ML19341A429
| ML19341A429 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/31/1980 |
| From: | Crutchfield D, Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341A430 | List: |
| References | |
| NUDOCS 8101230503 | |
| Download: ML19341A429 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION y
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WASHINGTON, D. C. 20555 g
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 54 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated July 31, 1978 as supplemented September 11, 1978, January 12, 1979, and June 26, 1979, 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 forth in 10 CFR Chapter I;
'N B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 conpliance with the Comission'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; i
and E.
The issuance of this amendment 1.4 in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 8101230 N
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Accordingly, the license is amended by changes to the Technical Specifi".ations as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating 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. 54, are herehy incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7M.MU)
Dennis M. Crutchfield, Chfef Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 31, 1980 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 54 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237
' Change the Appendix A Technical Specifications by removing the pages described below and inserting the enc.losed pages. The revised pages are identified by the captioned amendment numoer contain vertical lin's indicating the area of change.
REMOVE INSERT 91 91 98 98 98a 100-107 100-107 (Intentionally Blank) 4 i
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3.6 LIMITING CONDITION FOR OPERATION 4.6
$URVEILLANCE REQUIREMENT l
1.
Structural Integrity F.
S t ructura l Integrity 1.
Beginning November 1,1978, and The strt ctural integr',ty of the primary system bcundary shall be maintained at updated every 40 months thereafter, the level required by the ASME Boller and the component inservice inspection Pressure Vessel Code,Section XI, " Rules program shall f>e performed in accordance with Section XI of the for Inservice Inspection of Nuclear Power ASME Boiler and Pressure Vessel Plant Components".
Code and Addenda 'as required by Components of the primary system boundary 10 CfR 50, Section 50.SSa(g),
whose inservice examination reveals the except where specific written absence of flaw indications or tiew in-relief has been given liy the dications not in excess of the allowable fil(C pursuarit to 10 Cl~lt 50 Indication standards of this Code are Section 50.SSa(g)(6)(i).
' acceptable for continued service. Plant operatirn with components which have in-service examination flaw indication (s) in excess of the allowable indication standards of the Code shall be subject to NRC approval.
Components whose inservice examination a.
reveals " flaw indicaition(s) in excess
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of the allowable Indication standards of the ASME Code,Section XI, are un-acceptable for continued service un-less the following requirements are met:
91 Amendment No. 36, 54 k
o The perfor snee of resct:r coolcnt leakaga da-Inservica inspections cf ASME Code tcction system will be evaluatcd during tha first C1 css 1, 2 cnd 3 components wil,1 be five years of station operation and the conclusions performed in accordance with the ap-of this evaluation will be reported to the NRC.
plicable version of Sect ion XI of the ASME noller and Pressurc Vessel Code.
it is estimated that the main steam line tunnel Relief from any of the above require-leakage detection system is capable of detecting ments must be provided bi writing by the order of 3000 lb/hr.
the Commission. The Inservice inspec-The system perfor-tion program and the written reIIef mance will be evaluated during the first five do not form a part of these Technical years, of plant operation and the conclusions of-Specifications.
the evaluation will be reported to the NRC.
E.
Safety and Relief Valves - The frequency and testing requirements for the safety and re-lief alves are specified in the Inservice Te..ag Program which is based on Section XI of the ASME Boiler and Pressure Vessel Code.
Adherence to these code requirements provides adequate assurance as to the proper operational readiness of these valves. The tolerance value is specified in Section til of the ASME Boller and Pressure Vessel Code as + 1% of design pressure. An analysis has been performed which shows that with all safety valves set I% higher the reactor coolant pressure safety limit of 1375 psig is not exceeded. The safety valves are required.to be operable above the design pressure (90 psig) at which the core spray subsystems are not designed to deliver full flow.
F.
Structural integrity - A pre-service inspection of the components in the primary coolant pressure boundary will be conducted after site erection to assure the system is free of gross defects and as a reference base for later inspections.
