ML20214V425
| ML20214V425 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/28/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co |
| Shared Package | |
| ML20214V428 | List: |
| References | |
| NUDOCS 8706120098 | |
| Download: ML20214V425 (9) | |
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UNITED STATES
! % e g,j NUCLEAR REGULATORY COMMISSION
. L., K.,
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4 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC flLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCXET NO. 50-412 REAVER VALLEY POWER STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-64 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for license filed by the Duquesne Light Company
- acting for itself and as agent for Ohio Edison Company. The Cleveland Electric Illuminating Company, and The Toledo Edison Company, (the licensees), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regula-tions set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Beaver Valley Power Station, Unit 2 (the facility) has been substantially completed in conformity with construction Pemit No. CPPR-105 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.
The facility will operate in confomity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section t.D.
below)
D.
There is reasonable assurance:
(1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations set Section2.0,below)pter!(exceptasexemptedfromcompliancein forth in 10 CFR Cha "Duquesne Lfght Company is authorized to act as agent for Ohio Edison Company.
The Cleveland Illuminating Electric Companyl over the physical construction, and The Toledo Edison Company and has exclusive responsibility and contro operation, and maintenance of the facility.
070612o090 070520 fDR ADOCK 05000412 l
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E.
Ducuesne Light Company is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; i
F.
The licensees have satisfied the applicable provisions of 10 CFR l
Part 140, " Financial Protection Requirements and Indemnity l
Agreements," of the Comission's regulations; 4
G.
The issuance of this license will not be inimical to the comon 4
j defense and security or to the health and safety of the publict 1
H.
After weighing the environmental, economic, technical, and other i
benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-64, is subject to the conditions for protection of the environment set forth in the Environmental i
Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable 4
requirements have been satisfied; I.
The receipt, possession and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40, and 70.
t 2.
Based on the foregoing findings regarding this facility and satisfaction f
of conditions therein imposed. Facility Operating License No. NPF-64 is hereby issued to the Duquesne Licht Company.' Ohio Edison Company The Cleveland Electric Illuminating Company, and The Toledo Edison Company, (the licensees) to read as follows:
A.
This license applies to the Beaver Valley Power Station Unit 2 J
a pressurized water reactor and associated equipment (the facility) 3 owned by Ohio Edison Company. The Cleveland Electric illuminating Company, and The Toledo Edison Company and owned and operated by the Duquesne Light Company. The facility is located on the i
licensees' site on the southern shore of the Ohio River in Beaver 2
County, Pennsylvania, approximately 22 miles northwest of Pittsburgh and 5 miles east of East Liverpool, Ohio, and is described in i
Duquesne Light Company's Final Safety Analysis Report, as supplemented and amended, and in its Environmental Report, as supplemented and amended; i
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! l B.
Subject to the ecnditions and requirements incorporated herein, the Comission hereby licenses:
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, Duquesne Light Company to possess, use, and operate the facility at the designated location in Beaver County, Pennsylvania, in
'i accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 50, Ohio Edison Company, The Cleveland Electric Illuminating Company, and The Toledo Edison Company to possess the facility at the designated l
location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in the license; (3) Pursuant to the Act and 10 CFR Part 70, Duquesne Light Company to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the l
Final Safety Analysis Report, as supplemented and amended; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. Duquesne Light Company to receive, possess, and use at any time any byproduct, source, and special nuclear material such as sealed neutron sources for reactor startup, sealed sources for reactor j.
instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 Duquesne Light Company to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical fom, for sample analysis or instrument calibration or associated with radioactive l
apparatus or components; j
(6) Pursuant to the Act and 10 CFR Parts 30, 40, and 70. Duquesne i
Light Company to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation l
of the facility authorized herein.
C.
This license shall be deemed to contain and is subject to the conditions I
specified in the Comission's regulations set forth in 10 CFR Chapter I l
and is subject to all applicable provisions of the Act and to the rules, i
regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated i
below:
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i (1) Maximum Power Level Duquesne Light Company is authorized to operate the facility at reactor core power levels not in excess of 2652 megawatts thermal (100 percent power) in accordance with the conditions specified herein and in Attachment 1 to this license. The preoperational tests, startup. tests and other items identified i
in Attachment I to this license shall be completed as specified.
- is hertby incorporated into this license. Pending Comission approval, this license is restricted to reactor core power levels not to exceed 5 percent of full power (133 megawatts thermal).
1 (2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A and the i
Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this ifcense. Duquesne Light Company shall operate the facility in accordance with the Technical Specifications and the 4
j Environmental Protection Plan.
(3) Initial Startup Test Program (Section 14)*
[
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within i
one month of such change.
(4) Fresh Fuel Storace The following criteria apply to the storage and handling of i
new fuel assemblies in the Fuel Handling Building:
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(a) No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any l
one time.
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(b) The minimum edge-to-edge distance between the above two new 1
assemblies, the shipping container array, and the storage rack arrays shall be at least 12 inches.
)
d (c) New fuel assemblies shall be stored in such a manner that j
water would drain freely from the assemblies in the event i
of flooding and subsequent draining of the fuel storage area.
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l "The parenthetical notation following the title of license conditions denotes i
the section of the Safety Evaluation Report and/or its supplements wherein j
the license condition is discussed.
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(5) Formal Federal Emeroency Management Agency Findino In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adecuate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
(6) Fire Protection (Section 9.5.1)*
i Prior to exceeding 5% power Duquesne Light Company shall:
(a) Identify to the NRC all unsupervised fire alam circuits, including actuation and alarm annunciation circuits.
