ML19253A502
| ML19253A502 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/11/1979 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909100168 | |
| Download: ML19253A502 (23) | |
Text
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UNITE D STATES
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NUCLEAR REGULATORY COMMISSION n
' 2_, I o WASHINGTON, D. C. 20ss5 hL
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- f May 11, 1979
)
e MEMORANDUM FOR:
Victor Stello FROM:
Briar K.
Grimes SU3 JECT:
TMI DAILY REPORT A.
React 7r an Plant Status d
1 Technical Pr7gress Meeting - see Attachment i #
7r acenda and notes.
2.
5" stem Parameters and Core Mao - see Attachments ' and 3.
3.
Tes t s and 0,e ra t i ons in P-7gress - took pressurizer solid # rom LOO psi on 9/11/79.
Pressure was increased to 690 psi a-c reactor will be keot solid #,e at least two more days to make leak rate checks.
The vdro on JHR 1000 3 on 5/1;'/79 was
.a n s u c ce s s #u l cecause leakace out o# FE-2 (#17w e l ement) #!arge
~
was Found at 73 osi.
4 hen balts. sere tinh*ened the #iance
- a:es were c ound to be distorted (h71ts "ad been certi H
3 in-nd t7 h50 foot - be#,re gasket and #!ange bolts were ran?a J)
Tiange area was isolated and svste, hvdroed at '33 osi (minor leakace #ro-cumo drains was F'xed faring this
,r, 2dar3).
Uben valves were 70enec to #1ance run, nressure quick!", fix
- r7,ned to 73 osi, indicating on-sol i d con-17 tions.
Eccorts t B
1000 are continuinn wit" a caralfel effort t,
test and use the A loop for the contai ment sunn level test.
D 0
4.
Long term pressure control, Wil son, GPU, aresented recer-endat ion to continue with bubble in cressurizer wi th solid oceratior and L.s L.s other options (see Attach ent 4) as backup.
'ecommendat ion
~
- d " g h3 g
adooted bv stacring grouo.
-(0]-
Q ie i
T"e Mav and June GPU staf#ing at t"e site is in attacn e-*
5 ss This is a substantial recuction o# o,-site #arce, out :e same succort activities will continue at the GPU 2s.
6.
iater distnarges - in'7r-ad at I'L'
"';rc.
'O,
- - = * *
"avor of Lancaster is seeking a,reli i arv i-j;,cti-- aga:
c-anv #urthe-releases t7 t'e I,ar-
" ark 'n,use (7I? 7-3'
F 717-6F2 '23" "o,e) :311 e. this.,7eni g to reau3c-7#Fice 7r a eet inc 3 Ste117 or w cever is
?, :0m and wi t '~
"e 'b eer v at 'I31 M7nday.
I CalIed JaOk
- "I s a#ter977n t,
sav 14 onu I attend, aat aro')aalv not ^ tel?7, n,;se saaceste3 als- ~a"'
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7 ail: a#'airc oco7'e - ese,t.
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Victor Stello May 11, 1979 3.
Radwaste and HP 1.
Primary coolant sample was taken en 5/10 at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />.
Results S
o# the analysis are attached.
e 2.
Meted has established a schedule for sampling the crimary and secondary systens.
The schedule calls or d rawi ng a p r i-a rv 8
f coolant sanole every Thursday morning and a containment air sample every two weeks.
3.
All scent charcoal filters have been removed from the Aux Building and stored in trailers at the south end of the site.
4 EPICCR !! is screduled for pre-op testing on 5/16, however, this would slio due to pr,blems in cetting the area cainted.
5.
Ta n k 'a r, is proceeding on schedule.
sustems should be h"de, tested over the weekend.
Transfer pumo should be installe1 todav.
6.
A3/FHS 'ilter systen should be turned over to ocerations on 5/14 Tie-in to emergency diesels was not co aleted on schedule due to oroblem with diesels.
C.
