ML17059A086

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 R NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17059A087	List: ML17059A086 ML17059A088
References
NMP2L-1448, NUDOCS 9311040048
Download: ML17059A086 (266)

Text

NUNINEEARLEPOINTATION-UNIT2

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER6PageT=TableF=Ficture Amendment NumberPageT=TableF=Ficrure Amendment NumberPageT=TableAmendment FF=icFureNumber6-i6-ii6-iii6-iv6-v6-vi6-vii6-viii6-1x6-x6-xa6-xb6-xi6-xii6-xiii6x1v6-xiva6-xivb6-xv6-xvi6-xvii6-xviii6-xix6-xixa6-xixb6-xx6-xxi6-xxii6-xxiia6-xxiib6-xxiii6'-l6.1-26.1-36'-46.1-4a6.1-4b6.1-56.1-6T6.1-1T6.1-1T6'-2T6.1-2T6.1-3S111Sh2Sb1Sh2R04R03A24R03R04ROOROOA24A24ROOROOA11ROOA24A24A24A24A17A15R02A24A27R03R04R04A24A24A24A24A24R04A27A27R02R04A03A03A28A28A27A28ROOROOR046.2-16.2-26.2-2a6.2-2b6.2-36.2-46.2-56.2-6'6.2-6a6.2-6b6.2-76.2-86.2-96.2-106.2-116.2-126.2-136.2-146.2-156.2-15a6.2-15b6.2-166.2-176.2-186.2-196.2-206.2-216.2-226.2-236.2-246.2-24a6.2-24b6.2-24c6.2-24d6.2-256.2-25a6.2-25b6.2-266.2-276.2-286.2-296.2-306.2-30a6.2-30b6.2-316.2-32AOOA07ROOA07AOOAOOA23ROOA23ROOR03ROOA23AOOROOAOOAOOAOOROOROOROOROOAOOROOAOOAOOAOOAOOROOA20A18ROOROOA17ROOROOROOROOA05A05AOOAOOAllA11AOOAOO6.2-336.2-33a6.2-33b6.2-346.2-356.2-35a62-35b6.2-366.2-376.2-37a6.2-37b6.2-386.2-396.2-406.2-416.2-426.2-436.2-43a6.2-43b6.2-446.2-456.2-466.2-46a6.2-46b6.2-476.2-47a6.2-47b6.2-486.2-496.2-506.2-516.2-51a6.2-51b6.2-526.2-536.2-53a6.2-53b6.2-546.2-54a6.2-54b6.2-556.2-55a6.2-55b6.2-55c6.2-55d6.2-56ROOROOROOA11A23A05A05ROOA23ROOROOR02R03R03R04R03R03R01ROOA15ROOROOR04R04R04A05A05A15ROOROOA27A25A13A27R01A08A08ROOROOA27A21A27R01ROOROOA18USARRevision4EP6-1October1992

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER6PageT=Table~FiureAmendment NumberPageT=TableAmendment F=FicFFre NumberPageT=TableAmendment

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NineMilePointUnit2FSARLISTOFEFFECTIVE CHAPTER7PAGESPageT=TableFFicFureAmendment NumberPageT=TableF=Ficrure Amendment NumberPageT=TableAmendment F=FicFure Number7i7-ii7-iii7-iV7-V7-Vi7-Vii7-viia7-viib7-Viii71X7X7-Xi7-Xii7'-17e11a7.1-1b7~127~137~1-47.1-57.1-5a7.1-5b7.1-67.1-6a7.1-6b7.1-6c7.1-6d7~177~17a7.1-7b7'-8T7~11T7.1-1T7.1-1T7.1-2T7.1-2T7~12T7~13T7~13T7~1-3T7.1-3T7~13T7.1-4T7.1-4Sh1Sh2Sh3Sh1Sh2Sh3Sh1Sh2Sh3Sh4Sh5Sh1Sh2ROOA24R04ROOROOROOR03ROOA24ROOR04A24R03R03R04ROOROOROOA18AOOROOROOROOROOROOROOROOROOR04R02R02R02AOOA09A18A28A18A28A24A24ROOR02ROOR04ROO7e217~227~237~23a7.2-3b7.2-47'-57'-67~277.2-87.2-97.2-107~2117'-127e2137~213a7.2-13b7'13c7~213d7.2-147'-157.2-167~2177.2-187.2-197.2-207.2-217~222T7.2-1T7.2-2T7'-2T7.2-2T7~22T7.2-2T7.2-2T7~22T7~22T7.2-2T7~22T7.2-2T7~22T7~22T7~22T7.2-2T7~22T7~22Sh1Sh2-Sh3Sh4Sh5Sh6Sh7Sh8Sh9Sh10Sh11Sh12Sh13Sh14Sh15Sh16Sh17A23ROOROOROOA26A09AOOR04AOOA09AOOR01R03R01R01ROOROOROOROOR01AOOAOOAOOA09A09AOOROOROOR01ROOROOROOROOROOROOROOROOROOROOROOROOROOROOROOROOROOT7'-2F7.2-1F7.2-1F7.2-1F7.2-1F7.2-17~317~327~337.3-47.3-57.3-67~377~37a7.3-7b7.3-87.3-97.3-9a7.3-9b7.3-107~3117~3127~3137~313a7.3-13b7.3-147.3-157.3-167.3-16a7.3-16b7~3177;3-187.3-197.3-19a7.3-19b7.3-207~3217~3227e322a7.3-22b7~3237.3-247.3-257.3-267.3-26aShShShShShSh1812345ROOA23A23ROOR01A23AOOA23R01R02R01A26A25A25A09R01A23A13A13AOOROOA23A09A09A09ROOA09A28A18A18A28A28R04ROOA09R01R04R01ROOROOR04R03A26R04R01USARRevision4EP7-1October1992

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-~z NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER7PageT=TableAmendment F=FicFureNumberPageT=TableAmendment F=FicFureNumberPageT=TableF=FicFure Amendment NumberF7.6-6ShF7.6-6ShF7.6-6ShF7.6-6ShF7.6-6ShF7.6-7F7.6-8F7.6-9ShF7.6-9ShF7.6-9ShF7.6-9ShF7'-9ShF7'-9ShF7.6-9ShF7.6-9ShF7.6-9ShF7.6-9Sh7~717~71a7.7-1b7'727~737.7-47.7-57'-67~777.7-87.7-97'-107~7117~7127~7137.7-147.7-157'-167~7177~717a7.7-17b7.7-187.7-197.7-207~7217e721a7.7-2lb7~722A23A23A23A23A23A27A27A23A23A23A23A23R01A23A23A23ROOR04A10A10AOOA10AOOR03AOOR03A27R01R03AOOR03A27AOOAOOR01R03R03R03AOOROOROOROOA18A18A187~722a7.7-22b7~7237.7-247.7-24a7.7-24b7.7-257.7-267~7277~727a7.7-27b7.7-287.7-297.7-307~7317~7327~7337.7-347.7-357.7-367~7377~737a7.7-37b7.7-387.7-397.7-39a7.7-39b7;7-407.7-417.7-42T7~71T7~72T7.7-3Sh1T7.7-3Sh2F7.7-1Sh1F7.7-1Sh2F7.7-1Sh3F7.7-1Sh4F7.7-1Sh5F7.7-1Sh6F7.7-1Sh7F7.7-2Sh1F7.7-2Sh2F7.7-2Sh3F7.7-2Sh4F7.7-2Sh5A27A10ROOR01R01A14A10R03A23A23A23AOOA23ROOROOA14AOOAOOA09R03R04R03R03A10A26A26A26A10A10R03A10A10A10AOOROOR03A23R03A23ROOR03R03R03R03R03A23F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7'-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7'-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7.7-2F7'-2F7.7-2F7'-2F7.7-3F7.7-4F7.7-5F7.7-6F7.7-6F7.7-6F7.7-6F7.7-6F7.7-6F7.7-6F7.7-7F7.7-8F7'-9F7.7-10App7ASh6Sh7Sh8Sh9Sh10Sh11Sh12Sh13Sh14Sh15Sh16Sh17Sh18Sh19Sh20Sh21Sh22Sh23Sh24Sh25Sh26Sh27Sh28Sh29Sh30Sh31Sh32Sh33Sh34Sh35shShShShShShShR03A23R03R03A23A23A23R04R04A23A23A23A23A23A23A23A23R03R04R03R03A23R03A23A23R03A23A23A23R03AOOA10AOOA23A23ROOROOA23ROOROOROOR03AOOROOROOUSARRevision4EP7-4October1992 H

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NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER10PageT=TableAmendment F=Ficrure NumberPageT=TableFF=icFureAmendment NumberPageT=TableAmendment FFicrureNumber10-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

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER10PageT=TableF=Ficpure Amendment NumberPageT=TableF=FicFure Amendment NumberPageT=TableF=FicFure Amendment Number10.4-17b10.4-1810.4-1910.4-19a10.4-19b10.4-2010.4-2110.4-2210.4-2310.4-23a10.4-23b10.4-2410.4-2510.4-25a10.4-25b10.4-2610.4-26a10.4-26b10.4-2710.4-2810.4-28a10.4-28b10.4-2910.4-3010.4-3110.4-3210.4-3310.4-33a10.4-33b10.4-3410.4-34a10.4-34b10'-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

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER11PageT=TableAmendment g"=Figure NumberPageT=TableAmendment PageT=TableAmendment F=FicFure Number11-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 NineMilePointUnit2FSARLISTOFEFFECTIVE CHAPTER11PAGESPageT=TableAmendment F=FicFure NumberPagePageT=TableAmendment T=TableAmendment F=FicFure NumberF=FicFure NumberT114-3Sh4T11.4-3Sh5T11.4-4Sh1T11.4-4Sh2T11.4-5T11.4-6T11.4-7F11.4-1aF11.4-1bF11.4-1cF11.4-1dF11.4-1eF11.4-1fF11.4-1gF11.4-1h11.5-111.5-211.5-2a11.5-2b11.5-311.5-3a11.5-3b11.5411.5-511.5-5a11.5-5b11.5-611.5-711.5-811.5-911.5-1011.5-10a11.5-10b11.5.-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 NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER12PageT=TableF=FBFureAmendment NumberPageT=TableF=FicFure Amendment NumberPageT=TableAmendment F=FicFure Number12-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=R01R01R01ROOA07ROOROOA11AOOAOO12~3312.3-412.3-512.3-612~3712~37a12.3-7b12.3-812.3-912.3-1012.3-1112.3-11a1 12.3-11b1 12.3-11a12.3-11b12.3-11c12.3-11d12.3-11e12.3-11f12.3-1212.3-1312.3-1412.3-1512.3-15a12.3-15b12.3-1612.3-1712.3-1812.3-1912.3-2012.3-21123-2212e32312.3-23a12'-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~

NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER12PageT=TableF=FicFure Amendment NumberPageT=TableF=FicFure Amendment NumberPageT=TableAmendment F=FicFure Number12.3-31b12~33212~333T12'-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~

NineMilePaintUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER12PagePagePageT=Table.Amendment T=TableAmendment, T=TableAmendment F=FicFure NumberF~FicFure NumberF=FicFure Number12.5-20T12.5-1T12.5-2T12.5-3T12.5-4A26R01ROOA05A01USARRevision4EP12-3October1992

~t NineMilePointUnit2FSARLISTOFEFFECTIVE PAGESCHAPTER13PageT=TableF=FictureAmendment NumberPageT=TableAmendment FFicrureNumberPageT=TableAmendment F=FicFure Number13-i131113-iii13-iv13-iva13-ivb13-v13-vi13-vii13-viii13~1113.1-213.1-2a13.1-2b13'-313'-3a13.1-3b131-413.1-4a13.1-4b13.1-513.1-5a13.1-5b13.1-6T13'-1T13.1-2T13'-3T1301-3T13.1-3T1301-3T13.1-3T13.1-3T13'-3T13.1-3T13~13T13~1-3T13.1-4T131-4T13.1-4T13.1-4T13.1-4T13.1-5F13.1-1F13.1-1aF13.1-2ShShshShShShShshshShShShshShSh1234567891012345ROOROOROOR03ROOA09R04ROOR03R03A28R03R03A09R03R03A09ROOROOA01R03R03A09A28R03R04R04R04R04R03R03R03R03R03R03R04R03R03R03R03R03A28R03R03R03F13'-3F13.1-3aF13.1-4F13.1-4aF13.1-5F13.1-5aF13.1-5bF13.1-6F13.1-7F13'-8F13.1-9F13.1-1013~2113.2-21302-313.2-413.2-513.2-613~2713.2-813.2-913.2-1013.2-1113.2-1213~21313.2-1413.2-1513.2-1613.2-1713.2-1813.2-1913.2-2013.2-2113.2-2213~22313.2-2413.2-2513.2-2613.2-2713.2-2813.2-2913.2-3013'-3113.2-3213'-33R04R03R03R03R03A13R03R03R03R03R03R03R03ROOROOROOR03ROOR03ROOR03R03R03R03ROOR03R03R03R03R03R03R03R03R03R03R03R03R03R03R03R03ROOR03ROOR0313.2-3413.2-3513.2-3613~23713.2-3813.2-3913'-40T13'-1F13.2-113~3113~3213.4-113.4-213.4-2a13.4-2b13.4-313.4-4T13.4-1T13.4-2ShT13.4-2ShT13.4-2ShT13.4-3ShT13.4-3ShT13.4-3ShF13.4-113.5-113.5-213.5-313.5-3a13.5-3b13.5-413.5-4a13.5-4b13.5-513.5-613.5-7T13.5-1ShT13.5-1ShT13.5-2T13.5-3.sh T13.5-3ShT13'-3ShT13.5-4ROOROOROOROOR03R03ROOROOA28ROOROOR03R04R04R03R04ROO.R03ROOR03R03R03R03R03R04R03R03R03R03A06R03A06.A06R03R03R03R03R03R03R03R03R03R03USARRevision4EP13-1October1992 r

