ML20077N463
| ML20077N463 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/08/1983 |
| From: | Baxter T METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE |
| To: | Chilk S NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8309130113 | |
| Download: ML20077N463 (12) | |
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waivan s oinsc7 os Nuwata September 8, 1983 822-1090 Mr. Samuel J. Chilk Secretary U.S. Nuclear Regulatory Commission WasFington, D.C.
20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No. 1)
Docket No. 50-289 (Restart)
Dear Mr. Chilk:
It has recently come to Licensee's attention that the Appeal Board, in ALAB-729, nay have misunderstood the nature of Licensee's plans for installing backup incore thermocouple displays.
As the Appeal Board notes, Licensee had committed to install a backup incore thermocouple display system meeting the criteria of Item II.F.2 of NUREG-0737.
The Appeal Board further assumes that this system is fully safety-grade, except for environmental qualification.
See ALAB-729, slip op. at 146-147, 176.
This assumption is based upon Licensee's response to the Appeal Board's Order of July 14, 1982, which requested a brief status report on Licensee's progress in implementing certain modifications.
Id.
r309130113 830908 DR ADOCK 0500028
a SH w, PITTMAN. PoTTs & TROWBRIDGE A PARTHERSwer 0
- PecorteseOseAL CO#80 RATIONS Mr. Samuel J. Chilk September 8, 1983 Page Two The use of the term "(safety-grade) " in Licensee 's re'sponse was meant simply to distinguish the system mandated by NUREG-0737 from the existing control-grade backup incore thermocouple display system,1/ which is a subsystem of the installed primary incore thermocouple display system.
However, the Licensee is uncertain of the import of the Appeal Board's words " fully safety-grade except for environmental qualification".
The purpose of this notification is to inform the Commission that to the extent the Appeal Board assumed the backup incore thermocouple display system to be seismically qualified at this time, the assumption is incorrect.
By letter dated February 2, 1982, Licensee' submitted to the Staff its plans for complying with the incore thermocouple dis-play requirements of NUREG-0737, Item II.F.2.
See Attachment A.
In sum, TMI-1 presently has in place two separate incore therr.occuple display systems:
(1) a two-part control-grade
. primary display system meeting the criteria required by the Staff and the Licensing B'oard that grew out of the Control Room Human. Factors Review;2/ and (2) a backup system meeting the criteria of NUREG-0737, Item II.F.2., with the exception of environmental and seismic qualification.
As Licensee noted in l
1/
The requirement for a control-grade backup display system grew out of a recommendation from the Staff's control room l
design review (NUREG-0752) of TMI-1 and was subsequently adopted as a restart requirement by the Licensing Board.
See LBP-81-59, 14 N.R.C.
1211, 1306, 1325 (11 867, 913, 914).
Licensee's response to NUREG-0752, dated l
August 28, 1981, described the control-grade display installed at TMI-1.
This control-grade system remains l
in place at TMI-1, in addition to the NUREG-0737 backup display system.
i This display system consists of an input multiplexer which l
2/
feeds (a) the Mod Comp computer and associated printer and
(
CRT display as the principal subsystem and (b) the Bailey 855 computer and associated printer as the backup subsystem.
t
=
l
SH w, PITTMAN, PoTTs & TROWBRIDGE A PARTNERSMep OF pnOFEasecesAL ComponAfiONp Mr. Samuel J. Chilk September 8, 1983 Page Three the attached letter, a program.to seismically and environmentally _/
3 qualify the backup display system is to be completed'by'the Cycle'6 refueling outage.
Respectfully submitted, n
Thomas A. Baxter Counsel for Licensee cc:
Service. List attached
-3/
The description of the environmental qualification of the NUREG-0737 incore thermocouple system'was submitted to the Staff for review.by letter dated May 16, 1983.
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- .. n ATTACHMENT A GPU Nuclear
- F @bj=y I@
P.O. Box 480
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Middlet0wn..-ennsy!vania 17Cc,7 N-717-944-7621 Writer's Direct Dial Numbec February 2, 1982 r.
o> 007
,..,.,. t, w e se m.
ys sa l,1 y\\
its s
' Office of Nuclear Reactor Ec2nlation y%
J\\
Attn:
John F.'S cl:, Chie#
MAR _ "9 ~* d.C
'l-l g A P. P. & 1
- Divisicn of Licensing t
.c >
Operating Reactors 3 ranch No. 4 U. S. Nuclear Regulatory Cc._ ission Q,
tiashington, D.C.
