|
---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086B1731976-11-0909 November 1976 AO 50-267/74-20A:on 741116,during Low Power Physics Testing, Conflict Found Between Tech Specs 4.2.11 & 4.4.1 Re Moisture Limits.Caused by Last Minute Change in Tech Specs 4.2.11. Tech Specs Revised ML20086B1781976-11-0909 November 1976 AO 50-267/74-20A:on 741116,during Low Power Physics Testing, Conflict Found Between Tech Specs 4.2.11 & 4.4.1 Re Moisture Limits.Caused by Last Minute Change to Tech Specs 4.2.11. Tech Specs Revised ML20086B1001976-09-0303 September 1976 AO 50-267/74-21C:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Operator Error.Valves Will Be Replaced W/Kerotest Valves & Change Notice 91 Issued ML20086A0441976-05-28028 May 1976 Telecopy AO 76-012:on 760527,helium Circulator 1B Tripped Twice.Caused by Buffer Seal Malfunction.Sys Operating Procedure Will Be Revised ML20086A0691976-05-20020 May 1976 AO 76-011:on 760510,helium Circulator 1C Tripped Due to Negative buffer-midbuffer Differential Pressure.Cause Associated W/Test ML20086A0871976-05-0303 May 1976 Telecopy AO 76-010:on 760429 & 30,circulators 1A & 1B Tripped on Loss of Bearing Water.Caused by Operator Error ML20085M4351976-02-17017 February 1976 Telecopy AO 76/005:on 760227,loss of Essential 480-volt Bus 2 Caused Trip of Three Helium Circulators Due to Circulator Bearing Water Problems.Loss of 480-volt Bus Could Cause Temporary Loss of Forced Circulation ML20085M4731976-02-0606 February 1976 Telecopy AOs 76/03 & 76/04:on 760206,generator Set 1-B Load Breaker Would Not Close & Generator Set 1A Trouble Alarm Received,Indicating Partial Disconnection of Engine 1B from Generator.Causes Not Stated ML20085M5651975-12-22022 December 1975 AO 50-267/74/23A:on 741211,engine a of Standby Diesel Generator 1A Declutched During 2 H Surveillance Run & No Alarm Annunciated.Caused by Dirt Under Seat of Solenoid Valve.Plant Change Notice 12 Initiated ML20085M7181975-12-22022 December 1975 AO 50-267/75/15A:on 750709,during Repair of Minor Oil Leak on Gasoline Engine of Emergency Fire Pump,Inlet Manifold Piping Found Cracked.Caused by Component Failure.Manifold Repaired ML20086B1541975-12-18018 December 1975 AO 50-267/74-7A:on 740424,fuel Handling Machine Failed to Engage & Lift Reflector Element 09-06-R-01.Caused by Mfg Error.Reflectors de-burred & Ga Co Will Supply Two Column 1 Metal Clad Reflector Elements ML20085M5631975-11-18018 November 1975 AO 50-267/75/24:on 751108,static Seal on Helium Circulator B Inadvertently Released.Cause Presently Undetermined. Circulator B Brake & Seal Manually Set ML20085M6211975-10-21021 October 1975 AO 50-267/75/18A:on 750816,during Installation Preparation, Helium Circulation Damaged.Caused by Lack of Adherence to Approved Procedure.Personnel Counseled to Adhere to Approved Procedures & Supervision ML20085M5711975-09-26026 September 1975 AO 50-267/75/23:on 750916,essential Electrical Cable Discovered to Have Failed.Caused by Circumstances Associated W/Work in Progress.Damaged Cable Replaced ML20085M5771975-09-26026 September 1975 AO 50-267/75/22:on 750912,during Gas Waste Routine Release, Trouble W/Gas Vacuum Tank Observed by Reactor Operator.Cause of Malfunction Unknown.Failure Could Not Be Reproduced.No Further Action Planned ML20086B1151975-09-26026 September 1975 AO 50-267/74-21B:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Operator Error.Inlet