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EDFKTYININEMILEPOINTNUCLEARSTATION-UNIT27NIAGARAUMOHAWKVOL.1

NineMilePointUnit2FSARTABLEOFCONTENTS(Cont)Section5.35.4Appendixes CHAPTER66.16.26.36.46.56.6Appendixes CHAPTER77.17'7.37.47.57'7~7Appendixes CHAPTER88.18.28.3Appendix8ACHAPTER9TitleReactorVesselComponent andSubsystem Design5Ag5BENGINEERED SAFETYFEATURESEngineered SafetyFeatureMaterials Containment Systems'mergency CoreCoolingSystemsHabitability SystemsFissionProductRemovalandControlSystemsInservice Inspection ofSafetyClass2andClass3Components through6CINSTRUMENTATION ANDCONTROLSYSTEMSIntroduction ReactorProtection (Trip)System(RPS)Instrumentation andControlsEngineered SafetyFeatureSystemsSystemsRequiredforSafeShutdownSafety-Related DisplayInstrumentation AllOtherInstrumentation SystemsRequiredforSafetyControlSystemsNotRequiredforSafety7Ag7BELECTRICPOWERIntroduction OffsitePowerSystemOnsitePowerSystemAUXILIARY SYSTEMSVolume1313131313141515151515151515161616161616161616,1717I179.19.29.39.49.5Appendixes FuelStorageandHandlingWaterSystemsProcessAuxiliaries AirConditioning, Heating,Cooling,andVentilation SystemsOtherAuxiliary Systems9Ag9C17181920,2121,22IUSARRevisionApril1989 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd)SectionTitleVolumeCHAPTER10STEAMANDPOWERCONVERSION SYSTEM2310.110.210.310.4SummaryDescription TurbineGenerator MainSteamSupplySystemOtherFeaturesofSteamandPowerConversion System232324CHAPTER11RADIOACTIVE WASTEMANAGEMENT 2411.111.211.311.411.5Appendix11ASourceTermsLiquidWasteManagement SystemsGaseousWasteManagement SystemsSolidWasteManagement SystemProcessandEffluentRadiological Monitoring andSamplingSystems242425252525CHAPTER12RADIATION PROTECTION 2512.112.212.3EnsuringThatOccupational Radiation Exposures AreAsLowAsReasonably Achievable (ALARA)Radiation SourcesRadiation Protection DesignFeaturesDoseAssessment Radiation Protection Program2525252626CHAPTER13CONDUCTOFOPERATIONS 2613.113.213.313.413.513.6Appendix13AOrganizational Structure ofApplicant TrainingSiteEmergency PlanOperation ReviewandAuditPlantProcedures Industrial Security26262626262626CHAPTER14INITIALTESTPROGRAM2614.1SpecificInformation ToBeIncludedinPreliminary SafetyAnalysisReport(PSAR)26USARRevisionivOctober1991 NineMilePointUnit2FSARTABLEOFCONTENTS(Cont'd)SectionTitleVolume14.2CHAPTER15SpecificInformation ToBeIncludedinFinalSafetyAnalysisReport(FSAR)ACCIDENTANALYSIS26r272715.015.1GeneralDecreaseinReactorCoolantTemperature 15.2IncreaseinReactorPressure15.3DecreaseinReactorCoolantSystemFlowRate15.4Reactivity andPowerDistribution Anomalies 15.5IncreaseinReactorCoolantInventory 15.6DecreaseinReactorCoolantInventory 15.7Radioactive ReleaseFromSubsystems orComponents 15.8Anticipated Transients withoutScram(ATWS)Appendices 15Athrough15H27272727272727272728CHAPTER16CHAPTER1717.017.117.2CHAPTER18TECHNICAL SPECIFICATIONS QUALITYASSURANCE Introduction QualityAssurance ProgramDuringOperation QualityAssurance ProgramDuringtheOperations PhaseHUMANFACTORSENGINEERING/SAFETY P2QMMETER DISPLAYSYSTEM28282828282818.118.2APPENDIXADetailedControlRoomDesignReviewSafetyParameter DisplaySystemRELOADANALYSIS282828USARRevision3October1991

NineMilePointUnit2FSARCHAPTER1INTRODUCTION ANDGENERALDESCRIPTION OFPLANTTABLEOFCONTENTSSectionTitleINTRODUCTION Pacae1.1-11.21.2.11.2.11.2.11.2.11.F11.2.11.2.11.2.1.1.2.2.1.3.3.1.3.2.3.31.2.1.3.8 1.2.21.2:2.11.2.2.21.2.2.31.2.31.2.41.2.4.11.2.4.21.2'.31.2.4.41.2.4.51.2.4.61.2.51.2.5.11.2.5.21~2'.31.2.1~3.41.2.1.3.5 1.2.1.3.6 1.'2.1.3.7 GENERALPLANTDESCRIPTION Principal DesignCriteriaGeneralCriteriaPowerGeneration DesignCriteriaSafetyDesignCriteriaSystem-by-System ApproachNuclearSystemCriteriaPowerConversion SystemsCriteriaElectrical PowerSystemsDesignCriteriaRadwasteSystemDesignCriteriaAuxiliary SystemsDesignCriteriaShielding andAccessControlDesignCriteriaNuclearSafetySystemsandEngineered Safeguards DesignCriteriaProcessControlSystemDesignCriteriaSiteDescription SiteCharacteristics:

SiteLocationandSizeAccesstotheSiteDescription oftheSiteandEnvironsStructures andEquipment NuclearSteamSupplySystemReactorCoreandControlRodsReactorVesselandInternals ReactorRecirculation SystemResidualHeatRemovalSystemReactorWaterCleanupSystemNuclearLeakDetection SystemElectrical, Instrumentation, andContr'olSystemsElectrical PowerSystemNuclearSystemProcessControlandInstrumentation PowerConversion SystemsProcessControlandInstrumentation 1~2-11~21l.2-11~231.2-41~2-71.2-71.2-81.2-91.2-91.2-91.2-91.2-101.2-101.2-121.2-121.2-121.2-131.2-131.2-151.2-151.2-161.2-171.2-171.2-171.2-181.2-181.2-181.2-201.2-21Amendment 24February1986 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont)Section1.21.21.21.21.21.2~6.7.7.1.7.2.7.3.7.41.21.21~21~21.21.21.2.8.8.1.8.2.8.3.8.4.8.5~8.61.21.21.21~2.8.7~8.8.8.9.91.21~21.21.21.21.21~21.21.21.2.9.1.9.2.9.3.9.4.9.5.9.6.9.7.9.8.9.9.9.101.21.21.2.9.11.9.12.9.131.2.9.141.2.9'51.2.9.181.2.9.161.2.9.17TitleRadioactive WasteSystemFuelHandlingandStorageSystemsNewFuelStorageSpentFuelStorageFuelHandlingSystemSpentFuelPoolCoolingandCleanupSystemPowerConversion SystemTurbineGenerator MainSteamSystemMainCondenser MainCondenser AirRemovalSystemTurbineGlandSealingSystemSteamBypassSystemandPressureControlSystemCirculating WaterSystemCondensate andFeedwater SystemsCondensate Demineralizer SystemNuclearSafetySystemsandEngineered

'SafetyFeaturesReactorProtection SystemNeutronMonitoring SystemControlRodDriveSystemControlRodDriveHousingSupportsControlRodVelocityLimiterNuclearSystemPressureReliefSystemReactorCoreIsolation CoolingSystemEmergency CoreCoolingSystemsContainment SystemsContainment andReactorVesselIsolation Control.SystemMainSteamIsolation ValvesMainSteamFlowRestrictors MainSteamRadiation Monitoring SystemResidualHeatRemovalSystemVentilation ExhaustRadiation Monitoring SystemStandbyGasTreatment SystemSafety-Related Electrical PowerSystemsStandbyLiquidControlSystemPa<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.2-311.2-311.2-321.2-321.2-321.2-33Amendment 241-iiFebruary1986 NineMilePointUnit2FSARCHAPTER1TABIEOFCONTENTS(Cont)Section1.2.9.191.2.9.201.2.9.211.2.101.2.10.11.2.10.21.2.10.31.2.10.41.2.10.51.2.10'1.2.10.71.2.10.81.2.10.91.2.10.10 1.2.10.11 1.2.10.12 1.2.10.13 1.2.10.14 1.2.10.15 1.2.10'61~2~111.31.3.11.3.21.3'1.41.4.11.4.21.4.31.4.4TitleSafeShutdownfromOutsidetheControlRoomMainControlRoomHeating,Ventilating andAirConditioning SystemRedundant Reactivity ControlSystemCoolingWaterandAuxiliary SystemsReactorBuildingClosedLoopCoolingWaterSystemTurbineBuildingClosedLoopCoolingWaterSystemServiceWaterSystemUltimateHeatSinkPlantChilledWaterSystemHeating,Ventilating, andAirConditioning SystemsProcessSamplingCondensate MakeupandDrawoffSystemWaterTreatment andMakeupWater'Systems DomesticWaterandSanitaryDrainsandDisposalSystemsCompressed AirSystemsAuxiliary SteamSystemStandbyDieselGenerator FuelOilStorage,andTransferSystemFireProtection SystemCommunication SystemsLightingSystemsReferences COMPARISON TABLESComparison withSimilarFacilityDesignsComparison ofFinalandPreliminary Information Reference IDENTIFICATION OFAGENTSANDCONTRACTORS Applicant Architect-Engineer NuclearSteamSupplySystemTurbineGenerator SupplierPa<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.3-1I1.4-11.4-11.4-21.4-31.4-4Amendment 241iiiFebruary1986 NineMilePointUnit2FSARCHAPTER1TABLEOFCONTENTS(Cont)Section1.4.51.4.6TitleTechnical Consultants Reference Pacae1.4-41.4-824241.51.5.11.5.1.11.5.1.21.5.1.31.5.1.41.5.1.51.5.21.5.31.61.71.7.11.7.21.81.91.101.11l.121.12,.11.12.21~13REQUIREMENTS FORFURTHERTECHNICAL INFORMATION CurrentBWRDevelopment ProgramsInstrumentation forVibration Detection CoreSprayDistribution CoreSprayandCoreFloodingHeatTransferEffectiveness Verification ofPressureSuppression DesignBoilingTransition TestingGeotechnical Investigations References MATERIALINCORPORATED BYREFERENCE DRAWINGSANDOTHERDETAILEDINFORMATION Electrical, Instrumentation,,and ControlDrawingsPipingandInstrumentation DrawingsCONFORMANCE TONRCREGULATORY GUIDESSTANDARDREVIEWPLANCONFORMANCE TOACCEPTANCE CRITERIAUNIT2RESPONSETOREGULATORY ISSUESRESULTING FROMTMIABBREVIATIONS ANDACRONYMSGENERICLICENSING ISSUESIntroduction Iicensing IssuesUNIT2POSITIONONUNRESOLVED SAFETYISSUES1.5-11.5-11.5-11.5-11.5-11.5-21.5-31.5-31.5-51.6-11.7-11.7-11.7-11.8-11.9-11.10-11.11-11;12-11.12-11.12-11.13-1Amendment 241-3.VFebruary1986 NineMilePointUnit2FSARCHAPTER,1INTRODUCTION ANDGENERALDESCRIPTION OFTHEPLANT

1.1INTRODUCTION

ThisFinalSafetyAnalysisReport(FSAR)issubmitted bytheNiagaraMohawkPowerCorporation (Applicant) anditsco-owners (CentralHudsonGasandElectricCorporation, LongIslandLightingCompany,NewYorkStateElectricandGasCorporation, andRochester GasandElectricCorporation) insupportoftheapplication foraClass103operating licensefor0henuclearpowerstationdesignated NineMilePointNuclearStation-Unit2(Unit2).Unit2islocatedona364-ha(900-acre) siteownedbyNiagaraMohawkPowerCorporation (NMPC),andissituatedonthesoutheast shoreofLakeOntario,OswegoCounty,NY,approximately 10km(6.2mi)northeast ofthecityofOswego.Unit,2andsupportfacilities occupyabout18.2ha(45acres),andsharethesitewiththeexistingUnit1(DocketNo.50-220)whichhasbeenincommercial operation since1969.,TheNineMilePointsiteisadjacenttotheJamesA.FitzPatrick NuclearPowerPlantownedbytheNYPA;Unit2islocated274m(900ft)eastofNine'MilePointUnit1andabout716m(2,350ft)westoftheJamesA.FitzPatrick Plant.Unit2employsanuclearsteamsupplysystem(NSSS)consisting ofasinglecycle,forcedcirculating boilingwaterreactor(BWR).Theplantratedcorethermalpowerlevel(Figure1.1-1-)is3,323MWtcorresponding toanetelectrical outputof1,080MWe,anddesignthermalpowerof3,463MWtcorresponding toagrosselectrical outputof1,202MWe.Thethermalpowerusedfortheplanttransient andloss-of-coolant

'accident (LOCA)analysesis3,463MWt.Allsafetysystemshavebeendesignedforathermalpower.of3,489MWt.TheNSSSsupplierisGeneralElectricCompany-NuclearEnergyOperations (GE-NEO).

Thebalanceoftheplantisdesignedandconstructed byStoneEcWebsterEngineering Corporation (SWEC).OtherplantsdesignedbySWECthataresimilarinconceptarecurrently underreviewbytheNuclearRegulatory Commission.

