ML20082D128

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Proposed Tech Specs Re Feedwater Isolation Valves
ML20082D128
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/16/1983
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20082D113 List:
References
NUDOCS 8311220321
Download: ML20082D128 (5)


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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

- SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................ 3/4 7-1 Emergency Feedwater System............................... 3/4 7-4 Condensate Storage Tank.................................. 3/4 7-6 -

Activity................................................. 3/4 7-7 Main Steam Line Isolation Va1ves......................... 3/4 7-9

. Feechacrter cwten n u t. v ts , , , , , , , , , , , , , , , , , , , , , 3/4 7-Qa.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4 7-10 3/4.7.3 COMPONENT C00 LING WATER SYSTEM....................... ... 3/4 7-11 3/4.7.4 SERVICE WATER' SYSTEM..................................... 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK ...................................... 3/4 7-13

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3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM.... 3/4 7-14 3/4.7.7 SNUBBERS................................................. 3/4 7-16 3/4.7.8 SEALED SOURCE CONTAMINATION.............................. 3/4 7-23 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................ 3/4 7-25 Spray and/or Spri nkl er Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-28 CO 2

System............................................... 3/4 7-30 Fire Hose Stations....................................... 3/4 7-31 Yard Fire Hydrants and Hydrant Hose He ises. . . . . . . . . . . . . . . 3/4 7-33 3/4.7.10 FIRE RATED ASSEMBLIES.................................... 3/4 7-35 3/4.7.11 AREA TEMPERATURE MONITORING........... ................. 3/4 7-37 j

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SUMMER-UNIT 1 VIII l

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PLANT SYSTEMS FEEDWATER ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3 7 1.6 Each feedwater isolation valve shall be OPERABLE.

APPLICABILITY: E DES 1, 2 and 3 ACTION:

MODE 1 With one feedwater isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; Otherwise, be in HOP 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 HOT ShVIDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

EDES 2 With one feedwater isolation valve inoperable, subsequent and 3 operation in E DES 2 or 3 may proceed provided:

a. 'Ihe isolation valve is maintained closed.
b. 'lhe provisions of Specification 3 0.4 are not applicable.

Otherwise, be in HOP SPANDBY 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 HOP SHUIDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7 1.6 Each feedwater isolation valve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5 i

I SUMMER - UNIT 1 3/4 7-9a~

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PLANT SYSTEMS l( -

BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATI'ON 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 the reactor building in the event the f steam line rupture occurs within the reactor building. 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.

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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 the average impact valves of th'e steam generator material at 10*F and are sufficient to prevent brittle fracture.

i 3/4.7.3 COMPONENT COOLING WATER SYSTEM

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The OPERABILITY of the component cooling water system ensures that suf-1 ficient 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 SERVICE WATER SYSTEM The OPERABILITY of the service water system ensures that sufficient cooling ~ capacity is available for continued operation of safety related-

'g 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.

. 3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink 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. -

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SUMMER - UNIT 1 B 3/4 7-3

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PAGE B 3/4 7-3 3/4.7.1.6 FEEDWATER ISOLATION VALVES.

The OPERABILITY of the Feedwater Isolation Valves serves to (1) limit the effects of a Steam Line rupture by minimizing the positive reactivity effects of the Reactor Coolant System Cooldown associated with the blowdown, and (2) limit the pressure rise within the reactor building in the event of a Steam Line or Feedwater Line rupture within the reactor building.

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