ML20237G487
| ML20237G487 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/14/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237G490 | List: |
| References | |
| NUDOCS 8709020274 | |
| Download: ML20237G487 (7) | |
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT 2 FACILITY OPERATING L10ENSE License No. NPF-73 1.
The' Nuclear Regulatory Com.Jsion (the Comission or the NRC) has found that:
A.
7he application for license filed by the Duquesne Light Company
- octing for itself and as agent for Ohio Edison Company. The Cleveland i
Electric Illuminating Company, and The Toledo Edison Cunpany (the j
licensees), complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the C a ission's regula-j tions set forth in 10 CFR Chapter I, and all required notifications i
to other agencies or bodies have been daly made;
)
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' B.
Construction of the Beaver Valley Power Station, Unit 2 (the facility) has been substantially completed in confomity with Construction Permit No. CPPR-105 and tiie application, as amended, the provisions of the Act, and the regulations of the Comission; l
C.
The facility will operate in conformity with the application, as amer.ded, the provisions of the Act, and the regulations of the Commission (except as exeinpted from compliance in Section 2.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 (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exemoted from compliance in Section 2.0. below);
'*Duquesne Light Company (DLCo) is authorized to act as agent for Ohio Edison Company The Cleveland Illuminating Electric Company, and The Toledo Edison Company and has exclusive responsibility and control over the physical construction, operation, and maintenance of the f6cility.
87090202'74 G70814 PDR ADOCK 05000412 P
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. E.
Duquesne 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; F.
The lhensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this i
Facility Operating License No. NPF-73 is subiect to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable 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 eccordance-with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
2.
Based on the foregoing findings, review by the Nuclear Regulatory Commission at a meeting on July 8, 1987, and approval by the Commission on August 13, 1987, the License for Fuel Loading and Low Power Testing, License No. NPF-64, issued on May 28, 1987, is superseded by Facility Operating License NPF-73, hereby issued to the Duquesne Light 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, a pressurized water reactor and associated equipment (the facility) owned by Ohio Edison Company, The Cleveland Electric Illuminating Company, and The Toledo Edison Company an6 owned and operated by the Duquesne Light Company. The facility is located on the licensees' site on the southern shore of the Ohio River in Beaver County, Pennsylvania, approximately 22 miles northwest of Pittsburgh and 5 miles east of East Liverpool, Ohio, and is described in Duquesne Light Company's Final Safety Analysis Report, as supplemented and amended, and in its Environmental Report, as supplemented and amended; B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Pursuant to Secticn 103 of the Act and 10 CFR Part 50, Duquesne Light Company to posse:s, use, and operate.the facility at the designated location in Beaver County, Pennsylvania, in 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 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, Duquesoe 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 Final Safety Analysis Report, as supplemented and amended; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, Duquesne
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Light Company to receive, possess, and use at any time any byproduct, source, and special n clear material such as sealed neutron sources for reactor startup, sealed sources for reactor 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 form, for sample analysis or instrument calibration or other activity associated with radioactive apparatus or componen'cs; j
(6) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, Duquesne Light Company to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.
j C.
This license shall be deemed to contain and is subject to the conditions specified in the Comission's reguhtions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level DLCo is authorized to operate the facility at reactor core power levels not in excess of 2652 megawatts thennal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. DLCo shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
. (3)
Initial Startup Test Program (Section 14 of the SER, and.
supplements 3 and 5)
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 one month of such change.
(4) Fresh Fuel Storage The following criteria apply to the storage and handling of new fuel assemblies in the fuel handling building:
(a) No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any 1
one time.
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(b) The minimum edge-to-edge distance between the above two new assemblies, the shipping container array, and the storage rack arrays shall be at least 12 inches.
(c) New fuel assemblies shall be stored in such a manner that -
water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.
(5)
Inservice Inspection (Section 6.6 of SER Supplement 5)
. ',4 DLCo shall submit an inservice inspection program in accordance with 10 CFR 50.55a(g)(4) for staff review by June 1, 1988.
(6) Fonnal Federal Emergency Management Agency Finding In the event that the NRC finds that the lack of progress in a
completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an l
indication that a major substantive problem exists in achieving y
or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
(7) Plant Safety Monitoring System (PSMS)
DLCo sh611 submit, on or before November 27, 1987, a O
verification and validation (V&V) plan which will be able to I
demonstrate the reliability of the PSMS software. The approved V8V plan must be implemented before startup after the first refueling outage.
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(8) Detailed Control Room Design Review (DCRDR)
Before startup after the first refueling outage, DLCo shall complete all activities, satisfactorily resolve all open issues as described in Section 18.1 of SER Supplement 6, and implement all DLCo-proposed control room improvements resulting from this review.
(9) Safety Parameter Display System (SPDS)
Before startup after the first refueling outage, DLCo shall perform the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to issues as described in Section 18.2 of SER Supplement 6.
(10)
Fire Protection Modifications (Section 9.5.1 of SER Supplement 6)
'By September 30, 1987, DLCo shall complete the installation of back draft dampers to mitigate overpressurization caused by carbon dioxide system discharge. Until the time that this work is complete, DLCo shall maintain fire watches in those areas in accordance with the commitments made in letters dated May 20 and 21, 1987.
D.
Exemptions The following exemptions are authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
j (1) The facility requires an exemption from the requirements of General Design Criterion (GDC) 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)(1),
10 CFR 50.12(a)(2)(ii) and (iv), Beaver Valley Power Station, Unit 2 is exempt frem the requirements of 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 leading 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, l
. safety injection system, and residual heat remov'al system.
This exemption will expire when the current GDC 4 rGlemaking changes have been completed.
(2) The facility requires an exemption from the requirements of 10 CFR 50, Appendix J, Section III.D.2(b)(fi). The justification 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 12, 1987 (52 FR 17651). Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12(a)(2)(11) and (iii), Beaver Valley Power Station, Unit 2 is exempt from the quoted requirement and instead, is required to perform the overall air lock leak test at pressure P before establishing containment integrity if air lock maintenanc8 has been performed that could affect the air lock sealing capability.
(3) The facility was previously granted an exemption from the criticality 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.
E.
Physical Security DLCo shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission 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.
1 F.
Fire Protection Program (Section 9.5.1 of SER Supplement 3)
DLCo shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report through Amendment No. 17, and and submittals dated May 18, May 20 May 21, June 24 and July 6, 1987, and as described in the Safety Evaluation Report dated October 1985, and Supplements 1 through 6, subject to the following provision:
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DLCo may make changes.to the approved fire protection.
program without prior approval of the Comission only if
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those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G.
Reporting to the Commission Except as otherwise provided in the Technical Specifications.or Environmental Protection Plan, DLCo shall report any violations of the requirements contained in Section 2.0 of this license in the following manner:
initial notification shall be made within twenty-four (24) hours to' the NRC Operations Center via the Emergency Notification System with written followup within 30 days in 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 Comission shall_ require'in accordance with Section 170 of the Atomic Energy Act of 1954, as.
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amended, to cover public liability claims.
I.
Expira. tion This license is effective on the date of issuance and shall expire at midnight on May 27, 2027.
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FOR THE NUCLEAR REGULATORY COMMISSION
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Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
j 1.
Appendix A - Technical Specifications (NUREG-1279)
I 2.
Appendix B - Environmental Protection Plan
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Date of Issuance:
August 14 1987 c
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