ML19210B141
| ML19210B141 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/13/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210B140 | List: |
| References | |
| NUDOCS 7911040074 | |
| Download: ML19210B141 (14) | |
Text
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I; e.- 1 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1
~
DOCKET NO. 50-289 OPERATING LICENSE NO. DPR-50 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 6 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY r; ' /
ATTEST:
By
-/
> l' , < . <- J Vice President-Generation Sworn and subscribed to me this 13th day of December , 1974.
$ /'
e .d'.D e ?@ W N . .
Notary Public RITA f.' POWERS Notary PcMt. Muh!eeerg Tnp.. Ceas Co.
My Corr.m.ss on Empires September 40,1978 Cu
-a 306 qqy04001'
,.u- r UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 OPERATING LICENSE NO. DPR-50
- METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. 6 to Appendix A of the Operating License for Three Mile Island Nuclear Station, Unit 1, dated December 13, 1974, has this 13th day of D ecember been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and Dauphin County, Pennsylvania by deposit in the United States Mail, addressed as follows:
Dr. Edward O. Swartz, Chairman Mr. Charles P. Hoy, Chairman B oard of Supervisors of Board of County Commissioners of Londonderry Township Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, Pennsylvania 17057 P. O. Box 1295 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY is .
By - _h4' 'c.
Vice Prdsident-Generation 1586 ;07
i MEIROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 8
f DOCKET No. 50-289 '
OPERATING LICENSE NO. DPR-50 TECHNICAL SPECIFICATION CHANGE REOUEST NO. 6 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1. As a part of this request, proposed replace =ent pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY ATTEST:
By /s/ R. C. Arncld Vice President-Generation Sworn and subscribed to m this 13th day of Decenber , 1974.
/s/ Rita M. Powers Notary Public 1586 308
UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSION -
IN THE MATTER OF DOCKET NO. 50-289
' OPERATING LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request
- No. 6 to Appendix A of the Operating License for Three Mile Island Nuclear Station, Unit 1, dated December 13, 1974, has this 13th day of December been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and Dauphin County, Pennsylvania by deposit in the United States Mail, addressed as follows:
Dr. Edward O. Swartz, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of County Commissioners of Londonderry Township Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse hiddletown, Pennsylvania 17057 P. O. Box 1295 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY By_ /s/ R. C. Arnold Vice President-Generation 15u6 509
UIREE MII.E ISLAD NUCLEAR STATION UNIT 1 ,, ; 4 Ol'ERATING LICENSE NO. DPR-50 DOCKET No. 50-289 Technical Specificatica ~hange Request No. 6 Licensee requests that the following changes be made to Appendix A of the Technical Specifications. A copy of proposed changed pages marked
" Change Request No. 6" is attached as Enclosure 1.
Page 3-3, Specification 3.1.2.3: Change "100 F/h" to "100 F in any one hour".
Page 3-4, Para 1, Sent. 3" Change "100 F per hour" 'to "1000 F in any one hour".
Page 3-4, add following paragraph between end of first and beginning of second " Bases" paragraphs:
The heatup and cooldown rate limits in this specification are not intended to limit instaataneous rates of temperature change, but are intended to li=it tu:perature changes such that there exists no one hour interval, or sub-interval thereof, in which a tempera-ture change greater than the limit takes place.
Page 3-5, Para. 2 : Change "50 F/hr" to "50 F in any one hour".
Figure 3.1-1: Change " F/hr" on abscissa of graph to " F in my cne h our".
Figure 3.1-2: Change"F/hr"onabscissaoEgraphto"0F in any one hour".
Recsons for Proposed Change This change is being proposed to eliminate any ambiguity that may exist in interpreting the Technical Specification primary system maximum allowable heat-up and cooldown rates.
It should be noted thi.t this proposed change was requested by the Commission's Mr. George Lear in his letter to the licensee dated November 12, 1974.
Safety Analysis Justifying Change The Technical Specifications as they presently read, are ambiguous in that the heat-up and cooldown rate limits could be interpreted either as instantaneous rate limits or as derived-equivalent rate limics to be applied over a specified period of time eg.1000F per hour could be 1536 H0 1
interpreted either as an instantaneous rate limit--which is the most restrictive interpretation--or an equivalent rate limit such as 110 F over a period of 6 minutes.
