ML16138A820
| ML16138A820 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/25/1996 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16138A821 | List: |
| References | |
| NUDOCS 9611290393 | |
| Download: ML16138A820 (12) | |
Text
REG UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No. DPR-38
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated September 17, 1996, as supplemented October 23, 1996, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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'sregulations set forth in 10 CFR Chapter I; 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 hereby amended by page 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:
9611290393 961125 PDR ADOCK 05000269 P
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 219, 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION rbert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 25, 1996
AtREG(,
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No. DPR-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the licensee) dated September 17, 1996, as supplemented October 23, 1996, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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:
-2 B. Technical SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 219, 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate 11-2 Division of ReactorProjects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 25, 1996
ptREO&4-I.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated September 17, 1996, as supplemented October 23, 1996, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 B. Technical SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 216, 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION LHer ert N. Berkow, D rec tor Project Directorate 11-2 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 25, 1996
ATTACHMENT TO LICENSE AMENDMENT NO.
219 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO.
219 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 216 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3.3-6 3.3-6 3.3-7 3.3-7 3.5-31 3.5-31 3.5-32 3.5-32 3.6-2 3.6-2
Bases Specification 3.3 assures that, for whatever condition the reactor coolant system is in, adequate engineered safety feature equipment is operable.
For operation up to 60% FP, two high pressure injection pumps are specified. Also, two low pressure injection pumps and both core flood tanks are required. In the event that the need for emergency core cooling should occur, functioning of one high pressure injection pump, one low pressure injection pump, and both core flood tanks will protect the core, and in the event of a main coolant loop severance, limit the peak clad temperature to less than 2,200'F and the metal-water reaction to that representing less than 1 percent of the clad.(I) Both core flooding tanks are required as a single core flood tank has insufficient inventory to reflood the core.
The requirement to have three HPI pumps and two HPI flowpaths operable during power operation above 60% FP is based on considerations of potential small breaks at the reactor coolant pump discharge piping for which two HPI trains (two pumps and two flow paths) are required to assure adequate core cooling.(2) The analysis of these breaks indicates that for operation at or below 60% FP only a single train of the HPI system is needed to provide the necessary core cooling.
The requirement for a flowpath from LPI discharge to HPI pump suction is provided to assure availability of long term core cooling following a small break LOCA in which the BWST is depleted and RCS pressure remains above the shutoff head of the LPI pumps.
The borated water storage tanks are used for two purposes:
(a)
As a supply of borated water for accident conditions.
(b)
As a supply of borated water for flooding the fuel transfer canal during refueling operation.(3)
Three-hundred and fifty thousand (350,000) gallons of borated water ( a level of 46 feet in the BWST) are required to supply emergency core cooling and reactor building spray in the event of a loss-of-core cooling accident.
This amount fulfills requirements for emergency core cooling.
The borated water storage tank capacity of 388,000 gallons is based on refueling volume requirements. Heaters maintain the borated water supply at a temperature above 50'F to lessen the potential for thermal shock of the reactor vessel during high pressure injection system operation. The boron concentration is set at the amount of boron required to maintain the core 1 percent Ak/k subcritical at 70'F without any control rods in the core. The minimum boron concentration is specified in the Core Operating Limits Report.
It has been shown that the containment temperature response following a LOCA or main steam line break accident will be within the equipment qualification analysis conditions with one train of Reactor Building spray and two Reactor Building coolers operable.(4) Therefore, a mainte nance period of seven days is acceptable for one Reactor Building cooling fan and its associated cooling unit provided two Reactor Building spray systems are operable or one Reactor Building spray system provided all three Reactor Building cooling units are operable.
Oconee 1, 2, and 3 Amendment No.
219 Amendment No. 219 3.3-6 Amendment No. 216
Valve LPSW-108 is the LPSW isolation valve on the discharge side of each Unit's RBCUs.
This valve is required to be locked open in order to assure the LPSW flowpath for the RBCUs is available.
Three low pressure service water pumps serve Oconee Units 1 and 2 and two low pressure service water pumps serve Oconee Unit 3. There is a manual cross-connection on the supply headers for Unit 1, 2, and 3. One low pressure service water pump per unit is required for normal operation.
The Units I and 2 LPSW system requires two pumps to meet the single failure criterion provided that one of the Units has been defueled and the following LPSW system loads on the defueled Unit are isolated: RBCUs, Component Cooling, main turbine oil tank, RC pumps, and LPI coolers. In this configuration, if two of the three LPSW pumps are inoperable, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> are permitted by TS 3.3.7.b to restore two of the three LPSW pumps to operable status.