20555 s
x i I ' t \\ d' '
n; e
Dear Sir _:
Tnree l'ila Island Suelear 5:a:icn, ~Jni: 1 (TAI-1)
Operating License Sc. D?R-50 Decke: Sc. 50-289 Incore Ihe=ccouple Display (K!* RIG II.F.2)
In accordance with Item II.F.2(4) enciesed please find our evaluation en the ccnfe =ance of the Incere The = occupies with Ni: RIG C,.:./.
.nis
. evaluation is-supplemen ed by inic=a ica cen sined in :he !!!!-1 Restar:
Report,(2.1.1.'6, Supp. 1 ?ar: 1, questions 17, 39, 39a, 39b, Par: 2
- uestions.93, 95)
~' :=aring_ Record en Inadocua:e cere Coeling, lie:
id latters dated.;ugust 17,1931 (L1L 216) and Cecenber 16, 1981 (L1L 3'.8).
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R. C. Haynes L. Barrett i
R. Jacobs I
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G.:V Nue:sa is a car; cf tne General P :::: '.:'oes Sys:em
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II.F.2.
DES I G4 AND QU AL I F I CAT I CN CR I TER ! A F CR TM i -1 INCORE. THERM 000UPLES
= (1)
T h erm0 coup l es located at the core exit for each core cuadrant, in con.iuncTien with core in le? Temper aTure data, shall be of sufficient number to provice incication Of radial disTribuTien of the c clanT entha!;y (Temperature) rise ac ess representative regions of Tne core.
rower 4istribuTion symmetry snculd be censidered when cetermining Tne specific number anc location of Thermccouples to be provided for ciagnosis c4 local core pecclems.
'C" "
See TMl-1 Restart Re: Ort 2.1.1.c and SER (NUREG OSSC of June 16, 1950 Se: Tion 2.1.3b).
- (M Tnere sneuld ce a crimary coeraTor cisplay :cr cisplays) naving The capa:iliTies wnicn follow:
(a)
A s; aria!!y 0.-!? entec c re ma: availa:!e :n cema,c incica-ing The Temperature or Term eraTure ci f f ere.ca across -he core a-each : Ore exi-ine....
y Ie lccaTion.
(b' A sele:Tive reading of ecre exit Tempera u e, con-inuous on cemand, wni n is cens i sten? wiTn parameters pertinent to operater a:Tiens in connecting wi n :!an -scecific inacecuaTe terv : eling procecures.
0.
example, Tne a:Ticn recuiremenT and Tne displayed Temperature mign be eirner Tne nighes? Of alI operabie Tnermo Oua 1es er The average Of five nignesT thermoccupies.
(c)
Di. rect reaccur and hard-copy capability snoulc be availaole for all therme:Ouple Te=ceraTures.
Tr.e range should extend from 200 F (c.- less) To 1800 F (c. more).
(d)
Trend capabibiliTy showing ne tempera ure-time history of representative Ore ex?
Temperature va!ues shoutc Oe available on cemanc.
e (e)
Appropri ate aI arm capab i l iTy snou!d be previ ded consistent with cperator proce:ure requirements.
(f)
The operator-dispIay cevice inTertace snaIi be human-factor designed To provice rapid access 70 requested displays.
Atta nment 2 provices the ecmputer functions involving the incere
- ce s.
inermoccup!es.
C W A backuo display (or displsys) should be provided with the capability 4 from for selective reading of a minimum cf 16 cperable. nermecouples,
~ each core quadrant, alI within a Time interval no greater than 6 minutes.
The range should extend frem 200 F (or less) To 2300 F (or more).
n.
,f' R'spons9 The 3 ckup acors Resdout systes 'is ce=pesw of 16 salacted incore thsr=icouples ce= prised of 4 in each core quadrant -etpable of bain3 read in 6 =inutes. er less by an operator.
Tha range =enitored will ba o
o frem 200 F to 2300 F.
(See Figure 2)
Item-(4)
.The types and locations of displays and-alar:s should be deternined by perfor dng a-hu=&.u-factors analysis taking into consideration:
(a). the use of this inf or=ation bv, an operator during both nor=al and abno =al plant conditiens, (b) integration into e=ergency precedures,
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(d) other alar =s during e:ergency and need for pricritizations of alar =s.
Restonse
'A hu=an fac:c engineering revise has been perf ormed f or :he incere thermoccuple d' splay syste=.
Frecedural integra:icn and training is discussed in the IKI-l Res:ar: Ecper: Sc;;1e=en: 1 ?ar: 1 Ques:1cn c:
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I:e= (61 The pri=ary and backup diselay channels should be electrically independent, energi:ed frc= independen: sta icn. Class II power a.--.d-...a.
