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| #REDIRECT [[05000311/LER-1982-024]] | | {{Adams |
| | | number = ML20076M601 |
| | | issue date = 06/29/1983 |
| | | title = Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added |
| | | author name = Frahm R, Zupko J |
| | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | | addressee name = Allan J |
| | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | | docket = 05000311 |
| | | license number = |
| | | contact person = |
| | | document report number = LER-82-024-03X, LER-82-24-3X, NUDOCS 8307210009 |
| | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | | page count = 5 |
| | }} |
| | {{LER |
| | | Title = Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added |
| | | Plant = |
| | | Reporting criterion = |
| | | Power level = |
| | | Mode = |
| | | Docket = 05000311 |
| | | LER year = 2082 |
| | | LER number = 24 |
| | | LER revision = |
| | | Event date = |
| | | Report date = |
| | | ENS = |
| | | abstract = |
| | }} |
| | |
| | =text= |
| | {{#Wiki_filter:a, ~ |
| | fr 77) |
| | LICENSEE EVENT REPORT CONTROL BLOCK: l i |
| | l l l l l jh (PLE ASE PRINT CR TYPE ALL RECulRED INFOIMATIEN) 7 o 1 s9 lN l JLICENSEEl S lG CODE lS l142 l@16 oj ol -lLICENSE 0l 0lNJWBER 0] 0] Ol -l 0l 0l@l 26 26 4 lLICENSE 1l 1lT1] YPE1l@l JO l |
| | S1 C AT 66 lg CON'T o i E' '" LIJ@l 01 s1 01 0101 31 11 66il@l6901312 l 8 l 8 l 2jgl075 l 6#El PORT F4 2 l D9ATEl 8 l 3 lg 7 s 60 61 DOCKET NUMBER EVENT DATE SC EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h g lon March 28, 1982, sample results from Nos. 21 and 22 Boric Acid Storage Tanks (BATS) g gand the Boron Injection Tank (BIT) indicated the boric acid concentrations were below g o a lthe specification limit of 20,000 ppm boron. At 1500 hours, Nos. 21 and 22 BATS were g g g eclared d inoperable and Action Statement 3.1.2.6.a was entered. The BIT was declared g o 6 l noperable at 1620 hours, and Action Statement 3.5.4.1 was entered. The refueling g y l water storage tank rcn.ained c.perable and no transient initiating Rasctor Cool &nt y o8 lEystem was involved. g 7 se s: |
| | SYSTEM CAUSE CAUSE COv P. VALVE CODE CODE SU8 CODE COV'ONENT CODE SUBCCDE susCODE 7 |
| | O 9 s |
| | l Pl Clh Wh Wh l A lC lC lU lM lU lh Wh W h 9 10 11 12 13 18 19 20 SE QutNTI AL OCCup R E NCE REPORT REvtsiON LEn Ao EVENT YE AR REPORT NO. CODE TYPE NC h ,R E l8l2l 21 23 l 0 l2 l4 l 24 26 y |
| | 27 l 0] 3l 28 29 W |
| | 30 b31 |
| | { |
| | 32 22 T N AC ON ON PL NT WETb FOR 8. 5 PP l WAN FACT A[R d @!Zlh W h W h 33 34 36 l |
| | 37 MOURSgh ]g5 e{i g 0l 0l Oj 0 40 41 |
| | { g lX l9 l9 l9 lg 3t 42 43 A4 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ITTTl INo apparent reason for the decrease in boric acid concentration could be determined. g g l Boric acid was added and recirculated, the tanks were returned to within specification,; |
| | , , gand the action statements were terminated. The procedures involved were reviewed and g 1 3 l revised to provide impreved operator guidance to ensure that batching operations are l |
| | , , gproperly completed. ; |
| | 7 se sc |
| | $ YAWS % POWE R OTHERSTATus DISCO RY DISCOVERv CESCRJTION i 5 W@ l0 l8 l5 "l@l" NA l W hl** Routine Sampling l |
| | 's.CTiviry CoYTENT CELE ASED 08 RELE ASE AwouNT OF ACTIVITY LOCATION OF RELE ASE 7 |
| | 1 6 e e W h dh! NA to : 44 l l as NA so l |
| | PER10NNEL EXPOSURES huweER TYPE DESCRIPTION i > |
| | I 01 01 Ol@l zl@l" Na I |
| | ,ERio~NEl'.~d4Es huwsER DESCRIPTION eeI d 01 d@l i a NA I i u u 8307210009 830629 so Loss or om oAuAct To raciuTv (Jh PDR ADOCK 05000311 T vP E oEsCRiPTioN v S PDR b seWhl 7 io NA so I $UE . . |
| | 3,s. h.DE CRIPTION l NA l 11llllilllIlII so |
| | * NAME OF PREPARER |
| | . ab PHONE (609) 935-6000 Ext. 4309j |
| | |
| | C PSIEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 7, 1983 Mr. J. Allan Acting Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 |
| | |
| | ==Dear Mr. Allan:== |
| | |
| | LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-24/03X-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1.9b, we are submitting supplemental Licensee Event Report for Reportable Occurrence 82-24/03X-1. |
| | Sincerely yours, |
| | .')fl.17 J. M. Zupko, Jr. |
| | General Manager - |
| | 3 Salem Operations RF:ks l |
| | CC: Distribution i 7n E: . I' a;' t (( |
| | g - , r , , + +- ---r- w--- - -, . _,---,S =-w- - - - - - + ~ - - - - |
| | |
| | Report Number: 82-24/03X-1 Report Date: 06-29-83 Occurrence Date: 03-28-82 Facility: Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE: |
