GDC 26, Reactivity control system redundancy and capability
Two independent reactivity control systems of different design principles shall be provided. One of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding the reactor core subcritical under cold conditions.
Reactivity control system redundancy and capability
GDC 26, Reactivity control system redundancy and capability# QUERY04bc4b0480d404efc88443f5dde37934
GDC 26, Reactivity control system redundancy and capability# QUERY2c85a6c18d3cf238988ed7e2c1e1b48e
GDC 26, Reactivity control system redundancy and capability Beaver Valley
GDC 26, Reactivity control system redundancy and capability# QUERY8d1bd72058f58dde5d8a9c40c51172d8
GDC 26, Reactivity control system redundancy and capability# QUERYeaab54f0382cfb75158958c458bdcb3b
GDC 26, Reactivity control system redundancy and capability Calvert Cliffs
GDC 26, Reactivity control system redundancy and capability# QUERY5c780399da94f884ecd6fd7825bec694
GDC 26, Reactivity control system redundancy and capability# QUERYfdf2da87cf3bc6abd002a1c84630bfbe
GDC 26, Reactivity control system redundancy and capability FitzPatrick
GDC 26, Reactivity control system redundancy and capability# QUERY88c287e7166db0e0d74e9e6b65632729
GDC 26, Reactivity control system redundancy and capability# QUERY070b5748fa7b97998123439f4a14e6fc
GDC 26, Reactivity control system redundancy and capability Ginna
GDC 26, Reactivity control system redundancy and capability# QUERYc708f6225b67cae8ecf5794ff7ec2535
GDC 26, Reactivity control system redundancy and capability# QUERY6ea692c1c9f545779be2e4ee1a1e7802
GDC 26, Reactivity control system redundancy and capability Hope Creek
GDC 26, Reactivity control system redundancy and capability# QUERYfa6a118c149f13aeddea51c910fb5f73
GDC 26, Reactivity control system redundancy and capability# QUERYfb2222a3e72695aa11faf3781bcafda5
GDC 26, Reactivity control system redundancy and capability Indian Point
GDC 26, Reactivity control system redundancy and capability# QUERYa18c946b8c81a680ebed77637624eab4
GDC 26, Reactivity control system redundancy and capability# QUERY92ad0858d6639eaf21714f553f1c641e
GDC 26, Reactivity control system redundancy and capability Limerick
GDC 26, Reactivity control system redundancy and capability# QUERY221184bb9c3fd9542153ad4bbec167ac
GDC 26, Reactivity control system redundancy and capability# QUERY12ec577b02646f92d45a89a939217b60
GDC 26, Reactivity control system redundancy and capability Millstone
GDC 26, Reactivity control system redundancy and capability# QUERY04cf76d0b4aaf575f911c072ebd7c089
GDC 26, Reactivity control system redundancy and capability# QUERY4bca985f03e35a2bd7529330b1314780
GDC 26, Reactivity control system redundancy and capability Nine Mile Point
GDC 26, Reactivity control system redundancy and capability# QUERYdfbdac4f87cead67bdb63c695da5b6f7
GDC 26, Reactivity control system redundancy and capability# QUERYa743c89662115624e88b2ab5a90125b2
GDC 26, Reactivity control system redundancy and capability Peach Bottom
GDC 26, Reactivity control system redundancy and capability# QUERY6ffeb730f9b99b720e5acfb8ed878852
GDC 26, Reactivity control system redundancy and capability# QUERYef8518e317a51c21fcce1360ea88cbc4
GDC 26, Reactivity control system redundancy and capability Salem
GDC 26, Reactivity control system redundancy and capability# QUERY33ddbe238e418086a05f77474eb577ac
GDC 26, Reactivity control system redundancy and capability# QUERY2c01ef098ac54b3125e51563d43816e7
GDC 26, Reactivity control system redundancy and capability Seabrook
GDC 26, Reactivity control system redundancy and capability# QUERYf09b16e18568a2adb8c49b75dcc9b7d3
GDC 26, Reactivity control system redundancy and capability# QUERY8637259426f9c350bd5d6da74277208e
GDC 26, Reactivity control system redundancy and capability Susquehanna
GDC 26, Reactivity control system redundancy and capability# QUERYfe16691218fb49e22289153bd04359fd
GDC 26, Reactivity control system redundancy and capability# QUERY66a4be40eacd01966373d863eab90581
NRC Region 1 false
GDC 26, Reactivity control system redundancy and capability# QUERY7a67bed0767cfcf0d82172f65aac0556
GDC 26, Reactivity control system redundancy and capability Haddam Neck
GDC 26, Reactivity control system redundancy and capability# QUERYe2532fbe35c7a73e5462cbcaf5c9057b
GDC 26, Reactivity control system redundancy and capability# QUERY6faea45b6a878772c6a4e1562012dc03
GDC 26, Reactivity control system redundancy and capability Maine Yankee
GDC 26, Reactivity control system redundancy and capability# QUERYceb423643f8871780440312ba91452e4
GDC 26, Reactivity control system redundancy and capability# QUERY05da6ff083b5e4e1ce405ce8e6447518
GDC 26, Reactivity control system redundancy and capability Oyster Creek
GDC 26, Reactivity control system redundancy and capability# QUERY8508207c7b3a19226714146ecb47232a
GDC 26, Reactivity control system redundancy and capability# QUERY3c0c3d6f0791eaa84907cf179f1fbe99
GDC 26, Reactivity control system redundancy and capability Pilgrim
