ML20148D937
| ML20148D937 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/23/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20148D943 | List: |
| References | |
| DPR-66-A-203, NPF-73-A-084 NUDOCS 9706020200 | |
| Download: ML20148D937 (11) | |
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20066 4001
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2 DUQUESNE LIGHT COMPANY OHI0 EDIS0N COMPANY PENNSYLVANIA POWER COMPANY QQCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 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 March 10. 1997. complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act).
anc the Commission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will caerate in conformity with the application.
the provisions of t1e Act, and the rules and regulations of the 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 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9706020200 970523 DR ADOCK 0500 4
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Accordingly, the license is amended by changes to the Technical
. Specifications as indicated in the attachment to this license amendment.
1 and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby j
amended to read as follows:
l (2) Technical Soecifications 5
The Technical Specifications contained in Appendix A, as revised through Amendment No.203. are hereby incorporated in the license.
.The licensee shall operate the facility in accordance with the Technical Specifications.
i' 3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION L
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i John F. Stolz. Director Project Directorate I-2 i
Division of Reactor Projects.- I/II j
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 4
j Date of Issuance: May 23, 1997 i
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i ATTACHMENT TO LICENSE AMENDMENT N0.203 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET 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.
Remove Insert 5-1 5-1 6-20 6-20 6-21 6-21 i
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DPR-66 5.0 DESIGN FEATURES 5.1 SITE LOCATION l
The Beaver Valley Power Station Unit No. 1 is located in Shippingport Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.
The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.
The exclusion area boundary has a minimum radius of 2000 feet from the center of containment.
5.2 REACTOR CORE 5.2.1 FUEL ASSEMBLIES The reactor shall contain 157 fuel assemblies.
Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial l
composition of natural or slightly enriched uranium dioxide (UO ) as 2
fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel
- rods, in accordance with approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed w.lth applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases.
A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
5.2.2 CONTROL ROD ASSEMBLIES The reactor core shall contain 48 full length and no part length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
5.3 FUEL STORAGE 5.3.1 CRITICALITY 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having a maximum U-235 enrichment as set forth in Specification 3.9.14; b.
Kegf 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in UFSAR Section 9.12; BEAVER VALLEY - UNIT 1 5-1 Amendment No.203
DPR-66 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 4.
T.
M.
Anderson to K.
Kniel (Chief of Core Performance Branch,
Attachment:
Operation and Safety NRC)
January 31, 1980 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 6.
WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April 1995 (Westinghouse Proprietary).
Methodology applied for the following Specification:
3.2.2, Heat Flux Hot Channel Factor
- Fg(Z)
The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal-mechanical
- limits, core thermal-hydraulic
- 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 on 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 3.5.3.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
c.
Inoperable Meteorological Monitoring Instrumentatior.,
Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
e.
Sealed source leakage in excess of limits, Specification 4.7.9.1.3.
BEAVER VALLEY - UNIT 1 6-20 Amendment No.203
e DPR-66 ADMINISTRATIVE CONTROLS SPECIAL REPORTS (Continued) f.
Miscellaneous reporting requirements specified in the Action Statements for Appendix C of the ODCM.
g.
DELETED h.
Steam Generator Tube Inservice Inspection Results Report, Specification 4.4.5.5.
1.
Liquid Hold Up Tanks, Specification 3.11.1.4.
j.
Gas Storage Tanks, Specification 3.11.2.5.
1 k.
Explosive Gas Monitoring Instrumentation, Specification 3.3.3.11.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five (5) years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All Reportable Events.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License f
a.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
l BEAVER VALLEY - UNIT 1 6-21 Amendment No. 203 i
t** #84 g
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30666-0001
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DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.84 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 March 10, 1997, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Commission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will o)erate in conformity with the application, the provisions of t1e 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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Accordingly..the license is amended by changes to the Technical Specifications as indicated in the attachment to this licen.se 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.84
. and the Environmental Protection Plan contained in Appendix B. both of which are attached hereto are hereby incorporated in the license.
DLC0 shall operate the facility l
in accordance with the Technical Specifications and the Environmental Protection Plan.
f 3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION dk/ a?$My f John F. Stolz. Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 23, 1997 l
ATTACHMENT TO LICENSE AMENDMENT N0.84 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.
Remove Insert 6-20 6-20 6-21 6-21
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NPF-73 i'
ADMINISTRATIVE CONTROLS I
CORE OPERATING LIMITS REPORT (Continued) 1 2.
WCAP-10266 P-A Rev.
2
/ WCAP-11524-NP-A Rev.
2, "The 1981 i
Version of the - Westinghouse ECCS Evaluation Model Using the i
BASH Code," Kabadi, J.
N.,
et al.,
March 1987; including i
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 TOPICAL REPORT,"
September 1974 (Westinghouse 4
PROCEDURES 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,
Attachment:
Operation and Safety NRC) January 31, 1980 Analysis Aspects of an Improved Load Follow Package.
Methodology applied-for the following Specification:
3.2.1, Axial Flux Difference-Constant Axial Offset Control a
5.
NUREG-0800, Standard Review Plan, U.
S.
Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981.
Branch i
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 6.
" VANTAGE +
Fuel Assembly Reference Core Report," April'1995 (Westinghouse Proprietary).
Methodology applied for the following Specification:
3.2.2, Heat Flux Hot Channel Factor - Fg(Z)
The core operating limits shall be determined so that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic 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 J
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 3.5.3.
i f
BEAVER VALLEY - UNIT 2 6-20 Amendment No. 84
1 i-4 NPF-73 ADMINISTRATIVE CONTROLS j
ie
\\
i SPECIAL REPORTS (Continued) b.
Inoperable Seismic Monitoring Instrumentation, Specification i-3.3.3.3.
i c.
Inoperable Meteorological Monitoring Instrumentation, j
Specification 3.3.3.4.
j d.
Seismic event analysis, Specification 4.3.3.3.2.
l e.
Sealed. source leakage in excess of limits, Specification 4.7;9.1.3.
I' i
f.
Miscellaneous reporting requirements specified in the ACTION
]
Statements for Apper. dix C of the ODCM.
g.
DELETED 1
h.
Steam generator tube inservice inspection, Specification i
4.4.5.5.
I j
i.
Inoperable accident monitoring, Specification 3.3.3.8.
l j.
Liquid Hold-Up Tanks, Specification 3.11.1.4.
k.
Gas Storage Tanks, Specification 3.11.2.5.
l.-
Explosive Gas Monitoring Instrumentation, Specification 3.3.3.11.
6.10 REQORD RETENTION 6.10.1 The following records shall be retained for at least five (5) years; a.
Records and logs of facility operation cc' ---ing time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections', repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
BEAVER VALLEY --UNIT 2 6-21 Amendment No. 84
)