| | Reactivity Control / Emergency Core Cooling Systems - |
| | Boric Acid Storage Tanks and Boron Injection Tank - |
| | Inoperable. |
| | This report was initiated by Incident Reports 82-064 and 82-065. |
| | CONDITIONS PRIOR TO OCCURRENCE: |
| | Mode 1 - Rx Power 85% - Unit Load 980 MWe. |
| | DESCRIPTION OF OCCURRENCE: |
| | At 1500 hours and 1620 hours, March 28, 1982, sample results from Nos. 21 and 22 Boric Acid Storage Tanks (BATS) and the Boron Injection Tank (BIT) respectively, indicated the boric acid concentrations were below the specification limit of 20,000 ppm boron. Nos. 21 and 22 BATS were declared inoperable and Action Statement 3.1.2.6.a was entered. The BIT was declared inoperable and Action Statement 3.5.4.1 was entered. |
| | The Refueling Water Storage Tank remained operable as a borated water source throughout the occurrence. No transient initiating Reactor Coolant System (RCS) cooldown occurred during the period in concern and immediate measures were taken to restore the required negative reactivity control during plant operation. |
| | DESIGNATION OF APPARENT CAUSE OF OCCURRENCE: |
| | No apparent reason for the decrease in boric acid concentration could be determined. The BAT and BIT results were consistent making it unlikely that the analyses were incorrect. Investi-gation of previous tank sample results showed no downward trend. |
| | All previous batches were accounted for in the logs, and had been sampled with satisfactory results prior to addition. Sample results of subsequent batches were realistic, indicating no problem with reagents or method. There was no safety injection flow into Unit 2 RCS during this period. All other major water sources adjacent to the boron injection system were borated to greater than 20,000 ppm. |
| | |
| | LER 82-24/03X-1 . |
| | DESIGNATION OF APPARENT CAUSE OF OCCURRENCE: (continued) |
| | A subsequent detailed review of the procedures for boric acid solution preparation and transfer (as well as BIT operations - |
| | see Unit 1 LER 83-018/03L) revealed that it would be appropriate to provide additional operator guidance to ensure proper completion of these evolutions. |
| | AN_ALYSIS OF OCCURRENCE: |
| | ' The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include: 1) borated water sources, |
| | : 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, 5) associated heat tracing systems, and 6) an emergency power supply from ope 5able diesel generat rs. With the RCS average temperature above 200 F, and a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. |
| | The boration capability of either flow path is sufficient to provide a shutdown margin from expected operating g conditions of 1.6% delta k/k after xenon decay and cooldown to 200 F. |
| | The operability of the boron injection system as part of the ECCS 1 |
| | ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by |
| | . RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture. |
| | The limits on injection tank minimum contained volume and boron concentration ensure that the assumptions used in the steam line break analysis are met. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. |
| | i Technical Specification 3.1.2.6.a requires: |
| | l With the boric acid storage system inoperable and being used as one of the required borated water sources, re-store the storage system to operable status within 72 hours, or be in at least hot standby within the next 6 hours and borated to a shutdown margin equivalent to at least 1% |
| | i delta k/k at 200 F. |
| | f Technical Specification 3.5.4.1 requires: |
| | With the BIT inoperable, restore the tank to an operable status within 1 hour, or be in hot standby and boraged to a shutdown margin equivalent to 1% delta k/k at 200 F |
| | !. within the next 6 hours. |
| | i In either case, the Technical Specifications require if the inoperable component (s) are not restored to an operable status within the next 7 days, be in hot shutdown within the next 12 hours. |
| | l i |
| | |
| | LER 82-24/03X-1 ANALYSIS OF OCCURRENCE: (continued) |
| | Since, as noted, the redundant injection system was operable, and the appropriate measures were taken to ensure reactivity control of the plant, no undue risk to the health and safety of the public was involved. The occurrence constituted operation in a degraded mode permitted by a limiting condition for operation, and is reportable in accordance with Technical Specification 6.9.1.9b. |
| | CORRECTIVE ACTION: |