Envir,rmantal Measurn ents NRCgroundsurvevdatashowedal([-}'andh' level I.
s at 1 12 mr/hr.
2.
Sample of goat m i l '< ' c om #ar,on east side of river analyzed by NRC, showed L-131 level of 12 oCi/1, Grass sampics at !"e 2
goat fa rm ( 6E-5/4 Ci/m 1-131, 3.
Air sample results at various 17 cations around site rangea # am (9. 7E-12 to ( 5. ]E-12so Ci /mi 1-111 L.
Release data are provided by Attacb ents 7 and 8.
Al',trer Federal Agencies renorted no pas,i t : ve envi ronmental results.
/
/
7 3rian K.
G-i es Attacb ents
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3.
Eisenhut G. Smith, IE r73 r73 1 Vo11rer G.
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Gri es G.
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/ TTACHMENT t
.. e A G E '! D A TECH'TICAL L'ORKI"3 GRTJP 1303 5/11/.
l.
Radiosctive Release a.
748, 219 Auxiliary Building Fans b.
Vent Header and Drain Trunk c.
Dore Radiation Monitor - no new inf,r ation.
d.
Measuremant of Radiation Level Inside Containment
+
t 2
Plant Status a.
RCS Profile
.~
b.
Plant Operations Schedule DHP ' B ' Leak Te s t - probably next week t,
fi-Cycle DHV n roaaal v Mondav ir 1,o, A leaktig"t.
DHP ' A' Te s t - ederway, c.
Duration of solid operations r ew days.
3.
RCS Samle Results, - '7th i ng unusual.
4 Pressurizer Solid Oa2 rations a.
Lmak Rate Deterr.ination - apnears to be about i on out will cet i,-cer ie
+
b.
LT-3 Response -
easurement - w a!s, chance a;eu,,. r,,.nd tale considered ir,,e ante,
'eak rate.
5.
Construction Status Estimated Co,olecion, c.
Tank Farm 5/16 b.
'B' Longteru Coaling 5/15 c.
EPICOR (CAP-GIT.! II) 5/18 d.
RCS Pressure /Voltr:e Control turnover for testing 5/14 e.
Aux. Bldg. Roat Ventilation Ft.ns Full availability done (5f1C)
System Complete 5/13 f.
Aux. Diesel Generator 1 (grey) 5/11 2 (uhite) 5/12 g.
Alternate Decay Heat Removal 6/1 P00RORGINLI.
t a
/hTmHMatT 2
e PILEASES 1100(5/9/79) 1100:5;197 9:
1100(5/11/79)
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4.5 x 10 9.8 x 10 Train #1*
Not Runninc No Runninc Train #2*
Not Running LMD
-12 Train #3=
2.2 x 10 6.5 x 10- 2
- l ~'
Train #4*
Monitor 00C 2.1 x 10 12 hr. Cartridge Readings REACTOR COOLA';T SYSTEM PROFILE PLANT STATUS 1100(5/9/79) 1100(5/10/791 1100(5/11/79) o n
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12.S 72.3 12.5 73.8 Tstr 159.8 131.7 153.3 131.2 P2R LEVEL Cal.
358 364 D'v'M not taken not taken LT-3 274.3 282.2 R.C.
Press 660 485 S/G Level 408" 942 415" 94i Turb. B/P 841 Closed 841 Closed I. C_. m..
3, o,. 4 o
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195.08 195.1
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A WACHM874 Inter-Office Memorandum I r-May 10, 1979 W j. SerVDCe
- r +: Long Term Reactor C0clant Syste: Pressure Centrol
'c R.
C. Arnold
_ccrc" Three Mile Island 7
?:
The current plan is to take the reactor pri=ary system down to a pressure of approximately 300 psi for long ter: (2 - 4 + :onths) natural circulation.
Th s pressure is preferred since it does not cause additional gas to be r e --
drawn..: rom the control rod drives and provides a ple =argin on incore therro- !
couple T le all probability, the reactor coolant system te=perature will 37,.7 also oe held a: its approximately current value by periodic throttling of the condenser bypass valve.