With the proposed change, however, a heat-up rate limit of "1000F in any one hour" would be interpreted to mean that tecperature increases could take place at any instantaneous rate, provided there exists no one hour interval, or sub-interval thereof, in which greater than a 100 F temper-ature increase takes place. Exa=ples which serve to illustrate what this later statement means are provided in Enclosure (2) .
The propsed change as stated and interpreted herein has been reviewed and has been found to be consistent with B & W's position regarding how the FSAR stated heat-up and cooldown rate limits are to be applied to TMI-1 (ref. B & W 1ecter dated December 11,1974, (Enclosure 3)) ; and no un-reviewed safety questions are involved.
IO /
- 1
3.1.2 FRISSURIZATIC" "IA U?, A'.? C00I.LO:.77 LI.*:ITATF"9 Enclosure 1, Page ,A c,.
~
'D ** '
- D Change Request No. 6 A rlicetility 9 D 9
r
_6 6 J c .dJ.. .m Applies to pressurization, heatup, and cooldown of the reactor coolant system.
Ob3cetive To assure that tenperature and pressure changes in the reactor coolant system do not cause cyclic leads in excess of design for reactor coolant systen co:ponents.
Specification For the first 1.7 x 10 ther 6 al negawatt days (approxi=ating two 3.1.2.1 years) the react:r ecolant pressure and the system heatup and cooldown rates (with the exception as the pressurizer) shall be limited in accordance with Figure 3.1-1 and Figure 3.1-2 and are as follows:
Heatup:
Allowable cerbinations of pressure and te perature shall be to the right of and below the limit line in Figure 31-1. Heatup rates shall not exceed those shown on Figure 3.1-1. ,
Cooldown:
Allovable conbinations of pressure and temperature for a specific cooldown shall te to the left of and below the limit line in Figure 3.1-2. Cooldown rates shall not exceed those shown on Figure 3.1-2.
t Hydro Tests:
Fcr isothernal systen hydrotests during the first two years of operations, the syste= cay be pressurized to the lLnit: set forth in Specificatien 2.2, when there are fuel asse:blies in the vecrel and to AS$2 Code Section III limits when no fuel asse=blies are present if the syste: temperature is 215 F or greater. The systen may be tested to a pressure of 1150 psig provided systet temperature is 175 F or greater. Initial system hydrotests prior to criticality may be conducted if the reactor coolant system te=perature is llS F or greater.
3.1.2.2 The secondary side of the steam generator shall not be pressurized above 200 psig if the te=perature of the steam generator shell is below 100 F.
3.1.2.3 The pressurizer heatup and cooldown rates shall not exceed 100*F ir.
any one heur. The spray shall net be used if the te=perature differen:c between the pressurizer and the spray fluid is greater than h30F.
3.1.2.4 Within two years of power operation, Figures 3.1-1 and 3.1-2 shall be updated in accordance with criteria acceptable to the AIC.
Bases
$ All reactor coolant systen cenponents are designed to withstand the effects of cyclic loads due to systen tecperature and pressure changes.(1 These cyclic 3-3 IJu/
ir"d i*l7*
4
Enclosure 1, Fcce 2 of ~
Change Request No. 6 leads are intrcduced by unit icad transients, reactor trips, and unit heatup and cooldevn operations. The nu=ber of ther=al and Icading c"cles used for design purposes are shevn in Table L-8 6f the FSAR. The maximun unit heatup and cool-down rate cf 100 F in'd-4+
any ene hour satisfies stress licits for cyclic operation.(2) l The 200 psig pressure
- the seccndary side of the steam generator at a temperature less than 1CC F satisfies stress levels for temperatures below the D".'" The reactor vessel plate raterial and velds have been tested to '
verify conferrity to specified requirements and a taximum ICT value of 30 F has been deter =ined based en Charpy V-netch tests. The =axi=u= UOTT value -
obtained fer the steam generator shell caterial and velds was k0 F.