| | Boric acid was added and recirculated. At 1720 hours, March 28, 1982, a sample of the BIT showed 19,950 ppm. Power reduction and preparation for entering Mode 3 were commenced in compliance with Action Statement 3.5.4.1. At 1910 hours, sample results showed the BIT boric acid concentration was within specification. |
| | The BIT was declared operable, and Action Statement 3.5.4.1 was terminated. Sample results indicated that the BAT boric acid concentrations were within specification limits at 0043 hours, March 29, 1982. Nos. 21 and 22 BATS were declared operable, and Action Statement 3.1.2.6.1 was terminated. |
| | Operating Instruction 01 II-3.3.5 " Boric Acid Solution Preparation and Transfer" was revised to provide greater detail and ensure the BATS are not diluted. Operating Instruction OI II-4.3.5 " Flushing, Draining and Filling the BIT" was also revised to provide detailed guidance for restoring the BIT to recirculation following either dilution or draining. |
| | FAILURE DATA: |
| | Not applicable Prepared By R. Frahm . . Y f General Manager - |
| | Salem Operations SORC Meeting No. 83-086 1 |
| | .. _ _ . . _ _ _ _ _ . - _ _ . _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ . . |
| | }} |
| | |
| | {{LER-Nav}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
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Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing 05000272/LER-1982-008, Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added1982-12-29029 December 1982 Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added 05000311/LER-1982-015, Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip1982-12-0808 December 1982 Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip 05000311/LER-1981-089, Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened1982-11-0303 November 1982 Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened 05000311/LER-1982-027, Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State1982-10-20020 October 1982 Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State 05000272/LER-1982-042, Supplemental LER 82-042/03X-1:on 820628,valves 12AF10 & 12AF86 Discovered Open.Caused by Personnel Negligence in Failure to Notice That Chains on Valves Improperly Installed.Valve Operation & Tagging Lesson Plans Revised1982-10-20020 October 1982 Supplemental LER 82-042/03X-1:on 820628,valves 12AF10 & 12AF86 Discovered Open.Caused by Personnel Negligence in Failure to Notice That Chains on Valves Improperly Installed.Valve Operation & Tagging Lesson Plans Revised 05000272/LER-1982-009, Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage1982-10-20020 October 1982 Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage 05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo1982-10-20020 October 1982 Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage 05000311/LER-1982-072, Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled1982-10-20020 October 1982 Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled 05000272/LER-1982-004, Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration1982-10-20020 October 1982 Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration 05000311/LER-1982-111, Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-241982-10-0404 October 1982 Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-24 05000311/LER-1982-084, Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress1982-08-30030 August 1982 Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress 05000311/LER-1982-074, Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges1982-08-18018 August 1982 Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges 05000272/LER-1982-0031982-05-26026 May 1982 LER 82-03L/031-0:on 820502,while Testing Valve 11SW122, Safeguards Equipment Control Cabinet Actuation Occurred. Caused by Locked Out Supply Breaker to Safety Injection Pump 11,due to Spurious Nature of Actuation 05000272/LER-1982-028, Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated1982-05-21021 May 1982 Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated 05000311/LER-1982-0191982-03-31031 March 1982 LER 82-019/03L-0:on 820307,undervoltage Condition in Safeguards Equipment Control Cabinet Caused Mod 1 2A Sec Actuation.Caused by Failure of Card File Assembly.Card File Assembly Replaced & Loads Secured.Sys Returned to Svc 05000272/LER-1982-0141982-03-31031 March 1982 LER 82-014/03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable 05000311/LER-1982-0181982-03-31031 March 1982 LER 82-018/03L-0:on 