ThesearetheShorehamNuclearPowerStation,Brookhaven, LongIsland,NY,andtheRiverBendStation,St.Francisville, LA.Thecontainment designemploystheBWRMarkIIconceptofover-under pressuresuppression withmultiple,downcomers Amendment 191.1-1May1985 NineMilePointUnit2FSARconnecting thereactordrywelltothewater-filled pressuresuppression chamber.Theprimarycontainment,.-

is.asteel-lined, reinforced concreteenclosure housingthereactorandthesuppression pool.Thereactorbuildingcompletely enclosesthe.primarycontainment.

Thestructure providessecondary containment whentheprimarycontainment isclosedandinservice,andprovidesprimarycontainment whentheprimarycontainment isopen,asduringrefueling.

Thereactorbuildinghousestherefueling andreactorservicing equipment, newandspentfuelstoragefacilitie's,

'and--otherreactorauxiliary andserviceequipment.

Theprimarypurposeofthereactorbuildingistominimizeground.-level releaseofairborneradioactive material.

Theouterwallofthereactorbuildingisreinforced concreteuptothecraneraillevelabovetherefueling floor.Abovethecrane'ail level,thesuperstructure isasteelframeusingmetalwallpanelswithsealedjoints.Accesstothebuildingisthroughairlocks.

IIThepowergeneration complexincludesseveralcontiguous buildings:

thereactorbuildingwithtwoauxiliary bays,thecontrolbuilding, theturbinebuilding, andtheradwastebuilding.

Otherbuildings, suchasthesecurityfacility, are'lsolocatedinthegeneralplantarea.Ascreenwell forthecirculating andservicewatersystemsislocatedapproximately 107m(350ft)northwest ofthecenterline ofthereactorbuilding.

Condenser coolingforUnit2isprovidedfromacounterflow, natural-draft, hyperbolic, concretecooling,towerlocatedapproximately 330m(1,000ft)southofthecenterline ofthereactorbuilding.

Theultimateheat.sinkforemergency corecoolingisLakeOntario.Belowgradeandnorthofthescreenwell

building, therearetwoconcretetunnels'hatconveythe,servicewaterintake,servicewaterdischarge, andcoolingtowerblowdown.

Asafety-related intakepipeisenclosedin'eachtunnel.Theintakepipesextendfromtheintakeshaftapproximately 396m(1,300ft)northward underLakeOntariotothesubmerged intakestructures.

Onetunnelalsocontainsthedischarge pipewhichextendsapproximately 550m(1,800ft)tothedischarge diffuser.

Radionuclides areemittedtotheatmosphere fromtwolocations atUnit2.Thesearethestackandthecombinedventfortheradwaste-andreactorbuildings.

Fiquidradwasteisstoredfordecayorconcentrated toasolidwasteforcontrolled disposalatregulated storagesites.1~12 NineMilePointUnit2FSARTheshielding design'andplantlayoutarebasedonextensive experience ofNMPCandSWECincontrolling radiological exposures toaslowasreasonably achievable levels.Estimated radiological dosesfornormaloperations andpostulated accidents areallfractional partsofthedoseslistedinfederalradiological guidelines forsitingandoperation ofnuclearpowerplants.Environmental impactsaredescribed intheseparateEnvironmental ReportOperating LicenseStagebeingsubmitted forUnit2.ThisFSARiswritteninaccordance withRegulatory Guide1.70,StandardFormatandContentofSafetyAnalysisReportsforNuclearPowerPlants.ThecontentofthisFSARaddresses applicable regulatory guidesissueduptoJuly1982.TheUnit2Preliminary SafetyAnalysisReport(PSAR)wassubmitted onJune15,1972(DocketNo.50-410).TheNRCSafetyEvaluation ReportwasissuedonJune15,1973,andtheconstruction permit(CPPR-112) wasissuedonJune24,1974.Environmental impactsrelatedtotheplantarediscussed intheEnvironmental Report-Construction PermitStagesubmitted onJune15,1972.TheNRCFinalEnvironmental Statement wasissuedinJune1973.Theapproximate scheduleforUnit2fuelloadingandcommercial operation isasfollows:FuelloadingCommercial operation March1986October1986Amendment 241.1-3February1986 I

NineNilePointUnit2FSAR1.2GENERALPLANTDESCRIPTION 1.F1Principal DesignCriteriaTheprincipal architectural andengineering criteriaforthedesign,construction, andoperation ofUnit2aresummarized inthisSection.Therearetwowaysofconsidering principal designcriteria:

onaclassification-by-classification basis,oronasystem-by-system (systemgroup)basis.Safetyanalysesgenerally utilizetheinformation formatted intheclassification-by-classification approachbut/systemdescriptions aremoreeasilyunderstood throughthesystem-by-system method.Thissectionusesbothmethodsforsummarizing theprincipal designcriteria.

1.2.1.1GeneralCriteriaSomeofthecriteriaaregenerally applicable tomorethanoneclassification ormorethanonesystemgroup.Thesegeneralcriteriaareasfollows:Unit2isdesigned, fabricated, anderectedtoproduceelectricpowerinasafeand.reliablemanner.Unitdesigngenerally conformswithapplicable codesandregulations.

Exceptions areevaluated andjustified.

TheGeneralDesignCriteriaof10CFR50AppendixAhavebeensatisfied intheUnit2design.2.3.Unit2isdesigned, fabricated, anderectedtooperateinsuchawaythatthereleaseofradioactive materials totheenvironment islimitedtolessthanthelimitandguideline valuesofapplicable federalregulations pertaining tothereleaseofradioactive materials fornormaloperations andabnormalevents.Unit2isdesignedtosupportaGEboilingwaterreactor(BWR)andnuclearsteamsupplysystem(NSSS)toproducesteamfordirectuseinaturbinegenerator unit.Thisdesignincorporates

,features typicalofmanyotherBWRplants.4.Certainportionsoftheplantaredesignedtowithstand extremenaturalphenomena suchasearthquakes,

flooding, ortornadoes, andunnatural phenomena suchasfige,floodingfromin-plantleakage,internally orexternally generated

missiles, andothers.1.2-1 NineMilePointUnit2FSARThereactorcoreandreactivity controlsystemsaredesignedsothatcontrolrodactioniscapableofbringingthecoretosubcritical condition andmaintaining it,evenwiththerodofhighestreactivity worthfullywithdrawn andunavailable forinsertion.

Designmarginsforthenuclearsafetysystemsandengineered safeguards areconservative.

Nuclearabnormaldamage.environsmaterialAppendixsafetysystemsaredesignedtorespondtooperation transients toprecludefuel'nyfissionproductsreleasedtothevianormaldischarge pathsforradioactive willnotexceedthelimitsof10CFR50I.Nuclearsafetysystemsandengineered safeguards aredesignedtoassurethatnodamagetothereactorcoolantpressureboundary(RCPB)resultsfrominternalpressures causedbyabnormaloperational transients oraccidents.

Wherepositive, preciseactionisimmediately requiredinresponsetoaccidents, suchactionisautomatic andrequiresnodecisionormanipulation ofcontrolsbystationoperations personnel.

Essential safetyactionsarecarriedoutbysafety-related equipment ofsufficient redundancy andindependence sothatnosinglefailureofactivecomponents canpreventrequiredactions.Anysinglefailurewithinthesafety-related protection systemshalln'otpreventproperprotective actionatthesystemlevelwhenrequired.

Provisions havebeenmadeforcontrolofthecomponents ofnuclearsafetysystemsandengineered safeguards fromthecontrolroom.CNuclearsafetysystemsandengineered safeguards aredesignedtopermitdemonstration oftheirfunctional performance requirements.

Unit2featuresessential tothemitigation ofaccidentconsequences aredesigned, fabricated, anderectedtoqualitystandards thatreflecttheimportance ofthesafetyfunctiontobeperformed.

1.2-2 NineMilePointUnit2FSARI1.2'~2PowerGeneration DesignCriteriaPrincipal powergeneration designcriteriaareasfollows:1.Fuelcladding'designedtoretainintegrity asaradioactive materialbarrierthroughout thefulloperational rangeoftheplantandanyabnormaloperation transient.

Thefuelcladdingisdesignedtoaccommodate, withoutlossofintegrity, pressures generated byfissiongasesreleasedfromfuelmaterialthroughout thedesignlifeofthefuel.2.Heatremovalsystemsareprovidedinsufficient capacityandredundancy toremoveheatgenerated inthereactorcoreforthefullrangeofnormaloperating conditions fromplantshutdowntodesignpower,andalsoforanyabnormaloperational "transient.

Thecapacity'f suchsystemsisadequatetopreventfuelcladdingdamage.3.Backupheatremovalsystemsareprovidedtoremovedecayheatgenerated inthecoreundercircumstances wherenormaloperational heatremovalsystemshavebecomeinoperative.

Thecapacityofsuchsystemsisadequatetopreventfuelcladdingdamage.4Controlequipment isprovidedtoallowthereactortorespondautomatically tomajororminorloadchangesandotherabnormaloperational transients, including bringingthereactortoahotshutdowncondition.

5.Reactorpowerlevelismanuallycontrolled.

6.ControloftheNSSS,including thereactor,is'ossiblefromasinglelocation.

NSSSandreactorcontrols, including alarms,arearrangedtoallowtheoperatortorapidlyassessthecondition ofthenuclearsystemandlocateprocesssystemmalfunctions.

8.Fuelhandlingandstoragefacilities aredesignedtomaintainadequateshielding, cooling,andwaterqualityforspentfuelandtopreventinadvertent criticality.

Amendment 211.2-3September 1985 NineMilePointUnit2FSARInterlocks orotherautomatic equipment areprovidedasbackuptoprocedural controlstoavoidconditions requiring thefunctioning ofnuclearsafetysystemsorengineered safeguards.

SafetyDesignCriteriaThe.unitisdesigned, fabricated, anderectedtooperatesothatthereleaseofradioactive materials totheenvironment issignificantly lessthantherequirements of10CFR20or10CFR100.

ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrity asaradioactive barrierfollowing abnormaloperational transients oranaccidentevent.Thereactorcoreisdesignedsoitsnuclearcharacteristics do,notcontribute toadivergent powertransient.

TheNSSSandsupporting systemsaredesignedsothatthereisnotendencyfordivergent oscillation ofanyoperating characteristic, considering theinteraction ofthenuclearsystemwithotherappropriate unitsystems'aseous, liquid,andsolidwastedisposalfaci'lities aredesignedsothedischarge ofradioactive effluents andoffsiteshipmentofradioactive materials canbemadeinaccordance withapplicable regulations'esign oftheradwastesystemprovidesmeansbywhichUnit2operators canbealertedwhenlimitsonthereleaseofradioactive materialareapproached.

Sufficient indications areprovidedtodetermine thatthereactorisoperating withinthelimitsofapplicable regulations inanymodeofunitoperations.

Adequateradiation shielding isprovidedandaccesscontrolpatternsareestablished toallowaproperlytrainedoperating stafftocontrolradiation dosesto-alevelthatisaslowasreasonably achievable duringnormaloperation.

1.2-4 NineMilePointUnit2FSAREssential safetyactionsaredesignedtobecarriedoutbyequipment ofsufficient redundance andindependence thatnosinglefailurecanpreventtherequiredactions.Anysinglefailurewithintheprotection systemshallnotpreventproperactionatthesystemlevelwhenrequired.

Provisions aremadeforcontrolofthecomponents ofnuclearsafetysystemsfromthecontrolroom.Nuclearsafetysystemsaredesignedtodemonstrate functional performance requirements.

1Thedesignofnuclearsafetysystemsincludesdesignallowances forenvironmental disturbances atthesitesuchasearthquakes, floods,highwinds,stormsandotherdisturbances suchasfireandfloodingfromleakageoffluidsystems,internally andexternally generated

missiles, andothers.Standbyelectrical powersourcesareofsufficientcapacitytopowerall-necessary nuclearsafetysystemsrequiring electrical power.Standbyacanddcpowersourcesareprovidedtoremovedecayheatwhentheoffsitepowersupplyisnotavailable.

Engineered safeguards aredesignedtoassurethatnodamagetotheRCPBresultsfrominternalpressures causedbyanaccidentorabnormaltransient.

Aprimarycontainment isprovidedthatcompletely enclosesthereactorvessel.Theprimarycontainment usesthepressuresuppression concept.Theprimarycontainment isdesignedtoretainintegrity asaradioactive materialbarrierduringandfollowing accidents thatreleaseradioactive materialintotheprimarycontainment volume.Itispossibletotestprimary.containment integrity andleaktightness atperiodicintervals.

Areactorbuildingisprovidedthatcompletely enclosesboththeprimarycontainment andthefuelstorageareas.Thesecondary containment includesamethodforcontrolling releaseofradioactive materials fromthebarrierandincludesacapability forfiltering radioactive materials withinthebarrier.1.2-5 NineMilePointUnit2FSAR18.Thereactorbuildingisdesignedtoactasaradioactive materialbarrier,ifrequired, whentheprimarycontainment isopenforexpectedoperational purposes.

19.Theprimarycontainment andreactorbuilding, inconjunction withotherengineered safeguards, limitsradiological effectsofaccidents resulting inthereleaseofradioactive materialtotheprimarycontainment volumetosignificantly lessthantherequirements of10CFR100.

20.Provisions aremadeforremovingenergyfromwithintheprimarycontainment tomaintaintheintegrity oftheprimarycontainment systemfollowing accidents thatreleaseenergytotheprimarycontainment.

21.Pipingthatpenetrates theprimarycontainment structure andservesasapathfortheuncontrolled releaseofradioactive materialtotheenvironsisautomatically isolatedwheneversuchpotential forradioactive materialreleaseexists.Suchisolation iseffectedintimetolimitradiological effectstosignificantly lessthantherequirements of10CFR100.