The heatup and ecoldown rate limits in this specificatien are net intended to limit instantanecus rates of te=perature change, but are intended to limit tempera-ture changes such that there exists no one hour interval, or sub-interval thereof, in which a te=perature change greater than the limit takes place.
Figures 3.1-1 and 31-2 contain the liciting eactor coolant syste= pressure-temperature relationship for cperation at DC and belev to assure that stress levels are 1cv enough to preclude brittle. fracture. These stress levels and their bases are defined i: Paragraph h.3.3 of the FSAR.
As a result cf fact neutron irradiation in the regien of the core, there vill 1 be an increase in the I: T vith accu =ulated nuclear cperation. Tce predicted taxin"~ "*m i ncrease fer the LO-year exposure is shev: en Figure h-10.(h)
The actual shift in NDC will be determined periodically during plant operation by testg of irradiated vessel caterial semples located in this reactor .
vessel. The results of the irradiated sample testing vill be evaluated and co= pared to the design curve (Figure k-11 of the FSAR) being used to predict the increase in transitien te perature.
The design value fgr fast neutron (E > 1 MeV) exposure of the reactor vessel is 3 0 x 1010 n/c:'seeatthereferengedesig integrated exposure of 3.0 x 101 9 n/cc pcvercf2568rg<andan calculated raximum values are 2.2 x 1010 n/c for Lg years cperation.19 Tht see and 2.2 x 10 n/c '
integrated exposure for LO years operation at 80 percent lead. Figure 3.1-1 is based on the design value which is censiderably' higher than the calculated value. The Or value for Figure 3.1-1 is based on the projected ;~O"T at the end of the first two years of operation. During these two, years , the energy output has been conservctively esti=ated to be 1.7 x 10 0 ther=al megawatt days, which is equivalent to 655 days at 2568 :st ecre pcver. The projected., fast ;;eutron ex;caure to the reacter gessel for the two years is 1 7 x 1010 =/c ' which is based en the 1 7 x 10 thercal regavatt days and !
the design value for fast neutrcn exposure.
The actual shift in NDTT vill te estab'tished periodically during plant operatien g by testing vessel raterial samples which are irradiated cumulatively by securing '
ther near the inside vall cf the vessel in the core area. To ec pensate for the increases in the ::0'1T caused by irradiation, the limits en the pressure-te=perature relatienship are periodically chcnged to stay within the established stress limits during hestup and cooldevn.
The TDTT shift and the =agnitude of the therral and pressure stresses are sensitive to integrated reactor power and not to instantaneous pcVer level. Figures 3.1-1 and 3.1-2 are applicable to reactor core ther:a1 ratings up to 2568 !Gt.
i s o' u 3-h
Enclosure 1, Pace 3 of 5 Change Request No. 6 D**D PM'3' wd b[0. .. , i
(
The pressure limit line en Figure 3.1-1 has teea selected such that the ,
reactor vessel stres: res.C.tir.g f--- 3-+---=' pressure vill not exceed 15 percent yield strength considering the following:
- a. A 25 psi error in =easred pressure
- b. Syste= pressure is neasured in either loop
- c. 1'.axi=u: differential pressee between the point of syste pressure .
=easurenent and reactor vessel inlet for all operating pu=p cocbinations For adequate conservatis=, in lieu of portions of the Fracture Toughness Testing F.equire=ents cf the pre; sed Appeniix G to 10 CFR 50, a =szi=u= .
pressure of 550 psig a=d a =axinu= heatup rate of 50*F in any one hour has l been i= posed belev 275, F as shown en Figure 3.1-1.