820304,steam Generator 24 Feedwater Channel 2 Flow Indicator Failed.Caused by Failure of Force Motor in Flow Transmitter.Transmitter Properly Repaired, Calibr & Returned to Svc 05000272/LER-1981-0921981-11-0202 November 1981 LER 81-092/01T-0:on 811020,during Routine Containment Insp, Operator Discovered Svc Water Leaking from Third from Top Secondary Coil on Containment Fan Coil Unit 15.Caused by Secondary Coil Failure.Leaking Coil Blank Flanged Off 05000311/LER-1981-0361981-07-0606 July 1981 LER 81-036/03L-0:on 810606,pressurizer Pressure Channel 1 Indicated Greater than Max Allowable Tolerance.Caused by Pressure Transmitter 2PT455 Out of Spec.Unit Calibr & Returned to Svc 05000272/LER-1976-030, Updated LER 76-030/03L:on 761228,during Sample Analysis of Boric Acid Storage Tanks 11 & 12,boron Concentration Noted Low.Cause Unknown.Chemical Analysis After Batching Confirmed Findings1978-04-0404 April 1978 Updated LER 76-030/03L:on 761228,during Sample Analysis of Boric Acid Storage Tanks 11 & 12,boron Concentration Noted Low.Cause Unknown.Chemical Analysis After Batching Confirmed Findings 1990-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
[Table view] |
LER-2082-024, Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added |
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LICENSEE EVENT REPORT CONTROL BLOCK: l i
l l l l l jh (PLE ASE PRINT CR TYPE ALL RECulRED INFOIMATIEN) 7 o 1 s9 lN l JLICENSEEl S lG CODE lS l142 l@16 oj ol -lLICENSE 0l 0lNJWBER 0] 0] Ol -l 0l 0l@l 26 26 4 lLICENSE 1l 1lT1] YPE1l@l JO l
S1 C AT 66 lg CON'T o i E' '" LIJ@l 01 s1 01 0101 31 11 66il@l6901312 l 8 l 8 l 2jgl075 l 6#El PORT F4 2 l D9ATEl 8 l 3 lg 7 s 60 61 DOCKET NUMBER EVENT DATE SC EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h g lon March 28, 1982, sample results from Nos. 21 and 22 Boric Acid Storage Tanks (BATS) g gand the Boron Injection Tank (BIT) indicated the boric acid concentrations were below g o a lthe specification limit of 20,000 ppm boron. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, Nos. 21 and 22 BATS were g g g eclared d inoperable and Action Statement 3.1.2.6.a was entered. The BIT was declared g o 6 l noperable at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, and Action Statement 3.5.4.1 was entered. The refueling g y l water storage tank rcn.ained c.perable and no transient initiating Rasctor Cool &nt y o8 lEystem was involved. g 7 se s:
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{ g lX l9 l9 l9 lg 3t 42 43 A4 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ITTTl INo apparent reason for the decrease in boric acid concentration could be determined. g g l Boric acid was added and recirculated, the tanks were returned to within specification,;
, , gand the action statements were terminated. The procedures involved were reviewed and g 1 3 l revised to provide impreved operator guidance to ensure that batching operations are l
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. ab PHONE (609) 935-6000 Ext. 4309j
C PSIEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 7, 1983 Mr. J. Allan Acting Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Allan:
LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-24/03X-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1.9b, we are submitting supplemental Licensee Event Report for Reportable Occurrence 82-24/03X-1.
Sincerely yours,
.')fl.17 J. M. Zupko, Jr.
General Manager -
3 Salem Operations RF:ks l
CC: Distribution i 7n E: . I' a;' t ((
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Report Number: 82-24/03X-1 Report Date: 06-29-83 Occurrence Date: 03-28-82 Facility: Salem Generating Station, Unit 2 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Reactivity Control / Emergency Core Cooling Systems -
Boric Acid Storage Tanks and Boron Injection Tank -
Inoperable.
This report was initiated by Incident Reports82-064 and 82-065.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 - Rx Power 85% - Unit Load 980 MWe.
DESCRIPTION OF OCCURRENCE:
At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> and 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, March 28, 1982, sample results from Nos. 21 and 22 Boric Acid Storage Tanks (BATS) and the Boron Injection Tank (BIT) respectively, indicated the boric acid concentrations were below the specification limit of 20,000 ppm boron. Nos. 21 and 22 BATS were declared inoperable and Action Statement 3.1.2.6.a was entered. The BIT was declared inoperable and Action Statement 3.5.4.1 was entered.