GDC 26, Reactivity control system redundancy and capability# QUERYaf7c1f79ef7f1aa3e2446754726a7222
GDC 26, Reactivity control system redundancy and capability# QUERYeb46bc7267e531a4ce2e08941abe15e8
GDC 26, Reactivity control system redundancy and capability Saxton
GDC 26, Reactivity control system redundancy and capability# QUERYe74f83d8aef4ba3089c420eafb0cae14
GDC 26, Reactivity control system redundancy and capability# QUERY5a7dc0278489f9f1e70d12c01fb6018b
GDC 26, Reactivity control system redundancy and capability Shippingport
GDC 26, Reactivity control system redundancy and capability# QUERYcf511b0ac0a289fb4c77751115efc1c2
GDC 26, Reactivity control system redundancy and capability# QUERY6cc33cec56f907bcc66f94159ccc003b
GDC 26, Reactivity control system redundancy and capability Shoreham
GDC 26, Reactivity control system redundancy and capability# QUERY193fbcba0a50a7854571da90df3087e1
GDC 26, Reactivity control system redundancy and capability# QUERYdb23d202eb14de360fe2ae2a166520cf
GDC 26, Reactivity control system redundancy and capability Three Mile Island
GDC 26, Reactivity control system redundancy and capability# QUERYfd9e24141c3502f996a8f9a7f0d67fad
GDC 26, Reactivity control system redundancy and capability# QUERYd93e33f8ba38dd74560384071f2b17c3
GDC 26, Reactivity control system redundancy and capability Vermont Yankee
GDC 26, Reactivity control system redundancy and capability# QUERY0392dd90108255657f104e3277f48a1c
GDC 26, Reactivity control system redundancy and capability# QUERY786c65603f4d651b95bda6d8c4a910e3
GDC 26, Reactivity control system redundancy and capability Yankee Rowe
GDC 26, Reactivity control system redundancy and capability# QUERY595a1558eb14430df3756c0d14d53f3f
GDC 26, Reactivity control system redundancy and capability# QUERY621d36219223a784156835249493bfe1
GDC 26, Reactivity control system redundancy and capability Zion
GDC 26, Reactivity control system redundancy and capability# QUERY626d7a0f7fc5308ab4be0d0bacb1aa7c
GDC 26, Reactivity control system redundancy and capability# QUERYe0df3e670d184649874a0fbb6c46c420
NRC Region 1 true
GDC 26, Reactivity control system redundancy and capability# QUERYa3013f81b2c3556f952fc20ebfb722f7
GDC 26, Reactivity control system redundancy and capability Browns Ferry
GDC 26, Reactivity control system redundancy and capability# QUERY27f9d4afe2a0d0c93711a05c02cd07d8
GDC 26, Reactivity control system redundancy and capability# QUERY9476e94a8534b7a618170c5c96a51d2d
GDC 26, Reactivity control system redundancy and capability Brunswick
GDC 26, Reactivity control system redundancy and capability# QUERYd68be00edab060d05bf5a774e541638c
GDC 26, Reactivity control system redundancy and capability# QUERY42606b472b7baa73c9269487a75efec0
GDC 26, Reactivity control system redundancy and capability Catawba
GDC 26, Reactivity control system redundancy and capability# QUERYafa0354b8d7a3f5eaf48ffeff29d3439
GDC 26, Reactivity control system redundancy and capability# QUERYff2d42fd13580b33406ae179c15c7110
GDC 26, Reactivity control system redundancy and capability Farley
GDC 26, Reactivity control system redundancy and capability# QUERY852b39ea478c443a797aa55ebadbfdce
GDC 26, Reactivity control system redundancy and capability# QUERY6f24287f20d3cde0fd7c79c8bf312a20
GDC 26, Reactivity control system redundancy and capability Harris
GDC 26, Reactivity control system redundancy and capability# QUERY9a573ab6c06d8449ce226cc243854dbb
GDC 26, Reactivity control system redundancy and capability# QUERYc4ecdc5aa9f82617290bfbe053280c55
GDC 26, Reactivity control system redundancy and capability Hatch
GDC 26, Reactivity control system redundancy and capability# QUERYdbfb1a8772784ae8468e6d8ad224147b
GDC 26, Reactivity control system redundancy and capability# QUERY036fda10cb67a3f227bd4c3e34ce4e6a
GDC 26, Reactivity control system redundancy and capability Lee
GDC 26, Reactivity control system redundancy and capability# QUERY956f1e350e14e635664b32bdb3b0725e
GDC 26, Reactivity control system redundancy and capability# QUERY8626cd090d9f1ff4d4c52f9057f314db
GDC 26, Reactivity control system redundancy and capability McGuire
GDC 26, Reactivity control system redundancy and capability# QUERY23e8fd396737815b2d520e1331ab7008
GDC 26, Reactivity control system redundancy and capability# QUERY12e1637005395fed1e91c1e4048a7a4e
GDC 26, Reactivity control system redundancy and capability North Anna
GDC 26, Reactivity control system redundancy and capability# QUERY8b68c746b0e26ffe7b5c2eadda51e01c
GDC 26, Reactivity control system redundancy and capability# QUERY5cc576064b83c243592b2a15918c0a98
GDC 26, Reactivity control system redundancy and capability Oconee
GDC 26, Reactivity control system redundancy and capability# QUERY223a2ca98fed81692847625fc2b69ba1
GDC 26, Reactivity control system redundancy and capability# QUERYa709d6b2b1f1729cf2b801131da7306c
GDC 26, Reactivity control system redundancy and capability Robinson
GDC 26, Reactivity control system redundancy and capability# QUERYa5cf6c9519f4b4b94a9aa808a503d206
GDC 26, Reactivity control system redundancy and capability# QUERY4eeb449c9abcf02581df95b7ddc83a65
