ML20056H365
| ML20056H365 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/24/1993 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H366 | List: |
| References | |
| NUDOCS 9309090199 | |
| Download: ML20056H365 (5) | |
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NUCLEAR REGULATORY COMMISSION g s,4 /
WASHINGTON. D C. 20555-0001 GULF STATES UTILITIES COMPANY f
DOCKET NO. 50-458 i
RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License ho. NPF-47 1.
The Nuclear Regulatory Comission (the Comission) has, found that:
A.
The application for amendment by Gulf States Utilities Company (the licensee) dated July 2, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I;
i B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of l
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 not 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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9309090199 930824 PDR ADOCK 05000458 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. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 67 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 l-Suzann
. Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulatior i
Attachment:
Changes to the Technical Specifications Date of Issuance: August 24, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 1
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. The overleaf page is provided to maintain document completeness.
REMOVE INSERT 6-19a 6-19a r
i l
f f
ADMINISTRATIVE CONTROLS SEMIANNUAL EFFLUENT RELEASE REPORT (Continued) to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1.3) during the report period. All assumptions used in aaking these assessments (i.e., specific activity, exposure time and location) shall be in-cluded in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the OFFSITE DOSE CALCULA-TION MANUAL (00CM).
The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most-exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acteptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977.
The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the 00CM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specifi-cation 3.12.2 SPECIAL REPORTS 6.9.2 Special reports shall be submitted in the following manner:
Special reports shall be submitted to the U.S. Nuclear Regulatory a.
Commission, Document Control Desk, Washington, DC 20555, with a copy to the Regional Office of the NRC and a copy to the NRC Resi-dent Inspector, within the time period specified for each report.
b.
Special reports in regard to Corbicula will be submitted to the NRC within 30 days of identification of infestation.
In accordance with the settlement agreement dated October 10, 1984, these reports shall describe the level of infestation, affected systems and measures taken to prevent further infestation.
CORE OPERATING LIMITS REPORT 6.9.3.1 Core operating limits shall be established prior to startup from each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
The AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR) for a.
Specification 3.2.1.
RIVER BEND - UNIT 1 6-19 Amendment Ho. 77, 42
1.
i ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) b.
The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.3.
l c.
The LINEAR HEAT GENERATION RATE (LHGR) of Specification 3.2.4.
j I
d.
The REACTOR PROTECTION SYSTEM (RPS) response time for APRM thermal time constant for Specification 3.3.1.
j and shall be documented in the CORE OPERATING LIMITS REPORT (COLR).
6.9.3.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (the approved version at the time the reload analyses are performed).*
l 6.9.3.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits and nuclear limits such as shutdown margins, and transient and accident analysis limits) of the safety analysis are met.
6.9.3.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revision or i
supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.2 The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections,
'1 repair, and replacement of principal items of equipment related to nuclear safety.
t
- For Cycle 5 only, the result of misoriented fuel bundle analysis need not be l
considered in determining the OLMCPR due to the extensive verifications performed of fuel bundle placement and orientation for Reload 4.
I RIVER BEND - UNIT 1 6-19a Amendment No. 42, 67
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