22.Theemergency corecoolingsystem(ECCS)isprovidedtolimitfuelcladdingtemperature to2,200Fasaresultofaloss-of-coolant accident(IOCA).23.TheECCSprovidesforcontinuity ofcorecoolingoverthecompleterangeofpostulated breaksizesintheRCPB.24.TheECCSisdiverse,reliable, andredundant.

25.-Operation oftheECCSisinitiated automatically whenrequired,'regardless oftheavailability ofoffsitepower.26.Themaincontrolroomisshieldedagainstradiation topermitcontinued occupancy underaccidentconditions.

27.Intheeventthatthemaincontrolroombecomesuninhabitable, itispossibletobringthereactorfrompowerrangeoperation toacoldshutdown1.2-6 NineMilePointUnit2FSARcondition bymanipulating localcontrolsandequipment available outsidethemaincontrolroom.28.Backupreactorshutdowncapability isprovidedindependent ofnormalreactivity controlprovisions.

Thisbackupsystemshutsdownthereactorfromanynormaloperating condition andmaintains theshutdowncondition.

I1.2.1.3System-by-System ApproachTheprincipal architectural andengineering criteriafordesignaresummarized belowonasystem-by-system orsystem-group basis.Thesystem-by-system presentation facilitates understanding oftheactualdesignofanyonesystem.Onlythemostrestrictive ofanyrelatedcriteriaarestatedforasystem.Wherethemostrestrictive criterion isclassified asapowergeneration consideration, lessrestrictive safetycriteriamaynotbestatedinthesystem-by-system presentation.

However,theactualdesignofasystemmustreflectallcriteriathatpertaintoit.1.2.1.3.1 NuclearSystemCriteriaPrincipal designcriteriaforthereactor,ECCS,RCPB,andreactivity controlsystemsareasfollows:ThenuclearsystemisdesignedtosupportaGEBWRratedat3,323MWt.2.Fuelcladdingisdesignedtoretainintegrity asaradioactive materialbarrierthroughout thedesignpowerrange.Fuelcladdingisdesignedtoaccommodate, without.lossofintegrity, thepressures generated bythefissiongasesreleasedfromfuelmaterialthroughout thedesignlifeofthefuel.3.Fuelcladding, inconjunction withotherunitsystems,isdesignedtoretainintegrity throughout anyabnormaloperational transient.

ThoseportionsofthenuclearsystemthatformpartoftheRCPBaredesignedtoretainintegrity asaradioactive materialbarrierfollowing abnormaloperational transients andaccidents.

5.Heatremovalsystemsincluding theECCSandmakeupwatersuppliesareprovidedinsufficient

capacity, redundancy, andoperational adequacytoremoveheat1%27 NineMilePointUnit2FSARgenerated inthereactorcoreforthefullrangeofnormaloperational conditions fromunitshutdowntodesignpowerandforanyabnormaloperational transient oraccident.

Thecapacityofsuchsystemsisadequatetopreventfuelcladdingdamage.6.Thereactorcoreandreactivity controlsystemisdesignedto-ensurethatcontrolrodactioniscapableofbringingthecoresubcritical andmaintaining itthus,evenwiththerodofhighestreactivity worthfullywithdrawn andunavailable forinsertion.

Analternate reactivity controlsystemisprovidedshouldthecontrolrodsordrivesystembecomeinoperable.

Thealternate systemiscapableofshuttingdownthereactorandmaintaining itsubcritical.

7.Thereactorcoreis'designed sothat,itsnuclearcharacteristics donotcontribute to'divergent powertransient.

8.Thenuclearsystemisdesignedsothereisnotendencyfordivergent oscillation ofanyoperating characteristic, considering theinteraction ofthenuclearsystemwith'otherappropriate unitsystems.1.2.1.3.2 PowerConversion Systems.CriteriaComponents ofthepowerconversion systemsaredesignedtoperformthesebasicobjectives:

Reliablyproduceelectrical powerfromthesteamsuppliedbythereactor,condensethesteamintowater,andreturnthewatertothereactorasheatedfeedwater, withamajorportionofitsgaseousandparticulate impurities removed.2.Assurethatanyfissionproductsorradioactivity associated withthesteamandcondensate duringnormaloperation oraccidentconditions aresafelycontained withinthesystemorarereleasedundercontrolled conditions inaccordance withwastedisposalregulations.

1.2-8 NineMilePointUnit2FSAR1.2.1.3.3 Electrical PowerSystemsDesignCriteriaSufficient preferred andstandbyacanddcpowersourcesareprovidedtoattainpromptshutdownandcontinued maintenance oftheunitinasafecondition underallcrediblecircumstances.

Powersourcesareadequatetoaccomplish allrequiredengineered safeguard functions underpostulated designbasisaccidentconditions.

1.2.1.3.4 RadwasteSystemDesignCriteriaRadwastesystemsaredesignedtolimitreleaseofradioactive materials fromtheunitduringnormaloperation tosignificantly lessthantherequirements of10CFR20,andwithintheguidelines ofAppendixIto10CFRSO.Gaseous,liquid,,andsolidwastedisposalsystemsaredesignedsothatoffsiteshipments willbeinaccordance withapplicable regulations, including 10CFR20,10CFR71,and49CFR171through179,asappropriate.

3.Thedesignprovidesmeansbywhichunitoperations personnel canbealertedwheneveroperational limitsonthereleaseofradioactive materialareapproached.

1.2.1.3.5 Auxiliary SystemsDesignCriteriaAuxiliary systemsareprovidedtosupporttheNSSSandpowergeneration systemtoprovideformaintenance oftheplantenvironment, in-plantradiation andairbornecontamination control,compressed airsupplies, sealingsteam,etc.2.Essential auxiliary systemsaredesignedtofunctionduringaccidentconditions.

1.2.1.3.6Shielding andAccessControlDesignCriteriaRadiation shielding isprovidedandaccesscontrolpatternsareestablished toallowaproperlytrainedoperating stafftocontrolradiation doseswithinthelimitsofpublished regulations duringnormaloperation.

Shielding design,equipment layout,andzoninghavebeenperformed toensureradiation dosesaremaintained aslowasreasonably achievable.

1.2-9 NineNilePointUnit2FSAR2.Themaincontrolroomisshieldedagainst,radiation sothatinconjunction withthecontrolroomairconditioning systemoccupancy isallowedunderaccidentconditions.

1.2.1.3.7 NuclearSafetySystemsandEngineered Safeguards DesignCriteriaPrincipal designcriteriafornuclearsafetysystemsandengineered safeguards areasfollows:1.Thesecriteriacorrespond to10CFR50GeneralDesignCriteria1through64asdescribed inSection3.1.2~2.Standbyacanddcpowersourcesare,designedtohavesufficient capacitytopowerallnecessary nuclearsafetysystemsandengineered safeguards requiring electrical power.3.Standbyacpowersources-areprovidedtoallowreactorshutdownandremovalofdecayheatwhenoffsitepowerisnotavailable.

lntheeventthatthemaincontrolroomisuninhabitable, itispossibletobringthereactorfrompowerrangeoperation toacoldshutdowncondition byuseoftheshutdownroomormanipulating localcontrolsandequipment thatareavailable outsidethecontrolroom.5.Backupreactorshutdowncapability isprovidedindependently ofnormalreactivity controlprovisions.

Thisbackupsystemhasthecapability toshutdownthereactorfromanynormalorupsetoperating condition andsubsequently tomaintaintheshutdowncondition.

1.2.1.3.8ProcessControlSyst:emDesignCriteriaPrincipal designcriteriaforprocesscontrolsystemsarelistedasfollows:NSSSProcessControlDesinCriteria1.Controlequipment isprovidedtoallowthereactortorespondautomatically toloadchangeswithindesignlimits.1.2-10 NineMilePointUnit2FSAR2.Controlsareprovidedtomanuallycontrolreactorpowerlevel.3.Controlofthenuclearsystemispossiblefrom-a--single"location.

Nuclearsystemsprocesscontrolsandalarmsarearrangedtoallowtheoperatortorapidlyassessthecondition ofthenuclearsystemandtolocateprocesssystemmalfunctions.

5.Interlocks orotherautomatic equipment areprovidedasabackuptoprocedural controlstoavoidconditions r'equiring actuation ofnuclearsafetysystemsorengineered safeguards.

PowerConversion SstemsProcessControlDesinCriteriaControlequipment isprovidedtocontrolreactorpressurethroughout itsoperating range.2.Theturbineiscapableofresponding automatically tominorchangesinload.3.,Thefeedwater systemiscontrolled tomaintainthewaterlevelinthereactorvesselattheoptimumlevelrange.4Controlofthepowerconversion equipment ispossiblefromonelocation.

5.Interlocks orother,automatic equipment areprovidedasabackuptoprocedural controlstoavoidconditions requiring theactuation ofnuclearsafetysystemsorengineered safeguards.

Electrical PowerSstemProcessControlDesinCriteriaThesafety-related (Class1E)electrical powersystemisdesignedasathree-division system,anytwooutofthreedivisions beingadequatetosafelyshutdowntheunit.2.Theprotection systemisdesignedtodetectandisolatefaultedequipment fromthesystemwithaminimumofdisturbance intheeventofanyfaultinthesystem.Amendment 211.2-11September 1985 NineMilePointUnit2FSAR3.Intheeventofalossofoffsitepowertheprotection systemisolatestheemergency busesfromtheoffsitesystemandinitiates thestartingofthestandbyacpowersources.4.IntheeventoflossofoffsitepowerandLOCAtheprotection systemisolatesthe:emergency busesfromtheoffsitesystemandthenormalelectrical system,andthestandbydieselgenerators arestartedandsequentially loadedbyaprogrammed controlsystemtoenergizeallsafety-related loads.5.Allelectrically-operated breakersarecontrollable fromthecontrolroom.6'.Meteringforgenerators, transformers, andotheressential circuitsisavailable inthecontrolroom.1.2.2SiteDescription 1.2.2.1SiteCharacteristics:

SiteLocationandSizeTheprojectsitecomprises approximately 364ha(900acres)andislocatedonthesouthshoreofLakeOntariointhetownofScriba,OswegoCounty,NY,onlandownedbytheNiagaraMohawkPowerCorporation (NMPC).TheNineMilePointNuclearStation-Unit2(Unit2)sharesthesitewithexistingUnit1;Unit2andsupportfacilities occupyabout18.2ha(45acres)ofthetotalsiteacreage.TheJamesA.FitzPatrick plant,ownedbytheNYPA,islocatedeastoftheprojectsite.Thecenterline-to-centerline distancebetweenUnit2andtheFitzPatrick plantreactorsisabout716m(2,350ft).ThedistancebetweentheNineMilePointUnit1andUnit2reactorcenterlines isabout274m(900ft).ThesiteplanisshownonFigure1.2-1.Allactivities atthesiteareunderthedirectcontrolofNMPC"'.1.2.2.2AccesstotheSiteTheprotected areaofthesiteisisolatedfromthesurrounding areabyfencing.Accesstothesiteiscontrolled atthegateofthemainentrancetotheplantbysecuritypersonnel.

Allothergatesarekeptlocked"'.

USARRevision41.2-12October1992 NineMilePointUnit2FSAR1~2.2.3Description oftheSiteandEnvironsMostofthelandimmediately tothesouthandwestofthesiteispastureorinactivefarmland.

Fortheregionwest,south,andeastofthesite,thecountryischaracterized byrollingterrainrisinggentlyupfromLakeOntariowhichliesimmediately tothenorthofthesite.Withinanapproximate 8-km(5-mi)radiusofUnit2,the1980population was3,468.Thepopulation forthissameareaisprojected tobe5,301in1990and7,213in2010.Thenearestdwellings areonLakeviewRoadapproximately 1.6km(1mi)fromthestation.TheOntarioBibleConference operatesasummercamponthelakefront adjacenttothewesternboundaryofthesite'swego, whichisthenearestcity,islocatedabout10km(6.2mi)southwest ofthesiteandhada1980population of19,793.Thenearestpopulation centerwithapopulation inexcessof25,000isthecityofSyracuse, approximately 53km(32.8mi)southeast ofthesite.Buffaloisapproximately 217km(135mi)westofthesite.Figure2.1-1showsthelocationofthesiterelativetothelargercitiesinNewYorkStatewhicharewithinthe80-km(50-mi)radiusofthesite.1.2.3Structures andEquipment Thebuildings andstructures essential tothesafeoperation andshutdownoftheplantaredesignedtowithstand extremeenvironmental andabnormalloadingconditions.

Thestructures and/orportionsthereofsodesignated aredesignedtoprovidetheprotection asrequiredfromtornadoes,

missiles, earthquakes, pipewhip,andinternalorexternalflooding.

Additional discussions ofdesignconsiderations arefoundinChapter3.Locations andorientation ofthestructures areshownonFigures1.2-1and1.2-2.Thegeneralarrangement ofpersonnel accessbetweenstructures isshownonFigures1.2-3through1.2-5.Thegeneralarrangement ofthemajorstructures andequipment isshownonFigures1.2-6through1.2-40.Theprincipal structures locatedatthesitearelistedbelowalongwiththebriefdescription ofthemajorequipment, withineachstructure.

Theprimarycontainment structure (Figures1.2-6'through 1.2-12)housesthereactorpressurevessel,reactor1.2-13 NineMilePointUnit,2FSARrecirculation pumpsandmotors,drywellcoolingsystemunit,coolers,safetyreliefvalves,accumulators, andotherequipment.

Thereactorbuildingandauxiliary bays(Figures-1.2-6throughl.2-12)enclosetheprimarycontainment structure.

