ML17059A086: Difference between revisions

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| number = ML17059A086
| number = ML17059A086
| issue date = 10/29/1993
| issue date = 10/29/1993
| title = Forwards Rev 5 to Updated SAR Nine Mile Point Nuclear Station Unit 2 & Nine Mile Point Unit 2 Safety Evaluation Summary Rept 1993.
| title = Forwards Rev 5 to Updated SAR Nine Mile Point Nuclear Station Unit 2 & Nine Mile Point Unit 2 Safety Evaluation Summary Rept 1993
| author name = SYLVIA B R
| author name = Sylvia B
| author affiliation = NIAGARA MOHAWK POWER CORP.
| author affiliation = NIAGARA MOHAWK POWER CORP.
| addressee name =  
| addressee name =  
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'
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-4~P NineMilePointUnit2FSARLISTOFEFFECTIVECHAPTER9PAGESPageT=TableF=FicFureAmendmentNumberPagePageT=TableAmendmentT=TableAmendmentF=FicFureNumberF=FicFureNumberSh1Sh2TTTTTTTTTTTTTTTTTTTTTTTTTTTFFFFFFFFFFFFFFFFFFF9A.3-109A.3-109A.3-119A.3-129A.3-139A.3-149A3-159A.3-159A.3-159A.3-159A.3-159A.3-159A.3-169A.3-179A.3-179A.3-179A.3-189A.3-189A.3-189A.3-189A.3-189A-3-189A.3-189A.3-199A.3-209A.3-209A.3-219A.3-19A.3-29A.3-39A.3-49A.3-59A.3-69A.3-79A.3-89A.3-99A.3-109A.3-119A.3-129A.3-13.9A.3-149A.3-149A.3-159A3-159A.3-169A3-16Sh1Sh2Sh3Sh4Sh5Sh6Sh1Sh2Sh3Sh1Sh2Sh3Sh4Sh5Sh6Sh7Sh1Sh2Sh1Sh2Sh1Sh2Sh1Sh2R01ROOROOR01ROOA06A26A12A26A26A26A26R03A28A28R03A28R04A28A28R03A28A28R01A28A28ROOR03ROOR01R04R04R04R04ROOA23A23A23ROOROOROOA28A28A28A28A28F9A.3-17ShF9A.3-17ShF9A.3-18F9A.3-19F9A.3-20F9A.3-21F9A.3-22F9A.3-239B-1App9C9C-i9C-ii9C-iii9C.1-19C.2-19C-3-19C.3-29C.3-39C.3-49C.3-59C.3-69C.3-79C.3-89C.3-99C.3-109C.3-119C.3-12T3-1Sh1T3-1Sh2T3-2Sh1T3-2Sh2T3-2Sh3T3-2Sh4T3-3Sh1T3-3Sh2T3-3Sh3T3-4T3-59C.4-1T4-1Sh1T4-1Sh2T4-1Sh3T4-1Sh4-T4-1Sh5R03A28ROOA28A28A28A28R03A04ROOROOROOR03ROOROOROOROOROOROOROOROOR03ROOROOROOROOROOROOROOROOROOROOROOROOROOROOROOR04ROOROOROOROOROOROOT4-1Sh6T4-1Sh7T4-1Sh7aT4-1Sh8T4-1Sh9T4-1Sh109C.5-1F5-1F5-2F5-3F5-4Sh1F5-4Sh29C.6-19C.7-19C.8-19C.8-29C.8-39C.8-49C.8-59C.9-19C.10-19C.10-29C.10-39C.10-49C.10-5ROOROOROOROOR04ROOROOR02R02ROOR03R03ROOROOR03ROOROOROOROOROOROOROOROOROOROOUSARRevision4EP9-11October1992
 
NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER10PageT=TableAmendmentF=FicrureNumberPageT=TableFF=icFureAmendmentNumberPageT=TableAmendmentFFicrureNumber10-i10-ii10-iii10-iv10-v10-va10-vb10-vi10.1-110'-210.1-3T10'-1F10.1-1F10.1-2F10.1-3aF10.1-3bF10.1-3cF10.1-3dF10.1-3eF10.1-3fF10.1-3gF10.1-321F10.1-3jF10.1-3kF10.1-4aF10.1-4bF10.1-4cF10.1-4dF10.1-5aF10.1-5bF10.1-5cF10.1-5dF10.1-5eF10.1-6aF10.1-6bF10.1-6cF10.1-6dF10.1-6eF10.1-7aF10.1-7bF10.1-7cF10.1-7dF10.1-7eF10.1-7fF10.1-7gR04A24A24R04R03ROOA24R03R03AOOAOOR03AOOR03ROOROOROOROOROOR03R03R04ROOR04ROOROOROOROOR03R01R04R04R03R03R04R02ROOROOR01R01R01ROOROOR03R03F10.1-7hF10.1-7jF10'-7kF10.1-7LF10.1-7mF10.1-7nF10.1-7pF10.1-7qF10.1-7rF10.1-7sF10.1-7tF10.1-7uF10.1-7wF10.1-8aF10.1-8bF10.1-8cF10.1-8dF10.1-8eF10.1-8fF10.1-8gF10.1-9aF10.1-9bF10.1-9cF10.1-9dF10.1-9eF10.1-9fF10.1-9gF10.1-9?110.2-110.2-210.2-310.2-3a10.2-3b10.2-410.2-510.2-5a10.2-5b10'-610.2-710.2-7a10.2-7b10.2-7c10.2-7d10.2-810.2-9ROOROOROOROOR04ROOR03R03R03ROOROOROOROOR03ROOR03ROOROOROOROOROOROOROOR04ROOROOROOROOR03R04R04R04A07R03R04R04ROOR04R04R04R04R04R04A23AOO10.2-1010.2-1110.2-12T10.2-1T10.2-1T10.2-1F10.2-1F10.2-2F10.2-3F10.2-3F10'-310.3-110.3-1a10.3-1b10.3-210.3-310.3-3a10.3-3b10'-410.3-510.4-110.4-210'-310.4-3a10.4-3b10.4-410.4-4a10.4-4b10.4-510.4-610.4710.4-7a10.4-7b10'-810'-910.4-1010.4-1110.4-1210~4-1310.4-1410.4-1510.4-1610.4-1710.4-17aS?11Sh2S113S?11Sh2Sh3R02R02AOOR04R04R04AOOAOOR03A07A07A05A05A05A27R04ROOA05AOOA23AOOROOA21A06A06A28R03A06AOOAOOR01A21A21ROOA27A21A21AOOAOOR03ROOAOOROOROOUSARRevision4EP10-1October1992
 
NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER10PageT=TableF=FicpureAmendmentNumberPageT=TableF=FicFureAmendmentNumberPageT=TableF=FicFureAmendmentNumber10.4-17b10.4-1810.4-1910.4-19a10.4-19b10.4-2010.4-2110.4-2210.4-2310.4-23a10.4-23b10.4-2410.4-2510.4-25a10.4-25b10.4-2610.4-26a10.4-26b10.4-2710.4-2810.4-28a10.4-28b10.4-2910.4-3010.4-3110.4-3210.4-3310.4-33a10.4-33b10.4-3410.4-34a10.4-34b10'-35104-3610.4-3710.4-3810.4-39T10.4-1T10.4-2F10.4-1F10.4-1F10.4-1F10.4-1F10.4-1F10.4-2aF10.4-3S11S11ShSbS11S?1ROOA18A28A28A18AOOAOOAOOA26A05A05R01A10A05A05A21A05A05ROOR03A14A07ROOAOOAOOR02R02A25A20ROOA20A20AOOAOOAOOA24AOOROOA27R03R03ROOR03R03R03R03FFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFF10.4-3S11210.4-3Sh310.4-3Sh410'-3Sh5104-410'-510.4-610.4-7a10.4-7b10.4-7c10.4-7d10.4-7e10.4-7f10.4-7g10.4-7410.4-8Sh110.4-8S11210.4-8S?1310.4-8S11410.4-8S11510.4-8S11610.4-8Sh710.4-8Sh810.4-8Sh910.4-8Sh1010.4-9Sh110.4-9Sh210.4-9S11310.4-9Sh410.4-9Sh510.4-9Sh610.4-9S11710.4-9Sh810.4-9Sh910.4-9Sh,:1010.4-10Sh110.4-10SN210.4-10Sh310.4-10Sh410.4-10Sh510.4-10Sh610.4-10S?1710.4-10S?1810.4-10Sh910.4-10Sh1010.4-10Sh11R03R03R03R03AOOAOOAOOROOROOROOR02ROOROOROOROOR03ROOR03R03R03R03ROOR03R01ROOR03R03R03R03R03ROOR03R03R03R03ROOROOROOROOROOROOROOROOR03R03R03FFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFFF10.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1010.4-1110.4-1110.4-1110.4-1110.4-1110.4-1110.4-1110.4-1110.4-1110.4-1210.4-1210.4-1210.4-1210.4-1210.4-1210'-1210.4-1310.4-1310.4-1310.4-1310.4-1310.4-1310.4-1310.4-13Sh12Sh13Sh14S?115S?116Sh17Sh18Sh19Sh20S?121S1122S?123S?11S?I2S?13S?14S115S?16Sh7Sh8Sjl9S?11S?12S?13S?14S?15Sh6Sh7S?11S?12S113Sh4Sh5Sh6Sh7Sh8R03R03ROOROOROOR03ROOR03R03ROOR03R04R03R03R03R03R03R03ROOR03R03R03R03R03R03R03R03R03R03R03R03R03R03R03R03ROOUSARRevision4EP10-2October1992
 
NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER11PageT=TableAmendmentg"=FigureNumberPageT=TableAmendmentPageT=TableAmendmentF=FicFureNumber11-i11ii11-iia11-iib11iil11-iv11-vll-vill.1-111.1-211~1-311.1-411.1-511.1-611~1711.1-811.1-911.1-1011.1-1111.1-1211.1-1311.1-1411.1-15T11.1-1T11.1-1T111-1T11.1-2T11.1-3T11.1-4T11.1-5T11.1-6T11F1-7T11.1-8F11F1-1F11.1-2F11.1-311.2-111.2-211'-311~23a11.2-3b11.2-411.2-4a11.2-4bSh1Sh2Sh3A24A24A23A23ROOAOOA08R04AOOAOOAOOAOOAOOAOOAOOAOOAOOAOOAOOAOOAOOAOOROOAOOAOOAOOA23A19'19R01AOOAOOAOOAOOAOOAOOA23ROOA23A23A23ROOA05A0511.2-511.2-5a11.2-5b11'-611.2-6a11.2-6b11~2711.2-811.2-911.2-1011.2-1111.2-1211.2-1311.2-1411.2-14a11.2-14b11.2-1511.2-1611.2-1711.2-18T11.2-1ShT11.2-1ShT11.2-1ShT11.2-1ShT11.2-1ShT11.2-2T11.2-3T11.2-4T11.2-5ShT11.2-5ShT11.2-6ShT11.2-6ShF11.2-1aF11.2-1bF11.2-1cF11.2-ldF11.2-1eF11.2-1fF11.2-1gF11.2-1hF11.2-1jF11.2-lkF11.2-1LF11.2-1m11.3-1A05ROO"A05ROOA05A05ROOROOROOROOA23ROOROOROOROOA23A23AOOR04ROOROOR02ROOR02A25ROOROOAOOA27A27A27A27R03ROOROOROOROOR02ROOR02R01ROOROOR03A0311.3-1a11.3-1b11~3211.3-2a11.3-2b11%3311.3-411.3-511.3-5a11.3-5b11.3-611~3711.3-7a11.3-7b11.3-811.3-9T11.3-1ShT11.3-1ShT113-2ShT11.3-2ShT11.3-3ShT113-3ShF11.3-1aF113-lbF11.3-1cF11.3-211.4-111.4-1a11.4-1b11.4-211.4-2a11.4-2b11.4-311.4-3a11.4-3b11.4-411.4-4a-11.4-4b11.4-511.4-6T11.4-1T11.4-2T11.4-3ShT114-3ShT11.4-3ShA03A03ROOA23A05A23A23R02R04A05A24A09R04A09A12A12A12AOOROOROOA12A12R04R04ROOR04A03A03A03ROOROOA08ROORolROOROORolA23RolROORolROOA26A26AOOUSARRevision4EP11-1October1992 VII NineMilePointUnit2FSARLISTOFEFFECTIVECHAPTER11PAGESPageT=TableAmendmentF=FicFureNumberPagePageT=TableAmendmentT=TableAmendmentF=FicFureNumberF=FicFureNumberT114-3Sh4T11.4-3Sh5T11.4-4Sh1T11.4-4Sh2T11.4-5T11.4-6T11.4-7F11.4-1aF11.4-1bF11.4-1cF11.4-1dF11.4-1eF11.4-1fF11.4-1gF11.4-1h11.5-111.5-211.5-2a11.5-2b11.5-311.5-3a11.5-3b11.5411.5-511.5-5a11.5-5b11.5-611.5-711.5-811.5-911.5-1011.5-10a11.5-10b11.5.-1111.5-11a11.5-11b11.5-1211.5-12a11.5-12b11.5-1311.5-14T11.5-1Sh1T11.5-1Sh2T11.5-1Sh2aT11.5-2Sh1A26A26R04R04A08A08A08R01R03ROOROOROOROOROOROOA23A23ROOA23A23A23A23A23A23A23A23A23R04A23A23A23A23A23R01A25A23A23A07A07A28A23ROOROOROOAOOT115-2Sh2T11.5-2Sh3T11.5-2Sh4F11.5-1F11.5-2F11.5-3aF11.5-3bF11.5-3cF11.5-3dF11.5-4F11.5-5F11.5-6F11.5-7F11.5-8Sh1F11.5-8Sh2App11A11A-illA-ii11A.1-111A.1-2TllA.l-lT11A.1-2T11A.1-3T11A.1-4T11A.1-5TllA.1-6TllA.1-7T11A.1-8T11A.1-9T11A.1-10T11A.1-11T11A.1-12T11A.1-13T11A.1-14T11A.1-15T11A.1-16T11A.1-17T11A.1-18T11A.1-1911A.2-111A.2-2T11A.2-1T11A.2-2AOOROOAOOROOROOR03ROOROOR03A23AOOR04ROOAOOAOOAOOAOOAOOAOOROOROOROOROOROOAOOAOOROOAOOAOOAOOAOOAOOA25A25A25AOOROOROOROOROOAOOROOROOUSARRevision4EP11-2October1992 F4 NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER12PageT=TableF=FBFureAmendmentNumberPageT=TableF=FicFureAmendmentNumberPageT=TableAmendmentF=FicFureNumber12-i12ii12-lii12-iv12-iva12-ivb12-v12-vi12-vii12-viia12-viib12-viii12-ix12-x12-xi12-xii12.1-112'-212F1-312'-412.1-512.1-612'-712.1-812'-912.1-9a12.1-9b12.1-1012.1-1112.1-1212.1-1312.1-13a12.1-13b12.1-1412.1-14a12'-14b12.1-1512.2-112.2-1a12.2-1b12.2-212'-312.2-412.2-5R03A24ROOR03A24A12R03R01A24A24A24R02R02ROOROOROOR03R03AOOAOOR03ROOR03R03R03A09A09AOOAOOAOOA07A07A07A07A07A07AOOA11AllA11AOOA11A11ROO12.2-612~2712.2-812.2-8a12.2-8b12.2-912.2-1012.2-1112.2-1212.2-1312.2-1412.2-1512.2-16T12.2-1T12.2-2T12.2-3T12.2-4Sh1T12.2-4Sh2T12.2-4Sh3T12.2-5Sh1T12.2-5Sh2T12.2-6Sh1T12.2-6Sh2T12.2-6Sh3T12.2-7Sh1T12.2-7Sh2T12.2-8Sh1T12.2-8Sh2T12.2-9T12.2-10Sh1T12.2-10Sh2T12.2-10Sh3T12.2-11T12.-2-12Sh1T12.2-12Sh2T12.2-12Sh3T12.2-13Sh1T12.2-13Sh2T12.2-13Sh3T12.2-14T12.2-15aT12.2-15bT12.2-1612~3112~32AOOR02A09A09A09R03A25R04A07A07A09A09A11ROOROOROOROOROOR01A09A09R01ROOAOOROOR01AOOAOOR01R01R01R01AOOR01R01=R01R01R01ROOA07ROOROOA11AOOAOO12~3312.3-412.3-512.3-612~3712~37a12.3-7b12.3-812.3-912.3-1012.3-1112.3-11a112.3-11b112.3-11a12.3-11b12.3-11c12.3-11d12.3-11e12.3-11f12.3-1212.3-1312.3-1412.3-1512.3-15a12.3-15b12.3-1612.3-1712.3-1812.3-1912.3-2012.3-21123-2212e32312.3-23a12'-23b12.3-2412.3-2512.3-2612.3-2712.3-2812.3-2912.3-3012.3-30a12.3-30b12~3-3112.3-31aAOOROOAOOAOOROOROOROOAOOR02R04R03R02A20A13A13ROOROOROOA13ROOR02AOOR02A05A05AOOAOOA01AOOR01AOOA10A10A10A10ROOA10AOOAOOA10ROOROOROOROOROOROOUSARRevision4EP12-1'ctober1992 e~
NineMilePointUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER12PageT=TableF=FicFureAmendmentNumberPageT=TableF=FicFureAmendmentNumberPageT=TableAmendmentF=FicFureNumber12.3-31b12~33212~333T12'-1Sh1T12.3-1Sh2T12'-1Sb3T12.3-1S114T12.3-2Sh1T12.3-2Sh2T12.3-2S113T12'-3Sb1T12'-3S112T12.3-4S?I1T123-4S?12T12'-4S?13T12.3-4S?14F12'-1F12.3-2F12.3-3F12.3-4F12.3-5F12.3-6F12.3-7F12.3-8F12.3-9F12.3-10F12.3-11F12.3-12F12.3-13F12.3-14F'12.3-15F12.3-16F.12.3-17F12.3-18F12.3-19F12.3-20F12.3-21F12.3-22F12'-23F12'-24F12.3-25F12.3-26F12.3-27F12.3-28F12.3-29F12.3-30ROOROOAOOROOROOA24R01ROOROOROOROOROOR01R01ROOROOR03R02R03R02R02R02R02R02R03R02R02R02R02R03R02R02R04R02R02R02R03R02R02R02R02R02R02R02R02R03F12.3-30aF12.3-31F12.3-32F12.3-33F12.3-34F12.3-35F12.3-36F12.3-37F12.3-38F12.3-39F12'-40F12.3-41F12.3-42F'2.3-43F123-44F12.3-45F12.3-46F12.3-47F12.3-48F12.3-49F12'-50F12.3-51F12.3-52F12.3-53F12.3-54F12.3-55F12.3-56F12.3-57F12.3-58F12.3-59F12.3-60F12.3-61F12.3-62F12.3-63F12.3-63aF12.3-64F12.3-65F12.3-66F12.3-67F12.3-68F12.3-69S?11F12.3-69S?12F12.3-69Sh3F12.3-69S?1412.4-1R02R02R02R02R03R02R03R02R02R02R02R02R03R02R02R02R02R03R02R02R04R02R02R02R03R02R02R02R02R02R02R02R02R03R02R02R02R02ROOAOOROOROOROOR03ROO12.4-1a12.4-1b12.4-1c12.4-1d12.4-212.4-2a12.4-2b12.4-3T12'-1T12.4-2T124-3T12.4-4T12.4-5T12.4-6T12'-7S?11T12.4-7S?12T12.4-8T124-9T12.4-10T12.4-11T12.4-12T12.4-1312.5-112.5-212.5-312.5-412.5-512.5-612.5-712.5-7a12.5-7b12.5-812.5-912.5-1012.5-1112.5-1212.5-1312.5-1412.5-14a12.5-14b12.5-1512.5-1612.5-1712.5-1812.5-19A15ROOA24A15A12A12A12ROOROOROOROOROOROOA20A20A20A20A20ROOA20A15A15R03R03A26R01ROOAOOA01R04A01AOOR04A01AOOAOOR03R03A05A05R04R03R03ROOR03USARRevision4EP12-2October1992 P~