During the 2-4 or more months that the reactor is expected to be on natural circulation cooling, there are five potential options for pressure control.
These include:
1.
si the pressurizer with a nor al vapor bubble.
2.
Taking the plant solid and controlling through makeup and letdown.
3.
The new pressure volume control system.
Floating the plant on core flood tanks.
4.
5.
Floating the plant on the low pressure injection pump discharge.
The sixth option, letting the system pressure drop to atmospheric, is not viable in the near ter=.
The attached table summarizes sc e of the pros and cons of the various alternatives.
It is recommended that pressure control be maintained through normal pressuri er s '
'c heating with a vapor bubble.
This recommendation assumes that current efforts to retain / restore heaters will be successful, that solid operation will not show a marked change in syste: leak rate and that syste =akeup and letdown can be secu:'d after periodically taking the pressurizer solid and letting the syste drift down on leakage.
On going solid, P r level can be obviously benchmarked.
In the event that unforeseen problems or other restrictions prohibit operating tne pressurizer in the normal mode, it is recommended that the first fallback posttien be to take the plant solid and maintain pressure through normal makeup anc lerdown (assuming valves. pu=ps, etc. permit).
The second fallback position o
C?U 59*.~Ce Cc CCr3"O'1 3 Lt3:2 3'v O' 3d"e'a' R..t C U.
90 CC'07ryc"
~Arr +
Long Term Reactor Coolant System Pressure Page Two should be use of the new pressure volume control system.
Floating of the core flood tanks or the low pressure injection pumps should be considered as f rther fallback positions, although neither of these systems appear to be technically unacceptable.
R.
F. Wilson. _ _ _ _ _ _ _.
RFW/a1 ATT cc:
J.
C. Herbein L. Pletke - B&W E.
G. Wallace D. Vollmer - NRC J.
P. Moore M.
P. Morrell E.
D.
Elam G. Kulynych - B&W g
O
I a
l.ht.G 16111 N t ACIDH 0)oIANI M Silli IHt'SSUFF O miFlit.
list Of lit t F F t S 5l.lil 7t H I Af !!!G l HL l'lA!.I sol lb Al.D IJLW l'lILS50kE Vol t t!F CONIROL t ! OA t llE lilE l'iAN T ON l'! OAl t hG 111t. l'! A? I ON lilE Wi1H A teoHtAI. VAITR B t filB l.E u ml kiit !. i t.G liikutN.it itM t.Up S Y S i t ti Coke f t (x)D T AM~S 1.OW P h t S sui' t IHlff!!ON AND I El[n MN FlHP plSCHAL E tt;D AlWANIACL5
{
N.smal gfant operesting
' System ha teen demonstrated System completely r edu n.t an t System basically P.assive Uses installed plant n o.le
- ma x i. nom agesator enceir for mekeup of flooj equipment familiaalty titi t r ical heater s not System ac c e s s i t> l e for tank water s e piir ed mainten<ence System is reduadant
%y. tem w i t h vi.po r ho l> l. l e I
System is t e landan t - no j uses normal plant modi f icat ions r equir ed is turgiving an! has a los I i m <- response ieqqipment Fes mit s adetaate boron Ir.bam rare is p r ol,a b l y no
.Prgtet ts against up and down control worse L I.a n any oil.r a
' pr es sur e transients f
..ystem No l'z t chemistry problem Hi ragability of taking prissare opsunge as well as downsorye low pr es sor lier level heater l
d l.9I m t jr(H$t ana$ al,i I it y tu trarb level lents g
conftarore Chemistry control in j
pr..surtrer adequate t
_.DI$ADVANIAttS:-_
i Hequires some heater Constant operator attention i:ew system, probably a lot Reactor system must be Maxinmm pressure is PM capability - pr ot,ab l y r equ i r e.1 of bogs, and will require solid ag }-r ox ima t e l y 175 psi
~
200-1so kw extensive operator Response time r e qui r e l pumps Il t hrust pressure high pr essure over-protec-reautres continuous and valves on a praloJic t ransient s art a ntuated System provides protection tion, must still rely on operation of pump-I against pressure loss, 1,u t cole safettes.
