ML19290A344
| ML19290A344 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/19/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A341 | List: |
| References | |
| NUDOCS 7911060582 | |
| Download: ML19290A344 (8) | |
Text
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UNITED STATES y
NUCLEAR REGULATORY CCMMISSION
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JERSEY CENTRAL FCNER AND LIGHT CC5fPANY PENNSYLVANIA ELECTRIC CCMPA.NY DCCKET NO. 50-239 THREE MILE ISLAND NUCLEAR STATICN, UNIT 1 AMEND 5ENT TO FACILIT( CPEPATING LICENSE Amendment No. 13 License No. DPR-50 1.
The Nuclear Regulatory Ccenission (the Commission) has fcund that:
A.
The application for amendment by "etropolitan Edison Cc:peny, Jersey Central Power and Light Company, and Pennsylvania Electric Cc=pany (the licensees) dated January 16, 1976, as supplemented February 13, 1976, complies widh the standards and require:cnts of the Atomic Energy Act of 1954, as amended (the Act), and the Cc= ission's rules and regulations set forth in 10 CFK Chapter I; B.
The facility will cperat.e in conformity with the :pplicatica, the provisions of the Act, and the rules and regulaticas of the Cc:nission; C.
There is reasenable assurance (i) that the activities autheri:ed by this amendment can be condue:cd withcut endangering the health and safety of the public, and (ii) that such activities will be conducted in ecapliance with the Cc=:issien's regulations; D.
The issuance of this amendment will not be inimical to the common defenso and security or to the health and safety of the public; and E.
An environmental statement or negative declaration need net be prepared in connection with the issuance of this amendment.
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2.
Accordingly, the license is a. ended by a change to the Technical Specifications as indicated in the attachnent to this license amendnent.
3.
This license a.cndtent is effective as of the date of its issuance.
FOR THE NUCLEAR REGUL*yTCRY C050!ISSION m.
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Robert N. Reid, Chief Operating Reactors Eranch 4 Division of Cperating Reacters
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 19, 1976 1555 298 P00ROR8Na e
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ATTAC1BINT TO LICE.':SE M'EN0";NT NO.13 FACILITY OPERATING LICENSE NO. DPR-50 DCCKET NO. 50-239 Replace pages 2-S, 2-6, 2-9 and Figure 2.3-1 of the Appetdix A Technical Specifications with the attached revised pagcc 2-5, 2-5a, 2-6, 2-9 and Figure 2.3-1.
Chan;;es en these pages are shoc by carginal lines.
P0]RORlalNAL 1555 299 e
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2.3 L!MIT!?:0 SAFC: ev5TF.:.: 3rr:::cs, pec7gc7:3:;
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A rlicability Applies to instruments =cnitering reactor pcVer, reacter pcVer inhalance, reactor ecclant syste: pressure, reacter ecolant outlet te=;erature, flew, nu=her of pumps in operatien, and high reacter buildin6 pressure.
Objective To provide aute atic protection action to prevent any ce=bination of precess variables frc= exceeding a safety 11:10.
S;ecifications 2.3.1 The reacter prctection syste= trip setting limits and the permissible bypasses for the instrument channels shall be as stated in Table 2 3-1 and Figure 2.3-2.
2.3.2 For the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period prior to Cycle 1 shutdown for refueling the high pressure trip setpoint ay be increased to 2405 psig provided that the following precautions are taken during this period.
/
a.
If pressari:er level exceeds 315 inches as indicated by the high-high level alar =, the reacter shall be manually tripp ed.
b.
If the reactor drain ta=k pressure exceeds 15 psig, the reacter shall be manually tripped.
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1555 300 Amendment No. 13
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3as es The reacter protection system censists of four instr =ent chnnnels te neni;;r each of several selectei p'. ant :eniitions which nll :aus e 1 ructor P r' r _ f any One of these conditi:ns deviates frc= a pre-selected 0;ersting r
-;2 ::
the degree that a safety II=it =ay be reached.
The trip setting limits for prctection syste= ins
- r=entati n are li:t= ~a t-Table 2. 2-1.
"he safety analysis has been bas ed up n thes e prot ecti:n
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instr =entation trip set points plus calibration and instr =entation errers.
Nuclear Cver ::ver A reactor trip at high pcVer level (neutren flux) is provided to prevent da= age to the fuel cladding frc= reactivity excursions tco rapid to be detected by pressure and temperature measure =ents.
During ner=al plant cperatica with all reactor ecclant pumps c;erating, rea:ter trip is initiated when the reacter pcVer level reaches 105.55 Of rated ;cver.
Adding to this the possible variation in trip set peints due to calibraticn and instru=ent errers, the =aximu= actual ;cver at which a trip vculd be actu-ated could be 112%, which is =cre conservative than the value used in the safety analysis (l).
a.
Over;cuer trip based en flev and imbalance The power level trip set point produced by the reacter cecisnt syste=
ficv is based on a pover-to-flev ratio which has been established to acec=cdate the =est severe ther=al transient censidered in the design, the less-of-coolant flew accident frc= high ;cver. Anal / sis has de= castrated that the specified ;cver to flev ratic is adequate to prevent a IIGR of less than 13 should a lcv fl:V condition exist due to any =alfuncticn.
