
- c. sm !
~ E 2:
rp 3@- r EC A D-
i F- 4 ) TERMS FAILED BEARING (.002 IN. GAP CHECK) SURFACE SCORING HEALED SURFACE SCORING e
, a EDG 11 O
l M I++******l Jan 85 l********l Dec 3,85 1********l Dec 27.851**++ I I I I I I I Bearinos
! X 2' X 3 X o o 4 X 5 X o ,s 6 X o X ,
7 8 o 9 o 10 11 12 13 o o (Lower & o 14 Upper >
?++++****l l**++++++l l*****+++: 1++**
I i i l I l Pun Hours 346 125 20 Sterts Fast (PLM;- 127 25 0 Fast (NPL) 175 1 0 Slow 0 8 10 Total 302 34 10 Hours / Start 1.1 3.o 2.0 Notes -Replaced the -Replaced all -Realigned Ca.ps Upper Crank Upper Bearings -Replaced Failed
-Replaced all & Distressed Upper Bee. rings Bearings
-Flush Engine NOTE: THE ASSOCIATED CONNECTING RODS FAILED IN JAN 85.
PLM= Manual Prelube, NPL=Not Manually Prelubed X c w #%
l
)
i EDG 12 h I*+******I Jan 85 1***++**+t Dec 85 1*****++*I I I I I I I Beerincs 1 X 2 X 3 4 5 6 X 7 X 8 9 10 11 12 13 o slower) 14 i+,++++++l l++++*+++) 1++++++++l I I i i i i Run Hours 292 137 240 starts Fast (FLM) 52 23 0 Fast (NPL) 152 1 0 Slow 0 7 8 Total 204 31 8 , Hou r s/S t a r t 1.4 3.6 30 Notes -Rep 1 aced -Replaced upper crank 13M lower " bearing
-Inspected 14M, 12M, 10M and SM on 1ower erank
-Gap checked all other bearings l
PLM= Manual Prelube, NPL=Not Manually Prelubed l
EDG 13 g l******+*l Jan 85 l********l Nov 85 l********l Dec 85 l*+** I I I I i l ! Bearino 2 N, f' # 3 X iSi o (Groove) 4 o (Lcwer) 5 6 7 o (Groove > 8 0 10 11 12 13 o o 14 l********l l***++***l l********l !++++ l I I I I i ! Hours 214 94 234 S ? s r- t s Fast (PLM/ 25 24 3 Fast (NPL) 134 0 0 Slow 0 6 46 Total 159 30 49 Hours / Start 1.3 3.1 4.8 Notes -Inspected Upper -Replaced the -Replaced 3M. Crank Bearings Upper Crank 7M & 13M 1 -6 -Replaced all -Flushed Engine Upper Bearings -Demonstration
-All Other -Replaced 4M Bearings were Lower Bearing gap checked 1
l t> il' )f b . q p .. u f - l l l l PLM= Manual Prelube, NPL=Not Manually Prelubed
.~
o C EDG 14 Date l********l Jan 85 l****+***l Dec 85 l********l Jan 8e l**** 1 I I I I I i Bearinos 1 o 2 3 4 5 6 7 8 9 o 10 11 12 13 o 14 l******+*l l+++*****l I********l i++** I ! I I I I I i Run Hours 270 117 250 1 Starts Fast (PLM) 30 20 0 Fast <f 4PL) 142 2 0 Sl ow 0 7 8 Total 172 29 8 Hours / Start 1.6 4.0 31.3 Notes -Inspected -Inspected -Three Bearings 1-6 all upper and bearings l ower bear i ngs reused
-Observed some bearings had -Replaced all a dull matte upper crank-partial finish line bearings FLM= Manual Prelube, NPL=Not Manual l y Prelubed r
-, E. _
~ ~
b 't I TYP1 CAL CAUSES OF BEARING FAILURE DIRT OR FOREIGN MATERIAL IN OIL INSUFFICIENT LUBRICATION MISASSEMBLY MISALIGNMENT OVERLOAD CORROSION DESIGN OTHER I l l L - - -
- s. .
NOVEMBER 1985 EDG 13 EVENT: OPERATOR SHUTDOWN EDG 13 DUE TO NOISE CHANGE PROBLEM: BEARINGS 3CR, 3M AND 4M FAILED 13 M HAD BEARING WEAR CAUSE: PRIMARY - BEARING 3CR FAILED DUE TO MISASSEMBLY IN JANUARY 1985, THE BEARING WAS INSPECTED NO DISCOLORATION = N0 HIGH TEMPERATURE ALUMINUM DID NOT EXPERIENCE A HIGH TEMPERATURE FRETTING ON CONNECTING ROD FACES BENT CONNECTING ROD BOLTS BEARING FRAGMENTED SEC0f0ARY - BEARING 3M FAILED DUE TO DECREASED OIL FLOW TO BEARING FACES BEARING 13M BEARING TO JOURNAL CONTACT ACTION: o CHECKED ALL OTHER PREVIOUSLY REWORKED BEARINGS. NO OTHERS WERE FOUND TO BE A CONCERN. o REPLACED UPPER CRANKSHAFT o REPLACED ALL UPPER BEARINGS l
JANUARY 1985 EDG 11 EVENT: EDG 11 SHUTDOWN AUTOMATICALLY ON A LOW LUBE OIL PRESSURE SIGNAL PROBLEM: SEVEN FAILED BEARINGS 4 CAUSE: BEARINGS FAILED DUE TO INADEQUATE LUBRICAT10N DURING FAST STARTS ACTION: PRELUBE ALL PLANNED STARTS TEST EDG'S AT PLANT SPECIFIC LOAD LEVELS IMPROVED OIL SAMPLING PROGRAM INAUGURATED OIL FILTER SAMPLING PROGRAM REVISED PROCEDURES REVISED TECHNICAL SPECIFICATIONS i INCORPORATE SLOW START FEATURE (DELAYED) (ACTION STEPS APPLIED TO ALL EDG'S) EDG 12 EVENT: GAP CHECK INSPECT 10N PROBLEM: FIVE FAILED BEARINGS CAUSE: SAME AS EDG 11
- ACTION: SAME AS EDG 11 y - .- -, - - - - - - - - - - - . - _ _ . . - - - , , - - , , , - -
v r DECEMBER EDG 13 EVENT: VISUAL INSPECTION OF UPPER BEARINGS FOLLOWING SUCCESSFUL COMPLET10N OF DEMONSTRATION PROBLEM: BEARINGS 3M, 7M AND 13M FOUND WITH SURFACE SCORING CAUSE: BEARINGS 3M AND 7M - FOREIGN MATERIAL IN OIL BEARING 13M - BEARING TO JOURNAL CONTACT ACT10N: REPLACED THREE BEARINGS l l I
> s .
NOVEMBER 1985 EDG 14 EVENT: VISUAL INSPECTION OF ALL BEARINGS PROBLEM: NONE CAUSE: N/A ACTION: REPLACED ALL UPPER CRANK BEARINGS TO ELIMINATE A " DULL ROUGH" SURFACE APPEARANCE JANUARY 1986 EDG 14 EVENT: SECOND VISUAL INSPECTION PROBLEM: 3 BEARINGS WITH A TRACE OF SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT ACTION: REINSTALLED BEARINGS t i
u . NOVEMBER-1985 EDG 12 EVENT: VISUAL INSPECTION OF ALL BEARINGS PROBLEM: BEARING 13M L0tfR FOUND WITH SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT 1
- ACTION
- REPLACED BEARING
l
&> t ADG 11 FGS (995 u P PER. CR&MK BOEe MAMOREL AUGMMEDT
. co B .
(Hcurs ,co ; . ,
, oo G . . ,
J2. obtecc , oa s . , ESADiMGS 0c4 . . (APEX) .ce3 . . .
. cot .
, cot -
o ' '
- ; : : . : i ; ; : :
1 2 3 4 SG 7 9 1' to is Iz 13 14
- SsAEIU5S APEX. ct.cAAQMcG etAOIMGS
/ 5 4 4 S 2 3 + 5 C ReacInns 3 4 5 C S X lo'3 4 # # 3 0
- IMcHEs S S 3 C.5 6 +-
( g S & 4 s 7 7 6 5 G
$_ 9 4 S & G le 4 & 4 &
ll _ G & $ 5 I E 3 4f6 7 8910 gi gt 13 (4 Sensst A PostTlou l MEA 5dEE M64T Pot a, 6&Aetuc, ca P 0$$&l0 &
'SA00LE 1
E.M D V l E.v/ l e
- n. <
EDG tl DEC 1985- OPPER DRANK BORE MAN DEEL. ALWN MENT
. cot .
(NCHES .Ooi .
.cos . . . . . . . . .
/2 O b40d( .co J . . . . . .
24ADtWEJ .co+ . . . . . . (APEX.) .cos .
. Co L .
00I . o . I Z 3 4 SG 7 8 9 to it it 15 14 6CAGIMGS APGX CLgA A?Arger ggaptAfgS I 6 'S 3. 6 2 4. X 5 6 2EADtMGS 3 % 4 & S
- x. to ' 3 4 .. S & 4 &
INCHES S '& E & 4 s 6 kG E 0 + 4 6 & N $ G 4 + +
@$g 7 3 6 6 4 6 0 9 s G G G lo & G & &
ll C C C &
\
t z3 4 .r 4 7 8 9 to it te 15 l+ ! BaRetMa PostnoM LLQD5i.; Eewoeceo cn ps FtM4 L READl% S CAP 2 2 c. 005 Carp a .5 o. co 4 1 i l l
. . . _ _ _ . _ _- _ _ _ _ _ n.-
n . ; SOS ll UAN 198G UPPEE CEAMK BoRG MAUDBEL ALidiN M6MT
.oet 1 AJcHES ..7
. oo 6 12 O'cLoc( .co g / _
RfAD/NG3 .ee 4 \ lAPEt) .cos
. oat
.cos O ; . . : : : :
I 2 3 4SG7 8 9 to it it 13 i+ 66ABING S APSX CLEA2A AJCE BEAD /bkiS I S S S C Z S S S S ESA0lAlps 3 S S S S x fo ~ 5 4 5 S .CS S IdcHES S S CS S S wG SS S S S r k7 SS S LS C
%s s S S S k9 S S f f
/c S S S S
// 5 S S S
/ 23 4C& 7 8 9 to // /t 1314 8 eat /A)G post ricA) i a
v . ENGINE BEARINGS FUNCTIONAL REQUIREMENTS k ' l o PROVIDE LOW-FRICTION, LOW-WEAR JUNCTION BETWEEN MAJOR ENGINE COMPONENTS: PISTON - WRIST PIN WRIST PIN - CONNECTING ROD CONNECTING ROD - CRANKSHAFT CRANKSHAFT - ENGINE BLOCK o PROMOTE FORMATION OF LUBRICATING OIL FILM BEThEEN BEARING AND ADJACENT SHAFT OR JOURIML. 1 l 1 I I \ - - . ..-,_ -. - _ - _ . _ _ _ . - - .
o . - ENGINE BEARINGS l SPECIFIC REQUIREMENTS o DESIGNED TO CONTROL STRESSES WITHIN PROVEN CAPABILITIES o MANUFACTURED TO CLOSE DIMENSIONAL TOLERANCES o MATERIALS SELECTED TO PROVIDE: LOW FRICTION WITH JOURNAL ABILITY TO ABSORB AND NEUTRALIZE ABRASIVE PARTICULATES g STRENGTH FOR LONG, RELIABLE LIFE l#* COMPATIBILITY WITH ENGINE OIL o VIABLE MATERIALS: FOR BEARING PHASE TIN, LEAD, CADMlUM, INDIUM FOR MATRIX PHASE COPPER, ALUMINUM 2
ENGINE BEARINGS DESIGN PROCEDURES
- 1) COMPUTE LOADS INPUTS: HORSEPOWER COMBUSTION PRESSURE FIRING ORDER COMPONENT WEIGHTS COUNTERWEIGHTS GEARS AND ACCESSORIES
- 2) SELECT SIZES LENGTH AND DIAMETER GROOVES, OIL HOLES CLEARANCES
- 3) SELECT LUBRICANT VISCOSITY AND VISCOSITY INDEX SUPPLY PRESSURE SUPPLY TEMPERATURE i
i i 3 i i
* .m
e 5000 1b. 4
. TDC 1
i POLAR LOAD DIAGRAM UPPER MAIN #1 900 rpm / 2850 KW l 4
v - ENGINE BEARINGS ANALYTl CAL TECHNIQUES UNIT LOAD
#1 MAIN BEARING 24343 LB.
UNIT LOAD = = 1316 P.S.I. _B" x (2.75" .4375") JOURNAL ORBIT ANALYSIS SOLVES DIFFERENTIAL EQUATIONS OF FLUID FLOW IN BEARING FOR EVERY lo 0F CRANKSHAFT ROTATION. OUTPUT: PEAK OIL FILM PRESSURES MINIMUM OIL FILM THICKNESSES INTERPRETATION: COMPARISON TO GUIDELINES ESTABLISHED BY THE ANALYSIS OF MANY DIFFERENT ENGINES 5 i
D61E pat 15 01U15Ih CLE511[ D61E KNING JoutML hALYS15 R1 900 RPR MilitEt NO.- 255M021 i l NO.1 Mill t . (U5lylt IEWKil311 (0/f( 10ft 5.1250 ftC W15H1 93.200 IIDOCL COL 12 CYCLE OF 12 51t0EC 10.0000 201 W16H1 31.900 gir 3.10 ( W RAllt 9.0000 [N61Ett R R UOGL[I CYLINKIS 5 CA CA tli 23.0000 IAIC J e 21, 16 t90.tLIAR 0.0019 915C05mtIYMS) 3.2934 SHAflO!A 7.9950 [ff[C. LIN 1.1%3 OIL GEAK( 1) 986 E0 (1)%0-K6 OIL FRI55UIC 35.00 Olt IDF 170.00 A MxIME CllIILA PEI55KI Of 10178 PSI Ktuts R1 R ttRE kBLE II 20 K R EES U11H h RGL[ t[LAl!UE 10 INE BCMIN5 Of Ill K6t[t5 h: a h5LE ttLR11UC 101E J00 thal Or 163 KGREES thI LEAD R1 IMIS P01h115 21313 PONS EllM3 A1 k RhBLt of 176.9 KRIES THE n[M OIL Iltn PIC55dC 15 Illi PSI R r.INIMS OllIlln 1HittMISS Of .000169 IKES Otti:ts Al R Ctht blt Dr 276 KRIES u!1H Ah >RE EELAllUI 10 INI ERilNS OT 218 KREES R4 h BEE PCLAllK 10 THE J0$hAL OT 302 KREES TE LGAL R11HIS PDIM115 5255 POUE S E11h5 R1 h MELE Of 230.2 KRIES thIICCINit!C11Y tAllo A11HIS P0lh115 0.%55B 1HI rire DIL filn 1HICthE5515 .033137 IEE5 6
a . . s UPPER MAIN 1 (LOADED) 900 rpm /35 psi /170 F
+ ~~,~~~,
/, ! s 2200
/
. s
. s
/ -
s # i n.
/
/ :
s
. \
/ \
/ :- \
/ \ <
/ \
/ : ' \
/ : \
l : \ l l .,
' : \
- \
l : I I : I
.......I..
315 i ..........................................................{......
\ ;
\
; I
\ ; I
\ :
I
/
4
\ : /
\ : /
\ : /
\ -
/
\ /
;\ :
N / s
/
- /
\ .
/
s -
/
s : ! s s O 's s,
'- ,- ~
, ,,' 90 270 -
135 i 225 5 180 45 7
- c. a , .
[EE PRillIIYISIR EL[tII[ [414 Kpf!E J0aMAL INLYS1511 900 trH Kf[f[M(( NO.- 156195365 m ,00 ,,. [US!Kt IAA:4[if0!I [04[ Sol [ 8.1250 K[U[1641 93.206 fEL [0LT 2 MLE OP 12 Sit 0EC 10.0000 ROIUCI6Hi 30.900 ,
. INP l.II [0f RR!!O f.0000 [EM[R R R 806t[I Calc [ti 1 [4 [4 L61 23.0000 8Ai[ KC II, I6 PSO.[t[Ai 8.0015 VISEDS(NDMS) 3.3571 Sufti0!A 6.7560
[ff((. Liu 1.5625 91L6t:0[(9) 896 6tY (I)M-K6 OIL Pf[S9.8[ 35.00 OIL 109 170.00 A Wis.h CIL f!LM Pi[SS@[ Of 19506 PSI K[iGS Al A [rgr DRE of 20 K6t((S UITH & 4%[ t[LAIM 10 TE E80iw6 F 3 K6 FEES K E AkRE Kla1M TO INE JOUtMAL Of 339 K!8(($ M LDAD AT INIS POINT IS SIil7 POUNOS l Ki!E6 Ai M MLC Cr 358.0 K6 FEES N EAa CIL FILM 98[59J8[ IS $537 PSI ' 5 A MinWP OIL Flin TNI[tNESS Of .000219 IES MELES Ai A [92Er NR[ Or 202 K6fCES VITH an tunt p[LafM TO M KArJN6 Of 96 K68((S l N h Ni[ REL'4M 10 INE 100fu2L Of 133 K6t((S N LEJO 81 ilill PGINT !$ $032 P3A% K1N AT D kk[ Or 62.9 K68[IS ; M ((((mi81[Ily pai!O AT THIS POIpi IS 0.95586 I M EW GIL IILR TFIDu[55 IS .00045 luS 8 l O
m.. ;, i CON ROO (LOADED) 900 r pm/35 psi /170*F 135 90 i 180 45 225 m.' N 270
- 's e' -
/
- - s's 3200
< :- N u i n.
/ \
/ : N i / \
/ : \
/ : \ .
/ :- \
/ \
/ : \
/ : i
/ : . . t I : 1 1 : 1 i : 1 I : I
........y.................................... ...................... ........ ....g.......
l . I 1 : I 1 : I
\ : I
\ : /
\ : , . /
\
\
/
315
\ :- /
\ * /
\ 4 /
\ : /
\ -
/
s :- /
\ /
\ : /
N / ss - s s,'s'
, s' j
i 9 e - -~, - . --- -- ,,- ,, - , ,,--,e.- -, _-- , , ,v. --
I I i Q [41E PMIS 01U1510R , *Q CLEYli[ l [k61st BIP914 JOSA 92Lv515 R1 900 RPn ; g} Kf[t[([ NO.- 166685312 1 ./ < [n0.1 wina , [USTXR 'fRRAir[tn124[it 90tt 5.1250 EC WIPT 93.200 50KL *(Oli 2 (VfLE OP 1 Sit (tt 10.0000 901 KISMT N.900 BP 0.00 CW 8A110 0.0000 [41MEC9 *M M UO6LII CVLluMRS 5 C4 C4 LST 23.0000 DRi[ KC M, 85 PRD.tLCat 0.0013 U15C05NCYMS)3.2931 SaariOIR 7.9950 tif[C. Lik 1.1563 OIL 6tR0[( 1) 156 #U (8)360-K6 OIL Pl[5RSE 35.00 OIL 109 170.00 R M8FIO Olt FILM P9C55Utt F !?tSO PSI KCtf5R1RCtm AMRCOf 260 K6PCIS UITH M MR[ ffLRtIYC 10 TE KRi!4 Of IN K RIES K k R*RE t[Lativt 10 TWI JOUML or 2N K6fCES TE LOA 0 Ri IMIS Polut 15 32545 Pt10mDS K11NG Ri AM >RC Or 168.6 K6 TIES TE ntan CIL Fita PetSRSE 15 7240 PSI R MIhIV OIL FILM THIClutSS Or .000133 IK(5 KCtSS RI A [Em R4LE Or 128 K RCIS UIIW D MRI IItaIInt 1014 gatIM6 Or 233 KRIIS N Rh R4LE EtallyE 10 TE JOLSuRL Or 105 K RttS 14 LORD RI 1415 PCIMI 15 1915 POLotDS K!!4 RT > A4LI Of 213.9 KREES TE [tCCRf!!CIIY tallo Ri IMIS POIMI 15 0.97203 l iME MEAM OIL flLM INICiutS5 IS .000246 IKES I l 10
o ,. . . . UPPER MAIN 4 (LOADED) ' 1 o 900 rpm /35 psi /170 F 1 l
-f.~~~,s~,s
- sN
/
f'- i s 2200 N
/
/ : s 8 i n.
