BVY 12-055, Technical Specifications Proposed Change 297, Supplement 1, Response to Request for Additional Information
BVY 10-045, Technical Specifications Proposed Change No. 289 Suppression Chamber-Drywell Vacuum Breakers and Differential Pressure
05000260/LER-1997-004-03, :on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule
05000321/LER-1981-014-03, /03L-0:on 810304,isolation Valves RHR Pump Suction E11-F004B,F030B,F065B,RHR Test Line E11-F024A,F027A,F028A, E11-F024B,F027B,F028B & HPCI Exhaust E41-F021,F049 Found Leaking.Cause Unknown.Valves Will Be Repaired
L-MT-04-003, License Amendment Request for Technical Specification Table 3.2.3 and Section 3.7/4.7
05000298/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl
IA-87-255, Final Response to FOIA Request.Documents Listed in Encl App a Re Pumps in RHR Sys Available in PDR
IA-97-382, Package Consisting of Various Printouts of Publicly Available Records Re SFP Leakage
JPN-89-062, Forwards Application for Amend to License DPR-59,revising Tech Specs to Reflect Exemption from 10CFR50,App J Re Containment Leak Rate Testing to Permit Repair of Weld 10-14-884A on Core Spray Test Return Line
BECO-87-002, Withdraws 851115 Application for Amend to License DPR-35, Changing Tech Spec Section 4.7.A.2.g Requiring Primary Containment to Be Continuously Monitored for Gross Leakage by Review of Inerting Sys Makeup Requirements
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
B16432, Provides NRC Current Position Re Unit 1 Purge/Vent Valves Resilient Seal Matl Replacement Time Interval as Discussed in TMI Action Item II.E.4.2
B11641, Responds to NRC 850731 Request for Review of Planned Plant Improvement Projects.Reviews of Integrated Safety Assessment Program Topics 2.01,2.05,2.06,2.07,2.10 & 2.23,forwarded
BVY-98-124, Responds to NRC Re Violations Noted in Insp Rept 50-271/98-09.Corrective actions:OT-3114,OP-2172 & OP-2143 Were Revised to Allow Only Single Feedwater Pump in Standby Mode at One Time & to Control re-energization of Oil Pump
NG-92-5179, Request for TS Change RTS-249 to License DPR-49,adding TS 3.0 & 4.0,corresponding Bases & Modifying Existing Specs Consistent W/New Requirements Denoting Applicability of LCOs & Srs,Per STS & GLs 87-09 & 89-14
HL-3048, Application for Amend to License DPR-57,revising TS Re Removal of Primary Containment Isolation Valves E11-F022 & E11-F023
NLS8400242, Submits List of Actions Taken on Recommendations from GE 840214 Svc Info Ltr 402, Wetwell/Drywell Inerting. Evaluation of Inerting Sys Design Determined That Failure of Cold Temp Shutdown Switch Cause of Problem
BVY-95-123, Provides 30 Day Response to NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode
NG-95-2971, 1995 Cyclic Rept of Facility Changes,Tests & Experiments & Fire Plan Changes, Covering Period from 940101 - 951001.W/
BECO-92-039, Application for Amend to License DPR-35,changing TS Section 4.7 Re Primary Containment Integrity to Remove Words Each Operating Cycle for MSIV & Personnel Airlock Door Testing
NG-94-2629, Application for Amend to License DPR-49,proposing Changes to Ts,By Increasing Allowable Main Steam Isolation Valve Leakage & Deleting TS Requirements Applicable to MSIV LCS
NG-93-5095, Forwards Reactor Containment Bldg ILRT Types A,B & C Periodic Test Rept for 1993 Refueling Outage,Including Apps Consisting of Results & Analysis of Type B & Type C Tests Performed Prior to & During Refueling Outage
