ML20214F254
| ML20214F254 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/12/1987 |
| From: | Zwolinski J NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20214F257 | List: |
| References | |
| NUDOCS 8705260004 | |
| Download: ML20214F254 (18) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g
.,i wAsmNGTON, D'. C. 20555
+....
TENNESSEE VALLEY AUTHORITY-DOCKET NO.
50-322.
-SE000YAH NUCLEAR PLANT, UNIT'1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 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. OPR-77 filed.by the Tennessee Valley Authority (licensee), dated December 23, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and 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 Comission; 4
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 comoliance 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 Apoendix A 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 to read as follows:
1
. (2) Technical ~ Specifications The Technical' Specifications contained in Appendix A, as revised through
' Amendment No. 55 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 Original signed by 4
John A. Zwolinski,' Assistant Director'
'for Projects
~
Division of TVA Projects Office of Special Projects
- Attachment Appendix A Technical-Specification Changes Date of Issuance: May 12, 1987 a
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(2) Technical specifications The Technica Specifications contained in Appendix A, as revised through Amendment No.-
are hereby incorporated into the license. The licensee shall operate e facility in accordance with the. Technical Specifications.
3.
This license amendme t is effective as of its date ! issuance.
FOR THE NUCLE REGULATORY COMMISSION B. J. Y ngblood, Director PWR Pr ect Directorate #4 Divisi n of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO. 55-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. Overleaf page provided to maintain-document completeness.*
REMOVE INSERT 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32*
3/4 3 3/4 3-33 4
l
. TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 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) 1 32.0(1) b.
Reactor Trip (from SI) s 3.0 c.
Feedwater Isolation
< 8.0(2) d.
Containment Isolation-Phase "A"(3) 1 18.0(8)/28.0(9) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps 1 60 g.
Essential Raw Cooling Water System 1 65.0(8)/75.0( )
h.
Emergency Gas Treatment System 1 38.0(9) i SEQUOYAH_- UNIT 1 3/4 3-29 Amendment No. 55
P.
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)/28.0I7)
- bl 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-Not' Applicable 1
f.
Auxiliary Feedwater Pumps s '60 --
g.
. Essential. Raw Cooling Water System 1 65.0(8)/75.'0(9)
'h.
Emergency-Gas Treatment System-1 28.0(8) 4.
Differential Pressure Between 6 team Lines-High a.
Safety. Injection (ECCS) 1: 28.0(7)/28.0(1).
b Reactor Trip-(from SI)
-1 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 g.
Essential Raw Cooling Water System 65.0(8)/75.0(9) h.
Emergency Gas Treatment System 1-38.0(9) 5.
Steam Flow in Two Steam Lines - High Coincident-with T
--Low-Low a.
S f ty Injection (ECCS' 1 30.0(7)/30.0(1) b.
Reactor Trip (from SI) 1 5.0-l 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 1-60 g.
Essential Raw Cooling Water System 1 67.0(8)/77.d(9) h.
Steam Line Isolation
< 10.0
~
i.
Emergency Gas Treatment System 40.0(9) i
\\
SEQUOYAH - UNIT 1 3/4 3-30 Amendment No. 55
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.
Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure-Low a.
Safety Injection (ECCS) 1 28.0(7)/28.0(1) b.
Reactor Trip (from SI) 1 - 3. 0 c.
Feedwater Isolation
< 8.0(2) d.
. Containment Isolation-Phase "A"(3) 18.0(b)/28.0(9) e.
Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps
_$ 60 65.0(8)/75.0(9) g.
Essential Raw Cooling Water System 5
h.
Steam Line Isolation
< 8.0 i.
Emergency Gas Treatment System 38.0(9) 7.
Containment Pressure--High-High 58.00(9) a.
b.
Containment Isolation-Phase "B" s 65(8)/75(9) c.
Steam Line Isolation 1 7.0 d.
Containment Air Return Fan
> 540.0 and i 660 8.
Steam Generator Water Level--High-High a.
Turbine Trip-Reactor Trip-1 2.5 b.
Feedwater Isolation 1 11.0(2) 9.
Main Steam Generator Water Level -
Low-Low a.
Motor-driven Auxiliary 5 60.0 Feedwater Pumps (4) b.
Turbine-driven Auxiliary 1 60.0 Feedwater Pumps (5)
SEQUOYAH - UNIT 1 3/4 3-31 Amendment No.JZ, 55
. TABLE 3.3-5-(Continued)-
ENGINEERED SAFETY FEATURES RESPONSE TIMES
' INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 10.