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The pri=a y display and associated hardware beycnd the isolation device need not-be Class 1E, but should be energized frc= a high-reliability
- power source, ba::erv. backed, where =ccentarv. interrup icn is no:
clerable. - The backup display and associated hardware should be Ca. ass 1.
Easr:bse The pri=ary and back-up display channels are electrically independen:,
separa:ed (lE O. cr:icn) are energized frc: independent power suaplies.
~
e The eri=arv. disn. iav. channel utilizes the lant redunden: cc=ruters,cne of which is supplied frc= an on-site ba::ary backed power source and the other fre= a 'scer,ce: backed by the diesel generator but which is not a qualified lE source.
The back-up display channel is energi:4d f:c=
Tne back-up display and associate'd hard-an on-site, lE power scurce.
ware will be ce= prised ultinately of qualified lE equipment, or-The diesel genera:cr supplies back-up power elec:rically isolated.
for the =od ec=p.During a loss of power, he calculationsperforned by This the ModCc=p are not available un:11 the diesel restores pcuer.
will be a relative short period of ti=a and incere ther=ccouple readings =ay be cbtained frc= the 3ailey S53 during this period.
1 The instrumen:stion should be envirc==en: ally qualified as described in
- I:e= (7) that seis=ic cualification is not recuired Appendix 3, I e= 1, encep:
for the.pri=ary and associated hardware bayend the isolator /inpu:
buffer at a l'cca:icn accessible f or =aintenance follering an accident.
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m portion of Th3 diffic.ulty in 3 ding this rcquirenent is caly for th::(sensC:s Cabling) in that Rascon the system that is inside :he CCntainnent has to be qualified to tenperature, pressures, radiatica (norna117 cualified life plus nes: severe D3A) and expeCred over the equipnen Te are Currently planning for the affeC:s of. Chemical spray systen.
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The quality assurance provisions Ci:ed in Appendix 3, iten 5, should be applied excep for the prinarv. disc. lav. and associated hardware I nn (C) beyond the isolation device.
scall be in aCCorcance v :n :ne u?L.
n c.ssurance rec.uirenen:
Acceptance resting of the
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.Incou Th rm ccupla-Display Comput:r functions
- Tne desired computer functions involving the incere te=perature the=noccuples are as follows:
1.
Dete=ine core exit thermoccuple te=perature by averaging the five highest valid incere the=ccouple readings.
The operator can ec= pare this result with ?.igure 1 to dete cine if an ala= cendition exists.
- 2.. Produce ::end plot of cere exit the=occuple te=pera:ure as dere=ined in #1 versus ri=e.
.3.
On de=and display + readings of all incere the=occuples and have the option :o delete any =alfunctiening :he=ccouples f:c: being used in anv. calculatien.
- l..
Cc= pure te=perature saturatien cargin based on the average of the five highest' valid incere thermoccuples and ala= a: less than 20 ? =ar-in.
e 5.
Dete nine mean cere exit the= occur. le te perature by averagins. all of the va'_id incere ther:occuple readings.
S.
Dete=ine reactor vessel dernce=er re perature vi h no RC pumps rt=ing
-. a
- a g..a n e
. 4
_1_2;
.e. o r e
_.%..e _ _ n.cn._.1 -=
.a_pg.- e.a.
e,,.-...._._,,,.,_<.n
_ u.. - _2 2.r a.
n e _e.
e.
oc e
.3 and cc pare this value to satura:icn te=perature a: :he curren: RCS pressure.
c If the average the=occuple reading is =cre :han 100 ? subeccled then p;in:
an ala=.
7.
0: de==-> d'eplay a list of the tin':u= se: cf 15 incere the=occuple readine.s. fcur t.er c.uadrant.
a.
v.. u.a.ae a g< g2.,...n.,s j c...a.
. a_-
__s <_,.-..
_s.u se c_= _a_...a.
e.
the pecouples-have =alfunctioned based upc
- he=occuple validity cri:eria.
r..._.__.._<-,,,
4 _<__._
n,._< es _: o,.._ e c a ck....,,
sy.s.,_..e__s _,
m.-_
Is c.3.- _._e se..
n
.w v
the feature since direct centinui:y checks canno: be perfo=ed due ::
required isola:icn devices.
9.
Previde an optien :o substitu:e any pre-selec:ed alta= ate incere the=c-
...e.
,_ou,,a_s
...a.
e.
coup _3e.:o, any. c.,
. e ___<_<__._ se_
w r_
10.