RA-10-027, Technical Specification Change Request No. 356, Elimination of Daily Testing of an Operable Emergency Diesel Generator (EDG) When the Other EDG Is Declared Inoperable
B11766, Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 860131
05000298/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Submitted
05000254/LER-1989-002, :on 890109,total of Combined Local Leak Rate Test Interval on MSIV Exceeded Specified Surveillance Interval of 18 Months.Caused by Misinterpretation of Tech Specs.Tech Specs Revised
05000245/LER-1989-008, :on 890414,leakage Noted in Excess of Flow Instrumentation.Cause Not Known at Present.Atmospheric Control Valves Which Failed to Pass Local Leak Rate Test Will Be Inspected & Repaired as Required
05000321/LER-1987-009, :on 870427,primary Containment Penetrations Found Leaking in Excess of Leakage Requirements.Caused by Normal Use & Wear.Valves Either Cycled,Repaired,Rebuilt, Replaced or Plugged Until Replacement
05000298/LER-1998-008, :on 980804,TS Violation Was Noted Due to Missed Testing of RB Suppression Chamber Vacuum Breakers.Caused by Misinterpretation of Ts.Valves Tested IAW TS Requirements
05000245/LER-1987-015, :on 870606,during Refueling Outage,Addl Isolation Valves Did Not Meet Local Leak Rate Test (LLRT) Requirement,Per Tech Spec 4.7.f.2.c.LLRT Requirement Satisfactorily Retested Subsequent to Repair
05000333/LER-1987-001, :on 870118,valves on Six Primary Containment Penetrations Found W/Leakage Exceeding Tech Specs Limits. Cause of Failure Attributed to Wear.Valve Stem Repacked & Seating Surface Reconditioned
05000245/LER-1987-015-01, :on 870606,during Local Leak Rate Testing, Discovered That B Main Steam Isolation Valves Could Not Meet Required Leak Rate Test.Causes Listed.All Failed Valves Repaired & Retested Satisfactorily
05000321/LER-1986-027, :on 860612,drywell Vent Valves 1T48-F319 & F320 Failed to Pressurize During Special Purpose Procedure 42SP-061286-OU-1S Re Local Leak Rate Test.Caused by Damaged T-ring.T-ring Replaced
05000263/LER-1986-012, :on 860508 Five Penetrations of Transversing in-core Probe Sys Omitted from double-gasket Seal Testing Procedure.Procedure Revised.Penetrations Tested & Drawings Reviewed
05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
05000333/LER-1997-010-01, :on 971021,determined That Surveillance Testing of Primary Containment Pressure Chamber,Drywell Vacuum Breakers Coincident W/Loca.Caused by Inadequate Procedures Reviews.Procedures Revised
05000333/LER-1998-013, :on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup
05000293/LER-1986-011, :on 860419,during Local Leak Rate Testing of Msiv,Five Atwood & Morrill Y-Pattern,20-inch,Model 20849-H MSIVs Discovered to Have Leakage in Excess of Tech Spec 4.7.A.2 Requirements
05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
05000298/LER-1978-030-03, /03L-0:on 780815,13 Primary Containment Penetrations Not Leak Tested.Caused by Penetrations Not Identified During Preoperational Testing.Penetrations Will Be Added to Tech Spec Table 3.7.2 & Will Be Tested
05000321/LER-1985-047, :on 851220,use of GE Silicone Sealant (RTV-102) on Both Drywell Personnel Airlock Doors Prevented Adequate Leak Rate Testing of Door Seals.Caused by Personnel Error. New Seals Installed
05000254/LER-1986-001-02, :on 860106,during Shutdown,Discovered That Measured Combined Leakage Rate for All Penetrations & Valves Except MSIVs in Excess of 293.75 Scfh.Cause Undetermined. Corrective Action Delayed Until Rept Completed
