ML19210A657
| ML19210A657 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 04/15/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A654 | List: |
| References | |
| NUDOCS 7910300687 | |
| Download: ML19210A657 (17) | |
Text
. .
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 9 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 Nuc2 ear Station Unit 1.
METROPOLITAN EDISON COMPANY
,0 t By Vice Pre %nt-Generation d
Sworn and subscribed to me this /3 day o65 M , 1975
/
$ iE %
Notary Public
, . , . . . . . . . . , . . c .2. Ui s 1493 035 7910800 6 8 7
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF ,
DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY Ihis is to certify that a copy of Technical Specifiestion Change Request No. 9 to Appendix A of the Operating License for Three Mile Island Nuclear S tation Unit 1, dated Apri.1 15 , 1975 , and filed with the U. S. Nuclear Regulatory Commission on April 15th,1975, has this 15th day of April been served on the chief executives of Londonderry Township, Dauphin County, Penr.sylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as folle>ws:
Mr. Weldon B . Arehart , Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of t'ounty Commissioners Londonderry Township of Daupnin County R. D. #1, Ceyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 P.O. Box 1295 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY l
Br /
' Vice Ppident-Gen'kration 1493 036
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It is requested that the prese: "v? ' c a a" ' cal Specification pages 3-6, 3-7, 3-35, 3-35a, 3-36, and figures 3 5-EA, 23, 20, ED and 2E be replaced with the respectively desi_r:sted :ar_es of the attached Appendix 1; and _
that a new figure 3 5-2? (previously designated fi~g:re 3 5-25, and included in Appendix 1), be added to the TMI-1 Taab-4 aal . Specifications. Further, it shculd be noted that this 7aa'-4 al Specificatio: Charge Request,.if approved, vill serve o: (a) revise the t.resen: Power vs. Rod Withdrawal limits of the TMI-l Technical Specificati :s Figures 3.5-2A, 23, and 20, and (b) revise the related Technical Specifi:sti:: :ex so as to be consistent with the revised
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- Note: Technical Specifica:ic: Change Request No. h, previously submitted by tha ~'-a see, requested that cha Ses be made to s0:e of the sa-a a- 'osed pa3 es, and these previousl" s requested :ha=ges are :::ei by "C. 3. k".
Reasc for Teceriaa' : aa*-=-- Changa Fecuest No. 9 The presen: Fever vs . 2:d Wi+'-3-aval 14-4:s as provided by the present Technical Specificatics figures 3 5-EA, 23, and 2C, are. not adequate to ensure not exceeding t"* aa'--* al Ipecification single red vorth limits of TMI-l Tech ' cal Specifi:stic: 3 5.2.3.,for plan cperations subsequent to the next 00 trol rod interchange (note: refer to Licensee Non Routine 30 Day Report 75-O' , attached as Appendix II, for additional background in this subject area). The reason for this Change Request, therefore, is to obtain Power vs. Ecd Withdre. val limits which are adequate to ensure not exceeding the red verth "~4:s of Specification 3.5 2.3 for
. slant o.erations in the time :eriod from the first control rod interchange .
until c:=pletics of t'-a -st refueling.
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.. . o, i 493 037 It is the Licensee's pcsiti : tha: the IL=its provided by the enclosed, revisei ?cver vs. Red Withiraval Figures are adequate to ensure not exceeding the sir le r0d verth ':s Of E:ecificatic: 3.5.2.3, for plant cperations
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hr-her , it shculd 'ce ote a+ -.+ a .u.3. ~ core rod worth measure.ents vill ta obta<. - e4, 4n ac c A --. <->
- --- - ne im< arch 31, 1975, request or
- 'ss v' 't , ,
$,pr vide further verification that the re the C b ed lit ts a . , a.
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1493 038
D!I-I TICETICAL S?IO2ICA" ION CEX;GI RIO.UIS' 50. 9 CIA 3GI PAGIS Appendix (1)
. 1493 039 WW W .; ._ .. . . .,7. . . -- -- -
3 2C-1 T. S . CHANGE F~ " ? NO. 9 3 1.3 MInnrat CC:iDIC 0:i3 FC?. C?7ICALITY Aeolicability Applies to reactor coolant syste conditic:s required prior to .riticality.
