text
l MnC Pe. see un NuCLEAn nEoutATonY e ----
Apr9tOVED Oass eso. s100-410s LICENSEE EVENT REPORT (LER)
PAcaLITY Maa8E on OOCKET Nuessen tal PdMBE 43 Prairie Island Unit 1 o l5 l0 l0 lo l 2l8 l2 1loFl0l2 TITLE tel Boric Acid Tank Inventory Allowed to be Pelow Tech Spec Limit eve =T OATE im ten NumsEn is nEPO=T OATE ni OTieEn FACiuTies Nv0Lv80 m i
seONTM OAY YEAn YEAn
- 8' j
MONTH DAY YEAn
' AouTV maMee DOCKET foutsetatS) n 015l01010 I I l 1
011 1,2 8
5 8l 5 0l0l1 0l0 0l2 1l1 8l5 o isso to g o s l l 1
TNm mePOnT is evenNTTeO PunsuA=T TO TuS atouintuEms or is CPn 3: tenene
.,-., s= =n.--w on
- - m a
- se_s, es,m,.,
.3,, s.,
g se.asswone es.sewm esmimm ruiw nei 01010 aseeswmm es.sewm seannauw gaggg
~
se.aeewnna 1
.smimco sesmimi.antAs asses 34",
eswme.,
==m.
= = = < >.
so.asswmm sessis:ste es.rswt Man LICEpssEE costTACT Pon TMes LEn Ital seAast TELEPHONE NuMeEn AREA CODE Arne A. Hunstad, Staff Engineer 6ll2 3 8 l8; il i 1l2l1 i
1 COaAPLETE 080E Lises Pon EACH CoasPONENT PA8Lund DeeCaleEO IN Twas REPOn? (130 "A
"'Tu N8
~2
CAusE
SYSTEM ConaPONENT
CAUSE
SYSTEM COMPONENT Tu 70 s
l I I I I I I I
I l l I l l
+'
l I I I I l l l
l l 1 I l l suPPLEGAENTAL REPOnT EXPECTIO (14)
MONTM OAY YEAn SusMISSION f 800 l
l l
YES (19 ver sem.neer EXPtCTto SuenetSSION OA tti
- - nAC,-..-.__-,,.,
In preparation for cooldown for refueling, the reactor coolant system was borated to the cold shutdown boron concentration with the contents of the boric acid tank, whose level then fell below the Tech Spec minimum of 2000 gallons. Tech Spec 1
clarification may be pursued.
i i
)
8502150483 850211 PDR ADOCK 05000282
[
\\
S PDR Il
U.S. psUCLEAR C.EGULATORY C0hlhetBSIO80
'esRC Poem assA LICEN EE EVENT REPORT (LER) TEXT CONTINUATION Arenovio ome o. 3ino-om EXPIRES: 0/31!96 FaceLITY esaast (16 DOCKET peutsBER (21 ggn gynagan ggg pagg g3g
N[.'. ' i ::($l VEam Prairie Island Unit 1 0l0 0l2 0F 0l2 0l0l1 0 l5 l0 l0 l0 l2 l 812 815 TuxTw
. w.- - mce asse.nm On January 12th, Unit I was at hot shutdown and preparing for cooldown for refueling. The reactor coolant system (RCS) (AB) is borated to the cold shutdown boron concentration before cooldown is begun. Boric acid for this operation is supplied from the boric acid tank (BAT) (TK). At 0400, with the RCS at cold shutdown boron ccacentration, the BAT level dropped below 2000 gallons, the Tech Spec minimum. Since boration was to continue, several hundred gallons of boric acid were added to the BAT and the level was brought well above 2000 gallons. At 0900 the RCS had been borated to the refueling shutdown boton concentration and the level again dropped below 2000 gallons and was allowed to remain there.
Though this operation was technically in violatien of Tech Specs, the reactor core was in a safer condition with the boric acid in the RCS rather than in a BAT. The boric acid inventory is maintained to mitigate the consequences of a steam line break accident. At the first time the BAT was below the Tech Spec minimum, sufficient boric acid had already been added to the RCS to mitigate the postulated accident.
There was no effect on public health and safety.
