ML20206J465
| ML20206J465 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/16/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206J469 | List: |
| References | |
| NUDOCS 8811280213 | |
| Download: ML20206J465 (5) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION b
8 WASHINGTON, D. C. 20666 li GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDPENT T0_ FACILITY OPERATING LleENSE Amendment No. 30 License No. NPF-47 1.
The Nuclear Regulatory Comission (the Co, mission) t,as found that:
A.
The application for amendment by Gulf States Utilities Company (the licensee) daced June 21, 1988, as supplemented October 31, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as r, mended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of 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 license amendment will oct be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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' 2.
Accord (ngly, the license is amended by char.ges to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License l'o. NPF-47 is hereby amended to resd as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 30 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3-The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p'
G. dc. 6w Jose A. Calvo, Director Project Directorate - IV DivisionofReactorProjects-III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Char.ges to the Technical Specifications Date of Issuance: November 16, 1938 J
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i ATTAC4 MENT TO LICENSE At1ENDHENT NO.30 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 i
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amanc' ment number and contains a vertical line indicating the area of change. Overleaf page provided to maintain document completeness.
REtiOVE PAGE
@ER_TPAGE 6-15 6-15 l
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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2.
Integrated leak test requirements for each system, at refueling cycle intervals or more frequently.
b.
In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintensnce of sampling,and analysis equipment.
c.
Post-accident Samplina A program which will ensure the capebility to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents and containment atmosphere samples, under accident conditions.
The program shall include the following:
1.
Training of personnel, 2.
Procedures for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
d.
Biofoulina Prevention and Detection A program, which will include the procedures to prevent biofouling of safety-related equipment, to assure detection of Corbicula in the intake embayment and the clarifier influent, and to monitor and survey l
safety-rclated equipment to detect biofouling, Changes to this pro-gram will be submitted to and approved by the NRC (both the Region and NRR) prior to implementation.
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- 6. 9 REPORTING REQUIREMENTS i
ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, C 't 1
of Federal Regulations, the following reports shall be submitted to the U.S.
j Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resident Inspector, unless otherwise noted.
STARiUP REPORT 6.9.1.1 A summary report of plant startup and power esc 31stior, testing shall be submitted fo11cwing (1) receipt of an Operating License, (2) amendment to RIVER BEND - UNIT 1 6-15 Amendment No.17.30
ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) ti.e license involving a planned increase in power level, (3) installation of fuel that tias a dif ferent design or has been manufactured by a dif ferent fuei supplier, and (4) modifications that may have significantly altered the nuc %ar, thermal, or hydraulic performance of the unit.
6.9.1.2 The startup report shall address each of the tests identified in Final Safety Analysis Report (Section 14.2.12.2) and shall include a descrip-tion of the measured valces of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions ano specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days 'following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the startup report does not cover all three events (i.e., initial criticality, comple'. ion of startup test program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
ANNUAL REPORTS 6.9.1.4 Annuel reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each yc.tr.
The initial report shall be submitted prior to March 1 of the year follo' sing initial criticality.
6.9.1.5 Reports required on an annral basis shall include:
A tabulation on an annual basis of the number of station, utility, a.
j and other personnel (including contractors) receiving exposures greater j
than 100 arsa/yr and the!r associated man-rem exposure according to work and job functions * (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance waste processing, and refueling). The dose assip'.ments to various duty functions isay be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not b, accounted for.
In the aggregate, at least 40% of the total whole-body dose received i
free external sources st.ould be sssigned to specific major work l
functions; j
b.
Documentation of all challenges to safety / relief valves and a summary l
of SRV failures.
"Ints taculation suppl)ments the requirements of $20.407 of 10 CFR Part 20.
RIVER BEND - UNIT 1 6-16
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