ML20039G959
| ML20039G959 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/29/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A055 | List: |
| References | |
| DPR-38-A-106, DPR-47-A-106, DPR-55-A-103 NUDOCS 8201190348 | |
| Download: ML20039G959 (11) | |
Text
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~k UNITED STATES y;
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DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STAT 10ll, UNIT'NO. 1 A!!ENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.106 License No. DPR-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated April 17, 1981, 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 with the application, the pro-visions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendnent 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 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 Comission's regulations and all applicable requirements have been satis-fied.
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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendment No.106 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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' 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0-JohEF. Stolz, Chie Qp6 rating Reactors ranch f4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 29, 1981 4
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. UNITED STATES y ;
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DUKE POWER COMPANY DOCKET NO.
50 270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATINu LICENSE Amendment No.106 License No. DPRl47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated April 17, 1981, complies with the standards and requirements of tha 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 pro-visions 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 ar.d 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 satis-fied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this iicense amendment and paragraph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendment No.106are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
n F. Stolz, Chief I
Operating Reactors Branch f4 t 61 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: ~ December 29, 1981 e
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UMTED STATES E j l*i NUCLEAR REGULATORY COMMISSION 5*\\
E WASHINGTON. D. C. 20555 t h [p8 s, ~
DUKE POWER COMPANY DOCKET NO.
50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 4
License No. DPR-55 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A. The application for amendment by Duke Power Company (the licensee) dated April 17, 1981, 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 with the application, the pro-visions 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 Commission's regulations:
D.
The issuance of this amendment will not be inimical to the comnon 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 Conmission's regulations and all applicable requirements have been satis-fied.
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:
I 3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Anendment No.103 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is offective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CON 11SSION
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Jo F. Stolz, Chief' rating Reactors branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 29, 1981
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ATTACHMENT TO LI_ CENSE AMENDMENTS AMENDMENT '.0.105 TO DPR-38 AMENDMENT NO.106 TO DPR-47 AMENDMENT NO.103 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 3.4-1 3.4-1 3.4-2 3.4-2 3.4-3(added) 3.4-4 (added) i i
i
3.4 SECONDARY SYSTDi DECAY HEAT REMOVAL Applicability Applies to the secondary system requirements for removal of reactor decay heat.
Objective To specify minimum conditions necessary to assure the capability to remove decay heat from the reactor core.
Specification 3.4.1 Emergency [eedvater System The reactor shall not be heated above 250 F unless the following conditions are met:
Three emergency fetdwater pumps (one steam driven pump capable'of' being a.
powered from an operable steam supply system and two motor driven pumps) and associated initiation circuitry shall be operable.
b.
Two 100% erergency feedwater flow paths shall be operable. Each flow path shall have at least one flew indicator operable.
3.4.2 During operation greater than 250 F, the provisions of 3.4.1 may be modified to permit the~following conditions:
a.
One motor driven emergency feedwater pump may be inoperable for a period of up to seven days. If the inoperable pump is not restored to operable status within 7 days, the unit shall*be brought to hot shutdown within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and below 250* in another 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
One turbine driven emergency feedwater pump or one emergency feedwater flow path may be inoperable fer a period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the inoperable pump or flow path is not restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> the unit will be at hot shutdown within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and below 250*F in another 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Two motor driven emergency feedwater pumps may be inoperable for a period of up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If an inoperable pump is not restored to operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the unit shall be brought to hot shutdown within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and below 250* in another 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d.
With three emergency feedwater pumps and/or both emergency feedwater flow paths inoperable, immediately initiate corrective action to restore at least one emergency feedwater pump and associated emergency feedwater flowpath to operable status. The unit shall be at hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and below 250 F in another 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l 3.4-1 Amendment Nos.106
, 106, & 103
3.4.3 The 16 main steam safety relief valves shall be operable.
l 3.4.4 A minimum of 72,000 gallons of water per operating unit shall be available in the upper surge tank, condensate storage tank, and hot-well. A minimum of 5 ft. (=30,000 Gal.) shall be available in the upper surge tank.
3.4.5 The emergency condenser circulating water system shall be operable.
l 3.4.6 The controls of the emergency feedwater system shall be independent l
of the Integrated Control System.
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- 3. 4-2 Amendment Nos.106 106, s 103 6
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Bases I
The Main Feedwater Systen and the Turbine Bypass System are normally used for decay heat removal and cooldown above 250 F.
Feedwater makeup is supplied by operation of a hotwell pump, condensate booster pump, and a main feedwater pump.
Operability of the Emergency Feedwater System (EFW) assures the capability to remove decay heat and cool down the Reactor Coolant System to the operating conditions for switch over to decay heat removal by the Decay' Heat Removal System, in the event that the Main Feedwater System is inoperable. The EFW system consists of a turbine driven pump (880 gpm), two motor driven puu7s (450 gpm each), and associated flow paths to the steam generators.
Thedecayheatandthereactorcoolantpumgheat following a reactor trip from 102" power, and the EFW flow rate (90 F feedwater) required to remove this heat demand are as follows:
Heat Demand EFW Flowrate Time
(% of 2568 MWT)
(gpm) l 1 min 4.65 721 2 min 4.17 647 5 min 3.64 564 10 min 3.28 509 30 min 2.70 419 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2.35 365 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2.07 322 1
The limiting transient requiring maximum EFW flow is the loss of main feedwater l
with offsite power available. For this transient, a minimum EFW flow rate equivalent to 405 gpm at 1065 psia is adequate. Each of the three EFW pumps is capable of delivering this flow.
A 100% flowpath is defined as: The flowpath to either steam generator including associated valves and piping capable of being supplied by either the turbine driven pump or the associated motor driven pump.
One flow indicator or steam generator level indicator per steam generator is i
sufficient to provide indication of energency feedwater flow to the steam generators and to confirm emergency feedwater system operation. In the event that at least one indicator per steam generator is not available, then the flovpath to this steam generator is considered to be inoperable.
The EFW System is designed to start automatically in the event of loss of both main feedwater pumps or low main feedwater header pressure. All automatic initiation logic and control tunctions are independent from the Integrated Control System (ICS).
Normally, decay heat is removed by steam relief through the turbine bypass system to the condenser. Condenser cooling water flow is provided by a siphon effect from Lake Keowee through the condense.r for final heat rejection to the Keovee Hydro Plant tailrace. Decay heat removal via recirculation l
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Amendment Nos.106,106
,& 103
i.
flowpath may be maintained for up to 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per unit, assuming the minimum amount of water in the upper surge tanks, condensate storage tank, and hotwell is available. This is based on the conservative estimate of nonnal makeup being 0.5% of throttle flow. Throttle flow at full load, 11,200,000 lbs/hr., was used to calculate the operation time. For decay heat removal the operation time with the volume of water specified would be considerably increased due to the reduced throttle flow.
Decay heat can also be removed from the steam generators by steam relief through the main steam safety relief valves. The total relief capacity of the 16 main steam safety relief valves is 13.105,000 lbs/hr. In this case the minimian amount of water in the upper surge tank, condensate storage tank, and hotwell is sufficient to remove decay heat and reactor coolant pump heat for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per unit at hot shutdown conditions.
REFERENCE
.FSAR, Section 10.
3.4-4 Amendment Nos. 106 106, & 103 g
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