ML20206U419
| ML20206U419 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/09/1999 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206U421 | List: |
| References | |
| NUDOCS 9902160022 | |
| Download: ML20206U419 (8) | |
Text
&[# M4 9
0" UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20555-0001 o
Y+9
,o TENNESSEE VALLEY AUTHORITY DOCKET NO.50-32Z SEQUOYAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.242 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
)
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 16,1998, 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; 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 pub!!c; 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.
3 9902160022 990209 PDR ADOCK 05000327 P
- 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 t.o read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.242 are herrby 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 no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION gg/D 0 W W Cecil O. Thomas, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation 3
Attachment:
Changes to the Technical Specifications Date of issuance: February 9, 1999 i
ATTACHMENT TO LICENSE AMENDMENT NO.242 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.
j REMOVE INSERT 3/4 8-5 3/4 8-5 l
i l
l l
l
I ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l l
8.
Verifying that the auto-connected loads to each diesel generator R68 l
do not exceed the continuous rating of 4400 kW.
9.
Verifying the diesel generator's capability to:
a)
Synchronize with the offsite power source while the genera-tor is loaded with its emergency loads upon a simulated restoration of offsite power.
i b)
Transfer its loads to the offsite power source, and c)
Be restored to its shutdown status.
10.
Verifying that the automatic load sequence timers are OPERABLE with the setpoint for each sequence time.r within i 5 percent of its design setpoint.#
11.
This surveillance is deleted.
e.
At least once per 10 years or after any mcdifications which could affect diesel generator interdependence by starting the diesel generators simultaneously and verifying that each diesel generator achieves in less than or equal to 10 seconds, = 6800, volts and a 58.8 Hz.
R238 f.
At least once per 10 years by:
lR217 1.
Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypoclorite solution, and 2.
Performing a pressure test of those portions of the diesel fuel oil system design to Section III, subsection ND of the ASME Code at a test pressure equal to 110 percent of the system design pressure.
g.
At least once per 18 months by:
lR238 1.
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 6011.2 R103 Hz.
At no time shall the transient voltage exceed 8276V.
2.
Verifying the generator capability to reject a load of 4400 kw lR68 without tripping. The generator voltage shall not exceed 8880V lR174 during and following the load rejection.
- May be performed in Modes 1, 2, 3 & 4 if the associated equipment is out of service for maintenance or testing.
SEQUOYAH - UNIT 1 3/4 8-5 Amendment No. 52, 64, 99, 109,.
l 114, 137, 170, 173, 195, 213, 234 242 l
l
m,4 O
UNITED STATES g
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206fLM001 l
o, ;...../
s TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-123 EEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Arnendment No.232 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 November 16,1998, 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; i
C.
The,a is reasonable assurance (i) that the activities authorized by this i
l amendment can be conducted without endangering the health and safety of the l
public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical tc 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. 232, 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 no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y8 N
Cecil O. Thomas, Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date ofissuance: February 9,1999
~
ATTACHMENT TO LICENSE AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. DPR-79 6
DOCKET NO. 50-328 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 marginallines indicating the area of change.
REMOVE INSERT 3/4 8-5 3/4 8-5
ELECTRICAL POWER SYSTEMS SURVEILIANCE REQUIREMENTS (Continued) 8.
Verifying that the auto-connected loads to each diesel RS6 generator do not exceed the continuous rating of 4400 kw.
9.
Verifying the diesel generator's capability to:
lR41 m)
Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power.
b)
Transfer its loads to the offsite power source, and c)
Be restored to its shutdown status.
10.
Verifying that the automatic load sequence timers are OPERABLE with the setpoint for each sequence timer within R41 15 percent of its design setpoint.#
11.
This surveillance is deleted.
e.
At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously and verifying that each d.iesel generator achieves in less than or equal to 10 seconds, a 6800 volts and R224 a 58.8 Hz.
f.
At least once per 10 years by:
lR203 1.
Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypoclorite solution, and 2.
Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110 percent of the system design pressure.
g.
At least once per 18 months by:
lR224 1.
Verifying the generator capability to reject a load of greater than or equal to 600 kw while maintaining voltage at R88 within i 10 percent of the initial pretest voltage and frequency at 601 1.2 Hz.
At no time shall the transient voltage exceed 8276V.
2.
Verifying the generator capability to reject a load of RS6 4400 kw without tripping.
The generator voltage shall not exceed B880V during and following the load rejection.
lR160
- May be performed in Modes 1, 2, 3 & 4 if the associated equipment is out of service for maintenance or testing.
h SEQUOYAH - UNIT 2 3/4 8-5 Amendment Nos. 41, 50, 88, 123,232 160, 164, 186, 203, 224
..