ML20236E027
| ML20236E027 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/13/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236E030 | List: |
| References | |
| NUDOCS 8903230416 | |
| Download: ML20236E027 (12) | |
Text
m 9,
LpNITED STATES
[
g NUCLEAR REGULATORY COMMISSION g
5 WASHINGTON, D. C. 20686
\\*....J 1
J t
l TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-327 I
l SEQUOYAH NUCLEAR PLANT, UNIT 1-
]
AMENOMENT TO FACI (.!TY OPERATING LICENSE l
' Amendment No.106 License No. DPR-77 l
1.
The Nuclear Regulatory Comission (the Connission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 14, 1987, complies with the ctandards and j
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Consission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the l
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 Commission's regulations and all applicable requirements have been satisfied.
I 7
8903230416 890313 PDR ADOCK 05000327 P
j 2.
Accordingly the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby l
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, 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.
FOR THE NUCLEAR REGULATORY COMISSION Suzanne lack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications I
l l
Date of Issuance: March 13, 1989 I
L ATTACHMENT TO LICENSE AMEN 0 MENT NO. 106 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 1
Revise the Appendix A Technical Specifications by removing.the pages i
identified below and inserting the enclosed pages.
The revised pages i
are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 3-29 3/4 3-29 1
3/4 3-30 3/4 3-30 3/4 3-33a 3/4 3-33a l
l 1
1 4
1 i
i i
A+
4.
TABLE 3.3-5 ENGINEERED S_AFETY FEATURES RESPONSE-TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS 1.
Manual a.
Safety Injection (ECCS)
Not-Applicable
_Feedwater Isolation Not Applicable Reactor Trip (SI)
Not Applicable Containment Isolation-Phase "A" Not Applicable-Containment Ventilation Isolation Not Applicable Auxiliary.Feedwater Pumps Not Applicable Essential Raw Cooling Water System' Not Applicable Emergency. Gas Treatment System Not Applicable b.
Containment Spray Not Applicable Containment' Isolation-Phase "B" Not Applicable Containment Ventilation Isolation Not Applicable Containment Air Return Fan Not Applicable c.
Containment Isolation-Phase "A" Not Applicable Emergency Gas Treatment System Not Applicable 1
Containment' Ventilation Isolation Not Applicable
]
l-d.
Steam Line Isolation Not Applicable
.i 2.
Containment Pressure-High a.
Safety Injection (ECCS) 1 32.0(1) b.
Reactor Trip (from SI)
< 3.0 c.
Feedwater Isolation 8.0(2) d.
Containment Isolation-Phase "A"(3) 18.0(8)/28.0(9) e.
Containment Ventilation Isolation 5.5(8)(13) f.
Auxiliary Feedwater Pumps 60(11) g.
Essential Raw Cooling Water System
[65.0(8)/75.0(9) h.
Emergency Gas Treatment System 1 38.0(9)
SEQUOYAH - UNIT 1 3/4 3-29 Amendment No. 55, 77, 106 w___-___-_-_
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) 132.0(1)/28.0(7) b.
Reactor Trip (from SI) 1 3.0 c.
Feedwater Isolation
< 8.0(2) d.
Containment Isolation-Phase "A"(3) 18.0(8) e.
Containment Ventilation Isolation 5.5(8)(13) f.
Auxiliary Feedwater Pumps 160(11) g.
Essential Raw Cooling Water System 165.0(8)/75.0(9) h.
Emergency Gas Treatment System 128.0(8) 4.
Differential Pressure Between Steam Lines-High a.
Safety Injection (ECCS) 528.0(7)/28.0(1) b.
Reactor Trip (from SI)
<3.0 c.
Feedwater Isolation 8.0(2) d.
Containment Isolation-Phase "A"(3)
[18.0(8)/28.0(9) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps
<60(11) g.
Essential Raw Cooling Water System 65.0(8)/75.0(9) h.
Emergency Gas Treatment System 138.0(9) 5.
Steam Flow in Two Steam Lines - High Coincident with I
--Low-Low a.
S f ty Injection (ECCS) 130.0(7)/30.0(1) b.
Reactor Trip (from SI) 15.0 c.
Feedwater Isolation
<10.0(2) d.
Containment Isolation-Phase "A"(3)
[20.0(8)/30.0(9) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps
<60(11) g.
Essential Raw Cooling Water System 67.0(8)/77.0(9) h.
Steam Line Isolation
<10.0 i.
