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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20100H458  + (ML20100H458)
• 05000269/LER-1995-008, :on 951129,determined That Containment Isolation Valve Inoperable Due to Deficient Design Change. Valve 3RC-5 Disabled in Safety Position (Closed) Until Gear Ratio in Valve Corrected  + (ML20100H467)
• ML20100H475  + (ML20100H475)
• ML20100H487  + (ML20100H487)
• ML20100H491  + (ML20100H491)
• ML20100H494  + (ML20100H494)
• ML20100H503  + (ML20100H503)
• ML20100H509  + (ML20100H509)
• B11460, Responds to Insp Rept 50-336/85-01 Re NRC 850107-11 Audit of Work Performed in Response to IE Bulletins 79-02,79-04,79-07 & 79-14.Info Re Listed Items Concerning IE Bulletin 79-02 Will Be Submitted by 850401,per Varela 850111 Request  + (ML20100H516)
• GO2-96-029, Forwards Resignation Ltrs & Appointment & Acceptance Re Decommissioning Trust Fund Trustee  + (ML20100H520)
• ML20100H521  + (ML20100H521)
• ML20100H525  + (ML20100H525)
• ML20100H528  + (ML20100H528)
• ML20100H529  + (ML20100H529)
• ML20100H530  + (ML20100H530)
• ML20100H546  + (ML20100H546)
• ML20100H549  + (ML20100H549)
• RBG-19467, Interim Deficiency Rept DR-188 Re Hubs on Socket Weld Flanges Supplied by West Jersey Mfg Co.Next Rept Will Be Submitted by 841207  + (ML20100H550)
• RBG-19466, Interim Deficiency Rept DR-184 Re Shop Weld on Bf Shaw Co Support Trunnion.Next Rept Will Be Submitted by 850109  + (ML20100H567)
• 1CAN118413, Forwards Summary Results of Upper Core Barrel Bolt Replacement & Stress Analysis of Upper Core Barrel Joint W/Reduced Number of Bolts.Reactor Vessel Internal Bolting, Addl Insps & Bolting Replacements Satisfactory  + (ML20100H568)
• ML20100H572  + (ML20100H572)
• PMNS20200380, Public Meeting to Discuss NRC Information Needs to Review Amendment Requests Related to Technical Specifications Task Force (TSTF)-505  + (ML20100H578)
• ML20100H582  + (ML20100H582)
• ML20100H587  + (ML20100H587)
• ML20100H599  + (ML20100H599)

• ML20100H601  + (ML20100H601)

• L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1  + (ML20100H605)
• A04183, Forwards Response to NRC & Revised Pages to Draft Physical Security Plan.Encl Withheld (Ref 10CFR73.21 & 10CFR2.790)  + (ML20100H609)
• ML20100H612  + (ML20100H612)
• ML20100H623  + (ML20100H623)
• ML20100H625  + (ML20100H625)
• ML20100H629  + (ML20100H629)
• ML20100H631  + (ML20100H631)
• ML20100H635  + (ML20100H635)
• PY-CEI-NRR-2028, Forwards Rev 21 to PNPP Security Plan,Per 10CFR50.54(p). Encl Withheld  + (ML20100H639)
• 3F0296-20, Discusses Info Re NRC Response Technical Manual Training Session  + (ML20100H642)
• ML20100H673  + (ML20100H673)
• ML20100H682  + (ML20100H682)
• ML20100H698  + (ML20100H698)
• ML20100H722  + (ML20100H722)
• HL-5004, Application for Amends to Licenses DPR-57 & NPF-5, Respectively,Revising Changes of Drywell Air Temp LCO from 135 F to 150 F  + (ML20100H739)
• ML20100H743  + (ML20100H743)
• 05000445/LER-1996-002-01, :on 960122,loss of MFW Flow Due to FW Isolation Valves Closing Resulted in Manual Rt.Caused by Less than Adequate Initial Troubleshooting Plan.Revised Operations Procedures  + (ML20100H753)
• U-602549, Application for Amend to License NPF-62,proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier  + (ML20100H762)
• 05000388/LER-1984-026-01, :on 841029,during Installation of Mod,Open Penetration Found in Fire Barrier.Caused by Penetration Not Being Sealed During Const.Surveillance Procedure Revised to Clarify Insp Criteria  + (ML20100H770)
• W3P84-3145, Forwards Updated Const Status Rept as of 840930 for Next Issuance of Yellow Book (NUREG-0030),per NRC 811031 Request  + (ML20100H772)
• ML20100H774  + (ML20100H774)
• U-602554, Application for Amend to License NPF-62,deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Change TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function  + (ML20100H785)
• ML20100H790  + (ML20100H790)
• 05000373/LER-1984-063-01, :on 841010,snubber on Reactor Recirculation Pump a Seal Purge Line Found Locked Up & Rigid.Caused by Snubber Being Stepped on or Used as Hand Hold.Snubber Replaced  + (ML20100H800)
• U-602551, Application for Amend to License NPF-62,changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv  + (ML20100H801)