ML20125C922
| ML20125C922 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-165, DPR-79-A-155) |
| Issue date: | 12/08/1992 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20125C924 | List: |
| References | |
| NUDOCS 9212140154 | |
| Download: ML20125C922 (10) | |
Text
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UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0V0YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.165 License No. OPR-77 1.
The Nudear gulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated. November 9, 1992, 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 safet; 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.
9212140154 921208 PDR ADOCK 05000327 P
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1
. 2.
Accordingly, the license is amended by changes to the Technical Spacifications 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) lechnical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.165, ara 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION h
Frederick J. Heb on, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: December 8, 1992
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ATTACHMENT TO LICENSE AMENDMENT NO.165 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 3-33 3/4 3-33 3/4 3-33a 3/4 3-33a l
i
INSTRUMENTATION TABLE 3.3-5 (Continued)
TABLE NOTATION (1) Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps, SI and RHR pumps.
(2) Using air operated valve.
The ESFAS instrumentation channel RESPONSE TIME requirement for specific feedwater air-operated valve (s) can also be met when the associated air-operated valve is either closed with air supply (s) isolated, isolated by a closed manual valve, or isolated by a closed feedwater isolation valve with power removed.
When using one of these provisions for satisfying the air-operated valve response time, ths closed or isolated condition described above will be verified at least once per 7 days.
(3) The following valves are exceptions to the response times shown in the table and will have the vt. lues listed in seconds for the initiating signals and function indicated:
Valves:
FCV-28-240, -243 Response times:
2.d. 21((0)/31(9) i 8) 3.d. 22 4.d. 21(8)j (9) 5.d 24(8)j (9) 6.d. 21(8)j (9)
Valves:
FCV-61-96, 110, -122, -191, -192, -193, -194 Response times:
2.d. 31((8) 3.d. 32(8) 4.d. 31(8) 5.d 34(8) 0)
6.d. 31 Valve:
FCV-70-143 f
Response times:
2.d. 61( /71(9) 3.d. 62 4.d. 61I0)/ (9)
(9) 5.d. 64
/
(9) 6.d. 61
/
(4) On 2/3 any Steam Generator (5) On 2/3 in 2/4 Steam Generator (6) Radiation detectors for Containment Ventilation Isolation may be excluded from Response Time Testing.
1 SEQUOYAH - UNIT 1 3/4 3-33 Amendment No. 17, 55, 165
3.
-n INSTRUMENTATION TABLE 3.3-5 (Continued)
TABLE NOTATION (7) Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response time limit includes opening and closing of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(8) Diesel generator starting and sequence loading delays not included.
Response time -limit includes operating time of valves.
(9) Diesel generator starting and sequence loading delays included.
Response
time limit includes operating time of valves.
(10) The response time for loss of voltaga is measured from the time voltage is lost until the time-full voltage is restored by the diesel.
The response time for degraded voltage is measured from the time the load shedding signal is generated, either from the degraded voltage or the SI enable timer, to the time f'ill voltage is restored by tha diesel. The response time of the timers is covered by the requirements on their setpoints.
(11) The. provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven Auxiliary Feedwater Pump.
(12) The following valves are exceptions to the response times shown in the Table and will have the values listed in seconds for the initiating signals and the function Mdicated:
Valves:
FCV-67-89, -90, -1.25, -106 Response times:
- 7. b,
75(8)/85(9)
Valve:
FCV-70-141 Response times:
7.b, 70(8)/80(9)
(13) Containment purge valves only.
Containment radiation monitor valves have a responst time of 6.5 seconds or less.
(14) Does no';
x,"de Trip Time Delays.
Response times noted include the transmi % :3, dagle-21 process protection cabincts, solid tate s
protection cabinets, and actuation devices (up to and including pumps).
This reflects the response times necessary for THERMAL POWER in excess of 50% RTP.