NineMilePaintUnit2FSARLISTOFEFFECTIVEPAGESCHAPTER12PagePagePageT=Table.AmendmentT=TableAmendment,T=TableAmendmentF=FicFureNumberF~FicFureNumberF=FicFureNumber12.5-20T12.5-1T12.5-2T12.5-3T12.5-4A26R01ROOA05A01USARRevision4EP12-3October1992
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EDFKTYININEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAUMOHAWKVOL.1
 
NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4AppendixesCHAPTER66.16.26.36.46.56.6AppendixesCHAPTER77.17'7.37.47.57'7~7AppendixesCHAPTER88.18.28.3Appendix8ACHAPTER9TitleReactorVesselComponentandSubsystemDesign5Ag5BENGINEEREDSAFETYFEATURESEngineeredSafetyFeatureMaterialsContainmentSystems'mergencyCoreCoolingSystemsHabitabilitySystemsFissionProductRemovalandControlSystemsInserviceInspectionofSafetyClass2andClass3Componentsthrough6CINSTRUMENTATIONANDCONTROLSYSTEMSIntroductionReactorProtection(Trip)System(RPS)InstrumentationandControlsEngineeredSafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-RelatedDisplayInstrumentationAllOtherInstrumentationSystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ag7BELECTRICPOWERIntroductionOffsitePowerSystemOnsitePowerSystemAUXILIARYSYSTEMSVolume1313131313141515151515151515161616161616161616,1717I179.19.29.39.49.5AppendixesFuelStorageandHandlingWaterSystemsProcessAuxiliariesAirConditioning,Heating,Cooling,andVentilationSystemsOtherAuxiliarySystems9Ag9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSIONSYSTEM2310.110.210.310.4SummaryDescriptionTurbineGeneratorMainSteamSupplySystemOtherFeaturesofSteamandPowerConversionSystem232324CHAPTER11RADIOACTIVEWASTEMANAGEMENT2411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagementSystemsGaseousWasteManagementSystemsSolidWasteManagementSystemProcessandEffluentRadiologicalMonitoringandSamplingSystems242425252525CHAPTER12RADIATIONPROTECTION2512.112.212.3EnsuringThatOccupationalRadiationExposuresAreAsLowAsReasonablyAchievable(ALARA)RadiationSourcesRadiationProtectionDesignFeaturesDoseAssessmentRadiationProtectionProgram2525252626CHAPTER13CONDUCTOFOPERATIONS2613.113.213.313.413.513.6Appendix13AOrganizationalStructureofApplicantTrainingSiteEmergencyPlanOperationReviewandAuditPlantProceduresIndustrialSecurity26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformationToBeIncludedinPreliminarySafetyAnalysisReport(PSAR)26USARRevisionivOctober1991 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd)SectionTitleVolume14.2CHAPTER15SpecificInformationToBeIncludedinFinalSafetyAnalysisReport(FSAR)ACCIDENTANALYSIS26r272715.015.1GeneralDecreaseinReactorCoolantTemperature15.2IncreaseinReactorPressure15.3DecreaseinReactorCoolantSystemFlowRate15.4ReactivityandPowerDistributionAnomalies15.5IncreaseinReactorCoolantInventory15.6DecreaseinReactorCoolantInventory15.7RadioactiveReleaseFromSubsystemsorComponents15.8AnticipatedTransientswithoutScram(ATWS)Appendices15Athrough15H27272727272727272728CHAPTER16CHAPTER1717.017.117.2CHAPTER18TECHNICALSPECIFICATIONSQUALITYASSURANCEIntroductionQualityAssuranceProgramDuringOperationQualityAssuranceProgramDuringtheOperationsPhaseHUMANFACTORSENGINEERING/SAFETYP2QMMETERDISPLAYSYSTEM28282828282818.118.2APPENDIXADetailedControlRoomDesignReviewSafetyParameterDisplaySystemRELOADANALYSIS282828USARRevision3October1991
 
NineMilePointUnit2FSARCHAPTER1INTRODUCTIONANDGENERALDESCRIPTIONOFPLANTTABLEOFCONTENTSSectionTitleINTRODUCTIONPacae1.1-11.21.2.11.2.11.2.11.2.11.F11.2.11.2.11.2.1.1.2.2.1.3.3.1.3.2.3.31.2.1.3.81.2.21.2:2.11.2.2.21.2.2.31.2.31.2.41.2.4.11.2.4.21.2'.31.2.4.41.2.4.51.2.4.61.2.51.2.5.11.2.5.21~2'.31.2.1~3.41.2.1.3.51.2.1.3.61.'2.1.3.7GENERALPLANTDESCRIPTIONPrincipalDesignCriteriaGeneralCriteriaPowerGenerationDesignCriteriaSafetyDesignCriteriaSystem-by-SystemApproachNuclearSystemCriteriaPowerConversionSystemsCriteriaElectricalPowerSystemsDesignCriteriaRadwasteSystemDesignCriteriaAuxiliarySystemsDesignCriteriaShieldingandAccessControlDesignCriteriaNuclearSafetySystemsandEngineeredSafeguardsDesignCriteriaProcessControlSystemDesignCriteriaSiteDescriptionSiteCharacteristics:SiteLocationandSizeAccesstotheSiteDescriptionoftheSiteandEnvironsStructuresandEquipmentNuclearSteamSupplySystemReactorCoreandControlRodsReactorVesselandInternalsReactorRecirculationSystemResidualHeatRemovalSystemReactorWaterCleanupSystemNuclearLeakDetectionSystemElectrical,Instrumentation,andContr'olSystemsElectricalPowerSystemNuclearSystemProcessControlandInstrumentationPowerConversionSystemsProcessControlandInstrumentation1~2-11~21l.2-11~231.2-41~2-71.2-71.2-81.2-91.2-91.2-91.2-91.2-101.2-101.2-121.2-121.2-121.2-131.2-131.2-151.2-151.2-161.2-171.2-171.2-171.2-181.2-181.2-181.2-201.2-21Amendment24February1986 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont)Section1.21.21.21.21.21.2~6.7.7.1.7.2.7.3.7.41.21.21~21~21.21.21.2.8.8.1.8.2.8.3.8.4.8.5~8.61.21.21.21~2.8.7~8.8.8.9.91.21~21.21.21.21.21~21.21.21.2.9.1.9.2.9.3.9.4.9.5.9.6.9.7.9.8.9.9.9.101.21.21.2.9.11.9.12.9.131.2.9.141.2.9'51.2.9.181.2.9.161.2.9.17TitleRadioactiveWasteSystemFuelHandlingandStorageSystemsNewFuelStorageSpentFuelStorageFuelHandlingSystemSpentFuelPoolCoolingandCleanupSystemPowerConversionSystemTurbineGeneratorMainSteamSystemMainCondenserMainCondenserAirRemovalSystemTurbineGlandSealingSystemSteamBypassSystemandPressureControlSystemCirculatingWaterSystemCondensateandFeedwaterSystemsCondensateDemineralizerSystemNuclearSafetySystemsandEngineered'SafetyFeaturesReactorProtectionSystemNeutronMonitoringSystemControlRodDriveSystemControlRodDriveHousingSupportsControlRodVelocityLimiterNuclearSystemPressureReliefSystemReactorCoreIsolationCoolingSystemEmergencyCoreCoolingSystemsContainmentSystemsContainmentandReactorVesselIsolationControl.SystemMainSteamIsolationValvesMainSteamFlowRestrictorsMainSteamRadiationMonitoringSystemResidualHeatRemovalSystemVentilationExhaustRadiationMonitoringSystemStandbyGasTreatmentSystemSafety-RelatedElectricalPowerSystemsStandbyLiquidControlSystemPa<ac1.2-221.2-231.2-231.2-231.2-241.2-241.2-241.2-241.2-,251.2-251.2-251.2-251.2-261.2-261.2-26l.2-261.2-271~2271.2-271.2-271.2-271.2-281.2-281.2-281.2-281.2-291'-301.2-301.2-31l.2-311.2-311.2-321.2-321.2-321.2-33Amendment241-iiFebruary1986 NineMilePointUnit2FSARCHAPTER1TABIEOFCONTENTS(Cont)Section1.2.9.191.2.9.201.2.9.211.2.101.2.10.11.2.10.21.2.10.31.2.10.41.2.10.51.2.10'1.2.10.71.2.10.81.2.10.91.2.10.101.2.10.111.2.10.121.2.10.131.2.10.141.2.10.151.2.10'61~2~111.31.3.11.3.21.3'1.41.4.11.4.21.4.31.4.4TitleSafeShutdownfromOutsidetheControlRoomMainControlRoomHeating,VentilatingandAirConditioningSystemRedundantReactivityControlSystemCoolingWaterandAuxiliarySystemsReactorBuildingClosedLoopCoolingWaterSystemTurbineBuildingClosedLoopCoolingWaterSystemServiceWaterSystemUltimateHeatSinkPlantChilledWaterSystemHeating,Ventilating,andAirConditioningSystemsProcessSamplingCondensateMakeupandDrawoffSystemWaterTreatmentandMakeupWater'SystemsDomesticWaterandSanitaryDrainsandDisposalSystemsCompressedAirSystemsAuxiliarySteamSystemStandbyDieselGeneratorFuelOilStorage,andTransferSystemFireProtectionSystemCommunicationSystemsLightingSystemsReferencesCOMPARISONTABLESComparisonwithSimilarFacilityDesignsComparisonofFinalandPreliminaryInformationReferenceIDENTIFICATIONOFAGENTSANDCONTRACTORSApplicantArchitect-EngineerNuclearSteamSupplySystemTurbineGeneratorSupplierPa<ac1.2-331.2-331.2-331.2-341.2-341.2-341.2-341.2-341.2-341.2-351.2-351.2-351.2-351.2-361.2-361.2-371~2371~2371~2-371'-381.2-41'~311.3-11~31l.3-1I1.4-11.4-11.4-21.4-31.4-4Amendment241iiiFebruary1986 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont)Section1.4.51.4.6TitleTechnicalConsultantsReferencePacae1.4-41.4-824241.51.5.11.5.1.11.5.1.21.5.1.31.5.1.41.5.1.51.5.21.5.31.61.71.7.11.7.21.81.91.101.11l.121.12,.11.12.21~13REQUIREMENTSFORFURTHERTECHNICALINFORMATIONCurrentBWRDevelopmentProgramsInstrumentationforVibrationDetectionCoreSprayDistributionCoreSprayandCoreFloodingHeatTransferEffectivenessVerificationofPressureSuppressionDesignBoilingTransitionTestingGeotechnicalInvestigationsReferencesMATERIALINCORPORATEDBYREFERENCEDRAWINGSANDOTHERDETAILEDINFORMATIONElectrical,Instrumentation,,andControlDrawingsPipingandInstrumentationDrawingsCONFORMANCETONRCREGULATORYGUIDESSTANDARDREVIEWPLANCONFORMANCETOACCEPTANCECRITERIAUNIT2RESPONSETOREGULATORYISSUESRESULTINGFROMTMIABBREVIATIONSANDACRONYMSGENERICLICENSINGISSUESIntroductionIicensingIssuesUNIT2POSITIONONUNRESOLVEDSAFETYISSUES1.5-11.5-11.5-11.5-11.5-11.5-21.5-31.5-31.5-51.6-11.7-11.7-11.7-11.8-11.9-11.10-11.11-11;12-11.12-11.12-11.13-1Amendment241-3.VFebruary1986 NineMilePointUnit2FSARCHAPTER,1INTRODUCTIONANDGENERALDESCRIPTIONOFTHEPLANT
 
==1.1INTRODUCTION==
ThisFinalSafetyAnalysisReport(FSAR)issubmittedbytheNiagaraMohawkPowerCorporation(Applicant)anditsco-owners(CentralHudsonGasandElectricCorporation,LongIslandLightingCompany,NewYorkStateElectricandGasCorporation,andRochesterGasandElectricCorporation)insupportoftheapplicationforaClass103operatinglicensefor0henuclearpowerstationdesignatedNineMilePointNuclearStation-Unit2(Unit2).Unit2islocatedona364-ha(900-acre)siteownedbyNiagaraMohawkPowerCorporation(NMPC),andissituatedonthesoutheastshoreofLakeOntario,OswegoCounty,NY,approximately10km(6.2mi)northeastofthecityofOswego.Unit,2andsupportfacilitiesoccupyabout18.2ha(45acres),andsharethesitewiththeexistingUnit1(DocketNo.50-220)whichhasbeenincommercialoperationsince1969.,TheNineMilePointsiteisadjacenttotheJamesA.FitzPatrickNuclearPowerPlantownedbytheNYPA;Unit2islocated274m(900ft)eastofNine'MilePointUnit1andabout716m(2,350ft)westoftheJamesA.FitzPatrickPlant.Unit2employsanuclearsteamsupplysystem(NSSS)consistingofasinglecycle,forcedcirculatingboilingwaterreactor(BWR).Theplantratedcorethermalpowerlevel(Figure1.1-1-)is3,323MWtcorrespondingtoanetelectricaloutputof1,080MWe,anddesignthermalpowerof3,463MWtcorrespondingtoagrosselectricaloutputof1,202MWe.Thethermalpowerusedfortheplanttransientandloss-of-coolant'accident(LOCA)analysesis3,463MWt.Allsafetysystemshavebeendesignedforathermalpower.of3,489MWt.TheNSSSsupplierisGeneralElectricCompany-NuclearEnergyOperations(GE-NEO).ThebalanceoftheplantisdesignedandconstructedbyStoneEcWebsterEngineeringCorporation(SWEC).OtherplantsdesignedbySWECthataresimilarinconceptarecurrentlyunderreviewbytheNuclearRegulatoryCommission.ThesearetheShorehamNuclearPowerStation,Brookhaven,LongIsland,NY,andtheRiverBendStation,St.Francisville,LA.ThecontainmentdesignemploystheBWRMarkIIconceptofover-underpressuresuppressionwithmultiple,downcomersAmendment191.1-1May1985 NineMilePointUnit2FSARconnectingthereactordrywelltothewater-filledpressuresuppressionchamber.Theprimarycontainment,.-is.asteel-lined,reinforcedconcreteenclosurehousingthereactorandthesuppressionpool.Thereactorbuildingcompletelyenclosesthe.primarycontainment.Thestructureprovidessecondarycontainmentwhentheprimarycontainmentisclosedandinservice,andprovidesprimarycontainmentwhentheprimarycontainmentisopen,asduringrefueling.Thereactorbuildinghousestherefuelingandreactorservicingequipment,newandspentfuelstoragefacilitie's,'and--otherreactorauxiliaryandserviceequipment.Theprimarypurposeofthereactorbuildingistominimizeground.