1.ast, large preuore tecakIm.n Pequires almsjst cor.t inuoas over pressure protection Iwray heat removal "peration oa' rycling of still by primasy and code Adjustment of system train is univillable a<ross valve may c aus.
wear-out unless mabiop macup pumi s and letdown rm. l e t i e s.
,p piessure possible 1,ut and trtdewn pe r io.lls all y C
,, f, p3 awkw ard High s ee i s ( u l.a t ion W -
ilow 3CNulted "" the scruted.
Active compvoeuta contaetuated*
'pH k
maintenarue may t,e i mp r.u t i c a l p on.p u.
Seruses seal injection flow Upsets cause w at er uraing Chemit al addition ot her than c
)
boron must be dune through to rea< tor contant pomps f r r.m pressurizer to main 9
. toolant luop, msy rause makeup pump nat ur al c it r ulat ion upsets.
I l
.tinite possibility of p'
U(p
)
S a a.e conrern wit h lo"K nitrogen in kction intu t i s,e reliability Joe to the primary coulant system; I /,
high pressure breakdown O
y howe ve r, possibility is (f
aeross valve anj wear out
/
sisill in ab senc e of I.oCA w
.....a
. 1
Arrnannenf~
Inter-Office Memorandum Ca:e May 8, 1979
?@ Service
~ - ' "
Suwt Cn Site Manning Recuirements To CPU TECH SUPPORT GRCL'P
,_a n:. c.,
TMT
-1 Tae attached schedule projects the manning required by our group on site
-4 at TMI-2 over the next two-month period.
Most of us will be able to return j
to Mt. Lakes and begin the efforts required to assist Met-Ed in bringing
- -- Unit 1 back on line as well as the long term restoration of Unit 2.
The
~ ~ ~ ~ ~ ~ ~ ~ ~ ~~
current ef f orts in Unit 2,~however ? will'Fegtiire that -some Servi 5e' Cdrp.
personnel return to TMI from time to time.
This manning schedule outlines i
what efforts are still required on site at Unit 2 to monitor and assist in Reactor Operations. Additional support requirement to the near tern Radwaste effort on Unit 2 is still being finalized. The schedule was developed to be as equitable as possible to all employees and still assure the requisite capabilities are available to Unit 2.
This Support Group will be centralized in Trailers 106, 106A, 106B, and 202, with the exception of those required for the Control Room.
I
\\
R. F. WILSON RF.J:=s Attachment t
cc:
R. C. Arnold n
L' GPU Sea.< ce Cercora: on.s a su:M o v 3:-va 02: Ut t t cs Cercorr c-
l l
I i
TMI ON-SITE
}
CPU TECll SUPPORT (After May 12, 1979) i MT. LAKES I
e I
l l
s i
i CROUP I.EADER I
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CONTROI, itOOM OPEl(AT1011S ENGINEEltfNG DATA SUI' PORT ANAI,YSIS SYSTEMS REDUCTION e
h i
I-5 H se
...k se
. en
I e
CONTROL ROOM i
WEEK OF:
MAY 13 MAY 20 MAY 27 JUNE 3 JUNE 10 JUNE 17 (Seven days per week)*
7:00 am - 7:00 pm(I)
E. Wallace C. Mascari C. Staudt T. Fischer P. Walsi 7:00 am - 5:00 pm A. Easly E. Barr D. Cowdrick R. Fenti J. Abramovici 5:00 pm - 3:00 am R.
Fenti J.Abramovici D. Ilarcus A. Easly E. Barr I
t 6
(1) Requires week to week turnover overlap i
- NOTE:
Those individuals working a seven day week will be entitled to two days off prior to their reporting back to the llome office in Mt. Lakes.
i w.1 ex
... i.