GDC 26, Reactivity control system redundancy and capability Saint Lucie
GDC 26, Reactivity control system redundancy and capability# QUERY4d2f9bfb1754df45510288c2189efea3
GDC 26, Reactivity control system redundancy and capability# QUERY7d3f29b178640ccda89e9ffec89ed9c3
GDC 26, Reactivity control system redundancy and capability Sequoyah
GDC 26, Reactivity control system redundancy and capability# QUERY40674d2f4754d7d9dc2252a3b2866d76
GDC 26, Reactivity control system redundancy and capability# QUERY8dc9654216ebffdc7a4981a980c78234
GDC 26, Reactivity control system redundancy and capability Summer
GDC 26, Reactivity control system redundancy and capability# QUERY9acd2b13f9ec0da7dc3f94c92132c3ee
GDC 26, Reactivity control system redundancy and capability# QUERY0ea72bd29aee0c613dc97d12a4c4885d
GDC 26, Reactivity control system redundancy and capability Surry
GDC 26, Reactivity control system redundancy and capability# QUERY9f059d6903ddcb871ddc5b9e5fbe2c29
GDC 26, Reactivity control system redundancy and capability# QUERYea12d531316f2c415062ed8b42271b32
GDC 26, Reactivity control system redundancy and capability Turkey Point
GDC 26, Reactivity control system redundancy and capability# QUERY4a636b59dd23e1a943d96b95c4759afd
GDC 26, Reactivity control system redundancy and capability# QUERY764e34d4bd56cc9ca098bcc4fd598803
GDC 26, Reactivity control system redundancy and capability Vogtle
GDC 26, Reactivity control system redundancy and capability# QUERY8f94073c4ced844ad63d94154ff9150e
GDC 26, Reactivity control system redundancy and capability# QUERYb1850f3a886a4ef8d866929b680a2327
GDC 26, Reactivity control system redundancy and capability Watts Bar
GDC 26, Reactivity control system redundancy and capability# QUERY13644e516f556bd6d694baa26b7b0a99
GDC 26, Reactivity control system redundancy and capability# QUERY9d49305e6d52dac3c98e143e3da7cbf1
NRC Region 2 false
GDC 26, Reactivity control system redundancy and capability# QUERYef2ed89eccc51cc609623ec1f2ae0e81
GDC 26, Reactivity control system redundancy and capability Crystal River
GDC 26, Reactivity control system redundancy and capability# QUERY2ff13af7e34de1bb4b5a8693b41205a3
GDC 26, Reactivity control system redundancy and capability# QUERY983c64707194074afde9e1386b3e5d06
GDC 26, Reactivity control system redundancy and capability Parr
GDC 26, Reactivity control system redundancy and capability# QUERY7d679f22da8b620df2290da5fd622510
GDC 26, Reactivity control system redundancy and capability# QUERYe15f070229aeb5c96d89f980d7530001
NRC Region 2 true
GDC 26, Reactivity control system redundancy and capability# QUERY03a4ee5432c9daa6cecac06e7884f24d
GDC 26, Reactivity control system redundancy and capability Braidwood
GDC 26, Reactivity control system redundancy and capability# QUERY583f1f610648ac0f0ef7c5f3bb4b1688
GDC 26, Reactivity control system redundancy and capability# QUERY1b34d06c9cad43fce0f3a952b5066baa
GDC 26, Reactivity control system redundancy and capability Byron
GDC 26, Reactivity control system redundancy and capability# QUERY6952d57c292e197a1528f6bc0dce913c
GDC 26, Reactivity control system redundancy and capability# QUERYbccf86797d090f33134815dd00e84120
GDC 26, Reactivity control system redundancy and capability Clinton
GDC 26, Reactivity control system redundancy and capability# QUERY8ce12c27cef760f20841f8da3763bed7
GDC 26, Reactivity control system redundancy and capability# QUERY26690f3e81eecfc65099ebb3c8692268
GDC 26, Reactivity control system redundancy and capability Cook
GDC 26, Reactivity control system redundancy and capability# QUERY34d458b50909fff1c78e74a1e8c98540
GDC 26, Reactivity control system redundancy and capability# QUERYbee18d3c79f33717234a435595e1db56
GDC 26, Reactivity control system redundancy and capability Davis Besse
GDC 26, Reactivity control system redundancy and capability# QUERY154d887e1875b5e89de80f2aa26f078d
GDC 26, Reactivity control system redundancy and capability# QUERY7fb8500399ebfab6503893cd3e40d487
GDC 26, Reactivity control system redundancy and capability Dresden
GDC 26, Reactivity control system redundancy and capability# QUERY25661baab4e2375dd4f016b7cbae5687
GDC 26, Reactivity control system redundancy and capability# QUERY6a5564e9f443c63a8de3c01d921db9ca
GDC 26, Reactivity control system redundancy and capability Duane Arnold
GDC 26, Reactivity control system redundancy and capability# QUERYa96f57df0b873f38f77c1903a91ec36a
GDC 26, Reactivity control system redundancy and capability# QUERY22372571da1eb5106bbbd156e14cf655
GDC 26, Reactivity control system redundancy and capability Fermi
GDC 26, Reactivity control system redundancy and capability# QUERYd32a4940b543d43c853ae8a83ae30962
GDC 26, Reactivity control system redundancy and capability# QUERY6745847bfb29fe76652434770b2959bf
GDC 26, Reactivity control system redundancy and capability LaSalle
GDC 26, Reactivity control system redundancy and capability# QUERY3efa40de03c4dbba0481bbb4337b8559
GDC 26, Reactivity control system redundancy and capability# QUERY9d24cc19ebf8ce91ddefad774e73fb2d