-levelreleaseofairborneradioactivematerial.Theouterwallofthereactorbuildingisreinforcedconcreteuptothecraneraillevelabovetherefuelingfloor.Abovethecrane'aillevel,thesuperstructureisasteelframeusingmetalwallpanelswithsealedjoints.Accesstothebuildingisthroughairlocks.IIThepowergenerationcomplexincludesseveralcontiguousbuildings:thereactorbuildingwithtwoauxiliarybays,thecontrolbuilding,theturbinebuilding,andtheradwastebuilding.Otherbuildings,suchasthesecurityfacility,are'lsolocatedinthegeneralplantarea.Ascreenwellforthecirculatingandservicewatersystemsislocatedapproximately107m(350ft)northwestofthecenterlineofthereactorbuilding.CondensercoolingforUnit2isprovidedfromacounterflow,natural-draft,hyperbolic,concretecooling,towerlocatedapproximately330m(1,000ft)southofthecenterlineofthereactorbuilding.Theultimateheat.sinkforemergencycorecoolingisLakeOntario.Belowgradeandnorthofthescreenwellbuilding,therearetwoconcretetunnels'hatconveythe,servicewaterintake,servicewaterdischarge,andcoolingtowerblowdown.Asafety-relatedintakepipeisenclosedin'eachtunnel.Theintakepipesextendfromtheintakeshaftapproximately396m(1,300ft)northwardunderLakeOntariotothesubmergedintakestructures.Onetunnelalsocontainsthedischargepipewhichextendsapproximately550m(1,800ft)tothedischargediffuser.RadionuclidesareemittedtotheatmospherefromtwolocationsatUnit2.Thesearethestackandthecombinedventfortheradwaste-andreactorbuildings.Fiquidradwasteisstoredfordecayorconcentratedtoasolidwasteforcontrolleddisposalatregulatedstoragesites.1~12 NineMilePointUnit2FSARTheshieldingdesign'andplantlayoutarebasedonextensiveexperienceofNMPCandSWECincontrollingradiologicalexposurestoaslowasreasonablyachievablelevels.Estimatedradiologicaldosesfornormaloperationsandpostulatedaccidentsareallfractionalpartsofthedoseslistedinfederalradiologicalguidelinesforsitingandoperationofnuclearpowerplants.EnvironmentalimpactsaredescribedintheseparateEnvironmentalReportOperatingLicenseStagebeingsubmittedforUnit2.ThisFSARiswritteninaccordancewithRegulatoryGuide1.70,StandardFormatandContentofSafetyAnalysisReportsforNuclearPowerPlants.ThecontentofthisFSARaddressesapplicableregulatoryguidesissueduptoJuly1982.TheUnit2PreliminarySafetyAnalysisReport(PSAR)wassubmittedonJune15,1972(DocketNo.50-410).TheNRCSafetyEvaluationReportwasissuedonJune15,1973,andtheconstructionpermit(CPPR-112)wasissuedonJune24,1974.EnvironmentalimpactsrelatedtotheplantarediscussedintheEnvironmentalReport-ConstructionPermitStagesubmittedonJune15,1972.TheNRCFinalEnvironmentalStatementwasissuedinJune1973.TheapproximatescheduleforUnit2fuelloadingandcommercialoperationisasfollows:FuelloadingCommercialoperationMarch1986October1986Amendment241.1-3February1986 I
NineNilePointUnit2FSAR1.2GENERALPLANTDESCRIPTION1.F1PrincipalDesignCriteriaTheprincipalarchitecturalandengineeringcriteriaforthedesign,construction,andoperationofUnit2aresummarizedinthisSection.Therearetwowaysofconsideringprincipaldesigncriteria:onaclassification-by-classificationbasis,oronasystem-by-system(systemgroup)basis.Safetyanalysesgenerallyutilizetheinformationformattedintheclassification-by-classificationapproachbut/systemdescriptionsaremoreeasilyunderstoodthroughthesystem-by-systemmethod.Thissectionusesbothmethodsforsummarizingtheprincipaldesigncriteria.1.2.1.1GeneralCriteriaSomeofthecriteriaaregenerallyapplicabletomorethanoneclassificationormorethanonesystemgroup.Thesegeneralcriteriaareasfollows:Unit2isdesigned,fabricated,anderectedtoproduceelectricpowerinasafeand.reliablemanner.Unitdesigngenerallyconformswithapplicablecodesandregulations.Exceptionsareevaluatedandjustified.TheGeneralDesignCriteriaof10CFR50AppendixAhavebeensatisfiedintheUnit2design.2.3.Unit2isdesigned,fabricated,anderectedtooperateinsuchawaythatthereleaseofradioactivematerialstotheenvironmentislimitedtolessthanthelimitandguidelinevaluesofapplicablefederalregulationspertainingtothereleaseofradioactivematerialsfornormaloperationsandabnormalevents.Unit2isdesignedtosupportaGEboilingwaterreactor(BWR)andnuclearsteamsupplysystem(NSSS)toproducesteamfordirectuseinaturbinegeneratorunit.Thisdesignincorporates,featurestypicalofmanyotherBWRplants.4.Certainportionsoftheplantaredesignedtowithstandextremenaturalphenomenasuchasearthquakes,flooding,ortornadoes,andunnaturalphenomenasuchasfige,floodingfromin-plantleakage,internallyorexternallygeneratedmissiles,andothers.1.2-1 NineMilePointUnit2FSARThereactorcoreandreactivitycontrolsystemsaredesignedsothatcontrolrodactioniscapableofbringingthecoretosubcriticalconditionandmaintainingit,evenwiththerodofhighestreactivityworthfullywithdrawnandunavailableforinsertion.Designmarginsforthenuclearsafetysystemsandengineeredsafeguardsareconservative.Nuclearabnormaldamage.environsmaterialAppendixsafetysystemsaredesignedtorespondtooperationtransientstoprecludefuel'nyfissionproductsreleasedtothevianormaldischargepathsforradioactivewillnotexceedthelimitsof10CFR50I.Nuclearsafetysystemsandengineeredsafeguardsaredesignedtoassurethatnodamagetothereactorcoolantpressureboundary(RCPB)resultsfrominternalpressurescausedbyabnormaloperationaltransientsoraccidents.Wherepositive,preciseactionisimmediatelyrequiredinresponsetoaccidents,suchactionisautomaticandrequiresnodecisionormanipulationofcontrolsbystationoperationspersonnel.Essentialsafetyactionsarecarriedoutbysafety-relatedequipmentofsufficientredundancyandindependencesothatnosinglefailureofactivecomponentscanpreventrequiredactions.Anysinglefailurewithinthesafety-relatedprotectionsystemshalln'otpreventproperprotectiveactionatthesystemlevelwhenrequired.Provisionshavebeenmadeforcontrolofthecomponentsofnuclearsafetysystemsandengineeredsafeguardsfromthecontrolroom.CNuclearsafetysystemsandengineeredsafeguardsaredesignedtopermitdemonstrationoftheirfunctionalperformancerequirements.Unit2featuresessentialtothemitigationofaccidentconsequencesaredesigned,fabricated,anderectedtoqualitystandardsthatreflecttheimportanceofthesafetyfunctiontobeperformed.1.2-2 NineMilePointUnit2FSARI1.2'~2PowerGenerationDesignCriteriaPrincipalpowergenerationdesigncriteriaareasfollows:1.Fuelcladding'designedtoretainintegrityasaradioactivematerialbarrierthroughoutthefulloperationalrangeoftheplantandanyabnormaloperationtransient.Thefuelcladdingisdesignedtoaccommodate,withoutlossofintegrity,pressuresgeneratedbyfissiongasesreleasedfromfuelmaterialthroughoutthedesignlifeofthefuel.2.Heatremovalsystemsareprovidedinsufficientcapacityandredundancytoremoveheatgeneratedinthereactorcoreforthefullrangeofnormaloperatingconditionsfromplantshutdowntodesignpower,andalsoforanyabnormaloperational"transient.Thecapacity'fsuchsystemsisadequatetopreventfuelcladdingdamage.3.Backupheatremovalsystemsareprovidedtoremovedecayheatgeneratedinthecoreundercircumstanceswherenormaloperationalheatremovalsystemshavebecomeinoperative.Thecapacityofsuchsystemsisadequatetopreventfuelcladdingdamage.4Controlequipmentisprovidedtoallowthereactortorespondautomaticallytomajororminorloadchangesandotherabnormaloperationaltransients,includingbringingthereactortoahotshutdowncondition.5.Reactorpowerlevelismanuallycontrolled.6.ControloftheNSSS,includingthereactor,is'ossiblefromasinglelocation.NSSSandreactorcontrols,includingalarms,arearrangedtoallowtheoperatortorapidlyassesstheconditionofthenuclearsystemandlocateprocesssystemmalfunctions.8.Fuelhandlingandstoragefacilitiesaredesignedtomaintainadequateshielding,cooling,andwaterqualityforspentfuelandtopreventinadvertentcriticality.Amendment211.2-3September1985 NineMilePointUnit2FSARInterlocksorotherautomaticequipmentareprovidedasbackuptoproceduralcontrolstoavoidconditionsrequiringthefunctioningofnuclearsafetysystemsorengineeredsafeguards.SafetyDesignCriteriaThe.unitisdesigned,fabricated,anderectedtooperatesothatthereleaseofradioactivematerialstotheenvironmentissignificantlylessthantherequirementsof10CFR20or10CFR100.ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrityasaradioactivebarrierfollowingabnormaloperationaltransientsoranaccidentevent.Thereactorcoreisdesignedsoitsnuclearcharacteristicsdo,notcontributetoadivergentpowertransient.TheNSSSandsupportingsystemsaredesignedsothatthereisnotendencyfordivergentoscillationofanyoperatingcharacteristic,consideringtheinteractionofthenuclearsystemwithotherappropriateunitsystems'aseous,liquid,andsolidwastedisposalfaci'litiesaredesignedsothedischargeofradioactiveeffluentsandoffsiteshipmentofradioactivematerialscanbemadeinaccordancewithapplicableregulations'esignoftheradwastesystemprovidesmeansbywhichUnit2operatorscanbealertedwhenlimitsonthereleaseofradioactivematerialareapproached.Sufficientindicationsareprovidedtodeterminethatthereactorisoperatingwithinthelimitsofapplicableregulationsinanymodeofunitoperations.Adequateradiationshieldingisprovidedandaccesscontrolpatternsareestablishedtoallowaproperlytrainedoperatingstafftocontrolradiationdosesto-alevelthatisaslowasreasonablyachievableduringnormaloperation.1.2-4 NineMilePointUnit2FSAREssentialsafetyactionsaredesignedtobecarriedoutbyequipmentofsufficientredundanceandindependencethatnosinglefailurecanpreventtherequiredactions.Anysinglefailurewithintheprotectionsystemshallnotpreventproperactionatthesystemlevelwhenrequired.Provisionsaremadeforcontrolofthecomponentsofnuclearsafetysystemsfromthecontrolroom.Nuclearsafetysystemsaredesignedtodemonstratefunctionalperformancerequirements.1Thedesignofnuclearsafetysystemsincludesdesignallowancesforenvironmentaldisturbancesatthesitesuchasearthquakes,floods,highwinds,stormsandotherdisturbancessuchasfireandfloodingfromleakageoffluidsystems,internallyandexternallygeneratedmissiles,andothers.Standbyelectricalpowersourcesareofsufficientcapacitytopowerall-necessarynuclearsafetysystemsrequiringelectricalpower.Standbyacanddcpowersourcesareprovidedtoremovedecayheatwhentheoffsitepowersupplyisnotavailable.EngineeredsafeguardsaredesignedtoassurethatnodamagetotheRCPBresultsfrominternalpressurescausedbyanaccidentorabnormaltransient.Aprimarycontainmentisprovidedthatcompletelyenclosesthereactorvessel.Theprimarycontainmentusesthepressuresuppressionconcept.Theprimarycontainmentisdesignedtoretainintegrityasaradioactivematerialbarrierduringandfollowingaccidentsthatreleaseradioactivematerialintotheprimarycontainmentvolume.Itispossibletotestprimary.containmentintegrityandleaktightnessatperiodicintervals.Areactorbuildingisprovidedthatcompletelyenclosesboththeprimarycontainmentandthefuelstorageareas.Thesecondarycontainmentincludesamethodforcontrollingreleaseofradioactivematerialsfromthebarrierandincludesacapabilityforfilteringradioactivematerialswithinthebarrier.1.2-5 NineMilePointUnit2FSAR18.Thereactorbuildingisdesignedtoactasaradioactivematerialbarrier,ifrequired,whentheprimarycontainmentisopenforexpectedoperationalpurposes.19.Theprimarycontainmentandreactorbuilding,inconjunctionwithotherengineeredsafeguards,limitsradiologicaleffectsofaccidentsresultinginthereleaseofradioactivematerialtotheprimarycontainmentvolumetosignificantlylessthantherequirementsof10CFR100.20.Provisionsaremadeforremovingenergyfromwithintheprimarycontainmenttomaintaintheintegrityoftheprimarycontainmentsystemfollowingaccidentsthatreleaseenergytotheprimarycontainment.21.Pipingthatpenetratestheprimarycontainmentstructureandservesasapathfortheuncontrolledreleaseofradioactivematerialtotheenvironsisautomaticallyisolatedwheneversuchpotentialforradioactivematerialreleaseexists.Suchisolationiseffectedintimetolimitradiologicaleffectstosignificantlylessthantherequirementsof10CFR100.22.Theemergencycorecoolingsystem(ECCS)isprovidedtolimitfuelcladdingtemperatureto2,200Fasaresultofaloss-of-coolantaccident(IOCA).23.TheECCSprovidesforcontinuityofcorecoolingoverthecompleterangeofpostulatedbreaksizesintheRCPB.24.TheECCSisdiverse,reliable,andredundant.25.