The Refueling Water Storage Tank remained operable as a borated water source throughout the occurrence. No transient initiating Reactor Coolant System (RCS) cooldown occurred during the period in concern and immediate measures were taken to restore the required negative reactivity control during plant operation.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
No apparent reason for the decrease in boric acid concentration could be determined. The BAT and BIT results were consistent making it unlikely that the analyses were incorrect. Investi-gation of previous tank sample results showed no downward trend.
All previous batches were accounted for in the logs, and had been sampled with satisfactory results prior to addition. Sample results of subsequent batches were realistic, indicating no problem with reagents or method. There was no safety injection flow into Unit 2 RCS during this period. All other major water sources adjacent to the boron injection system were borated to greater than 20,000 ppm.
LER 82-24/03X-1 .
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE: (continued)
A subsequent detailed review of the procedures for boric acid solution preparation and transfer (as well as BIT operations -
see Unit 1 LER 83-018/03L) revealed that it would be appropriate to provide additional operator guidance to ensure proper completion of these evolutions.
AN_ALYSIS OF OCCURRENCE:
' The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include: 1) borated water sources,
- 2) charging pumps, 3) separate flow paths, 4) boric acid transfer pumps, 5) associated heat tracing systems, and 6) an emergency power supply from ope 5able diesel generat rs. With the RCS average temperature above 200 F, and a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable.
The boration capability of either flow path is sufficient to provide a shutdown margin from expected operating g conditions of 1.6% delta k/k after xenon decay and cooldown to 200 F.
The operability of the boron injection system as part of the ECCS 1
ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by
. RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture.
The limits on injection tank minimum contained volume and boron concentration ensure that the assumptions used in the steam line break analysis are met. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
i Technical Specification 3.1.2.6.a requires:
l With the boric acid storage system inoperable and being used as one of the required borated water sources, re-store the storage system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a shutdown margin equivalent to at least 1%
i delta k/k at 200 F.
f Technical Specification 3.5.4.1 requires:
With the BIT inoperable, restore the tank to an operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in hot standby and boraged to a shutdown margin equivalent to 1% delta k/k at 200 F
!. within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i In either case, the Technical Specifications require if the inoperable component (s) are not restored to an operable status within the next 7 days, be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l i
LER 82-24/03X-1 ANALYSIS OF OCCURRENCE: (continued)
Since, as noted, the redundant injection system was operable, and the appropriate measures were taken to ensure reactivity control of the plant, no undue risk to the health and safety of the public was involved. The occurrence constituted operation in a degraded mode permitted by a limiting condition for operation, and is reportable in accordance with Technical Specification 6.9.1.9b.
CORRECTIVE ACTION:
Boric acid was added and recirculated. At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, March 28, 1982, a sample of the BIT showed 19,950 ppm. Power reduction and preparation for entering Mode 3 were commenced in compliance with Action Statement 3.5.4.1. At 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br />, sample results showed the BIT boric acid concentration was within specification.
The BIT was declared operable, and Action Statement 3.5.4.1 was terminated. Sample results indicated that the BAT boric acid concentrations were within specification limits at 0043 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, March 29, 1982. Nos. 21 and 22 BATS were declared operable, and Action Statement 3.1.2.6.1 was terminated.
Operating Instruction 01 II-3.3.5 " Boric Acid Solution Preparation and Transfer" was revised to provide greater detail and ensure the BATS are not diluted. Operating Instruction OI II-4.3.5 " Flushing, Draining and Filling the BIT" was also revised to provide detailed guidance for restoring the BIT to recirculation following either dilution or draining.
