ML19312C426
| ML19312C426 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/23/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C420 | List: |
| References | |
| NUDOCS 7912130948 | |
| Download: ML19312C426 (21) | |
Text
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UNITED STATES
/
o, NUCLEAR REGULATORY COMMISSION y p.,(
-t WASHINGTON, D. C. 20555
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DUKE POWER COMPAhY, 00CXET NO. 50-269 OCOUEE NUCLEAR STATION, UNIT NO. 1 AME.40NENT TO. r,ILITY OPERATING LICENSE Amendment No. 53 License No. OPR-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The apolication for amencment oy Duke Power Company (tne licensee) dated November 9,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amenced (the Act), and the Ccmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amencment can be conducted witnout endangering the health and safety of the public, and (ii) that such activities will be conducteo in ecmpliance with the Commission's regulations; 0.
The issuance of tnis amencment will not be inimical to ne common defense and security or to the healtn and safety of the puolic; and E.
The issuance of this amendnant is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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2-2.
Accordingly, the license is amended oy changes to the Technical Specifications as indicated in the attachment to this license amendnent and caragraph 3.3 of Facility License No. OPR-38 is hereby amended to read as folicws:
B.
Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised thrcugh Amendment No. 53, are hereoy incorporated in the license. The licensee shall operate the facility in accorcance with the Technical Specifications.
3.
This license amencment is effective as of tne date of its issuance.
I FCR THE NUCLEAR REGULATORY CCM?i!SSION
.,s?,
% Lsev.pe,-
J.' A. Schwencer,JChief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 23, 1977 l
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gM IIIg UNITED STATES
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!1 NUCLEAR REGULATORY COMMisslON
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s DUKE PO'aER CCMPANY 00CKET i40. 50-270 OCCNEE NUCLEAR STATION, UNIT NO. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No.
53 License No. OPR-47 1.
The Nuclear Regulatory Commission (the Ccmmission) has found that:
The application for amencment oy Duke Power Company (the A.
licensee) cated November 9,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amenced (the Act), and the Ccmmission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be concucted in compliance with the Ccomission's regulations; 3.
The issuance of tnis amendment will not te inimical to the ccomon defense and security or to the health and safety of tne oublic; and The issuance of this amencment is in accordance witn 10 CFR Part E.
51 of the Commission's regulations and all applicable requirements have been satisfied.
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- Accordingly, the license is amenced by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment and paragraph 3.3 of Facility License No. OPR-47 is hereby amended to read as follows:
3.
Technical Scecifications The Technical Specifications contained in Appendices A and 3, as revised through Amendment No. 5% are hereby incorporated in the license. The ifcensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the cate of its issuance.
FOR ThE NUCLEAR REGULATCRY CCMMISSION s, am,
'/7
- ' A. Schwencer, Chief c
Operating Reactors Branch 51 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 23, 1977 l
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UNITED STATES f
'o, NUCLEAR REGULATORY COMMISSION g
y WASHINGTON D. C. 20555 j
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s.,...
DUKE POWER COMPANY OCCKET NO. 50-287 CCONEE NUCLEAR STATION, UNIT NO. 3 AMENDItEST TO FACILITY CPERATING LICENSE Amencmant No. 50 License No. CPR-55 1.
The Nuclear Regulatory Ccnmission (the Ccmmission) has found that:
The application for amendment cy Duke Pcwer Ccepany (the A.
liceasee) dated November 9,1977, cceplies with the standards and recuirecents of the Atemic Enercy Act of 1954, as acended (tre Act), and the Ccemission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccmission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be ccnducted without endangering the health and safety of the puolic, and (ii) that such activities will be cese.icted in ccepliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amencment is in accordance with 10 CFR Part 51 of the Comission's regulationr and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragrach 3.B of Facility License No. OPR-55 is hereby amended to read as folicws:
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B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment flo. 50, are hereDy incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amencment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATCRY CCMMISSICN
?.
S 4!*&M r
' %' ' G
,A Schwencer,* Chief 4ry' Operating Reactors Branch *1 Division of Operating Reactors
Attachment:
Changes to the Technical Speci fications Date of Issuance: November 23, 1977
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ATTACHME?tT TO LICENSE AMENCMENT NOS. 53, 53AtlD 50 FACILITY OPERATING LICENSE NOS. DPR-38, OPR 47 AND CPR-55 DOCXET NOS. 50-259, 50-270 Atl0 50-287 Revise Apoendix A as follcws:
Remove the follcwing pages and replace with identically nurrbered revised pages.