Prior to operation, the reacto'r primary system will be free of gross defects.
in addition, the facility has been designed such that gross defects should not occur throughout life.
98 Amendment No. 26, 54
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(Intentionally Blank) e 100-107 Amendment No. 54
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION o
E WAsHINCToN D. C. 20$55 f
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated July 31, 1978 as supplemented September 11, 1978, January 12, 1979, and June 26, 1979, 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 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 amerdment 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 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.
k
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility Operating License No.
DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 47, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci fications.
^
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION o
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical
- Speci fications Date of Issuance:
December 31, 1980 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 47 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249
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Change t'he Appendix A Technical Specifications by removing the pages described below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 91 91 9
98 98 98a 100-107 100-107 (Intentionally Blank) e T
e i
I 4
e m
3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVE'lLLANCE REQUIREMENT f
F.
Structural Integrity 1.
Structural integrity The structural integrity of the primary 1.
Beginning November 1,1978, and system boundary shall be maintained at updated every 40 months thereafter, the level required by 'the ASME Boller and the component inservice inspection Pressure Vessel Code,Section XI, " Rules program shall be performed in for Inservice inspection of Nuclear Power accordance with Section XI of the Plant Components".
ASME Boiler and Pressure Vessel Code and Addenda as regiired by Components of the primary system boundary 10 CFR 50, Section 50.55a(g),
whose
- ervice examination reveals the except where specific written absence.cf flaw Indications or flaw In-relief has been given by the dications not in excess of the allowable ilRC purs:(dent, to 10 Clit 50, Indication standards of this Code are section 50.55a(g)(6)(i).
acceptable for continued service.
Plant operation with components which have in-service examination flaw Indication (s) in excess of the allowable indication standards of the Code shall be subject to NRC approval.
a.
Lam-.acnts whose inservice examination
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re-exts flaw indicaition(s), excess e fac *llowable Indication sc. 'ards r
C Se & AE Code,Section XI, a.s un-Orat,nce7e for continued service un-Icss the Psilowing requirements are met:
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'l Amendment No. Sr5, 47
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A j:
The parformanca of reacter coolant leakags da-
. inssrvica inspecticns of ASME, Code
.f s
-Section system will be evalustsd during tha first Cicss 1,'2 cod 3 components will be 1
five years of station operation and the conclusions performed in accordance with the ap-of this evaluation will be reported to the NRC.
plicable version of Section XI of the-ASME Boller and Pressure Vessel Code, It is. estimated-that the main steam line tu:ael Relief from any of the above require-leakage detection system is capable of detecting ments must be provided in writing by the order of 3000 lb/hr.
the Commission. The inservice inspec-The system perfor-tion program and the written relief mance will be evaluated during the first five.
do not form a part of these Technical years of plant operation and the conclusions of Specifications.
the, evaluation will be reported to the NRC.
E.
Safety and Relief Valves - The frequency and testing requirements for the safety and.re-lief valves are specified.in the Inservice i
Testing Program which is based on Section XI of the ASME Boiler and Pressure Vessel Code.
Adherence to these code requirements provides adequate assurance as to the proper operational readiness of these valves. The tolerance value is specified in Section lil of the ASME Boiler and Pressure Vessel Code as + 1% of design pressure. An analysis has been performed which shows that with all safety valves set 1% higher the reactor coolant pressure safety limit of 1375 psig is not exceeded. The safety valves are required to be operable above the design pressure (90 psig). at which the core spray subsystems are not designed to deliver full flow.
i F.
Structural integrity - A pre-service inspection of the components in the primary coolant pressure boundary will be conducted after site erection i
to assure the system is free of gross defects and as a reference base for later inspections.
Prior to operation, the reacto'r primary system will be free of gross defects.
In addition, the facility has been designed such that gross defects should not occur throughout life.
98 Amendment No. 75, 47 1
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(IntentionallyBlank) i 1
i 100-107 Amendment No. 47