GDC 26, Reactivity control system redundancy and capability Monticello
GDC 26, Reactivity control system redundancy and capability# QUERYd218c6cc00a95b557a0b9271af0708d9
GDC 26, Reactivity control system redundancy and capability# QUERYb0a794aa2ec1a629dff8047d3312e8bb
GDC 26, Reactivity control system redundancy and capability Palisades
GDC 26, Reactivity control system redundancy and capability# QUERYed56aa04757fc1f7c35d3fb42c6fb3d9
GDC 26, Reactivity control system redundancy and capability# QUERYec0f9784cc2babacbfb59fdf587c5af8
GDC 26, Reactivity control system redundancy and capability Perry
GDC 26, Reactivity control system redundancy and capability# QUERYb5916c03e8cfb77bab803fd94e23473f
GDC 26, Reactivity control system redundancy and capability# QUERYd3003cff2bd28b60fd6755cbaa835b63
GDC 26, Reactivity control system redundancy and capability Point Beach
GDC 26, Reactivity control system redundancy and capability# QUERYe0168c6fe40384d543e226ada328a85a
GDC 26, Reactivity control system redundancy and capability# QUERY7ad2f4c20c4ee64237d60fb57bec3c1a
GDC 26, Reactivity control system redundancy and capability Prairie Island
GDC 26, Reactivity control system redundancy and capability# QUERY193f5cf3d092f237e817d0702aee70fd
GDC 26, Reactivity control system redundancy and capability# QUERY034673bc920841062966d1293a13414f
NRC Region 3 false
GDC 26, Reactivity control system redundancy and capability# QUERY17d44176888b71912ab695a95185b945
GDC 26, Reactivity control system redundancy and capability Big Rock Point
GDC 26, Reactivity control system redundancy and capability# QUERY4ddf48c8946256a3d92988fee4e4d7ce
GDC 26, Reactivity control system redundancy and capability# QUERY4b322d6c67de439c597ecdfff72323a6
GDC 26, Reactivity control system redundancy and capability Kewaunee
GDC 26, Reactivity control system redundancy and capability# QUERY69db4005f14a6dd6ab44873fc76c7006
GDC 26, Reactivity control system redundancy and capability# QUERYc1ee6726e9d1230c9003f11894c1bc82
GDC 26, Reactivity control system redundancy and capability La Crosse
GDC 26, Reactivity control system redundancy and capability# QUERYede35d86a075a3c09658b9230cd3ca81
GDC 26, Reactivity control system redundancy and capability# QUERYc6231e96e2a8442989db58b828879125
NRC Region 3 true
GDC 26, Reactivity control system redundancy and capability# QUERY4b875cd2f5745a1db5699c9bf7b8b28c
GDC 26, Reactivity control system redundancy and capability Arkansas Nuclear
GDC 26, Reactivity control system redundancy and capability# QUERYfa16191cbe5efaf65757e41e17d7d648
GDC 26, Reactivity control system redundancy and capability# QUERY0776f29c8c899acd9319bb1cd24c9a23
GDC 26, Reactivity control system redundancy and capability Callaway
GDC 26, Reactivity control system redundancy and capability# QUERY9a0502985669a41cfb96acbcdb0480f0
GDC 26, Reactivity control system redundancy and capability# QUERY42e679e02f48cfc3b4cc7e3b2fa0169b
GDC 26, Reactivity control system redundancy and capability Columbia
GDC 26, Reactivity control system redundancy and capability# QUERY2debe2b01c6bba17116993ea328cf02d
GDC 26, Reactivity control system redundancy and capability# QUERYc72ba62c253a889dd40cd4dc81f0ff34
GDC 26, Reactivity control system redundancy and capability Comanche Peak
GDC 26, Reactivity control system redundancy and capability# QUERYd4bca90545a7a05b285e145da46a5d30
GDC 26, Reactivity control system redundancy and capability# QUERYc0b2bd4471616af7fe7567e11c0e55be
GDC 26, Reactivity control system redundancy and capability Cooper
GDC 26, Reactivity control system redundancy and capability# QUERY791abd4cda9840e0e45832102e5ba0da
GDC 26, Reactivity control system redundancy and capability# QUERYd39f6178d43b49cda2ceb5caffdad575
GDC 26, Reactivity control system redundancy and capability Diablo Canyon
GDC 26, Reactivity control system redundancy and capability# QUERYf76558922d1d5c8349598e25926624fb
GDC 26, Reactivity control system redundancy and capability# QUERY52af9bb592a2cd6b402c103f6516ba6f
GDC 26, Reactivity control system redundancy and capability Grand Gulf
GDC 26, Reactivity control system redundancy and capability# QUERY4aa4b35def99b5e3e7efb18d5e8f34b4
GDC 26, Reactivity control system redundancy and capability# QUERY76b6da7c4d2ce9ff3a0d6bc8dca14ab9
GDC 26, Reactivity control system redundancy and capability Palo Verde
GDC 26, Reactivity control system redundancy and capability# QUERYac082247796168db1752bdac940249d2
GDC 26, Reactivity control system redundancy and capability# QUERYc0271677e6142bd8d87a00b985fbf458
GDC 26, Reactivity control system redundancy and capability Quad Cities
GDC 26, Reactivity control system redundancy and capability# QUERY6909c01515b9ee2b12bd7511db524368
GDC 26, Reactivity control system redundancy and capability# QUERY271156ac7d1b5d6831704cc9b66387e7
GDC 26, Reactivity control system redundancy and capability River Bend
GDC 26, Reactivity control system redundancy and capability# QUERY0b45cbdc24a810e8923b5de949de48f3
