ML20151R658
| ML20151R658 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/29/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151R663 | List: |
| References | |
| NUDOCS 8602060175 | |
| Download: ML20151R658 (11) | |
Text
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NUCLEAR REGULATORY COMMISSION o
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JAN 2 919es TENNESSEE VALLEY AtITHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. OPR-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
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Tennessee Valley Authority (licensee), dated May 6, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 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 Comission's regulations and all applicable requirements have been i
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 amend-ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.43, are hereby incorporated into the license.
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PDR ADOCK 05000327 P
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. 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 hW B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Appendix A Technical Specification Changes
.Date of Issuance: January 29, 1986 PWR WR-A PWR PWR-A PW N-A OELD PW PWR-A MDb mac cst h MM r
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ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and l
contain vertical lines indicating the areas of change.
Amended i
f_ age, 1
3/4 3-56 B3/4 3-3a
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TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION ag MINIMUM REQUIRED NO.
CHANNELS INSTRUMENT OF CHANNELS OPERABLE z
1.
Reactor Coolant THot (Wide Range) 2 1
2.
Reactor ~ Coolant TCold (Wide Range) 2 1
3.
Containment Pressure 2
1-4.
Refueling Water Storage Tank Level 2
1 5.
Reactor Coolant Pressure 2
1 6.
Pressurizer Level (Wide Range) 2 1
7.
Steam Line Pressure 2/ steam line 1/ steam line R
8.
Steam Generator Level - (Wide Range) 1/ steam generator 1/ steam generator
[
9.
Steam Generator Level - (Narrow Range) 1/ steam generator 1/ steam generator h
- 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 f
- 15. Containment Water Level (Wide Range) 2 1
- 16. In Core Thermocouples 4/ core quadrant 2/ core quadrant "Not applicable if the associated block valve is in the closed position.
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- Not applicable if the block valve is verified in the closed position with power to the valve operator removed.
k At least one channel shall be the acoustic monitors.
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INSTRUMENTATION BASES Sequoyah has four separate methods of determining safety valve position (i.e.,
open or closed).
a.
Acoustic flow monitors mounted on each safety valve line (one per valve).
A flow indicating module in the main control room is calibrated to detect failure of a valve to reclose. An alarm in the main control room will actuate when any valve is not fully closed.
b.
Temperature sensors downstream of each safety valve (one per valve).
Tem-perature indication and alarm are provided in the main control room.
c.
Pressurizer relief tank temperature, pressure and level indication, and alarm in main control room.
d.
Pressurizer pressure indication and alarm in the main control room.
., Although all the above position indicators for the pressurizer safety valves and the PORVs are acceptable as one of the channels, the acoustic monitors must be one of the two required operable chanels.
In addition to the four methods described above, the PORVs use an electromagnetic " reed"-switch to determine valve position.
The stem mounted switches are no longer in use since the PORVs were changed.
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SEQUOYAN - UNIT 1 8 3/4 3-3a Amendment No. 43 l
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j EASHINGTON, D. C. 20655 t%,,,,,/-
JAN 2 S 1986 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH N4 CLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) 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 May 6, 1985, 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; 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 Com-mission; 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 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 CFP 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 Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical ' Specifications contained in Appendix A, as revised through Amendment No.35, are hereby incorporated into the license.
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.- 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 ls, B. J. Youngblood, Director PWR Project Directorate #4 Division.of PWR Licensing-A
Attachment:
Appendix A Technical Specification Changes Date of Issuar.ce:
January 29, 1986 Jf
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ATTACHMENT TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 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
_P, ale 3/4 3-57 B3/4 3-3 B3/4 3-4 O
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TABLE 3.3-10 wE ACCIDENT MONITORING INSTRUMENTATION 5g MINIMUM t
REQUIRED NO.
CHANNELS
. INSTRUMENT OF CHANNELS OPERABLE E
Z
- 1. Reactor Coolant THot (Wide Range) 2 1
N
- 2. Reactor Coolant TCold (Wide Range) 2 1
- 3. Containment Pressure 2
1
- 4. Refueling Water Storage Tank Level 2
1
- 5. Reactor Coolant Pressure 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 m
- 9. Steam Generator Level - (Narrow Range) 1/ steam generator 1/ steam generator g
- 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/ valva
- 14. Safety Valve Position Indicator 2/ valve #
1/ valve l
- 15. Containment Water Level (Wide Range) 2 1
- 16. In Core Thermocouples 4/ core quadrant 2/ core quadrant "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.
p At least one channel shall be the acoustic monitors.
E ae
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INSTRUMENTATION 8ASES 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION l
The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data la available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the ublic and is consistent with the recommendations of Regulatory Guide 1.23, p'Onsite Meteorological Programs," February 1972.
i 3/4.3.3.5 REMOTE SHUTOOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT i
STANDBY of the facility from locations outside of the control room.
This
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capability is re' quired in the event control room habitability is lost and is I consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.3.6 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release.
This capability is required to protect control room personnel and is consistent with the recommendations of
' Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and l
Following an Accident," December 1975.
Sequoyah has four separate methods of determining safety valve position (i.e.,
open or closed).
a.
Acoustic flow monitors mounted on each safety valve line (one per valve).
A flow indicating module in the main control room is calibrated to detect failure of a valve to reclose. An alarm in the main control room will i
actuate when any valve is not fully closed.
I b.
Temperature sensors downstream of each safety valve (one per valve). Tem-perature indication and alarm are provided in the main control room.
I Pressurizer relief tank temperature, pressure and level indication, and c.
i alarm in main control room.
I d.
Pressurizer pressure indication and alarm in the main control room.
SEQUOYAH - UNIT 2 B 3/4 3-3 Amendment No. 35
m i
f INSTRUMENTATION 4
BASES j
3/4.3.3.7 ACCIDENT MONITORING INSTRUMENTATION (continued)
~
Although all the above position indicators for the pressurizer safety valves and the PORVs are acceptable as one of the channels, the acoustic monitors must l
be one of the two required operable chanels.
In addition to the four methods described above, the PORVs use an electromagnetic " reed"-switch to determine i
valve position. The stem mounted switches are no longer in use since the PORVs were changed.
I 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment'and is an integral element in the overall facility fire protection program, f
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effuents during actual or potential releases of liquid effluents. The alare/
trip setpoints for these instruments shall be calculated in accordance with the procedures in the 00CM to ensure that the alare/ trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION i
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alare/ trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
SEQUOYAH - UNIT 2 8 3/4 3-4 Amendment No. 35 I
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