Thesestructures housetheremaining portionsoftheNSSS,refueling andfuelstorageequipment, controlroddrive(CRD)hydraulic units,equipment forthereactorwatercleanupsystem(RWCU),equipment forthestandbyliquidcontrolsystem(SLCS),equipment forthereactorbuildingclosedloopcoolingwatersystem,andotherequipment.

Theradwastebuilding(Figures1.2-13and1.2-14)housesprimarily thetanksandequipment associated withtheliquidandsolidradwastesystems.Thecontrolbuilding(Figures1.2-15and1.2-16)housesthemaincontrolroom,standbyswitchgear, batteries andassociated instrumentation, cables,andequipment.

Thedieselgenerator building(Figures1.2-17and1.2-18)housesthreestandbydieselgenerators, dieseloilstoragetanks,andassociated controlsandinstrumentation.

Theturbinebuildingincluding heaterbay(Figures1'-19through1.2-25)housestheturbinegenerator, condensers, moistureseparator

reheater, condensate demineralizer system,feedwater heaters,steamjetairejectors, reactorfeedpumps,turbinebuildingclosedloopcoolingwatersystem,andmiscellaneous tanksandequipment tosupportthepowerconversion systemandotherrelatedsystems.Thescreenwell building(Figures1.2-26through1.2-28)housesthecirculating waterpumpsandtheservicewaterpumpswithassociated equipment andinstrumentation.

Theintakeanddischarge tunnelsandintakestructures (Figures1.2-29'and1.2-30)areusedfortransporting servicewatertoandfromthelake.Theintaketunnelsalsosupplymakeupwaterforthecirculating watersystem.Themainstack(Figure1.2-31)isusedtoprovideelevatedreleaseofgasesfromtheoff-gas,standbygastreatment, andothersystems.Theoff-gasregeneration andcondensate demineralizer rooms(Figures1.2-19through1.2-25)housethecatalytic recombiners, off-gasfilter,condensate demineralizer, andrelatedequipment.

1.2-14 NineMilePointUnit2FSARThenormalswitchgear building(Figures1.2-32and1.2-33)housesthenormalswitchgear andassociated equipment.

Theauxiliary boilerbuilding(Figure1.2-34),locatednorthofthescreenwell

building, housestheelectricboilersandaccessories tosupplysteamtotheplantduringshutdown.

Thestandbygastreatment buildingandrailroadaccessarea(Figures1~2-35and1.2-36)housethestandbygastreatment, filtersandassociated equipment andallowaccessforspentfuelshipping.

IThecondensate storagetankbuilding(Figure1.2-37)housesthecondensate storagetanksandassociated equipment.

Thenatural-draft coolingtower(Figures1.2-38and1.2-39)providesthenormalheat,sinkforheattransferred tothecirculating watersystemfromthemaincondensers.

Theauxiliary servicebuilding(Figures1.2-7and1.2-8),adjacenttothereactorbuilding, housestheHVACroomanddecontamination andshowerfacilities forpersonnel.

Thedecontamination area(Figures1.2-19through1.2-21,1.2-23,and1.2-24),immediately southoftheradwastebuilding, providesthefacilityfordecontamination oflargetoolsandequipment, andasampleroom.Italsohousescleansteamreboilers andrelatedequipment.

Thehydrogenstoragearea(forhydrogencoolingoftheturbinegenerator, Figure1.2-40)islocatedwestoftheoff-gasarea.Thehydrogenstoragebottlesaremountedonconcrete.padsandareinafencedarea.1.2.4NuclearSteamSupplySystemThenuclearsystemincludesadirect.-cycle, forcedcirculation, GEBWRthatproducessteamfordirectuseinthesteamturbine.Aheatbalanceshowingthemajorparameters ofthenuclearsystemforthewarranted powercondition isshownonFigure1.1-1.Thenuclearsteamsupplysystemisfurtherdiscussed inChapters4and5.1.2.4.1ReactorCoreandControlRodsThereactorfuelandcoredesignaredescribed inSe'ction2ofReference 5andSection1ofReference 6.Amendment 211.2-15September 1985 NineMilePointUnit2FSARExperience hasshownthatthecontrolrodsare.notsusceptible todistortion andhaveanaveragelifeexpectancy manytimestheresidence timeofafuelloading.1.2.4.2ReactorVesselandInternals Thereactorvesselcontainsthecoreandsupporting structures; thesteamseparators anddryers;thejetpumps;thecontrolrodguidetubes;thedistribution linesforthefeedwater, coresprays,andstandbyliquidcontrol;theincoreinstrumentation; andothercomponents.

Themainconnections tothevesselincludethesteamlines,coolantrecirculation lines,feedwater lines,CRDandincorenuclearinstrument

housings, corespraylines,residualheatremovallines,standbyliquidcontrolline,coredifferential pressureline,jetpumppressuresensinglines,andwaterlevelinstrumentation.

Thereactorvesselisdesignedandfabricated inaccordance withapplicable codesforapressureof1,250psig.Thenominaloperating pressureinthesteamspaceabovetheseparators is1,020psia.Thevesselisfabricated oflow-alloysteelandiscladinternally withstainless steel(exceptforthetopheadnozzlesandnozzleweldzoneswhichareunclad).Thereactorcoreiscooledbydemineralized waterthatentersthelowerportionofthecoreandboilsasitflowsupwardaroundthefuelrods.Thesteamleavingthecoreisdriedbysteamseparators anddryerslocatedintheupperportionofthe.reactorpressurevessel(RPV).Thesteamisthendirectedtotheturbinethroughthemainsteamline'.Eachsteamlinehastwoisolation valvesinseries,oneoneithersideoftheprimarycontainment barrier.Amendment 211.2-16September 1985 NineMilePointUnit2FSAR1.2.4.3ReactorRecirculation SystemThereactorrecirculation systemconsistsoftworecirculation pumploopsexternaltotheRPV.These,loopsprovidethepipingpathforthedrivingflowofwatertotheRPV~jetpumps.Eachexternalloopcontainsonehighcapacitymotor-driven recirculation pump,twomotor-operated maintenance valves,andonehydraulically operatedflowcontrolvalve.Thevariablepositionhydraulic flowcontrolvalveoperatesinconjunction withalow.frequency motorgenerator settocontrolreactorpowerlevelthroughtheeffectsof'coolant flowrateonmoderator void.content.ThejetpumpsareRPVinternals.

Theyprovideacontinuous internalcirculation pathforthemajorportionofthecorecoolantflow.Thejetpumpsarelocatedintheannularregionbetweenthecoreshroudandthevesselinnerwall.Anyrecirculation linebreakstillallowscorefloodingtoapproximately two-thirds ofthecoreheight,theleveloftheinletofthejetpumps.1.2.4.4ResidualHeatRemovalSystemTheresidual, heatremoval(RHR)systemisasystemofpumps,heatexchangers, andpipingthatfulfillsthefollowing functions:

1~Remove'sdecayandsensibleheatduringandafterplantshutdown.

2.InjectswaterintotheRPVfollowing aLOCAtorefloodthe,coreindependently ofothercore.coolingsystems.3.Removesheatfromtheprimarycontainment following aLOCA,tolimittheincreaseinprimarycontainment pressure.

Thisisaccomplished bycoolingandrecirculating" thesuppres'sion poolwater.andbysprayingthedrywellandsuppression poolairspaceswithsuppression poolwater.1.2.4.5ReactorWaterCleanupSystemTheRWCUsystemrecirculates aportionofreactorcoolantthroughafilter-demineralizer toremoveparticulate anddissolved.

impurities fromthe.reactorcoolant.Italsoremovesexcesscoolantfromthereactorsystemundercontrolled conditions.

1.2-17 NineMilePointUnit2FSAR1.2.4.6NuclearLeakDetection SystemThenuclearleakdetection andmonitoring systemconsistsoftemperature,

pressure, flow,andfission-product sensorswithassociated instrumentation andalarms.Thissystemdetectsandannunciates leakageinthefollowing.

systems:1~Mainsteamlines.2.Reactorwatercleanupsystem.3.Residualheatremovalsystem.4.Reactorcoreisolation cooling(RClC)system.5.Feedwater system.6.Emergency corecoolingsystems~7.Miscellaneous systems.Smallleaksgenerally aredetectedbymonitoring areatemperatures, radiation levels,anddcainsumpfillupandpumpoutrates.Largeleaksarealsodetectedbychangesinreactorwaterlevel,primarycontainment pressureandchangesinflowratesinprocesslines.1.2.5Electrical, Instrumentation, andControlSystems1.2.5.1Electrical PowerSystemTheplantelectrical powersystemconsistsoftheunitgenerator, theswitchyard, andtheunitauxiliary powerdistribution system.'ITheunitgenerator isconnected directlytothegenerator step-up.transformers andthenormalstationservicetransformer throughisolatedphasebusduct.Thegenerator step-uptransformers stepuptheoutputoftheunitgenerator from25kVtoanominal345-kVtransmission systemvoltage.Thenormalstationservicetransformer stepsdowntheunitgenerator voltagefrom25to13.8kVandprovidesanonsite(ac)powersourcetotheunitauxiliary power~distribution system.Theswitchyard hastwoseparateandindependent sections:

the345-kVswitchyard andthe115-kVswitchyard.

Theoutputofthegenerator step-up.transformers isconnected tothe345-kVswitchyard whichconnectstheunitAmendment 181.2-18March1985 NineMilePointUnit2FSARgenerator totheoutgoingtransmission system.-The115-kVswitchyard receivespowerfromtwoseparateoffsitepowersourcesthrough'wo physically andelectrically independent incomingcircuits.

'hetwocircuitsfeed'twoseparatereservestationservicetransformers andanauxiliary boilertransformer.

Thereser'vestationservicetransformers stepdowntheoffsitepowerfrom115to13.8and4.16kV,andprovidetwoindependent "offsitepowersourcesfortheunitauxiliary

-powerdistribution system.Theauxiliary boilertransformer stepsdowntheoffsitepowerfrom115to13.8and4.16kV.Its'3.8-kV windingsuppliespowertotheauxiliary boilerandassociated equipment; the4.16-kVtertiarywindingprovidesabackupsource'or theemergency 4.16-kVbuses.Theunitauxiliary powerdistribution systemfeedsallunitauxiliary loadsthrough13.8-kVswitchgear, 4.16-kVswitchgear, 600-Vloadcenters,600-Vmotorcontrolcenters,andvariousacanddcdistribution panels.Thesystemisdivided'into'nuclearnonsafety-related andnuclearsafety-relatedsystems.Thenuclearnonsafety-related auxiliary power'distribution systemfeedsallnon-Class 1Eunitauxiliary loads.'ndernormalplantoperating conditions, itisenergized fromthenormalstationservicetransformer..

During'-startupandnormalshutdownconditions, it.isenergized fromoffsitepowersourcesthroughreservestationservicetransformers' normal125-Vdcsystem,consisting ofbatteries, batterychargers, anddistribution panels,providesareliablesourceofpowerforprotection, control,andinstrumentation loadsanddcmotorsundernormalandemergency conditions oftheplant.Ai24-Vdcsystemprovides'areliablesourcefortheneutronmonitoring system.Thenuclearsafety-related auxiliary powerdistribution systemsuppliesallClass1Eunitauxiliary loads.Thissystemis,dividedintothreeindependent divisions.

DivisionIandDivisionIIareindependent redundant divisions andsupplyallnuclearsafety-related auxiliary loadsexceptthehighpressurecorespray(HPCS)system.TheHPCSsystem,andrelatedequipment aresuppliedbyDivision.III..Allthreedivisions arenormallyenergized fromtheoffsitepowersourcesthroughreservestationservicetransformers.

Theauxiliary boilertransformer canbeconnected manuallytoactasabackupsourceforeithertheDivisionIorDivisionIIsupply.Eachofthethreedivisions ofthenuclearsafety-related auxiliary powerdistribution systemshasitsownindependent standbydieselgenerator.

IntheeventofaLOCAand/or1.2-19 NineMilePointUnit2FSAR.lossofoffsitepower,eachdivisionisenergized fromits,,ownstandbydieselgenerator.

A125-Vemergency.

dcpower;systemfeedsallsafety-related dc,protection, control,andinstrumentation loadsandsafety-related dcmotorsundernormal.operation oftheplantaswellasduringemergency.

conditions.

,Thesystemisdividedintothree,independent divisions eachconsisting ofitsownbattery,primaryandbackupbatterychargers, switchgear, motorcontrolcenters,anddistribution panels.Eachdivisionfeedsthedc.loadsassociated withthe.corresponding divisions ofthenuclearsafety-related auxiliary powerdistribution system.tChapter8describes theelectrical, powersystemindetail.1.2.5.2NuclearSystemProcessControlandInstrumentation ReactorManualControlSstemThereactormanualcontrolsystem(RMCS)providesthemeansbywhichcontrolrodsarepositioned fromthecontrolroomforpowercontrol.Thesystemoperatesvalvesineachhydraulic controlunittochangecontrolrodposition.

Onecontrolrodcanbemanipulated atatime.TheRMCSincludesthelogicthatrestricts abnormalcontrolrodmovement(rodblock)undercertainconditions asabackuptoprocedural controls.

Recirculation FlowControlSstemPfDuringnormalpoweroperation, avariablepositiondischarge valveisused'tocontrolflow.Adjusting thisvalvechangesthecoolantflowratethroughthecoreandtherebychangesthecorepowerlevel.NeutronMonitorin Sstem!'heneutronmonitoring system(NMS)isasystemofincoreneutrondetectors andout-of-core electronic monitoring equipment.

Thesystemprovidesindication ofneutronflux,which'anbecorrelated tothermalpowerlevelfortheentirerangeoffluxconditions thatcanexistinthecore.Thesourcerangemonitors(SRMs)andthe"intermediate rangemonitors(IRMs)providefluxlevelindications duringreactorstartupandlow-power operation.