Involved personnel have reviewed this event. A Tech Spec change may be pursued to clarify the requirements for a boric acid inventory.
i pomu sesa
- f a-Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401 Telephone (612) 330-5500 February 11, 1985 U S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 Boric Acid Tank Inventory Allowed to be Below Tech Spec Limit The License Event Report for this occurrence is attached.
This event was reported via Emergency Notification System per 10 CFR Part 72 on January 12, 1985.
hDavidMusolf Manager - Nuclear Support Services DMM/EFE/ dab c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC MPCA Attn: J W Ferman j
Attachment l
gi
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000282/LER-1985-001, :on 850112,in Preparation for Cooldown for Refueling,Rcs Borated to Cold Shutdown Boron Concentration & Boric Acid Tank Level Fell Below Tech Spec Min |
- on 850112,in Preparation for Cooldown for Refueling,Rcs Borated to Cold Shutdown Boron Concentration & Boric Acid Tank Level Fell Below Tech Spec Min
| | | 05000306/LER-1985-001-02, :on 850220,while Recirculating Caustic Standpipe,Valve Left Open,Causing Loss of Level to Below Tech Spec Limit.Valve Closed & Level Restored |
- on 850220,while Recirculating Caustic Standpipe,Valve Left Open,Causing Loss of Level to Below Tech Spec Limit.Valve Closed & Level Restored
| | | 05000282/LER-1985-002, :on 850112,during Surveillance Test at Shutdown for Refueling,One of Ten Main Steam Safety Valves Failed to Open at Setpoint.Cause as Yet Undetermined.Supplemental Rept Will Be Made |
- on 850112,during Surveillance Test at Shutdown for Refueling,One of Ten Main Steam Safety Valves Failed to Open at Setpoint.Cause as Yet Undetermined.Supplemental Rept Will Be Made
| | | 05000306/LER-1985-002-02, :on 850218,diesel Cooling Water Pump 12 Control Switch Mistakenly Put in Manual.Cause Not Stated.Switch Returned to Automatic |
- on 850218,diesel Cooling Water Pump 12 Control Switch Mistakenly Put in Manual.Cause Not Stated.Switch Returned to Automatic
| | | 05000282/LER-1985-003, :on 850107,cooling Water Outlet Valve CL-40-2 Closed.One Component Cooling HX in Each Unit Inoperable. Caused by Human Error.Valve Opened Upon Discovery |
- on 850107,cooling Water Outlet Valve CL-40-2 Closed.One Component Cooling HX in Each Unit Inoperable. Caused by Human Error.Valve Opened Upon Discovery
| | | 05000306/LER-1985-003-02, :on 850808,turbine Overspeed Trip Test Overdue. Caused by Personnel Error in Scheduling Turbine Tests.Test Conducted Upon Discovery of Error on 850810 |
- on 850808,turbine Overspeed Trip Test Overdue. Caused by Personnel Error in Scheduling Turbine Tests.Test Conducted Upon Discovery of Error on 850810
| | | 05000282/LER-1985-005, :on 850123,one Containment Isolation Check Valve Exhibited Leakage in Excess of Tech Spec Limits During Local Leakage Rate Testing at Refueling.No Cause Determined. Valve Replaced |
- on 850123,one Containment Isolation Check Valve Exhibited Leakage in Excess of Tech Spec Limits During Local Leakage Rate Testing at Refueling.No Cause Determined. Valve Replaced
| | | 05000282/LER-1985-006, :on 850206,relay Misoperation Caused Lockout of Transformer 10 & auto-start of Diesel Generators.Caused by Bad Connection within Relay.Relay Replaced |
- on 850206,relay Misoperation Caused Lockout of Transformer 10 & auto-start of Diesel Generators.Caused by Bad Connection within Relay.Relay Replaced
| | | 05000282/LER-1985-007, :on 850319,component Cooling Pump 12 Started. Caused by Loss of Pressure Signal During Dc Transfer Switch Operation.Procedures Will Be Revised |
- on 850319,component Cooling Pump 12 Started. Caused by Loss of Pressure Signal During Dc Transfer Switch Operation.Procedures Will Be Revised