3.5-7 3.5-8 3.5-9 3.5-12 3.5-13 3.5-13a 3.5-18 3.5-18a 3.5-}8b 3.5-b 3.5-21a 3.5-21b 3.5-23d 3.5-23e 4.1-1
e If within eno (.1) hour of'datW -=:1cn of an inoperablo :cd, g.
1: is see determised that a 1".ak/k het shutdcwn margin exis s ccab4 d g de worth, of the isoperable cd vitb. each of da other reds, de sac:ct shall be. 5:cught :o cha hoc sta=dby condi:icu utr d i this merg1= is establishad.
h.
To11cwing -de decarmd-=~d u of an i=cperable cd, all reds shall be exar:1 sed vi-' '
24 hcurs a=d azercised weekly==:11 ~.he cd problem is solved.
1.
If a. cent =cl red is tha regula:1=g or safety red g cups is decla:sd i=cperable, pcwer shall be :tducad :: 60 percent of de dermal pcwer al'.cwable for da. : ac:cr cociant pump ccm-bisation.
j.
If a con s1 red i=. tha :sgula:1=g or axial pcwer shay 1=g g: cups is decia. sd i=cperabla, operacicu abova 60 peruan: of ra:ed r
power may cen:1=ne provided. tha cds is de p g a:s posi:1 cued such.tha: de :cd. -la: vas dec12:ed i=cperable is ~' -*' ed vi-4d alicwabia 3: cup averags posd-d~- ' s of Speed"d-* dcn s
3.5.2. 2.a and. -de vi *.drzwal 1 ' d:s of Spes 'd-*:1cu 3.5.1.3.c.
3.5.2.3
- te aar-As of singla i=serted. ceni M
cds 8 d- - cri-d - ' 7 i
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ars l ' d:ad by,the rasc=1;;;1cus. of Specifies dcn 1.L.1 i and -Ja.
I control :cd. posi dcn l'* :s def1=ed.12 Soerd 'd ca:icn 3.5.2.5.
3.5.1.4 quad:sne ?cwer *.11:
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=vd --" = posi:17e quadrant pcwer 2xcepe for physics cases, if.ha a.
til. exceecs 6.031 Uni: 1, ei her the quad.an power.d1: shall l
3.4I% Uni: I 3.41% Uni: 3 be reduced c less han. (f.02% Uni: 1 wi h1= two $*. curs or :ba I
~ I.4I: Uni: 2 7.41% Uni: 3 fellcwing acticus shall be :2km:
(1) If four reaccer ecolanc pumps are is. operacion, the allcweble power shall be reduced balcw the pcwur 1sval cuccff
- % === 1 (as identified in speed #d -= tion 3.5.2.3) a=d further reduced by 2 of full power fer each.1% til: in excess of 6.03 Cnic 1.
l 3 41; Uni:- 2 3.413 Uni: 3 (b *15 less han four reac:cr ecolane pumpe ara in operati.m, the alloweble charmel power for the react...r cocianc pump combi =acien
.shall be :sduced by 2 of full power for each 1* cil:.
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3.5-7 Amencrent fics. '53, 53 & 50 i
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shal'-bn brought to thn hot shutd:wn-ondition within four hour _ if the quadrant power tilt is c :cduccd to leca than 6~.03; Uni: 1 vichin 24 houra.
I 3.41: Unic 2 3.412 Unic 3 b.
If the quadrane til: exceeds 6.03% Uni: I and there is sinul aneous 1 3'.41 Uni: 2 3.41% Uni: 3 indication of a nisa11gned control rod per Specification 3.5.2.2, reactor operation may continue provided power is reduced to 60%
of the the: mal power allavable for the reac:or coolant pump combination.
c.
Excepe for physics cast, if quadrant til: exceeds 9.44: Uni: 1, 9.44% Uni: 2 9.44 Uni: 3 a controlled shutdown shall be imiated **'=taly, and de d
- ac:or shall be br=ught :o he hoc shutdown c="d'-d m within l
four hours.
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d.
~4hanswer the : sac:ce is br=ught s bec shu:down pursuanc :s 3.5.2.4.4(3) or 3.5.2.4.c above, subsequan: : ac:=r cpera:1cn is pas eted. for he purpose of measurement, :esed g,. and.
c=r:setive ac_1=n pr vidad the :ha =al ;cwer a=d de. pcwer range high fluz. sa:pc1== allcwable for de ranc:c= c=clant pump c=mo1=ation ara. :matric:ei by a red =cti:n of 2 permsne of f-17 power for each. L per.. ant :11= for the.