Ob.i ective_
- a. To licit the magnitude of a gr power excursions resulting from n > ivity insertion due to =0derator pressre and noderator temperature coefficients.
- b. To assure that the rea: tor coolant systes vill not go solid in the event of a rod withdrawal or startup accident.
Suecification - ,
3.1.3.1 'Ibe reactor coolant te ;e_ature shall be above 525 F except for portions of low power physics testing when the require-nents of Specification 3.19 shall apply.
3.1. 3. 2 Reactor coolant terpere:re she.11 be .above DTT +10 F.
31.3.3 tihen the reactor coolar te perature is below the mini .:
t'e perature spe:ified in 3.1.3.1 above, except for portic s of low power physics testing when the requirements of Specification 3.1.9 sh c apply, the reactor shall be sub-critical by an c=ount elual to or greater than the calculated -
reactivity inseMion due to depressurization.
3.1.3.h The reactor shall be tair: sized suberitical by at least one percent Ak/h until a stea= bubble is forced and an indicated water level be:veen 80 and 385 inches is established in the press' ricer.
3.1.3.5 Safety rod g: oups sv is fully withdravn prior to any other reduction in shutdev: cargin by deboration or regulatin;; rod withdrawal dring the approach to criticality with the following exceptions:
(a) Inoperable roi per 3.5.2.2.
(b) Physics testing per 3.1 9 (c) Shutdov: cargin nay not be reduc d below l's AAk/k per 3 5 2.1.
(d) Exercising rois p er .l. 2.
Following safety red vi:htaval, the regulating rods shall be !
positioned within their p:sitica limits as defined by specification 3.5 2.5 prier :: det:raci: .
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a a d. t a u . ; m .e
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s 2 asea At the beginning of life of the initial fuel cycle, the =oderator temperature coefficient is expected to be slightly positive at opere. ting temperatures with the operating configuration of :ntrol' red 3. (1) Or.lculations show that above 525 F the positive coderator : efficient is acceptable.
Since the moderator terperatu e coefficient at lover te peratures vill be less negative or more positive than at Operating temperature, (2) sta-tup and operation of the reactor -inen fea: Or coolant te=perature is less {
that 525 F is prohibited except where ne:essary for lov power physics tests.
Tae potential reactivity insertica dne to the coderator pressure coeffi-cient(2) that cculd result frc: depressurizing the coolant fro: 2100 psia to saturation pressnre of 900 psia is appre e'-Atel, 0.1 percent Ak/k.
During physics tests, special operating precautions vill be taken. In addition, the strong negative Doppler e: efficient (1) and the small integrated Ak/k would licit the agnituie of a power excursion resulting fre a reduction of coderator density.
l Tne requirement that the reactor is 20t 50 be rade critical below DTT
+10 F provides increased assurances that the proper relationship between pri=ary coolant pressure and te..peratres vill be "*"tained relative to the 'iDTT of the pr i=ary coolant syster. Eestup to this temperature vill be acco:plished by operating the reac:Or coola.nt pu=ps.
If the shutdown cargin required by Specificatica 3 5.2 is nainta aed, there d is no possibility of an acc da -v :riti:ality as a result of a decrease of i
coolant pressure, j
i The require ent for pressurizer bubbla '-- =' ion and specified water level -
\
when the reactor is less than one percent suberitical -ill assure that the reactor coolant systen cannot bec0:e solid in the event of c. rod withdraval accident or a start-up accident and that the water level is above the tinitun detectable level.
- , ar'Fner'a egzireneu . hat =the sah .. .. ..d 3...a . bet 17 vindravn- befort5. >c?iti- - -- -- ,
cality ensares shutiova capability dring staMup. Tnis does not prohibit ;
roi latch confirration, i.e. , withd-ava by g oup to a saxinun of 3 inches withdrawn of all seven groups prir to safety rod withdrawal.
i Tne requirement for regulating rods being within their -od position lini. f ensures that the shutdown =a: gin and ef s :ei r:d criteria at hot zero .
f
{
power are not violated.