GDC 26, Reactivity control system redundancy and capability# QUERY1f508a5d206ef21b99c60ea31688c3fa
GDC 26, Reactivity control system redundancy and capability South Texas
GDC 26, Reactivity control system redundancy and capability# QUERYa9ee81dc08adf9140dc9def97c5578d7
GDC 26, Reactivity control system redundancy and capability# QUERY48bb8be2f8edf2e57fd45f6123a37146
GDC 26, Reactivity control system redundancy and capability Waterford
GDC 26, Reactivity control system redundancy and capability# QUERY9c6611d1331b0274b5560563996eeb60
GDC 26, Reactivity control system redundancy and capability# QUERYfc8065b42872757e6d3f3be826f6e18b
GDC 26, Reactivity control system redundancy and capability Wolf Creek
GDC 26, Reactivity control system redundancy and capability# QUERY9de342b9ca189ae3c62c2fc36c3161b2
GDC 26, Reactivity control system redundancy and capability# QUERYaaf5eb52d305c8b78d540513d5498563
NRC Region 4 false
GDC 26, Reactivity control system redundancy and capability# QUERY2836896f439495127d76eeae8956a4dc
GDC 26, Reactivity control system redundancy and capability Fort Calhoun
GDC 26, Reactivity control system redundancy and capability# QUERY3e42ace55907a897c74555b043897481
GDC 26, Reactivity control system redundancy and capability# QUERY1feafdc0edb05e852f3c465e61fede95
GDC 26, Reactivity control system redundancy and capability Fort Saint Vrain
GDC 26, Reactivity control system redundancy and capability# QUERY14568bdd9a307f1d1ff39b8b440a2a68
GDC 26, Reactivity control system redundancy and capability# QUERY79b1a62af5eb8f704052fa8381b6d7cd
GDC 26, Reactivity control system redundancy and capability Hallam
GDC 26, Reactivity control system redundancy and capability# QUERYcd2c2a00117dd1b809472e5ed8758013
GDC 26, Reactivity control system redundancy and capability# QUERY9834adfb744af3766b6b93ddb7ef9093
GDC 26, Reactivity control system redundancy and capability Humboldt Bay
GDC 26, Reactivity control system redundancy and capability# QUERYcdb994702e2101dadce9a4a227664baa
GDC 26, Reactivity control system redundancy and capability# QUERYab3336d710328220d424715f0df9c2ff
GDC 26, Reactivity control system redundancy and capability Rancho Seco
GDC 26, Reactivity control system redundancy and capability# QUERY3ba8b7c8e85acf4818050ce2a72374f9
GDC 26, Reactivity control system redundancy and capability# QUERY7d040c081bc7cbb4e98501efeeabb565
GDC 26, Reactivity control system redundancy and capability San Onofre
GDC 26, Reactivity control system redundancy and capability# QUERY53379544dd246c04d811153c41c2e0b8
GDC 26, Reactivity control system redundancy and capability# QUERYbee5a779378643375028915be99e3850
GDC 26, Reactivity control system redundancy and capability Trojan
GDC 26, Reactivity control system redundancy and capability# QUERYe912d3f1c4450612a1654627f5c5f89e
GDC 26, Reactivity control system redundancy and capability# QUERY32ae40eb7e3672a5bbc47b2c21528dca
NRC Region 4 true
GDC 26, Reactivity control system redundancy and capability# QUERY3f48e2e2d298162fc4e22365ef7b7e59
GDC 26, Reactivity control system redundancy and capability
GDC 26, Reactivity control system redundancy and capability# QUERY601ab0b9aa1869879de21db05ca94edd
GDC 26, Reactivity control system redundancy and capability Elk River
GDC 26, Reactivity control system redundancy and capability# QUERY6481040b0d4297bf4f3bceb391d1a293
GDC 26, Reactivity control system redundancy and capability# QUERYc4c9430c004763aefc44ddf81682167c
GDC 26, Reactivity control system redundancy and capability Sundesert
GDC 26, Reactivity control system redundancy and capability# QUERY06d1858887613f7558109af37f458c33
GDC 26, Reactivity control system redundancy and capability# QUERY70d620f5d0508735698e7a49e161550d
GDC 26, Reactivity control system redundancy and capability Victoria
GDC 26, Reactivity control system redundancy and capability# QUERY0cdf8e7e3c019a9793f28dabaefbec68
GDC 26, Reactivity control system redundancy and capability# QUERY0589ecb24865e8bffbeb78097f6a72ac
GDC 26, Reactivity control system redundancy and capability Clinch River
GDC 26, Reactivity control system redundancy and capability# QUERY1933edf053296415f4717ea5975d8e24
GDC 26, Reactivity control system redundancy and capability# QUERY9581d98be14626bffd7f4a4f2d900199
GDC 26, Reactivity control system redundancy and capability Kemmerer
GDC 26, Reactivity control system redundancy and capability# QUERY8c3f11f02dc85e6821084abfd6a2c2d5
GDC 26, Reactivity control system redundancy and capability# QUERY9696962a7f7f0c5389689f2f085cccdb
NG-17-0084, License Amendment Request (TSCR-164), Revision to Technical Specification 3.1.2, Reactivity Anomalies
CNS-17-033, Technical Specification Bases Changes
CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
DCL-17-076, Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements (License Amendment Request 17-01)
CNL-16-148, Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
PNP 2016-049, License Amendment Request: Control Rod Drive Exercise Surveillance
CNS-16-031, Technical Specification Bases Changes
NOC-AE-16003351, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