=vd we *d t : obserred.
prior ta shutdcun fraquenc7 e.
Quad.ane pcwor *P: shalI be moni:cred en a d'-
of once every : Jar hours. during pcwer opern 1:n abcve 15 perese of ratad. pcwer.
3.5.2.5 C'en rel. 3cd. ?csd -d-c.s.
a M d-=T Sp= d*d-=edm. 3.1.J.5 does so: pr:mi de exar-d ad !
.cf i=diriduaL safa:T :=ds as =quirad. by Tahia 4.1-1 or apply.2 i=operabia safsc7 :cd. ' d=d :s in Cac5 ad e=1 Sp=ed'd-=:1:n 3.5.2.2.
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5.
Ezcape far physics tast.r, %4 red' g =up overlspr shall be 25 ? SI between :eo-sequential zrouns. If'.his 7d-d: is exceeded, corrective nessures shall be cakan d---dd =caly em achiave an aceso-
- able overlap. Acceptable overlap. shall be at**'~=d si:hin two hours. or the resc:sr Shit be placed. in, a hot. ed-n c=ed4 -d-n-within an =ddd*d M 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Position liai:a are specified for regulating and axial power shaping control rods. Except for physics tests or exercising control cds, de reguisting control :cd inser:1cn/wi:hdrreal
' l 1131:s are specified en figures 3.5.2-1A1, (Uni: 1); 3.5.2-131, 3.5.2-L32 and 3.5.2-133 (Uni: 2) ;
3.5.2-1C1, 3.5.2-1C2 and 3.5.2-1C3 (Uni: 3) for four pump operation, and on figuras 3.5.2-2A1, I
(Uni: 1); 3.5.2-231, 3.5.2-232 and 3.5.2-233 (U:.1: 2);
3.5.2-2C1, 3.5.2-2C2 and 3.5.2-2C3 (Uni: 3) for :vo or :hree
=
an.
.w-l pump cparation.
Also, excepting physics toets or exercising ccntrol reds, the axial power shaping control rod inssrtion/
withdrawal limits are specified on figures 3.5.2-4A1, (Unit 1), 3.5.2-431, 3.5.2-432, and 3.5.2-433 (Unit 2), and 3.5.2-4C1, 3.5.2-4C2, and 3.5.2-4C3 (Unit 3).
If the control red position li=its are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position.
An acceptable control red position shall-then be attained within two hours.
The minimum shutdown margin.
required by Specification 3.5.2.1 shall be maintained at.all times.
o d.
Except 'for physics tests, power shall not be incre'ssed above the..
Power level cuteff as shown on Figures 3.5.2-1A1, (Unit 1), 3.5.2-131, 3.5.2-132, and 3.5.2-133 (Unit ~2), and 3.5.2-1C1, 3.5.2-1C2, 3.5.2-1C3 (Unic 3), unless :he foll: wing requirements are met.
(1)
The xenon reac:tvi:y shall be w1:hi= 10 percent of :he value for operation at steady-state raced power.
(2)
The renon reactivi:y.wo::h has passed its final =ax1=um or mini =um peak. during 1:s approach to its equilibriu= value for opera:ica at :he power level cu:off.
.3.5.2.6 Reactor. power i= balance shall be meni:ored on a frequency not to exceed two hours during ;cuer operacion abcve 40 percent rated power.
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Except for physics :ests, imbalance shall be saintained w1:hin the cnvelope defined by Figures 3.5.2-3A1,
, 3.5.2-331 l
3.5.2-332, 3.5.2-333, 3.5.2-3C1, 3.5.2-3C2, and 3.5.2-3C3.
If the i=-
balance is not wi:hin the envelope defined by these figures, corrective measures.shall be taken to achieve an acceptable i= balance.
If an accep-table imbalance is not achieved wi:hin two hours, reactor pcwer shall be reduced until i= balance limits are =et.
3.5.2.7 The control red drive pa::h panels shall be locked at all ti=es wi:h lizi:ed access to be auth' rized by the sanager or his designated al: erns:e.
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3.5-9 Amendment Nos. 53, 53 & 50
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OCONEE 1 CYCLE 4 RCD POSITION LIMITS FOR FOUR PUMP OPERATICN G
FRCM 0 TO 100 (+10) EFF0 TION.