-OperationoftheECCSisinitiatedautomaticallywhenrequired,'regardlessoftheavailabilityofoffsitepower.26.Themaincontrolroomisshieldedagainstradiationtopermitcontinuedoccupancyunderaccidentconditions.27.Intheeventthatthemaincontrolroombecomesuninhabitable,itispossibletobringthereactorfrompowerrangeoperationtoacoldshutdown1.2-6 NineMilePointUnit2FSARconditionbymanipulatinglocalcontrolsandequipmentavailableoutsidethemaincontrolroom.28.Backupreactorshutdowncapabilityisprovidedindependentofnormalreactivitycontrolprovisions.Thisbackupsystemshutsdownthereactorfromanynormaloperatingconditionandmaintainstheshutdowncondition.I1.2.1.3System-by-SystemApproachTheprincipalarchitecturalandengineeringcriteriafordesignaresummarizedbelowonasystem-by-systemorsystem-groupbasis.Thesystem-by-systempresentationfacilitatesunderstandingoftheactualdesignofanyonesystem.Onlythemostrestrictiveofanyrelatedcriteriaarestatedforasystem.Wherethemostrestrictivecriterionisclassifiedasapowergenerationconsideration,lessrestrictivesafetycriteriamaynotbestatedinthesystem-by-systempresentation.However,theactualdesignofasystemmustreflectallcriteriathatpertaintoit.1.2.1.3.1NuclearSystemCriteriaPrincipaldesigncriteriaforthereactor,ECCS,RCPB,andreactivitycontrolsystemsareasfollows:ThenuclearsystemisdesignedtosupportaGEBWRratedat3,323MWt.2.Fuelcladdingisdesignedtoretainintegrityasaradioactivematerialbarrierthroughoutthedesignpowerrange.Fuelcladdingisdesignedtoaccommodate,without.lossofintegrity,thepressuresgeneratedbythefissiongasesreleasedfromfuelmaterialthroughoutthedesignlifeofthefuel.3.Fuelcladding,inconjunctionwithotherunitsystems,isdesignedtoretainintegritythroughoutanyabnormaloperationaltransient.ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrityasaradioactivematerialbarrierfollowingabnormaloperationaltransientsandaccidents.5.HeatremovalsystemsincludingtheECCSandmakeupwatersuppliesareprovidedinsufficientcapacity,redundancy,andoperationaladequacytoremoveheat1%27 NineMilePointUnit2FSARgeneratedinthereactorcoreforthefullrangeofnormaloperationalconditionsfromunitshutdowntodesignpowerandforanyabnormaloperationaltransientoraccident.Thecapacityofsuchsystemsisadequatetopreventfuelcladdingdamage.6.Thereactorcoreandreactivitycontrolsystemisdesignedto-ensurethatcontrolrodactioniscapableofbringingthecoresubcriticalandmaintainingitthus,evenwiththerodofhighestreactivityworthfullywithdrawnandunavailableforinsertion.Analternatereactivitycontrolsystemisprovidedshouldthecontrolrodsordrivesystembecomeinoperable.Thealternatesystemiscapableofshuttingdownthereactorandmaintainingitsubcritical.7.Thereactorcoreis'designedsothat,itsnuclearcharacteristicsdonotcontributeto'divergentpowertransient.8.Thenuclearsystemisdesignedsothereisnotendencyfordivergentoscillationofanyoperatingcharacteristic,consideringtheinteractionofthenuclearsystemwith'otherappropriateunitsystems.1.2.1.3.2PowerConversionSystems.CriteriaComponentsofthepowerconversionsystemsaredesignedtoperformthesebasicobjectives:Reliablyproduceelectricalpowerfromthesteamsuppliedbythereactor,condensethesteamintowater,andreturnthewatertothereactorasheatedfeedwater,withamajorportionofitsgaseousandparticulateimpuritiesremoved.2.Assurethatanyfissionproductsorradioactivityassociatedwiththesteamandcondensateduringnormaloperationoraccidentconditionsaresafelycontainedwithinthesystemorarereleasedundercontrolledconditionsinaccordancewithwastedisposalregulations.1.2-8 NineMilePointUnit2FSAR1.2.1.3.3ElectricalPowerSystemsDesignCriteriaSufficientpreferredandstandbyacanddcpowersourcesareprovidedtoattainpromptshutdownandcontinuedmaintenanceoftheunitinasafeconditionunderallcrediblecircumstances.Powersourcesareadequatetoaccomplishallrequiredengineeredsafeguardfunctionsunderpostulateddesignbasisaccidentconditions.1.2.1.3.4RadwasteSystemDesignCriteriaRadwastesystemsaredesignedtolimitreleaseofradioactivematerialsfromtheunitduringnormaloperationtosignificantlylessthantherequirementsof10CFR20,andwithintheguidelinesofAppendixIto10CFRSO.Gaseous,liquid,,andsolidwastedisposalsystemsaredesignedsothatoffsiteshipmentswillbeinaccordancewithapplicableregulations,including10CFR20,10CFR71,and49CFR171through179,asappropriate.3.Thedesignprovidesmeansbywhichunitoperationspersonnelcanbealertedwheneveroperationallimitsonthereleaseofradioactivematerialareapproached.1.2.1.3.5AuxiliarySystemsDesignCriteriaAuxiliarysystemsareprovidedtosupporttheNSSSandpowergenerationsystemtoprovideformaintenanceoftheplantenvironment,in-plantradiationandairbornecontaminationcontrol,compressedairsupplies,sealingsteam,etc.2.Essentialauxiliarysystemsaredesignedtofunctionduringaccidentconditions.1.2.1.3.6ShieldingandAccessControlDesignCriteriaRadiationshieldingisprovidedandaccesscontrolpatternsareestablishedtoallowaproperlytrainedoperatingstafftocontrolradiationdoseswithinthelimitsofpublishedregulationsduringnormaloperation.Shieldingdesign,equipmentlayout,andzoninghavebeenperformedtoensureradiationdosesaremaintainedaslowasreasonablyachievable.1.2-9 NineNilePointUnit2FSAR2.Themaincontrolroomisshieldedagainst,radiationsothatinconjunctionwiththecontrolroomairconditioningsystemoccupancyisallowedunderaccidentconditions.1.2.1.3.7NuclearSafetySystemsandEngineeredSafeguardsDesignCriteriaPrincipaldesigncriteriafornuclearsafetysystemsandengineeredsafeguardsareasfollows:1.Thesecriteriacorrespondto10CFR50GeneralDesignCriteria1through64asdescribedinSection3.1.2~2.Standbyacanddcpowersourcesare,designedtohavesufficientcapacitytopowerallnecessarynuclearsafetysystemsandengineeredsafeguardsrequiringelectricalpower.3.Standbyacpowersources-areprovidedtoallowreactorshutdownandremovalofdecayheatwhenoffsitepowerisnotavailable.lntheeventthatthemaincontrolroomisuninhabitable,itispossibletobringthereactorfrompowerrangeoperationtoacoldshutdownconditionbyuseoftheshutdownroomormanipulatinglocalcontrolsandequipmentthatareavailableoutsidethecontrolroom.5.Backupreactorshutdowncapabilityisprovidedindependentlyofnormalreactivitycontrolprovisions.Thisbackupsystemhasthecapabilitytoshutdownthereactorfromanynormalorupsetoperatingconditionandsubsequentlytomaintaintheshutdowncondition.1.2.1.3.8ProcessControlSyst:emDesignCriteriaPrincipaldesigncriteriaforprocesscontrolsystemsarelistedasfollows:NSSSProcessControlDesinCriteria1.Controlequipmentisprovidedtoallowthereactortorespondautomaticallytoloadchangeswithindesignlimits.1.2-10 NineMilePointUnit2FSAR2.Controlsareprovidedtomanuallycontrolreactorpowerlevel.3.Controlofthenuclearsystemispossiblefrom-a--single"location.Nuclearsystemsprocesscontrolsandalarmsarearrangedtoallowtheoperatortorapidlyassesstheconditionofthenuclearsystemandtolocateprocesssystemmalfunctions.5.Interlocksorotherautomaticequipmentareprovidedasabackuptoproceduralcontrolstoavoidconditionsr'equiringactuationofnuclearsafetysystemsorengineeredsafeguards.PowerConversionSstemsProcessControlDesinCriteriaControlequipmentisprovidedtocontrolreactorpressurethroughoutitsoperatingrange.2.Theturbineiscapableofrespondingautomaticallytominorchangesinload.3.,Thefeedwatersystemiscontrolledtomaintainthewaterlevelinthereactorvesselattheoptimumlevelrange.4Controlofthepowerconversionequipmentispossiblefromonelocation.5.Interlocksorother,automaticequipmentareprovidedasabackuptoproceduralcontrolstoavoidconditionsrequiringtheactuationofnuclearsafetysystemsorengineeredsafeguards.ElectricalPowerSstemProcessControlDesinCriteriaThesafety-related(Class1E)electricalpowersystemisdesignedasathree-divisionsystem,anytwooutofthreedivisionsbeingadequatetosafelyshutdowntheunit.2.Theprotectionsystemisdesignedtodetectandisolatefaultedequipmentfromthesystemwithaminimumofdisturbanceintheeventofanyfaultinthesystem.Amendment211.2-11September1985 NineMilePointUnit2FSAR3.Intheeventofalossofoffsitepowertheprotectionsystemisolatestheemergencybusesfromtheoffsitesystemandinitiatesthestartingofthestandbyacpowersources.4.IntheeventoflossofoffsitepowerandLOCAtheprotectionsystemisolatesthe:emergencybusesfromtheoffsitesystemandthenormalelectricalsystem,andthestandbydieselgeneratorsarestartedandsequentiallyloadedbyaprogrammedcontrolsystemtoenergizeallsafety-relatedloads.5.Allelectrically-operatedbreakersarecontrollablefromthecontrolroom.6'.Meteringforgenerators,transformers,andotheressentialcircuitsisavailableinthecontrolroom.1.2.2SiteDescription1.2.2.1SiteCharacteristics:SiteLocationandSizeTheprojectsitecomprisesapproximately364ha(900acres)andislocatedonthesouthshoreofLakeOntariointhetownofScriba,OswegoCounty,NY,onlandownedbytheNiagaraMohawkPowerCorporation(NMPC).TheNineMilePointNuclearStation-Unit2(Unit2)sharesthesitewithexistingUnit1;Unit2andsupportfacilitiesoccupyabout18.2ha(45acres)ofthetotalsiteacreage.TheJamesA.FitzPatrickplant,ownedbytheNYPA,islocatedeastoftheprojectsite.Thecenterline-to-centerlinedistancebetweenUnit2andtheFitzPatrickplantreactorsisabout716m(2,350ft).ThedistancebetweentheNineMilePointUnit1andUnit2reactorcenterlinesisabout274m(900ft).ThesiteplanisshownonFigure1.2-1.AllactivitiesatthesiteareunderthedirectcontrolofNMPC"'.1.2.2.2AccesstotheSiteTheprotectedareaofthesiteisisolatedfromthesurroundingareabyfencing.Accesstothesiteiscontrolledatthegateofthemainentrancetotheplantbysecuritypersonnel.Allothergatesarekeptlocked"'.USARRevision41.2-12October1992 NineMilePointUnit2FSAR1~2.2.3DescriptionoftheSiteandEnvironsMostofthelandimmediatelytothesouthandwestofthesiteispastureorinactivefarmland.Fortheregionwest,south,andeastofthesite,thecountryischaracterizedbyrollingterrainrisinggentlyupfromLakeOntariowhichliesimmediatelytothenorthofthesite.Withinanapproximate8-km(5-mi)radiusofUnit2,the1980populationwas3,468.Thepopulationforthissameareaisprojectedtobe5,301in1990and7,213in2010.ThenearestdwellingsareonLakeviewRoadapproximately1.6km(1mi)fromthestation.TheOntarioBibleConferenceoperatesasummercamponthelakefrontadjacenttothewesternboundaryofthesite'swego,whichisthenearestcity,islocatedabout10km(6.2mi)southwestofthesiteandhada1980populationof19,793.Thenearestpopulationcenterwithapopulationinexcessof25,000isthecityofSyracuse,approximately53km(32.8mi)southeastofthesite.Buffaloisapproximately217km(135mi)westofthesite.Figure2.1-1showsthelocationofthesiterelativetothelargercitiesinNewYorkStatewhicharewithinthe80-km(50-mi)radiusofthesite.1.2.3StructuresandEquipmentThebuildingsandstructuresessentialtothesafeoperationandshutdownoftheplantaredesignedtowithstandextremeenvironmentalandabnormalloadingconditions.Thestructuresand/orportionsthereofsodesignatedaredesignedtoprovidetheprotectionasrequiredfromtornadoes,missiles,earthquakes,pipewhip,andinternalorexternalflooding.AdditionaldiscussionsofdesignconsiderationsarefoundinChapter3.LocationsandorientationofthestructuresareshownonFigures1.2-1and1.2-2.ThegeneralarrangementofpersonnelaccessbetweenstructuresisshownonFigures1.2-3through1.2-5.ThegeneralarrangementofthemajorstructuresandequipmentisshownonFigures1.2-6through1.2-40.Theprincipalstructureslocatedatthesitearelistedbelowalongwiththebriefdescriptionofthemajorequipment,withineachstructure.Theprimarycontainmentstructure(Figures1.2-6'through1.2-12)housesthereactorpressurevessel,reactor1.2-13 NineMilePointUnit,2FSARrecirculationpumpsandmotors,drywellcoolingsystemunit,coolers,safetyreliefvalves,accumulators,andotherequipment.Thereactorbuildingandauxiliarybays(Figures-1.2-6throughl.2-12)enclosetheprimarycontainmentstructure.ThesestructureshousetheremainingportionsoftheNSSS,refuelingandfuelstorageequipment,controlroddrive(CRD)hydraulicunits,equipmentforthereactorwatercleanupsystem(RWCU),equipmentforthestandbyliquidcontrolsystem(SLCS),equipmentforthereactorbuildingclosedloopcoolingwatersystem,andotherequipment.Theradwastebuilding(Figures1.2-13and1.2-14)housesprimarilythetanksandequipmentassociatedwiththeliquidandsolidradwastesystems.Thecontrolbuilding(Figures1.2-15and1.2-16)housesthemaincontrolroom,standbyswitchgear,batteriesandassociatedinstrumentation,cables,andequipment.Thedieselgeneratorbuilding(Figures1.2-17and1.2-18)housesthreestandbydieselgenerators,dieseloilstoragetanks,andassociatedcontrolsandinstrumentation.Theturbinebuildingincludingheaterbay(Figures1'-19through1.2-25)housestheturbinegenerator,condensers,moistureseparatorreheater,condensatedemineralizersystem,feedwaterheaters,steamjetairejectors,reactorfeedpumps,turbinebuildingclosedloopcoolingwatersystem,andmiscellaneoustanksandequipmenttosupportthepowerconversionsystemandotherrelatedsystems.Thescreenwellbuilding(Figures1.2-26through1.2-28)housesthecirculatingwaterpumpsandtheservicewaterpumpswithassociatedequipmentandinstrumentation.Theintakeanddischargetunnelsandintakestructures(Figures1.2-29'and1.2-30)areusedfortransportingservicewatertoandfromthelake.Theintaketunnelsalsosupplymakeupwaterforthecirculatingwatersystem.Themainstack(Figure1.2-31)isusedtoprovideelevatedreleaseofgasesfromtheoff-gas,standbygastreatment,andothersystems.Theoff-gasregenerationandcondensatedemineralizerrooms(Figures1.2-19through1.2-25)housethecatalyticrecombiners,off-gasfilter,condensatedemineralizer,andrelatedequipment.1.2-14 