ML20206C881
| ML20206C881 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/26/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206C884 | List: |
| References | |
| NUDOCS 9905030237 | |
| Download: ML20206C881 (6) | |
Text
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UNITED STATES g
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WASHINGTON. D.C. 20065 0001 i
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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION 4
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.170 License No. DPR-28
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by the Vermont Yankee Nuclear Power Corporation (the licensee) dated November 2,1998, 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 4
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 bee satisfied.
9905030237 990426 DR ADOCK 05000271 noR s
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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 3.8 of Facility Operating License No. DPR-28 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.170, 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 is to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION mes W. Cliffor, Chief, Section 2 Project Directorate I Division of Licensing Project Management i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 26,1999 i
i
r ATTACHMENT TO LICENSE AMENDMENT NO.17n FACILITY OPERATING LICENSE NO. OPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. These revised pages are identified by amendment number and contain marginallines indicating the areas of change.
i Remove inse' 38 38 39 39 79 79 I
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9
VYNPS BASES:
3.2 ~(Cont'd)
The Degraded Grid Protective System has been installed to assure that
-safety-relatea electrical equipment will not be subjected to sustained degraded voltage.
This system incorporates voltage relays on 4160 Volt Emergency Buses 3 and 4 which are set to actuate at the minimum voltage required to prevent damage of safety-related equipment.
If Degraded Grid conditions exist for 10 seconds, either relay will actuate an alarm to alert operators of this condition.
Based upon an assessment of these conditions the operator may choose to manually disconnect the off-site power.
In addition, if an ESF signal is initiated in conjunction with low voltage below the relay setpoint for 10 seconds, the'off-site power will be automatically disconnected.
The Reactor Core Isolation Cooling (RCIC) System provides makeup water to the reactor vessel during shutdown and isolation to supplement or replace the normal makeup sources without the use of the Emergency Core Cooling Systems. The RCIC System is initiated automatically upon receipt of a reactor vessel low-low water level signal. Reactor vessel high water level signal results in shutdown of the RCIC System.
However, the system will restart on a subsequent reactor vessel low-low water level signal. The RCIC System is normally lined up to take suction from the condensate storage tank. Suction will automatically switch over from the condensate storage tank to the suppression pool on low condensate storage tank level.
Upon receipt of a LOCA initiation signal,.if normal AC power is available, all RHR pumps and both Core Spray pumps start simultaneously with no intentional time delay.
If normal AC power is not available, RHR pumps A and D start immediately on restoration of power, RHR pumps B and C start within 3 to 5 seconds of restoration of power and both Core Spray pumps start within 8 to 10 seconds of restoration of power. The purpose of these time delays is to stagger the' start of the RHR and Core Spray pumps on the associated Division 1 and Division 2 Buses, thus limiting the starting transients on the 4.16 kV emergency buses. The time delay functions are only necessary when power la being supplied from the standby power sources (EDGs).
The time delays remain in the pump start logic at all times as the time delay relay contact is in parallel with the Auxiliary Power Monitor relay contact.
Either contact closure wi)1 initiate pump start. Thus, the time delays do not affect low pressure ECCS pump operation with normal AC power available. With normal AC power not available, the pump start relays which would have started the B and C RHR pumps and both Core Spray pumps are blocked by the Auxiliary Power Monitor contacts and the pump start time, delay relays become the controlling devices.
4 Amendment No. 48, 444 133 79