.g' CCCNEE NUC1. EAR STA Figure 3.5.2-1A1 3.5-12 Amendment Nos. 53., 53 & 50
4 ENTIRE PAGE DEL:.TED (These figures will be provided af ter analyses for operation of Ocenee Uni: I beyond 100 EFPD is perfor ned.)
3*I-I3 imendment Nes,' 53, 53 & 50
i 1
ENTIRE PAGE DELETED (These figures will be provided after analyses for operation of Oconee Unit I beyond 100 E.:PO is performed.)
3.5-13a Arendment Nos.'53, 53 & 50 e
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'd EFPD 3.5-13
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Figure 3.5.2-2Al g
6 Mend: ent Nos. 53 53 & 50
ENTIRE PAGE DELETED (These figures will be provided af ter analyses for operation of Oconee Unit i beyond 100 EFPO is performed.)
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3.5-18a Amencment Nos. 53, 53 & 50 O
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ENTIRE PAGE DELETED (These figures will be provided after analyses for operation of Oconee Unit I beyond 100 EFPD is performed.)
3.5-18b Amendment Nes,. 53, 53 1 50 e
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i ENTIRE PAGE DELETED (These figures will be provided after analyses for operation of Oconee Unit 1 beyond 100 E.PO is performed.)
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l 3,5-21a Amendment Mos.'53, 53 & 50 1
e e
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.s E.NTIRE PAGE DELETED i
(These figures will be provided after analyses for operation of Cconee Unit I beyond 100 EFF0 is performed.)
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3.5-216 Amencment Ncs,53, 53 & 50 l
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ENTIRE PAGE DELETED (These figures will be provided af ter analyses for operation of Oconee Unit 1 beyond 100 EFPD is performed.)
3.5-23d Amendment Nos, 53, 53 & 50 O
ENTIRE PAGE DELETED (These figures will be provided after analyses for operation of Cconee Uni: I beyond 100 EFF0 is performed.)
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- Amendment Nos.' 53, 53 1 50 l
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4.1 OPERATIONAL 4AFITY REVIL'W Applicabilit!
D**O 9 0
' 3 kf f Applies to 1: cms directly related to safety limits and II:dt.1 g o
1 im for operation.
Obiective To specify the frequency and type of surveillance to be applied to unit equip-ment.and conditicas.
Specification 4.1.1 The frequency and type of surveillance required for Reactor Pro-tactive System and Engineered Safety Feature Protective System instrumentation shall be as stated in Table 4.1-1.
4.1.2 Equipment and samplihg :est shall be perfor=ed as detailed in Tables 4.1-2 and 4.1-3.
4.1.3 Using the Incore Instrume'neation System, a power =ap shall be made to verify expected pcwer distributich at periodic intervals not to exceed :en effec:ive full pcuer days. In the case of Unit 1, the power distribution shall be monitored daily during power operation above 75% full pcwer.
In the event the power distribution cannot be obtained, power shall be reduced to 75%
or less within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Bases Failures such as blewn instrument fuses, defective indicators, and faulted amplifiers which result in " upscale" or "downscale" indica: ion can be easily recognized by simple observa:1on of :he functioning of an ins:rumen: or system.
Furthermore, such f ailures are, in =any cases, revealed by alarm er annuncia:or action. 'Cceparison of ou:put and/or state of independent channels =easuring the same variable supple =ents this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear sys:e=s, when :he unit is in operation, the sinimum checking frequency s:sted is dee=ed adequa:e i
for reactor system instrumenta:icn.
Calibration is performed to assure the presenta: ion and acquisi: ion of ac-curate infor,(=ation.. The nuclear flux (pewer range) channels a=plifiers a,red calibra ted power.and core ;hermal pewer dif f er by more than two percent.
During acn-s,teady-state operat' ion, the nuclear flux channels a plifiers are calibra:ed
.- daily :o cocpensate for ins:ru=enta:icn drif t and changing red pa:: erns and
.- core physics parameters.
t.
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Channels subject only :o " drift" errors induced within the instrumentation itself can :olerate longer intervals between calibrations.
Process sys:em instrumentation errors induced by drif t can be expected :o remain wi:hin
- he in:arvals specified.
acceptable tolerances if recalibration is perforced a:
Substantial calibra:ica shif ts within a channel (essen:ially a channel l
failure) are revealed during routine checking and tes:ing procedures.
- Thus, l
the sinimum calibra ion f requencies set forth are considered acceptable.
Amendment Nos. 53, 53 & 50
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