/
N
/ : N
/
s
- . s
/ g .
/ : s
/ : g i : g I : \
l l : \
- 1 i : 1 1
- 1 I
.......)........................................................................l......,
i : i : ;
\ :
I
\ : 1
\ : f
\ : f
\ : f
\ : /
\ :- /
\ /
- /
s . f 135 's % i
* /
s : / 180 : '/
's~%~ .
~~. .m-. -
,s' 90 :
45 i i a 315 225 270 l 11 e
- c. 1, o
ENGINE BEARINGS CONCLUSION FOR FAIRBANKS-MORSE DIESELS AT FERMI II o BEARING STRESSES DUE TO PEAK OIL FILM PRESSURE ARE SAFELY WITHIN CAPABILITY OF ALUMINUM - 6% TIN BEARINGS, P.O.F.P. CAPABILITY = 25000 PSI
, o Oil FILM THICKNESSES ARE GENEROUS IN CONNECTING ROD ys P' ACCEPTABLE IN MAIN BEARINGS ' ,.n d FOR TYPICAL MEDIUM SPEED DIESEL ENGINES l
vos j l I i OTHER CAUSE BEARING SCORING MOST LIKELY OCCURS o WITH A NEWLY LAPPED JOURNAL AND NEW BEARINGS PRIOR TO SHAFT SEASONING o LOW OCCURRENCE PROBABILITY l l 1 i 1 l
- l 9 _
u~ u .
SUMMARY
FAILED BEARINGS , EDG 11 INADEQUATE LUBE ALIGNMENT EDG 12 INADEQUATE LUBE BEARING CONTACT EDG 13 MISASSEMBLY WDRN BEARINGS (VISUAL INSPECTION) . EDG 11 ALIGNMENT EDG 12 BEARING CONTACT EDG 13 FOREIGN MATERIAL BEARING CONTACT EDG 14 TRACE BEARING CONTACT q.9 e es D t}N', g(6 1 r a - _ . . - , , -
u... CORRECTIVE ACTION l o REPLACED FAILED AND SCORED BEARINGS EXCEPT 3 ON EDG 14 (TRACE) l 0 CONTINUE OIL SAMPLING PROGRAM o ELIMINATE OIL FILTER SAMPLING PROGRAM o FLUSH EDG'S 11 AND 13 WHICH EXPERIENCED BEARING FAILURES o CHANGE OIL TO MOBIL (ONE DIVISION)
~
o SEASON BEARINGS FOLLOWING REPLACEMENT o MINIMlZE DISASSEMBLY o CONTINUE REQUIRED SURVEILLANCES o GAP CHECK BEARINGS EVERY 6 MONTHS o PROCEED WITH BATTELLE LABS ANALYSIS OF BEARINGS o RESOLVE EDG 12 01L VISCOSITY PROBLEM -id ' o CONDUCT A RELIABILITY DEMONSTRATION o SibOLATE A FUEL CYCLE o 100 HOURS SEASONING RUN 1 y o 20 SLOW STARTS y 3 p o 10 FAST STARTS o
,[a p' RUN FOR 7 DAYS (168 HOURS) #s M p clurk2 -
u..u SCHEDULE . ALL EDG WORK AND TESTING TO BE COMPLETED BY i FEBRUARY 19, 1986 l i f v l j } N s J l i
- -_ --e.- , _. . -4 .- ..4-..., . .,_ -w,--.., - - , _ _ _ _ _ .-.-,_y,_.-
- - - -w - - - , - - , . - - - -- ,- - --- - . , - - - - - . - , - - ,, u,---,.--
u.* s l COLT'S POSITION
; 1. Long storage time (1975 - 1982) 7 years.
. 2. Galvanic action as shown by Technimet report. i
- 3. Bearings were subjected to large number of fast starts (with quantity not pre-lubed) prior to bearings being conditioned to crankshaft.
- 4. As a result of the failures in Unit #11 in January 1985, all units were subjected to disassembly and replacement of bearings in Unit #12.
2
- 5. Units #13 & 14 - The upper bearings in position 1 thru 6 were removed, visually accepted and re-assembled. All bearings inspected were good.
4 l 6. Unit #13 failed #3 upper conn rod bearing due to improper re-assembly. As noted in brinnelling of cap & rod fits.
- 7. DECO & NRC decided to disassemble all engines to visually inspect bearings.
, a) Problem - Any disassembly of engine bearings places jeopardy on proper re-assembly. i b) DECO /NRC replaced bearings against Colt's recommendation. Example -
#14 unit upper main bearings. No problems until bearings were replaced.
i j c) Opening crankshaft / bearing assembly introduces debris into bearings
- As noted in #4 & 7 main bearings on #13 unit.
]; 8. Colt recommends immediate stop to disassembling components for visual inspection of bearing surfaces. Inspect bearings with feeler gauge check l only. ! 9. Correct problem with lube oil dilution on Unit #12 & 14.
- 10. Run engine per:
l e i a) Extended wear in - 40 hours
' b) Continuous load - 2500/2600 kw - 100 hours c Check bearings w/ feeler gauge ]
- d Run NRC qualification tests ,
; e Re-check bearings with feeler gauge. '
l - - d g \c & ')JA l " .I
..io JANUARY 24, 1986 FERMI 2 DIESEL GENERATORS -
AGENDA Introduction - C. Paperiello (NRC) attendees / introductions purpose agenda process for public interaction { Technical Presentation Diesel Generator Overview - J. Nyquist (DECO) j - Diesel Generator Operational History - J. Nyquist Discussion of Recent Problems - J. Nyquist Program for Resolution - J. Nyquist Discussion of Cause(s) of Failures and Proposed Program for Resolution - NRC Closing Remarks NRC Assessment - C. Paperiello - Process to resolve concerns and allow restart 4 i e I 88
,- e l
SUMMARY
o USE PROVEN DIESELS o EXTENSIVE DIESEL SURVEILLANCE PROGRAM o HAD SOME BEARING PROBLEMS AND SURFACE INDICATIONS o IDENTIFIED CAUSES (MISALIGNMENT, STORAGE, MISASSEMBLY, LACK 0F PRELUBE, PARTICULATES o TAKING APPROPRIATE CORRECTIVE ACTIONS (ALIGNED, CONDITIONING, REASSEMBLED, PRLUBE, FLUSHED) o IMPLEMENTED SLOW START CAPABILITY o BELIEVE DIESELS WILL RELIABLY START AND OPERATE WHEN CALLED UPON o PLAN TO RESTART ABOUT 2/19 AND NEED TO IDENTIFY REGULATORY PROCESS S0 THAT OUR ACTION SUPPORT TIME FRAME
- _ _ .a .
l juMMARY o USE PROVEN DIESELS o EXTENSIVE DIESEL SURVEILLANCE PROGRAM o HAD SOME BEARING PROBLEMS AND SURFACE INDICATIONS o IDENTIFIED CAUSES (MISALIGNMENT, STORAGE, MISASSEMBLY, LACK OF PRELUBE, PARTICULATES o TAKING APPROPRIATE CORRECTIVE ACTIONS (ALIGNED, CONDITIONING, REASSEMBLED, PRLUBE, FLUSHED) o IMPLEMENTED SLOW START CAPABILITY o BELIEVE DIESELS WILL RELIABLY START AND OPERATE WHEN CALLED UPON o PLAN TO RESTART ABOUT 2/19 AND NEED T0 IDENTIFY i REGULATORY PROCESS S0 THAT OUR ACTION SUPPORT TIME FRAME I e 1
. - - - _ , - ,. --r -- -
p-,, - ,rm,.e ,,,._,e .-- y-_.r-.,, - . - , _ . - . , . . . .r . - - .. r - ~ . - - - , _ - - . .#-- - . . _ - -- -
I .% Y [l- Q l LA.11: > AGEf0A 9 ;00'pn EQUIPMENT HISTORY PROBLEMS OTHER CAUSES l CORRECTIVE ACTION
< SCHEDULE J
't 1 a i
- 1 I
h b l
EQUIPMENT l l FOUR EMERGENCY DIESEL GENERATORS (EDG'S) TWO EMERGENCY DIESEL GENERATORS PER DIVISION DIVISION 1 - EDG 11 a 12 DIVISION 2 - EDG 13 a 14 BACKUP ON-SITE A.C. POWER SOURCE REDUt0 ANT POWER SOURCES FAIRBAfKS MORSE DIESEL ENGINES NAVY 400 . NUCLEAR PLANTS 49 OTHER SURVEILLANCE TEST PROGRAM 1
f _? Y: ., LQ 1
.p dt ' ' AQ OucT I-
^
_T k_ . -@5 _ .w I ~ ~~~ i 4 ua.1o I gx--,.;c pT
.L ' ,r- ,
\ -
y_ qyg,q,y.
'. ..r.m.
.Q
-3 p! -VE, -(
\ f' '
YWMi(di g4% y , lEt M ,
! NO
~
-] m/ l-;?'0 ?.25.
1 Th n .' . .wa
% .d '/ N . v - - -
.< =
l >
'f7-T' l[
- a. .
I'" /,' K)1 p
~
r AIR FR2/ 1, , l
/ ], us.: 1 d lI h
[5il
< r-- -
4 gawi ._ n _ _ _ 1_x
, J' ,__ 3 ,
10
/ l l' -
k] - - - - l m e s i;; i 6.I
, u gc K\it :.
ec xMe 7
- x .-
-- J a 2^ m e ~I.'r.'. .y ,...
j an'nrn 2 m+ h !_!./ s, I
-< I,k.. . - Q,u.se ti ,
t +- c - o N.' '54
/
- M P -f vt
$.-[] ._.) i,/
--- k
~
l y
- , ?, l L l ;V R 1 y
}r-
\
t --- -
! e \,
\
*~*
'~
o e
- o. _
5:[- 6{u.*
\ l j .[ L .N
- C.
cI o (~ .
;-7
( ! TURSOSUPERCHARCED l T 8&olO CLR ENCtd ! 12 CYL. CROSS SECTCN W . ,.
_ _ , , . au. - - - . . .-aa - - . _ . a - e HISTORY BUILT 1974 - 1977 INSIDE STORAGE PERMANENT LOCAT10N ONE ENGINE SOLD Ato REPLACED ( DG 14) OIL SYSTEM MODIFICATION \~ u_ mn s s%% & Etf /% uk M uaniae s I l
m ' 1 Ar0Tb Q&uMu 4 ) .* nMk A.d M s/ t r a - l r t r s
?. ;
i i O A m e wk a n
\
r e. b 3 1 0 it asy os on l a oc r i t S a r T T ^ 2 1 1 1 t,n l aa
~ lahc E
r e g x d 4ME M T S Y o 1 S
%L t
r t e. i 9 . l f - I O R wE E 8 D A E , R
~'
H E D
n B L 7 A E t e A'e I
ll f v u U O
E R ai h r Ier L B E SD P l 6 T iL S O G N O I B A D M 5 L I
0 E R /
E R P I P [
U i s
A R
3 .T c
rp P
M t m p t cu S eP R
I P
D& $h f4Mh FAILED BEARING (.002 IN. GAP CHECK) c SURFACE SCORING
/ 's HEALED SURFACE SCORING M'O h O^ I # c u e Jg A %
k W 2o ocJ~p#s' y: f Tm >~ w 6 u f U"f in p f]h4 CO $ - M W h. I l .
.' .' gR f E
J N rb
- c. ,; ft '**
W l********l I I Jan 85 l********l Dec 3,85 l********l Dec 27,851**** I I I I I Bearinos 1 X 2 X 3 X o o 4 X , 5 X o X 6 X o X 7 f,%g i 0 #
- l. ,
2o r J-- J 12 g 13 14 o[ .. r o (Lower & Upper) o l********1 l********l (********l 1**** 1 1 1 1 1 1 1 Run Hours 346 125 20 Starts Fast (PLM) 127 25 0 Fast (NPL) 175 1 0
, Slow 0 8 10 1
Total 302 34 10 Hours / Start 1.1 3.6 2.0 Notes -Replaced the -Replaced all -Realigned Caps Upper Crank Upper Bearings -Replaced Failed
-Replaced all & Distressed Upper Bearings Bearings
-Flush Engine NOTE: THE ASSOCIATED CONNECTING RODS FAILED IN JAN 85.
.1 PLM= Man u al Prelube, NPL=Not Manually Prelubed
i EDG 12 p_gt1 l********l Jan 85 l********l Dec 85 l********l i I I I I I B,arinos 1 X 2 X 3 X 4 5 6 X 7 X 8 9 10 11 12 13 o (Lower) 14 l********l l********l l********1 1 I I I I I Run Hours 292 137 240 Starts Fast (PLM) 52 23 0 Fast (NPL) 152 1 0 Slow 0 7 8 Total 204 31 8 Hours / Start 1.4 3.6 30 l Notes -Replaced -Replaced upper crank 13M lower bearing
-Inspected 14M, 12M, 10M and BM on 1ower erank
-Gap checked ,
I all other bearings
! _ __ _ h h A & & NM& RAkA NOl m! !M h Nhh3a & $ LJ NAA $ A A kA M O
EDG 13 gitt l********l Jan 85 l********l Nov 85 l********l Dec 85 l**** I I I I I i I Bearino 1 2 3 X o (Groove) 4 o (Lower) 5 , 6 7 o (Groove) 8 9 10 11 12 13 o o 14 l********l l********l l********l ( l**** I I I I I I I f Hours 214 /\ 94 f< -- 234 Starts Fast (PLM) 25 24 3 Fast (NPL) 134 0 0 Sl ow 0 6 46 Total 159 30 49
)
Hours / Start 1.3 3.1 4.8 N Inspected Upper -Replaced the
-Replaced 3M,
, Notes Crank Bearings Upper Crank 7M & 13M 1 -6 -Replaced all -Flushed Engine Upper Bearings -Demonstration
-All Other -Replaced 4M Bearings were Lower Bearing gap checked PLM=Manu al Prelube, NPL=Not Manually Prelubed l
l
l l EDG 14 ' Jan 85 l********l Dec 85 l********l Jan 86 l**** Qatt l********l I i i l i I I Bearinos 0 1 2 3 4 5 6 7 8 9 o , 10 11 12 13 o 14 l********l 1********1 1********l 1**** 1 1 I I l i I Run Hours 270 117 250 4 Starts Fast (PLM) 30 20 0 2 Fast (NPL) 142 2 0 Slow . 0 7 8
, Total 172 29 8 Hours / Start 1.6 4.0 31.3 Notes -Inspected -Inspected -Three Bearings 1-6 all upper and bearings lower bearings reused
-Observed some bearings had -Replaced all a dull matte upper crank- '
partial finish line bearings PLM= Manual Prelube, NPL=Not Manuall y Prel ubed l
TYPICAL CAUSES OF BEARING FAILURE DIRT OR FOREIGN MATERIAL IN OIL INSUFFICIENT LUBRICATION MiSASSEiELY j MISALIGNMENT OVERLOAD CORROSION DESIGN i OTHER i 1 i 6
. . , , _ _ . - , _ _ _ . . _ - - ,_.,y-- , . w _ _ - - -,_ _ . - - - , . . __ y ,m _._ - . _ - _ ._ . _ -, - -
NOVEMBER 1985 EDG 13
- EVENT
- OPERATOR SHUTDOWN EDG 13 DUE TO NOISE CHANGE 4
PROBLEM: BEARINGS 3CR, 3M Ato 4M FAILED 4 13 M HAD BEARING M AR
, CAUSE: PRIMARY - BEARING 3CR FAILED DUE TO MISASSEMBLY IN JANUARY 1985, THE BEARING WAS INSPECTED NO DISCOLORATION = N0 HIGH TEMPERATURE l ALUMINUM DID NOT EXPERIENCE A HIGH TEMPERATURE FRETTING ON CONNECT 1NG R0D FACES 1
i BENT CONNECTING R00 BOLTS l BEARING FRAGMENTED i SEC0f0ARY - BEARING 3M FAILED DUE TO DECREASED OIL FLOW T0 a BEARING FACES i BEARING 13M BEARING TO JOURNAL CONTACT ACTION: ! o CHECKED ALL OTHER PREVIOUSLY REWORKED BEARINGS. NO OTHERS WERE FOUt0 TO BE A CONCERN. I o REPLACED UPPER CRANKSHAFT i o REPLACED ALL UPPER BEARINGS l l l _ . _ _ _}
~
JANUARY 1985 EDG 11 EVENT: EDG 11 SHUTDOWN AUTOMATICALLY ON A LOW LUBE OIL PRESSURE SIGNAL PROBLEM: SEVEN FAILED BEARINGS CAUSE: BEARINGS FAILED DUE TO INADEQUATE LUBRICATION DURING FAST STARTS ACTION: gg M ndf A' PRELUBE ALL PLANNED STARTS ' M
- h, g -
)
TESTEDG'SATPLANTSPECIFICLOADLEVELS i IMPROVED OIL SAMPLING PROGRAM INAUGURATED OIL FILTER SAMPLING PROGPAM REVISED PROCEDURES REVISED TECHNICAL SPECIFICATIONS INCORPORATE SLOW START FEATURE (DELAYED) (ACTION STEPS APPLIED TO ALL EDG'S) EDG 12 EVENT: GAP CHECK INSPECTION PROBLEM: FIVE FAILED BEARINGS CAUSE: SAME AS EDG 11 ACTION: SAME AS EDG 11
DECEMBER EDG 13 EVENT: VISUAL INSPECTION OF UPPER BEARINGS FOLLOWING SUCCESSFUL COMPLETION OF DEMONSTRAT10N PROBLEM: BEARINGS 3M, 7M Ato 13M FOUt0 WITH SURFACE SCORING CAUSE: BEARINGS 3M AND 7M - FOREIGN MATERIAL IN OIL BEARING 13M - BEARING TO JOURNAL CONTACT ACTION: REPLACED THREE BEARINGS l l l 9
. #..e
- NOVEMBER 1985 EDG 14 EVENT: VISUAL INSPECTION OF ALL BEARINGS PROBLEM: NONE CAUSE: N/A ACTION: REPLACED ALL UPPER CRANK BEARINGS TO ELIMINATE A " DULL ROUGH"
; SURFACE APPEARANCE JANUARY 1986 EDG 14 EVENT: SEC0tO VISUAL INSPECTION PROBLEM: 3 BEARINGS WITH A TRACE OF SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT ACTION: REINSTALLED BEARINGS e
l e
J 8 NOVEMBER 1985 EDG 12 l EVENT: VISUAL INSPECTION OF ALL BEARINGS i PROBLEM: BEARING 13M LOW R FOUND WITH SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT ACTION: REPLACED BEARING f n e D l I ' ~ - - - -
1 DECEMBER 3, 1985 EDG 11 EVENT: VISUAL INSPECTION OF ALL BEARINGS PROBLEM: BEARINGS 3M, SM, 6M, 8M, 9M, 13M(UPPER Ato LOE R) FOUf0 WITH SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT AGGRAVATED BY ALIGM4ENT ACTION: REPLACED ALL UPPER MAIN BEARINGS Ato ONE L0kfR BEARING DECEMBER 27, 1985 EDG 11 EVENT: INSPECTION DURING BEARING RUN-IN PROBLEM: TWO FAILED BEARINGS AND TWO BEARINGS WITH SURFACE SCORING CAUSE: BEARING TO JOURNAL CONTACT AGGRAVATED BY ALIGM4ENT ACTION: DETAILED REALIGNMENT OF UPPER BEARING CAPS
I l l noc it FE8 1995 uPPee. cRAMK SoEr M APD REL. 4Ll4MLAEOT l l
. co 8 .