?0011DRl8NL Anendment No. 13
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Se pcVer level trip set point produced by the power-te-ficv ratic provides both high power level and Icv flev protection in the event k
the reactor power level increases or the reactor ecolant flev rate decreases. The pcver level trip set point produced by the pcver to flev ratio provides over;cuer D:G protection for all =cdes of pump cperatics. For ev-ry flow rate there is a maxi =u= per=issible pcVer level, and for every pcVer level there is a =ini=un pe. issible lov flow rate. Typical pcver level and icv flev rate ecchinatiene for the pu=p situa:,1 cts of Table 2 3-1 are as follevs:
1.
Trip would occur Wen four reactor ecolant pt ;s are Operating if pcuer is 108 percent and reactor flev rate is 100 percent, or flev rate is 92.6 percent and pcVer level is 100 percent.
2.
Trip vculd cecur when three reacter ecclant pu=ps are operating if pcVer is 80.7 percent and reacter flev rate is Th.7 percent er flev rate is 69.2 percent and pcuer level is 75 percent.
3 Trip veuld cecur when ene reacter ecclant pu=p is operating in each loop (total of two pu=ps operating) if the pcVer is 52 9 percent and reacter flev rate is h9 0 percent or flev rate is h5.h percent and the pcVer level is h9 percent.
For safety analysis calculations the =axi=un calibration and instru=entatien errors for the pcver level were used.
The pcVer-i= balance boundaries are established in order to prevent reactor
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ther=al limits fre= being exceeded. These ther=al limits are either pcver peaking kW/ft limits or D:GR limits.
Be reactor pcVer imbalance (pever in the tcp half of ecre minus pcVer in the bottc= half of core) reduces the pcver level trip produced by the pcVer-tc-flev ratic so that the beundaries of Figure 2.3-2 are prcduced. The pcVer-te-flev ratio reduces the pcver level trip and asscciated reacter-;cver reactor-pever-i= balance boundaries by 1.08 percent for a one percent flev reduction.
b.
Pu=p =eniters The redundant pu=p ::enitors prevent the =ini - ecre 233 fr =
decreasing bel:V 1.3 by tripping the reactor due te the less of reacter ecolant pu=p(s). The pu=p==nitors also restrict the pcver level for the nu=ber of pu=ps in c;eration.
c.
Reacter ecclant syste= pressure During a startup accident frc= low power er a sicv red withd-aval frc= high pcVer, the syste= high pressure trip set peint is reached before the nuclear ever;cver trip set point. ':he trip s etting lini-shavn in Figure 2.3-1 fer high reae:Or ecciant system pressure (2355*psig) has been established :: naintain the sy te= pressu e l
belev the safety limit (2750 psig) for any desir. transient.
- Bteept as specified in 2.3.2 1555 302 Anendment No. 13 2-6
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- C TAllLE 2.3-1
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ItEACTOH PROTECTION SYSTEM TRIP SETfING LIMITS N
n.
One Reactor Coolant Pump E""d Four Itenctor Coolant Pumps Three Heactor Coolant Pumps Operating in Fach Loop rhutdown p
M Operating (Nominal Operating (Nominal (Nominal Operat,ing Hypass i~
Operating Power - 100%)
Operating Power - 75%)
Power 19%)
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Nuclear g<;wer, Max.
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% or rat.ed power 105 5 105.5 105.5 5.0 P.
Unelene power based 1.08 t,imes flow minus 1.08 times now minus 1.08 times flow minus Bypass ed riou(*) and imbal-reduct. ion due to reduction due to reduct.fon due t.o ance, ma r.. or rated imbalance (s) imbalance (s) imbalance (s) on power NA NA 91%
Bypassed 3
Nuclear lower based (5) on pinnp monitors, max.
% or rated power l'
is. lii r,b reactor coolant 2355
- 2355
- 2355" 1720(I')
system pressure, psig, nnx.
5 I,ow renetor coolant 1800 1800 1800 Bypassed nyutem pressure, psig, min.
6.
Variable low reactor (16.25 Tout - 7756)(1)
(16.25T ut - 7756)(1)
(16.25T ut - 7756)(1) Bypassed o
o coolant uysten prenaure, psig, min.
'(. Heuc tor coolant, temp.
619 619 619 619 U
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LT1 8.
Ili r,h Henet.or Building la la la la prenuure, psig, max.
CD
( 1 ) Tout, is in degrees Fahrenheit (F)
- Except as specified in 2.3.2 u
( 2) :tenct or coolant, system flow, %
(.$) Aihnini t rat,i vely cont, rolled reduc t,lon set only during reactor shutdown (ii) Aut onatJeally set, when other segments of the IIPS (as specified) are bypassed
( ',) The plunp monitors also produce a trip on:
(a) loss of two reactor coolant pumps react.or coolant. loop, and (b) loss or one or two reactor coolant pumps during two-pump operation.
in one
2500
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2300 l
ea
- =.
.s E 2100 S
a.
Z 2
E 1900 c
f
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u 2
a:
1700 1500 540 560 580 600 620 640 Reactor Outlet Temperature, F
- Except as specified in 2.3.2
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8 PROTECTICH SYSTEM MAX;9UM ALLOWASLE SET PCINTS THREE MILE ISLAND NUCLEAR STATION 131T I 15 5 5 3 Qi{URE 2.3-Amendment No. 13
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