NineMilePointUnit2FSARThenormalswitchgearbuilding(Figures1.2-32and1.2-33)housesthenormalswitchgearandassociatedequipment.Theauxiliaryboilerbuilding(Figure1.2-34),locatednorthofthescreenwellbuilding,housestheelectricboilersandaccessoriestosupplysteamtotheplantduringshutdown.Thestandbygastreatmentbuildingandrailroadaccessarea(Figures1~2-35and1.2-36)housethestandbygastreatment,filtersandassociatedequipmentandallowaccessforspentfuelshipping.IThecondensatestoragetankbuilding(Figure1.2-37)housesthecondensatestoragetanksandassociatedequipment.Thenatural-draftcoolingtower(Figures1.2-38and1.2-39)providesthenormalheat,sinkforheattransferredtothecirculatingwatersystemfromthemaincondensers.Theauxiliaryservicebuilding(Figures1.2-7and1.2-8),adjacenttothereactorbuilding,housestheHVACroomanddecontaminationandshowerfacilitiesforpersonnel.Thedecontaminationarea(Figures1.2-19through1.2-21,1.2-23,and1.2-24),immediatelysouthoftheradwastebuilding,providesthefacilityfordecontaminationoflargetoolsandequipment,andasampleroom.Italsohousescleansteamreboilersandrelatedequipment.Thehydrogenstoragearea(forhydrogencoolingoftheturbinegenerator,Figure1.2-40)islocatedwestoftheoff-gasarea.Thehydrogenstoragebottlesaremountedonconcrete.padsandareinafencedarea.1.2.4NuclearSteamSupplySystemThenuclearsystemincludesadirect.-cycle,forcedcirculation,GEBWRthatproducessteamfordirectuseinthesteamturbine.AheatbalanceshowingthemajorparametersofthenuclearsystemforthewarrantedpowerconditionisshownonFigure1.1-1.ThenuclearsteamsupplysystemisfurtherdiscussedinChapters4and5.1.2.4.1ReactorCoreandControlRodsThereactorfuelandcoredesignaredescribedinSe'ction2ofReference5andSection1ofReference6.Amendment211.2-15September1985 NineMilePointUnit2FSARExperiencehasshownthatthecontrolrodsare.notsusceptibletodistortionandhaveanaveragelifeexpectancymanytimestheresidencetimeofafuelloading.1.2.4.2ReactorVesselandInternalsThereactorvesselcontainsthecoreandsupportingstructures;thesteamseparatorsanddryers;thejetpumps;thecontrolrodguidetubes;thedistributionlinesforthefeedwater,coresprays,andstandbyliquidcontrol;theincoreinstrumentation;andothercomponents.Themainconnectionstothevesselincludethesteamlines,coolantrecirculationlines,feedwaterlines,CRDandincorenuclearinstrumenthousings,corespraylines,residualheatremovallines,standbyliquidcontrolline,coredifferentialpressureline,jetpumppressuresensinglines,andwaterlevelinstrumentation.Thereactorvesselisdesignedandfabricatedinaccordancewithapplicablecodesforapressureof1,250psig.Thenominaloperatingpressureinthesteamspaceabovetheseparatorsis1,020psia.Thevesselisfabricatedoflow-alloysteelandiscladinternallywithstainlesssteel(exceptforthetopheadnozzlesandnozzleweldzoneswhichareunclad).Thereactorcoreiscooledbydemineralizedwaterthatentersthelowerportionofthecoreandboilsasitflowsupwardaroundthefuelrods.Thesteamleavingthecoreisdriedbysteamseparatorsanddryerslocatedintheupperportionofthe.reactorpressurevessel(RPV).Thesteamisthendirectedtotheturbinethroughthemainsteamline'.Eachsteamlinehastwoisolationvalvesinseries,oneoneithersideoftheprimarycontainmentbarrier.Amendment211.2-16September1985 NineMilePointUnit2FSAR1.2.4.3ReactorRecirculationSystemThereactorrecirculationsystemconsistsoftworecirculationpumploopsexternaltotheRPV.These,loopsprovidethepipingpathforthedrivingflowofwatertotheRPV~jetpumps.Eachexternalloopcontainsonehighcapacitymotor-drivenrecirculationpump,twomotor-operatedmaintenancevalves,andonehydraulicallyoperatedflowcontrolvalve.Thevariablepositionhydraulicflowcontrolvalveoperatesinconjunctionwithalow.frequencymotorgeneratorsettocontrolreactorpowerlevelthroughtheeffectsof'coolantflowrateonmoderatorvoid.content.ThejetpumpsareRPVinternals.Theyprovideacontinuousinternalcirculationpathforthemajorportionofthecorecoolantflow.Thejetpumpsarelocatedintheannularregionbetweenthecoreshroudandthevesselinnerwall.Anyrecirculationlinebreakstillallowscorefloodingtoapproximatelytwo-thirdsofthecoreheight,theleveloftheinletofthejetpumps.1.2.4.4ResidualHeatRemovalSystemTheresidual,heatremoval(RHR)systemisasystemofpumps,heatexchangers,andpipingthatfulfillsthefollowingfunctions:1~Remove'sdecayandsensibleheatduringandafterplantshutdown.2.InjectswaterintotheRPVfollowingaLOCAtorefloodthe,coreindependentlyofothercore.coolingsystems.3.RemovesheatfromtheprimarycontainmentfollowingaLOCA,tolimittheincreaseinprimarycontainmentpressure.Thisisaccomplishedbycoolingandrecirculating"thesuppres'sionpoolwater.andbysprayingthedrywellandsuppressionpoolairspaceswithsuppressionpoolwater.1.2.4.5ReactorWaterCleanupSystemTheRWCUsystemrecirculatesaportionofreactorcoolantthroughafilter-demineralizertoremoveparticulateanddissolved.impuritiesfromthe.reactorcoolant.Italsoremovesexcesscoolantfromthereactorsystemundercontrolledconditions.1.2-17 NineMilePointUnit2FSAR1.2.4.6NuclearLeakDetectionSystemThenuclearleakdetectionandmonitoringsystemconsistsoftemperature,pressure,flow,andfission-productsensorswithassociatedinstrumentationandalarms.Thissystemdetectsandannunciatesleakageinthefollowing.systems:1~Mainsteamlines.2.Reactorwatercleanupsystem.3.Residualheatremovalsystem.4.Reactorcoreisolationcooling(RClC)system.5.Feedwatersystem.6.Emergencycorecoolingsystems~7.Miscellaneoussystems.Smallleaksgenerallyaredetectedbymonitoringareatemperatures,radiationlevels,anddcainsumpfillupandpumpoutrates.Largeleaksarealsodetectedbychangesinreactorwaterlevel,primarycontainmentpressureandchangesinflowratesinprocesslines.1.2.5Electrical,Instrumentation,andControlSystems1.2.5.1ElectricalPowerSystemTheplantelectricalpowersystemconsistsoftheunitgenerator,theswitchyard,andtheunitauxiliarypowerdistributionsystem.'ITheunitgeneratorisconnecteddirectlytothegeneratorstep-up.transformersandthenormalstationservicetransformerthroughisolatedphasebusduct.Thegeneratorstep-uptransformersstepuptheoutputoftheunitgeneratorfrom25kVtoanominal345-kVtransmissionsystemvoltage.Thenormalstationservicetransformerstepsdowntheunitgeneratorvoltagefrom25to13.8kVandprovidesanonsite(ac)powersourcetotheunitauxiliarypower~distributionsystem.Theswitchyardhastwoseparateandindependentsections:the345-kVswitchyardandthe115-kVswitchyard.Theoutputofthegeneratorstep-up.transformersisconnectedtothe345-kVswitchyardwhichconnectstheunitAmendment181.2-18March1985 NineMilePointUnit2FSARgeneratortotheoutgoingtransmissionsystem.-The115-kVswitchyardreceivespowerfromtwoseparateoffsitepowersourcesthrough'wophysicallyandelectricallyindependentincomingcircuits.'hetwocircuitsfeed'twoseparatereservestationservicetransformersandanauxiliaryboilertransformer.Thereser'vestationservicetransformersstepdowntheoffsitepowerfrom115to13.8and4.16kV,andprovidetwoindependent"offsitepowersourcesfortheunitauxiliary-powerdistributionsystem.Theauxiliaryboilertransformerstepsdowntheoffsitepowerfrom115to13.8and4.16kV.Its'3.8-kVwindingsuppliespowertotheauxiliaryboilerandassociatedequipment;the4.16-kVtertiarywindingprovidesabackupsource'ortheemergency4.16-kVbuses.Theunitauxiliarypowerdistributionsystemfeedsallunitauxiliaryloadsthrough13.8-kVswitchgear,4.16-kVswitchgear,600-Vloadcenters,600-Vmotorcontrolcenters,andvariousacanddcdistributionpanels.Thesystemisdivided'into'nuclearnonsafety-relatedandnuclearsafety-relatedsystems.Thenuclearnonsafety-relatedauxiliarypower'distributionsystemfeedsallnon-Class1Eunitauxiliaryloads.'ndernormalplantoperatingconditions,itisenergizedfromthenormalstationservicetransformer..''During'-startupandnormalshutdownconditions,it.isenergizedfromoffsitepowersourcesthroughreservestationservicetransformers'normal125-Vdcsystem,consistingofbatteries,batterychargers,anddistributionpanels,providesareliablesourceofpowerforprotection,control,andinstrumentationloadsanddcmotorsundernormalandemergencyconditionsoftheplant.Ai24-Vdcsystemprovides'areliablesourcefortheneutronmonitoringsystem.Thenuclearsafety-relatedauxiliarypowerdistributionsystemsuppliesallClass1Eunitauxiliaryloads.Thissystemis,dividedintothreeindependentdivisions.DivisionIandDivisionIIareindependentredundantdivisionsandsupplyallnuclearsafety-relatedauxiliaryloadsexceptthehighpressurecorespray(HPCS)system.TheHPCSsystem,andrelatedequipmentaresuppliedbyDivision.III..Allthreedivisionsarenormallyenergizedfromtheoffsitepowersourcesthroughreservestationservicetransformers.TheauxiliaryboilertransformercanbeconnectedmanuallytoactasabackupsourceforeithertheDivisionIorDivisionIIsupply.Eachofthethreedivisionsofthenuclearsafety-relatedauxiliarypowerdistributionsystemshasitsownindependentstandbydieselgenerator.IntheeventofaLOCAand/or1.2-19 NineMilePointUnit2FSAR.lossofoffsitepower,eachdivisionisenergizedfromits,,ownstandbydieselgenerator.A125-Vemergency.dcpower;systemfeedsallsafety-relateddc,protection,control,andinstrumentationloadsandsafety-relateddcmotorsundernormal.operationoftheplantaswellasduringemergency.conditions.,Thesystemisdividedintothree,independentdivisionseachconsistingofitsownbattery,primaryandbackupbatterychargers,switchgear,motorcontrolcenters,anddistributionpanels.Eachdivisionfeedsthedc.loadsassociatedwiththe.correspondingdivisionsofthenuclearsafety-relatedauxiliarypowerdistributionsystem.tChapter8describestheelectrical,powersystemindetail.1.2.5.2NuclearSystemProcessControlandInstrumentationReactorManualControlSstemThereactormanualcontrolsystem(RMCS)providesthemeansbywhichcontrolrodsarepositionedfromthecontrolroomforpowercontrol.Thesystemoperatesvalvesineachhydrauliccontrolunittochangecontrolrodposition.Onecontrolrodcanbemanipulatedatatime.TheRMCSincludesthelogicthatrestrictsabnormalcontrolrodmovement(rodblock)undercertainconditionsasabackuptoproceduralcontrols.RecirculationFlowControlSstemPfDuringnormalpoweroperation,avariablepositiondischargevalveisused'tocontrolflow.Adjustingthisvalvechangesthecoolantflowratethroughthecoreandtherebychangesthecorepowerlevel.NeutronMonitorinSstem!'heneutronmonitoringsystem(NMS)isasystemofincoreneutrondetectorsandout-of-coreelectronicmonitoringequipment.Thesystemprovidesindicationofneutronflux,which'anbecorrelatedtothermalpowerlevelfortheentirerangeoffluxconditionsthatcanexistinthecore.Thesourcerangemonitors(SRMs)andthe"intermediaterangemonitors(IRMs)providefluxlevelindicationsduringreactorstartupandlow-poweroperation.Thelocalpowerrangemonitors(LPRMs)andaveragepowerrangemonitors(APRMs)allowassessmentoflocalandoverallfluxconditionsduringpowerrangeoperation.Thetraversingincoreprobe(TIP)'systemprovidesa'eanstocalibratetheUSARRevision01.2-20April1989 