The spray tenperature difference restriction, hased on a stress e=alysis of the spray line nozzle is i= posed to =si .tain the ther=al stresses at the pressurizer spray line no::le belov the design li=it. Te=perature require-
=ents for the stean generator correspond with the =easured UDIT for the shell.
t REFERE'!CIS (1) ISAR, Section L.1.2.L (2) ASME Boiler and Pressure Code,Section III, N k15 (3) FSAR, Section k.3.10 5 (k) TSAR, Section k.3.3 (5) FSAR, Section k.k.5 (6) FSAR, Sections L .l.2.8 a .d L .3.3 e
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1 3-5
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i Enclosure 1, Page h of 5' ' -
Change Request :lo. 6 i
POINT TEMP. PRESS. 2 A 40 550 B 275 550 C 275 '
1400 2400 -
0 380 2275
-D 2200 _
2000 -
E. -
. 1800 -
s 2 -
a y 1600 -
UPPER PRESSURIZATION I -
LIWii '
3 1400 -
C
- )
E 1200 _ i
$O '
[ 1000 _ ,
S UPPER -
3 800 _ PRESSURIZATION , ;
[ LlWIT 3"
600 -
k A' $
400 -
WAXINUM HEATUP RATE,hourT in any one 200 - -
50 -
100 _
1 0
' I ' I ' I ' I ' I O 100 200 300 400 500 275 -
Indicated Reactor Coolant System Temperature,'F e
REACTOR COOLANT SYSTEM HEATUP LIMITATIONS (APPLICABLE UP TO AH INTEGRATED EXPOSURE OF 1.7 x 10I S N/CM2 OR DTT = 154 F) ,
THREE hlILE ISLAND NUCLEAR STATION UNIT I .
FIGUR E 3,1-1
Enc 1csure 1, Page 5 of 5 Change Request Ilo. 6 POINT TEMP PRESS A 380 2275 275 1400 B
C 275 550 {
0 250 550 E 250 450 2400 - F 175 450 G 175 200 A
N 120 200 2200 -
g; pavP C0431 NATION!'ALLCaASLE.
AB3VE 185F ALL 2000 -
BEL 0e It5F 1.A,1.B;0.A,2.B;I.A,0.g;0.A,1.g
?' (1) M EN CECAY HEAT REW: VAL SYSTEM (OH) IS E 1800 -
CPERATihG WITHOUT ANY RC PUMPS OPERATING.
$ INDICATED OH RETURN TEMP. TO THE REACTCR y 1600 -
VESSEL SHALL BE USED.
= B E #' 0
- I400 -
2 NAllNv'M STEP TEMPERATURE CHANGE OF 75F 0 IS Alt 0rABLE FOLLC9EO Bf A CNE HOUR y 1200 NINIP V HOLO CN TEVPERATURE. IF THE STEP
, CHANGE IS TAKEN EELC# 250F RC TEMP!RATURE, 3 1000 - THE MAIINL'N ALLC#ABLE STEP SHALL BE THAT a WHICH YlELCS A Fit.AL TEMPERATURE OF 175F, 3 800 - THE STEP TEMPERATURE CHD. E IS DEFlhEO AS
- 600 - /
VESSEL.
ll C' -F i
/
G
,H i
.' b 3 20C -
/ las
- UPPER PRESS'.RI Z ATICN f LIMIT .
0 -
'NAIINUM C00Locn RATE *F in any one hour (2) +
i_ !
100 i 50 g g i t t '
t t ' t t f 530 4 4 8 4 250
- 175 120 1 275 400 300 200 100 SCO 500 Indicates Rea: tor Coolant Syste:s Terperature.*F II) 1535 615 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
('
(APPLICABLE UP TO DTT : 135F)
THREE MILE ISLAND NUCLEAR STATION UNIT I FIGURE 3.1-2
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, .. helesure 2, PaEe 1 Of 2
. _ . . . . . - . . . . . a t
Examles on Meaninc of '
.. t Proposed Chance >
t Fro proposed Figure 3.1-1, when F.eactor Coolant Syste= (ROS) te=perature exceeds 300 F, the maxi =un heat-up rate limit vill be 100'F in any one hour. The following .
exa=ples ser9e to illustrate vtat is and what is not acceptable for this condition.
Acceptable Tenperature Transients s
gg,, y _ _ _ . . . .
. - - . . . ....--....._. Case B - - - - - - - - - - -
- . k50 & . - .. .. .. -
k50 ^ . -_. - - ..- - b e
a5h25- h25 -
e 4
- 8, h00 - -- -.