Station Blackout a.
Auxiliary Feedwater Pumps
~1 60
- 11. Trip of Main Feedwater Pumps a.
Auxiliary Feedwater Pumps 1.60
- 12. Loss of.' Power a.
6.9 kv Shutdown Board - Degraded 5.10(10)-
Voltage or Loss of Voltage 13.
RWST Level-Low Coincident with Containment Sump Level-High and Safety Injection a.
Automatic Switchover to Containment Sump i 250 14.
Containment Purge Air Exhaust Radioactivity - High a.
Containment Ventilation Isolation i 10(6) 15.
Containment Gas Monitoi Radioactivity High a.
Containment Ventilation Isolation i 10(6) 16.
Containment Particulate Activity High a.
Containment Ventilation Isolation i 10(6)
- NOTE:
This technical specification to be implemented at the startup following the second refueling outage or following completion of the modification, whichever is earlier.
SEQUOYAH - UNIT 1 3/4 3-32 Amendment No. 29 a
4
~
. TABLE 13.3-5 (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 (3) The_following valves are exceptions to the response 1 times shown-in the
-table and will have the values liste'd in seconds for-the; initiating.sig-nals and function' indicated:
-Valves:.FCV-26-240, -243z.
Response times:
2.d.'21
/ 31(9)-
3.d. 22 4.d. 21((8)/ 31(9)
(9) 5.d.24(8)f3p9)'
6.d. 21 8)/31 Valves:
FCV-61-96, -97, -110, -122, -191, -192,'-193, -194
. Response times:
2.d. 31(8) 3.d. 32(8) 4.d. 31((8) 8)
5.d. 34 6.d. 31(0) t Valve:
FCV-70-143 Response times:
2.d. 61
/71( )
3.d. 62
)
4.d. 61(8)/71( )
5.d. 64(8)/74( )
6.d. 61( /715}
(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.
(7) Diesel generator starting and sequence loading'd'elays not included. ' Offs'i te power available.
Response time' limit includes opening and closing offvalves l.
~
to establish SI path and-attainment of discharge pressure-for centrifugal.
I 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
2 time limit includes operating time of valves.
j i
- SEQUOYAH - UNIT 1 3/4 3-33 Amendment,No.J7,.55
' UNITED STATES
-1 t, -
NUCLEAR REGULATORY COMMISSION
{
Y WASHINGTON, D. C. 20555
's.,.....j TENNESSEE VALLEY AUTHORITY DOCKET NO.
50-328 SE000YAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATtNG LICENSE Amendment No. 47 License.No. DPR-79 1.
The Nuclear Regul$ tory 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 December 23, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the'Act) and the Commission's rules and 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 Comission; 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 accoroance 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 I
amendinent, 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 Soscifications; The-.TechnicalSpecificationscontainedDkn;AppendixAfasrevisedthrough.
Amendment No. 47 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 _REGULATORYCOMMISSION.-
Original' signed by
-John A._Zwolinski, Assistant Director for Projects-Division of TVA Projects Office of Special Projects Attachment Appendix A Technical Specification Changes-Date of Issuance:
May 12, 1987 4
4 i
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' f' (2) Technical Specifications The Technical Spec fications contained in Appendix A, as revised through Amendment No.
a hereby incorporated into the license. The licensee shall operate the f ility in accordance with t e Technical Specifications.
3.
This license amendment is fective as of its dat of issuance.
FOR THE NUC EAR REGULATORY COMMISSION B. J. Y ungblood, Director PWR Pr ject Directorate #4 ivis n of PWR Licensing-A Attachment Appendix A Technical Specification Changes Date of Issuance:
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 47 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. Overleaf page provided to maintain document completeness.*
REMOVE INSERT 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32*
3/4 3-33 3/4 3-33
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TABLE ~3.3 ENGINEERED SAFETY FEATURES RESPONSE' TIMES
' INITIATING SIGNAL AND-FUNCTION
. RESPONSE TIME IN SECOND'S 1.
Manual a.
Safety Injection-(ECCS)
Not Applicable Feedwater, Isolation Not Applicable Reactor Trip (SI)
Not Applicable-Containment Isolation-Pha'se "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) 13.0 d.
Containment Isolation-Phase "A"(3)
~<8.0(2) c.
Feedwater Isolation 118.0(8)/28.0( )
e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps
- 160 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
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-Not Applicable f.