Thelocalpowerrangemonitors(LPRMs)andaveragepowerrangemonitors(APRMs)allowassessment oflocalandoverallfluxconditions duringpowerrangeoperation.

Thetraversing incoreprobe(TIP)'systemprovidesa'eanstocalibrate theUSARRevision01.2-20April1989 NineMilePointUnit2FSARindividual LPRM.sensors.

TheNMSprovidesinputstotheRMCStoinitiaterodblocksifpresetfluxlimitsareexceeded, andinputstothereactorprotection systemtoinitiateascramifotherlimitsareexceeded.

RefuelinInterlocks Asystemofinterlocks thatrestrictmovementofrefueling equipment andcontrolrodswhenthereactorisintherefueling andstartupmodesisprovidedtopreventaninadvertent criticality duringrefueling operations.

Theinterlocks backupprocedural controlsthathavethesameobjective.

Theinterlocks affecttherefueling

platform, refueling platformhoists,fuelgrapple,andcontrolrods.ReactorVesselInstrumentation reactorvesselheadannProcessComuterSstemInadditiontoinstrumentation forthenuclearsafetysystemsandengineered safetyfeatures, instrumentation isprovidedtomonitorandtransmitinformation thatcanbeusedtoassessconditions existinginsidethereactorvesselandthephysicalcondition ofthevesselitself.Thisinstrumentation monitorsreactorvesselpressure, waterlevel,coolanttemperature, reactorcoredifferential

pressure, coolantflowrates,andersealringleakage.Anonlineprocesscomputerisprovidedtomonitorandlogprocessvariables andtomakecertainanalytical computations.

Thenuclearmeasurement analysisandcontrolrodworthminimizer (NUMACRNM)preventsrodwithdrawal underlow-power conditions iftherodtobewithdrawn isnotinaccordance withapreplanned pattern.Theeffectoftherodblockistolimitthereactivity worthofthecontrolrodsbyenforcing adherence tothepreplanned rodpattern.Chapter7describes thesesystemsindetail.1.2.5.3PowerConversion SystemsProcessControlandInstrumentation PressureRelatorandTurbineGenerator ControlThepressureregulator maintains controloftheturbinecontrolandturbinebypassvalvestoallowpropergenerator andreactorresponsetosystemload-demand changeswhilemaintaining thenuclearsystempressureessentially constant.

USARRevision31.2-21October1991 NineMilePointUnit2FSARTheturbinegenerator speed-load controlscaninitiaterapidclosureoftheturbinecontrolvalves(rapidopeningoftheturbinebypassvalves)topreventturbineoverspeed onlossofthegenerator electricload.Feedwater ControlSstemThefeedwater controlsystemautomatically controlstheflowoffeedwater intothereactorpressure.vesseltomaintainthewaterwithinthevesselatpredetermined levels.Athree-element controlsystem(mainsteamflowrate,feedwater flowrate,andreactorvesselwaterlevel)isusedtoaccomplish thisfunction.

Chapter10describes thesystemingreaterdetail.1.2.6Radioactive WasteSystemThedisposalofradioactive wastesfromthesiteismanagedbywastesystemsdesignedtomeetallapplicable regulatory

>9[requirements, including 10CFR20,10CFR60,10CFR61,GeneralDesignCriterion 60,andRegulatory Guide1.21.Therearethreeinterrelated radioactive wastetreatment systems:radioactive liquidwaste,radioactive gaseouswaste,andradioactive solidwaste.Thesesystemsaredescribed inChapter11.Theradioactive liquidwaste(LWS)systemcollectsandprocesses radioactive wasteliquidsgenerated duringplantoperation andrefueling, eitherforrecyclewithintheplantorfordischarge offsite.Theprocessoperations available totreattheliquidwastesarefiltration, evaporation, demineralization, anddecantation.

Processdescriptions andflowchartsillustrate thenumberandsequenceof.processing stepstobeappliedtoeachtypeofliquidwaste.Gaseousradwastefromthemaincondenser isprocessed througharecombiner toremovehydrogen, afterwhichthegasiscooled,thendried.Wastegasisthenpassedthroughacharcoalbedandfiltersystem,whichholdsupradioactive components andremovesparticulate matterbeforerelease.Contaminated drywellandbuildingventilation exhaustsareprocessed bythestandbygastreatment andventilation systems.Theradioactive solidwastesystemprovidesholdup,packaging, andstoragefacilities foreventualoffsiteshipmentandultimatedisposalofsolidradioactive wastematerial.

Theprocessoperations consistofvolumeAmendment 191.2-22May1985 NineMilePointUnit2FSARreduction andsolidification withasphaltofradioactive wastessuchasLWSevaporator concentrates, spentresins,andfiltersludges.Dryradioactive wastessuchascontaminated paper,clothing, andtoolsarecompacted andpackaged.

Afterprocessing, thesolidwastematerials arestoredforadditional decayandthen'shippedoffsiteforappropriate disposal.

Shielding, asrequiredduringtheprocessing andshipmentofthesolidwastes,isincludedintheplannedoperation ofthesolidwastesystem.Adescription andflowdiagramoftheprocessing andhandlingsequences forthesolidwastesgenerated onsiteisprovidedinChapter11.1.2'FuelHandlingandStorageSystems1.2.7'NewFuelStorageThenewfuelfacilityisdesignedtopreventinadvertent criticality andloadbucklingofthenewfuelassemblies.

BoththenewfuelstoragevaultandstorageracksaredesignedtocomplywithCategoryIrequirements.

Thenewfuelstoragevaultisdesignedwithsufficient drainagetoprecludeflooding.

Thevaultisalsoequippedwithamonitoring systemtowarnofradiation levelincreases abovenormaloperating conditions.

tThedesignofthenewfuelstoragerackslimitskeff50.90inthedrycondition andkeff60.95inafloodedcondition.

1.2.7.2SpentFuelStorageThespentfuelstorageracksaredesignedtomaintainspentfuelinaspacegeometrythatpreventscriticality innormalandabnormalconditions.

Theracksarecapableofwithstanding maximumupliftforcesgenerated withouteffectonthesubcritical array.Thedesignofthespentfuelrackswilllimitkeff50.95innormalandabnormalstorageconditions.

Thereissufficient shielding, acoolingsystem,andradiation monitoring topreventoverheating andexcessive personnel exposure.

Thespentfuelstoragepoolandracksarecorrosion resistant, andadheretoCategoryIrequirements.

1.2-23 NineMilePointUnit2FSAR1.2.7.3FuelHandlingSystemThefuelhandlingequipment includesthefollowing:

1.Fuelinspection stand.2~Fuelpreparation machine.3.125-toncrane.4.Refueling platform.

5~Generalpurposegrapple.6;Jibcranes.7.Otherrelatedtoolsforfuelandreactorservicing.

Allequipment conformstoapplicable codesandstandards.

1.2.7.4SpentFuelPoolCoolingandCleanupSystemThespentfuelcoolingandcleanup(SFC)systemprovidesremovalofdecayheatfromthestoredspentfuelandmaintains specified watertemperature, purity,clarity,andlevel.Thisprocesspreventsthespentfuelfromoverheating

'ndthebuildupofexcessive radioactive materials inthecoolingwater,therebyminimizing radiation levels.Thesystemincludes.

twoheatexchangers, eachofwhichiscapableofremovingthefulldecayheatfromanormalrefueling offloadofspentfuelsAcrossconnection totheRHRsystemprovidesadditional emergency backupcoolingandcoolingduringafullcoreoffload.Chapter'givesfurtherdetailsofthefuelhandlingandstoragesystem.1.2.8PowerConversion SystemChapter10providesadetaileddiscussion ofthefollowing equipment systems.1.2.8.1TurbineGenerator Theturbineisan1,800-rpm tandem-compound, six-flow, single-stage reheatunitwithanelectrohydraulic governorcontrol.Theturbinegenerator hasanemergency tripsystemforturbineoverspeed.

Theoutputoftheturbinegenerator Amendment 211.2-24September 1985 NineMilePointUnit2FSARis1,165,663kWeatturbineguarantee conditions with2.0inHgabsbackpressure and0percentmakeup.Thegenerator isadirectdriven,three-phase, 60-Hzt25)000Vf1,800-rpm hydrogeninner-cooled, synchronous generator ratedat1,348,400 kVAat0.90powerfactor,0.58short-circuit ratioatmaximumhydrogenpressureof75psig.1.2.8.2MainSteamSystemThemainsteamsystemdeliverssteamfromthenuclearboilersystemthroughfour26-/28-in ODsteamlinestotheturbinegenerator, turbinebypassvalves,steamjetairejectors, off-gaspreheaters, steamsealevaporator, andradwastesteamreboiler.

1.2.8.3MainCondenser Themaincondenser maintains

2.0 inHgabswhenoperating

atturbineguarantee conditions with67.97Fcirculating waterinlettemperature.

Thecondenser includesprovisions foraccepting steambypassedaroundtheturbinegenerator.

Deaeration ofcondensate isaccomplished inthecondenser.

1.2.8.4MainCondenser AirRemovalSystemThemaincondenser airremovalsystem,usingairejectorsfornormaloperation andvacuumhoggingpumpsforstartup,evacuates gasesfromthemainturbineandcondenser duringplantstartupandmaintains thecondenser essentially freeofgasesduringoperation.

Thissystemhandlesallinleakage ofnoncondensable gasesthroughtheturbineseals,condensate, feedwater, andsteamsystems,andnoncondensables thataregenerated inthereactorbydisassociation ofwater.1.2.8.5TurbineGlandSealingSystemTheturbineglandsealingsystemprovidesmildlyradioactive steamtothesealsoftheturbinethrottlevalvestemglandsandtheturbineshaftglands.Thesealingsteamissuppliedbyacleansteamreboilerusingcondensate.

Theunitauxiliary boilerprovidesanauxiliary steamsupplyforstartupandwhenreactorheatingsteamisnotavailable.

Thesteampackingexhauster collectsandcondenses theairandsteammixtureanddischarges theairandothernoncondensables totheplantexhaustducttotheatmosphere, usingamotor-driven exhauster.

USARRevision31.2-25October1991 NineMilePointUnit2FSAR1.2.8.6SteamBypassSystemandPressureControlSystemAturbinebypasssystemisprovidedwhichpassessteamdirectlytothemaincondenser undercontrolofthepressureregulator.

Steamisbypassedtothecondenser wheneverthereactorsteamingrateexceedstheloadpassedtotheturbinegenerator.

Thecapacityoftheturbinebypasssystemis25percentoftheturbineratedsteamflow.Thepressureregulation systemprovidesmainturbinecontrolvalveandbypassvalveflowdemandstomaintainanearlyconstantreactorpressureduringnormalplantoperation.

Italsoprovidesdemandstotherecirculation systemtoadjustpowerlevelsbychangingreactorrecirculation flowrates.l.2.8.7Circulating WaterSystemThecirculating watersystemprovidesthecondenser withacontinuous supplyofcoolingwater.Thecirculating watersystemisapumpedclosedloopsystemutilizing anair-cooled natural-draft coolingtowerasaheatsink.Sixone-sixth capacitycirculating waterpumpsareprovidedtopumpcoolingwaterfromthecoolingtowerbasinthroughthemaincondenser andbacktothetopofthecoolingtower.Makeupwaterisprovidedfrom?akeOntariobytheservicewatersystem.1.2.8.8Condensate andFeedwater SystemsThecondensate andfeedwater systemssupplycondensate fromthecondenser hotwelltotheRPV~Thecondensate ispumpedbytwoofthethreecondensate pumpsthroughthefullflowcondensate demineralizer system,theintercooler oftheairejectors, andthesteampackingexhauster tothecondensate boosterpumps.Thecondensate boosterpumpspumptheflowthroughthreestringsconsisting oftwodraincoolersandfivestagesoflowpressureheaterseach.Inaddition, threeheaterdrainpumpsprovideapproximately one-third ofthefeedwater flowrequirements.

Thelastlowpressureheatersdischarge tothesuctionofthreeparallelmotor-driven reactorfeedwater pumps.Thedischarge ofthereactorfeedwater pumpspassesthroughthreeone-third capacityparallelheatersandintotheRPV.Thefeedwater flowiscontrolled byvaryingthefeedwater flowcontrolvalveposition.

1.2.8.9Condensate Demineralizer SystemAfullflow,deepbedcondensate demineralizer systemcompletewithregeneration facilities, instrumentation, and1.2-26 NineMilePointUnit2FSARsemiautomatic controlsisdesignedtoensureaconstantsupplyofhighqualitywatertothereactor.1.2.9NuclearSafetySystemsandEngineered SafetyFeaturesChapters3,4,5,6,=7,9,and10givefurtherdetailsfor)iethefollowing equipment andsystems.1.2.9.1ReactorProtection SystemThereactorprotection system(RPS)initiates arapid,automatic shutdown(scram)ofthereactor.Itactsintimetopreventfuelcladdingdamageandanynuclearsystemprocessbarrierdamagefollowing abnormaloperational transients.

TheRPSoverrides alloperatoractionsandprocesscontrolsandisbasedonafail-safe designphilosophy thatallowsappropriate protective actionevenifasinglefailureoccurs.11.2.9.2NeutronMonitoring SystemTheneut"onmonitoring systemisasystemofincoreneutrondetectors andoat-of-core electronic monitoring equipment.

Thesystemprovidesindication ofneutronflux,whichcanbecorrelated tothermal-power levelfortheentirerangeofflu".conditions thatcanexistinthecore.TheSRMsandtneIRMsprovidefluxlev'el'indications duringreactorste.tupandlowpoweroperation.

