10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

More documents

Recommendations

Info

Figure 2-3General Arrangement - Decks - C, D, Flats, Tank Tops and Containment VesselUpdated Final Safety Analysis Report - (STS-004-002)Rev. VI 26
Updated Final Safety Analysis Report - (STS-004-002)3 SITE AND SITE CRITERIA3.1 Site DescriptionThe licensed site of the NSS is the boundary defined by the ship’s hull (see Figures 2-2 and 2-3).Because the NSS is mobile, the off-ship characteristics of the site vary with the location of the vessel.During the NSS’s operating period, the basic limitations on operations in all ports were described in thePort Operating Criteria which required the development of Port Operating Plans. The specific sitecharacteristics of ports that the NSS entered were evaluated prior to the visit of the ship and documentedin a Port Operating Plan. The limitations on operation were based on site analysis assuming theoccurrence of the maximum credible accident (MCA) that is associated with reactor startup and operation.The MCA is a major loss-of-coolant accident (LOCA) from the primary system. The specific LOCA wasassumed to be instantaneous, complete, transverse shear of a primary system pipe. The details of theoriginal Port Operating Criteria are described in 3.2 Revision III of the FSAR. The details of the LOCAare described in 13.5 of Revision III of the FSAR.Following defueling in Fall 1971 when the reactor was no longer operated, the MCA could have beenrevised to a worst case defueled accident as there was no longer any possibility of a reactor criticalityaccident. Regardless, the Port Operating Criteria remained in effect and unchanged as a conservativedevelopmental tool for Port Operating Plans. Technical Specification Change Number 12, datedDecember 20, 1971, noted that “approval of the proposed changes would permit the ship to be towed,berthed, moored or drydocked in the defueled condition at any domestic location having an approved portentry and docking plan.”Prior to 1976 when the Possession-only License (Amendment 8) was issued, the Port Operating Criteriawas an attachment to the Operating License NS-1. Port Operating Plans have been developed andapproved by MARAD and forwarded to NRC for information to allow ship movement, berthing, publicdisplay and maintenance as needed.During the ship’s operating period, the acceptability of a location was dependent on establishing the lowpopulationzone such that following the MCA, the dose to members of the public would not exceedestablished limits. Prior to permanent defueling in 1971, the Maximum Credible Accident was a loss ofcoolant accident assuming continuous operation at 100% for two years. Following defueling in 1971,there has been no possibility of any reactor/criticality accident. Following the 1976 decommissionactivities to remove the three primary purification system ion-exchangers, their resins and dewatering theprimary, auxiliary and secondary systems, no decommissioning activities have been allowed.Following the final shutdown on November 8, 1970 and the subsequent defueling, the remainingradioactive material is primarily the activated pressure vessel and other primary system components. Theactivation estimates have dropped dramatically in the subsequent years: 108,496 Ci (1976 calculatedusing power history and core physics), 13,000 Ci (1994, estimate based on decay of the principal isotopesfrom the 1976 data) and 452 Ci (2005). Note that the 2005 estimate is lower because it used the actualpower history, the results of the intrusive sampling and was calculated using ORIGEN-II computer-basedmodeling code.General area dose rates measured during the 2005 radiological and environmental characterizationscoping survey are discussed in Chapter 13.In January 2007, the Safety Evaluation Report for License Amendment 13 noted that:Given the reduced the inventory of radioactive material onboard, and the low activation estimatesand general area dose rates, there is no Credible Accident that could cause the dose to the public toRev. VI 27
Page 1 and 2: 0U.S. Department Savannah Technical
Page 3 and 4: Docket No. 50-238; License NS-1; N.
Page 5: Ttit 1 ►'1 ltt tU.S. Department o
Page 8: PageNo.Rev.No.Updated Final Safety
Page 11 and 12: Updated Final Safety Analysis Repor
Page 33 and 34: U p da te d Fi na lS af et yA n al
Page 43: Figure 2-2General Arrangement - Inb
Page 47 and 48: 3.2.3 Port Operating CriteriaUpdate
Page 59 and 60: U p da te d Fi na lS af et yA n al
Page 61 and 62: Table 4-1List of Containment Penetr
Page 73 and 74: 5.3.3 Local ShieldingUpdated Final
Page 79 and 80: 7.1.2 General Performance DataUpdat
Page 81 and 82: 7.1.2.3 Water ChemistryUpdated Fina
Page 87 and 88: 7.5 Primary PumpsUpdated Final Safe
Page 91 and 92: 8.1.3 Construction Features8.1.3.1
Page 95 and 96:
Updated Final Safety Analysis Repor
Page 97 and 98:
Page 99 and 100:
Figure 8-2Current Electrical Distri
Page 101 and 102:
Page 103 and 104:
Page 105 and 106:
Page 107 and 108:
Page 109 and 110:
Page 111 and 112:
Page 113 and 114:
Page 115 and 116:
9.2.1.2 DescriptionUpdated Final Sa
Page 117 and 118:
9.2.2 Buffer Seal (SL) System9.2.2.
Page 119 and 120:
Page 121 and 122:
Page 123 and 124:
Page 125 and 126:
Page 127 and 128:
Page 129 and 130:
Page 131 and 132:
9.2.8 Shutdown Circulation (SC) Sys
Page 133 and 134:
Page 135 and 136:
Page 137 and 138:
Page 139 and 140:
Page 141 and 142:
10.3.3 Non-nuclear InstrumentationU
Page 143 and 144:
Page 145 and 146:
11.5 Quality Assurance PlanUpdated
Page 147 and 148:
Page 149 and 150:
Page 151 and 152:
Page 153 and 154:
Page 155 and 156:
Deck/compartmentsUpdated Final Safe
Page 157 and 158:
Page 159 and 160:
Page 161 and 162:
Page 163 and 164:
Page 165 and 166:
Page 167 and 168:
Page 169 and 170:
show all

10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

Create successful ePaper yourself

Delete template?

Save as template?