ML20056H628
| ML20056H628 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/27/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056H629 | List: |
| References | |
| NUDOCS 9309100224 | |
| Download: ML20056H628 (7) | |
Text
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TENNESSEE VALLEY AUTHORITY DOCKET N6. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.170 License No. OPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 1, 1993, 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 d ety of the public, and (ii) that such activities will be coi. ducted 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.
9309100224 930827 PDR ADOCK 05000327 P
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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 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, 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, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION Freder
. Hebdon, Direct A'
Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 27, 1993 a
ATTACHMENT TO LICENSE AMENDMENT NO.170 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 8-4 3/4 8-4 l
ELECTRICAL POWER SYSTEMS SVRVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage within i 10 percent of the initial pretest voltage and frequency at 60.: 1.2 Hz. At no time shall the transient voltage exceed 827tiV.
3.
Verifying the generator capability to reject a load of 4400 kw without tripping. The generator voltage shall not exceed 8880V l
during and following the load rejection.
4.
Simulating a loss of offsite power by itself, and:
a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.
b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 1 690 volts and C0 i 1.2 Hz during this test.
5.
Verifying that on a ESF actuation test signal (without loss os offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 6900 1 690 volts and 60 i 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and fre-quency shall be maintained within these limits during this test.
6.
Simulating a loss of offsite power in conjunction with an ESF actuation test signal, and a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.
b)
Verifying the diesel starts on the auto-start signal, energi?es the shutdown boards with permanently connected loads t;' thin 10 seconds, energizes the auto-connected emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 i 690 volts and 60 i 1.2 Hz during this test.
3/4 8-4 SEQUOYAH - UNIT 1 Amendment No. 49,64,114,137,154,170
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 s.,
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.160 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March i, 1993, 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.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.1 6 t> 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, to be implemented with 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION Frederic Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 27, 1993
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months during shutdown by.
I 1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's
)
recommendations for this class of standby service, i
2.
Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage at within i 10 percent of the initial pretest voltage and frequency at 60 i 1.2 Hz. At no time shall the transient voltage exceed 8276V.
3.
Verifying the generator capability to reject a load of 4400 kw without tripping.
The generator voltage shall not exceed 8880V l
during and following the load rejection.
4.
Simulating a loss of offsite power by itself, and:
I a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.
b)
Verifying the diesel starts on the auto-start signal, energizes the shutdown boards with permanently connected loads within 10 seconds, energizes the auto-connected shutdown loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady state voltage and frequency of the shutdown boards shall be maintained at 6900 1 690 volts and 60 i 1.2 Hz during this test.
5.
Verifying that on a ESF actuation test signal, without loss of offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be 6900 i 690 volts and 60 i 1.2 Hz within 10 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test.
6.
Simulating a loss of offsite power in anjunction with an ESF actuation test signal, and a)
Verifying de-energization of the shutdown boards and load shedding from the shutdown boards.
b)
Verifying the diesel starts on the auto-startc sion 1, energizes the shutdown boards with pc:ianently csnhected l
loads within 10 seconds, energizes the auto-connected i
emergency (accident) loads through the load sequencers and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 6900 1 690 l
volts and 60 i 1.2 Hz during this test.
SEQUOYAH - UNIT 2 Amendment No. 41, 123, 144,._160