05000271/LER-1986-001, :on 860107,during Pipe Replacement Outage, Discovered That Containment Isolation Valves Not Accounted for in App J Program.Caused by Failure of Personnel.App J Program Will Be Updated to Include Subj Valves
05000298/LER-1985-005, :on 850818,discovered Two Type B & Nine Type C Penetration Failures During Primary Containment Local Leak Rate Testing,Resulting in Excessive Leak Rate.Cause Not Stated.Valves Replaced or Repaired
05000333/LER-1985-008, :on 850301,during 1985 Refueling Outage,Five Penetrations Showed Leakage Possibly Exceeding 0.6La Limit in Tech Spec 4.7.A.2.b.2.Caused by Normal Wear.Valve Repairs &/Or Replacements Successfully Completed
05000245/LER-1997-011-01, :on 970214,discovered TS Surveillance Requirement 4.7.A.3.d,containment Airlock Leakage Rate Test, Exceeded.Caused by Personnel Error.Unit Surveillance Coordinator Rescheduled Containment Airlock Leak Rate Test
05000259/LER-1985-008, :on 850318,HPCI & RCIC Turbine Exhaust Valve Flanged Bonnets Not Local Leak Tested in Accordance w/10CFR50,App J Requirements.All Valves Will Be Repaired & Pass Leak Test
05000333/LER-1992-027, :on 920516,CS Isolation Testable Check Valve 14A0V-13A Exhibited Seat Leakage in Excess of TS Limit Due to Misalignment by One Bolt Hole.Valve Bonnet Correctly Aligned W/Valve Body
05000278/LER-1992-002, :on 920117,discovered That DW Oxygen Concentration Level Exceeded Value Specified in Ts,Due to an Analyzer Failure.Round Sheets Have Been Revised to Include Instrument Nitrogen Compressor Run Times
05000259/LER-1985-008-02, :on 850315,discovered Listed Valves Not Local Leak Tested.Caused by Failure to Identify Valves Per 10CFR50.Two Valves Failed Subsequent Test & Unit Manually Scrammed.Two Other Valves to Be Modified
05000265/LER-1985-007-07, :on 850318,while Performing Refueling Outage Local Leak Rate Testing,Measured Combined Leakage Rate in Excess of 293.75.Probable Cause Unknown.Supplemental Repair Rept Will Be Submitted
05000254/LER-1996-008-02, :on 960607,TS Required Pressure Not Met During Local Leak Rate Testing.Caused by Procedural Deficiency. Procedure Changes Submitted & Check Valves Retested Using Appropriate Vent Paths
05000331/LER-1985-005, :on 850206,four MSIVs Failed to Meet Leakage Criteria of 11.5 Std Cubic Ft/H.Probably Caused by Seat & Disc Wear.Valves Being Repaired
05000333/LER-1992-033, :on 920617 & 25,determined That Type B Local Leak Rate Testing Program Per TS 4.7.A.2.b.1 for Primary Containment Penetrations Contained Deficiency.Caused by Personnel Error.Procedures Changed
05000321/LER-1991-032, :on 911228,missed TS Required Surveillance Noted.Caused by Personnel Error.Personnel Counseled & Training Will Be Given to Operations Shifts Re Event
05000271/LER-1995-015, :on 950720,determined That TS SR 4.7.A.4 Exceeded for Valve SB-16-19-A (AC-8) Due to Inadequate Procedure.Flange for Valve AC-8 Tightened & Leakage Path Eliminated
05000293/LER-1991-023, :on 910728,11 of 76 Drywell Head Bolts Discovered Loose During Integrated Leak Rate Test.Caused by Failure of spherical-type Washer Sets & Use of Wrong Matl. Washer Sets Replaced & Procedure Revised
05000321/LER-1991-024, :on 911016,determined That Procedure Re Surveillance Checks of Torus Oxygen Concentration Not Performed Once Per Day.Caused by Misinterpretation of Ts. Procedure Revised to Require Daily Check
05000260/LER-1982-037-03, /03L-0:on 821122,while Performing Local Leak Rate Tests During Refueling Outage,Total as-found Leakage from Primary Containment Found Greater than Allowable,Per Tech Spec 4.7.A.2.g.Caused by Deterioration of Valve Seating