INcHrs ..o v . .
. .e t.
\.
12 ohoct , ,o s . , t.eAotMss .oad . . ( A&x) .. 3 . . .
. cot .
,ool .
o : I 2 3 4 SG 7 9 1
- Jo In tz is 14
- SiAEtM5 S APEX. ct see4ucs gEA0lAJGS I 5 4 4 S 2 3 4 S C 3 4 5 C S Reactums ,
x go-3 4 : ? s 4 + S S 3 5*S (*
- IMCHE3 S & 4 S y&
7 7 6 5 G If 6 S G G O4 5 4 G G 6 4 6 6 h/o ll G & S 5
/ t 3 4f6 7 8 9 to is at #514 Esasa uci Fostflod gruW$
MEASOBE MENT @ f
. Foto t ' 66A E tN6i cA F i
66ARtug
' SADDLE E.4 D VIE W
EDG tl DEC 198 5 UPPER CRANK BORE MANDEEL. ALMNMENT
. dot .
INCHES .ooT .
.cos . . . . . . . . .
/2 ocec( .co.5 . . . . . .
MDlWGS .co+ . . . . . . (APEX) .cos . 00L .
.o*I .
O . : : : ; . I E 3 4 5G 7 8 9 to it it 15 14 66A2tMG5 APGX cleA AMw ggAD/MGS
/ G X X 6 2 XX 5 6 2EADtMGS 3 '*- 4 0 '
y.to'3 4 & 4 &
.,. _S INCHES S s. W & 4 s 4
't G $ 3t + G G 6 7 N I G 4 + +
B 3 6 6 4 6 0 to & G & G
// C C f &
I Z3 4 .S~ 4 7 8 9 to ll /c 15 14 Bs9EtAka fosinoA3 M1 EEWoSCEO CAPS Fluel REA DfM S CAP
- 2 c. coE CA P st.5 0.004
SOG ll - -- VAN 198G UPP6E CEA9 K BoRs. MARDBEL AtidiN M6MT l , 0o1 l AICHES . .o 7
. oo 6 iE O'cLoc( . oo g - l&
REhp/NG3 .oe 4 (APEt) .cos
. c o 2.
.ool O ; . : : : : : . ; ; ; ; ,
I z34SG7 8 9 to it it. 13 14 BEABINGS AP6X QEn2A aJCG 2EAD(bhii5 i S S S C 2 S S S C CGA0lA]q3 3 S S S S xto-5 4 5 S Cf S IUCHES S S CS S S Mr G KS S S S 7 SS S LC C S S S S 38 Q9 S S S C to S S S S
// 5 5 S S
/ 23 4S& 7 f 9 to // /t 13 /t 8&AL/A)G Po3/r/CA) i -
l
ENGINE BEARINGS FUNCT10NAL REQUIREMENTS o PROVIDE LOW-FRICT10N, LOW-WEAR JUNCT10N BETWEEN MAJOR ENGlNE COMPONENTS: PISTON - WRIST PIN WRIST PIN - CONNECTING R00 CONNECTING R00 - CRANKSHAFT . , CRANKSHAFT - ENGINE BLOCK < \ o ; Cau~d~
%octes- w
~~ o PROMOTE FCRMATION OF LUBRICATING OIL FILM BETifEN BEARING A.T -- - -- ADJACENT SHAFT OR JOURNAL. ae
. 1-
ENGINE BEARINGS SPECIFIC REQUIREMENTS o DESIGNED TO CONTROL STRESSES WITHIN PROVEN CAPABILITIES o MANUFACTURED TO CLOSE DIMENSIONAL TOLERANCES o MATERIALS SELECTED TO PROVIDE: LOW FRICT10N WITH JOURNAL jt-ABILITY TO ABSCRB AND NEUTRALIZE ABRASIVE PARTICULATES N 7
/
r M -- STRENGTH FOR LONG, RELI ABLE LIFE 2dem COMPATIBILITY WITH ENGINE OIL fW A' o VIABLE MATERIALS: FOR BEARING PHASE TIN, LEAD, CADMlUM, INDIUM FOR MATRIX PHASE COPPER, ALUMINUM i 2
ENGINE BEARINGS DESIGN PROCEDURES
- 1) C0W UTE LOADS IWUTS: HORSEPOVER+ 3f63 #C"' 967> /7847 COMBUSTION PRESSURE FIRING ORDER COWONENT WEIGHTS COUNTERWEIGHTS GEARS AND ACCESSORIES
- 2) SELECT SIZES LENGTH AND DIAMETER GROOVES, OIL H0LES CLEARANCES
- 3) SELECT LUBRICANT VISCOSITY Ato VISCOSITY INDEX SUPPLY PRESSURE SUPPLY TEMPERATURE l
3 l i l l - w - l
I - 5000 1b. f . TDC POLAR LOAO DIAGRAM i UPPER MAIN #1 900 r pm / 2850 KW I 4
ENGINE BEARINGS ANALYTICAL TECHNIQUES UNIT LOAD
#1 MAIN BEARING 24343 LB.
UNIT LOAD = - -
= 1316 P.S.I.
8" x (2.75" .4375") JOURNAL ORBIT ANALYSIS SOLVES DIFFERENTIAL EQUATIONS OF FLUID FLOW IN BEARING FOR EVERY lo 0F CRAtKSHAFT ROTAT10N. OUTPUT: PEAK OIL FILM PRESSURES MINIMUM OIL FILM THICKNESSES ' INTERPRETATION: COMPARIS0N TO GUIDELINES ESTABLISHED BY THE ANALYSIS OF MANY DIFFERENT ENGINES l i l 5 l
, - , , - - - -,-,w , ,,, n-,- - -- , , - , ,
(Kit PM15 31V1515 atViiI [ Milt Kuls Joura IMLY515 N 900 IFR Kf(tCKt W.- tumell i l No.1 El 3 , CU5131CI iL$.UKII311 (04E 80t[ I.1250 KC KIM 93.200 MEL (112 CYCLt OF 12 SitKt II.1000 t0! K!M M.900 br I.R CBIPIRill 9.0000 [E!Ett R R WELII
- CYLluGCIS 5 (A CA L51 23.0000 IR1[ Jk 21, M RRC.tttM 8.0019 515C0501tCW5) 3.2931 SMIflIII 7.9954
[ff[t. LII 1.1%1 IIL6290[(1) Its Stu (I)3&K5 BIL PK$$Utt E.10 IIL IDF IM.10 5 MEu Olt flLA PK55UK K 101M PSI Ktuts II I CtM kGLE II 29 KGIEES U11H D kBLE KLR11UE la 1E KMIE F 183 KitCES M k ML[ KLRilUC 10 TE JoutML If 163 KEEE5 IE LGE R1 IMS Polut 15 21343 Poues KilE R1 h RELE Of 176.9 KIKE 5 IE Ek Olt Illn PRI5WIC 15 3331 PSI I ENIU lit flLM TEttE55 K .000169 IKE5 Ktut5 Al R CfM DGLE K 276 Kit [ES UlTK M MLI KLA11UC 101T KMIE K 218 KitEIS E k MLE KLMIUC 101E J0t,fML K ' 302 KEREES If LGG R1 INIS POIN115 5255 Pout 5 KilE II k MLI II 230.2 KGREES 1E [CIENititliY 2811011 INIS P0lN115 I.%558 IE Kh Gil filn 1HitW5515 .00C1D IEE5 6
, o- ..
1 i UPPER MAIN 1 (LOADED) 900 rpm /35 psi /170 F
, s ~, s
' sN e
- -i s 2200
. s
/ ; s s 8 i n.
/ .
N
/ : s
/ :. s
/ g ,
/ : g
/ : s I : s 1 : \
/ : n : 1 1 : g i : 1
- i
.......j.....
315 i ..............................:..........................,,,.....)i..,,,,, i 1 - : ;
\ : ;
\ : ;
\ : ;
\ : f 3
\ : f
\ :. /
s f s : f
\ :. /
s f N : s . j/ s s :. /e; ss : - 0 N s , ,
'~
,- ~
,,' 90 270 :
- 135 225 : 180 45 l
1 7 I l
DEIE PMil 9191515 util1[ [ E!E K NI 4 M R M VSil 11 300 RPM Kr[t[KE E.- 1%I8555
- c. ,-
(1510M[t IMR4ff0li(04[10l[ 8.1258 KC WIM $1.200 M0KL (8Li ! CYCLI IP 12 lif0tt 10.0000 ROI KIM N.3OI
. Ilr I.N (SP19111 0.0000 [WIED R R INlti CYLluKP5 1 (4 C4 L51 23.9000 IRi[ KC R. E ft0. CLIN l.0019 IISC0505CW 3.571 SMRrl313 6.7564 (fIEC. Lip 1.%25 lltSrE(1) IRS WY (I)%Q-K6 l!L PetSR8C 35.N SIL IDIP IM.10 i MiWI5.B OIL fM PfCSRei F 1955 PSI KtWS 51 R Ctfg MLE F 20 KIECIS j Ulip p DRC KLpi!YC 10 iMC KasIn6 F i Kit (($
M M MLIKLAfivC19it M MILF in Kletts it LDAG Al INIS NInt 15 52717 PONS Kil4 81 All DGL[ K 358.0 Kit [IS TE MCan git IIts PetsgsE 15 5537 PSI I MIW IIL f!LP TECTCSS W .900211 IKK5 KCL 8181 A CPM MLt F 202 KistIS UliR * >RE KL4f1K 10 IE KWlp6 F 18 KEEEIS M M MRI KL8tlK 16 iT MVML F in KpCES l'( LC4 pi IRIS POINI 15 W32 P9MS K1196R1D MLIF 62.8 KEEIS f( [tttut:Ittty tails si ig5 POIp1 !$ l.955W TE T4 SIL IILR TKItr($5 IS .000%$ Irgl 8 l l
s t CON ROO (LOADED) 900 r pm/35 psi /170*F 135 90
' 180 45 225 J 1
- ' '~ 270 e'
/ ,. .
,'s's 3200 l
i e :. N # i n.
/ N
/ :- \
/ \
/ : s
/ : \ ..
/ :- \
/ *
\
/ \
i : \ I : - . \ I : \ l : 1 i : 1 i : I
........g.....................................y...................... .............).......
t : 1 1 : I 1 : I
\ : I
\ :- I
\ . I
\
\
i
. /
315
\ :- /
\ /
\ 4 /
\ :- /
\ *
/
\ /
\
ss
- e e/
s .
's~,~ :
. ,s-
~~~~ :. . **
i I l 9 i l l l .
\
[414 PRit$ B19151R " CLCHit (M514 KPrI4 MA PU515 81 900 IPM ILf ttC(C W.- 166685342 (4. i WIN j 1 testMt *fMR.1[WI 2/ Kit IOtt 8.1258 KtWIFT $3.298 It0CL *t9ti2 MLtIP151f31 10.0000 MiWlpi M.900 kP I.10 CM tA!!O I.0000 [El([I 1 M 906LD CVLICEIS 5 t/L C A L6T 21.K10 mit KC08.85 M.Ctter 8.0M9 U1K05ASDW 3.2539 SNK1 l!A 7.9950 [fTIt. Lis 1.1561 91L StROC( i) Its say (1)360-Ki 81L PRI553I 35.90 I!L IDF 170.10 R MEU OIL IILR PK55URC F 17050 PS! KCWS 11 A (f84 MLE K 260 Kit [IS UITH W MLC KLAtlE 10 TE KRiIE K 179 KitCES M M WLI KLatlX10it mea F 271 KifEE5 it LM R1 INIS K!E 15 32595 P0utS K115 81 m MLE F 168.6 K6tII5 TK Em DIL flLM Pt[55tfi15 7No PSI I MIE2 OIL IILM INICM55 K .500131 IKES KCUti Al A ttN MLt F 128 K6EIS Ulik D MLE Elli!E 10 IE Kariq y 233 KiqiIS M Ih MLI Klatlyt is it asWil F 195 Kit [IS it LORD #1165 POIM115 1945 P9tet$ Kils li > MLt F 293.9 KII[IS TE ((CCNitIC11Y 19110 Ri TES Polui 15 9.97291 1 TE Em OIL IILft INICM5515 .00CNE LEES l ) 10
1 1 UPPER MAIN 4 (LOADED) 900 r pm/35 psi /170 F
'p- i.
~~~~
ss s'ss 2200
/ . s
/ -
s # i n.
/
/ i
'ss
/ :- \
/ \ '
/ : s
/ : \
/ : \
I : \ l : \ l :- 1 1 1 I i I
.......j........................................................................j.......
i : I 1 1 : I
\
\ ; I I
\ : /
\ : /
s : /
\ :- /
\ /
- /
\ :- /
s / s - s ' 135 s : /
\ i ,/
180 ! ss, .Q ~ - -
=, '-
..a. .
90 : 45 :
- ; o 315 225
- 270 4
E i l {.. -
ENGINE BEARINGS CONCLUSION FOR FAIRBAN(S-f0RSE DIESELS AT FERMI Il o BEARING STRESSES DUE TO PEAK OIL FILM PRESSURE ARE SAFELY WITHIN CAPABILITY OF ALUMINUM - 6% TIN BEARINGS, P.O.F.P. CAPABILITY = 25000 PSI _Mh*ghhM o OIL FILM THICKNESSES ARE GENEROUS IN CONNECTING R00 ACCEPTABLE IN MAIN BEARINGS l i FOR TYPICAL MEDIUM SPEED DIESEL ENGINES 4 e 12 i
OTHER CAUSE . BEARING SCORING MOST LIKELY OCCURS o WITH A NEWLY LAPPED JOURNAL AND NEW BEARINGS PRIOR TO SHAFT SEASONING o LOW OCCURRENCE PROBABILITY i 4 M
y ,
SUMMARY
FAILED BEARINGS
~
W $ 4 w [6 EDG 11 INADEQUATE ALIGtNENT Gy LUBE M f d & p [M EDG 12 INADEQUATE LUBE BEARING CONTACT EDG 13 MISASSEMBLY WORN BEARINGS (VISUAL INSPECTION) EDG 11 ALIGtNENT EDG 12 BEARING CONTACT EDG 13 FOREIGN MATERIAL BEARING CONTACT EDG 14 TRACE BEARING CONTACT
CORRECTIVE ACTION l i O REPLACED FAILED AND SCORED BEARINGS EXCEPT 3 ON EDG 14 (TRACE) o CONTINUE OIL SAMPLING PROGRAM o ELIMlMTE OIL FILTER SAMPLING PROGRAM o FLUSH EDG'S 11 AND 13 WHICH EXPERIENCED BEARING FAILURES o CHANGE OIL TO MOBIL [NE DIVISION){ Ns) , o SEASON BEARINGS FOLLOWING REPLACEMENTamartvvs4eiC4/ lW 7 /M o MINIMlZE DISASSEMBLY j " o CONTINUE REQUIRED SURVEILLANCES o GAP CHECK BEARINGS EVERY 6 MONTHS o PROCEED WITH BATTELLE LABS ANALYSIS OF BEARINGS o RESOLVE EDG 12 OIL VISCOSITY PROBLEM - o C0f0UCT A RELiAB1LITY DEMONSTRAT10 ryL 4 + # b 4 l3 0 YTl A 3 g
~
o SIMULATE A FUEL CYCLE o 100 HOURS SEASONING RUN 7 o 20 SLOW STARTS
} OtMt#%cMI d #1'd MX,
[O2#fa o 10 FAST STARTS 3 o RUN FOR 7 DAYS (168 HOURS)
# bd 8 c_ n t
e - SCHEDULE I l ALL EDG WORK AND TESTING TO BE COMPLETED BY FEBRUARY 19, 1986 4 'I I 4 4 i i I l
COLT'S POSITION
- 1. Long storage time (1975 - 1982) 7 years.
- 2. Galvanic action as shown by Technfmet report.
- 3. Bearings were subjected to large number of fast starts (with quantity not pre-lubed) prior to bearings being conditioned to crankshaft.
- 4. As a result of the failures in Unit #11 in January 1985, all units were subjected to disassembly and replacement of bearings in Unit #12.
- 5. Units #13 & 14 - The upper bearings in position 1 thru 6 were removed, visually accepted and re-assembled. All bearings inspected were good.
- 6. Unit #13 failed #3 upper conn rod bearing due to improper re-assembly.
As noted in brinnelling of cap & rod fits.
- 7. DECO & NRC decided to disassemble all engines to visually inspect bearings, a) Problem - Any disassembly of engine bearings places jeopardy on proper re-assembly.
b) DEC0/ $ replaced bearings against Colt's recommendation. Example -
#14 unit upper main bearings. No problems until bearings were
- r_eplaced.
I
- c) Opening crankshaft / bearing assembly introduces debris into bearings
! - As noted in #4 & 7 main bearings on #13 unit.
- 8. Colt recommends immediate stop to disassembling components for visual inspection of bearing surfaces. Inspect bearings with feeler gauge check j only.
- 9. Correct problem with lube oil dilution on Unit #12 & 14. i
- \
i 10. Run engine per: I a Extended wear in - 40 hours b Continuous load - 2500/2600 kw - 100 hours c Check bearings w/ feeler gauge d Run NRC qualification tests - e Re-check-bearings with feeler gauge.
Q S t.in s tcT : ICAt ems EAlu,tas ou Tka 6%CE AEuc, )ttest dCatan tpa s av Ft asi - 2. TscwiCat issa.E : 'Pertu ri .L come,~ m,3 c v4.wa. .c m oi.mu s w. e i.uc, n . cs. asus .,,c s (.E.u s) wasui.Tius in a Less er e siewineaur wanes or sne uax.y eus Tc %se C4tAsicire. EEhutA tta v IS5acs: 8 7eTC4n4L viaLAThas #F IED C.
