ML20086H842
| ML20086H842 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/27/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20086H845 | List: |
| References | |
| DPR-66-A-189, NPF-73-A-071 NUDOCS 9507180295 | |
| Download: ML20086H842 (9) | |
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4 UNITED STATES j ~
j NUCLEAR REGULATORY COMMISSION
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DV0VESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STfl10LN. UNIT N0.1
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.189 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 8,1993, as supplemented June 15, 1995, 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 i
Commission; 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 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 Pcet 51 of the Commission's regulations and all applicable requirements have been satisfied.
9507100295 950627 PDR ADOCK O5000335 P
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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.-(2) of Facility Operating License No. DPR-66 is hereby I
amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.189,- are hereby 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, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
&7 J Dn F. Stolz, Diredor oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27,1995
'l
ATTACHMENT 10 LICENSE AMENDMENT NO 189 FACILITY OPERATING LICENSE NO. DPR-66 QQCEET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Egmqy_q insert 1-8 1-8 6-19 6-19
DPR-66 e
DEFINITIONS l
2)
Major changes in the design of radwaste treatment systems (liquid, gaseous and solid) that could significantly increase the quantities or activity of effluents released or volumes of solid waste stored or shipped offsite from those previously considered in the FSAR and SER (e.g.,
use of asphalt system in place of cement);
3)
Changes in system design which may invalidate the accident analysic as described in the SER (e.g.,
changes in tank capacity that would alter the cmries released); and 4)
Changes in system design that could potentially result in a
significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate shielding provisions)
MEMBER (S) OF THE PUBLIC 1.36 MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated w'.th the plant.
This category does not include employees of the utility, its contractors or its vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries and pe. sons who traverse portions of the site as the consequence of a public highway, railway or waterway located within the confines of the site boundary.
This category does include perso s who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
CORE OPERATING LIMITS REPORT 1.37 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle.
These cycle-specific core operating limits shall be determined for each reload cycle in accordance with bracification 6.9.1.12.
Plant operation within these operating l
limits is addressed in individual specifications.
1 i
BEAVER VALLEY - UNIT 1 1-8 Amendment No.189
DPR-66 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTI4) 6.9.1.11 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted before April 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
CORE OPERATING LIMITS REPORT 6.9.1.12 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a
reload cycle.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
1.
" WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (Westinghouse Proprietary).
Methodology applied for the following Specifications:
1 3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control 3.2.2, Heat Flux Hot Channel Factor-F9(Z) 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H 2.
WCAP-10266-P-A Rev. 2 / WCAP-11524-NP-A Rev.
2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"
- Kabadi, J.
N., et al., March 1987; including Addendum 1-A " Power Shape Sensitivity Studies" 12/87 and Addendum 2-A
" BASH Methodology Improvements and Reliability Enhancements" 5/88.
Methodology applied for the following Specification:
3.2.2, Heat Flux Hot Channel Factor-Fg(Z) 3.
" POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT,"
September 1974 (Westinghouse Proprietary).
Methodology applied for the following Specification:
3.2.1, Axial Flux Difference-Constant Axial Offset Control (4) A single submittal may be made for a multi-unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste
- systems, the submittal shall specify the. releases of radioactive material from each unit.
BEAVER VALLEY - UNIT 1 6-19 Amendment No.189
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UNITED STATES s
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,j NUCLEAR REGULATORY COMMISSION
's WASHINGTON, D.C. 20555-0001
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43 DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLED0 EDISON COMPANY DOCKET N0. 50-412 i
BEAVER VALLEY POWER STATION. UNIT 2 tl AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 8, 1993, as supplemented June 15, 1995, complies with the standards and requirements of the Atomic Energy i
Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; l
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 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 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.
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f '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. NPF-73 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shal1~ operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Jd M. Stolz, Direc r
- ject Directorate
-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
. Changes to the Technical Specifications Date of Issuance: June 27, 1995 l
t
A 4
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remova Insert 6-20 6-20 i
i NPF-73 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 2.
WCAP-10266-P-A Rev.
2
/
WCAP-11524-NP-A Rev.
2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"
- Kabadi, J.
N.,
et al., March 1987; including Addendum 1-A
" Power Shape Sensitivity Studies" 12/87 and l
Addendum 2-A
" BASH Methodology Improvements and Reliability Enhancements" 5/88.
Methodology applied for the following Specification:
3.2.2, Heat Flux Hot Channel Factor-F (Z).
q 3.
" POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT,"
September 1974 (Westinghouse Proprietary).
Methodology applied for the following Specification; 3.2.1, Axial Flux Difference-Constant Axial Offset Control.
4.
T.
M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC)
January 31, 1980
Attachment:
Operation and Safety Analysis Aspects of an Improved Load Follow Package.
Methodology applied for the following Specification:
3.2.1, Axial Flux Difference-Constant Axial Offset Control.
5.
NUREG-0800, Standard Review
- Plan, U.S.
Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev.
2, July 1981. Methodology applied for the following Specification:
3.2.1, Axial Flux Difference-Constant Axial Offset Control.
The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic 1
- limits, ECCS
- limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS
- REPORT, including any mid-cycle revisions or supplements
- thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S.
Nuclear Regulatory Commission, Document Control Desk within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a.
ECCS Actuation, Specifications 3.5.2 and 3 N.a.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
BEAVER VALLEY - UNIT 2 6-20 Amendment No.
71