ML19312C450
| ML19312C450 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/28/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C448 | List: |
| References | |
| NUDOCS 7912130976 | |
| Download: ML19312C450 (9) | |
Text
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UNITED STATES Nt. EAR REGULATORY COMMISSION f
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DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-38 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendments by Duke Power Company (the licensee) dated May 6,1977, ccmplies 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; B.
The facility will operate in conformity with the application, 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 amendment will not be inimical to the cocoon 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 Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-38 is hereby amended.to read as follows:
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"3.B Technical Specifications The Technical Specifications containedin Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifi-ca ti ons.'"
3.
This license amendment is effective within 30 days after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. M MA4/' M'L.-
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: October 28, 1977 i
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UNITED STATES
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NUL. CAR REGULATORY COMMISSIOTJ j, t}l[,'.npgj;}
WASHINGTON. D. C. 20555 p
DUKE POWER COMPANY DOCKET N0. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-47 1.
The Nuclear Regulatory Comission (the Commission) has found that A.
The application for amendments by Duke Power Company (the licensee) dated May 6,1977, complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set fcrth 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 Comission; C.
There is reasonable assurance (i) that the activities authori:ed 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 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.
g 2.
Ac;ordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-47 is hereby amended to read.as follows:
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. " 3. 8 Technical Specifications The Technical Specifications containedin Appendices A and B, as revised through Amendment No.48
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifi-cations.
3.
This license amendment is effective within 30 days after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
f httdd$L A. Schwencer, Chief Operating Reactors Branch #1 Division of 0perating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 28, 1977 4
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UNITED STATES
.i NUCLEAR REGULATORY COMMISSION f,.,h), '
- j WASHINGTON, D. C. 20555
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- o. M %l}'l DUKE POWER COMPANY 00CKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENCMENT TO FACILITY OPERATING IICENSE Amendment No. 45 License No. OPR-55 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendments by Duke Power Company (the licensee) dated May 6,1977, 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; B.
The facility will operate in conformity witn the appli;ation, 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 acendment can ba 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 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.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-55 is hereby amended to read as follows:
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,.* 3.B Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.45
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifi-cations:"
3.
This license amendment is effective within 30 days after the date of issuance.
FOR THE N ' LEAR REGULATORY COMMISSION WB'YA4--
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications 1
October 28, 1977 Date of Issuance:
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J ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 48 TO DPR-38 AMEN 0 MENT NO. 48 TO DPR-47 AMEN 0 MENT N0. 45 TO DPR-55 DOCKET NOS. 50-269, 50-270 AND 50-287 i
1 Revise Appendix A as folicws:
Remove pages 4.1-1 and 4.1-3 and replace with identically I
numbered pages.
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4.1 OPERATIONAL SAFETY REVIEW Appifcability Applies to items directly related to safety limits and limiting conditions for operation.
Obiective To specify the frequency and type of surveillance to be applied to unit equip-ment and conditions.
Specification 4.1.1 75e frequency and type of surveillance required for Reactor Pro-tective System and Engineered Safety Feature Protective System instrumentation shr'1 be as stated in Table 4.1-1.
4.1.2 Equipment and sampling test shall be performed as detailed in Tables 4.1-2 and 4.1-3.
4.1.3 Using the Incore Instrumentation System, a power map shall be made to verify expected power distribution at periodic intervals not to exceed ten effective full power days.
Bases Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which result in " upscale" or "downscale" indication can be easily recognized 'oy simple observation of the functioning of an instrument or system.
Furthermore, such failures are, in many cases, revealed by alarm or annunciator action. Comparison of output and/or state of independent channels measuring the same variable supplements this type of built-in surveillance. Sased on experience in operation of both conventional and nuclear systems, when the unit is in operation, the minimum checking frequency stated is deemed adequate for reactor system instrumentation.
Calibration is performed to assure the presentation and acquisition of ac-curate information. The nuclear flux (power range) channels amplifiers are calibrated (during steady-state operating conditions) when core thermal power exceeds indicated neutron power by more than two percent. During non-steady-state operation, the nuclear flux channels amplifiers are calibrated ear.h shift.to ecmpensate for instrunentation drift and changing rod patterns and core physics parameters.
Channels subject only to "drif t" errors induced within the int trumentation itself can tolerate longer intervals between calibrations. Process system instrumentation errors induced by drif t can be expected to remain within acceptable tolerances if recalibration is performed at the intervals specified.
Substantial calibration shif ts within a channel (essentially a channel failure) are revealed during routine checking and 'esting procedures. Thus, the minimum calibration frequencies set forth are considered acceptable.
4.1-1 Amendments 48, 48 & 45
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Table 4.1-1 INSTRITMENT SURVEILLANCE REQUIREMENTS Channel Description Check Test Calibrate Remarks 1.
Protective Channel NA M0 NA Coincidence Logic 2.
Control Rod Drive NA MO NA Trip Breaker 3.
Power Range Amplifier ES(l)
NA (1)
(1) llea t balance check each shif t.
Ileat balance calibration whenever Indi-cated core thermal power exceeds neutron power by more than 2 percent.
4.
Power Range ES M0 M0(1)(2)
(1) Using incore instrumentation.
(2) Axial offset upper and lower chambers y
after each startup if not done pre-u vious week.
5.
Intermediate Range ES(l)
PS NA (1) When in service.
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6.
Source Range ES(l)
PS NA (1) When in service.
o 57 7.
Reactor Coolant ES M0 AN e.
Temperature
,co 8.
High Reactor Coolant ES M0 AN 0*
Pressure o.
9.
Low Reactor Coolant ES H0 AN Pressure 10.
Flux-Reactor Coolant ES MO AN Flow Comparator 11.
Reactor Coolant Pressure ES MO AN Temperature Comparator-