- 17 6LEcTir.ic Yes. asst. Sf 5Tsms "
wJ mc ga g uits. AN eustrt Ps.is.a Stsicu cAPA 8Le
- F bpP Pa ETIN4 Tht cPCsatiau er saPsyt A4 4.4TE D S Ts T&m t Dut,N6. ANDCIPM fEb cPsaansun s ee.w g eLdM CE.S 44JD Y@$Tb LA rkb A $d3 D E M T$5 lMCEMIIMk Cawst0ge.Anou #F A Sut4Ls FeiLuta. As stes ub IN Ste nau 3.1.1. E.8 esr Tks FEen s -7. MA L , Ye 6 iiGh a tute4 rnes p r.t o r ba rricgAny CA 9 A c.4TT in P et.s v it t 89 t us m u M E s s g a,,n A L CAC44,E n e c.f LOAb s , sMCueb Afd.
A StM &LE FAttaa&& , Ancn A S Tie t 6,e&s e r A DIESEL 4KNC.EAfDR #E E S S E.A,1t m. sus.* 4 Licaniscs .i As sera insretenus At esta attsn,w s, enri,<st rwt moof CAuSE er 7ML FAtt.ustts ot. A4EANINA Pub CattacT1vs ACDONS. J. 6.W.fis& YEcmNeat $ 9 Ecir tC a r:04 .5udvElu.A NCE ftEsu s2Latt4TT A4D U CE us E cosubi n e Ass HAVE t' AIL &b TD : DEUT 1 P Y 8WCI PiauT FA4 LL1K45. fip.ce.e lauuc411eus: 1. 'i~n&se is seue so4tcar euroEx4neu suaice.nu4 THAT be4E cf TM . O Titst. FACiu?)ES &A3lud TMEtt b3 [s '.5 Wave CyM.cieuCE sE4 tJas4 FEa sbLEms (EGi )*4*ut A tveta su RSS). T,,c c>Ts rr er 1wc Tueur.ws og uer xuw. Ezeien III' .uiu. us Tucs.s Eb 4 cue.4ut. l l AT EAirit O S t.A ub i~ Fcam m y l'i S t. un 4, 'D v A w e. A tarec Tha suMmet. C LsC4iuSLs Lt PALLinie, Th6tE Aub onten TAtluTiti 73 2. SPtua91 a.r( hrsz4cascAs . Z. O b PuWL.444 S&Pa&DM4 36ltM18&sutauTE MAT 6C HJAb L Q u eTE. did d i4AX4 8
l Faiu4c5 Esr,cv: soc n,mc no EM brw : bu lo b u stnie s , fe.cr3,u.s M,es, , it e- .uosit e rreert Pis ten, 3 iv; w e , Sco gnt. Ts24uniu Et a t.n zen Ius n ru re Faubiu A :
- 1. Tsua es s:seven FAiLu s4 mEtmuisms
- e.. E co s io u o r E 64 e:N 4 si,s r a es s ca usso er 4 e ca save m a r. e s = L . di. cree s copic
.suo specm s.s. rue nu. u ses s waw sm.. so so c u- ce, ,e
- co-co mt.
10, ME A rs MCf>L esurMst hvc Et rH e t r4 ane A M+ ala rt LN8EJf4T18h ose Lusts &sV' vi $ g4 n # u s MCs* As r)ts T Ch 64 b (4, % im ped 96C T175 8 M4.
- 6. tt6- t 6a c .N s LA P Pi pw & Cgr> p gq,, Ai> 48 Mei su trat Titt LAC 6 a.a s 46 54,9 s r was [_C.rE>h
- 3. lorrcu.5, o m oav, m c mc. m o sc. .u. wewes. deur .s issuo 4 pu*no sario r- = me s,ut. m .iu s ,a u ,r . T== uu.ua m wr 3r A SCAflud FAILUC6 OccuCl, T 4 stfys#Ae&s Ca u M 44r4 *blarDr.rd M. Art A14 su Abiflasw A L PAiua 44s .
huCLsstaus ' L Yre, t TCems - L 0 L 's etL ucr Pus wn., esunta svnass or Osseswer rwu ; teussausurs.r, rn uur voss uor cuesnrs, unsn G.bc.s7 n aa inse 6Tt, resrur serv 6b ver es Acessocreb , t ae6 LaCMus C( etog YdT rp E:6 rm4U 5 46 A Ectn CAsant Fet The ,Esterib Fsertua41. NXb 0Fi1015 *. L 464.se Twt t.acsu sse ra wasosius Esor t.Avss , ruxe es c a.a.e ri v e A rnsur, Aun nsmoustrears Abe o v 4c v Er EvrtMS N6 T Ekr 4 4. Z. EE4aise Tkt uc& o s a ra nev4urt Twa Eb 4 's Fee Um a ra,1, Ste v 'es or Thnus Suo messe. Au u4mcurab sve v4unuct/m .ae raun u:6 r ua c am. 2LeuML6 bh&S : l OM spirw utuste ou sire eu IIt 4 ra tiScu G3 'Tw e i t 'ut A35 .
- z. couruaru.x nus.
> _ n . ~ -
IEPM1 -1 ED[r f54ttuats e
~
Ws PErion GD6 Osssnit vc b FAitu e_.s _c l.tcsu.tss 'Postuus rab C4nst Coeuenvs Acnona N ec Ac_rions avan, M9f 11 Ticieres ou Low tuu oit s% sener 5 sec43pe4s Asia.mr.uts4 suausutaued ftnsuet. IMsPiccoM ttaV(Atib REvdEb Ta Efouise stowtast teninisesta n av LittJusM SkiMIFifaur tippte cieugsp4fT _ INMOEqt4 4rs Luetir47:ans 7 tem 6tranau huac to Att lucetroid7tb is/T3 t)GN54 SEARIN6 DMM Adi C. DetteuA E% $Ther $Carnators PtA umE f) STMs.rl, . 4sissinnvest NOT&t CEI Iastreefer asut lZ lNSPEcnosa rif(Attb urret. SantampaA4 suctistrus Rits00ec NEC ou sits Assesseur ef4cgstr4Fr BEMst4 ~0susA(C. j 6fAnw4 4r CEfA5 [t0 3st Dr0 4d7 f(6L TWs talas 13 lNSPEcnoM KEV 6Atib UDIW4446 Ml4 9mrc os II m%{ ort. Fat *Est ADE4 daTE.. O Aa8% E 18] I4%fEtn#4 RifkAlf t derfy N oM E pl54tnous, ott AWAo3 s,34tm afiryMsrD Mnaus cw vsstacesrwa ou sood einesass. Tstawn.%inua poes rasma utsusee suseunuus . [; mgr is u se w la uln ecaroo g i.,,,ws.n A tu.c oc rit.,a nusmn,=>. Rs u eunita ,o u sic e roes, tug 8&fDc couctaseep Titadedme wr wawc novecana. wern. cue.MS!r e Mawowi trirra a. neweest, lme mit wae'us. 4 a<Aews cm u trai) .,,, wo.sw. ,.as rum.o. os,=a,e ne w . w p visa w n w reos. ene. wuw m, 7 ,,s. 3m or sc.ne.imes ,u.ec teatusntaucc MT. Iunnensv leawques use2cionou, %,ga %,% , eie, ,cAe ,s, c,ug,, cewuss um couns.w<weg t e .s4. - <. v n, == .s ,u bcwsc6 iu nare a rest Staan* '*"'"' '**'88'a-Ascainst to osiaissat vsuseet, 43 g , IMlfibtLA fie W. j l Out asude. CtAN(fWf N8t'Of1 VCutoe 164 uitt,b Rus- 16 teres N"=='
.'fuaa m. . in . 40 m e. t,,a m ra,as immin, en m
4 - 4 1 e = s - 5 eI e f o
, t 3 -
j
- -{a f, k ', I I I* S)3f$5v.h{
4 2 . , i j EI g is
. e 3 2 Ik l
i&
< =
s i , : . =>g e
- ls$
j
< gj 6 ijg1 2 4 ( E E3'V E d u -
E w . L= . . EI E I
!uJ% e $$ * $
3 Iaea Ie@ a 8 a I a ii e
=
4 a . e# 3 x, 1iE
- 1 g
+ 1 A - 9 a l
-i J g I1 1.2 g a R ;
E $$ ]Ii ! Te 1 5 l e 2 m 3 e 3 3 t
. 1 >.
I ..g* i!3 c N 2 2 a ;E
~
5 ? a
. 5 i A E A
!3IF a
I I d ,$ 3 e
, a e
< ~ e W 1
. J g
g g- G 1 3 i g E IA53 - IE71$3 w C . 2 E b
+ e h
3 5
& B L i o
w A
- a2 i ,,
S ea > I 3
=
Ia } I i O 3 $ E . _ _ _ _ _ . . . . . . o u) 4 S
- = . $ E -
a 1 s ,
' ,sS 3 $ $ @ < 5 E 3 c
-3
, t
= {
3 4 3 e w $ "9 j h5e
- 5 5 d g w C b
g a w a =
~ r 3
s o h 4 a E= a ewe r
=
a e g u
,a .? q a m
3g
. u
- 3 1 3 a A B h 8 Q t 3 y i
? ? 3 " . 3 ~y 1
- 3 o - a a ac o s a 2 -
w 3a . E
* * < g 3
# 3 O $ bW kh 5 __
3 ~ i
& w
& ) .
- - I- A
a g e C 9 tJ mJ 2 k - t 1 E i ? h . e - , e 1 a o g i a P j e 7 p g i 2 0 w v g e 3 3 4
- g 2 a g C C g k h h g E M
$, i i,
c a
!3!3~5 yg.lE
-t < E 1 1-
- 3s 3
n C f
-r E 4
~
d I j @
- F ge __ _. . .. .
5 e p 8 w f v d"
- 5-a e
- b a s .
E 3 $ 3 3 ' 5 t
- g 4
s a . M c b 1 5 3 m s e c 2 & N 2 ~E 3
= g J = .
- 2 f
a a e! 3 a
.s m i .s a
it
- g. __.
b.) " b
- w ( s 5 .m y o*
,4 a
-5
- i 5
- t { $ % h d i g
. i. 3 g
a 1 2 i
-g
= 2 eas u e ,
$ I d $
> > a - ' 2 3 3 ,
a 3 $ e
=
,e =
$k !f $ 5
- b. 3,
=
(- 3
*
- 3-m I= .s..[ g 4
s t e 5 a 4 3 1 i y 2
< r P ~
sn u y -
.c b D e
- d
.s t -
* ~ ~ ' ' * " - - - - - - - - - -
a'6 ^ - ~ ~ "
-, 4# a ,
I s Fs.cm - t E 55 Powcw h e,wri,e stoXV orr5 tty 345 KV WM 4A5 Tut.6:wL5 D'v650WI T-D 'S S'80 l 88 "Y M$ il st 13 19 Mm M m .. .. I /
) ') ) es w c.
S l
)
)
~l x
T es es
? I I I
. .,, - ,es i
I I f
~
l t r
.v
-c
\
l EARTHQUAII 0F JANUARY 31, 1986 1
, DESIGN ISStriS:
o SEISMIC o EQUIPMEllT QUALIFICATION o DESIGN VERIFICATION OF CHANGE DOCUME! TIS DER-85-712 o EMBEDDED PLATES o HANGER LOG BO N o CONCLUSI0!! W 9 + 1 l l t
- e. -. ,
l [ l Earthouake or January 11. 1c86
- 1. Femi 2 seimic mnitoring system
. Active sensors with a seismic trigger preset at an acceleration of .01g.
. Six passive peak shock recorders.
- 2. Response of Femi 2 seimic mnitoring system on January 31, 1986
. The active recorders did not actuate as a result of the earthquake. The active sei mic recording syst s was functionally tested on February 1,1986, and detemined to 1
be functional. 1
. The record plates of the passive peak shock recorders have
] been interpreted. The equivalent static acceleration of the ~r ecording device at the base mat at a frequency of 25.4 hertz was less than .01g. i .
- 3. Femi 2 design accelerations
. Operating basis earthquake (OBE)
Zero period acceleration (ZrA) a = .08g horizontal
. Safe shut down earthquake (SSE) .
, Zero period acceleration (ZPA) a = .15g horizontal
- 4. Effect of January 31, 1986 earthquake on Perry Nuclear Plant in Perry, Ohio Femi 2 engineers have had several telephone conversations with personnel of Cleveland Electric. On February 7, 1986, the Femi 2 seismic-systes engineer and the seismic consulting engineer for Femi 2 visited the Perry Plant and obtained the following unorricini information.
. Tlie earthquake epicenter is located about 10 iles south of the Perry Plant.
. The USGS rated the earthquake at 4.9 on the Richter sale.
l 1 i
i i
. Peal: accelerations neasured at Perry base ist elevation:
a = 0.45g EV at 12 hertz (0.226 expected) a = 1.0g !.'S at 20 hcrtz (0.18s expected) a = 0.7g vertical at.12 hertz zero period acceleration (ZPA) = 0.18g horizontal
. The event lasted 7 seconds.
. Cleveland Electric will submit a written seismic report to the NRC on 2/11/86.
. Thorough walkdowns of the plant have been performed. No damage to safety related strvetures or systems has been detected. Non-safety structures have experienced minor damage such as cracked plaster, ceiling tile displacement.
. Cleveland Electric have operated all safety syste::s reafy for operation since the earthquake.
6* l e l i i l l l
r l i Seimic Issue Prob! er' Numerous EDPs and ECRs were generated by Nuclear Engineering from August 1984 thru August 1985 without evidence of seimic qualification review. (See DER NO-85-680)
. Problem was detected as a result of a survey of 50 EDPs and ECRs by Resident En51neering Arch / Civil in July 1985. This was a SAETEA!1 issue also.
Problem was doctzt ted via Engineering Asstrance audit finding A-QS-P-55-28-14 Jr y 25, 1985. Resolution Giffels Associates (GAI) was contracted to review 1995 change documents processed between August 1984 and Auspst 1985. GAI classified the change doctnents as either type I (1000 c sei mic I or II/I) or type II (995 non-sei mic). Identify type I change doctnent: which already had been seismicly reviewed or did not need a seimic review per procedure NE 3.9.(300 documents)f y Identify type I change doctnents requiring ibrther investigation for seimic qualification. (54 documents)poo Detailed review of the 54' doctcents requiring fbrther investigation revealed that all of the change documents are seismicly qualified and no hardware changes are needed. The GAI review was completed by 12/4/85. The Edison prepared SORsvwere cocpleted by -12/17/85. Cause
%^a Q.J,q Kya.4
- The cause of problem was lack of doctmentation adequcte to decrsnstrate seimic reviews had been completed in all cases throughout the period of developnent of I.bclear Engineering.
i
,b -
, , + , . - _ _ ... -_ , , , , , . _ - _ _ _ - -
l l l l EO REVIEW OF EI)Ps Statement of Problem o Concem regarding seismic review of EDP not having taken place. Outgrowth of seimic concern. ' Caust o Nuclear Engineering did not have an Equipment Qualification Group until November,1985. o All EQ reviews were performed by Fermi 2 En51 neering in Troy. o Needed to be sure all EDPs gent: rated by Nuclear Engineering which required EQ review had been properly reviewed. Solution to Preblen
+ o Review initiated by NE-EQ group on November 25, 1985.
o 273 EDPs total, issued against 21 safety-related systems that contain EQ equipment was reviewed and completed on December 10, 1985. o Results: 48 EDPs and related ECRs received EQ review. 53 contain equipment that either is located in mild envimment or not required to operate in an accident environment. 106 non safety-related 20 cancelled 45 not yet issued 1 combined with another EDP that was in mild environment. W3 - conclusions: o EDPs were properly reviewed and approved by QE group or properly determined that it is not applicable to EQ program. o Nuclear Engineering, as of November,1985, is staffed with EQ group. As design modifications occur or existing equipment * ! becomes obsolete, new EQ equipment will continue to be { evaluated adequately. '
,- -.- - - - -.,,--r -- -
c- - - , . - , - ,, - , - - - - - -wrm -
_ ._ _ - - -. - - m m an, . - ~ - - - l
\
l DESIGN VERIFICATION OF NUCLEAR EICINEERING GENERATED DESIGH CHANT DOCUtiEffrS l l Statemnt of ProbJ g As a result of QSFs and audit findings, DER NO-85-712 issued on December 11, 1985 by Nuclear Engineering De;srtment identified a potential generic problem regarding inadequate docmsentation of design review and verification of Nuclear Engineering generated safety-related design change docsients (EDPs, ECRs, and ABNs). This was done at Edison initiative. h Procedure NE-2.5.7 Design Verification Rev. O issued 5-23-83, applied to all design documents generated or revised by NE or NP but did not require documentation of complete verification. Solution to Problem DER Task Force formed to reverify design change paper. l 1 4 1
Itethndolocv Master checklist and instructions developed (PCN No. 2.of HE-2.5.7)
- o. More than 60 attributes, including QA level, seis.ic, environraental qualification, codes / standards, ccr.nitments/
requirements, piping / hanger stress, rattlespace, fire protection, alara, inspection requirenents. ...etc.
. o Supported by other checklists on specific items such as envirorruental qualification, fire protection, iscznetric, conduit...etc.
o Auditable record will be filed in Doctraent Control. Status Schedule -
- February 20, 1986 expected completion Prorress -
- Scope identified: approx. 111 EDPs, 250 ECRs and 250 ABNs.
- There are approximately 100 items that emerged from the evaluation which need disposition.. All EDPs, ECRs and ABNs have been evaluated. These should be dispositioned prior to 2-20-86. .
- No hardware changes have been identified to date.
e e m6
l \ 1 DESIGff CALCUllTIOf,'S FOR EfGEDDED PilTES Statenent of Preblem and Enckereund j During the process of performing the Reactor-Auxiliary Building design verification, calculations were pre;mred for structural embedded plates which had pipe supports, elect supports, etc., attached. During process of review, concern developed that scue plates may be overloaded. Concern was reported to the NRC and systens affected taken out of service. . Issues
- 1. Why calculations not made sooner:
o Design process was to install embeddments - 15T71. o Design information on loads not available till end of piping analysis. o Scce checks made to detennine embeddments okay. o Decided to perform verification at time of building structure final verification.
- 2. During NRC audit errors found in some calculations.
- 3. One (1) calculation had not been verified before returning systems to service. -
Cause of the Problem The cause of the problem was:
- 1. Failure of the engineer to recognize the difference between the documentation required for a technical answer to this problem and. the doctznentaton required to return the systens to service. ~
- 2. Calculations not ntznerically checked.