NMP1L3070, License Amendment Request - Reactivity Anomalies Surveillance
2CAN121705, Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26
NOC-AE-15003315, Emergency License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies for Cycle 20
NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2
2CAN021501, License Amendment Request Allowance to Eliminate Movement of Control Element Assembly 18 from Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 24
JAFP-13-0063, Application to Revise Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs
2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
L-MT-13-030, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs
2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
DCL-12-050, Attachment 2 to DCL-12-050, Final Safety Analysis Report Changes for Process Protection System Replacement
2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
GNRO-2012/00001, License Amendment Request - Standby Liquid Control System
L-2011-028, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Safety Analyses Issues - Round 1
RS-18-035, License Amendment Request to Revise Technical Specification 3.2.3, Axial Flux Difference
TSTF-15-13, TSTF Comments on Draft Model Safety Evaluation of Traveler TSTF-547, Revision 0, Clarification of Rod Position Requirements, and Transmittal of TSTF-547, Revision 1
TSTF-14-06, Transmittal of TSTF-547, Revision 0, Clarification of Rod Position Requirements
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 4, Reactor
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 15, Accident Analyses
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 9.3, Process Auxiliaries
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3D-137 Through 4.3-41
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 7, Instrumentation and Control
NL-16-109, Indian Point, Unit 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 1, Introduction and Summary
NL-15-169, Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped)
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 8 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 7 - Instrumentation and Control
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 1, Introduction and Summary
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 7 - Instrumentation and Control
NL-13-130, Indian Point, Unit 2 - Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 1 - Introduction and Summary
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control Systems
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and Controls
NL-11-1812, Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
U-603987, Transmittal of Revision 13 to Technical Specification Bases
GO2-10-024, License Amendment Request to Change Technical Specifications Relating to Control Rod Operability and Control Rod Scram Accumulators
NL-09-1380, Revision to Technical Specifications LCO 3.1.2, Reactivity Anomalies
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
L-09-218, Submittal of Technical Specification Bases, Revision 7
ULNRC-05633, Revision of Technical Specification 3.3.9
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
GNRO-2009/00008, Technical Specification Bases Update to the NRC for Period Dated January 23, 2009
LR-N08-0205, Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
NOC-AE-08002351, Revision 2 to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations
NOC-AE-08002319, Response to RAI Revision to Proposed Amendment to TS 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
PLA-6330, Proposed Amendment Nos. 300 and 270: Request for Adoption of TSTF-475, Rev. 1, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Using the Consolidated Line Item Improvement Process (CLIIP)
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
NL-08-0013, Units 1 and 2, Editorial Revision to Standby Liquid Control Solution Figure
GNRO-2008/00025, Technical Specification Bases Update to the NRC for Period Dated March 5, 2008
NOC-AE-07002234, Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation and Technical Specification 3.4.1.4.2 Action C
NRC-08-0001, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
TSTF-07-19, Response to NRC Request for Additional Information (RAI) Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated February 28, 2007
ULNRC-06328, Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011)
NL-16-0388, Draft License Amendment Request Regarding Alternative Source Team
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 1 - Introduction and Summary
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), List of Effective Pages
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RBG-46771, Emergency License Amendment Request (LAR 2007-22) Local Power Range Monitor Surveillance Frequency Extension Request
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
2CAN080701, License Amendment Request to Revise Technical Specification 3.1.3.4, CEA Drop Time
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