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(1) FSAR, Section 3 o o IU -1NNq m (2) FSAR, Section 3.2.2.1. -
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1493 041
. -em we e =
i t
TMI-l T.S. CHANGE REQUEST 50 9 3 5.2 5 Control rod positicas:
- a. Operating rod group overlap shall not exceed 25 percent,
+ 5 percent, between two sequential groups except for physics tests.
- b. Except for physics tests or exercising control rods, the control rod insertion /vithdrawal li=its are specified on Figures 3 5-2A (for up to the control rod interchange),
Figure 3 5-23 (fro = control rod interchange up to 440 full power days of operation), Figure. 3.5-2C (for after 440 full power days of operation) for four pu=p operation, and Figure 3 5-2D for three or two pu=p operation. If the control rcd position li=its are exceeded, ccrrective =easures shall be taken 4-~ediately to achieve an acceptable control rod position.
Acceptable control roi positions shall be attained within four hours.
- c. Except for physics tests, power shall not be increasad above the power level cutoff (See Figures 3 5-2A, 3.5-23 and 3 5-2C) unleas the xenon reactivity is within 10 percent of the equilibriu= value for cperation at rated power and asy=ptotically approaching stability.
- d. Core i= balance shall be =cnitored on a =ini=u= frequency of once every two hours during power operation above ho percent of rated power. Corrective =easures (reduction of i= balance by AFSR tove=ents and/or reduction in reactor power) shall be taken to =aintain operation within the envelope defined by Figure 3 5-22 If the idbalance is not within the envelope defined by Figure 3 5-2E, correcti.e =easures shall be taken to achieve' aa acceptable imbalance. If an acceptable idbalance is not achieved within four hours, reactor' pover shall be reduced until idbalance li=its are
=et.
- e. Safety rod limits are given in 3.1.3 5 3.5.2.6 The control rod drive patch panels shall be locked at all ti=es with li=ited access to be authorized by the superintendent.
3.5 2 7 A power =ap shall be taken to verify the expected power distri-bution at peri: die intervals of approximately 10 full power days using the incore instru=entatica detection syste=.
Bases The power-i= balance envelepe defined in Figure 3 5-2Z is based on LOCA a..alyses which have defined the =axi u: linear heat rate (see Figure 3 5-2F) such that C.R.h the =axi=u= clad temperature vill not exceed the Final Acceptance Criteria.
Operation outside of the power i=balan:e envelope alone dces not consitute a situation that vould cause the Final Acceptance Criteria to be exceeded should I C.?.L a 1CCA occur. Che pcVer idbalance envelope represents the boundary of operation 3-35
ts
. . [;'
ld CII-l "..s. CHA' IGE RZO.UIST :IO. 9 2
i li=ited by the F*nal Acceptance Crite * * ~'y if the control rods are at the !
vithdraval/icsertion li=its as defined by Figures 3 5-2A, 3.5-23, 3.5-2C, and f 3 5-23 and if a h percent quadrant power tilt exists. Additional censervatiss is p.R.he.
introducted by application of: '
l
- a. IIuclear uncertainty facters j
-i I
- b. Ther=al calibration uncertainty
- c. Fuel densification effects !
- d. Hot rod =anufacturing tolerance factors.
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1493 043 3-35a
T.q - 1 T . S . Cy_al;GI t IST NO. 9 ,
t T e 33 percent overlap between su::essive control roi groups is a' loved since the vorth of a rod is lover at the upper and lov== .-s -; of the stroke. Contrcl '
I rods are arranged in pou. s or b? .is defined .as follows:
Gre r: Function
.e. n . . ._e..]
2 Safety.
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8 A.?S?. (axial power shaping back) i Control rod groups are withi ava in sequence beginning with poup 1. C-roups 5, 6 ala. 7 a-=- ove _ =-,, =. 4_ .s o.r t. . ..-- ._ . r- -. .. . . .o r= _'- o3 - 2_4._1_.. r - .f.. .. _4 - s ."o ,.
- r. o"_o. s 6 an- 7 '-o d
%_ =_ ~ , _ . * . . * . = . ' _._ _.
,- *.a. . .=_4_ .r The =inicu= available roi vorth pro rides for achieving hot shutdovn by reactor -
trip at any time ass"-i g, the highest aarth control roi r=-='- s in the full out position (1).