| | | 05000282/LER-1985-009-01, :on 850508,reactor Tripped on Low Steam Generator Level Plus Feedwater Flow/Steam Flow Mismatch. Caused by Separated Solder on Instrument Air Line Joint. Repairs Made & Reactor Restarted |
- on 850508,reactor Tripped on Low Steam Generator Level Plus Feedwater Flow/Steam Flow Mismatch. Caused by Separated Solder on Instrument Air Line Joint. Repairs Made & Reactor Restarted
| | | 05000282/LER-1985-010, :on 850509,reactor Tripped on Low Steam Generator Level.Cause Not Stated.Main Feedwater Pump Discharge Valve Opened & Restart Completed.Rept Will Be Circulated for Training |
- on 850509,reactor Tripped on Low Steam Generator Level.Cause Not Stated.Main Feedwater Pump Discharge Valve Opened & Restart Completed.Rept Will Be Circulated for Training
| | | 05000282/LER-1985-011-01, :on 850801,breaker 228 Accidentally Tripped by Const Electricians Working in Area.Caused by Missing Manual Trip Blocking Device.Workmen Counseled Re Activities & Addl Physical Barrier Erected in Work Area |
- on 850801,breaker 228 Accidentally Tripped by Const Electricians Working in Area.Caused by Missing Manual Trip Blocking Device.Workmen Counseled Re Activities & Addl Physical Barrier Erected in Work Area
| | | 05000282/LER-1985-012-01, :on 850915,reactor Tripped Due to Voltage Transient During Troubleshooting.Caused by Unfamiliarity W/ Regulator.Event Will Be Discussed in Licensed Operator Requalification Program |
- on 850915,reactor Tripped Due to Voltage Transient During Troubleshooting.Caused by Unfamiliarity W/ Regulator.Event Will Be Discussed in Licensed Operator Requalification Program
| | | 05000282/LER-1985-013, :on 850915,one Feedwater Containment Isolation Valve to Steam Generator 1B Failed to Open During Startup. Caused by Overheating of Motor Operator to Valve.Motor Valve Program implemented.W/880107 1tr |
- on 850915,one Feedwater Containment Isolation Valve to Steam Generator 1B Failed to Open During Startup. Caused by Overheating of Motor Operator to Valve.Motor Valve Program implemented.W/880107 1tr
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000282/LER-1985-013-01, :on 850915,feeder Breaker to Motor Control Ctr 1KA2 Tripped Due to Electrical Fault in Motor Operator for Valve MV-32024.Caused by Overheating During Repeated Attempts to Open Valve.Motor Replaced |
- on 850915,feeder Breaker to Motor Control Ctr 1KA2 Tripped Due to Electrical Fault in Motor Operator for Valve MV-32024.Caused by Overheating During Repeated Attempts to Open Valve.Motor Replaced
| | | 05000282/LER-1985-014, :on 851001,breaker 12M Accidentally Tripped Making Safeguards Bus 120 Inoperable.Caused by Contractor Workman Bumping Manual Trip Device & Mgt Deficiency.Breaker Reclosed.Administrative Controls Tightened |
- on 851001,breaker 12M Accidentally Tripped Making Safeguards Bus 120 Inoperable.Caused by Contractor Workman Bumping Manual Trip Device & Mgt Deficiency.Breaker Reclosed.Administrative Controls Tightened
| | | 05000282/LER-1985-015-01, :on 851012,during Testing of Diesel Cooling Water Pump,Other Diesel Cooling Water Pump Started on Low Header Pressure Nonsafeguards Actuation of Safeguards Equipment.Procedure Will Be Revised |
- on 851012,during Testing of Diesel Cooling Water Pump,Other Diesel Cooling Water Pump Started on Low Header Pressure Nonsafeguards Actuation of Safeguards Equipment.Procedure Will Be Revised
| | | 05000282/LER-1985-016, :on 851016,minor Leakage Occurred from Cooling Water Pipe.Caused by Crack from Cyclic Fatigue.Temporary Patch in Place.Permanent Repairs Formulated,Per IE Bulletin 80-24 |
- on 851016,minor Leakage Occurred from Cooling Water Pipe.Caused by Crack from Cyclic Fatigue.Temporary Patch in Place.Permanent Repairs Formulated,Per IE Bulletin 80-24
| |
|