Emergency Gas Treatment System 40.0(9)
SEQUOYAH - UNIT 2 3/4 3-30 Amendment No. 47, 68, 96
I' e
TABLE 3.3-5 (Continued)
TABLE NOTATION (10) The response time for loss oi 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 j
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 j
MODE 3 for the turbine-driven Auxiliary Feedwater Pump.
l l
(12) The following valves are: exceptions to the response times shown in the i
l Table and will have the values listed in seconds for the initiating I
signals and the function indicated:
Valves:
FCV-67-89,-90,-10{3)/85pg)
-10 Response times:
7.b, 75 1
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.
SEQUOYAH - UNIT 1 3/4 3-33a Amendment No. 29, 77, 82, 106
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NUCLEAR REGULATORY COMMISSION 3
l wAsHWGTON, D. C. 20566
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i TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE l
)
Amendment No. 96 l
License No. OPR-79 I
.1 1
1.
The Nuclear Regulatory Cosnission (the Connission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedSeptember 14,.1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
-1 I
and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in ecnfomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by l
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 j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cosmission'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. 96, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Cb Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 12, 1989
ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-79 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 marginal l
l lines indicating the area of change.
REMOVE INSERT 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-33a 3/4 3-33a j
f i
i f
l
~
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS l
1.
Manual a.
Safety Injection (ECCS)
Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI)
Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Essential Raw Cooling Water System Not Applicable Emergency Gas Treatment System Not Applicable b.
Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation Isolation Not Applicable Containment Air Return Fan Not Applicable c.
Containment Isolation-Phase "A" Not Applicable Emergency Gas Treatment System Not Applicable Containment Ventilation Isolation Not Applicable d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High a.
Safety Injection (ECCS)
$ 32.0(1) b.
Reactor Trip (from SI)
<3.0 c.
Feedwater Isolation 8.0(2) d.
Containment Iso'1ation-Phase "A"(3) 18.0(8)/28.0(9) e.
Containment Ventilation Isolation 1 5.5(8)(13) f.
Auxiliary Feedwater Pumps 160(11) g.
Essential Raw Cooling Water System 165.'0(8)/75.0(9) h.
Emergency Gas Treatment System 138.0(9)
SEQUOYAH - UNIT 2 3/4 3-29 Amendment No. 47, 68, 96
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS)
_1 32.0(1)/28.0(7) b.
Reactor Trip' (from SI)
< 3.0 c.
Feedwater Isolation 8.0(2) d.
Containment Isolation-Phase "A"(3) 18.0(8) i e.
Containment Ventilation Isolation 5.5(8)(13)
- f.
Auxiliary Feedwater Pumps 60(11) g.
Essential Raw Cooling Water System 65.0(8)/75.0(9) h.
Emergency Gas Treatment System 1 28.0(8) l 4.
Differential Pressure Between Steam Lines-High a.
Safety Injection (ECCS) 1 28.0(7)/28.0(1)-
b.
Reactor Trip (from SI)
< 3.0 c.
Feedwater Isolation 8.0(2) d.
Containment Isolation-Phase "A"(3) k18.0(8)/28.0(9) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps
< 60(11) g.
Essential Raw Cooling Water System 65.0(8)/75.0(9) l h.
Emergency Gas Treatment System 1 38.0(9) l 5.
Steam Flow in Two Steam Lines - High Coincident l
l with T
--Low-Low
]
a.
S ty Injection (ECCS) 1 30.0(7)/30.0(1)
I b.
Reactor Trip (from SI) 15.0 J
c.
Feedwater Isolation
< 10.0(2) d.
Containment Isolation-Phase "A"(3)
}20.0(9)/30.0(9) e.
Containment Ventilation Isolation Not Applicable
]
f.
Auxiliary Feedwater Pumps
< 60(11) l g.
Essential Raw Cooling Water System 67.0(8)/77.0(9) h.
Steam Line Isolation
< 10.0 1.
Emergency Gas Treatment System k40.0(9) j I
SEQUOYAH - UNIT 1 3/4 3-30 Amendment No. 55, 77, 106 i
TABLE 3.3-5 (Continued)
TABLE NOTATION (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 anlicable for entry into MODE 3 for the turbine-driven Auxiliary Feedwatv Pump.
(12) The following valves are exceptions to the respt.1se times 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,-10{g)/85pg)
-10 Response times:
7.b, 75 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.
1 SEQUOYAH - UNIT 2 3/4 3-33a Amendment No. 18, 68, 73, 96