NineMilePointUnit2FSARindividualLPRM.sensors.TheNMSprovidesinputstotheRMCStoinitiaterodblocksifpresetfluxlimitsareexceeded,andinputstothereactorprotectionsystemtoinitiateascramifotherlimitsareexceeded.RefuelinInterlocksAsystemofinterlocksthatrestrictmovementofrefuelingequipmentandcontrolrodswhenthereactorisintherefuelingandstartupmodesisprovidedtopreventaninadvertentcriticalityduringrefuelingoperations.Theinterlocksbackupproceduralcontrolsthathavethesameobjective.Theinterlocksaffecttherefuelingplatform,refuelingplatformhoists,fuelgrapple,andcontrolrods.ReactorVesselInstrumentationreactorvesselheadannProcessComuterSstemInadditiontoinstrumentationforthenuclearsafetysystemsandengineeredsafetyfeatures,instrumentationisprovidedtomonitorandtransmitinformationthatcanbeusedtoassessconditionsexistinginsidethereactorvesselandthephysicalconditionofthevesselitself.Thisinstrumentationmonitorsreactorvesselpressure,waterlevel,coolanttemperature,reactorcoredifferentialpressure,coolantflowrates,andersealringleakage.Anonlineprocesscomputerisprovidedtomonitorandlogprocessvariablesandtomakecertainanalyticalcomputations.Thenuclearmeasurementanalysisandcontrolrodworthminimizer(NUMACRNM)preventsrodwithdrawalunderlow-powerconditionsiftherodtobewithdrawnisnotinaccordancewithapreplannedpattern.Theeffectoftherodblockistolimitthereactivityworthofthecontrolrodsbyenforcingadherencetothepreplannedrodpattern.Chapter7describesthesesystemsindetail.1.2.5.3PowerConversionSystemsProcessControlandInstrumentationPressureRelatorandTurbineGeneratorControlThepressureregulatormaintainscontroloftheturbinecontrolandturbinebypassvalvestoallowpropergeneratorandreactorresponsetosystemload-demandchangeswhilemaintainingthenuclearsystempressureessentiallyconstant.USARRevision31.2-21October1991 NineMilePointUnit2FSARTheturbinegeneratorspeed-loadcontrolscaninitiaterapidclosureoftheturbinecontrolvalves(rapidopeningoftheturbinebypassvalves)topreventturbineoverspeedonlossofthegeneratorelectricload.FeedwaterControlSstemThefeedwatercontrolsystemautomaticallycontrolstheflowoffeedwaterintothereactorpressure.vesseltomaintainthewaterwithinthevesselatpredeterminedlevels.Athree-elementcontrolsystem(mainsteamflowrate,feedwaterflowrate,andreactorvesselwaterlevel)isusedtoaccomplishthisfunction.Chapter10describesthesystemingreaterdetail.1.2.6RadioactiveWasteSystemThedisposalofradioactivewastesfromthesiteismanagedbywastesystemsdesignedtomeetallapplicableregulatory>9[requirements,including10CFR20,10CFR60,10CFR61,GeneralDesignCriterion60,andRegulatoryGuide1.21.Therearethreeinterrelatedradioactivewastetreatmentsystems:radioactiveliquidwaste,radioactivegaseouswaste,andradioactivesolidwaste.ThesesystemsaredescribedinChapter11.Theradioactiveliquidwaste(LWS)systemcollectsandprocessesradioactivewasteliquidsgeneratedduringplantoperationandrefueling,eitherforrecyclewithintheplantorfordischargeoffsite.Theprocessoperationsavailabletotreattheliquidwastesarefiltration,evaporation,demineralization,anddecantation.Processdescriptionsandflowchartsillustratethenumberandsequenceof.processingstepstobeappliedtoeachtypeofliquidwaste.Gaseousradwastefromthemaincondenserisprocessedthrougharecombinertoremovehydrogen,afterwhichthegasiscooled,thendried.Wastegasisthenpassedthroughacharcoalbedandfiltersystem,whichholdsupradioactivecomponentsandremovesparticulatematterbeforerelease.Contaminateddrywellandbuildingventilationexhaustsareprocessedbythestandbygastreatmentandventilationsystems.Theradioactivesolidwastesystemprovidesholdup,packaging,andstoragefacilitiesforeventualoffsiteshipmentandultimatedisposalofsolidradioactivewastematerial.TheprocessoperationsconsistofvolumeAmendment191.2-22May1985 NineMilePointUnit2FSARreductionandsolidificationwithasphaltofradioactivewastessuchasLWSevaporatorconcentrates,spentresins,andfiltersludges.Dryradioactivewastessuchascontaminatedpaper,clothing,andtoolsarecompactedandpackaged.Afterprocessing,thesolidwastematerialsarestoredforadditionaldecayandthen'shippedoffsiteforappropriatedisposal.Shielding,asrequiredduringtheprocessingandshipmentofthesolidwastes,isincludedintheplannedoperationofthesolidwastesystem.AdescriptionandflowdiagramoftheprocessingandhandlingsequencesforthesolidwastesgeneratedonsiteisprovidedinChapter11.1.2'FuelHandlingandStorageSystems1.2.7'NewFuelStorageThenewfuelfacilityisdesignedtopreventinadvertentcriticalityandloadbucklingofthenewfuelassemblies.BoththenewfuelstoragevaultandstorageracksaredesignedtocomplywithCategoryIrequirements.Thenewfuelstoragevaultisdesignedwithsufficientdrainagetoprecludeflooding.Thevaultisalsoequippedwithamonitoringsystemtowarnofradiationlevelincreasesabovenormaloperatingconditions.tThedesignofthenewfuelstoragerackslimitskeff50.90inthedryconditionandkeff60.95inafloodedcondition.1.2.7.2SpentFuelStorageThespentfuelstorageracksaredesignedtomaintainspentfuelinaspacegeometrythatpreventscriticalityinnormalandabnormalconditions.Theracksarecapableofwithstandingmaximumupliftforcesgeneratedwithouteffectonthesubcriticalarray.Thedesignofthespentfuelrackswilllimitkeff50.95innormalandabnormalstorageconditions.Thereissufficientshielding,acoolingsystem,andradiationmonitoringtopreventoverheatingandexcessivepersonnelexposure.Thespentfuelstoragepoolandracksarecorrosionresistant,andadheretoCategoryIrequirements.1.2-23 NineMilePointUnit2FSAR1.2.7.3FuelHandlingSystemThefuelhandlingequipmentincludesthefollowing:1.Fuelinspectionstand.2~Fuelpreparationmachine.3.125-toncrane.4.Refuelingplatform.5~Generalpurposegrapple.6;Jibcranes.7.Otherrelatedtoolsforfuelandreactorservicing.Allequipmentconformstoapplicablecodesandstandards.1.2.7.4SpentFuelPoolCoolingandCleanupSystemThespentfuelcoolingandcleanup(SFC)systemprovidesremovalofdecayheatfromthestoredspentfuelandmaintainsspecifiedwatertemperature,purity,clarity,andlevel.Thisprocesspreventsthespentfuelfromoverheating'ndthebuildupofexcessiveradioactivematerialsinthecoolingwater,therebyminimizingradiationlevels.Thesystemincludes.twoheatexchangers,eachofwhichiscapableofremovingthefulldecayheatfromanormalrefuelingoffloadofspentfuelsAcrossconnectiontotheRHRsystemprovidesadditionalemergencybackupcoolingandcoolingduringafullcoreoffload.Chapter'givesfurtherdetailsofthefuelhandlingandstoragesystem.1.2.8PowerConversionSystemChapter10providesadetaileddiscussionofthefollowingequipmentsystems.1.2.8.1TurbineGeneratorTheturbineisan1,800-rpmtandem-compound,six-flow,single-stagereheatunitwithanelectrohydraulicgovernorcontrol.Theturbinegeneratorhasanemergencytripsystemforturbineoverspeed.TheoutputoftheturbinegeneratorAmendment211.2-24September1985 NineMilePointUnit2FSARis1,165,663kWeatturbineguaranteeconditionswith2.0inHgabsbackpressureand0percentmakeup.Thegeneratorisadirectdriven,three-phase,60-Hzt25)000Vf1,800-rpmhydrogeninner-cooled,synchronousgeneratorratedat1,348,400kVAat0.90powerfactor,0.58short-circuitratioatmaximumhydrogenpressureof75psig.1.2.8.2MainSteamSystemThemainsteamsystemdeliverssteamfromthenuclearboilersystemthroughfour26-/28-inODsteamlinestotheturbinegenerator,turbinebypassvalves,steamjetairejectors,off-gaspreheaters,steamsealevaporator,andradwastesteamreboiler.1.2.8.3MainCondenserThemaincondensermaintains2.0inHgabswhenoperatingatturbineguaranteeconditionswith67.97Fcirculatingwaterinlettemperature.Thecondenserincludesprovisionsforacceptingsteambypassedaroundtheturbinegenerator.Deaerationofcondensateisaccomplishedinthecondenser.1.2.8.4MainCondenserAirRemovalSystemThemaincondenserairremovalsystem,usingairejectorsfornormaloperationandvacuumhoggingpumpsforstartup,evacuatesgasesfromthemainturbineandcondenserduringplantstartupandmaintainsthecondenseressentiallyfreeofgasesduringoperation.Thissystemhandlesallinleakageofnoncondensablegasesthroughtheturbineseals,condensate,feedwater,andsteamsystems,andnoncondensablesthataregeneratedinthereactorbydisassociationofwater.1.2.8.5TurbineGlandSealingSystemTheturbineglandsealingsystemprovidesmildlyradioactivesteamtothesealsoftheturbinethrottlevalvestemglandsandtheturbineshaftglands.Thesealingsteamissuppliedbyacleansteamreboilerusingcondensate.Theunitauxiliaryboilerprovidesanauxiliarysteamsupplyforstartupandwhenreactorheatingsteamisnotavailable.Thesteampackingexhaustercollectsandcondensestheairandsteammixtureanddischargestheairandothernoncondensablestotheplantexhaustducttotheatmosphere,usingamotor-drivenexhauster.USARRevision31.2-25October1991 NineMilePointUnit2FSAR1.2.8.6SteamBypassSystemandPressureControlSystemAturbinebypasssystemisprovidedwhichpassessteamdirectlytothemaincondenserundercontrolofthepressureregulator.Steamisbypassedtothecondenserwheneverthereactorsteamingrateexceedstheloadpassedtotheturbinegenerator.Thecapacityoftheturbinebypasssystemis25percentoftheturbineratedsteamflow.Thepressureregulationsystemprovidesmainturbinecontrolvalveandbypassvalveflowdemandstomaintainanearlyconstantreactorpressureduringnormalplantoperation.Italsoprovidesdemandstotherecirculationsystemtoadjustpowerlevelsbychangingreactorrecirculationflowrates.l.2.8.7CirculatingWaterSystemThecirculatingwatersystemprovidesthecondenserwithacontinuoussupplyofcoolingwater.Thecirculatingwatersystemisapumpedclosedloopsystemutilizinganair-coolednatural-draftcoolingtowerasaheatsink.Sixone-sixthcapacitycirculatingwaterpumpsareprovidedtopumpcoolingwaterfromthecoolingtowerbasinthroughthemaincondenserandbacktothetopofthecoolingtower.Makeupwaterisprovidedfrom?akeOntariobytheservicewatersystem.1.2.8.8CondensateandFeedwaterSystemsThecondensateandfeedwatersystemssupplycondensatefromthecondenserhotwelltotheRPV~Thecondensateispumpedbytwoofthethreecondensatepumpsthroughthefullflowcondensatedemineralizersystem,theintercooleroftheairejectors,andthesteampackingexhaustertothecondensateboosterpumps.Thecondensateboosterpumpspumptheflowthroughthreestringsconsistingoftwodraincoolersandfivestagesoflowpressureheaterseach.Inaddition,threeheaterdrainpumpsprovideapproximatelyone-thirdofthefeedwaterflowrequirements.Thelastlowpressureheatersdischargetothesuctionofthreeparallelmotor-drivenreactorfeedwaterpumps.Thedischargeofthereactorfeedwaterpumpspassesthroughthreeone-thirdcapacityparallelheatersandintotheRPV.Thefeedwaterflowiscontrolledbyvaryingthefeedwaterflowcontrolvalveposition.1.2.8.9CondensateDemineralizerSystemAfullflow,deepbedcondensatedemineralizersystemcompletewithregenerationfacilities,instrumentation,and1.2-26 NineMilePointUnit2FSARsemiautomaticcontrolsisdesignedtoensureaconstantsupplyofhighqualitywatertothereactor.1.2.9NuclearSafetySystemsandEngineeredSafetyFeaturesChapters3,4,5,6,=7,9,and10givefurtherdetailsfor)iethefollowingequipmentandsystems.1.2.9.1ReactorProtectionSystemThereactorprotectionsystem(RPS)initiatesarapid,automaticshutdown(scram)ofthereactor.Itactsintimetopreventfuelcladdingdamageandanynuclearsystemprocessbarrierdamagefollowingabnormaloperationaltransients.TheRPSoverridesalloperatoractionsandprocesscontrolsandisbasedonafail-safedesignphilosophythatallowsappropriateprotectiveactionevenifasinglefailureoccurs.11.2.9.2NeutronMonitoringSystemTheneut"onmonitoringsystemisasystemofincoreneutrondetectorsandoat-of-coreelectronicmonitoringequipment.Thesystemprovidesindicationofneutronflux,whichcanbecorrelatedtothermal-powerlevelfortheentirerangeofflu".conditionsthatcanexistinthecore.TheSRMsandtneIRMsprovidefluxlev'el'indicationsduringreactorste.tupandlowpoweroperation.TheLPRMsand~'iPRMsallowassessmentoflocalandoverallfluxconditionsduringpowerrangeoperation.TheTIPsystemprovides=ameanstocalibratetheindividualLPRMsensors.TheNMSprovidesinputstotheRMCStoinitiaterodblocksifpresetfluxlimitsareexceeded,andinputstotheRPStoinitiateascramifotherlimitsareexceeded.1.2.9'ControlRodDriveSystemWhenascramisinitiatedbytheRPS,theCRDsysteminsertsnegativereactivitynecessarytoshutdownthereactor.Eachcontrolrodisindividuallycontrolledby'ahydrauliccontrolunit(HCU).Whenascramsignalisreceived,highpressu'rewaterstoredinanaccumulatorintheHCUorreactorpressureforcesthecontrol"rodintothecore.1.2.9.4ControlRodDriveHousingSupportsCRDhousingsupportsarelocatedunderneaththereactorvesselnearthecontrolrodhousings.Thesupportslimitthetravelof'controlrodintheeventthatacontrolrodhousingisruptured.ThesupportspreventanuclearAmendment181.2<<27March1985 