SEQUOYAH - UNIT 1 3/4 3-33a Amendment No. - 29, 77, 82, 106, 141
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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IENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 l
SE0VOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
- i Amendment No.155 License No. OPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee-Valley Authority (the licensee) dated November 9, 1992, complies with the standards and-recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Comission's rules and regulations' set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thert is_ reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and-afety 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 defe.re and securf ty or to the health and safaty of the public; and E.
The issaance of this amendment is in accordance with 10 CFR part 51' of.tht, Comission's regulations and all applicable requirements have been satisfied.
1 1
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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 paragrapl) 2.C.(2) of Facility Operating License No. OPR-79 is hereby amended to read as follows:
(2) Inchnical Soecifications The Technical Specifications contained in A)pendices A and B, as revised through Amendment No.155, are hereay 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION I
-l Frederick J. 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: December 8,1992
1 ATTACHMENT TO LICENSE AMENDMENT NO.155 FACILITY OPERATING LICENSE NO. DPR-79 QQLKET 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 marginal lines indicating the area of change.
REMOVE INSERT 3/4 3-33 3/4 3-33 3/4 3-33a 3/4 3-33a i
INSTRUMENTATION TABLE 3.3-5 (Continued)
TABLE NOTATION (1) Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps SI and RHR pumps.
(2) Using air operated valve.
The ESFAS instrumentation channel RESPONSE TIME requirement for specific feedwater air-operated valve (s) can also be met when the associated air-operated valve is either closed with air supply (s) isolated, isolated by a closed manual valve, or isolated by a closed feedwater isolation valve with power removed.
When using one of these provisions for satisfying the air-operated valve response time, the closed or isolated condition described above will be verified at least once per 7 days.
(3) The following valves are exceptions to the response times shown in the table and will have the values listed in seconds for the initiating signals and function indicated:
Valves:
FCV-26-240, -243 2.d. 21((0)/31 0)
I9)
Response times:
3.d. 22 4.d. 21(0)/31(9) 50)/34(9) 5.d. 24(0)/31(9) 6.d. 21 Valves:
FCV61-96, -97, -110, -122, -191, -192, -193, -194 Response times 2.d. 31(0) 0)
3.d. 32(
4.d. 31 5.d. 34 6.d, 31(8)
Valve:
FCV-70-143 Response times:
2.d. 61
/71(0) 3.d. 62 4.d. 61((8)/71((9) 0)/74 9) 5.d. 64(0)/71( )
6.d. 61 (4) On 2/3 any Steam Generator (5) On 2/3 in 2/4 Steam Generator (6) Radiation detectors for Containment Ventilation Isolation may be excluded from Response Time Testing.
SEQUOYAH - UNIT 2 3/4 3-33 Amendment No. 8, 47, 155
INSTRUMENTATION TABLE 3.3-5 (Continued)
TABLE NOTATION (7) Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response time limit includes opening and closing of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(8) Diesel generator starting and sequence loading delays not included.
Response time limit includes operating time of valves.
(9) Diesel generator starting and sequence loading delays included.
Response
time limit includes operating time of valves.
(10) The response time for loss of voltage is measured from the time voltage is lost until the time full voltage is restored by the diesel.
The response time for degraded voltage is measured from the time the load shedding signal is generated, either from the degraded voltage or the SI enable timer, to the time full voltage is restored by the diesel.
The response time of the timers is covered by the requirements on their setpoints.
(11) The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven Auxiliary Feedwater Pump.
(12) The following valves are exceptions to the response timos shown in the table and will have the values listed in seconds for the initiating signals and the function indicated:
Valves:
FCV-67-89, -90, -105, -106 Response times:
- 7. b,
75(8)/85(9)
Valve:
FCV-70-141 Response times:
7.b, 70(8)/80(9)
(13) Containment purge valves only.
Containment radiation monitor valves have a response time of 6.5 seconds or less.
(14) Does not include Trip Time Delays.
Response times noted include the transmitters, Eagle-21 process protection cabinets, solid state protection cabinets, and actuation devices (up to and including pumps).
This reflects the response times necessary for THERMAL POWER in excess of 50% RTP.
SEQUOYAH - UNIT 2 3/4 3-33a Amendment No. 18, 47, 68, 73, 96, 132