ML20009E398
| ML20009E398 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/15/1981 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009E399 | List: |
| References | |
| NUDOCS 8107280154 | |
| Download: ML20009E398 (7) | |
Text
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4 u
y Tr.hul5LLE VALLEY AUTHORITY DUCKET NO. 50-327 SLOUbYAh huCLEAR PLANT, UNIT 1 AtiEND::ENT TO FACILITY OPLnATlhG LILEH5r, Atendment No. 8 License No. CPR-77 1.
The !!uclear Regulatory Comission (the Conr.ission) having found that:
A.
The application for ar.:endment to the Sequoyah liuclear Plant, Unit 1 (the tacility) Facility Operating License do. DPR-77 filed by the Tennessee Valley Authority (licensee), dated July 14, 1981, couplies with the standards and requircraents of the Atomic Energy Act of 1954, as amended (the Act) and tne Coahission's regulations as set forth in 10 CFK Chapter I; b.
The f acility will operate in confereity with the license, as ar.. ended, the provisions of the Act, and the rules and regulations of the Co.r.-
uission; C.
There is reasonable assuanet.: (i) tnat the activities authorized by this amendraent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cor,tpliance with the Comission's regulations; D.
The issuance of this aa.enduent will not be inimical to the cotr.on defense and security or te the health and safety of the public; and E.
The issuance of tnis auendi..ent is in accordance with 10 CFR Part 51 of the Conaission's regulations and all applicable requirements have been satistiec.
2.
Accordingly, the arenced license is hereby anenced by page changes to the Appendix A Tecnnical Specifications as indicated in the attach.::ents to this license acencaent and paragrapn 2.L.(2) of Facility Operating License Lo.
I'PR-077 is hereDy anended to read as follows:
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- (2) Technical Specifications The Technical Specifications contairied in Appenaix A, as revised through Amendr.ent No. 8, are hereby incorporated into the lic..7se.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This atended license is ef fective as of its date of issuance.
FOR TliE NULLEAF: REGULATURY CulOISSION Elinor G. Adensam, Acting Branch Chief Licensing Branch flo. 4 Division of Licensing Attachnent:
Appendix A Technical Specification Changes Date of 1ssuance: July 15, 1981
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i ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. DPR-77 t
DOCKET NO. 50-327 1
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 area of change. The corresponding overleaf pages are also provided to maintain document completeness. '
I Overleaf Amended Page Page 3/4 7-16 3/4 7-15 j
B3/4 7-3 B3/4 7-4 4
}
I
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PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITfNG CONDITION FOR OPERdTION 3.7.5 The ultimate heat sink shall be OPERABLE with the average temperature of water at the ERCW system suction of less than or equal to 83*F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the average temperature of the water at the ERCW system suction greater than 83*F 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 REQUIRMENTS 4.7.5 The ultimate heat sink shall be determined OPERABLE 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 temperature to be within its limits.
SEQUOYAH - UNIT 1 3/4 7-15 Amendment No. 8
PLANT SYSTEMS 3/A.7.6 FLOOD PROTECTION
- LIMITING CONDITION FOR OPERATION 3.7.6 Flood protection shall be provided for all safety related components and structures.
APPLICABILITY: At all times ACTION:
With a Stage I flood warning issued initiate and complete within a.
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> the Stage I flood protection procedure which shall include b :ng in at least HOT STAND 8Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; with a SHUTDOWN PARGIN of at least 5% delta k/k and T 1ess than or equal to 350'F within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If wit $5810 hours following the issuance of a Stage I flood warning communications between the TVA Division of Water Pesources and the Sequoyah Plant cannot be verified, or if a Stage II flood warning is issued verify that the Stage I flood protection procedure is ca,olete and initiate and complete the Stage II flood protection procedure within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
b.
With a critical ca,bination of flood and/or headwater alert issued concurrent with a loss of communications between the TVA Power Control Center and the Seouoyah Plant restore the ca,munications system to OPERABLE status within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or initiate and complete the Stage I flood protection procedure described in ACTION a above within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Upon completion of the Stage 1 flood protection procedure initiate and complete the Stage II flood protection procedure within the following 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />, c.
With a Fontana Dam alert concurrent with a loss of cannunications between the Fontana Dam and the Sequoyah Plant restore the connuni-cation system to OPERARLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or initiate and complete the Stage I flood protection procedure described in ACTION a above within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Upon completion of the Stace I flood protection procedure initiate and complete the Stage II flood protection procedure within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
d.
With either the Norris, Cherokee, Douglas, Fort Loudoun, Fontana, Hiwassee, Apalachia, Plue Ridge or Tellico dan failed seismically, and with a critical combination of flood and/or beadwater alert issued initiate and complete the Staae I flood protection procedure described in Action a above within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Upon completion of the t
Stage I flood protection procedure initiate and complete the Stage II flood protection procedures within the following 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />.
l SEQUOYAH - UNIT 1 3/4 7-16 4
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 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 consisten,t 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 f 60 F and are sufficient to NDT prevent brittle fracture 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system cnsures 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 C09 LING WATER SYSTEM The OPERABILITY of the essential raw cooling water system and the auxilia~ry essential raw cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident cor.ditions.
',he redundant cooling capacity of this system, assuming a single failuce, is consistent with the assumptions used in the accident conditions within acceptable limits.
SEQUOYAH - UNIT 1 B 3/4 7-3 i
o
' ' PLANT SYSTEMS 4,
BASES 3/4.7.5 ULTIMATE HEAT SINK The limitations on the temperature ensure that sufficient cooling l
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 l
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.
3/4.7.6 FLOOD PROTECTION The requirements for flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. A Stage i flood warning is issued when the water in the forebay is predicted to exceed 697 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 when the water in the forebay is predicted to exceed 703 fesi. Mean Sea Level USGS datum. A maximum allowed water level of 703 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 flood warning requires the imple-mentation of procedures which include plant shutdown.
Further, in the event of a loss of cornmunications 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 ensures that 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 OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of Gt:aral Design Criteria 19 of Appendix "A",10 CFR 50.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
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SEQUOYAH - UNIT 1 B 3/4 7-4 Amendment No. 8
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