NineMilePointUnit2FSARexcursionasaresultofahousingfailureandthusprotectthefuelbarrier.1.2.9.5ControlRodVelocityLimiterAcontrolrodvelocitylimiterisattachedtoeachcontrolrodtolimitthevelocityatwhichacontrolrodcanfalloutofthecoreshoulditbecomedetachedfromtheCRD.Thisactionlimitstherateofreactivityinsertionresultingfromaroddropaccident.Thelimiterscontainnomovingparts.1.2.9'NuclearSystemPressureReliefSystemApressurereliefsyst:emconsistingofsafety/reliefvalves(SRV),mountedonthemainsteamlinesisprovidedtopreventexcessivepressureinsidethenuclear.systemfromoperationaltransientsoraccidents.TheSRVdischargesteamisdirectedtothesuppressionpoolwithintheprimarycontainment.1.2.9.7ReactorCoreIsolationCoolingSystemTheRCICsystemprovidesmakeupwatertotheRPVwhenthevesselisisolated.TheRCICsystemusesasteam-driventurbine-pumpunitandautomaticallyoperatestomaintainadequatewaterlevelintheRPVforeventsdefinedinSection5.4.6.1.1.2.9.8EmergencyCoreCoolingSystemsFourECCSsareprovidedtomaintainfuelcladdingbelowthetemperature.limitin10CFR50.46intheeventofabreachintheRCPBthatresultsinalossofreactorcoolant.Thesystemsareasfollows.HihPressureCoreSraHPCSTheHPCSsystemprovidesandmaintainsanadequatecoolantinventoryinsidetheRPVtolimitfuelcladdingtemperaturesintheeventofbreaksintheRCPB.Thesystemisinitiatedbyeitherhighpressureinthedrywellorlowwaterlevelinthevessel.Itoperatesindependentlyofallothersystemsovertheentirerangeofpressuredifferencesfromgreaterthannormaloperatingpressuretozero.TheHPCScoolingdecreasesvesselpressuretoenablethelowpressurecoolingsystemstofunction.TheHPCSsystempumpmotorispoweredbyanonsitedieselgeneratorif.offsitepowerisnotavailable.ThesystemmayalsobeusedasabackupfortheRCICsystem.1.2-28 NineMilePointUnit2FSARAutomaticDeressurizationSstemADSTheADSrapidlyreducesRPVpressureinaLOCAsituationinwhichtheHPCSsystemfailstomaintaintheRPVwaterlevel.ThedepressurizationprovidedbythesystemenablesthelowpressureECCStodelivercoolingwatertotheRPV.TheADSusessomeofthereliefvalvesthatarepartofthenuclearsystempressurereliefsystem.TheautomaticreliefvalvesarearrangedtoopenonconditionsindicatingboththatabreakintheRCPBhasoccurredandthattheHPCSsystemisnotdeliveringsufficientcoolingwatertotheRPVtomaintainthewaterlevelaboveapreselectedvalue.SetpointsarediscussedinSection5.2.2.TheADSisnotactivatedunlesseitherthelowpressurecorespray(LPCS)orlowpressurecoolantinjection(LPCI)pumpsareoperating.Thisistoensurethatadequatecoolantisavailabletomaintainreactorwaterlevelafterthedepressurization.LowPressureCoreSraTheLPCSsystemconsistsofoneindependentpumpandvalvesandpipingtodelivercoolingwatertoasprayspargeroverthecore.Thesystemisactuatedbyeitherlowwaterlevelinthereactorvesselorhighpressureinthedrywell,but,waterisdeliveredtothecoreonlyafterRPVpressure'isreduced.Thissystemprovidesthecapabilitytocoolthefuelbyspraying.waterintoeachfuelchannel.TheLPCSloopfunctioninginconjunctionwiththeADSorHPCScanprovidesufficientfuelcladdingcoolingfollowingaLOCA.LowPressureCoolantInectionLPCIisanoperatingmodeoftheRHRsystem,butisdiscussedherebecausetheLPCImodeactsasanengineeredsafetyfeatureinconjunctionwiththeotherECCSs.LPCIusesthepumploopsoftheRHRtoinjectcoolingwaterintotheRPV.LPCIisactuatedbyeitherlowwaterlevelinthereactorvessel'orhighpressureinthedrywell,butwaterisdeliveredtothecoreonlyafterRPVpressureisreduced.LPCIoperationprovidesthecapabilityofcorereflooding,followingaLOCA,intimetomaintainthefuelcladdingbelowtheprescribedtemperaturelimit.1.2.9.9ContainmentSystemsPrimarContainmentTheprimarycontainmentisaMarkIIdesignthatincor-poratesadrywellpressuresuppressionsystemandutilizesa1.2-29 NineNilePointUnit2FSARlargereservoirofwatertofunctionasaheatsinktoabsorbenergy.1.FunctionalDesinTheprimarycontainmentisasteellinedreinforcedconcretestructure.Itconsistsofaconicaldrywellchamberaboveacylindricalsuppressionpoolchamberseparatedbyadrywellfloor.ThisfloorcontainsapipingsystemwhichwoulddirectdrywellsteamintothesuppressionchamberreservoirintheeventofaLOCA.2.HeatRemovalThecontainmentheatremovalsystemissummarizedinSection1.2.9.14.3.ContainmentSraThecontainmentspraysystemconsistsoftworedundantsubsystems,eachwithitsownfull-capacitysprayheader.EachsubsystemissuppliedfromaseparateredundantRHRsubsystem.4.CombustibleGasControlThecontainmentcombusti-blegascontrolsystemissummarizedinSection6.2.5.1.2.9.10ContainmentandReactorVesselIsolationControlSystemTheprimarycontainmentandRPVisolationcontrolsystemautomaticallyinitiatesclosureofisolationvalvestocloseoffallprocesslinesthatarepotentialleakagepathsforradioactivematerialtotheenvirons.ThisactionistakenuponindicationofabreachintheRCPB.1.2.9.11NainSteamIsolationValves28Althoughallpipelinesthatbothpenetratetheprimarycontainmentandofferapotentialreleasepathforradioactivematerialhaveredundantisolationcapabilities,themainsteamlines,becauseoftheirlargesizeandlargemassflowrates,aregivenspecialisolationconsideration.Automaticisolationvalvesareprovidedineachmainsteamline(MSIVs).Eachisclosedbyspringforceandpneumaticforceandopenedbypneumaticforce.Thesevalvesfulfillthefollowingobjectives:PreventexcessivedamagetothefuelbarrierbylimitingthelossofreactorcoolantfromtheRPVresultingfromeitheramajorleakfromthesteampipingoutsidetheprimarycontainmentoraAmendment,281.2-30Nay1987 NineMilePointUnit2FSARmalfunctionofthepressurecontrolsystemresultinginexcessivesteamflowfromtheRPV.2.Limit,thereleaseofradioactivematerialsbyisolatingtheRCPBincaseofagrossreleaseofradioactivematerialsfromthefueltothereactorcoolingwaterandsteam.3.Limitthereleaseofradioactivematerialsbyclosingthecontainmentbarrierincaseofamajorleakfromthenuclearsysteminsidethecontainment.1.2.9.12MainSteamFlowRestrictorsAventuri-typeflowrestrictorisinstalledineachsteamline.ThesedeviceslimitthelossofcoolantfromtheRPVbeforetheMSIVsareclosedincaseofamainsteamlinebreakoutsidethepr'imarycontainment.1~2.9.13MainSteamRadiationMonitoringSystemThemainsteamradiationmonitoringsystemconsistsoffourgammaradiationmonitorslocatedexternallytothemainsteamlinesjust.outsidetheprimarycontainmentinthemainsteamtunnel.Themonitorsaredesignedtodetectagrossreleaseoffissionproductsfromthefuel.Ondetectionofhighradiation,thetripsignalsgeneratedbythemonitorsareusedbytheRPStoinitiateareactorscramandtoclosetheMSIVs.1.2.9.14ResidualHeatRemovalSystemTheRHRsystemisplacedinoperationtolimitthetemperatureofthewaterinthesuppression'oolandoftheatmospheresinthedrywellandsuppressionch'amberfollowingadesignbasisLOCA,tocontrolthepooltemp'eratureduringnormaloperationoftheSRVsandtheRCICsystem,andtoreducethepooltemperaturefollowinganisolationtransient.Inthecontainmentcoolingmodeofoperation,theRHRmainsystempumpstakesuctionfromthesuppressionpoolandpumpthewaterthroughtheRHR.heat.'e'xchangersAmendment281.2-31May1987 NineMilePointUnit2FSARwherecoolingtakesplacebytransferringheattotheservicewater.Thecoolantisthendischargedbacktothesuppressionpool,thedrywellsprayheader,thesuppressionchambersprayheader,ortheRPV.1.2.9.15VentilationExhaustRadiationMonitoringSystemPermanentlyinstalledprocessandarearadiationmonitorsprovideindicationsandalarmsonairborneradiationinthereactorbuildingventilationsystem,drywellatmosphere,fuelstorageandrefuelingareas,andcontrolroomatmosphere.Additionally,connectionsareprovidedinthereactorbuildingventilationsystemductworkforcontinuousairbornemonitors(CAMs).1,.2.9.16StandbyGasTreatmentSystemThestandbygastreatmentsystem(SGTS)processesexhaust.airfromvariousplantsystemstolimitthereleaseofairborneradioactivity,maintainingoffsitedoseratesbelowthespecifiedlimits.DuringadesignbasisaccidenttheSGTSsystemisautomaticallyactuated.WhenhighradiationlevelsaresensedinanyexhaustsystemconnectedtotheSGTSsystemitisautomaticallyplacedinoperation.TheSGTSconsistsoftwoidentical,parallelbutphysicallyseparatedairfiltertrainassemblies.Each'ssemblyiscapableofhandlingthemaximumdesignairflowrate.1.2'.17Safety-RelatedElectricalPowerSystemsAstandbypowersupplysystemisprovidedfortheoperationofemergencysystemsandengineeredsafetyfeaturesduringandfollowingtheshutdownofthereactorwhenthepreferredpowersupplyisnotavailable.Thestandbypowersupplysystemconsistsofthreestandbydieselgenerators.Onegeneratorisdedicatedtoeachofthethreedivisionsofthesafety-relatedelectricpowerdistributionsystemfeedingeach'lass1Eloadgroup.Anytwoofthethreestandbydieselgeneratorshavesufficient,capacitytostartandsupplyallneededengineeredsafetyfeaturesandemergencyshutdownloadsincaseofaLOCAand/orlossofoffsitepower.Thestandbydieselgeneratorfueloilstoragetanksaresizedtoholda7-daysupplyoffueloilbasedontheenginerunningcontinuouslyatfullload.ALOCAand/orlossofoffsitepowersignalinitiatesstartofthestandbydieselgeneratorsandthegeneratorspickuptheloadsinaprogrammedsequence.Standbydieselgeneratorsareindependent,andfeedseparateloadgroupsthroughseparate,physicallyandelectricallyisolateddistributionsystems'.2-32 NineMilePointUnit2FSARFailureofanyoneunitwillnotjeopardizethecapabilityoftheremainingstandby'ieselgeneratorstostartandruntherequiredshutdownsystemandengineeredsafetyfeatureloads.A125-Vemergencydcpowersystemfeedsallsafety-relateddcprotection,controlandinstrumentationloads,andsafety-relateddcmotorsundernormaloperationoftheplantaswellasduringemergencyconditions.Thesystemisdividedintothreeredundantdivisionseachconsistingofitsownbattery,primaryandbackupbatterychargers,switchgears/motorcontrolcenters,anddistributionpanels.Eachdivisionfeedsdcloadsassociatedwithcorrespondingdivisionsofthesafety-relatedelectricpowerdistributionsystem.Batteriesandbatterychargersareredundantandfeedseparateloadgroupsthroughseparateandisolateddistributionsystems,andfailureofanyoneunitwillnotjeopardizethecapabilityofremainingunitstofeedassociatedloads.1.2.9'8StandbyLiquidControlSystemAlthoughnotintendedtoprovidepromptreactorshutdown,asthecontrolrodsare,theSLCSprovidesaredundant,independent,andalternatewaytobringthenuclearfissionreactiontosubcriticalityandtomaintainsubcriticalityasthereactorcools.Thesystemmakespossibleanorderlyandsafeshutdownintheeventthatnotenoughcontrolrodscanbeinsertedintothereactorcoretoaccomplishshutdowninth'enormalmanner.Thesystemissizedtocounteractthepositivereactivityeffectfromratedpowertothecoldshutdowncondition.1.2.9.19SafeShutdownfromOutsidetheControlRoomIntheeventthatthecontrolroombecomesinaccessible,thereactorcanbebroughtfrompowerrangeoperationtocoldshutdownconditionsbyuseofneccessarycontrolslocatedintheremoteshutdownroom.1.2.9.20MainControlRoomHeating,VentilatingandAirConditioningSystemThemaincontrolroomHVACsystemprovidesandmaintainsanenvironmentnecessaryforthesafetyandcomfortofcontrolroompersonnelduringshutdownoftheplantandintheeventofaLOCA.1.2.9.21RedundantReactivityControlSystemTheredundantreactivitycontrolsystem(RRCS)determinesifthereisanexistingtransientthatexceedscertainRPVAmendment231.2-33December1985 NineMilePointUnit2FSARpressureandwate'rlevelparametersandimmediatelyactivatesATWSpreventionequipment.,Ifthelogichasdetermined,thatacontrolledshutdownisnotoccurring,theRRCSactivatesATWSmitigationequipment..Amendment181.2-33aMarch1985 NineMilePointUnit2FSARTHISPAGEINTENTiONALLYBLANKAmendment181.2-33bMarch1985 