LOO _. --. .-
a O t b J m 375 375 - -
o e c'. f e 350 " -
350 o - . 4
$ 5
- -o 325 325 . .- - .
e c
- H 300 "
300 - - -- -- - - -- - -
. _ . . s -
s 30 6'o 90 120 30 60 90 120
-- - t (mins) . .. . . .
t (= ins)
~ ~ ~
Both cases A and 3 are acceptable in that there exists no one hour interval, or sub-interval thereof, in which greater than a 10b F te=perature increase takes
- place. - -- -- - -- - -
- Non-acee; table Temperature Transients ... . _ _ _ . - .
n Case C g Case D h50 "
h50- -- - - - - -
e a$ h25 h25 e
- ks h00 .. . . ... ..
.koo. .. . ._ - . _ - . . . _ _ . ._ _ . .
e ,
6 e m
o 375 - - - -- --- -
375- ; - - - - - - - - - - - - - - - - - - - - - -
a: . t
-g 350 - - --
350-- j. . - - . .. -- --
M e B
.S 325 3
325- i --
--" 300 .. -
300. .i - . .._. .. _ _ . _ . .
- i s . s 30 60 90 120 30 h2 60 90 120
-. .. . . t (= ins) __ . , _ _ __ _ _ , _ _ _ t (= ins) ,
1556 317
4.
Enclosure 2, Pace 2 02 2
- 3 t
Case C is Cunacceptable in that evei the tire period from 30 to 90 minutes, greater 7 than a 100 F te=perature change takes place.
Case D is unacceptable in that there exists one hour intervals that contain sub-intervals in which the temperature change is greater than 100 F (e.g., the 30 to -
90 minute interval contains many sub-intervals during which the temperature !
increase is greater than 100 F; i.e., 30 =inutes to any time t such that h2<t<60 _
=inutes constitute ene set of such sub-intervals) . 3 i>
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i December 10,197h ;
REM-21 l i
Mr. ;, G. Merbein htrepolitan Edison Ceepany Post Office Ucx LD Midlietevn, PA l'7057 subject: 01arifiestion to Tech. Spec. 31.2 Des. Mr. Herbein; i.
I:s reep;mse to the question . posed to Met. T,d.fb the AE0 on the interpre- !.p tatie- rf hestny ro. c001dovn rate lhite, ~rXa' hat the fellowing tosition.
A :er. up er coo.idevv rsta limit is interpreted at the .utxi:nn chrin:3e in ter parat s c in one , ire: tion durin4; a or.: hour period. Thus, c 50*F ch0nSe in n :nort
- ine per od i Meep% bis (relative to a 50*F/hr li: nit) if a h[
p
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h01d in terpert.ture. 0%nd $s cherved for the re:tinkt Of W hour. If0v- :/
ever., .s 609 decrea: e a.:2 a subcquent 10"? !*:cre!.ce (t.ba, n rich 50? jf cocr .tec) is r:et ti: ertc.blo in nc -escing cc a.plic.-nce vit.w. the Toch. Epaes. ;J B~ ove ry re.w eve:-hi a . ire. or overceding is not considered, but retther the enxix.c ?.ifference in tc:=p::reture durin(' a enh hour period. , f
!. i It is st.g;e-r::.e4 tht a statc:::ent clarifying this position be adi:d to the cno er t he b oo r, to 7.c h . Spee , 3.1.2. Such a etstement tkt in acceptable j
- Mu in o in12cva: e i
The heatun u:! Oceldcun tr.tes stated in tMp epcetricatien nru in '
te:r.ied nn t he n.v'inc.cNN*.es in temperature in one direct $o'n in a l l't
, f) one hour p.0-ic.d. The actud tmpratur. lingar ramp rste.a may exceed i ig tha at:.ted li.W,2 Gr a tMe period pro'.'$ded tMt the eaxitmn totrl ;g te per.stu c d.irf t: e :ce 'ne. . et 9.ceed the limit and that a tc::pern- l*
' tc.:N ndd 12 Mafwvr -i to pr:1vont. the totta br.persture .df fforence I fre., eset dit:3 th: "icit for thir one hw yriod.
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