...h. is
.u
i CONTROL ROOM l
l l
i llEEK OF:
JUNE 24 JULY l JUIX 8 JULY 15 (Seven days per week)*
l I
7:00 am - 7:00 pm(l)
M. Morrell C. Broughton E. Itallace C. Mascari 7:00 am - 5:00 pra D. Cowdrick A. Easly E. Barr D. Barcus i
5:00 pm - 3:00 am D. Barcus R. Fenti J.Abramovici D. Cowdrick 1
(1) Requires week to week turnover overlap
- NOTE:
Those individuals working a seven day week will be entitled to two days off prior to their reporting back to the llame Office in Mt. Lakes.
E c
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6.
.... is
. as
i j
li ENGINEERING SYSTEMS l
l i
WEEK OF:
MAY 13 MAY 20 MAY 27 JUNE 3
.]UNE 10, (Five days per week) 8:00 am to 5:00 pm Groun Leader J. Moore J. Moore B. Elam 11.' Elam J. Moore t
Mechanical Systems L.
Zanis L. Zanis M. Kostrey M.'Kostrey L. Zaats N. Dye (GCA)
N.
Dye (GCA)
N. Dye (GCA)
N.! Dye (CCA)
N.
Dye (GCA)
C.
I.c hma nn G.~Lehmann T.
Lu fb I&C R. Chisholm R. Chisholm A. VanRiper A. VanRiper R. Chisholm Electrical B. Can B. Can J. Torcivia J. Torcivia B. Gan Drafting / Designer D. Valleau D. Valleau J. Snyder J. Snyder D. Valleau Project Engineer J. Langenbach J.
Langenbach T. Collan T. Golian J.
Lang'enbach i
C_lerical/ Secretarial J.
Drescher A. Longo J. Rebhol:
J.:Drescher M. llornick c
R. L7HTZ-Procedures P. Deltete(1)
I g,.M A u S B. Behrle
- B. Behrle Rc
- F.Mnus
- x.. Jc
- u. Tunael in. Tundel G. Ravas:
.' s P. Boucher P-Boucher 1
F. Kiraly(CE) l R. Ryan(CE) j (1) Through Wednesday, May 16 I
- h. '
- n
.s.t. st n
!I!!
E'4GINEERING SYSTEMS f
I i
WEEK OF:
JlltJE 17 JifNE 24
.IULY l l Ill.Y 8 JULY l5 (Fiv2 days per week) 1 8: 00 am to 5:00 pm i
I Group Leader J. Moore li. Elam B. Elam J. Moore J. Moore Mechanical Systems L. Zanis M. Kostrey M. Kostrey L. Zanis L. Zanis N. Dye (GCA) fl. Dye (GCA)
N. Dye (GCA)
IN. Dyc(GCA) fl. Dye (GCA)
T. Lu G. Lehmann G. Lehman;r l T. Lu T. 1.u I&C R. Chisholm A. VanRiper A. VanRiper
{ R. Chisholm R. Chisholm Electrical B. Can J. Torcivia J. Torcivia B. Can B. Gan Drafting / Designer D. Valleau J. Snyder J. Snyder
,D.
Vallcaa D. Valleau Project Engineer J. Langanbac.h T. Golian T. Colian J. Langenbach J. Langenbach A.LQKs?
- 3. Rugnott M.Howsct R.l> % o Clerical / Secretarial
. L-b 1 ' :..Lc J.
J. Drescher
.uuu P
.m uov u R.Lwrc Procedures C
R. Lentz R.
Lentz l G. Maus G. Maus G. Ravanz P. Boucher P. Boucher G. Ravasz G. Ravasz M
s D
(CE) y 9-i I
e p 6.n d
1,
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t i
a l
l DATA REDUCTION l
I
}JEEK OF:
MAY 13 MAY 20 MAY 27 JUllE 3 JUNE 10 (Five days per week) 8:00 am - 5:00 pm CROUP 1.EADERI E.