NineMilePointUnit2FSAR1.2.10CoolingWaterandAuxiliarySystemsChapter9providesadetaileddiscussionofthesesystems.1.2.10.1ReactorBuildingClosedLoopCoolingWaterSystemTheRBCLCWsystemisademineralizedwater,closed-circuitheattransfersystemthatconsistsofthree50-percentcapacitypumpsandheatexchangers,alongwithappropriatecontrolsandinstrumentationtoensureadequatecoolingcapacityforreactorplantauxiliarysystemsandcomponentsduringnormalplantoperations'eatremovedfromcomponentsbytheRBCLCWsystemistransferred,totheservicewatersystem.1.2.10'TurbineBuildingClosedLoopCoolingWaterSystemTheTBCLCWsystemisademineralizedwater,closed-circuitheattransfersystemthatconsistsofthree50-percentcapacitypumpsandheatexchangers,alongwithappropriatecontrolsandinstrumentationtoensureadequatecoolingcapacityfortheturbinebuildingandradwastebuildingauxiliarysystemsandcomponents,duringnormalplantoperation.HeatremovedfromcomponentsbytheTBCLCWwatersystemistransferredtotheservicewatersystem.1.2.10.3ServiceWaterSystemTheservicewatersyst:emprovidescoolingwatertovariousessentialandnonessentialcomponentsthroughouttheplant.Essentialcomponentsareservicedbytwo100-percentredundantsubsystems.T2;enonessentialcomponentswillbeautomaticallyisolateduponreceiptofaLOCAsignalcoincidentwithalossofoffsitepower.TheservicewaterpumpstaketheirsuctionfromLakeOntarioviathescreenwellcomplexandintaketunnels.Afterpassingthrough'hesystem,thedischargeisreturnedtothelakeandtothecirculatingwatersystemasmakeup.1.2.10.4UltimateHeat,SinkTheultimateheatsinkisLakeOntario,whichprovideswatertotheintake/dischargetunnelsandisavailableatthescreenwellbuildingforplantuse.1.2.10.5PlantChilledWaterSystemTheplantchilledwatersystemconsistsoftwosubsystems,oneservingtheturbine,normalswitchgear,andradwastebuildings,andoneservingthecontrolbuilding.The1.2-34 NineMilePointUnit2FSARsubsystemsprovidespacecoolingbydistributingchilledwaterthroughcoolingcoilslocatedinairmovingunits.Thecontrolbuildingsubsystemisanessentialsystemdesignedtoprovidechilledwaterforcoolingduringallmodesofplantoperation.Eachsubsystemcontainsmechanicalrefrigerationwaterchillers,circulationpumps,pipingvalves,coolingcoils,accessories,instrumentation,andcontrols.1.2.10.6Heating,Ventilating,andAirConditioningSystemsIndividualheating,ventilating,andairconditioningsystemsareprovidedthroughouttheplanttomaintainindoortemperatureandhumiditydesignconditionsasrequiredforoptimumperformanceofplantequipmentand,whereapplicable,forhumancomfort.1.2.10.7ProcessSamplingTheprocesssamplingsystemconsistsofthereactorplant,turbineplant,andradwastesamplingsubsystems.Thesesubsystemsarecomposedofthenecessarypiping,valves,coolers,instrumentation,andanalyzerstodrawandanalyzesamplesofvariousplantprocessstreams.Representativesamplesaretakenautomaticallyand/ormanuallyforonlineandlaboratoryanalysesofpH,conductivity,turbidity,oxygen,hydrogen,gaseousactivity,fissionproductactivity,dissolvedgasconcentration,andvariousmetallicconcentrations(suchascopper,iron,andsilica).'1.2.10.8CondensateMakeupandDrawoffSystemThecondensatemakeupanddrawoffsystemconsistsoftwostoragetanks,piping,andinstrumentation.Itreceivesdrawoffwaterfromandsuppliesmakeupwatertothemaincondenserandfuelpool,andprovidesmakeupofreactorcoolantinventoryfortheRCICandHPCSsystems.Waterinthecondensatestoragetanksisreplenishedfromthemakeupwatertreatmentsystem.1.2.10.9WaterTreatmentandMakeupWaterSystemsThewatertreatmentsystemiscomposedofawaterfilter,anactivatedcarbonfilter,an'acidexchangerunit,a'orced-draftdegasifier,abaseanionexchanger,andamixed-bedionexchangedemineralizer.Thesystem'purifieslakewatersuppliedfromtheservicewatersystemanddeliversittothedemineralizedwaterstoragetanks.1.2-35 NineMilePointUnit2FSARThemakeupwatersystemprovidesdemineralizedmakeupwaterfromthestoragetanksforthepowerconversionsystemandtheTBCLCWandRBCLCWsystems.Inaddition,themakeupwatersystemsatisfiesvariousmiscellaneousplantrequirementsfordemineralizedwater,includingthesuppressionpoolandthespentfuelpool.1.2'0.10DomesticWaterandSanitaryDrainsandDisposalSystemsDomesticWaterSstemDomesticwaterfordrinkingandtosatisfytheflowandpressurerequirementsofallinstalledplumbingfixturesissuppliedfromanexistingcitymain.WaterqualityisinaccordancewithapplicablestandardspromulgatedbytheStateofNewYork.SanitarDrainsandDisosalSstemRawsanitarywastefromUnit2isdirectedtotheNineMilePointUnit1sanitarywastetreatmentplant.Thisplantconformstoallapplicablelocal,state,andfederaldischargelimitations.1.2.10.11CompressedAirSystemsThecompressedairsystemsarecomposedofaserviceandinstrumentairsystemandabreathingairsystem.ServiceandInstrumentAirSstemThreeaircompressors,eachdischargingthroughanaftercooler,afilter,andanairreceiverintoacommonheader,supplyalltheserviceandinstrument.airrequiredbytheplant.Theserviceairistakendirectlyfromthecommonheader.Theinstrumentairispassedthroughoneoftwo100-percentcapacityairdryersandthenthroughoneoftwo100-percentcapacityairfiltersbeforedeliverytothevariousplantinstruments.BreathinAirSstemAsingleaircompressordischargesthroughanaftercoolertoareceiver.AirfromthisreceiverisfilteredtocomplywithOSHArequirementsforbreathingair.1.2-36 NineNilePointUnit2FSAR1.2.10.12AuxiliarySteamSystemAnauxiliarysteamsystemfurnishesaseparateandindependentsteamsupply.Processsteam.isgeneratedinhighvoltage,electrodeboilersanddistributdthroughouttheplantbyanauxiliarysteamheader.Auxiliarysteamisrequiredformainturbineshaftsealingsteamduringstartupandfortheradwastebuildingduringplantshutdown.1.2.10.13StandbyDieselGeneratorFuelOilStorageandTransferSystemThestandbydieselgeneratorfueloilstorageandtransfersystemsuppliesfueloilforoperationofthestandbydieselgenerators.Thissystemisanessentialsystemandiscapableofsupplyingfueloilduringallmodesofplantoperation,includinglossofoffsitepowercoincidentwithaLOCA.1.2..10.14FireProtectionSystemThefireprotectionsystemconsistsoffirehydrants,hosestations,andautomaticsprinkleranddelugesystems.Whererequired,automaticormanuallyactuatedcarbondioxide,foam,orHalonfiresuppressionsystemsareprovided.Automaticfiredetectorsareprovidedinselectedareas.Portablefireextinguishersandfirehosereelsarelocatedthroughouttheplant.1.2.10.15CommunicationSystemsThestationcommunicationsystemsaredesignedtoprovidereliablecommunicationbetweenallessentialareasofthestationandtolocationsremotefromthestationduringnormalandemergencyconditionsandundermaximumpotentialnoiselevels.Thisisachievedthroughfivedifferentcommunicationsystemsasfollows:1.Adialtelephonesystemforvoicecommunicationbetweenselected-officeareasandselectedlocationsinsideandoutsidethestation.Thedialtelephonesystemisconnectedtothetelephonetiesystemforoffsitecommunicationincludingcommunicationwithlocallawenforcementauthoritiesandthelocalfiredepartment.2.AportableradiocommunicationsystemforcommunicationbetweenstationpersonnelandNNPCpersonnellocatedoutsidethestationincasethedialtelephonesystembetweenthestationandthe1.2-37 NineMilePointUnit2FSARpointsoutsidethestationbecomesinoperable.Theradiosarepoweredbyrechargeablebatteriesandareindependentofanyelectricalsystemoftheplant.3.Apageparty/publicaddress(PP/PA)communicationsystemwithfivepartychannelsandonepagechannelforcommunicationbetweenallbuildingsandlocationswithintheplant,evenunderextremelynoisyconditions.Thisisalso-usedfortheemergencyalarmandevacuationsystemandispoweredfromanuninterruptiblepowersupply(UPS).Aseparate.maintenanceandcalibrationcommunication(M/CC)systemforuseinareasrequiringcommunicationfortesting,instrumentcalibration,maintenance,andforuseduringconstructionandstartup.5.OneofthechannelsoftheM/CCsystemiscapableofbeingoperatedasasound-poweredcommunication(SPC)system.ThissystemcanbeusedincaseofatotallossofelectricpowertothePP/PAandM/CCsystems.ThissystemrequiresnoplantelectricpowerandworksthroughM/CCsystemwiring.Thedesignofthecommunicationsystemspermitsroutinesurveillanceandtestingwithoutdisruptingnormalcommunicationfacilities.Thepagingsystemiselectrically.supervised,permittingimmediatecorrectiveactiontobetakenifthelinebecomesinoperative.1.2.10.16TightingSystemsThestationlightingsystemsaredesignedto-provideadequatelightinginallnecessaryareasofthestationduringbothemergencyandnormaloperatingconditions.Thisisachievedthroughthefollowinglightingsubsystems:1.Normalstationlightingsystem.2~Emergencylightingsystem.3.Essentiallightingsystem.4.Egresslightingsystem.Thenormalstationlightingsystemprovidesadequatelightinginallareasofthestationundernormaloperatingconditions.Thisisfedfromthestationnormal600-Vload1.2-38 NineMilePointUnit2FSARcentersthroughthemainlightingdry-typedistributiontransformers,panels.distributionpanels,andsubdistributionTheemergencylightingsystemprovidesadequatelightingrequiredforoperatingthesafety-relatedequipmentduringemergencyconditionsinthecontrolroom,dieselgeneratorrooms,emergency'switchgearareas,andrelayandcomputerroom.ThisistreatedasaClass1Esystemexceptforthelightingfixtures.Thelightingfixturesareseismicallysupported.Theemergencylightingsystemisdividedinto'threeseparatedivisionscorrespondingtoDivisionsI,II,andIIIoftheplantemergencyacdistributionsystemandisfedfromthecorrespondingClass1Eloadcenters/motorcontrolcentersthroughthemainlightingdistributionpanels,.dry-typedistributiontransformers,andsubdistributionpanels.Incaseofalossofoffsitepower,theemergencylightingsystemisfedfromthestandbydieselgeneratorsthroughmanuallyoperatedcircuitbreakers.Theemergencylightingsystemfixturesareconstantlyenergized.Theessentiallightingsystemprovidespartiallightingforcertaincri'ticalareasofthestationrequiringcontinuouslightingsuchasthecontrolroom,relayandcomputerroom,standbydieselgeneratorrooms,andemergencyswitchgearrooms'heessentiallightingsystemreceivespowerfromthestationnormalUPSsystemandisfedthroughdry-typedistributiontransformersandsubdistributionpanels.TheessentiallightingfixturespoweredbytheUPSsystemareconstantlyenergized.Theegresslightingsystemprovidesadequatelightingforallegresssignsinsidetheplant.ThisisdesignedasaseparatesystemspecificallyfortheinsidebuildingegressemergencyconditionsinaccordancewithOSHArequirements.TheegresslightingsystemreceivespowerfromthestationnormalUPSsystemaspartoftheessentiallightingdistributionsystem.Theegresslightingfixturesareconstantlyenergized.The8-hrbatterypacklightingprovidesilluminationinallareasrequiredforoperationofanysafeshutdownequipmentandinaccessandegressroutestheretoincaseofafire.23Fluorescent,incandescent,andhighpressuresodiumlampsareusedforstationlighting.Fluorescentlampsareusedforallofficesandformostoftheoperatingareassuchasthecontrolroom,relayandcomputerroom,andemergencyandnormalswitchgearrooms.Incandescentlampsareusedintheprimarycontainment,primarycontainmentaccesshatches,mainsteamtunnel,newfuelstoragevault,spentfuelpoolfilterroom,andinallotherareaswherelightingisinfrequentlyrequired.HighpressuresodiumlampsareusedAmendment231.2-39December198S NineMilePoint.Unit2FSARforallhighbaylightingsuchasintheturbinebuildingandreactorbuildinggeneralareas.1.2-40 NineMilePointUnit2FSAR1.2.llReferencesNiagaraMohawkPowerCorporation.PreliminarySafetyAnalysisReport,VolumeI,NineMilePointNuclearStation-Unit2,June1972.2.3.NiagaraMohawkPowerCorporation.(ConstructionPermitStage),NineStation-Unit2,June1972.IOswegoCountyPlanningBoard.Plan,August1976.EnvironmentalReportMilePointNuclearPreliminaryLandUseGulf6WesternTopicalReport.GGW-FSD2538,NuclearMainSteamIsolationValveSystems,January1979.5.GeneralElectricLicensingTopicalReport.GeneralElectricStandardApplicationforReactorFuel.NEDE-24011-P-A(latestapprovedrevision)~6~GeneralElectricLicensingTopicalReport.GeneralElectricStandardApplicationforReactorFuel(U.STSupplement),NEDE-24011-P-A-US(latestapprovedr'evision).Amendment211.2-41September1985}}

Latest revision as of 12:01, 9 January 2025

Forwards Rev 5 to Updated SAR Nine Mile Point Nuclear Station Unit 2 & Nine Mile Point Unit 2 Safety Evaluation Summary Rept 1993
ML17059A086
Person / Time
Site: Nine Mile Point 
Issue date: 10/29/1993
From: Sylvia B
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059A087 List:
References
NMP2L-1448, NUDOCS 9311040048
Download: ML17059A086 (266)
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