Duquesne Light Company shall develop and implement a test procedure, to confirm the operability of these circuits.
The test shall be performed on a frequency not to exceed once per 31 days.
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(b) Complete installation of all fire protection provisions in accordance with its commitment to Standard Review Plan Section 9.5.1, and as identified in the Final Safety Analysis Report.
Until that time, Duquesne Light Company shall maintain fire watches in those areas in accordance with its comitment in letters dated May 20 and 21,1987.
(7) Plant Safety Monitoeing System (PSMS)
Duouesne Light Company shall submit within six months from the date of the low-power license a verification and validation (V8V) plan which will be able to demonstrate the reliability of -
the PSMS software. The approved V&V plan must be implemented prior to startup following the first refueling outage.
D.
Exemptions Th'e following exemptions are authorized by law and will not endanger life ar property or the common defense and security, and certain special circumstances are present. With the granting of these eenptions, the facility will operate, to tile extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission.
(1) The facility requires a schedular exemption from the requirements of General Design Criterion 4, Appendix A to '
10 CFR 50. The staff has described in detail in Supplement 4 and Supplement 5 to the Safety Evaluation Report the technical basis and "special circumstances" associated with this exemption.
The staff's environmental assessment was published on March 27, 1987 (52 FR 9979). Therefore, pursuant to 10 CFR 50.12(a)(li, 1
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w 6-10 CFR 50.12(a)(2)(11) and (iv), Beaver Valley Power Station, Unit 2 is exempt from the requirements of General Design Criterion (GDC) 4, Appendix A to 10 CFR 50 with respect to the dynamic loading effects associated with the postulated pipe breaks described in detail in Section 3.6.3 of Supplement 4 to the Safety Evaluation Report. These dynamic loading effects include pipe whip, jet impingement, and break-associated dynamic transients. Specifically, this eliminates the need to install jet impingement barriers and pipe whip restraints associated with postulated pipe breaks in the pressurizer surge line, reactor coolant bypass system, safety injection system and residual heat removal system. This exemption will expire upon completion of the current GDC-4 rulemaking changes.
(2) The facility requires a technical exemption from the requirements of 10 CFR 50, Appendix J Section III.D.2(b)(ii). The.iustification of this exemption is contained in Section 6.2.6 of Supplement 5 to the Safety Evaluation Report. The staff's environmental assessment was published on May 11, 1987 (52 FR 17651). Therefore, pursuant to 10 CFR 50.12(a)(1), 10 CFR 50.12(a)(2)(ii) and (iii),
Beaver Valley Power Station, Unit 2 is exempt from the quoted i
requirement and instead, is required to perform the overall air lock leak test at pressure P prior to establishing containment integrity if air lock mainteAance has been performed that could affect the air lock sealing capability.
(3) The facility requires a schedular exemption from 10 CFR 50.55a(h), which requires compliance with IEEE Standard 279-1971 pertaining to feedwater isolation on a high steam generator level. The staff has documented its review in Section 7.3.3.12 of Supplement 5 to the Safety Evaluation Report. The staff's environmental assessment was published on May 11, 1987 (52 FR 17651).
Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12(a)(2)(v),
Beaver Valley Power Station, Unit 2, is granted a schedular exemp-tion to postpone installation of the steam generator high level median selector, which is reouired to ensure that fee Gater isolation on high steam generator level is in compliance with IEEE Standard 279-1971, to the end of the first refueling outage.
(4) The facility was previously granted an exemption from the criti-cality alarm requirements of 10 CFR 70.24 (See License No.-
SNM-1954 dated April 9,1986, which granted this exemption).
Beaver Valley Power Station, Unit 2 is hereby exempted from the criticality alarm system provisions of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
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- E.
Physical Security Duquesne Light Company shall fully implement and maintain in effect all provisions of the physical security, guard training and qualifi-cation, and safeguards contingency plans previously approved by the Comission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled:
" Beaver Valley Power Station Security Plan," with revisions submitted through April 15,1987; " Beaver Valley Power Station Security Training and Qualification Plan," with revisions submitted through April 15, 1987; and Beaver Valley Power Station Security Contingency Plan," with revisions submitted through February 19, 1987.
F.
Fire Protection Program (Section 9.5.1)*
Duquesne Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as amended and as described in the Safety Evaluation Report dated October 1985, and Supplements 1 through 5, subject to the following provision below:
Duquesne Light Company may make changes to the approved fire protection program without prior approval of the Comissior only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G.
Reportino to the Commission Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Duquesne Light Company shall report any violations of the requirements contained in Section 2.C of this license in the followin initial notification shall be rade within twenty-four (24)g manner: hours to the NRC Operations Center via the j
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Emergency Notification System with written follow-up within 30 days in i
accordance with the procedures described in 10 CFR 50.73(b).(c) and (e).
H.
Financial Protection The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
_ I.
This ifcensb is effective as of the date of issuance and shall expire at midnight on May.27, 2027.
FOR THE NUCLEAR REGULATORY COMMISSION
'2-n Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1.
2.
Appendix A - Technical Specifications (NUREG-1259) 3.
Appendix B - Environmental Protection Plan Date of Issuance: May 28,1987 a
- to Operating License NPF-64 Prior to criticality:
1.
Resolve outstanding items related to emergency preparedness as defined in Unresolved Items 87-14-09, 87-14-17, 87-14-18, 87-14-19, 87-14-20, and 87-14-21.
2.
Complete installation of electrical cable wrapping and tray covers to meet the comitment to Regulatory Guide 1.75.
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