Schuler E. Schuler D. DeMaio D.
DeMaio E. Schuler i
CLERICAL
- 11. Kistner (S&W)
- 11. Kistner (S&W)
N. Kistner (S6W)
N. Kistner (S&W)
N. Kistner (S6W)
Coding & Filing M. Costello(S6W)
M. Costello(S6W)
M. Costello(S&W)
M. Costello(S&W)
M. Costello(S&W)
Cl.ERICAL J. Christy J. Christy J.
Christy J. Christy J. Christy Data Pick Up 6 Distribution I
i 1 - J. Weiser or R. Locke will be required on site 1-2 days per week.
6 s
?l S
T l
. i.
.i.
I Ij i
l DATA REDUCTION WEEK OF.
.1UNE 17
.IllNE 24
.IULY l
.Illi.Y 8-l
.JilLY 15 (Five days per week) 8:00 am - 5:00 pm b
1 GROUP LEADER C. Schuler D. DeMaio D. DeMaio E. Schuler E. Schuler i
CLERICAL N. Kistner (S6W)
N. Kistner (S&W)
N. Kistner (S&W)
N. Kistner (S&W)
N. Kistner (S6W)
Coding & Filing M. Costello(S&W)
M. Costello(S&W)
M. Costello(S6W)
M. Costello(S&W)
M. Costello(S6W)
CLERICAL Data Pick Up &
Distribution 1
.I. Weiser or R. Locke will be required on site 1-2 days per week, M
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C. R. SKII.12iAN Free H. J. Bell set asu Cust.
File No.
WI-2 or Ref, i
SAMPIE ANALYSES h 11, 1979 (1135) l m...
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THE ANALYSES FRedi THE PRESSL*RIZED RZAcr03 CCOLANT SAIFLE TAKEN CW 5/10/79 AR3 LIST 2D BEIA7J:
CA3 A:ALTSE.S Total Gas 5.1 CC/KC Sydrogen 4.1 CO/KG Nttregen
<1.0 CC/EG D
D QO Orygan MOT DETECTED n'
0 3_T Ie-131s 1.13 pC1/CC
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Ir-133 0.08 pCI/CC I-131 0.01 wCI/CC LIQUID ARALYSES noROW 3032 ps p3 8.10 I-131 390 vCI/CC Ca-134 41 pCI/CC Cs-136 10 pCI/CC Cs-137 190 vCI/CC Ba-140 52 pCI/CC 9
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/lin L T1tB A:tALYTICAL RESULTS GIVCf PCR THE LIQUID PORTION 07 TEE SAMPLE ARE COWSIDERSD m TEL3 AND 00ARECT. 11CRE IS, HOWBVER, SOME QUESTION COHCERNING T11E CAS ANALTSES. THE VALVE ltANDLE GET SCKEW3 WERE FOUND TO BE 3
LOO 3B AND SOME TROUBLB WAS DICOUNTERED IM OPENING THE 7ALVES.
IT IS PROBABl.E TilAT THIS CONDITION EXISTED WEN THE SAMPLE WAS TAEEE WICH WOULD CAllSE TTIE
??LVE(S) TO NOT BE SECURELY CLOSED AND RESULT IN SONE CAS LEAKAGE. THE NJMBERS
~
F2FORTED FAY BE LOW WITU THE TRUE SYDid> GEN CONTENT E. M. TUB 4.1 CC/KG REPCRTED AND 18.6 CC/FB (REPORTO FOR TTIE 5/2/79 SAMPLE). A MORS EIACT VALUE WOULD REQUIRE AN ADDITIONAL S/Jf?LE.
VE RECCMMDfD UlAT EACH SAXPLE BON 3 33 INSPSCTED PRIOR TO SAMPLING TO C072ECT ANY DEFICIDfCIES SUC11 AS VERE ENCOUNTE:IED IN THE 5/10/79 SAMPLE, MJ3/dh
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