ML20040G452
| ML20040G452 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/29/1982 |
| From: | Crutchfield D, Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20040G453 | List: |
| References | |
| DPR-19-A-066, DPR-25-A-058 NUDOCS 8202160054 | |
| Download: ML20040G452 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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WASHINGTON, D. C. 20555
%..... /c COMMONWEALTH EDISON COMPANY 5
DOCKET NO. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE
, g Amendment No,66
' License No. DPR -19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (thelicensee)datedOctober 30, 1981 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 t'he' application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endan.gering the health and safety of the public, and (ii) that such activities will be
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conducted in compliance with the Cofnmission's regulations;.
D.
Theissuanceo[thisamendmentwillnotbeinimicaltothecommon 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 Comission's regulations and all applicable requircmants have been satisfied.
2.
Accordingly, the licens'e is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.B of Provisional License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.66, are hereby incorporated in the' license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8202160054 820129
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PDR ADDCK 05000237 P
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COM4ISSION 1,
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DennisM.Crutchfield,d5tef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
January 29, 1982 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE NO: DPR-19
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DOCKET N0!'50-237
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Revise the Appendix "A". Technical Specifications as follows:
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3.7 LIMITING CONDITION FOR OPEltATION 4.7 SURVEIIJANCE HEQUIRIMNIS above. In connection with d.
A visual inspection of the suppression such testing, the pooi temper-chamber interior, including waterline ature must be reduced to below regions, shall be made at each major the normal power operation limit refueling outage.
'specified in (1) above within le 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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T y.J (3) 'Ihe reactor shall be scramed from any operating condition if p pool temperature reaches
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-110 F.
' Power operation shall 1
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not be resumed until the pool
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,the normal operation limit l
specified in (1) above.
'(4)i During reactor isolation
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l conditions, the reactor tpressure vessel shall be depressurized to less than
- 150 psig at normal cooldown rates if thg pool temperature reaches 120 F.
d.' Maximum downcomer sutmergence is 4.00 ft.
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Minimum downoamer submergence is 3.67 ft.
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If Specifications 3.7.A.l.a or 3.7.A.l.b are not met and suppression pool water volume cannot be restored within the sub-a i
sequent 'six (6) hour period, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Primary containment integrity shall be maintained 2.
'1he primary containment integrity *shall be at all times when the reactor is critical gr when demonstrated by either Method A or Method B, the reactor water temperature is atxwe 212 P and as follows:
fuel is in the reactor vessel except while performing low power physics tests at atmospheric pressure at power a.
Integrated Primary Containment Imak Test levels not to exceed SMw(t).
(IPCLT)
Amendment No. 66 108A
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UNITEp STATES NUCLEAR REGULATORY COMMISSION 3
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,E WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 '
f DRESDEN STATION UNIT NO. 3 4
AMENDMENT TO FACILITY OPERATING LICENSE
' Amendment No.58 License No. DPR-25 1.
The Nuclear Regulatory Commission (the.Comission) has found that:
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A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated October 30, 1981 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; 8.
The facility will operate in conformity with th'e ' application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the acitivities authorized by this amendment can be conducted without endan.gering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cominission's regulations;
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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; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable j
requirements have been satis.fied.
1 2.
Accordingly, the license is. amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.B of Facili ty Operating. Li. cense _No. DPR-25. _. __. \\
'is hereby amended to read as follows:
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B.
Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 58, are hereby. incorporated in the license.
The licensee shall operate the facility in i
l accordance with the Technical Specifications.
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'2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY t.3MMISSION nd :,r).
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Daca-of Issuance: January 29, 1982 e
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e ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACILITYOPERATINdLICENSEN0.DPR-25 DOCKET NO. 50-249 Revise the Appendix "A" Technical Specifications as follows:
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i 3.7 LIMITING ENDITION FOR OPERATION 4.7 SURVEIIJANCE REQUIRIMNIS above. In connection with d.
A visual inspection of the suppressicn such testing, the pool tempe.:-
chamber interior, including waterline ature must be reduced to belas regions, shall be made at each major I
the normal power operation limit refueling outage.
specified in (1) above within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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(3) %e reactor shall be scranmed ii.
from any operating condition.
if p pool temperature reaches
.110 F.. Power operation shall not be resumed until the pocl temperature is reduced below the normal operation limit specified in (1) above.
~. (4) 1During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 150 psig at normal cooloown rates if thg pool temperatute reaches 120 P.
a d..
Maxinman downoomer submergence is 4.00 ft.
e.
Minimum downoomer sutmergence is 3.67 ft.
f.
If Specifications 3.7.A.1.a or 3.7.A.l.b are not met and suppression pool water volume cr.nnot be restored within the sub-sequent six (6) hour period, an orderly shutdown shall be initiated and the reactor
.i shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1
.l 2.
Primary containment integrity shall be maintained 2.
%e primary contairunent integrity shpil be at all times when the reactor is critical gr when demonstrated by either Method A or Method B, the reactor water temperature is atxne 2A2 F and as follows:
I fuel is in the reactor vessel except while performing low power physics tests at atmospheric pressure at power a.
Integrated Primary Containment Ieak Test levels not to exceed SMw(t).
(IPCLT)
Amendment No. 58 108A i.
,