05000321/LER-1979-086-03, /03L-0:on 791027,secondary Containment Violated by Simultaneous Opening of Airlock Doors Between Reactor Bldg & Radwaste Bldg.Caused Y Design Deficiency.Interlocking Scheme Under Review
BVY 05-062, Technical Specification Proposed Change No. 270 - Supplement No. 1 Administrative Changes - Response to Request for Additional Information
BVY 04-118, Technical Specification Proposed Change No. 270 Administrative Changes
BECO-89-018, Forwards Revs 25 & 26 to Procedure 8.7.3, Secondary Containment Leak Rate Test. Test Results Indicated Leakage in Excess of Tech Spec Acceptance Criteria
BECO-LTR-95-020, Forwards Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test. Secondary Leak Rate Test Satisfactorily Performed 941121.Test Verified Secondary Containment Integrity as Defined by PNPS TS 4.7.C.1
05000298/LER-1985-001, :on 840922,during Secondary Containment Leak Test,Fuel Handling Operations Conducted W/O Verification of Secondary Containment Integrity.Caused by Combination of Procedural & Personnel Errors
05000321/LER-1979-001-03, /03L-0 on 790109:during Steady State Power at 2400 Mwt,Plant Personnel Inadvertently Opened Both Doors of Reactor Bldg 130-ft Airlock R106.For Reasons Unknown,Switch Which Allows Defeat of Interlock Was Operated
05000254/LER-1991-011-02, :on 910813,determined That Differential Pressure Could Not Be Maintained During Secondary Containment Capability Test.Caused by Air in-leakage Via Reactor Bldg Roof.Setpoint Changed
05000254/LER-1983-032-03, /03L-0:on 830901,while Preparing for Refuel Outage,Secondary Containment Capability Test Revealed Vacuum Attainment of 0.15-inch Water.Caused by Aged Gaskets on Personnel Access Doors.Gaskets Replaced
05000254/LER-1993-002-01, :on 930302,determined Average .25 Inches of Water Cannot Be Maintained in Secondary Containment Per Ts. Caused by Testing Deficiency.Procedure Qts 160-5 Will Be Changed to Adjust for Test Deficiency
BECO-LTR-93-088, Forwards Pilgrim Nuclear Power Station Procedure 8.7.3, Secondary Containment Leak Rate Test. Test Satisfactorily Performed on 930404 Prior to Refueling Outage 9 Fuel Offload
05000254/LER-1990-002-05, :on 900204,determined That Only Reactor Bldg Differential Pressure of 0.24-inch Water Vacuum Could Be Obtained,In Violation of Tech Spec Required 0.25 Inch.Caused by Testing Deficiency.Leak Paths Sealed
05000321/LER-1980-027-03, /03L-0:on 800310,during Review of Surveillance Schedule,Discovered Rod Block Monitor Functional Test & Calibr Not Performed within Required Interval.Caused by Personnel Oversight.Surveillance Acceptably Performed
05000321/LER-1980-028-03, /03L-0:on 800313 & 17,during Full Power Operation, Secondary Containment Integrity Momentarily Violated at 164 Ft Elevation Reactor Bldg Airlock.Caused by Design Deficiency.Design Change Request Has Been Written
05000321/LER-1979-011-03, /03L-0 on 790124:while in Cold Shutdown,Both Doors of Reactor Bldg Were Opened,Violating Secondary Containment. Bracket Into Which Dead Bolt Projects Was Bent,Preventing Interlock from Functioning.Bracket Was Repaired
05000293/LER-1917-004, Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System
BVY 05-105, Correction to Technical Specifications Pages
BECO-88-160, Advises That Secondary Containment Leak Rate Test Satisfactorily Performed on 880921.Test Verified Secondary Containment Integrity,As Defined by Tech Spec 4.7.C.1.C, Prior to RFO 7 CRD Venting