Auxiliary Feedwater Pumps 610 g.
Essential Raw Cooling Water System
<65.0(8)/75.0(9) h.
Emergency Gas Treatment System 128.0(8) 4.
Differential Pressure Between Steam Lines-High a.
Safety Injection (ECCS) 128.0(7)/28.0(I) b.
Reactor Trip (from SI) 53.0 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 610 g.
Essential Raw Cooling. Water System 165.0(8)/75.0(9) h.
Emergency Gas Treatment System 138.0(9) 5.
Steam Flow in Two Steam Lines --High Coincident' with T
--Low-Low a.
Saf 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 160 67.0(8)/77.0(9) g.
Essential Raw Cooling Water System 1
h.
Steam Line Isolation (10.0 f.
Emergency Gas Treatment System 40.0(9)
SEQUOYAH - UNIT 2 3/4 3-30 Amendment No. 47
TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES-INITIATING SIGNAL AND FUNCTION RESPONSE TIME-IN SECONDS.
i 6.
Steam Flow in Two Steam-Lines-High Coincident with Steam Line Pressure-Low a.
Safety Injection (ECCS)
< 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)
$ 18.0(8)/28.0(9)'
e.
Containment Ventilation Isolation Not~ Applicable l
i f.
Auxiliary Feedwater Pumps 160
.g.
Essential Raw Cooling Water System 5 65.0(8)/75.0(9) h.
Steam Line Isolation
< 8.0 C9) i.
Emergency Gas Treatment System 138.0 I-7.
Containment-Pressure--High-High
[
a.
Containment Spray 1 58.00(9) j b.
Containment Isolation-Phase "B"
< 65(8)/75(9) c.
Steam Line Isolation
< 7.0 4
d.
Containment Air Return Fan
> 540.0 and 1660 4
8.
Steam Generator Water Level--High-High a.
Turbine Trip-Reactor Trip
$ 2.5 l
b.
Feedwater Isolation
< 11.0(2).
l 9.
Main Steam Generator Water Level -
Low-Low a.
Motor-driven Auxiliary
< 60.0 Feedwater Pumps (4)
}
b.
Turbine-driven Auxiliary
< 60.0 Feedwa5erPumps(5)
~
l l
SEQUOYAH - UNIT 2 3/4 3-31 Amendment No. 47 1.
1
- -,~..,.
~
TABLE 3.3-5 (Continued)~
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 10.
Station Blackout a.
Auxiliary Feedwater Pumps-1 60-11.
Trip of Main Feedwater Pumps a.
Auxiliary Feedwater Pumps 5 60
- 12. Loss of Power a.
6.9 kv Shutdown Board - Degraded
'< 10(10)
Voltage or Loss of Voltage 13.
RWST Level-Low Coincident with Contair. ment Sump Level-Hioh and Safety Injection a.
Automatic Switchover to Containment Sump
$ 250 14.
Containment Purge Air Exhaust 4
Radioactivity - High a.
Containment Ventilation Isolation 1 10(6) 15.
Containment Gas Monitor Radioactivity High a.
Containment Ventilation Isolation i 10(6) 16.
Containment Particulate Activity Hioh a.
Containment Ventilation Isolation i 10(6)
J
- NOTE: This technical specification is to be implemented during the startup following the first refueling outage, SEQUOYAH - UNIT 2 3/4 3-32 Amendment No. 18
-A
INSTRUMENTATION TABLE 3.3-5 (Continued)
LTABLE 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-r L(3) The following valves are exceptions to the response times shown.in the 2
-table and will have.the. values listed.-in seconds for the initiating signals and function indicated:
Valvesi FCV-26-240, -243 Response times:
2.d. 21
/31(9) 3.d..22
{,
4.d. 21
/
9 (9) 8 (9) 1 5.d. 24 j
3 6.d. 21 j (9) 8 L
Valves:
FCV61-96, -97, -110, -122, -191, -192, -193, -194 Response times l-2.d. 31(8) 3.d. 32(8)
^
4.d. 31((8) 8)-
l S.d. 34(8) 6.d. 31 4
i Valve:
FCV-70-143 Response times:
2.d. 61
/71(9) 3.d. 62 1
4.d. 61 j (9) 8 i
8 (9) 5.d. 64 j
6.d. 61 j (9) 8 (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 4
from Response Time Testing.
1 i
(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.
l (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 Ifmit includes operating time of valves.
SEQUOYAH - UNIT 2 3/4 3-33 Amendment No. 8, 47
-