ML19312C523
| ML19312C523 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/27/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C520 | List: |
| References | |
| NUDOCS 7912160084 | |
| Download: ML19312C523 (14) | |
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e, UNITED STATES 8y NUCLE AR REGULATORY COMMISslON
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W ASHING TON. D. C. 20555
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's DUKE POWER COMPANY
' T, DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 A.MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR 38 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for, amendment by Duke Power Company (tne licensee) dated June 22., 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the li.nse is amended by changes 'to the Technical 2.
Specifications as icated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical 3pecifications.
3.
This license amendment is effective as of June 27, 1978.
FOR THE NUCLEAR REGULAA COMMISSION
.h M.* 1 YbertW.Reid, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 6,1978 O
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WASHINGTON. D. C. 20555
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- l DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-47 l.
The Nuclear Regulatory Commissics (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated June 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set 'arth 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi'l be conducted in compliance 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations 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 paragraph 3.8 of Facility Operating License No.
DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of June 27, 1978.
FOR THE NUCLEAR REGULATORY COMMISSION
)d/hh-a Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 6, 1978 O
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NUCLEAR REGULATORY COMMisslON l'.. e I
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DOCKET NO. 50-287 5
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OCONEE NUCLEAR SIATION, UNIT NO. 3
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AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 59 License No. DPR 65 1.
The Nucle?- Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated June 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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.
Th'ere 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 conducted in compliance with th:: Comiss ion '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 amendment is in accordance with 10 CFR Part 51 of the Commusion's regulations 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 paragraph 3.8 of Facility Operating Li:ense No.
DPR-55 is hereby amended to read as follows:
3.B Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of June 27, 1978.
FOR TijE NUCLEAR REGULAT Y COMMISSION k l &?>
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 6,1978 e
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4 ATTACHMENTS TO LICENSE AMENDMENTS n,
AMENDMENT NO. 62 TO DPR-38 AMENDMENT NO. ': T0 DPR-47 AMENDMENT NO. 59 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove page 3.5-7 and insert the revised identically numbered page.
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If virk ana,..) hou: of' ds:
d-=:1c= of a:.. _=cperable rod, 11 is =c da:ar:1 sed da: c 1%1k/k.het shutd=v: sarg1= exis:s combi =1=g da worth, of de inoperable red vd d each. of da other rods, the reac::: shall be brough: :n da hat sta=dby ce=di:1 =
u=til this _4:31= is establi.shed.
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Folleving the dete==1=a:1 = cf an inep arable : d, all :=ds shall be exar:1. sed vi:' d" 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a=d exercised weekly u=-11 'de ::d problem is solved.
1.
I.f a c== 1 : d i= the res 12:1=g c safery : d g: ups is declarsd i==;erable, pcver shall be reduced := 60 per==== ci the tha - pcver a.11:vable f : the reae::: c:ela= pu=p c==-
I bi=a:ics.
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If a c== 1 : d i=. de reg =12:1=g er axial pcver shaping g:=ps is declared i==perabia, opers:'c= above 60 per:s== cf :s:ec power =ay c=-*- a A.s.ded tha ::c.s i= de p:up are pesi:1:=ed such ": de ::d..ha: vas der' n ed i= per ble is =212.=i=ed Vi* ' # ** a1107abla p dp average pCsi:,.O ' # d :3 Cf Speed #' :3:# ::.
3.5.1.2.a a=d de vidd:= val. I' d :s c:' spe d'd-*:1:=.3.3.2.3.c.
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1, 3.5.2.3 Iha vc:-'a ci singla. i=ser.ed c:=
'.::d.s du:1 ; c.-i d - 7 il ara i d d ::d by :he res=1:,1:=3 of Specift:=_i:= 3.1.,3 d a=d :=e.
C=:201 ::. ;;cs1:i0.1'~":s defined i: 5:ectii:.2.1:= 3.5.2.f.
i 3.5.2.1 Quadra=: ?:ver 11:
q a.
Except for ph7s
-a tes:s, if tha a=i=== posi:17e quadra== pc.er d
tilt exceeds 3.41% Unit 1, el der :ne quacrant pcVer :il sha'1 3.11% Uni: 1 3.41 U:1: 3 be. reduced to less tha= 3.41% Uni: 1 vi-
- se hours or tha I
.T.4I U:1: 2 3.41% C=1: 3 fc11=v'.=g aetic=s shall be taken:
0 (1) If four : sac:=r c ola== pu=ps are is. Operatic =, the allevable ther=al pcver shall be reduced belev da power level en: ff i
(as ident.ified in specif'-':1 = 3.5.2.3) and fur:her reduced by 2% of full pcver fer each.1
- d ' : i= e=:es s o f 3. 41 *.' t=1: 1.
3.41; Uni: 1 3.41% C=1: 3 (2) If less than. four reac::: coolan pu==s are in operatic =, the allevable ther=al power for :he :=_ac::: coola== pu=p co-.:1=a::.:=
. shall be reduced by 2" of full pcver for each 1*. til:.
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- This requirement dcas not apply in the case of Ro ~6 of Safety G.oup 4 of Unit 2 until July 1,1978. The power reduction will not be required due to tne inoperability of this rod for the limited period thrcugh July 1, 19'*3 or untii the licensee obtains information indicating that this rod may r.ot be capaele of performing its assigned safety function, wnichever oce:.rs firs +
1 I l 3.5-7 knendment Nos. 62, 62 & 59
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