NL-07-0258, Technical Specifications Revision to Allow File Movement with Refueling Interlocs Inoperable
ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
RS-06-084, Supplemental Information Concerning License Amendment Request to Revise License Basis to Allow Ganged Rod Drive Capability of the Rod Control Management System (Rcms)
PLA-6049, Proposed License Amendment Nos. 289 and 257, Standby Liquid Control System
ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
SBK-L-18094, License Amendment Request 18-02, Application to Revise the Technical Specifications Associated with Movable Control Rods
JAFP-18-0093, License Amendment Request - Reactivity Anomalies Surveillance
SECY-18-0099, NuScale Power Exemption Request from 10 CFR Part 50, Appendix a, General Design Criterion 27, Combined Reactivity Control Systems Capability
W3P81-1169, Forwards Itemized Reviews of Compliance W/Various Sections of 10CFR.Util Meets or Exceeds Requirements
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation
CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis
RAIO-0418-59415, LLC Response to NRC Request for Additional Information No. 402 (Erai No. 9449) on the NuScale Design Certification Application
L-2019-053, License Amendment Request 269, Modify Reactor Trip System (RTS) Turbine Trip Instrumentation Requirements and Resolve Two Non-Conservative Requirements
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
PLA-5990, Proposed Amendment No. 283 to Unit 1 MCPR Safety Limits and Reference Changes PLA-5990
L-MT-05-107, Reply to Revised Notice of Violation Dated September 22, 2005
LR-N05-0432, Request for Change to Technical Specifications on Standby Liquid Control System
NL-05-1362, Supplement to Technical Specifications Revision Request to Standby Liquid Control Figure 3.1.7-1
RBG-46419, Revisions to the Technical Requirements Manual and the Technical Specifications Bases
2CAN121903, License Amendment Request, Revise Control Element Assembly Drop Time
2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations
RAIO-0719-66334, LLC - Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application
RAIO-0418-59506, LLC Response to NRC Request for Additional Information No. 368 (Erai No. 9242) on the NuScale Design Certification Application
L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1
RAIO-0919-66988, LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application
ND-18-0364, Supplement to Request for License Amendment: Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes (LAR-17-024S2)
ND-17-1559, Request for License Amendment: Technical Specification Changes to Support Control Rod Testing in Cold Shutdown with Reactor Coolant Pumps Not in Operation (LAR-17-034)
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
ET 09-0019, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NLS2004122, License Amendment Request to Revise the Required Channels Per Trip System for Primary and Secondary Containment Isolation and Control Room Emergency Filter System Instrumentation
L-04-124, License Amendment Request Nos. 318 and 191
PLA-5793, Proposed Amendment No. 233 to Unit 2 License NPF-22: MCPR Safety Limits and Reference Changes
NL-04-0981, Transmittal of Quarterly Update for Hatch, Units 1 and 2 Technical Specifications Bases
GNRO-2004/00002, Technical Specification Bases Update to the NRC for Period Dated January 22, 2004
NUREG/CR-6839, Fort Saint Vrain Gas Cooled Reactor Operational Experience
NG-03-0654, Change of Commitment to Regulatory Guide 1.97
NL-03-1563, TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
L-03-020, License Amendment Request Nos. 303 and 174
LR-N03-0022, Revision to Request for Change to Technical Specifications
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
U-603588, Transmittal of Revision 7 to Clinton Power Station Technical Specification Bases
L-02-094, Technical Specifications Bases Change Submittal
NRC-02-0043, Proposed Technical Specification Change (License Amendment) - Refueling Equipment Interlocks
ULNRC-04721, Technical Specification Bases Revision 3
BSEP 02-0124, Application for Amendment to Licenses DPR-71 & DPR-62 to Revise Technical Specifications Section 3.1.7 to Reflect Modifications as Result of Transition to GE14 Fuel Design
DCL-02-038, License Amendment Request 02-02, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
1CAN030201, License Amendment Request Re Proposed Change to Support Implementation of ANO-1 Improved Technical Specifications
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
ND-20-0507, Request for License Amendment: Core Makeup Tank Boron Concentration Requirements (LAR-20-004)
L-20-151, License Amendment Request to Correct Non-conservative Technical Specifications 3.2 .1, Heat Flux Hot Channel Factor Fa(Z) and 5.6.3, Core Operating Limits Report (COLR)
IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review
IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
NUREG/CR-7299, Fuel Qualification for Molten Salt Reactors
CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications
NRC-94-4290, Forwards Responses to NRC RAIs on AP600 from NRC 940502,05, 23,0601,08 & 0714 Ltrs.Revs of Responses Previously Submitted Also Provided
PY-CEI-NRR-2295, Application for Amend to License NPF-58,revising TS 3.1.7, Standby Liquid Control Sys to Increase Boron Concentration in Standby Liquid Control Sys for Cycle 8 Fuel Design & to Provide Margin for Future Cycles as Required
PY-CEI-NRR-2418, Application for Amend to License NPF-58,incorporating Addl Option Into TS 3.9.1 Required Actions When Refueling Interlocks Are Inoperable
LD-94-036, Forwards Comments of Chapter 4 of Sys 80+ Final SER, NUREG-1462 for Technical Accuracy & Consistency w/CESSAR-DC
05000370/LER-1986-008-03, :on 860620,control Rod L-3 Discovered Stuck & Unable to Drop Into Reactor Core.Caused by Small Particle Debris.Debris Removed
AECM-81-202, Forwards Assurance That Facility Will Be in Compliance W/All Applicable NRC Regulations,In Response to NRC Request.Public Health & Safety Will Be Protected
AECM-80-225, Forwards Response to NRC Questions 031.56,031.71 & Revised Responses to Questions 031.38,031.54,031.60 & 031.75. Responses Will Be Incorporated Into Oct 1980 Amend to FSAR
AEP-NRC-2024-20, Updated Final Safety Analysis Report (Ufsar), Revision 32, Chapter 3, Reactor (Unit 2)
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
RAIO-0818-61411, LLC Response to NRC Request for Additional Information No. 488 (Erai No. 9525) on the NuScale Design Certification Application
RAIO-0718-61158, LLC Response to NRC Request for Additional Information No. 490 (Erai No. 9556) on the NuScale Design Certification Application
RAIO-0218-58506, LLC Response to NRC Request for Additional Information No. 305 (Erai No. 9194) on the NuScale Design Certification Application
RAIO-0118-58190, LLC Supplemental Response to NRC Request for Additional Information No. 58 (Erai No. 8835) on the NuScale Design Certification Application
05000315/LER-1998-052, :on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
L-81-429, Forwards Itemized Review of Compliance W/Significant Rules & Regulations,Per 10CFR,in Response to NRC 810929 Request
L-17-223, Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements
BSEP 16-0083, Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs
CNL-15-102, 3 - Responds to NRC Request for Additional Information Related to License Amendment Request for the Adoption of Technical Specifications Task Force Traveler TSTF-535, Rev 0, Revise Shutdown Margin Definition to Address Advanced
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
BW140102, CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report
DCL-12-002, Revision to the Updated Final Safety Analysis Report Section 4.3.2.2, Power Distribution; and Technical Specification Bases 3.1.7, Rod Position Indication; 3.2.1, Heat Flux Hot Channel Factor (Fo(Z)),3.2.2,.
RS-11-073, License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies
RS-17-058, License Amendment Request to Incorporate Changes Supported by TSTF-547, Clarification of Rod Position Requirements
NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC
RS-10-172, Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
LIC-10-0034, License Amendment Request (LAR) Revision to Technical Specification (TS) 2.15, Table 2-5, Item 1 and TS 3.1, Table 3-3, Items 1, 2 and 4 Control Element Assembly Position Indication and Correction of TS 2.10.2(7)c
RS-10-028, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
BVY 06-080, Extended Power Uprate - License Amendment No. 229 Clarifications to NRCs Final Safety Evaluation
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
ULNRC-04883, Proposed Revision to Technical Specification (TS) 3.9.2, Unborated Water Source Isolation Valves, to Revise & Rename Specification 3.9.2, Dilution Source Isolation Valves & Associated Revision to TS 3.3.9, Boron Dilution.
NUREG-0754, Requests Commission Approval of Issuance of Draft Fr Notice Requiring Documentation of Deviations from SRP & Draft NUREG-0754, Plan for Systematic Safety Evaluation of Nuclear Power Reactors. Related Documentation Encl
NLS2002008, License Amendment Request to Revise the Ultimate Heat Sink and Reactor Equipment Cooling Water Temperature Requirements
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications
ND-21-0486, 0 to Updated Final Safety Analysis Report, Chapter 4, Reactor
NL-21-0042, Units 1 and 2, Vogtle Electric Generating Plant - Units 1 and 2, Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
DCL-25-029, License Amendment Request 25-01: Application to Utilize Optimize ZIRLO for Improved Fuel Rod Cladding Performance
RA-19-0424, 2 to Updated Final Safety Analysis Report, Chapter 4, Reactor
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID
PLA-8042, Proposed Emergency Amendment to License NPF-22: Temporary Addition of Analyzed Rod Position Sequence
TXX-9400, Proposed Tech Specs Replacing Existing Spec & Bases Re QPTR W/Spec & Bases Consistent W/Improved Stds TS for Westinghouse Plants (NUREG-1431)
NL-25-0317, Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating