ML20207G975
| ML20207G975 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/15/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20207G981 | List: |
| References | |
| NUDOCS 8808240316 | |
| Download: ML20207G975 (14) | |
Text
.
a ue o
UNITED STATES g
NUCLEAR REGULATORY COMMISSION e
n f
WASHINGTON, D. C. 20555 h
l n
i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. OPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 20, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
1 and the Comission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity 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 authori;'ed by this amendment can be conducted without endangering the nealth and safety of the public, and (.1) that such activities will be
' conducted in compliance with the Coginission's regulations; D.
The issu'ance 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 reauirements have been satisfied.
ff 0
7 P
l 1
. 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. OPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical.pecifications contained in Appendices A and B, as revised through Amendment No. 79, 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 COMMISSION sx Suzann lack, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 15, 1988 8
=,,
?
ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 1
l 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. Overleaf pages* are provided to maintain document completeness.
l REMOVE INSERT l
3/4 7-13 3/4 7-13*
3/4 7-14 3/4 7-14 8 3/4 7-3 8 3/4 7-3*
B 3/4 7-4 8 3/4 7 a 1
J
a PLANT SYSTEMS 3/4.7.? ESSENTIALRAWCp0LINGWATERSYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two andependent essential raw cooling water (ERCW) loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With only one ERCW loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
)
and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i SURVEILLANCE REQUIREMENTS 1
4.7.4 At least two ERCW loops shall be demonstrated GPERA8LE:
a.
At least once per 31 days by verifying that each valve (mancal, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position, j
b.
At least once per 18 months, during shutdown, by:
Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.
i 2.
Verifying that each ERCW oump starts automatically on a Safety Iajection test signal.
SEQUOYAH - UNIT 1 3/4 7-13 Amendment No.
12
PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION
- 3. 7. 5' The ultimate heat sink shall be OPERABLE with:
- A minimum water level at or above elevation 670 feet mean -
a.
sea level USGS datum, and b.
An average ERCW supply header water temperature of less than or-equal to 83'F, and When the water level is above 680 feet mean sea level USGS c.
datum, the average ERCW supply header water temperature may be less than nr equal to 84.5'F.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With the requirements of the above specification not satisfied, be_in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIPEMENTS 4.7.5.1 The ultimate heat sink will be determined CPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average ERCW supply header temperature and water level to be within their limits.
SEQUOYAH - UNIT 1 3/4 7-14 Amendment !o. ///7'(/I?j 79
6 PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of J.e Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70 F and 200 psig are based on a steam generator RT of 25 F and are sufficient to HDT prevent brittle fracture 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM The OPERABILITY of the essential raw cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
SEQUOYAH - UNIT 1 B 3/4 7-3 Amendment No. 12 Revised 08/18/87 I
a-ou.su
PLANT SYSTEMS BASES 3/4.7.5 ULTIMATE HEAT SINK (UHS)
The limitations on UHS water level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitations on the maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Plants", March 1974.
The limitations on minimum water level are based on providing sufficient flow to the ERCW serviced heat loads after a postulated event assuming a time-dependent drawdown of reservoir level.
Flow to the ma,ior transient heat loads (CCS and CS heat exchangers) is balanced assuming a reservoir level of elevation 670.
The time-independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of elevation 636.
3/4.7.6 FLOOD PROTECTION The requirements for fload p'rotection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. A Stage 1 finod warning is issued when the water 'in tha forebay is predicted to exceed 69/ feet Mean Sea Level USGS datum during October 1 through April 15, or 703 Feet Mean Sea Level USGS datum during April 15 through September 30.
A Stage II flood warning is issued wnen the water in the forebay is predicted to exceed 703 feet Mean Sea Level USGS datum.
A maximum allowed water level of 703 feet Mean Sea level USGS datum provides sufficient nar
.n to ensure waves due to high winds cannot disrupt the flood mode preparation.
A Stage I or Stage II flood warning requires the imple-mentation of procedures which include plant shutdown.
Further, in the event of a loss of communications simultaneous with a critical combination flood, headwaters, and/or seismi'cally induced dam failure the plant will be shutdown e
and flood protection measures implemented.
3/4.7.7 CONTROL ROOM EMERGENCY VENT!LATION SYSTEM The OPERABILITY of the control room ventilati r system ensures that o
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPEPABILITY of this system in conjunction with control room design provisions is bcsed on limitino the radiation exposure to personnel occupyino the control rocn to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of Generai Desiyn Criteria 19 of Appendix "A",10 CFR 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
1 SEQUOYAH - UNIT 1 P. 3/4 7-4 Amendrent No. / 79 1
-y v
~
- pa ntaug'o, UNITED STATES
! " ),,.. J'.,g NUCLEAR REGULATORY COMMISSION -
I WASHINGTON. D. C. 20555 g,
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.70 License No. OPR-79 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 20, 1988, 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 Comiscion; 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 Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the ccmon defense and security or to the %alth and safety of the public; and i
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.
l l
1
. ~.
2-2.
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. OPR-79 is hereby 4
amended to read as follows i
)
-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revisec.arough Amendment No. 70, are hereby incorporated in the j
license. The licensee shall operate the facility in accordance with the Technical Specifications.
J 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION j wy__
.(C
(.-
Suzann' Black, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 15, 1988 l
e f
-_w-,
,e
.,m.
- m. - -
-_.-y-
,yyg--
.y-,
y,-.,,,,
,9 rwg-9
,,_____,,,_-,4,p
,.pgom y-
_,,wg,.c,g5g-,.p-_
m.-
9,
,. y
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 70 FACILITY OPERATING LICENSE NO. OPR-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 lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3/4 7-13 3/4 7-13*
3/4 7-14 3/4 7-14 B 3/4 7-3 B 3/4 7-3*
B 3/4 7-4 8 3/4 7-4
..,,--..,-,,,,,n.-.
PLANT SYSTEMS 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent essential raw cooling water (ERCW) loops.
shall be OPERABLE.
APPLICABILITY: ' MODES 1, 2, 3 and 4.
ACTION:
With only one ERCW loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the,following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4 At least two ERCW loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, ~is in its correct position.
b.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each ERCW pump starts automatically on a Safety Injection test signal.
l SEQUOYAH - UNIT 2 3/4 7-13
C i
. PLANT SYSTEMS 3/4.7.5 ULTIMATEHEATSIE LIMITINGCONDITIONFOROPERATION 3.7.5 The ultimate heat sink shall be OPERABLE with:
A minimum water level at or above elevation 670 feet mean a.
sea level USGS datum, and b.
An average ERCW supply header water temperature of less than or equal to 83 F, and When the water level is above 680 feet mean sea level USGS c.
datum, the average ERCW supply header water temperature may be less than or equal to 84.S*F.
APPLICABILITY:' MODES 1, 2, 3 and 4.
ACTION:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 6 hnurs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.7.5.1 The ultimate heat sink will be determined OPERABLE at least once per 24 hnurs by verifying the average ERCW supply header tenperature and wat9r leval to be within their limits.
a SEQUOYAH - UNIT 2 3/4 7-14 Amendment No. 70
PLANT SYSTEMS BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70*F and 200 of 25*F and are sufficient to prevent psig are based on a steam ganerator RTHDT brittle fracture.
3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses 3/4.7.4 ESSENTIAL RAW C(0 LING WATER SYSTEM The OPERABILITY of the essential raw cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
SEQUOYAH - UNIT 2 8 3/4 7-3 Revised 08/18/87 2a.1J UkL'by
PLANT SYSTEMS BASES 3/4.7.5 ULTIMATE HEAT SINK (UHS)
The limitations on UHS water-level-and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitations on the maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Plants", March 1974.
The limitations on minimum water level are based on providing sufficient flow to the ERCW heat loads after a postulated event assuming a time-dependent drawdown of reservoir level.
Flow to the major transient heat loads (CCS and CS heat exchangers) is balanced assuming a reservoir level of elevation 670.
The time-independent heat loads (ESF room coolers, etc.) are balanced assuming a reservoir level of elevation 636.
3/4.7.6 FLOOD PROTECTION The requirements for flooo protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions.
A Stage 1 flood warning is issued when the water in the forebay is predicted to exceed 697 feet Mean Sea Level USGS datum during October 1 throuch April 15, or 703 Feet vean Sea level USGS datum during April 15 through September 30.
A Stage II flood warning is issued when the water in the forabay is predicted to exceed 703 feet Mean Sea level USGS datum.
A maximum allowed water level of 703 feet Mean Sea Level USGS datum provides sufficient margin to ensure waves due to high winds cannot disrupt the flood mode preparation.
A Stage I or Stage II flond warning requires the imple-mentation of procedures which include plant shutdown.
Further, in tha avent of a loss of communications simultaneous with a critical combination flood, headwaters, and/or seismically induced dam failure the plant will be shutdown and flood protection measures implemented.
3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ersures that
- 1) the ambient air temperature does not exceed the allowable temperature for continuous duty ratir.g for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations pernannel during and following all credible accident conditions.
The OPERAS!LITY of this system in conjunction with control room design provisinns is casec on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is censistent with the requirements of Geraral Design Criteria 19 of Appendix "A".10 CFD En.
l ANSI N510-1975 will be used as a procedural guide for surveillance testino.
SEQUOYAH - UNIT 2 8 3/4 7 4 Amendment "c. 70 l
....