At all other times when the RCS of Unit 1 or 2 is 350 psig or 250'F, all three LPSW pumps are required to meet the single failure criterion.
When all three LPSW pumps are required to be operable and one of the three pumps is inoperable, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> are permitted by TS 3.3.7.b to restore the pump to operable status.
The operability of redundant equipment(s) is determined based on the results of inservice inspection and testing as required by Technical Specification 4.5 and ASME Section XI.
REFERENCES (1)
ECCS Analysis of B&W's 177-FA Lowered-Loop NSS, BAW-10103, Babcock &
Wilcox, Lynchburg, Virginia, June 1975.
(2)
Duke Power Company to NRC letter, July 14, 1978, "Proposed Modifications of High Pressure Injection System".
(3)
FSAR, Section 9.3.3.2 (4)
FSAR, Section 15.14.5 Oconee 1, 2, and 3 Amendment No.
219 Amendment No. 219 3.3-7 Amendment No. 216
3.5.3 Engineered Safety Features Protective System Actuation Setpoints Applicability This specification applies to the engineered safety features protective system actuation setpoints.
Objective To provide for automatic initiation of the engineered safety features protective system in the event of a breach of RCS integrity.
Specification The engineered safety features protective actuation setpoints and permissible bypasses shall be as follows:
Functional Unit Action Seoint High Reactor Building Reactor Building Spray 515 psig Pressure High-Pressure Injection 4 psig Low-Pressure Injection
_<4 psig Start Reactor Building Cooling & Reactor Building Isolation (Essential and 4 psig Non-essential Systems)
Penetration Room Ventilation 54 psig Lower Reactor Coolant
-High Pressure Injection (1) 1500 psig System Pressure
& Reactor Building Isolation (Non-essential systems)
Low Pressure Injection (2) 500 psig (1)
May be bypassed below 1750 psig and is automatically reinstated above 1750 psig.
(2)
May be bypassed below 900 psig and is automatically reinstated above 900 psig.
Oconee 1, 2, and 3 Amendment No. 219 Amendment No. 219 Amendment No. 216 3.5-31
Bases High Reactor Buildin2 Pressure The basis for the 15 psig and 4 psig setpoints for the high pressure signal is to establish a setting which would be reached immediately in the event of a DBA, cover the entire spectrum of break sizes and yet be far enough above normal operation maximum internal pressure to prevent spurious initiation.
Low Reactor Coolant System Pressure The basis for the 1500 psig low reactor coolant pressure setpoint for high pressure injection initiation and 500 psig for low pressure injection is to establish a value which is high enough such that protection is provided for the entire spectrum of break sizes and is far enough below normal operating pressure to prevent spurious initiation.(1)
REFERENCE (1)
FSAR, Section 15.14.
Amendment No. 219 Oconee 1, 2, and 3 Amendment No. 219 Amendment No. 216 3.5-32
- 2.
For plant conditions when the Reactor Coolant System temperature is above 2500F and pressure is above 350 psig but the reactor is at or below hot shutdown, one Reactor Building Purge isolation valve on each penetration may be open for testing and/or maintenance per Specification 4.4.4.1 and 3.6.6.
- 3.
For plant conditions other than contained in Specification 3.6.3.b. 1,.2 above, with one or more Reactor Building purge valves open, the open valves shall be closed within one hour, or the plant shall be in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Reactor Coolant System temperature below 250'F and pressure below 350 psig.
- c.
A containment isolation valve, other than a Reactor Building Purge isolation valve, may be inoperable provided either:
- 1.
The inoperable valve is restored to operable status within four hours.
- 2.
The affected penetration is isolated within four hours by the use of a deactivated automatic valve secured and locked in the isolated position.'
- 3.
The affected penetration is isolated within four hours by the use of a closed manual valve or blind flange.'
- 4.
The reactor is in the hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.4 The reactor building internal pressure shall not exceed 1.2 psig or a vacuum of
-2.45 psig if the reactor is critical.
3.6.5 Prior to criticality following refueling shutdown, a check shall be made to confirm that all manual containment isolation valves which should be closed are closed and tagged.
Penetration flow paths (except for the Reactor Building Purge flow path) may be unisolated intermittently under administrative controls.
Oconee 1, 2, and 3 Amendment No. 219 Amendment No.
219 3.6-2 Amendment No.
216