TheLPRMsand~'iPRMsallowassessment oflocalandoverallfluxconditions duringpowerrangeoperation.

TheTIPsystemprovides=ameanstocalibrate theindividual LPRMsensors.TheNMSprovidesinputstotheRMCStoinitiaterodblocksifpresetfluxlimitsareexceeded, andinputstotheRPStoinitiateascramifotherlimitsareexceeded.

1.2.9'ControlRodDriveSystemWhenascramisinitiated bytheRPS,theCRDsysteminsertsnegativereactivity necessary toshutdownthereactor.Eachcontrolrodisindividually controlled by'ahydraulic controlunit(HCU).Whenascramsignalisreceived, highpressu're waterstoredinanaccumulator intheHCUorreactorpressureforcesthecontrol"rodintothecore.1.2.9.4ControlRodDriveHousingSupportsCRDhousingsupportsarelocatedunderneath thereactorvesselnearthecontrolrodhousings.

Thesupportslimitthetravelof'controlrodintheeventthatacontrolrodhousingisruptured.

ThesupportspreventanuclearAmendment 181.2<<27March1985 NineMilePointUnit2FSARexcursion asaresultofahousingfailureandthusprotectthefuelbarrier.1.2.9.5ControlRodVelocityLimiterAcontrolrodvelocitylimiterisattachedtoeachcontrolrodtolimitthevelocityatwhichacontrolrodcanfalloutofthecoreshoulditbecomedetachedfromtheCRD.Thisactionlimitstherateofreactivity insertion resulting fromaroddropaccident.

Thelimiterscontainnomovingparts.1.2.9'NuclearSystemPressureReliefSystemApressurereliefsyst:emconsisting ofsafety/relief valves(SRV),mounted onthemainsteamlinesisprovidedtopreventexcessive pressureinsidethenuclear.systemfromoperational transients oraccidents.

TheSRVdischarge steamisdirectedtothesuppression poolwithintheprimarycontainment.

1.2.9.7ReactorCoreIsolation CoolingSystemTheRCICsystemprovidesmakeupwatertotheRPVwhenthevesselisisolated.

TheRCICsystemusesasteam-driven turbine-pump unitandautomatically operatestomaintainadequatewaterlevelintheRPVforeventsdefinedinSection5.4.6.1.1.2.9.8Emergency CoreCoolingSystemsFourECCSsareprovidedtomaintainfuelcladdingbelowthetemperature.

limitin10CFR50.46 intheeventofabreachintheRCPBthatresultsinalossofreactorcoolant.Thesystemsareasfollows.HihPressureCoreSraHPCSTheHPCSsystemprovidesandmaintains anadequatecoolantinventory insidetheRPVtolimitfuelcladdingtemperatures intheeventofbreaksintheRCPB.Thesystemisinitiated byeitherhighpressureinthedrywellorlowwaterlevelinthevessel.Itoperatesindependently ofallothersystemsovertheentirerangeofpressuredifferences fromgreaterthannormaloperating pressuretozero.TheHPCScoolingdecreases vesselpressuretoenablethelowpressurecoolingsystemstofunction.

TheHPCSsystempumpmotorispoweredbyanonsitedieselgenerator if.offsitepowerisnotavailable.

ThesystemmayalsobeusedasabackupfortheRCICsystem.1.2-28 NineMilePointUnit2FSARAutomatic Deressurization SstemADSTheADSrapidlyreducesRPVpressureinaLOCAsituation inwhichtheHPCSsystemfailstomaintaintheRPVwaterlevel.Thedepressurization providedbythesystemenablesthelowpressureECCStodelivercoolingwatertotheRPV.TheADSusessomeofthereliefvalvesthatarepartofthenuclearsystempressurereliefsystem.Theautomatic reliefvalvesarearrangedtoopenonconditions indicating boththatabreakintheRCPBhasoccurredandthattheHPCSsystemisnotdelivering sufficient coolingwatertotheRPVtomaintainthewaterlevelaboveapreselected value.Setpointsarediscussed inSection5.2.2.TheADSisnotactivated unlesseitherthelowpressurecorespray(LPCS)orlowpressurecoolantinjection (LPCI)pumpsareoperating.

Thisistoensurethatadequatecoolantisavailable tomaintainreactorwaterlevelafterthedepressurization.

LowPressureCoreSraTheLPCSsystemconsistsofoneindependent pumpandvalvesandpipingtodelivercoolingwatertoasprayspargeroverthecore.Thesystemisactuatedbyeitherlowwaterlevelinthereactorvesselorhighpressureinthedrywell,but,waterisdelivered tothecoreonlyafterRPVpressure'isreduced.Thissystemprovidesthecapability tocoolthefuelbyspraying.

waterintoeachfuelchannel.TheLPCSloopfunctioning inconjunction withtheADSorHPCScanprovidesufficient fuelcladdingcoolingfollowing aLOCA.LowPressureCoolantInectionLPCIisanoperating modeoftheRHRsystem,butisdiscussed herebecausetheLPCImodeactsasanengineered safetyfeatureinconjunction withtheotherECCSs.LPCIusesthepumploopsoftheRHRtoinjectcoolingwaterintotheRPV.LPCIisactuatedbyeitherlowwaterlevelinthereactorvessel'or highpressureinthedrywell,butwaterisdelivered tothecoreonlyafterRPVpressureisreduced.LPCIoperation providesthecapability ofcorereflooding, following aLOCA,intimetomaintainthefuelcladdingbelowtheprescribed temperature limit.1.2.9.9Containment SystemsPrimarContainment Theprimarycontainment isaMarkIIdesignthatincor-poratesadrywellpressuresuppression systemandutilizesa1.2-29 NineNilePointUnit2FSARlargereservoir ofwatertofunctionasaheatsinktoabsorbenergy.1.Functional DesinTheprimarycontainment isasteellinedreinforced concretestructure.

Itconsistsofaconicaldrywellchamberaboveacylindrical suppression poolchamberseparated byadrywellfloor.Thisfloorcontainsapipingsystemwhichwoulddirectdrywellsteamintothesuppression chamberreservoir intheeventofaLOCA.2.HeatRemovalThecontainment heatremovalsystemissummarized inSection1.2.9.14.

3.Containment SraThecontainment spraysystemconsistsoftworedundant subsystems, eachwithitsownfull-capacity sprayheader.Eachsubsystem issuppliedfromaseparateredundant RHRsubsystem.

4.Combustible GasControlThecontainment combusti-blegascontrolsystemissummarized inSection6.2.5.1.2.9.10Containment andReactorVesselIsolation ControlSystemTheprimarycontainment andRPVisolation controlsystemautomatically initiates closureofisolation valvestocloseoffallprocesslinesthatarepotential leakagepathsforradioactive materialtotheenvirons.

Thisactionistakenuponindication ofabreachintheRCPB.1.2.9.11NainSteamIsolation Valves28Althoughallpipelines thatbothpenetrate theprimarycontainment andofferapotential releasepathforradioactive materialhaveredundant isolation capabilities, themainsteamlines,becauseoftheirlargesizeandlargemassflowrates,aregivenspecialisolation consideration.

Automatic isolation valvesareprovidedineachmainsteamline(MSIVs).Eachisclosedbyspringforceandpneumatic forceandopenedbypneumatic force.Thesevalvesfulfillthefollowing objectives:

Preventexcessive damagetothefuelbarrierbylimitingthelossofreactorcoolantfromtheRPVresulting fromeitheramajorleakfromthesteampipingoutsidetheprimarycontainment oraAmendment, 281.2-30Nay1987 NineMilePointUnit2FSARmalfunction ofthepressurecontrolsystemresulting inexcessive steamflowfromtheRPV.2.Limit,thereleaseofradioactive materials byisolating theRCPBincaseofagrossreleaseofradioactive materials fromthefueltothereactorcoolingwaterandsteam.3.Limitthereleaseofradioactive materials byclosingthecontainment barrierincaseofamajorleakfromthenuclearsysteminsidethecontainment.

1.2.9.12MainSteamFlowRestrictors Aventuri-type flowrestrictor isinstalled ineachsteamline.ThesedeviceslimitthelossofcoolantfromtheRPVbeforetheMSIVsareclosedincaseofamainsteamlinebreakoutsidethepr'imarycontainment.

1~2.9.13MainSteamRadiation Monitoring SystemThemainsteamradiation monitoring systemconsistsoffourgammaradiation monitorslocatedexternally tothemainsteamlinesjust.outsidetheprimarycontainment inthemainsteamtunnel.Themonitorsaredesignedtodetectagrossreleaseoffissionproductsfromthefuel.Ondetection ofhighradiation, thetripsignalsgenerated bythemonitorsareusedbytheRPStoinitiateareactorscramandtoclosetheMSIVs.1.2.9.14ResidualHeatRemovalSystemTheRHRsystemisplacedinoperation tolimitthetemperature ofthewaterinthesuppression'ool andoftheatmospheres inthedrywellandsuppression ch'amberfollowing adesignbasisLOCA,tocontrolthepooltemp'erature duringnormaloperation oftheSRVsandtheRCICsystem,andtoreducethepooltemperature following anisolation transient.

Inthecontainment coolingmodeofoperation, theRHRmainsystempumpstakesuctionfromthesuppression poolandpumpthewaterthroughtheRHR.heat.'e'xchangers Amendment 281.2-31May1987 NineMilePointUnit2FSARwherecoolingtakesplacebytransferring heattotheservicewater.Thecoolantisthendischarged backtothesuppression pool,thedrywellsprayheader,thesuppression chambersprayheader,ortheRPV.1.2.9.15Ventilation ExhaustRadiation Monitoring SystemPermanently installed processandarearadiation monitorsprovideindications andalarmsonairborneradiation inthereactorbuildingventilation system,drywellatmosphere, fuelstorageandrefueling areas,andcontrolroomatmosphere.

Additionally, connections areprovidedinthereactorbuildingventilation systemductworkforcontinuous airbornemonitors(CAMs).1,.2.9.16StandbyGasTreatment SystemThestandbygastreatment system(SGTS)processes exhaust.airfromvariousplantsystemstolimitthereleaseofairborneradioactivity, maintaining offsitedoseratesbelowthespecified limits.DuringadesignbasisaccidenttheSGTSsystemisautomatically actuated.

Whenhighradiation levelsaresensedinanyexhaustsystemconnected totheSGTSsystemitisautomatically placedinoperation.

TheSGTSconsistsoftwoidentical, parallelbutphysically separated airfiltertrainassemblies.

Each'ssemblyiscapableofhandlingthemaximumdesignairflowrate.1.2'.17Safety-Related Electrical PowerSystemsAstandbypowersupplysystemisprovidedfortheoperation ofemergency systemsandengineered safetyfeaturesduringandfollowing theshutdownofthereactorwhenthepreferred powersupplyisnotavailable.

Thestandbypowersupplysystemconsistsofthreestandbydieselgenerators.

Onegenerator isdedicated toeachofthethreedivisions ofthesafety-related electricpowerdistribution systemfeedingeach'lass 1Eloadgroup.Anytwoofthethreestandbydieselgenerators havesufficient, capacitytostartandsupplyallneededengineered safetyfeaturesandemergency shutdownloadsincaseofaLOCAand/orlossofoffsitepower.Thestandbydieselgenerator fueloilstoragetanksaresizedtoholda7-daysupplyoffueloilbasedontheenginerunningcontinuously atfullload.ALOCAand/orlossofoffsitepowersignalinitiates startofthestandbydieselgenerators andthegenerators pickuptheloadsinaprogrammed sequence.

Standbydieselgenerators areindependent, andfeedseparateloadgroupsthroughseparate, physically andelectrically isolateddistribution systems'.2-32 NineMilePointUnit2FSARFailureofanyoneunitwillnotjeopardize thecapability oftheremaining standby'iesel generators tostartandruntherequiredshutdownsystemandengineered safetyfeatureloads.A125-Vemergency dcpowersystemfeedsallsafety-related dcprotection, controlandinstrumentation loads,andsafety-related dcmotorsundernormaloperation oftheplantaswellasduringemergency conditions.

Thesystemisdividedintothreeredundant divisions eachconsisting ofitsownbattery,primaryandbackupbatterychargers, switchgears/motor controlcenters,anddistribution panels.Eachdivisionfeedsdcloadsassociated withcorresponding divisions ofthesafety-related electricpowerdistribution system.Batteries andbatterychargersareredundant andfeedseparateloadgroupsthroughseparateandisolateddistribution systems,andfailureofanyoneunitwillnotjeopardize thecapability ofremaining unitstofeedassociated loads.1.2.9'8StandbyLiquidControlSystemAlthoughnotintendedtoprovidepromptreactorshutdown, asthecontrolrodsare,theSLCSprovidesaredundant, independent, andalternate waytobringthenuclearfissionreactiontosubcriticality andtomaintainsubcriticality asthereactorcools.Thesystemmakespossibleanorderlyandsafeshutdownintheeventthatnotenoughcontrolrodscanbeinsertedintothereactorcoretoaccomplish shutdowninth'enormalmanner.Thesystemissizedtocounteract thepositivereactivity effectfromratedpowertothecoldshutdowncondition.

1.2.9.19SafeShutdownfromOutsidetheControlRoomIntheeventthatthecontrolroombecomesinaccessible, thereactorcanbebroughtfrompowerrangeoperation tocoldshutdownconditions byuseofneccessary controlslocatedintheremoteshutdownroom.1.2.9.20MainControlRoomHeating,Ventilating andAirConditioning SystemThemaincontrolroomHVACsystemprovidesandmaintains anenvironment necessary forthesafetyandcomfortofcontrolroompersonnel duringshutdownoftheplantandintheeventofaLOCA.1.2.9.21Redundant Reactivity ControlSystemTheredundant reactivity controlsystem(RRCS)determines ifthereisanexistingtransient thatexceedscertainRPVAmendment 231.2-33December1985 NineMilePointUnit2FSARpressureandwate'rlevelparameters andimmediately activates ATWSprevention equipment.