I.s= -'ad
. - ro' e,.o o_s- - d--4-e , y e - . , .-a'.
- .. 4.'_'_ r..,t o....'... s _'n.,'a . . ' . o
_ . . '.h. s .
g' eater than 0.65 percent t.%/2. T is ve._ue has been shov: to be safe by the safety analysis of the hjpothetical rod e',e tion accident (2). Single inserted Co..+s_o1 road w * *w *. . o * .1 0 -f_=.- . - '. .. ./.0..,/.> c '. x a.- 5 -iU. 4 S- -. oA
.'._4'.=., '.-.m', , . . = . - y ova- .
vould result in lower transient peak ther=al power, and .,herefore, less severe l
environmental consequences as a C.65 percent 4.h/% ejectei roi vorth at rated power.
Tne plant computer vill scan for tilt and i= balance and eill satisfy the tech-nical specification require:ents. If the co:puter is out of service, than manual ;
calculation for tilt above 1 2 r.e- ent 70ver and inbalar:e above L0 percent power l
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Tae quadra:: pove:- tilt li=its set fo :h in Specificatio: 3.5.2.h have been es w_ ol_4s.,.e4 . . .-iv4n
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Test ?over Tri Settoint O < 5 ".,,
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.I 1. Rea inces is the percentage ~ s of the wit:-drawal of the operating - :aos.
s T:tI-1 T . S . CH.CGE
, 2. F.e s t r i c t .s :ns on wi th ira.c' tshed arsas) are sodified af ter in REQUEST NO. 9 s
inter:hange (See Figare 'J. .. trol red '
23)
(125,102) (194,102) (2'42.102}
l02 . -
100 -
RESTRicTro '
REGION
.[- .
80 82.5 /
(132.3,32.5) -
(252.7.82.5)
POWER LEVEL CUTdFF 60 -
g
$ P E Rtf 1 S S I S L E , _ ,
v OPi?.AitxG Y REGION 40 - J - -
f -
2 -
20 -
~
0 . _, f I I i ' ' I 5 1 0 50 100 150 200 250 300 Red Index, T Withdrawal
. 0 25 53 75 100.
I I I I I Group 7 O 25 50 75 100 -
I f I i - I
"'*"d D**D DI).Q.
o cu fbhM W(@j)d!/ta D 25 50 75 100 -
! I I I 1 -
Group 5 C O t i R 0 !_ 2 3 0 3 ?. 3'J? W i iH O R A ri A L L t .'4 t T 3 F3R 4 PUMP OPERATION UNIT l
, Fi;;ure 3 5-2A
1
- - DTI-1 T. S. CHAIIGE RMUEST :
1 1 a 6 i i "O. 9 l
' i i I. Rod inder is *he percentage soa,of the withdrawal of the .
operating groups.
2.
The additional restrictions on withdrawal (hashed areas) are in ef fect af ter the con trol rod i'n t e rch a n ge'. The restrictions on withdra.al are furtner modified after i 440 full power dafs of operation (See Figure 3.5r20 (ieu, 02) ,(242.iez) '
100 - ' ,
(172.4.32.5) * *
~ 32.5 -
4 - (300,32.5}
oO .
k (182.9. 32.5) 3 (262.7.s2.5) l t POWER LEVEL. ' I
~
. RESTRICTED E REGION
. CUF0FF ~
c u .
3n 60 -
I c::: -
e O k (162,50) . - -
u ,
~ ,
5
- PERMISSISLE
~
OPERATING REGION _
20 -
(121.I5)
(!!9.5.0) .
O I I I ' ' l I I I I I I O 50 100 150 200 250 300 Rad index. ' Withdrawal .
0 25 50 75 100 I I i i I Group 7 0 25 50 7d 100 0"" 1A I r i f i
- D'I b u
- aw dd . ~A _,
G r c'.:; 5 s 0
1 25 1
50 I
75 i
100 1 W 046
- 'Jagt 20 G a l'; ? . T E ? ?
- i ' t.