- 3. Verification step not complete.
p . DESIGN C/LC.Ul#IO"S FDR D4 BEDDED PLATES Cont'd Solution of the Problem Engineering must become more sensitive to the requirenents of an operating plant in that the design basis calculations nust be complete (both from the standpoint of verified and approved and from the standpoint of properly addressing all the appropriate design requirements) prior to returning a systen to service. Numeric checks of calculations will be required. Calculations have been completed and the embedded plates reviewed were qualified within code allowable stresses without modification. e G D l 1 _ _ _ _ . _,. . .- .. - . _ . - . - -
I j 1 RECONCR.IATION OF STRESS. REPORTS AfD HAtSER DESIGN CALCULATION HAfSER LDG Statement of Problem Troy Engineering transmitted a listin5 of chan6e Paper to Nuclear Engineering which included large bore stress reports, large bore piping hanger DCRs and small bore piping and tubing work of a similar nature. Prorran in Effect The program in effect was to bring up to date all QAI Class I stress reports as of 9-1 85. This was performed. The QAI Class I stress reports also had been revised and issued for fuel load incorporating all changes. The change paper was reviewed for impact on the stress reports, stamped accordingly and entered into the punchlist. Change paper written against large bore pipe hanger sketches would be evaluated for impact against their design calculations. A reconciliation fom would be filled out. It . was to be signed by the preparer and a second engirser who is the verifier. A DER was written to document the fact that there was opn change paper against stress reports and original hanger design calculations. W ~ Stress' Report - Computer Runs - Big effort to update. This has been done periodically on Class 1 stress reports and others based on judgement of engineer. To keep track of changes, they were logged. Solution to Probleg - Nuclear Engineering needs to be sure that design calculations are adequate, checked and verified to support operating plant. Therefore, the actions taken are: Cocpare calculation list to embedded plate list. 17 calculations used for embedded study are now listed on DER N0-86-006. 1
~
l RECOTEILIATIOf! OF STRESS REPOBIS Cont'd I
- Identirv list of plant systems affected.
o HSS has declared systems listed on DER-86-006 inoperable. o Prioritize systen for clearing inoperable status.
!.'uclear Producti n priorities , issued 2-3-86.
feh hedrdi ndyof grooc
- Review individual systa:s, ISOS & Hanger Sketches to be certain all changes are identified.
- Resolve problems, if any, and update or re/ise calculations if and as required.
4~
- Verify calculations and issue to Information Systens.
Shadult Will be trying to complete by 2-28-86.
\
gh% b
- s G-al,4, w:aL p<rL-b 'WE
&dpaA, um i
CO! ELUSION i Threading through these examples is lack of documentation in some cases l of the verification process.
, Action Taken Recently issued totally rewritten procedure requiring that:
i
- 1. Design nust have verification before release using checklists.
- 2. Engineering decisions will have to be doctanented and verified.
This we believe will resolve our identified Root Cause problem. In addition, an evaluation of. Engineering by outside Edison third party is just gettin6 started to be sure that:
- 1. We are ready for restart.
- 2. Our procedures and programs are adequate.
3 Needed improvements will be identified. N l l
" .[L -4 3Q . _ j
~.. __ _ . . . _ __. . _ . _ _ _ _ _ _ . _
G. cJ, A P i ll } 4 i d i i I I FERMI 2 I
; PRESENTATION TO E. C. ADENSAM AND M. D. LYNCH 1
l FEBRUARY 10 1986 i d I 4 I 4 6 z'
- FEB 131986 i
i
- d e
DETROIT EDISON PRESENTATIONS TO E. ADENSAM/M. LYNCH i TOPIC PRESENTOR l 10:30 Introduction F. Agosti ' Fermi 2 Organization F. Agosti 10:45 Plant Status and Milestones R. Lenart l through 100% Power , 11:30 Licensing Status R. Woolley i . Restart Licensing Issues
. License Conditions / Commitments 11:45 Open Discussion , F. Agosti 2
Noon Plant Tour Preparation R. Lenart i e
- - - _ , . - - - , x - - - - - - -.. --.-- - - - . . . . - - - , - , , y - . . . . . - - r-- . - , . - - - - - - ~ - - -
k--
\" I e/"I cE.i",c 'd 'Ji
// , ic.>ta
\ n l 1
1 I I/ w f g l a, I
\ j '
\ 1 nowuu o 1
\
. L
> \
I g
" [,'
r .; .:, h 1> lt. y ' 50U1H . l (6 COOL.ING 10 [R 'l t
. y\
.ses
)T
- k. p
.\
/' ,_ .,-
's f
j ~\g= ,,,-}i. l
' \
b' \ (
~~~~$vl'[~
~ ~ ~ ~
y ,
,. ms . ,
' wl IINC[ -
I, __.p a _ _ _ _ 7 g s. ;
/
$ y1 3 a. ..g:.\ 'i_1 % ];
. i 4 4<. m m anit,o tst., s
,c .
c , cc inx m
~\\r ....il OL_ t: .
}.
- ,u.
i
= nors s, o n.w t, i _;
. us n ig?
i j. s.
-m ic +e g3 c--lL.sh.'-
. -t_.'
c g p( . ' ~ o oon j s g1,. e o. r n. s.wim . < s .
+ l n0C0C00 a, V
~
r=i b g e)"D, N - D t 4 ".U U y-f g i
]
- ~
,N_
?
] l 3=t..,,,t -
- l u.h . w...*
..: l
( "*
, at,1 e air .I ,,
/
L Q $ ,c , san j') yf.
)
' eiw. .
swmu n'ctst \
~ .
1 p .?, . , in ei, if = ^ * " vps...a J'7e ,// 0 .
/ J s s \\
n .)?ow,r;
~,a e .o x v.
., .=- , y~ . .
/ 'A3 ' \
74
^ L[6 .. 'g Ii *. d. ..
,u . -
'.'4 . 'l .
$t -
y( ', _ .. gr ' 7 I.
\
?;/
. . , , ,s
\-
l l l l l l l l ./ .
/ M ntias+ **** /M. I
4 l
- VICE PRE 518ful heCLEAS SPtaAllea5 '
j MANAGiB i huCLEAR SPERAllens l l l I l ! ! 05555fA4T MANAGER A5515fAbi MANAGER A5515fant mAnAsta 6(a(SAL Sl8(CI48 atGutATIOe A nuCLEAN ENGintielt4 meCLEAR PeetuClles 'avCitat GPLAAllSG5 j COPPL'Atti StavlCES l k A [ ~ LA E861GIESIES SUPERINTENSEMI 13A333[a ACE & IIGGiflCAilGE lg = gitEClet BUCt(AG ISAltl56 j l SUPitlNI(20tal
" T ettlet
; af AFFAIR 5 -
NUCLEAR SEC W If l 'A5515fAuf SISECISE 4 g 'G(m(RAL Supfevl504 j , SAS10t0GICAL " QdALIFICalleus = ele (CIO4-fl5 CAL 4 i 1._AnI M03 'gnGin([ElWG 'maltalALS seasAGEnf5T
,_ inD8PLOtti 5AFETT Y OletCIOS-NWAAB
} t u!ait4?sG GuG3P ] ggggang gggttas systegliet FutL - af500htt5 8 A0mle suPPout 5(avlCf5 I
,_ mLCLfAR SAflif ELVIEW l
- niv?!v GaoJP G(h(RAL SurtRV1505 'cle(CIOR-Compuffe j .
- njCL(At SAf(If 4
- 5(AvlCf & lhfetaAiles sesitM E4Gl1EERING i ST5ffM5 j
IG(atAAL svPfaul50a' 4 - 'P40JtCf5 4 PLAMI " huCLfAR P9098Cll44 { (4Gl1LLRl46 A0misl51aAIOR ) A l
,_ AnCulttCTI
- inclutta 4
) i 1 I i
I lJ
! STARTUP TEST PHASE SCHEDUI.E PART A 1
4 1 3/20/85 4/4/85 6/18/85 10/11/85 I
- E FtEL IDAD OPEN VPN. 'IESTING .HEA'ItJP (5%)
. * * *
- i
- w w w w f
'!ET 'ITJTING EVEL IDAD CRD INITIAL PEREORMANCE INITIAL IEl11RON MONI'IORING PERf0RMANCE COLD WALKDOWN EDR SYS. EXP. HOP CED PERfDRMANCE SYSIEM EXPANSION MONI'IORING INITIAL HPCI/RCIC PERfDRMANCE i
i 2 i
STARTUP TEST PHASE SCHEDULE PART B 1 l 10/11/85 1/10/86 HEA'IUP OUTAGE 85-01 PRE-START UP m m s a a s " " 2 WKS
- 7 f RHR PUMP "C" INSP.
ICUIPMENT ENVIR0tNENTAL QUALIFICATION HPCI ESTING I 3L SUPERVISORY SHUIDOWN PANEL G33P120 VALVE AC'IUA'IOR B21F076 VALVE SPRINGS HPCI/RCIC OPERABE
!@C CA'IEGORY "B" AS BUILT I'IEMS MSIV/ ADS OPERABM MAIN STEAM BYPASS LINE REPLACEMENP 3L PANEL MODS EDG POST-MAINP. 'IESTS M.S. BYPASS LI!E SRFP REPAIRS AND MODIFICATIONS 'IESTING I MAIN CONDENSER CEANING-PAINTING SAFETY SYS'IEM LI!EUPS LIfEUP VERIFICATION SRFP. 'IESTING EDG REPAIR AND 'IESTING OFF-GAS 'IESTING .
RHR PUMP "B" REP!ACDfElff DRYWELL MAN. ISO. LItEUP FIRE BARRIER WA MDOWN ROIP OOALS DET OR
'IEERMAL RECOMBI!ER SEAL REPtACEMENP 'IRENDING FAVORABLY SECURITY BARRIER WA MDOWN CCNTROL ROOM STA'IUS FIM VERIFIED OP. COND 2 SURVEILIANCES TEMP M00. REVIEW OPERA'IOR SIMJtA'IOR 'IRAINING TECH SPEC CHANGE REVIN DEVIATION EVEMP REPORT REVIN QA REVIN OF REPORTABM EVENTS ROIP OOALS MET OR 'IRENDING FAVORABLY QA REVIN OF CODMITIEE TASKS 4
STARTUP TEST PilASE SCilEDULE PART C OUTAGE 86-01 OUTAGE 86-02
'IORUS 11A'IC11 REPL.
'IC2(45%) OUTAGE 86-03 'IC3 ( 75%) 'IC5 (65%) 'IC4
-
- a \
i _'IC1(20%)m &
, w w w w w f 3 WKS 4 WKS S WKS 8 WKS 6 WKS
'IURBINE PROCESS COMP. LLRT'S O WrROL SYSTEM CONTROL SYSIEM llYDRAULIC SYEH DYNAMIC OIECK 18 MONI11 'IUNEUPS OlECKOUP INSTABILITIES
'IllERMAL LIMIT SURV. OlECK DURING VERIFICATION SRV S'IEEL CONIROL SYSIEM BATTERY RESPONSE 'IESTING OIANGEOUP COMPLE'IE s OUTAGE 86-04 ,
'IC6(100%) jl00%)[
r w , , 8 WKS (UNDER REVIEW) 11 WKS 2 WKS LLRT'S / 24 MONI11 SURV. MAJOR 'IRANSIENPS 'IESTING 100 HR. NSSS WARRANTY RUN
'IURBINE SYSTEM PERP. RUN
.-._-.4 J --:- a a _ . _. ! e o e I
l l LICENSING STATUS RESTART LICENSING ISSUES TECH SPECS PENETRATION Z-35G i FIRE PROTECTION DIESELS DESIGN ISSUES 50.54(f) j STATUS OF LICENSE CONDITIONS AND MAJOR COMMITMENTS s l i I l
~
l LICENSE CONDITIONS AND MAJOR COMMITMENTS FIRST REFUELING SUPPRESSION POOL TEMPERATURE MEASUREMENTS (2.C.(5) i ! IMPLEMENT SYMPTOMATIC E0Ps REV 4 (ATT 2, 3.(b)) CONTROL ROOM HABITABILITY (2.C.(7) 1 CONTROL SYSTEM FAILURES ( 2.C . ( 8)) DEMONSTRATE FUNCTIONABILITY OF IODINE PARTICULATE SAMPLING SYSTEM (2.C.(15) CORRECT REMAINING DRAWING DEVIATIONS (ATT 1, 2) i COMPLY WITH GDC 56 i l l 1
.r._
1 i RESTART LICENSING ISSUES TECHNICAL SPECIFICATION CHANCES CONTAINMENT INERTING l SUBMITTED 11/13/85 i FEDERAL REGISTER NOTICE 11/21/85 ; l COMMENT PERIOD END 12/21/85 i
)
ALTERNATIVE SHUTDOWN SYSTEM 1 SUBMITTED 09/27/85 FEDERAL REGISTER NOTICE 11/09/85 COMMENT PERIOD END 12/09/85 j SRM COUNT RATE i
! l SUBMITTED 12/23/85 i FEDERAL REGISTER NOTICE 01/29/86 i
COMMENT PERIOD END 02/28/86 3 1
i RESTART LICENSING ISSUE PENETRATION X-35C IDENTIFICATION BY NRR 11/21/85 EDISON RESPONSE / EXEMPTION REQUEST 12/31/85 INSTALLATION OF INTERIM FIX COMPLETE I i t 6
. , . .* .. - - , - , . , - - - - . - - - , - . - - . , - --+---,.,,.--,,n. ,. - --- ,--, .-.,- --. --
,nn., . ,. -n ., , - - ,-< .- ,, -r . , . - -, , , ,,
l l l RESTART LICEN,EING ISSUES FIRE PROTECTION 1 o TORUS WATER LEVEL INSTRUMENT LINES 01/21/86 VP-86-0002 o INSPECTION REPORT 85-50 BASES FOR CTG BACKUP 12/11/85 , CALVERT BUS 01/03/86 VP-85-0221 l POWER CABLE TO SRV 01/03/86 VP-85-0221 CABLES IN FIRE ZONE 2 01/03/86 : VP-86-0221 l l l l l s l - 6 l
RESTART LICENSING ISSUE EMERGENCY DIESEL CENERATORS PUBLIC MEETING 01/24/86 RELIABILITY DEMONSTRATION TEST PROGRAM VP-86-0010 02/05/86 i i SUPPLEMENTAL OPERATING INFORMATION PENDING i i
=_ -
I i i ! L_ICENSE CONDITIONS AND MAJOR COMMITMENTS EDG LUBE OIL SURVEILLANCE (2.C.(10)) 09/20/85(C) i ISI PROGRAM DESCRIPTION (2.C.(13)) 09/30/85(C) 09/30/85(C) REG. GUIDE 1.97 REPORT (ATT 2, 2)
; ALTERNATIVE SHUTDOWN PANEL (2.C.(9)(d)) 10/30/85(C)
OUTAGE EQUIPMENT QUALIFICATION (2.C.(6)) 11/30/85(C) 4 SPDS OPERABLE (ATT 2, 4) 12/31/85(C) l i i 1
.+
l
b LICENSE CONDITIONS AND MAJOR COMMITMENTS f NEAR TERM UE ERIS DOSE ASSESSMENT AND METEOROLOGICAL PROGRAM OPERABLE 02/28/86 EMERGENCY PROCEDURES GENERATION PACKAGE (ATT 2, 3.(A)) 07/31/86 DCRDR REPORT (ATT 2, 1) ))/30/86 SRV TESTS (2.C.(4) STUP FSAR UPDATE 03/20/87
-- - - ~ , , - e,--, ,- ,-.-
l
)
I LICENSE CONDITIONS AND MAJOR COMMITMENTS FIRST REFUELING SUPPRESSION POOL TEMPERATURE MEASUREMENTS (2.C.(5) IMPLEMENT SYMPTOMATIC E0Ps REV 4 (ATT 2, 3.(b)) CONTROL ROOM HABITABILITY (2.C.(7) 3 CONTROL SYSTEM FAILURES 2.C.(8) DEMONSTRATE FUNCTIONABILITY OF IODINE PARTICULATE SAMPLING SYSTEM (2.C.(15) CORRECT REMAINING DRAWING DEVIATIONS (ATT 1, 2) COMPLY WITH GDC 56 }
l l AGENDA MANAGEMENT MEETING WITH DETROIT EDISON COMPANY TO DISCUSS EMERGENCY DIESEL GENERATOR ISSUES GLEN ELLYN, ILLIN0IS FEBRUARY 14, 1986
/l.' 00 AM Openirig Remarks (Paperiello)
Brief summary of EDG Test Program (DECO) Discussion of all problems encountered in test program (DECO) Brief summary of present status of test program (DECO) Discussion on post testing inspection DECO NRC Decision on post testing inspection to be required (NRC) 3n
l NRC - DETROIT EDISON MANAGEMENT MEETING TO DISCUSS EMERGENCY DIESEL GENERATOR ISSUES GLEN ELLYN, ILLINOIS ^ FEBRUARY 14, 1986 11:00 AM 9..
EDG TEST PROGRAM (RELIABILITY DEMONSTRATION) PURPOSE: SIMULATE FUEL CYCLE INCLUDE 168 HOUR ENDURANCE RUN TEST ENGINES: EDG 11 EDG 13 DEMONSTRATION SEQUENCE: BEARING SEASONING - 100 HOUR RUN MIN. BEARING GAP CHECK 20 SLOW STARTS BEARING CAP CHECK 10 SLOW STARTS BEARING GAP CHECK ENDURANCE TEST - 168 HOUR RUN l l
\
\
t l l EDG 12 OIL DILUTION . OIL DILUTED BY FUEL OIL 49 FUEL OIL TO LUBE OIL BOUNDARIES 24 FUEL INJECTOR N0ZZLES (TESTED) 24 FUEL INJECTOR PUMPS 1 MAIN FUEL OIL PUMP (SEAL REPLACED) LUBE OIL CHANGED TO MOBILGUARD 450 (DUE TO SHELL OIL FOAMING) EDG 14 OIL' DILUTION RESOLVED BY CHANGING OIL i l l
- l
\
O EDG 12 PISTON OIL RING SEGMENT FOUND ON UPPER OIL DECK NEAR #10 CYLINDER PIECE NOT MANGLED UPPER PISTONS REMOVED IN JANUARY 1985
#9 PISTON REMOVED IN DECEMBER 1985
. DiECKED UPPER PISTON OIL RINGS NOT A BEARING CONCERN F
O -, - - -
- EDG 11 f Oil FOAMING OBSERVED INITIALLY ON START FOLLOWING FLUSH , INITIAL START WITH COLD OIL DIL LEVEL HIGH REMOVED 20 GALLONS . CONSUMES ABOUT ONE GALLON PER HOUR INSPECTED MAIN PUMP OIL SUCTION PIPE SHELL OIL REPRESENTATIVE TOOK OIL SAMPLE
. SHUTDOWN ENGINE AFTER ABOUT 42 HOURS RUNNING OiANGED TO MOBILGUARD 450 OIL SHELL OIL CAPRINUS R 40 (DID NOT FOAM)
CHANGED OIL ADDITIVE PACKAGE . REVISED OIL CAPRINUS U 40 (DID FOAM) MOBILGUARD 450 OIL NOT FOAMING IN EDG 11 PUT IN EDG 12 ALL FOUR DIESELS
EDG 13 CAP SCREW ENGINE COVER ItSPECTION PLATE CAP SCREW (1/2"-13 x 1") VICINITY OF VERTICAL DRIVE , INSPECTION UPPER OIL DECK ADJACENT PIST0t6 VERTICAL DRIVE AREA OIL PAN FEEL DRAINED 8 SEARW ED CAP SCREW NOT LOCATED BASED ON INSPECTION RESULTS ENGINE REASSEMBLED SCREEN OVER OIL PUMP SUCTION DEM0t6TRATION CONTINUED Y sm j)-
$y ~& W W ,
*^)*
I E *h
*M-A QRbAftyyy fj:t
-y . . .