A trend plo: of any :he=occuple reading versus :i=e is provided f::: the
,me c: :ne
_,a anc :c:varc.
- _ ace.
e
_.y..
g
.a,, _a_<__
gg.. c. _.e..a.
- v..c..a g e..- r. c > _a_.,.. o ea, a_,..
the=occuples if :his became necessary due to ultiple failuris during
~~
operation.
12.
Provide a spatially oriented core cap en de=and indicating te perature across the core at each core exit ther:ccouple 1::a:icn.
A core =ap of all incore :he=ccouples is planned for la:er 1982.
- 12. J.llow prin:ing in hard copy of any data displayed.
(Range of 200 F
--2300 y.)
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.6
.. 6 UNITED STATES OF AMERICA NUCLEAR REGULATORY CO2EISSION In the Matter of
)
)
METROPOLITAN. EDISON COMPANY
)
Docket No. 50-289
)
(Restart)
(Three Mile Island Nuclear
)
Station, Unit No. 1)
)
SERVICE LIST Chai= an Nunrio J. P=11=di m Dr. Regin&ld L. Gotchy O.S. Nuclear Pagulatory Ccr:rcission Atcmic Safety and Licensing @ eal Washing a, D.C.
20555 Scard Panel-U.S. Nuclear Regulatory Cct:rcissicn r=
miasicner Victor Gilinsky Washington, D.C.
20555 l
U.S. Nuclear Pegulatory Ca missica l
Washingten, D.C.
20555 Ivan W. Smith, Esqui.,e c524 - n reissioner James K. Asselstine Atomic Safety and Licensine Scard U.S. Nuclear Regulatory Cor: mission U.S. Nuclear Regulatory CadrEi.ssion l
Washington, D.C.
20555 Washington, D.C.
20555 t
Camissicner Frederick M. Bernthal Dr. Walter H. Jordan c
U.S. Nuclear 7egulatory n,miasion Atem1.c Safety and Licensing Scard i
Washington, D.C.
20555 Panel 881 West Outer Drive Catnissioner 'Ihemas M. Roberts Oak Ridge, Tennessee 37830
- U.S. Nuclear Regulatory r e irsion Washington, D.C.
20555 Dr. Linda W. Little Atcmic Safety and Licensing Scard Docketing and Service Section Panel Office of the Secreviry 5000 Bermitage Drive U.S. Nuclear Regulatory C e iasion Raleigh, North Carolina 27612 Washington, D.C.
20555 James M. Opchin, IV, Esquire Gary J. Edles, "Ei{ dire"~~
Office of the Executive Iagtl Director U.S. Nuclear Regulatory C = iasion
~
~'~~ ~
Chairman l
Atcmic Safety and Licensing Appeal W==hington, D.C.
20555 l
Board U.S. Nuclear Regulatory C e iasien John A. Levin, Esquire Washington, D.C.
20555 Assistant Cbunsel Pennsylvania Public Utilty C=ission Dr. John H. Buck P.O. Box 3265 Aterric Safety and Licensing Appeal R= M ahurg, Pennsylhnia 17120 Board Panel U.S. Nuclear Regulatory Cc: mission
- Douglas R. Blazey, Esgaire Washi p, D.C.
20555 Chief Ccunsel Decart:nent of Enviremen+-=1 Rescurces Sli Executive House, P.O. Bex 2357 Harr M' Pennsylvania 17120
,-v r-w.
m...w-v.-r 6--.
,c-
-,,,.-.e,,--.w--
w F
.iN*b, *-
Jordan D. Cunninghan, Esquire 2320 North Second Street Harrisburg,_ Pennsylvania 17110 Ms. Icuise Bradford UMI AIERT 1011 Green Street Harristurg, Pennsylvania 17102 Ellyn R. Weiss, Esqu2.re Harmon & Weiss 1725 Eye Street, N.W., Suite 506 Washington, D.C.
20006 Steven C. Sholly Union of Concerned Scientists 1346 Connecticut Avenue, N.W., Suite 1101 Washington, D.C.
20036 MGE/IMI PIRC 1037 Maclay Street F^ N " %,_ Pennsylvania 1,7,103 William S. Jordan, III, Esqture Harmon & Weiss 1725 Eye Street, N.W., Suite 506._
Washington, D.C.
20006 Chauncey Kepford Judith H. Johnsrud Envi m n=ntal Coalition on Nuclear Power 433 Orlando Avenue State College, Pennsylvania 16801 Marjorie M. Aamodt l
R.'D. 5 i-Coatesville, Pennsylvania 19320 l
l I
-