ML19344E222
| ML19344E222 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/08/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19344E221 | List: |
| References | |
| NUDOCS 8008280147 | |
| Download: ML19344E222 (11) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-39 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Connonwealth Edison Company (the licensee) dated May 27, 1977, as supplemented by letters dated June 29, August 9 and December 13,1977, March 15,1978, June 28 and October 26, 1979, and March 4,1980, conplies 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 f acility will operate in conformity with the application, the provisions er 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 endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the connon 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 gf the Comission'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 2.C.(2Lof Facility Operating License No. DPR-39 is herehy amended to read as follows:
(2) Technical Specifications The Tichnical Specifications contained in Appendicer A and B, as revised through Amendment No. 55, 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 I
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e Operating Reactors r nch #1 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8,1980 t
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o COMMONWEALTH EDISON COMPANY DOCKET N0. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-48 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated May 27, 1977, as supplemented by letters dated June 29, August 9 and December 13,1977, March 15,1978, June 28 and October 26, 1979, and March 4,1980, conplies 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 Comission; C.
There is reasonable assurance (i) that the activitics authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon l
defense and security or to the health and safety of the public; and
'I E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Comission's regulations and all applicable requirements have been satisfied.
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2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C (2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendment No. 52, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
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- Nga, perating Reactors.
anch #1 Division of Licens'n
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8,1980 J
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' ATTACMENT TO LICENSE AMENDMENTS AMENDMENT NO. S5 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT r:0. 52 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET N05. 50-295 AND 50-304 Revise Appendix A as follows:
Recove Pages Insert Pages 94 94(correctedpage) 102 102 104 104 1
106-117 119 119 328a 328a (corre-ted page) t e
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We repair period of 7 days is based on Bases: tow Temperature Overpressure Protection allowing suf ficient time to effect repairs using safe and proper procedures and upon 3.2.2.G There are 3 means of protecting the the coerability of the redundant IVRV.
t, RCS from overpressurization by a we 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period to reach the 4.3.2.G pressure transient at low testperatures restrictive conditions in the pressurizer (telow 250 F). The first type of prcuides sof ficient time to meet these protection is ensured by the operation conditions.
and surveillance of the power operated relief valves with a lift setting of 435 psig.
5 ne Irw Temperature Overpressure Protection System A single power operated relief valve (PORV) will r:ust be tested on a periodic basis consistent with relieve a pressure transient caused by 1) a mass the need for its use. A chanr.el functional test shall addition into a solid TS from a charging ptanp be pdfor.aed prior to enablinq the overpressure or 2) a heat input based on a reactor coolant protection system during cooldown and startup. %is rumo being started in an idle BCS and circulating test shall be repeated msnthly when the PORVs are 3
water into a steam generator whose tonperature recuired to be operable. The channel functional is 59F greator than the RCS ter:perature. (1) test shall include verification of the backup air supply.
Ooerability of each low temperature overpressure The second means of protection is ensured by a PORV protection channel requires the control switch being open. It will have the same relieving capabilities to be in the proper position, the pressure point I
as trentioned above.
set, the PORV isolation valves open, instrtraent and solenoid power on, and the FORV backup The t'aird means of protection limits the pressurizer level to 25S and the pressurizer pressure to 100 osig, air supply charged.
A pressure transient caused by the inadvertent mass
%e limitations and surveillance requirenents on the addition from a charging pump running for 10 minutes EECS equipnent provides assurance that a mass will te relieved by the large gas 61ume and low pressure addition pressure transient can be relieved by the Nintain-present in the pressurizer as rentioned above.
ing the pressurizer level below 2% will also make the hi operation of a single PORV or the limiting conditions placed on the pressurizer.
pressurizer icvel deviation alarm available to the operator during a mass addition accident.
We restrictions for startup of a PCP limits the heat input accident to within the relieving capabilities of a single PORV.
i (1) Pressure Mitigating Systems Transient Analysis Results July 1977 Westinghouse Owners Group on DCS Overpressurization.
1 94 Amendment tb. 54, Unit 1 Amendment No. 51, Unit 2
l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIRDENT 3.3.4 4.3.4.B manufactured by Westinghouse.
The finished flywheels are subjected i
to 1001 volumetric ultrasonic inspec-tion using Section III Class A code while at the manufacturer.
The finished machined bores are also subjected to magnetic particle, or liquid penetrant examination.
C.
In-Service Inspection 1.
Inservice inspection of ASME Code Class 1, Class 2 and Class 3 com-ponents shall be performed in i
accordance with Section XI of the ASME Boiler and Pressure vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific 4
written relief has been granted by the NRC pursuant to 10CFR50, Section 50.55a(g) (6) (i).
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f 102 Amendment No. 55, Unit 1 Amendment f;o. 52, Unit 2
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4
4.3.4.C.2 I
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3.
Should certain ASME Section XI codct requirements as described in i
Section 4.3.4.C.1, 4.3.4.C.2 or
~3.3.2.E.2 be discovered to be j
impractical due to unforeseen 4
reasons during the process of i
performing inspections, tests, i
or during review, relief will be requested from the specific j
Section XI code requirements at l
that time.
No additional reporting requirements other than those l
specified by Section XI ASME j
Boiler and Pressure Vessel Code are required.
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i Mendment No. 55, Unit 1 104 Mer.dment No. 52, Unit 2 4[' ya
DELETED Pages 106 -117 Amendment tio. 55, Unit 1 Amendment tio. 52, Unit 2 4
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4.3.4 The surveillance inspection program has been developed to comply with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10CFR50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, Section 50.55a(g) (6) (i).
The design of the plant, state of non-destructive testing technology and access to areas to be inspected require such relief.
The materials irradiation surveillance program is designed to evaluate the effects of radiation on the fracture toughness of reactor vessel steel based on the transition temperature approach and the fracture mechanics approach, and is in accordance with ASTM-E-185-70, "Reevennended Practice for Surveillance
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Tests for Nuclear Reactor Vessels." (1)
Reference (1)
FSAR Section 4.5 4
1 119 Amendment J.o. 55, Unit 1 Amendment No. 52, Unit 2
6.6.3.c special Reporta Reports on the following areas shall be as indicated:
SUBMITTAL DATE ARFA a.
Primary Coolant Irakage Initial report within one year of initial criti-cality: 5 years af ter comnercial service.
b.
In-Service Inspection Developnent First in-service inspection perio$ after initial full power operation.
c.
In-Service Inspection Evaluation
'Ihe requirements of Section 11 ASk1E Eciler Code (IS-620),
d.
Icose parts nonitoring program Oi same date as in-service inspection report.
e.
Containment Building Structural Testing Report Within 90 days following empletion of each test.
f.
Iake Michigan Continuing take Study Within 60 days following the end of each 6 nonth Projects No. 1, 6, 9, 10, 11, 12***
routine operating report period. Each report shall contain tabular and graphical information, analysis and interpretation, of information obtained pursuant to each project, g.
Waukegan Menorial Airport Expansion Plans
'Ihe expansion plans and status of such plans for the Waukegan Menorial Airport will be reported yearly in the Annual Report including PAA 45010 report.
h.
O' crpressure Protection Systen Operation Within 30 days cf operation.
- Zion Nuc2 ear Ibwer StaGm Environmental Report, Section 2.3.6, Table 9.
SPII'IAL REPORTS Table 6.6.2 Amendment No. 54, Unit 1 Amendment No. 51, Unit 2 328a