ML15112A857

From kanterella
Revision as of 13:08, 10 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Amends 69,69 & 66 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Which Revises ETS by Deleting Aquatic Surveillance Program & Special Study Programs
ML15112A857
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/02/1979
From: Reid R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML15112A858 List:
References
NUDOCS 7905250018
Download: ML15112A857 (11)


Text

REG UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269' OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-38

- 1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated December 2, 1977, as supplemented September 11, 1978, 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 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.

790525 0012

-2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.

DPR-38 is hereby amended to read as follows:

3.3 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.69 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactort Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 2, 1979

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-47

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated December 2, 1977, as supplemented September 11, 1978, 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 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.

g

- 2

2. Accordingly, the license is amended by changes to the Technical Specifications as.indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No.

DPR 47 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifi cations Date of Issuance:

March 2, 1979

SREG~0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Z

DUKE POWER COMPANY DOCKET NO.

50-287 OCONEE NUCLEAR STATION, UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-55 1

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated December 2, 1977, as supplemented September 11, 1978, 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 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.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No.

DPR-55 is hereby amended to read as follows:

3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 66 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 2, 1979

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.69 TO DPR-38 AMENDMENT NO.69 TO DPR-47 AMENDMENT NO.66 TO DPR-55 DOCKETS NOS. 50-269, 50-270, AND 50-287 Revise Appendix B as follows:

Remove Pages Insert Pages Table of Contents Table of Contents 1-18 1-3 Changes on the revised pages are indicated by a marginal line.

TECHNICAL SPECIFICATIONS Table of Contents Page 1.1 Station Cooling Water Systems Thermal Limits.........

1.2 Chemical Discharge Limits...................********:2 Amendments Nos. 69 69, & 66

1.1 STATION COOLING WATER SYSTEMS THERMAL LIMITS Oblective:

To specify thermal limiting conditions for the operation of the station cooling water systems.

AP Plicability:

Applies to the maximum temperature and rate of change of temperature of the cooling water discharged from the station condenser cooling and service water systems.

Specification: A. The cooling water effluent temperature at the discharge shall not exceed 100*F for a time period in excess of' two hours. In the event of the once-in-20 years combi nation of extreme natural conditions the station's generating capacity shall be limited as necessary to keep the discharge temperature from exceeding 1000.F inless there is a serious need for the lost power. A serious need for lost power is defined here as a condition which would result in voltage reductions or load shedding (except contracted interruptable loads).

Under these circumstances, the licensee shall notify AEC/DOL immediately by telephone and the discharge temperature shall not be allowed to exceed 103*F.

B. Temperature rise from the condenser intake to the discharge shall not exceed 28.F. Further, the temperature rise should not exceed 22.F when the inlet temperature is greater than 680F.

C. Normal station operations shall be programmed so that effluent temperatures shall not decrease more than 6oF per hour during the winter and 10*F per hour during the spring, summer, and fall.

Monitoring:

Station cooling water intake and discharge temperature and cooling water flow rate shall be measured continually at intervals of less than 1 minute. Summaries to include maxim, minimum, and average values shall be printed out hourly; and during periods when the measuring equipment is defective or under repair, representative data readings shall be logged hourly.

Basis:

The limits on plaitdischarge temperature and rate of temperature change permit sufficient operational flexibility to allow for the starting or shutdown of a circulation water pump during plant loading and unloading, while at the same time requiring that procedures incorporate the programming of load changes to mini mize the resulting transient thermal change.

Specification C recognizes that a slower rate of plant unloading during the cooler months is desirable due to the fact that some aquatic organisms require more time to adapt during those periods.

Whenever feasible, refueling and scheduled maintenance shall be performed during periods when the ambient lake surface temperatures are -above 60*F.

Amendments Nos. 69 69, & 66

1.2 CHEMICAL DISCHARGE LIMITS Objective To insure that all chemical releases from the station are controlled so as to be nontoxic to aquatic organisms and non-deleterious to down stream water quality in Hartwell Reservoir.

Applicability Applies to release of chemical effluents from the station.

Specification A. Limits for certain chemical wastes and pH of water released from the Waste Water Treatment System and the Low Level Radwaste System shall not exceed the concentrations indicated in Table 1.2-1, "Limits and monitoring Requirements on Certain Chemicals and pH of Water Released from Oconee Nuclear Station."

B. Chlorine or other chemical biocides will not be used for condenser cleaning.

Monitorin&

The concentration of the chemicals and pH of water allowed to be released from the-station under this specification shall be monitored as specified in Table 1.2-1.

Action Reauirements In the event any of the above specified limits are exceeded, a report shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone to the Director of the Regional Regulatory Operations Office, followed by a written report within one week to the Director of the Regional Inspection and Enforcement Office (cc to Director of Nuclear Reactor Regulation).

The written report and to the extent possible, the preliminary telephone report, will: (a) describe, analyze and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occur rence, and (c) indicate the corrective action (including any significant changes made in procedure) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

Bases Operation within the chemical monitoring and effluent limits specified in Table 1.2-1 will assure that concentrations of chemical effluents are maintained at levels that will provide adequate protection of aquatic and downstream water quality, and will assure that the water quality is not degraded beyond that described in the FES.

Amendments Nos. 69 69

& 66

-3 0

TABLE 1.2-1 LIMITS AND MONITORING REQUIREMENTS ON CERTAIN CHEMICALS AND pH OF WATER RELEASED FROM OCONEE NUCLEAR STATION Type Waste Water Tr atment System Low Level Rad Waste System b Monitoring Frequency Limit Frequency Limit pH Daily 6.0 -

9.0 Hydrazine Daily 0.7 ppm Prior to Release 0.1 ppm Boron Prior to Release 1.0 ppm aMonitored at point of release to Hartwell Reservoir.'

bConcentrations are measured prior to point of discharge. Limits apply on downstream incremental increases in concentration in the Hartwell Reservoir following dilution in.the Keowee tailrace.

Amendments Nos. 69, 69, & 66