,Ifthelogichasdetermined, thatacontrolled shutdownisnotoccurring, theRRCSactivates ATWSmitigation equipment..

Amendment 181.2-33aMarch1985 NineMilePointUnit2FSARTHISPAGEINTENTiONALLY BLANKAmendment 181.2-33bMarch1985 NineMilePointUnit2FSAR1.2.10CoolingWaterandAuxiliary SystemsChapter9providesadetaileddiscussion ofthesesystems.1.2.10.1ReactorBuildingClosedLoopCoolingWaterSystemTheRBCLCWsystemisademineralized water,closed-circuit heattransfersystemthatconsistsofthree50-percent capacitypumpsandheatexchangers, alongwithappropriate controlsandinstrumentation toensureadequatecoolingcapacityforreactorplantauxiliary systemsandcomponents duringnormalplantoperations'eat removedfromcomponents bytheRBCLCWsystemistransferred, totheservicewatersystem.1.2.10'TurbineBuildingClosedLoopCoolingWaterSystemTheTBCLCWsystemisademineralized water,closed-circuit heattransfersystemthatconsistsofthree50-percent capacitypumpsandheatexchangers, alongwithappropriate controlsandinstrumentation toensureadequatecoolingcapacityfortheturbinebuildingandradwastebuildingauxiliary systemsandcomponents, duringnormalplantoperation.

Heatremovedfromcomponents bytheTBCLCWwatersystemistransferred totheservicewatersystem.1.2.10.3ServiceWaterSystemTheservicewatersyst:emprovidescoolingwatertovariousessential andnonessential components throughout theplant.Essential components areservicedbytwo100-percent redundant subsystems.

T2;enonessential components willbeautomatically isolateduponreceiptofaLOCAsignalcoincident withalossofoffsitepower.TheservicewaterpumpstaketheirsuctionfromLakeOntarioviathescreenwell complexandintaketunnels.Afterpassingthrough'hesystem,thedischarge isreturnedtothelakeandtothecirculating watersystemasmakeup.1.2.10.4UltimateHeat,SinkTheultimateheatsinkisLakeOntario,whichprovideswatertotheintake/discharge tunnelsandisavailable atthescreenwell buildingforplantuse.1.2.10.5PlantChilledWaterSystemTheplantchilledwatersystemconsistsoftwosubsystems, oneservingtheturbine,normalswitchgear, andradwastebuildings, andoneservingthecontrolbuilding.

The1.2-34 NineMilePointUnit2FSARsubsystems providespacecoolingbydistributing chilledwaterthroughcoolingcoilslocatedinairmovingunits.Thecontrolbuildingsubsystem isanessential systemdesignedtoprovidechilledwaterforcoolingduringallmodesofplantoperation.

Eachsubsystem containsmechanical refrigeration waterchillers, circulation pumps,pipingvalves,coolingcoils,accessories, instrumentation, andcontrols.

1.2.10.6Heating,Ventilating, andAirConditioning SystemsIndividual heating,ventilating, andairconditioning systemsareprovidedthroughout theplanttomaintainindoortemperature andhumiditydesignconditions asrequiredforoptimumperformance ofplantequipment and,whereapplicable, forhumancomfort.1.2.10.7ProcessSamplingTheprocesssamplingsystemconsistsofthereactorplant,turbineplant,andradwastesamplingsubsystems.

Thesesubsystems arecomposedofthenecessary piping,valves,coolers,instrumentation, andanalyzers todrawandanalyzesamplesofvariousplantprocessstreams.Representative samplesaretakenautomatically and/ormanuallyforonlineandlaboratory analysesofpH,conductivity, turbidity, oxygen,hydrogen, gaseousactivity, fissionproductactivity, dissolved gasconcentration, andvariousmetallicconcentrations (suchascopper,iron,andsilica).'1.2.10.8 Condensate MakeupandDrawoffSystemThecondensate makeupanddrawoffsystemconsistsoftwostoragetanks,piping,andinstrumentation.

Itreceivesdrawoffwaterfromandsuppliesmakeupwatertothemaincondenser andfuelpool,andprovidesmakeupofreactorcoolantinventory fortheRCICandHPCSsystems.Waterinthecondensate storagetanksisreplenished fromthemakeupwatertreatment system.1.2.10.9WaterTreatment andMakeupWaterSystemsThewatertreatment systemiscomposedofawaterfilter,anactivated carbonfilter,an'acidexchanger unit,a'orced-draftdegasifier, abaseanionexchanger, andamixed-bed ionexchangedemineralizer.

Thesystem'purifies lakewatersuppliedfromtheservicewatersystemanddeliversittothedemineralized waterstoragetanks.1.2-35 NineMilePointUnit2FSARThemakeupwatersystemprovidesdemineralized makeupwaterfromthestoragetanksforthepowerconversion systemandtheTBCLCWandRBCLCWsystems.Inaddition, themakeupwatersystemsatisfies variousmiscellaneous plantrequirements fordemineralized water,including thesuppression poolandthespentfuelpool.1.2'0.10DomesticWaterandSanitaryDrainsandDisposalSystemsDomesticWaterSstemDomesticwaterfordrinkingandtosatisfytheflowandpressurerequirements ofallinstalled plumbingfixturesissuppliedfromanexistingcitymain.Waterqualityisinaccordance withapplicable standards promulgated bytheStateofNewYork.SanitarDrainsandDisosalSstemRawsanitarywastefromUnit2isdirectedtotheNineMilePointUnit1sanitarywastetreatment plant.Thisplantconformstoallapplicable local,state,andfederaldischarge limitations.

1.2.10.11Compressed AirSystemsThecompressed airsystemsarecomposedofaserviceandinstrument airsystemandabreathing airsystem.ServiceandInstrument AirSstemThreeaircompressors, eachdischarging throughanaftercooler, afilter,andanairreceiverintoacommonheader,supplyalltheserviceandinstrument.

airrequiredbytheplant.Theserviceairistakendirectlyfromthecommonheader.Theinstrument airispassedthroughoneoftwo100-percent capacityairdryersandthenthroughoneoftwo100-percent capacityairfiltersbeforedeliverytothevariousplantinstruments.

BreathinAirSstemAsingleaircompressor discharges throughanaftercooler toareceiver.

AirfromthisreceiverisfilteredtocomplywithOSHArequirements forbreathing air.1.2-36 NineNilePointUnit2FSAR1.2.10.12Auxiliary SteamSystemAnauxiliary steamsystemfurnishes aseparateandindependent steamsupply.Processsteam.isgenerated inhighvoltage,electrode boilersanddistribut dthroughout theplantbyanauxiliary steamheader.Auxiliary steamisrequiredformainturbineshaftsealingsteamduringstartupandfortheradwastebuildingduringplantshutdown.

1.2.10.13 StandbyDieselGenerator FuelOilStorageandTransferSystemThestandbydieselgenerator fueloilstorageandtransfersystemsuppliesfueloilforoperation ofthestandbydieselgenerators.

Thissystemisanessential systemandiscapableofsupplying fueloilduringallmodesofplantoperation, including lossofoffsitepowercoincident withaLOCA.1.2..10.14 FireProtection SystemThefireprotection systemconsistsoffirehydrants, hosestations, andautomatic sprinkler anddelugesystems.Whererequired, automatic ormanuallyactuatedcarbondioxide,foam,orHalonfiresuppression systemsareprovided.

Automatic firedetectors areprovidedinselectedareas.Portablefireextinguishers andfirehosereelsarelocatedthroughout theplant.1.2.10.15Communication SystemsThestationcommunication systemsaredesignedtoprovidereliablecommunication betweenallessential areasofthestationandtolocations remotefromthestationduringnormalandemergency conditions andundermaximumpotential noiselevels.Thisisachievedthroughfivedifferent communication systemsasfollows:1.Adialtelephone systemforvoicecommunication betweenselected-officeareasandselectedlocations insideandoutsidethestation.Thedialtelephone systemisconnected tothetelephone tiesystemforoffsitecommunication including communication withlocallawenforcement authorities andthelocalfiredepartment.

2.Aportableradiocommunication systemforcommunication betweenstationpersonnel andNNPCpersonnel locatedoutsidethestationincasethedialtelephone systembetweenthestationandthe1.2-37 NineMilePointUnit2FSARpointsoutsidethestationbecomesinoperable.

Theradiosarepoweredbyrechargeable batteries andareindependent ofanyelectrical systemoftheplant.3.Apageparty/public address(PP/PA)communication systemwithfivepartychannelsandonepagechannelforcommunication betweenallbuildings andlocations withintheplant,evenunderextremely noisyconditions.

Thisisalso-usedfortheemergency alarmandevacuation systemandispoweredfromanuninterruptible powersupply(UPS).Aseparate.maintenance andcalibration communication (M/CC)systemforuseinareasrequiring communication fortesting,instrument calibration, maintenance, andforuseduringconstruction andstartup.5.OneofthechannelsoftheM/CCsystemiscapableofbeingoperatedasasound-powered communication (SPC)system.ThissystemcanbeusedincaseofatotallossofelectricpowertothePP/PAandM/CCsystems.ThissystemrequiresnoplantelectricpowerandworksthroughM/CCsystemwiring.Thedesignofthecommunication systemspermitsroutinesurveillance andtestingwithoutdisrupting normalcommunication facilities.

Thepagingsystemiselectrically

.supervised, permitting immediate corrective actiontobetakenifthelinebecomesinoperative.

1.2.10.16 TightingSystemsThestationlightingsystemsaredesignedto-provideadequatelightinginallnecessary areasofthestationduringbothemergency andnormaloperating conditions.

Thisisachievedthroughthefollowing lightingsubsystems:

1.Normalstationlightingsystem.2~Emergency lightingsystem.3.Essential lightingsystem.4.Egresslightingsystem.Thenormalstationlightingsystemprovidesadequatelightinginallareasofthestationundernormaloperating conditions.

Thisisfedfromthestationnormal600-Vload1.2-38 NineMilePointUnit2FSARcentersthroughthemainlightingdry-typedistribution transformers, panels.distribution panels,andsubdistribution Theemergency lightingsystemprovidesadequatelightingrequiredforoperating thesafety-related equipment duringemergency conditions inthecontrolroom,dieselgenerator rooms,emergency'switchgear areas,andrelayandcomputerroom.ThisistreatedasaClass1Esystemexceptforthelightingfixtures.

Thelightingfixturesareseismically supported.

Theemergency lightingsystemisdividedinto'threeseparatedivisions corresponding toDivisions I,II,andIIIoftheplantemergency acdistribution systemandisfedfromthecorresponding Class1Eloadcenters/motor controlcentersthroughthemainlightingdistribution panels,.dry-typedistribution transformers, andsubdistribution panels.Incaseofalossofoffsitepower,theemergency lightingsystemisfedfromthestandbydieselgenerators throughmanuallyoperatedcircuitbreakers.

Theemergency lightingsystemfixturesareconstantly energized.

Theessential lightingsystemprovidespartiallightingforcertaincri'tical areasofthestationrequiring continuous lightingsuchasthecontrolroom,relayandcomputerroom,standbydieselgenerator rooms,andemergency switchgear rooms'heessential lightingsystemreceivespowerfromthestationnormalUPSsystemandisfedthroughdry-typedistribution transformers andsubdistribution panels.Theessential lightingfixturespoweredbytheUPSsystemareconstantly energized.

Theegresslightingsystemprovidesadequatelightingforallegresssignsinsidetheplant.Thisisdesignedasaseparatesystemspecifically fortheinsidebuildingegressemergency conditions inaccordance withOSHArequirements.

TheegresslightingsystemreceivespowerfromthestationnormalUPSsystemaspartoftheessential lightingdistribution system.Theegresslightingfixturesareconstantly energized.

The8-hrbatterypacklightingprovidesillumination inallareasrequiredforoperation ofanysafeshutdownequipment andinaccessandegressroutestheretoincaseofafire.23Fluorescent, incandescent, andhighpressuresodiumlampsareusedforstationlighting.

Fluorescent lampsareusedforallofficesandformostoftheoperating areassuchasthecontrolroom,relayandcomputerroom,andemergency andnormalswitchgear rooms.Incandescent lampsareusedintheprimarycontainment, primarycontainment accesshatches,mainsteamtunnel,newfuelstoragevault,spentfuelpoolfilterroom,andinallotherareaswherelightingisinfrequently required.

HighpressuresodiumlampsareusedAmendment 231.2-39December198S NineMilePoint.Unit2FSARforallhighbaylightingsuchasintheturbinebuildingandreactorbuildinggeneralareas.1.2-40 NineMilePointUnit2FSAR1.2.llReferences NiagaraMohawkPowerCorporation.

Preliminary SafetyAnalysisReport,VolumeI,NineMilePointNuclearStation-Unit2,June1972.2.3.NiagaraMohawkPowerCorporation.

(Construction PermitStage),NineStation-Unit2,June1972.IOswegoCountyPlanningBoard.Plan,August1976.Environmental ReportMilePointNuclearPreliminary LandUseGulf6WesternTopicalReport.GGW-FSD2538,NuclearMainSteamIsolation ValveSystems,January1979.5.GeneralElectricLicensing TopicalReport.GeneralElectricStandardApplication forReactorFuel.NEDE-24011-P-A (latestapprovedrevision)

~6~GeneralElectricLicensing TopicalReport.GeneralElectricStandardApplication forReactorFuel(U.STSupplement),

NEDE-24011-P-A-US (latestapprovedr'evision).

Amendment 211.2-41September 1985