FAILURE DATA:
Not applicable Prepared By R. Frahm . . Y f General Manager -
Salem Operations SORC Meeting No.83-086 1
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05000311/LER-1982-001, Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed | | 05000272/LER-1982-002, Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | Supplemental LER 82-002/01X-2:on 820119,during Surveillance, Indications of Tube Thinning Detected by Eddy Current Exam. Tubes Above 30% Degradation Plugged.Tube R44C62 Sent to Westinghouse for Chemical & Metallurgical Testing | | 05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo | Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage | | 05000272/LER-1982-003 | LER 82-03L/031-0:on 820502,while Testing Valve 11SW122, Safeguards Equipment Control Cabinet Actuation Occurred. Caused by Locked Out Supply Breaker to Safety Injection Pump 11,due to Spurious Nature of Actuation | | 05000311/LER-1982-004, Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | Forwards LER 82-004/03X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-004, Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | Supplemental LER 82-004/03X-1:on 820108,charging Pump 13 Declared Inoperable Due to Component Cooling Water Sys Being Tagged Out for Planned Maint.On 820109,positive Reactivity Change Found in RCS Boron Concentration | | 05000272/LER-1982-005, Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | Forwards LER 82-005/01X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-007, Forwards LER 82-007/01X-2 | Forwards LER 82-007/01X-2 | | 05000272/LER-1982-008, Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | Supplemental LER 82-008/03X-1:on 820126,boric Acid Concentrations in Boric Acid Storage Tanks 11 & 12 Found Below Tech Spec Limit.Caused by Dilution of Concentration by Flushing Water in Tank Following Maint.Boric Acid Added | | 05000272/LER-1982-009, Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | Supplemental LER 82-009/03X-1:on 820118 & 25,Cardox Fire Suppression Sys for 1A,1B & 1C Diesel Generator Areas & Fuel Oil Storage Area 12 Inoperable for More than 14 Days.Caused by Sys in Manual Mode Due to Maint Outage | | 05000272/LER-1982-011, Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | Forwards LER 82-011/03X-1.Detailed Event Analysis Encl | | 05000311/LER-1982-012, Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | Forwards LER 82-012/03X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-014 | LER 82-014/03L-0:on 820306,wind Speed Indications for 150 & 300-ft Elevations Failed.Local Indications Also Failed. Caused by iced-up Anemometers.Anemometers Thawed & Declared Operable | | 05000311/LER-1982-015, Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip | Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip | | 05000272/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-016, Forwards LER 82-016/03L-0.Detailed Event Analysis Encl | Forwards LER 82-016/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-017, Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve | Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve | | 05000272/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-018 | LER 82-018/03L-0:on 820304,steam Generator 24 Feedwater Channel 2 Flow Indicator Failed.Caused by Failure of Force Motor in Flow Transmitter.Transmitter Properly Repaired, Calibr & Returned to Svc | | 05000272/LER-1982-018, Forwards LER 82-018/01T-0.Detailed Event Analysis Encl | Forwards LER 82-018/01T-0.Detailed Event Analysis Encl | | 05000311/LER-1982-019 | LER 82-019/03L-0:on 820307,undervoltage Condition in Safeguards Equipment Control Cabinet Caused Mod 1 2A Sec Actuation.Caused by Failure of Card File Assembly.Card File Assembly Replaced & Loads Secured.Sys Returned to Svc | | 05000311/LER-1982-020, Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-022, Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-024, Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised | Supplemental LER 82-024/03X-1:on 820410,svc Water Flow to Containment Fan Coil Unit 12 Discovered to Be Less than Required 700 Gpm.Caused by Valve 12SW223 Being Stuck in Closed Position.Valve Exercised | | 05000311/LER-1982-024, Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added | Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added | | 05000311/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-027, Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State | Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State | | 05000272/LER-1982-028, Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated | Corrected LER 82-028/03L-0:on 820425,both Channels of Refueling Water Storage Tank (RWST) Level Indication Showed Less than Min Vol.Caused by Refilling Spent Fuel Pool. Makeup to RWST Initiated | | 05000311/LER-1982-028, Forwards LER 82-028/01X-1.Detailed Event Analysis Encl | Forwards LER 82-028/01X-1.Detailed Event Analysis Encl | | 05000272/LER-1982-029, Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve | Supplemental LER 82-029/03X-1:on 820501,during Surveillance Testing,Svc Water Flow to Containment Fan Coil Unit 12 Discovered Less than Required 2,500 Gallons Per Minute for Low Speed.Caused by Stuck Flow Control Valve | | 05000311/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl | Forwards LER 82-029/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-030, Forwards LER 82-030/03L-0.Detailed Event Analysis Encl | Forwards LER 82-030/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-031, Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-031, Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | Forwards LER 82-031/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-032, Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-032, Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | Forwards LER 82-032/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | Forwards LER 82-033/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-034, Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | Forwards LER 82-034/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-035, Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-035, Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced | Supplemental LER 82-035/99X-1:on 820526,fire Pump 2 Failed to Start.Caused by Damaged Fire Pump Electrical Sys Voltage Regulator/Alternator,Due to Faulty Wiring Harness.Damaged Components Replaced | | 05000272/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-037, Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-037, Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | Forwards LER 82-037/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-038, Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | | 05000272/LER-1982-038, Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | Forwards LER 82-038/03L-0.Detailed Event Analysis Encl | | 05000311/LER-1982-039, Forwards LER 82-039/01T-0.Detailed Event Analysis Encl | Forwards LER 82-039/01T-0.Detailed Event Analysis Encl | |
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