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

More documents

Recommendations

Info

Updated Final Safety Analysis Report – (STS-004-002)The NSS has four remaining safety features in the power plant design that merit specialmention:1. Reactor System Containment - The reactor and primary coolant system are located inside acontainment vessel. During the operating period, any failure of the primary system wouldhave been contained by the containment vessel system. The CV system, consisting of aUSCG approved pressure vessel and associated isolation valves, was designed andhydrostatically tested to withstand a pressure of 173 psig. During the operating period, thesystem was routinely pneumatically tested at 60 psig and demonstrated to have a leak rateof less than 1.2% of the contained volume per day. No integrated leak rate testing has beenperformed since the final shutdown in November 1970.2. Containment Vessel Isolation – During the operating period, the reactor system wasoperated with the CV hermetically sealed at all times. The penetrating pipe lines wereisolated by automatic valves if the pressure inside the containment vessel rose above 5 psigfor any reason whatsoever. The steel containment vessel, moreover, was sufficiently thickthat no danger of penetration existed from any high speed missiles within the containmentvessel, such as a thermocouple well from the primary coolant system. No individualpenetrations have been leak rate tested since the final shutdown in November 1970.3. Radioactive Waste Control - During the operating period, the power plant operated with aminimum of radioactive waste disposal. Gaseous and liquid wastes were discharged inaccordance with the “Standards for Protection Against Radiation” (10 CFR Part 20) andthe Technical Specifications. Any solid wastes are kept aboard the ship and periodicallydischarged to a licensed waste disposal facility.4. Shielding – During the operating period, the reactor vessel was surrounded laterally by 33inches of water and 1 to 4 inches of lead shielding so that maintenance work was possibleshortly after shutdown. In 1976, the reactor vessel shield water tank was drained. Thesecondary shielding around the containment vessel reduced the surface dose level at fullreactor power to no more than 100 mR per week.1.3 Ship and System Status – 1976 to Present1.3.1 Power Plant Status as reported in April 1976In support of the request for a possession only license in 1976, MARAD provided a “current” (i.e.,contemporary) status of the ship. The April 1976 status of the NSS reactor plant followingprotective storage modifications to its operating condition was noted as follows:1. Reactor Vessel - All 32 Core Ia fuel elements were removed from the reactor vessel to the spentfuel pool at the MARAD Refueling Facility, Todd Shipyards, Galveston, TX [License SNM-1015-YGP (Docket 70-1062)]. All reactor internal components are in place, i.e., core basket,upper grid plate, upper flow baffle. Thirty-six upper flow transition pieces and one irradiatedcontrol rod (cut in three pieces) have been loaded into six fuel element channels in the corebasket. Thirty-two upper flow transition pieces were from Core I and four were from Core Ia(i.e., the 1968 fuel shuffle). The additional control rod was the one replaced during the 1968fuel shuffle. The reactor head is in place with six of the original 48 reactor head hold downstuds tensioned.2. Spent Fuel - Per September 21, 1973, Operations Report, thirty six spent fuel elements (Core Iand Ia) were shipped from Galveston, TX to USDOE - Savannah River Plant, Aiken, SC in nineRev. VI 10
Updated Final Safety Analysis Report – (STS-004-002)shipments from October 4 through December 21, 1972 via a lowboy trailer using the Piqua/ElkRiver Shipping cask.3. Fission Chambers - Per September 21, 1973, Operations Report, five fission Chambers wereremoved and shipped to Todd Shipyards, Galveston, TX in May 1973. On June 28, 1973, thesefive and an additional three stored on the NSV Atomic Servant (the nuclear services barge forNSS) were shipped to Chem-Nuclear Systems, Inc., Barnwell, SC for disposition as radioactivematerial.4. Pressurizer - One relief valve PR-1V was removed. The nozzle flange was fitted with anabsolute filter vent to allow for pressure equalization. Circuit breakers for the heaters have beenopened at the switchboard.5. Control Rod Drive System -a. Electrical - The breakers for the rod drives have been opened and tagged in the ControlRod Drive Electrical Cubicle and the Control Room. The cables between the junctionboxes on the Control Rod Drive (CRD) structure and the junction boxes located around theperiphery of the cupola have been disconnected, coiled and secured on the CRD structurein the containment vessel. The support wireways have been removed, packaged and storedin Hold No. 4. In addition, the twenty one buffer seal flow meter cables and the vibrationmonitor cables have been disconnected.b. Mechanical - All hydraulic oil has been drained and the piping disconnected between thecupola and the CRD structure. Buffer seal system valves have been closed and tagged out.The inlet and outlet header spool pieces between the cupola and structure were removed.The buffer seal system has been drained.The 21 control rods were disconnected from their respective CRD extension shafts andremain in their fully inserted position between the empty fuel location channels. The CRDextension shafts have been disconnected from the lead screw and are in a fully insertedposition from the reactor head nozzles to the top of the control rods. The CRD lead screwswere withdrawn and pinned in place. Steel caps are placed onto the 21 reactor headnozzles to completely seal the nozzle from the containment vessel atmosphere andmechanically separate the CRD mechanism from the control rod.6. Primary Coolant System - The system has been drained as completely as practical. All loopisolation inlet and outlet valves are open and back seated.Primary Pump motors and impellers were removed. Blank flanges are installed over the voluteopenings. The grating, piping, valves, ducting, etc. that were disconnected while removing thepump motors and impellers are left in the removed condition within the containment vessel.7. Secondary System - Both steam generators and piping were drained of water as completely aspractical. The water on the secondary side of the steam generators was transferred to the doublebottom tank below the reactor compartment. The isolation valves outside of the containmentvessel are closed. There have been no modifications to the secondary system.Rev. VI 11
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 27: Updated Final Safety Analysis Repor
Page 33 and 34: U p da te d Fi na lS af et yA n al
Page 43 and 44: 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 83 and 84:
Updated Final Safety Analysis Repor
Page 85 and 86:
Page 87 and 88:
7.5 Primary PumpsUpdated Final Safe
Page 89 and 90:
Page 91 and 92:
8.1.3 Construction Features8.1.3.1
Page 93 and 94:
Page 95 and 96:
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 ...

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?