*H- '
($sp$ I
l e EDG TEST PROGRAM PRESENT STATUS (As of Thursday 1300 Hrs)
~
EDG 11 COMPLETED SLOW START #9 EDG 13 COMPLETED 72 HOURS OF 168 HOUR RUN 9
- , e - . - - - - - - . - - - . . .- ,, - ,-
y < I G i DETROIT EDISON POSITION SUCCESSFUL COMPLETION OF DEMONSTRATION VERIFIES EDG RELIABILITY GAP OiECK BEARINGS EVERY 6 MONTHS MINIMIZE EDG DISASSEMBLY l l
3 S&W EVALUATION COMPLETION OF EtGINEERI!G WORK PURPOSE: o EVALUATE PROCESS TO DETERMINE IF E!GINEERIfC PACKAGES AND ASSOCIATED CHA!GES TO BE COMPLETED ARE IDEhTIFIED, PRIORITIZED AND CONTRCLLED. SCOPE: o PROCESS USED DURING 9 H0hTH PERIOD PRIOR TO FUEL LOAD. o PROCESS USED SINCE FUEL LOAD. METHOD: o REVIEW PROCESS IN PLACE. o TEST PROCESS IMPLEMENTATION TO DETERMINE IF EfGINEERI)G WORK ITENS ARENERE (REF SCOPE) BEI!G IN10DED IN APPROPRIATE LISTS. o IMPLEMENTATION WILL BE TESTED USItG PLANS (CHECKLISTS) FOR SELECTED ACTIVITIES & DISCIPLINES. DURING THE EVALUATION, IDEhTIFIED PCTTENTIAL FINDINGS / CONCERNS WILL BE l o COMMJNICATED TO DECO FOR RES1UTION. 1
~
I EVALUATION TCAM: o EXPERIENCED PERSONNEL FROM OFFICES OTHER THAN CHERRY HD.L A?;D FERMI-2 SITE ORGANIZATION. o APPROPRIATE DISCIPLI!?ES REPRESEhTItG CROSS-SECTION OF BACKGROUNDS IN NUCLEAR PC4ER PLAhT DESIGN, COMPLETION, OPERATION AND EVALUATION. SCHEDULE / STATUS: PLANNED ACTUAL o APPROVE PLAN (S) 2/11/86 2/11-13/86 e o ORIEhTATION OF EVALUATION TEAM 2/10-11/86 ALL BUT "IN-PROCESS" COMPL. o PERFORMANCE 2/11-28/86 INITIATED o POST EVALUATION CONFERENCE 3/3/86 --- o FINAL WRITTEN REPORT 3/21/86 ---
-, c., ,- -. --
. l to >
e' K.bnf- . f f
/Obn 6My , V one A@6.Ta.
NRC f/k E. R. & A ~" A Re
/
pJ w>1gud som e mmm pac
$ 14. TX6KL} DWlg .
5 8v [ 3esfrAG.7/~ SdW F% k. G. A% e s,r, h (o enfS be~dstr fECO G-eh GOao ((ey D6Ce d e G? ' NRa
@;,'E&E
&) hr
~ Mec_
?BWLlK d/kC- Olha d Twhrunws 393 swus~A Nec Muc Ar-anc J As wantt. C Ortt l
i
~
l 0,
, Il}
3
- .= Cr. J +7 b '-
h3'7"II h-- 7i - 3.. ,
- 1 SCOPE
. 1 273 EDPs JSSED ON 21 SAFETY RELATED SYSTDt5 NOVDEER 26, 1986 15% S# FLED GC DECD WER 3, 1985 239 REYlEE D OC 34 RDRINING TO REVIEW 1
\. -_
~
!i y . -,- w - . .~ w =h. p.. -
L*.L -- l t l l . L ' l t- ! : l
- l r ., SPARE PARTS ARE BOUGHT QUALIFIED F,DR INTFJOED USE , .
JY, G.lALIFIED USES ARE LISTED ON IWACT IF LISTED, MATERIAL 15 RELEASED IF NOT LISTED, MATERIAL APPLICATION REVIEED BY E6 1 I
i
- }. g..
,-- gg ~ - g.. .r
- g. c
..s-PROCEDLRES IN PLACE ,
A. SPARE PARTS GROLP Mi-M245 REV 5 5/12/83
- . Mi-44245 REV 1 7/6/84 9/13/84
~
Ml-M245 NEV 2 l
. B. CIMERCIAL M1ALITY (CQ) ENGIEERING r
PPM 3.58 REV 1 7/18/84 F2E 4.87 REV 5 4/18/85 C. MATERIEL ENGIEERIE (EG) ERDLP E-1.16.1 REV 5 4/26/85
^
, T ,,_2 ,_, g- -
vs. -v g- _ ..h_ I - TERE IS NO SWSTANCE TO THIS SAFETEAM N ECAUSE F TE SPARE PARTS,
- COMERCIAL QUALITY (CQ) AM) MTERIEL
- ENGIEERING IROLP (ES) EFF(RT l
l i t ( l
w
. ';f,^ .iF il 5 + s w ..n., ,_ -
{ ,
.e e- ...,,
t
' ! I IECAPE ANARE F CONCERN APO INSTRUCTED ..I
. SAFETEAM TO GET CONCERN INTO PROCESS -
9 l J
ik; 1 2
- r. r -
t- r.. ' a 6 SAFETEAM RECORDED STATDENT MO DID PCT INITIATE ACT10ff . f l 1
}" . _d.. (
r r-
- i. .. 'tt E.fi.
EQ SEISKIC ENGIEER STATED TERE MAY IE A POSSIBILITY THAT EQ REVIEW HAD 80T EEEN . DOE ON CHANES E WAS REVIEWING
~ - ___.__ - _ _ - - - .
}: 4 . . , _ . _ g- s:
- 1 ff t .-n q _ ,,
t
. 1 j
SEISMIC ACTUAL l l TOTAL POTENTIALLY DEFICIENT DOCUENTS ;
; TYPE I CHANGE PAPERS 798 TYPE 1 CHANE PAPERS EGJ1 RING SSE EVIEW 1%
l TYPE I CHANE PAPERS EQJIRING SSE EVIEW APO FtRTER INVESTI-6ATION (TRANSMITTED TO E) 38 l TYPE I CHANE PAPERS POTENTIALLY EQUIRING HARDWARE MG)lFICATION 8 1
r-s .
._--- w=~ g A_ _ : UL v O
t SEISMIC ISSE 1 TOTAL POTENTIALLY DEFICIENT DOCLPENTS 1995 1 t TYPE I CHANE PAPERS 18EMI l TYPE I CHANE PAPERS RECUIRING , SSE REVIEW 38E1 TYPE I CHANE PAPERS REQUIRING SSE REVIEW APO FURTER INVESTI-GATION (TRANSMITTED TD E) 58 TYPE I CHANE PAPERS POTENTIALLY RECUlRING HARDWARE MODIFICATION 4 i 1
)
I
H - - - w _ ,1 L __ g. .c . .g .. g, t- .-- I"f$.3 _ . , 7 - z, . e**L F: .Miniaiae the a33.)_qr of rgrozu.b1m)fp.a.gL_9tgggrygggy.a_,8 Objective . Number of Licensee .- 3/ week Manageneat Attention Level Event Reports (LER's) - 1.5/ week Aseeptable I 5I 5 I I I 4 I I I Nuober ! 3I 3 3-3 I I 2 - Ngat of I L 2 l--2-.-----.---2----- ..- -- ----....----- ---....-----Attention l Level 1- - - - . ...-. -------...-- ---.-...- -- .-.....--- 1.5 LER's I j Accept 11 1-1 [ 1
\0.--c -o/
o1 i i i i i 1 l t I_1 1 L1 I t i 1 i 1_ i September l Cotober ! Iovember I Desember l l e Note: Reportable Operational Oeeurrences do not include Security-related LER's. l 1
I' .
._us-== %+ . gg';&& {.js1
- c. ..
(
, 3: M i n i m i s e t h e Jy.p.)tM.-.9f. t y).Pj a n d i n a . time seegitive LCO's
- l Objective - Number of dated - 5 Management 4tteattom Level l
. LCO's outstanding - 3 Expected l l
10 l
-l 9I I
Nuober 8l 1 of 7I I Dated 6I 5 - Mgat I 5 1------------------------------------------------------ Attention LCO's ! Level i t 1 4 ~ I Outotanding 3 l---------------- --- ------------------------- ------ 3 i Expected 2 l 2 I
' -' \ ' % ,/'
l .
.L J--.L i i i f r I t 1. 1 I I .t 1 i i l geptember i October l November l December l t
i
=
W 2s M Q ?+ f 3e *t, n : 2.t.ttp?A .9Pr5.tt i)Mo f 7..tt . ) art. R(9 % F.!A148. MllLAtt91.9.2fitA obiootivD Surveillances completed on time feeluding grace period 995 Management Attention Level 100$ Expected Surveillances not completed within 24 hours of reaching the grace period '- 7/ week Management attention Level
- Erweek Expected I
101 1 1 100 Surveillances i 100 1100- 00--------- ---100-=,10 (----p q-j00--------------Expected y 5.7 Cocpleted 1
----------------------------------- Mgat 99 I --- -----------
Attention on Time ! - Level 98 i Including l 97 1 0-aco Period .I 96.5 96 1 (5) I , 95 l 1 1 1 1 I I I t 1 1 1 I I I I i
- 1. _ _I 1 _1 i September i October l November i December i 1
10 i 7 - Mgst Survoillances l Attention Not 8 I Level Cocpleted 1------------------------------------------------------ Within 6 l 5 24 Hours l---------------------------- Expected of ontering 4 l h(3--3 tho Orace ! ,g3 Poriod 2 l (No./ Week) 1 1 I I I _1 1 1 1 1 1 1 0 1 1 1 September 1 1 1 1 October l November 1 - December i l ! l
\ l 1
I
3-- J .- gg Q:J. L {--
. C: Minimise ausber of taoperable or continuessly alarmies annunciators g
. gponArel RgpA.
Object - Number of 11ghted, non-fuastional annuneisters ,
- 15 Management Attention Level 3
- 10 Expected i
1 1 100 I I to I Outstanding i 80 I control 1 70 1 Boom I . Problem e 60 i 1 51 f(5
/
50 I l Annunciators 1 4 6-4746 ! 40 1 136
- 30 I 15 - Mgat i
20 1 . Attention I------------------------------------------------------ Level 10 l-------'--------------------- ------------------------ 10 1 Expected i I I l_ l f._ I 1 - 1 l_ _ i November I I _ _L I i l i I 1 December l September l Cotober i l l l e probles annunoistors are all inoperable, avisanos, setpoint, logie, etc. related annunciators.
- - - - - , . - ,- - - - ,m , .- =-,- r- -. m -
. - Q ,;.;'J.ea gE? Q. . . - g r t, 3 : Mialaise ausber of 3DP's which remais eyes efter work. bas been s_e.nf.1.fA14.. Ate uf.Ar18 sut=>1 et.. .._ _ .... .
object - EDP's open 30 days - 15 Management Attention Level after field work = 7 Espected complete l l 200 I i 180 i Nuobor ! of 150 l I Fiold 1
- Couplote 140 l EDF'o i 120 I i
100 1 ! 0p00 1 ! Foot 80 1 30 70 Days 60 1 1 7(9 5 D4 I 40 1 I - s4 %7 20 1 15 - Ngat 1 [...................................................... Attention 10'I Level 1------------------------------------------------------ T 0 i Expected i I I _ J . l ..J.__1. . .L . . J . . .t . . .l. . . t . . .L __ J ._ .t _ _1. l iI l sept.ener I cotoner i sevenner I seoenner 9 k l
i.,
~ l'
- W 3 .5,Q bQ@@ \ , .. .-
-. y u
00aL At Minia1At Eumber mf ones _PN-tt 's (Vork QtgiggJ . . Object - TOTAL - 150 Management Attention Level . TOTAL - 110 Expected E l l og;agg 45-01 l g 9 : I 1 g N 400 l l 3 .I I 38b379 I E I i / f62 366 g ' R l l34 l I I i 0 l 300 1 1 P 1 I I E l g l 250 _ _ . . 265, i 218 ,2 6,, g g ig V 200 I j gy g, 4 0 1 l----- 173 4-- t, F
'II _ _ _ _ _ _ _ attention150 - Ngnt 1
29 I .g g.,,1 1 i l i o 100 l- - - - - - - - - . I-.. .... . . . . . . . , gg,
- Expected l l l I I I !
R I , l l s o 1 i g I-.L__1_..L 1. . .I J_ I I t i t i i i i
! 8eptember i Detsber i Noventer i December NOTE: Includes plant system related FN-21's (work orders). During an Outage greater than one week in duration, total numbers aan be inorgaaed by o factor of 2.5.
() { n [m eq. 1 2o; .-, nyLynL w4- ) pgo y Tk o bf ' _i r 2060 i
('j -
!i'l 4 Ei.T"F $;, -77 ff j '~[
- .a . ,L .
- )
r : IEACT(R rFERATIGIS IBFRDVEMENT PUW (RDIP). - i STATUS AS 7 DECEMBER 4, 1985 -
- 1. ROIP ACTION ITEMS COMPLETED A. TOTAL COMMITMENT ACTION ITEMS 64 B. ACTION ITEMS REPORTED AS COW LETED OR ON-G0 LNG 45 C. ACTION ITEMS SCHEDULED FOR COMPLET10N 17 D. ACTION ITEM RESPONSES OVERDUE 2 TOTAL 64 64
- 11. NQA VERIFICATION OF ROIP ITEMS l
A. VERIFICATIONS OF COMPLETED ITEMS 41 B. VERIFICATIONS IN PROCESS 4 C. VERIFICATIONS SCHEDULED UPON COMPLET10N OF ACTION 19 1
9 e o g FERMI 2 ENGINEgyzyg ggy3gy l 1
)
I
~.
PURPOSE o EXCHANGE INFORMATION ON ENGINEERING STATUS l VERIFICATION OF DESIGN CHANGES ENGINEERI!:G STATUS T F j w -#mt T
Agenda Verification of Design Chances o seismic concern o EQ concern o re-verification of design changes o Ssw assessment Design Status o At Fuel Load prioritization process remaining tasks at fuel load embedded plates concern hanger cales and stress reports concern o At Present o S&W Evaluation of Design Status Summary
[- . SEISMIC REVIEW CONCERN CONCERN ,- 0 HAS SEISMIC BEEN CONSIDERED IN NE-GENERATED DESIGN MODIFICATIONS? SEISMIC REVIEW o INITIATED BY NE VIA DER NO-85-680 DUE TO: A SAFETEAM CONCERN AN NQA AUDIT FINDING SCOPE 4 0 ADDRESSED ALL NE-GENERATED SEISMIC I AND 11/1 DESIGN CHANGE DOCUMENTS TOTAL IDENTIFIED: 1995 (EDPs, ECRs, ABNs) AS OF AUGUST 1985. 133 SEISMIC CATEGORY [ OR 11/1 DESIGN MODIFICATIONS. RESULTS o 104 GIFFELS ASSOCIATES ASSESSED AS AudQUATE o 29 REVIEWED APO ACCEPTED BY DECO-o DOCUENTATION COWLETE VIA 133 SQR FORMS - o IN ADDIT 10N, PROCEDURES E RE REVISED TO REQUIRE SE SMIC SIGNATURE kos.,P,ic/ CONCLUS10N _ o CONCERN HAS BEEN ADDRESSED NRC REVIEW o Deco ~ ASSESSMENT WAS CONCURRED BY REGION lil TECHNICAL STAFF 4 l l 1 i
ENVIR0f9 ENTAL QUALIFICATION (EQ) REVIEW CONCERN
* ,9 e w'ps,j , s% l
m. o rP ,
Q ' y ., ;'(' _(
,,,S '.
CONCERN o
<i3,p4("
O HAS EQ BEEN CONSIDERED IN NE-GENERATED DESIGN MODIFICATIONS? EQ REVIEW 0 INITIATED BY NE-EQ GROUP ON NOVEL 6ER 25, 1985 l
- WHEN BECAME MARE OF THE SEISMIC CONCERN OBSERVATION IDENTIFIED BY NQA FROM AUDIT OF TROY-QE GROUP SAFETEAM CONCERN SCOPE o IDENTIFIED 273 EDPs AND ASSOCIATED ECRs AGAINST 21 SAFETY-RELATED SYSTEMS THAT CONTAIN EQ ELECTRICAL EQUIPENT RESULTS 1
1 20 EDPs WERE CANCELLED 45 NOT YET ISSUED l 106 NON SAFETY-RELATED 48 RECEIVED EQ REVIEW FROM TROY-E GROUP 53 EITHER IN MILD ENVIRONENT OR NOT REQUIRED TO OPERATE 1 CONEINED WITH ANOTER EDP IN MILD ENVIR0tNENT 273 TOTAL CON 1US10N o ENVIRONENTAL QUALIFICAITON OF EQUIPENT HAS BEEN PROPERLY ADDRESSED IN NE-GENERATED DESIGN CHANGE DOCUENTS. NRC REVIEW I o REGION Iii UNANNCUNCED lNSPECTION DECENBER 4-6, 1985 o NO VIOLATIONS OR DEVIATIONS E RE IDENTIFIED
DESIGN VERIFICATION CONCERN -
,'r'/ w.v C&
,,e s j c-o INADEQUATE DOCUMENTATION OF DESIGN REVIEW Af0 VERIFICATION OF NE-GENERATED SAFETY-RELATED DESIGN CHANGE DOCthENTS- '
DVR REVIEW 0 INITIATED BY THE NE VIA DER NO-85-712 e o COWREHENSIVE REVIEW OF ALL EXISTING CONCERNS: (VIA A CHECKLIST) SEISMIC, EQ, EEEDDED PLATE, PIPING STRESS, HANGER...ETC. SCOPE SAFETY-RELATED EDPs 97
- SAFETY-RELATED ECRs 267 SAFETY-RELATED ABNs 233 g
j [ TOTAL 597+ Aq 'f'/ - *b xPf' f: 2 s N::t r ie .# RESULTS hau e ; / ' ' ' " " ~ ,~ "
/ ->
57 CHANGE PAPERS, 39 DESIGN CALCULATIONS APO 2 PN-21s MITTEN: NO HARDWARE IWACT, NO SAFETY IWACT 3 NON CONFORMANCES WITTEN HAVING HARDWARE IWACT (FUSES a SNUBBER). CORRECTIVE ACT10N TO BE IMPLEENTED PR10R TO l REACTOR RESTART [9 4 C ' * ' L ' * '~9 5 CI % vo ^ t t. per scenks DANE Q ,y .,,g, y,-o, 57;2:;~p i. ! uito,,g fis ce va o '- ;y w x,, d[
, CONCLUSION g)ecfae Ece 4 wb" ' e " '^;' "' 0l'd i'%,,
< w e u r::ea h m .
o NO I M DIATE SAFETY IW ACT TO PLANT OPERATION AND SHUTDOWN . NQA AtmlT j o MEK 3/7 - 3/M
,_. , , _ , _ _ -. - - - , - - - - - - - - - - - . = . - - . - - - = , - - - - - - ~ > - - - , - - ~ ~ ~ ~ ~ - * * - - ' ' * - + - * ~ ~ ' ' ' ~ ~ ~ '
, , , _ _ . - -. . - - - 1 IEEPEMENT EVAIIRTIW W 3ERVERIFICATICH Bf WCIJRR ENGINEERDG Addresses o Method (Coupliance with Comnitments). o Inplementation (Compliance with Process). o Product (Consistency with Base Design & Criteria). 4proach:- o Covers all Disciplines in Population. o Covers all Types of Documents. o Exasnines all Cases Involving Hardware Change. o Exarnines all Cases Involving Analysis. o Examines Remainder of Populatica by Sanple.
FERMI 2 ENGItEERING (TROY) KEY EVENTS DURING T E PRE-FUEL LOAD PERIOD 0 APRIL 4, 1984 DESIGN CLOSURE PLAN IDENTIFIED REMAINING WORK AND C0t44ITENTS AND ESTABLISHED A SYSTEM F0,R COWLETION OF OPEN ITEMS. , , ,, w p . , . -- . c me ' t,i. t 3 - O p <asL v.3~ p -&pc.o warkjen n :70 O APRIL 24, 1984 PRESENTATION OF CLOSURE PLAN TO THE NUCLEAR SAFETY REVIEW GROUP. O MAY 1984 REMAINING ENGINEERING WORK REVIEWED AND A SC EDULE AND CONTROL E ASURES ESTABLISHED A WEEKLY ENGINEERING REVIEW. c v ... :.- [ ,, py h . L 0 JUNE 1984 MID-YEAR BUDGET REVIEW ASSIGNED PRIORITIES TO REMAINING WORK. BUDGET AUTHORIZATION BY F50 MANAGEENT Ato VICE PRESIDENT (; ',,l , , g ,,. y; oy O AUGUST-SEPTEMBER 1984 _ l PRESENTATIONS BY SUPERVISORS TO PROJECT MANAGEE NT AND VICE PRESIDENT ON REMAINING WORK. UPDATE OF BUDGET FORECAST.
, gpQ r < n, /,
O FEBRUARY-APRIL 1985 /> r $ k M b c POSTFUELLOADENGINEERINGWORKIDENTIFIEDAND" WHITE BOOK" ISSUED. TASKS REVIEWED WITH NUCLEAR OPERATIONS MANAGEENT FOR AUTHORIZATION.
*n .
( s,'.. v,. n.lt l'
,v.o['
t TROY ENGRG. JULY TROY BEGINS MID TROY ENGRG. , JUNE SEPT. TROY ENGRG. A/E'S 1982 ENGRG. 1984 POST FUEL- f 1985 1985 CLOSED OUT
~'
, CLOSE0UT j LOAD MORK l ,1 A
i SUMMARIZED
- i h
//7'I-
/
f , NUCLEAR APRIL NUCLEAR FEB. 1985 DECISION A/E JAN. 198b ENGRG. 1984 ENGRG. [AM TO SELECTED FORMED BEGINS SUPPORT' C t 'M PERFORMING NUCLEAR QA I MORK gNcgg, ON SITE
. aa.
d
CRITERIA PRIORITY 1 - (WRK REQUIRE FOR FUEL IDAD)
- TASKS REQUIRED TO COMPLITE PHYSICAL CONFIGURATION OF SAFETY RELATED SYSTEMS AND QA1 COMFONENTS OF THE PLANT.
- TASKS REQUIRED TO SATISFT REGULATORY REQUIREMENTS AND FSAR LICENSI!C COMMITMENTS.
- TASKS WHOSE F1JNCTIONAL FAILURE CAN CAUSE, OF FAIL TO MITIGATE A !
NUCLEAR INCEENT AND CAUSE UlOUE RISK TO WE HEALTH AND SAFE 1Y OF THE PUBLIC. PRIORITI 2 - (WORK REQUIRED FOR PLANT OPERATION)
- TASKS REQUIRED FOR COMIONENTS OR SYSTDiS IDENTIFIED AS BOP AND WHOSE F1JNCTIONAL FAILURE CCULD CAUSE AN UNSCHEDULED REDUCTION IN UNIT OUTPUT.
PRIORITY 9 - (WORK REQUIRED FOR COMMEICIAL OPERATION AND BEYOND)
- THOSE ACTIVITIES EAT WERE DETEININED NOT BE PRIORITY 1 AND 2 4
1 i E f (
- ^
Page 1 of 4 FIO OIMDIE TARS ITEM TWYRIPTION STA'll!S P)C-1 REACTOR /AUXILAIRY BUILDI!G COMPLETE IN 1986
' STRUCIURAL DESIGN VERIFICATION
\
REACTOR / AUXILIARY BUILDING COMPLETED IN 1986
\ PIO-2 SIRUCTURAL ANALYSIS (y .a P)O-3 REACTOR / AUXILIARY BUILDING COMPLETED IN 1986 g EMBEDDE PLATE ANALYSIS p- PPO-4 PROCESS SARGEhT & LUf0Y COMPLETED IN SEPTEEBER PREPARED DRAWINGS P)O-5 STRUCTURAL DESIGN COMPLETED IN AUGUST VERIFICATION OF REACTOR BUILDING SUPER-STRUCTURE STEEL Plo-6 UPDATE OF NON Q CIVIL DRAWINGS CCHPLETE IN OCTOIER PPO-7 LDNG TERM IDAD CONTRG. REVIEW TRANSFERRED TO N. O.
PMD-8 UPDATE PENETRATION DRAWINGS TRANSFERRE TO N. O. P)O-9 COMPLETE FERMI 2 RIGGING MANUAL COMPLETED IN AUGUST PMO-10 RATTLESPACE MAINTENANCE-COMPLETE IN AUGUST PtO-11A SEISMIC DESIGN QUALIFICATION COMPLETED IN NOVEMBER OPEN ITEMS P)O-11B SEISMIC DESIGN QUALIFICATION TRANSFERRED TO N.O. PACKAGES P)O-12 SEISMIC DESIGN QUALIFICATION COMPLETED IN AUGUST MANUAL P!O-13 CABLE TRAY HANGER RESQ.UTION COMPLETED IN MARCH . Y PMO-14 DRYWELL STRUCTURAL STEEL FOST COMPLETE IN MARCH I PHASE 2A DESIGN VERIFICATION PMO-15 PREPARE INDEX OF NON-SAFETY- COMPLETE IN OCTOBER RELATE STRUCTURAL DESIGN CALCULATIONS
'hi c.1 o'pri i]irab tid' A wtV wG5 91 tas . or. al fal loacd c. , g g 6 yg
----. --. - .- .. . . n_
1 Page 2 of 4 . i l ITD4 DESCRIPTION STAills l PMO-16 SETPOINTS VERIFICATION TENTATIVEI.T APPROVED CALCULATIONS TRANSFERRED TO N. E. ENGINEERING TO PROVIDE ADDITIONAL INFD. AS SOON AS GE/Nlt DEVELOPMENTS PERMIT. P)O-17 MAINTENANCE OF FSAR DRAWINGS- COMP ET E IN AUGUST FUICTIONAL CONTRA. DIAGRAMS (FCD) PHO-18 DETAILD C0hTROL ROOM DESIGN APPROVED - TO BE PERFOPF.ED REVIEW IN 1986 BY N. O. P)O-19 COMPETION OF THE RADWASTE PARTIALLY APPROVED - SYSTEM TO ADVISE ON UPDATDiG OF PODICOM LOGIC PHO-20 PIPE SUPIORT CALCUMTION/ IN PROCESS REEONCILIATION PHO-21 S&W HANTR CALCUUTION IN PROCESS PROCESSING AND QA1 URGE BORE HANGER SKETCH UPDATE P)O-22 URGE AND SMALL BORE STRESS IN PROCESS REIORTS P!O-23 EQUIPENT ANCHOR BOLT DESIGN
.. p dj N
- (( $ {
CALCUMTIONS P)O-24 S&L HANGER SKEK H AND APPROVED CALCUMTION UPDATE I P!O-25 HVAC STRESS REPORT REVISIONS IN PROGRESS PHO-26 EQUIPMENT QUALIFICATION COMPETED IN AUGUST CENTRAL FILE DOCUMEhTATION UPGRADE TO DESIGN DOCUMENT STAWS PPO-27 ELECTRICAL EQUIPENT COMPLETED IN NOVEMBER QUALIFICATION TESTI)G PROGRAM P!O-28 REVIEW OF MDC ENVIROM4 ENTAL COMPLETED IN MARCH PROFILE REDUCTION REIORT FOR 2ND FIDOR REACTOR BUILDING
- P)O-29 MECHANICAL EQUIPMENT CCMPLETED IN NOVEMEER QUALIFICATI0F PROGRAM i
._ - - . _ _ _ _ . _ . ~ . , , . _ - , . _ _ . _ , , _ _ _ . , _ _ , _ _ , _ . - . , _ . _ . . . _ _ . - - - . _ , . ,
Page 3 of 4 l ITD4 DF9ER1PTION STAWS Pto-30 DECO'S RESPONSE TO 10CFR50.49 C0r4PLETE IN NOVEMER l l (COMPETION CF ASSOCIATED CIRCUIT REVIEW AND PREPARATION l j OF DETAILED POSITION ON CtOS ' ELECTRONICS IN RADIATION FIEI.D) Pto-31 HARSH ENVIRO) MENTAL CNPETE IN NOVEMER NURED-0588 SUBMITTAL UPDATE PMD-32
SUMMARY
REIORT VERIFICATION ONCDING P)D-33 ELECTRICAL EQUIPEhT COMPLETED IN NOVEMBER QUALIFICATION CEhTRAL FILE UPDATE Pto-34 EQUIPEhT QUALIFICATIDN EDPs COMPLETED IN h0VEMER Pto-35 MAINTENANCE AND SURVEILLANCE CCHPETE IN NOVEMER REQUIREMENTS FOR ELECTRICAL AND __ _ MECHANICAL EQUIPMENT IN 1985 Pto-36 ENVIR0tMEhTAL QUALIFICATION COMPLETED IN NOVEMBER DESIGN QUALIFICATION MANUAL Pto-37 PREPARATION OF EQUIPPENT LIST OPCOING FOR NUREG-0588 SAFETY CATEGORY 2C MECHANICAL AND EI.ECTRICAL , EQUIPMENT. Pto-38 REVIEW OF QA1 POV VENDOR . COMPLETED IN OCTOBER DRAWINGS Pto-39 UPDATE OF BOP GROUP II FOS COMPLETED IN JUE AND P& ids Pto-40 REVIEX AND UPDATE OF QA1 POSTPONED - NO FURTHER PROJECT DESIGN CALCULATIONS DESIGN IS TO BE DONE UNESS FORMALLY REQUESTED BY NUCLEAR OERATIONS Pt0-41 PROJECT SPECIFICATION UPDATE 10STPONED - NO FURTER DESIGN IS TO BE DONE UNIISS FORMALLY REQUESTED BY NUCLEAR OPERATIONS Pto-42 PREOPEPf7IONAL TEST PROCEDURES ASSIGNED TO N. O. Pto 43 TEST RESULTS PACKAGES ASSIGNED TO N. O.
Page 4 of 4 - l DfjCMPTION STAWS _JID Pt044 DESIGN DOCUMENT PACKAGES ! AND VENDOR DOCUMENT LISTS
' 't,O P90-45 DESIGN VERIFICATEN OF PROJECT t (
CHANGE PAPER P10 46 INCORPORATION OF PRCUECT CATE00RY 1 PORTION OF TASK CHANGE PAPER APPROVED. NO FURTHER )ORK IS TO BE DONE ON CATEGORY 3 ASSIGNED TO N. O. PMD-47 FERMI 2 A/E DESIGN POSTPONED - NO FURTHER DOCUPINTATION CLDSURE WORK IS TO BE DONE UNLESS FORMALLY REQUESTED BY NUCLEAR OPERATIONS Pto 48 SEI!NIC CALCUMTIONS CCHPIETED IN JUNE i Pto-49 HVAC SYSTENS DESIGN COMPLETED IN SEPTEMBER VERIFICATION (S&L TASK 7203-62) Pto-50 RESCLUTION OF N3 DATA REPORT COMPLETED IN JUE PROBLEMS Pto-51 PREPARATION OF HANGER DESIGN COMPLETED IN NOVEPJ3ER CALCU MTIONS Pto-52 HVAC AIR BALANCING TEST RESULTS , Pto-53 VERIFICATION OF PROPER OPERATION TRANSFERRED TO N. O. P10-54 M.I.L. VERIFICATION TRANSFERRED TO N. O. i ___ _ ___. .__ _ __ __ _ ___.___._ _- . __ _ _ _ _ . _ _ _ _ _ . . . , . . _. e. -
l l l IMBGDG PLATE CODEERN CONCERN DURING DESIGN CLOSURE IT WAS DISCOVERED THAT A NUMBER OF EMBEDDED SUPPORT PLATES WERE 10TEhTIALLY OVERLDADED BASED ON TE (DNSERVATIVE ENVELOPING LDAD CALCULATIONS PERFORMED. g HISTORI 3D Ad THE EMBEDDED PLATES ARE CONSIDERED PART OF THE STRUCulRAL DESIGN. THE iV' DESIGN CLOSURE TASK OF THE BUILDING SYSTEMS WAS PRIORITIZED AND k ;h STARTED IN 1979 AND IS AS FOLLOWS: h - DRYWELL STRUCTURAL STEEL INCLUDING WE EMBEDDED PLATES Oa - SLAB OVER TORUS STRUCRIRAL STEEL INCLUDING EMBEDDED PLATES sm k - BALANCE OF OWER STRUCTURAL STEEL AREAS CAhTILEVER WALLS AND HIGiLY LDADED WALLS, BIASED LDADED h t* ? , EMBED PLATE SAMPLE
,h - CO) CRETE FIDORS AND WALLS, BALANCE OF EMBEDDED PLtTES
('g w o EARLY EMBEDDED PLATE CALCULATIONS WERE PERFORMED IN 1979 BUT THE LACK q c' { d 0F FINAL IDADS FRCH THE PIPING ANALYSES AND LDAD TABLES DELAYED CLDSURE UhTIL FUEL IDAD. WHILE COMPLETION OF THIS TASK WAS PREFERRED IT WAS JUDGED TO BE A LDW RISK ITEM. EDf.E ISSUED DER NP-8 -0652 EMBEDDED PLATES - POTEhTIAL OVERSTRESS. ADDRESSES PLATES IN THE REACTOR / AUX BUILDING FLOORS AND WALLS. l l l l. -.
- Page 2 of 2 EMBEDED PLATE ColCERN IASK l
4 - IDENTIFICATION OF OVERIDADD PLATES BY SARGENT & LUl0Y
- REFINED IDADS GENERATED BY If.TROIT EDISON AND STONE &
WEBSTER
- AS BUILT VERIFICATION OF IDCATION OF AITACHMEhT ON EMBED . i,U PLATE \ #;
s./'}U(- EVALUATION OF PLATE F
.. '/ C DOCUMENTATION OF RESULTS IN DESIGN CALCULATIONS L
fi' j l,[
**1 a
RESULTS ^D 'cgc \
/ Vg ,'
- ALL PLATES QUALIFIED TO CARRY IMIOSED IDADS DESIGN CALCULATIONS PREPARED. AUDITED BY NRC TECHNICAL STAFF. ALL PASSED.
CONCLUSION DESIGN TASK COMPLETED WITH ALL PLATES QUALIFIED TO SUPEORT IlGOSED LDADS. THIS CONFIRMS THAT ADEQUACY OF THE ENGINEERING JUDGEMENT AND CALCULATIONS MADE TO LDAD FUEL.
1 PIPE SUPPORT CAlfULATION AIO STRESS REDEILIATION CDEERN (IDG B0%) CONCERN THAT THE PIPE SUPPORT AND STRESS REPORT DESIGN CALCULATIONS HAVE NOT BEEN KEPT CURRENT AND WAT DOCUMENTED REVIEWS TO ASSURE DESIGN COMPLETENESS OF THE SYSTEMS HAVE NOT BEEN MADE IN ALL CASES. E.QP.E THE QAI CLASS I, II AND III STRESS REPORTS WERE CONFLETELY UPDATED AND ISSUED AT FUEL IDAD. TE CLASS I D.C.s )ERE FURTER UPDATED AT 9-85. IkK THIS TASK IS WE COLIICTION AND CONFIRMATION OF WE OPEN DESIGN CHANGE DOCUMENTS AGAINST TIE RESPECTIVE DESIGN CALCULATIONS ERSUS TE LAIEST ISSUED OF WE D.C. IN INFO SYSTENS. EVALUATION OF TE OPEN DESIGN CHANGE DOCUMENTS AGAINST TE D.C. AKD PERFORMANCE OF WE REFERENCE REVISION OR FULL REVISION OF WE BASE CALCUIATION. THIS WORK WILL BE PERFORMED TO CURRENT N.
E. PROCEDURE
S. ESTABLIS}f4ENT OF A PROCEDURAL REDUIRENENT FOR PERIODIC UPDATING OR LIMITI!C NUMIER OF OPEN CHAKES AGAINST A DESIGN CALCULATION. SCHEDULE - STAWS o LARGE BORE HANGERS STRESS REPORTS IDNG TERi o SMALL EDRE HANERS IDAD C0hTROL o 0100ING EFFORT BY DECO, S&W AND S&L o NO HARDWARE PROBLEMS TO DATE F _ _
PK) TAKES ARRTCNED TO NUcl71R FETNFFFTE
. PMO 3 EMBEDDED PMTE ANALYSIS PMO 7 WNG TERM WAD C0hTROL ON-GOIE - 40 YEARS PMO 8 MAINTAIN PENETRATION DRAWINGS ON-00I!O - 40 YEARS PMO 11B SEISMIC DESIGN QUAL PACKAGES ON-00I}0 - 40 YEARS f PMO 16 SETPOINTS - GE METHODOLOGY 1986 +
PMO 18 CONTROL ROOM DESIGN REVIEW 1986 + . PtO 20 PIPE SUPPORT CALC /RECO}C ON-GOING - 40 YEARS PHO 21 S&W HANGER CALC & LB SKETCH UPDATE ON-GOI!G - 40 YEARS P}O 25 HVAC STRESS REPORT REVISIONS MARCH 1986 P!O 40 CALCUMTION UPDATE APRIL-MAY 1966 ON-GOING DFSTGN STAWS o EMBEDDED PLATES C0!CERN o PIPE SUFFORT CALCUI.ATION AND STRESS REC 0!CILIATIDN PRESEhT DESIGN STAWS o MISCELMNEQJS PLANT HARDWARE AND }0DIFICATIONS o PMO 20 PIPE SUPIORT CALCULATION RECO}CILIATION (LOG BOOK) o ~ PtO 40 DESIGN CALCUMTIDN UPDATE o SCHEDUII l o PROCESS - METHODOLOGY COW 1USION o DEFERRALS HAVE BEEN BASED ON SQJND ENGINEERING JUDGEMEhT o REMAINING TASKS SCHEDULED FOR CI.DSURE l o BASED ON THE WORK COMPLETED TO DATE IT IS OUR POSITION THAT THE SYSTEMS CAN BE DECLARED OPERABLE.
i
SUMMARY
VERIFICATION OF DESIGN CHANGES RE-VERIFICATION ASSURES ADEQUATE REVIEW AND THAT DOCUMENTATION EXISTS S&W AUDIT GIVES ADDITIONAL CONFIDENCE DESIGN STATUS DEFERRALS AT FUEL LOAD BASED ON SOUND ENGINEERING JUDGEMENT CONFIDENT IN DESIGN ADEQUACY DOCUMENTATION BEING IMPROVED i l 'I l e , , -, - - . , - . _ , . . , , - - , -
l ~ .j .
/
p a j ;) -, d e. /: t (D '.;a hm i REVERIFICNrIGE BY MCIJRR BEDEERDC j w Addresses: e Method (Compliance with Ccannitments). e Implementation (Coupliance with Process). e Product (Consistency with Base Design & Criteria). Approach: o Covers all Disciplines in Population. e Covers all Types of Documents. o Examines all Cases Involving Hardware Change. o Examines all canaa Involving Analysis. e Eranines Remainder of Population by Sample. 61
- u n'ah v. r; 6n oghr. fupe.It.e_
- v(. C ke.v>#off wa s eO o 5 feleC t' r'NL N? 91* $ v)Y o O @WL.
i
.,..__ _ - _ . -- - - - - - - - . - - -~- - - - - - - - - - ' - - - - - - - -
- - _ =
t. i 2MEPMestr Emulieras e mesICat smets
- 1. Reasmableness of Pre-Licensing Process.
O Process for Identifying Ehgineering Work to be Completed.
; o criteria for Deferral Decisions.
o Jlpplication of the Process and Criteria. J
- 2. Reasonableness of Qarrent Process.
O For Selected Safety Systas;
- Determine Required Design ocements.
i - Identify Missing or Incomplete Docusants. i o haluate Reasonableness of: 1
- Process for Identifying Incomplete Calculaticms.
i
- - Criteria for Deferral.
a ! - wucation of irocess .nd C,it.,la. 1 9 b e
- - - - - . , - . - . - - . - . . . , , , - ,e, , ,,w----,-~,n-~y, e--- - - - - - ,-,v, , - - . -v-- - - , .-- - - - , - - - - - , , - , - - - e-,-----,-,-,,_-y,,-m.,,-.-n----- - , - - - - + ,,,-,wa,v-n,,m,--,,-- ,,,m,--
f l- \
/ /
l l l S & W EVALUATION Directed by C. M. HEIDEL (President, Deco) PURPOSE: l o ASSESS EfGINEERIfC PROCESSES TO DETERiINE IF EfGIf1EERIfG WORK PACKAGES AND ASSOCIATED CHANGES WERE/ARE IDENTIFIED, PRIORITIZED AND C0ffrR1 LED IN A MANNER TO SUPR)RT FUEI, LOAD AND RESTART. I o PEPEORM EVALUATION OF DESIGN C0ffrR1 PROCEDURES TO ASSURE THAT PROPER CONTROL OF THE DESIGN PROCESS IS MAINTAINED. l {Ref. 50.54(f).) ! SCOPE: o TRANSITION PRQJECT E!GINEERIfG - NUCLEAR EfGINEERIfG. l (ca 3rd Qtr. '84) to now. f l o EVALUATE PROCESSES & THEIR IMPLEMEf6ATION.- , EVALUATION TEAM - o EXPERIENCED EfGINEERS FROM S&W - BOSTON. o APPROPRIATE DISCIPLIfiES REFRESEf6IfG GOSS-SECTION OF BACKGROUta)S IN NUCLEAR POWER PLAffr DESIGN, COMR.ETION, OPERATION & EVALUATION ACTIVITIES. STATdS - o MOBILIZED 2/10/86. o PLAN APPROVED 2/11/86. o ORIE! CATION INITIATED. o IMPLEMEffrATION OF PLAN 2/12/86. Cmlleessl"hblbl2 N S/zs
l Fw ELAE 40 0 ~L c 21.~ hM~. S W stet : IEAE W6 EAlu,ess ou Ws Emsc4Euc t litss t. dE.n tz4 Teses At Ft a i - 2. Tst.wNic a s 155'LE : 78TLuT'*L Commew me1DE FA *w as er m uss,ete E ME s.4 Euc.x Diosse ause.Av c 3 (E.wsT sesus.rms w 4 Less er a siewineauf **enen MN or sagentax.7 ous TE Pewst catA sac t re .
\
EEhutA tte ? 155aci: 3 7CTC4nAL w i e L A Tl *
- 8' SD d
- 17 66.CcTit.s c ?ewit. SYst&m s "
l w meu g4 ( p.es, AN eus s rs Paar e s t sicu ea e,ists e r s uppserio 4 i Tut op ca.4ricu er sarsn s.4Las&D s ys t em s Dvewt AsunciPmfED Crinansves. * **. u n e.Lu c L s sub ?csTys. Arts AcobENss , sucLUDJMk CousitetAtlou as A Sin 4Ls FA u s4. As srAr=b is S Ee n,4; 3.1. t. t.E en Tus Fg eg i t FGd t., T.e s usw.u gsuce4rees A cc o r su rr.cgA,7 CAP A c.at t it> P ts v it t Asiusmum Esssurin6 car.zAs o c.T WAbs educcu 3 ba*4 A SWALE FAIL 147& , 3mCM AS ThE s.cbs or A *blEs(L - diuc.EATDat at E s s sa.,Tini,. s eas , *
&. l tCEMEM HAS DEEAl sNt rFienvf AT ESTA6LisNN A EITWt2 not Root Canst er THE Fait s4stts et MEANaNA Fut Coc14cTiv6 ACDeN S .
J. 6 M nN& YEcaiN6 cat Sozcia ica fico .lsuavctu. A uct (C4.si< szt att.o rs AND O CE us E terub i n ous s+4ve f'AILI b TD : DEUT 17 Y W CI M AUT FAILLI 8145. htt. t. lA41WAT18his " 3. H&A* 88 SdMt 58.CTLM Y INF0EMA71cu subicA Du6 THAT bo4E cr TkC O TWER. FActuMES 6451u4 ThEst bM 'J HavE tyPEtituct SEA tfoa veemams (.c6 but Ar.uoa m l'l83). Tec e>Tsyv er nic 7a m s is act xu s w. Ec6,ea T5 anu. wiru u.s Et 4 e wr*Avi l AT TE en t e st 15 La u b ,~ Fce w ey ici g (, 4ub , h4ut A s.uc.b h SaMfhtT THC DC4.n.5LC LS PALLIM6 Thd.6 E. Aub ODt& E TA C4 L,tT145 TD t. ePT.a4ti s.i4 c5 pgg4capca g ,
- 2. Eb& rAib 4s4 r.sr,s. nut e.situissanciurs xAv at u.iAtcqu ATc. Eireisucs t
lNDICATM W Ar gr Fdit.utts AEL "JiL5CJvcR.T.b tuiziu& evin&cs weetu Thrt /
Faitues br,cv: ses ariwown 1 i 1 [g ) A T% ; LT A AJ D 64 S rfa t& s ,b s Er3 A us s Motst , IL 4 rb8 &Ot/t O P ralst Pl& TD As, 3 if, 7 w r , ico KPM . s CLA u g.Lg u k g Ld tt#s U S f) rw TE faubludt * (. he e45 sev60 FAicus4 ed.t wauis es
- e.. G eessou tar te,Atos.ss suern ess esuus er nonencove mor****L. tihertesternt m specn us.emse e u.u ses s wcw ,,,mm sue.u. co r.u. e. , ,, m: .
- b. 41s w 70 m erkt eeuwt bue ** TH . e n, ,u . m a . rs. wecac4neu e,e suc4 ws<.
vi s e4 ns a s ge,. 4. ntmT e** se b 4.s smreerec T'*'M4. f,s . ft& S da t N 4 LA P P 3 N s C#hi P44/Mb 48 AJ#T g;er>T M 6AC6AJ546 SAto # F lef AS kT*Og,
- 3. lur,cou., ,
m e.v, ,% e m o, yc.o gc.c.u, w,e tem s. (.'t , .s issues . sanu sar uu rm n. unasus, un,us,uss au var svu.s- w.nsua m na ir a scaesud FAiwcc pecuc4, r4 m ius.4 cau Mten6 " Dis 7Dc.rs) EesAtive su Ah srlpW Ab PAlud441 eCLu.%sDUS
- 5. Irs t VLLms=2 G b i 's Att 90T Vt45&MTL4 E4 LIA 4U E vP!LI GS O F Odf-4 CA.!C Y Pp.ca 3 Ecus' a u6uYt.r, rue Paur Tces uer c4.ecant r4 rssre &b( .s7 n ua immtemet, essner sirrptb AlcT et ##s 0(dtb ,
t & LLC &Wsst etag T&T TD Es 7 mad $ a4 A Rgt ; CA96( Fot. Tidt CESEcWsb FAttunds. NKL Grnous.t tw as M uesosu n um.. rs es.1 es a u , m, ea a.wr,,,e unaus, Aus it u.r u rs A3.o vu v s, s m us,u u m us.
- 2. lAIS& M UC40$ES- 'Ts E4 G L/ A u r' Y T)t& E.D 4 's For LI#flT3.b S&ereed gr Thri u s, Sus imtest. Au ,694ascursb Spertu.nua/,wurwa uc6 r at a t aat.
fLeVNLb bOf45 l MEr1 lo Tu Lttavsie ou .1:rE pu IITA ra 3iscuG3 Tw 6 sr. PLA M C.
- z. courw u ns, erra s a..
t
- 3. W.ruess h. 1suus as hwe Acu% E M rus,u ,,,,y3
f5 f"1 3 i u 2 a *==,[ a a 3 gj$ I w 3 - o
*Id 6 .-
!g y 5 "
o u If D { $E
*5 Ngi
-3 i e !
2 )g g8 f i e <
- E s
- J o Te - *
$5* l l- { 2 2 *
} *$.
l 5 ,e e a a
&e
- 1? --
a 3 stc 8 d i a I t j I e o 3 W t U 8 W g b a m 8 3 *5 m w 2 $ i t 0 s a e i e 5 r :u y a6 sE
* *E y" 3 j 6s*i3i! I ye s
{ E = s 2 o A i B s s 2 3 5 4 5 34 5 e , dW - i 1 * { E d - h2 E ! a 2 3!8 S 3 3 5
=
I di3 3s E 2 a g "e
=
.g E e3 m
\
a-d q e!g fi , l)!!: g e a.< e b e s2: i5 o
!$e 5 0 =
.: F. " 3 6 3 E h i , j
- 3 S =
3' e8 ? 5 . G S & = c o 3 3!! w w
- 2
! g s)$ssip
'N j u
x A
! E s m i ! "
V .:
+ u . <
g s 2 W E 2 3 d E 4 5 5 - 3 2 d e e ,5 *e i 3 e
$e3 3 s j 5 3 : < g a .e -
e
- a
# e e 5
- w F e 4 x E 4 3 o $ 5 a o i
3 S5
- s i 5# E N' g 3 . 2 g e e <
8 j i 5 ? g
- s< s - o 2 2 w
g
, a 1 ;i sl u i .
d l I b_ y a4I 6 I f \ w d g s= e
< d 1 3 :
?
a I 2 c }w = e e= 3as = t E = = a - i a 2 7 g 3 3 I3
- 3 g !A= E 3 g$
3 9 5 $ E a I ! fg q* 0 ! a hE$$ a z e $u 5 5 ua I 5 2 ts s e! 3 x = 0 t l
*d ! ;. t A g
. I a ? " I e 1 2
!3 5
o 0 e t 3 s= e e s s 5 :s l sa< f s e 1 *
.a3 e:l 5M b3 a ,
3 E
} w -
8 w g$2l , , i $ i E ,_3 y= t> s t - e 0 - cm
?
4* tl
~
w h Y
! 5 5 1_a$_ d a
ks ! t a l {a !;s
.,t 1
W e 3
!a
=
5
- 4
'l 3
I.e h
~n $
2 v.h{. 3 E i=t gip 2 . , . 3 3 a yg i 4 =f a 3 3 5 Vlg!"
- 2 i e
o g {$g 3
=
t E E e g *E E l u - e at b ( - A s-j a e# a g$ I!u$%
. . . 1 i % !13 # $ 1 E 3 1 $ $
g . e g a p 2 .! t g .
$, a (
g g )
. ; 1a s asina 3 e# D l i a i
~ -6 3
5 333!ie
$$ 5 "T5 i
e 3 M i !$ - 1> 5 c*
'a I
2 m s e i 5 e 3 3 i
$ia <
* = 5 e s I3 a 2-
=w
[$ 3 e 3 4 < s
< i
=
< e o
{"
= c
- 5 e
a c I-b' I $ Ia ^ l i 3 g : n e E
~ t. m s. 1 8 _a m w e
5 : v e v i
+ 9 e i 3 5 a 2 k &
F w o E w a , - a = 3 s W 3 i I I
' s s =
5 E _..... ._.. w d >= W 3 4 , C 5 a .
- a 5 i ga ,
'< 1 e
0 3 a 2 5 O 3
; 3
<5
$%3 5
E e w g
$ "?
9 c g lE=5 g
=
5 A h" a
'a 1
; =
2 e
=
j ge u s i. a p g e r I
=
sO . b a [ $$$ sa M3 f55$$$ n ! E *s
$ =
s 2 5 t
=
$ 5 $
? $ .s c : a a a o s a- E l 5 I d! S -i ! ! $' 3 k f -
E A *** w 7._
& u 4
i c Y d I l F i
~
,. '; a 7
o C o T tJ tu I t g a 2 : i s . g j
- 4 E S 3 2 2 1 3 o g 2 .s -
4 > i P $oq \p 3 i a 0 w 3 3 3 3 I~ki
$ I I E #
3 $ 5 5 e s- - 2 -t
! -!, s35
- a 1i1
- 3
% h 2 $ ) h C E 3 , % 3
- I n C r = s a p .3 e to @ A F
$ ~
2 . o 5 c v s a U d O e G
$,, e a O $ $
3 3 L 5 N 5 o E- h 4 3 w M ., 5 c 2. 3
'4
- 1 }
* ?
2 E 2 a i 9 . J 3 . 2
- 6 a a a
- o. 2 e, w s S W e
g -- - __
- h. "
3 u O $ 0 4 a te ( w w 4
- 4 4 -1 41 5 a 3 i B e 3 i ! j' d$ g E 35 1 i : 4 s! !
5 a 2
= ! -
a a. . w g ep ,'
$ E G d E
d C I jI E D d -
$ s k , 3 3 w h) (
$$$$! I $ $
)! $5$ _' ;,
e 3 a 2 . . 3. P u E
- E
?
E Y (: e < 532 y5
- s u
1 2
<r P ~
- sn u g - c a
9 b
- te sa O
t t
~
N q 9 Fs.emi- 2. E sF Powaw h veiaun.c 120 KV ot15tTE 3 d ' "' #" 625 WESIES D'V'5'0"T D ' *"T g 83 8M 4% g ii 12. 83 34 mM
- ... .. -s
) )
l f swa. ws l) I
)
I kl T n m
? I l I
,,, w ,es 4
/
l - l l l NRC - DETROIT EDISON MANAGEMENT MEETING TO DISCUSS EMERGENCY DIESEL GENERATOR ISSUES GLEN ELLYN, ILLIN0IS FEBRUARY 14, 1986 11:00 AM d 27
EDG TEST PROGRAM (RELIABILITY DEMONSTRATION) PURPOSE: SIMULATE FUEL CYCLE d INCLUDE 168 HOUR ENDURANCE RUN TEST ENGINES: EDG 11
! EDG 13 i
DEMONSTRATION SEQUENCE: BEARING SEASONING - 100 HOUR RUN MIN. BEARING GAP CHECK 20 SLOW STARTS BEARING CAP CHECK
- 10 SLOW STARTS BEARING GAP CHECK i ENDURANCE TEST - 168 HOUR RUN I
l
I EDG 12 OIL DILUTION . OIL DILUTED BY FUEL OIL 49 FUEL OIL TO LUBE OIL B0UNDARIES 24 FUEL INJECTOR N0ZZLES (TESTED) 24 FUEL INJECTOR PUMPS 1 MAIN FUEL OIL PUMP (SEAL REPLACED) LUBE OIL CHANGED TO MOBILGUARD 450 (DUE TO SHELL OIL FOAMING) EDG 14 OIL DILUTION i i RESOLVED BY CHANGING OIL 1 + e
a 4 - h 8 9 e e EDG 12 PISTON OIL RING SEGMENT
- FOUND ON UPPER OIL DECK NEAR #10 CYLINDER PIECE NOT MANGLED UPPER PISTONS REMOVED IN JANUARY 1985
#9. PISTON REMOVED IN DECEMBER 1985
, CHECKED UPPER PISTON OIL RINGS NOT A BEARING CONCERN 1
l EDG 11 OIL FOAMING OBSERVED INITIALLY ON START FOLLOWING FLUSH INITIAL START WITH COLD OIL OIL LEVEL HIGH REMOVED 20 GALLONS . CONSUMES ABOUT ONE GALLON PER HOUR INSPECTED MAIN PUMP OIL SUCTION PIPE SHELL OIL REPRESENTATIVE TOOK OIL SAMPLE
, SHUTDOWN ENGINE AFTER ABOUT 42 HOURS RUNNING OiANGED TO MOBILGUARD 450 OIL SHELL OIL CAPRINUS R 40 (DID NOT F0AM)
CHANGED OIL ADDITIVE PACKAGE . REVISED OIL CAPRINUS U 40 (DID FOAM) MOBILGUARD 450 OIL NOT F0AMING IN EDG 11 PUT IN EDG 12 i ALL FOUR DIESELS l i ii
, . ~ - , - , . , . .
EDG 13 CAP SCREW J
; ENGINE COVER INSPECTION PLATE CAP SCREW (1/2"-13 x 1") !
VICINITY OF VERTICAL DRIVE INSPECTION 4 . UPPER OIL DECK ADJACENT PISTONS VERTICAL DRIVE AREA OIL PAN FEEL DRAINED 8 SEARCHED CAP SCREW NOT LOCATED BASED ON INSPECTION RESULTS ENGINE REASSEMBLED SCREEN OVER OIL PUMP SUCTION DEMONSTRATION CONTINUED I i
+ - - ,--r. .-
, --- a - ,- . , . . , - . , ~ w , , , - -
~
.N EDG TEST PROGRAM PRESENT STATUS (As of Thursday 1300 Hrs)
EDG 11 COMPLETED SLOW START #9 EDG 13 COMPLETED 72 HOURS OF 168 HOUR RUN 4
7 1 I DETROIT EDISON POSITION j- )i SUCCESSFUL COMPLETION OF DEMONSTRATION j . VERIFIES EDG RELIABILITY i GAP OiECK BEARINGS EVERY 6 MONTHS 4 MINIMIZE EDG DISASSEMBLY I l ) l I i [ e d}}