ML20210C655
| ML20210C655 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-046, DPR-77-A-46, DPR-79-A-038, DPR-79-A-38) |
| Issue date: | 09/16/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210C661 | List: |
| References | |
| NUDOCS 8609180393 | |
| Download: ML20210C655 (10) | |
Text
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UNITED STATES I
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g NUCLEAR REGULATORY COMMISSION y
- a W ASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO.
50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. LPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated January 25, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will o>erate in confonnity with the license, as amended, the provisions of tie Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) lows:of Facility Operating License No. DPR-77 is hereby amended to read as fol 8609180393 060916 PDR ADOCK 0D000327 P
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 46 are hereby incorporated into 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.
FOR THE NUCLEAR REGULATORY COMMISSION d\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance: September 16, 1986 f
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i ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 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.
Amended Page
.3/4 3-56 3/4 3-57 S
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l TABLE 3.3-10
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E ACCIDENT MONITORING INSTRUMENTATION 8s MINIMUM REQUIRED NO.
CHANNELS INSTRUMENT OF CHANNELS OPERABLE E
Q 1.
Reactor Coolant Th t (Wide Range) 2 1
]
2.
Reactor Coolant TCold (
Range) 2 1
3.
Containment Pressure (Wide Range) 2 1
l l
4.
Refueling Water Storage Tank Level 2
1
]
5.
Reactor Coolant Pressure (Wide Range) 2 1
l-
)
6.
Pressurizer Level (Wide Range) 2 1
~!
7.
Steam Line Pressure 2/ steam line 1/ steam line 8.
Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator w
9.
Steam Generator Level - (Narrow Range) 1/ steam generator 1/ steam generator i
J,
- 10. Auxiliary Feedwater Flow Rate 1/ pump 1/ pump l
- 11. Reactor Coolant System Subcooling Margin Monitor.
1 0
- 12. Pressurizer PORV Position Indicator
- 2/ valve #
1/ valve l
- 13. Pressurizer PORV Block Valve Position Indicator **
2/ valve 1/ valve l
- 14. Safety Valve Position Indicator 2/ valve #
1/ valve
- 15. Containment Water Level (Wide Range) 2 1
- 16. In Core.Thermocouples 4/ core quadrant 2/ core quadrant
- 17. Reactor Vessel Level Instrumentation System ***
2 1
l "k
- Not applicable if the associated block valve is in the closed position.
- Not applicable if the block valve is verified in the closed position with power to the valve operator removed.
5
- This Technical Specification and surveillance requirement will not be implemented until Sequoyah Specific
-l Instructions are developed for the use of this system as committed to in the TVA response to Supplement 1 of I
2 P
I At least one channel shall be the acoustic monitors.
TABLE 4.3-7 vs 19 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8s CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION g
1.
Reactor Coolant THot (Wi e Range)
M R
[
2.
Reactor Coolant TCold (Wide Range)
M R
3.
Containment Pressure (Wide Range)
M R
j 4.
Refueling Water Storage Tank Level M
R 5.
Reactor Coolant Pressure (Wide Range)
M R
l 6.
Pressurizer Level-M R
7.
Steam Line Pressure M
R 8.
Steam Generator Level - Wide M
R j'
9.
Steam Generator Level - Narrow M
R 9
- 10. Auxiliary Feedwater Flowrate M
R
- 11. Reactor Coolant System Subcooling Margin Monitor M
R
- 12. Pressurizer PORY Position Indicator M
R
- 13. Pressurizer PORV Block Valve Position Indicator M
R
- 14. Safety Valve Position Indicator M
R
- 15. Containment Water Level (Wide Range)
M R
l
- 16. In Core Thermocouples M
R
- 17. Reactor Vessel Level Instrumentation **
M R
l i
N y
- This Technical Specification and surveillance requirement will not be implemented until Sequoyah Specific i
j St Instructions are developed for the use of this system as committed to in the TVA response to Supplement 1 of M
e
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
h' WA9HINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated January 25, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter.I; B.
The facility will operate in conformity with the license, as amended, 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A 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:
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 38 are hereby incorporated into 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.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment Appendix A Technical Specification Changes Date of Issuance: September 16, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE N0. DPR-79 DOCKET N0. 50-328 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.
Amended Page 3/4 3-57 3/4 3-58 e
9 l
l
,.. - ~. - -
TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION E
S MINIMUM.
E REQUIRED NO.
-CHANNELS i
INSTRUMENT OF CHANNELS OPERABLE l
- 1. Reactor Coolant THot (Wide Range) 2 1-to
- 2. Reactor Coolant TCold (Wide Range) 2 1
l
- 3. Containment Pressure (Wide Range) 2 1
- 4. Refueling Water Storage Tank Level 2
1 l
j
- 5. Reactor Coolant Pressure (Wide Range) 2 1
- 6. Pressurizer Level (Wide Range) 2 1
- 7. Steam Line Pressure 2/ steam line 1/ steam line
- 8. Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator l
1
- 9. Steam Generator Level - (Narrow Range) 1/ steam generator 1/ steam generator T
- 10. Auxiliary Feedwater Flow Rate 1/ pump 1/ pump
- 11. Reactor Coolant System Subcooling Margin Monitor 1
0
- 12. Pressurizer PORV Position Indicator
- 2/ valve #
1/ valve
- 13. Pressurizer PORV Block Valve Position Indicator **
2/ valve 1/ valve
- 14. Safety Valve Position Indicator 2/ valve #
1/ valve
- 15. Containment Water Level (Wide Range) 2 1
- 16. In Core Thermocouples 4/ core quadrant 2/ core quadrant
- 17. Reactor Vessel Level Instrumentation System ***
2 1
l I
- Not applicable if the associated block valve is in the closed position.
- Not applicable if the block valve is verified in the closed position with power to the valve operator removed.
- This Technical Specification and surveillance requirement will not be implemented until Sequoyah Specific Instructions are developed for the use of this system as committed to in the TVA response to Supplement 1 of j
At least one channel shall be the acoustic' monitors.
TABLE 4.3-7 m
E ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8
5 CHANNEL CHANNEL 7
INSTRUMENT CHECK CALIBRATION E
1.
Reactor Coolant THot (Wide Range)
M R
[
2.
Reactor Coolant TCold (Wide' Range)
M R
3.
Containment Pressure (Wide Range)
M R
l 4.
Refueling Water St.crage Tank Level M
R 5.
Reactor Coolant Pressure (Wide Range)
M R
l E.
Pressurizer Level M
R 7.
Steam Line Pressure M
R 8.
Steam Generator Level - (Wide)
M R
{
9.
Stean Generator Level - (Narrow)
M R
w
- 10. Auxiliary Feedwater Flowrate M
R E
- 11. Reactor Coolant System Subcooling Margin Monitor M
R
- 12. Pressurizer PORV Position Indicator M
R
- 13. Pressurizer PORV Block Valve Position Indicator M
R
- 14. Safety Valve Position Indicator M
R
- 15. Containment Water Level (Wide Range)
M R
l
- 16. In Core Thermocouples M
R
- 17. Reactor Vessel Level Instrumentation System
- M R
r M
- This Technical Specification and surveillance requirement will not be implemented until Sequoyah Specific Instructions are developed for the use of this system as committed to in the TVA response to Supplement 1 of E
2 a
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., _ _