05000293/LER-1994-007, :on 941228,primary Containment Pressure Boundary Degraded Due to Uninstalled Instrument Plug.Caused by Personnel Error.Isolation Valves Will Be Installed on Selected Instruments
05000278/LER-1993-007, :on 930820,identified That Stated Surveillance Test Not Performed Prior to Exceeding TS Out of Surveillance Date,Resulting in Violation on 930808.Caused by Inadequate Review.Personnel to Be Counselled
05000277/LER-1990-028, :on 900801,discovered Missed Surveillance on Drywell Suppression Chamber Vacuum Breaker
05000331/LER-1993-005, :on 930801,unacceptable MSIV Leak Rate Results Due to Excess Leakage Msiv.Replaced Integral Valve Seat & re-machined Valve Bore
B14524, Application for Amend to License DPR-21,revising TS to Eliminate Exemption Granted on 850510 for Air Lock Testing & Require Facility to Meet Paragraph III.D.2(b)(ii) of App J
05000298/LER-1993-020, :on 930507,determined That H2/O2 Sys Not Leak Tested to Verify Primary Containment Integrity During Testing of Sys.Caused by Failure to Have Administrative Controls in Place.Pressure Testing Conducted
05000293/LER-1990-007, :on 900507,discovered That Drywell to Suppression Chamber Vacuum Breaker Surveillance Not Performed Prior to Startup in 1988.Caused by Misunderstanding of Requirements
JPN-93-044, Proposed Tech Spec 4.7.A.2.f Re Containment Leak Rate Testing
05000321/LER-1981-125-03, /03L-0:on 811123,leakage Rate on Drywell Personnel Airlock Innerspace Exceeded Tech Specs.Caused by Leaking Inner & Outer Door Seals & O Ring Seal on Inside Shaft of Inner Door.Seals Replaced & Ring Seal Tightened
05000271/LER-1993-003, :on 930205,identified That Portions of Primary Containment Hydrogen/Oxygen Monitoring Sys Not Properly Leak Tested.Caused by Inadequate Procedure.Procedure OP 4029 Revised
05000293/LER-1990-004, :on 900316,leakage for Feedwater Check Valves Found to Be in Excess of Limits.Caused by Damaged Soft Seat & Inconsistencies in Valves.Soft Seat Matl & Bushings in Valves Replaced & Hinge Pins Reinstalled
05000293/LER-1980-020-03, /03L-0:on 800426,during Refueling Outage 4,14 Primary Containment Isolation Valves Found to Have Seat Leakage Over Requirements.Caused by Normal Deterioration of Disc to Seat Mating Surface
05000265/LER-1981-018-03, /03L-0:on 810908,09,14,15,17,22,23 & 24 While Performing Main Steamline Local Leak Rate Tests,Ten Occurrences of Excessive Leakage Were Measured W/Respect to Primary Containment Isolation Valves
05000259/LER-1982-078-01, /01T-0:on 821012,pressure Used to Comply W/Tech Spec 4.7.A.2.j Found to Be Nonconservative.Caused by Personnel Error Due to Incorrectly Typed Equations for Gross Leak Rate for Temp & Pressure.Procedure Revised
05000331/LER-1983-021-01, /01T-0:on 830527,containment H202 Analyzer Channel a Rendered Inoperable.Caused by Calibr Difficulties Due to Fouled Pressure Regulators Resulting from Sys Contamination. Tech Specs Revised
05000259/LER-1983-020-01, /01T-0:on 830418,line A,B,C & D MSIVs Exceeded Allowable Leakage Rates.Caused by Deterioration of MSIV Seating Surfaces During Operation.Valves Will Be Repaired Prior to Startup & MSIV Improvement Program Implemented
05000245/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Encl
05000298/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted
05000298/LER-1981-015-03, /03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed
05000321/LER-1981-045-03, /03L-0:on 810526,vacuum Relief Valves T48-F310 & F328A Found Leaking Excessively During Local Leak Rate Test. Caused by Leaking o-ring & t-ring.Rings Replaced,Valves Reassembled & Retested
05000321/LER-1981-027-03, /03L-0:on 810406,feedwater Valve B21-F032A Was Determined Not to Pressurize.Caused by Excessive Leakage. Investigation Underway.Valve Will Be Repaired
05000321/LER-1981-016-03, /03L-0:on 810306,review of Data Sheets from 810304 LLRT of Inboard MSIVs B21-F022A,B & C Determined That Valves Were Leaking in Excess of Tech Spec.Cause Unknown. Investigation Underway.Valves Will Be Repaired & Retested
JPN-90-008, Forwards Application for Amend to License DPR-59,revising Tech Spec Section 4.7.A.2 & Associated Bases Re Primary Containment Leak Rate Testing Requirements
05000321/LER-1981-022-03, /03L-0:on 810319,purge Exhaust Emergency Valves T48-F334A & F335A Determined Leaking at Fast Rate,Possibly Causing Overall Leakage Limit to Exceed Tech Spec.Cause Unknown.Valves Repaired & Retested.Updated Rept Forthcoming
05000321/LER-1981-023-03, /03L-0:on 810319,reactor Core Isolation Cooling Turbine Exhaust Valve E51-F001 Was Determined to Be Leaking. Cause Unknown.Investigation Underway
05000254/LER-1980-021-03, Fifth of Five LERs 80-021/03L-0:on 800904,during Local Leak Rate Testing,Containment Purge Vol Bounded by Valves AO 1-1601-21,22,55 & 56 Found to Have Excessive Leak Rate. Cause Not Stated.Containment Purge Valves Will Be Re
05000259/LER-1980-003-03, /03L-0:on 800112,while Performing Local Leak Rate Testing During Refueling Shutdown,Path Leakage Through MSIVs for 3 of 4 Main Steam Lines Exceeded Leak Rate Per Tech Specs.Caused by Normal Wear & Erosion
05000265/LER-1979-027-03, /03L-0:on 791126,six Occurrences Identified Whereby Excessive Leakages Were Measured W/Respect to Primary Containment Isolation Valves During Local Leak Rate Testing.All Valves to Be Repaired & Tested
05000321/LER-1978-008-01, /01T-0 on 780209:during Steady State Power Operation,Test Valve Found to Be Broken Off.Cause Unknown. Valve Repaired.Investigation Under Way
05000260/LER-2078-009, For Browns Ferry Nuclear Plant, Unit 2, Local Leak Rate Tests of All Containment Isolation Valves Where Leak Rate Exceeded Allowable Leak Rate of 60 Percent of La Per 24 Hours or 707.1 Scfh
05000260/LER-2078-006, For Browns Ferry Nuclear Plant, Unit 2, Check Valve 2-73-603 in High-Pressure Coolant Injection System Was Found in Open Position During Maintenance Inspection After Failing Local Leak Rate Test
05000259/LER-2078-205-01, Four Main Steam Isolation Valves Which Exceeded the Leakage Limits of Technical Specification 4.7.A.2.i While Performing Local Leak Rate Testing During Refueling
05000260/LER-1993-011-01, :on 930525,facility Started W/Invalid LLRT Having Been Performed on Drywell Head Seals.Initial Investigation Determined That RTV Applied W/O Approved Procedure.Incident Investigation Being Conducted
05000260/LER-1993-010-01, :on 940822,discovered That on 930525,primary Containment for Facility Restored W/O LLRT Having Been Performed Due to Inadequate Procedures & Drawings.Applicable Drawings & Procedures Will Be Revised
05000260/LER-1980-038-03, /03L-0:on 800911,during Refueling Outage W/Unit in Cold Shutdown,Hpci Check Valve 2-73-609 Failed Local Leak Rate Test.Caused by Buildup of Residual Matl on Body,Causing Disc of Hcpi Valve to Be Cocked Open.Matl Removed