Group 5 LI:llTS FOR 4 PU?,iP OPERAT10fi 1t'IT I
~
~
( -
Figure 3.5,-2B
~
~
1 i i i a e i 4 l i i - [E I. Rod indes is the rcentage sua of the withdrawal f the C4I-1 T. S. il C3XIGI P.IO!JE32 0.5 op era ti n g groups. '
([
ti
- 2. The additional restriculons on wiiadrawal a r e. , g in effect after 4'40 full power dafs of operation.
N p
~ II b
. (270, 102) (291.4.
102)
~' '
100 - ~
l.r
_. ,il (172.4,82.5) 3,
-32.5 (300,32.5) 80 -
f -
(244.5.82 5) O i t s
RESTRICTED
~
POWER LEVEL. CUTOFF
~
k E REGION
~
2 't u ,
'ERMISSIBLE r .!
(
~
OPERATING
~
REGION ll o (l62.50) -
i[
j y 40 -
o a,,
n.
e!
- :)
Il II 20 - "
)
,(121.15) t 3
0 I I I I f (II9.5.0)
I I I I I I O 50 100 150 200 250 300
.I',
R0d Inder, .5 IfittIdrawal !
ll 0 25 50 75 100 f f I I i 1 ;l Group 7 '!
O' 25 50 75 100 1493 047 il l I I I h
Group 5 D**D '
do 'NtidMJ pfldY "sa 0
l 25 l
50 75 I
100 I
. j '$i !
00003 5 lhi C 3 N T 3 0 L '4 0 0 G R O U P ?f l iM O R A .f a t. i. i :l i 7' FOR 4 PUMP OPERATION UN!i I F i pit r e 3 r - 7 r.
i 't
q, I I
'TMI-l T.S.
I i 6 6 i I i i
' CNr:G E ?.2 0.i 2.5 2
- 0, 9 .
L
- - 1. ROD INDEx IS THE PERCENTAGE SUM OF THE WITHDRAWAL OF THE .
OPERATING GROUPS. I e,
e h Il i
-102 .
100 - I (177.14,102) _
~
i ;
. V 8
=
o .
l-C 56 - RESTRICTED PERMISSIBLE _ ,
l j REGION OPERATING g REGl0N g - .
E I 2 80 _
E
- l o
_ (162.50) _
E 40 -
- i
-e -
o {;
o '
.- 20 -
o E ,(121.15)
~ _
~ ~
0 _.
I I I I
/_._(189.5.0)
<r i I- 1 I l l 0 50 100 150 ' 200 250 300 R0d index. ', Vii thdrawal l:
0 25 50 75 100 ,
I I I I I i Group 7 i; O 25 50 75 100 l-I I I I I Group 6
}d) f f
0 25 50 75 100 i t i ! I '
Group 5 CONTROL R00 GROUP WITHOR Ai!AL LI iliS FOR 3 AND 2 P U.'.1 P O P E R A T I O N UJ!i I F i a tt r e 3 5 99
, g.g _1 6. CEAUGE REOUEST UO. 9 POWER LEVEL, S ,,
f RESTRICTE0 102
~
REGION .
~
-20.4 +5.1 '
.2 100
?
30
_60 __
PERMISSISLE OPERATING REGION
'O -
(s'
_ _20 .
-40 20 0 +20 +40 1493 049 Core labalance, 5 OPERATIONAL POWER IMBALANCE EHYELOPE k'
T4REE MILE ISuND NUCLEAR STATION UNIT I -
FIGURE 3.5_2 E
[ . . .
T- .~'fi-1 2,5. _CE.t';GE ?ZL7.ST 50. 9 .
20
~
18.
tu.-
N -
^
c' ~
e-.
c=
Io E
-E o
=: 14 v
12 0 2 4 6 -8 10 12
. Axial Location Frca Bottom Of Care.Ft:
1493 050
. LOCA LIMITED MAXIMUM ALLOWABLE LlHEAR HIAT 7. ATE THREE MILE ISLAND NUCLEAR STATION UNIT 1 FIGUR2 3.5-2F
.1=. - w x m ,-,..ur u _2 _
_ _ _ _ m
t OfI-1 ESTICAL S?ICIFICATIO?
r.u
. . a_.
u .. . _S,- ..o . 9 1493 051 Appendix (2) tw=*= - - -- ~ ~ --:m- - --
m.w_m r_m,w ~_ . _._ ., . , _ , _