05000296/LER-1979-014-03, /03L-0:on 790831,five MSIVs Exceeded Tech Spec Leakage Limits.Caused by Age & Use of Seating Surfaces.Valve Seating Surfaces Will Be Repaired & MSIVs Retested to Meet Tech Specs
05000296/LER-1979-021, Supplemental LER 79-021/01T-1:on 791208,following Return to Svc After Refueling Outage,Primary Containment Pressure Would Not Stabilize.Caused by Leaking Due to Unevenly Tightened Bolts.New Controls & Hatch Lock to Be Used
05000296/LER-1979-021-01, /01T-0:on 791208,following Refueling Outage & Unit 3 Return to Svc,Excessive Drywell Leakage Occurred.Caused by Loose Bolts Around Hatch Door.Bolts Were Retightened & Administrative Controls Initiated to Verify Seal Worthine
05000237/LER-1977-058, /01T-0 for Dresden, Unit 2 Re During Refueling Tests Required by LLRT Procedure Dts 1600-1, Torus Air Sample Line Isolation Valves 8501-1A and 1B Had Through Leakage in Excess of Single Valve Ad Penetration Limits
05000249/LER-1978-003, /01T-0 for Dresden 3 Regarding Discovery of Containment Valve Leakages in Excess of Technical Specification 4.7.A Limits
05000249/LER-1988-001, :on 880105,discovered That 41 Individual Type B & C Local Leak Rate Tests Performed During Previous Refueling Outage Had Individual Testing Intervals Exceeding 24 Months.Review Conducted
05000331/LER-1981-013-01, /01T-0:on 810324,MSIVs 4412,4413,4416,4418,4419, 4420 & 4421 Found W/Seat Leakage on Inboard & Combined Seat & Steam Leakage on Outboard Valves.Cause Under Investigation.Valves Will Be Repacked & Repaired
05000293/LER-2011-004, For Pilgrim Nuclear Power Station, Regarding Technical Specification Required Shutdown - Drywell to Torus Dp
BVY 05-098, Technical Specification Proposed Change No. 263 - Supplement No. 38 Extended Power Uprate - Containment Overpressure Credit
05000333/LER-2000-015-02, Re Containment Leakage Rate Exceeds Authorized Limits
BECO-LTR-96-092, Submits Response to NRC Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers,
JPN-89-029, Forwards Application for Amend to Tech Specs Revising Tech Spec 4.7.A.3, Continuous Leak Rate Monitoring, to Remove Misleading Ref to Continuous Leak Rate Monitoring Sys
B11586, Forwards Addl Info Re NUREG-0737,Item II.F.1.6, Containment Hydrogen Monitoring Sys, for Millstone Unit 1 & Documents Telcons Re Items II.F.1.4 & II.F.1.5 for Haddam Neck Plant
05000321/LER-1981-024-03, /03L-0:on 810401,data Sheets from 810325 & 28 Local Leakage Rate Tests Showed Valves Leak Rate Could Exceed Tech Spec Limit.Cause of Leaking Unknown. Investigation Underway
05000296/LER-1979-017-79, /03L-0:on 790917,during Leak Rate Testing,Total Leak Rate Exceeded Tech Spec Limit.Caused by Deterioration of Valve Seats Through Normal Operation on Main Steam & Containment Inerting Sys.Valves Will Be Repaired & Retested
05000331/LER-1992-009, :on 920301,during Local Leak Rate Testing,Three of Eight MSIVs Failed to Meet Established Acceptance Criteria.Caused by Improper Positioning of Disk Piston.Msivs Remachined to within Design Specs
05000333/LER-1995-011-01, :on 950531,leakage of Primary Containment Isolation Valves Was Exceeded.Caused by 02-2AOV-39 & 02- 2AOV-40 Experiencing Repeated Difficulty in Passing Llrt. Flushed Seat on Inboard Isolation Valve
05000277/LER-1991-012-01, :on 910514,discovered That Primary Containment Isolation Valve on Units TIP Sys Purge Lines Not Being Leak Tested.Caused by Inadequate Review of TIP Sys Purge Piping. Procedure Revised to Allow Testing Downstream
B13666, Rev 4 to Millstone Nuclear Power Station Unit 1 Inservice Test Pump & Valve Program