Valve Seats Will Be Replaced W/Soft Seats ML20085M5821975-09-22022 September 1975 AO 50-267/75/21:on 750911,control Rod Drive Inserted Into Pcrv Rotated 180 Degrees from Required Orientation During Control Rod Drive Mod.Caused by Design & Procedure Error. Procedures Modified ML20085M6181975-09-0505 September 1975 AO 50-267/75/19:on 750825,engine a of Standby Generator a Automatically Shut Down & Declutched During Cooldown Portion of Weekly Surveillance Test.Caused by Difference in Fuel Rack Setting.Setting Changed ML20085M6231975-09-0505 September 1975 AO 50-267/75/18:on 750816,during Installation Preparation, Helium Circulator Damaged.Caused by Lack of Adherence to Approved Procedure.Personnel Counseled to Adhere to Approved Procedures & Supervision ML20085M6121975-09-0505 September 1975 AO 50-267/75/20:on 750826,12 Cord Sets Connecting Process Controllers at I-05 & I-06 Control Board to Cable Rack in Auxiliary Electric Equipment Room Switched.Caused by Malicious Mischief ML20085M6781975-08-15015 August 1975 AO 50-267/75/17:on 750808,instrument Air Compressor 1C Observed Running Continuously in Unloaded Condition.Caused by Component Failure.Failed Unloader Actuator Replaced W/New Unloader Actuator & Tested ML20085M7021975-07-21021 July 1975 AO 50-267/75/16:on 750610,when Engine B of Standby Generator a Dissassembled,Broken Rings,Scored Cylinders & Cracked Pistons Found.Caused by Water Engine.Engines Inspected.Pistons,Liners & Rings Replaced ML20085M7251975-07-18018 July 1975 AO 50-267/75/15:on 750709,during Repair of Minor Oil Leak on Gasoline Engine of Emergency Fire Pump Inlet Manifold, Piping Found Cracked.Caused by Component Failure.New Manifold Ordered & Defective Casting Replaced ML20085M7401975-06-11011 June 1975 AO 50-267/75/14:on 750530,engine B of a Diesel Generator Oversped to 1,900 Rpm While Electrical Overspeed Trip Being Set.Caused by Procedure Error.Test Procedure Changed ML20085L6331975-05-27027 May 1975 AO 75-267/75/13:on 750519,I-B Engine of I-A Standby Diesel Generator Failed to Start.Caused by Failure to Transmit Info That Engine Was Out of Svc to Adjust Overspeed Switches ML20085L6481975-05-12012 May 1975 AO 50-267/75/10:on 750501,exam Revealed Pin on Declutching Mechanism of Engine D of Standby Diesel Generator D Sheared Off.Caused by Inadequate Lubrication.Pin Replaced & Lubrication Frequency Increased ML20085L6301975-05-12012 May 1975 AO 50-267/75/9:on 750404,valve HV-2188-8 Did Not Open When Circulator Seal Release Permissive Circuit Directed Valve to Open.Cause Not Stated.Air Solenoids Inspected & Cleaned ML20085L7871975-05-0707 May 1975 AO 50-267/74-25:on 741018,diesel Engine B of Standby Generator a Tripped from High Water Jacket Temp on Routine Test.Caused by Improper Filling of Water Jackets.Personnel Counseled ML20085L6411975-05-0707 May 1975 AO 50-267/75/11:on 750424,preliminary Calculations Indicated That Helium Bottles Supplying Reserve Shutdown Sys Did Not Have Adequate Restraint for Dbe.Cause Not Stated.New Bottle Racks Designed & Installed ML20085L7881975-04-16016 April 1975 AO 50-267/74/24A:on 741222,static Seal on Helium Circulator a Released During Removal of Temporary Jumpers.Caused by Jumper Contact W/Station Ground ML20085L7671975-04-0808 April 1975 AO 50-267/75/3A:on 750123,dew Point Moisture Monitor Failed to Initiate Reactor Scram When Moisture Content Exceeded Trip Setpoint.Caused by Design & Procedure Inadequacies.New Procedure Developed ML20085L6491975-04-0707 April 1975 AO 50-267/75/9:on 750329,leak in Mechanical Seal of Helium Circulator B Discovered.Caused by Foreign Matl on Sealing Surfaces.No Corrective Actions Planned ML20085L6831975-04-0202 April 1975 AO 50-267/75/6A:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Improper Closure of Air Operated Drain Valve Due to Foreign Matl on Valve Seat.Seat Repaired ML20086E1651975-03-21021 March 1975 AO 50-267/74/6A:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Failure of Air Operated Drain Valve to Close Properly.Valve Repaired & Reinstalled ML20085L7071975-03-14014 March 1975 AO 50-267/75-4-A:on 750125,tritium Leaked from Secondary Closure of Refueling Region 1.Caused by Normal Presence of Tritium in Pressurizing Gas ML20085L6511975-03-0707 March 1975 AO 50-267/75/8:on 750224,diesel Engine B of Standby Generator a Failed to Function Properly During Weekly Test. Caused by Defective Temp Thermocouple.New Thermocouple Installed & Preventive Maint Program Instigated ML20085L6581975-03-0404 March 1975 AO 50-267/75/7:on 750121-23,reactivity Anamoly Occurred Due to Release of Hopper of Reserve Shutdown Mall Into Core. Cause Not Stated.Valve Seats Modified ML20086B0681975-02-26026 February 1975 AO 50-267/74-22A:on 741129,high Pressure in Gas Waste Vacuum Tank Blew Rupture Disc & Lifted Relief Valve Allowing Release of 750 Scf Uncontaminated Gas.Caused by Design Inadequacy.Pressure Indicator Installed ML20085L6851975-02-18018 February 1975 AO 50-267/75/6:on 750202,gas Waste Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Improper Closure of Air Operated Drain Valve.Valve Will Be Disassembled for Insp ML20085L7011975-02-17017 February 1975 AO 50-267/75/5:on 750127,gas Vacuum Tank Rupture Disc Ruptured,Releasing Small Quantity of Gas.Caused by Inadequate Procedures.Procedure Rewritten ML20085L7121975-02-14014 February 1975 AO 50-267/75/4:on 750125,tritium Leaked from Secondary Closure of Refueling Region 1.Cause Will Be Determined When Vessel Pressure Dropped to Atmospheric or Below ML20085L7721975-02-12012 February 1975 AO 50-267/75/3:on 750123,dew Point Moisture Monitors Failed to Initiate Reactor Scram When Moisture Content Exceeded Trip Setpoint.Caused by Failure of Sample of Primary Coolant to Reach Monitor.Tech Specs Revised ML20086B1231975-02-12012 February 1975 AO 50-267/74-21A:on 741121,high Pressure in Gas Waste Vacuum Tank Lifted Relief Valve Allowing Release of 700 Scf Uncontaminated Gas.Caused by Procedural Error.Inlet Valve Seats Will Be Replaced & Interim Procedure Modified ML20085L7401975-02-0707 February 1975 AO 50-267/75/1:on 750118,230-kV Breaker Tripped Due to High Winds,Causing Standby Diesel Generator a to Receive Start Signal.Generator B Did Not Receive Start Signal.Caused by Sensitive Relay Setting.Relay Recalibr ML20085L7271975-01-31031 January 1975 AO 50-267/75/2:on 750113,reactor Bldg Exhaust Charcoal Filters Failed to Meet Tech Spec Leak Rate Requirements. Caused by Use of oil-based Paint & Organic Solvents.Filters Changed Out ML20085L6501975-01-25025 January 1975 AO 50-267/75/24A:on 741222,static Seal on C-2101 (Helium Circulator C) Released During Removal of Temporary Jumpers. Caused by Blown Fuse & Seal Release Valve Leak.All Circulator Brake & Seal Vent Valves Checked ML20085L7341975-01-24024 January 1975 Telecopy Ao:Charcoal in Reactor Bldg Exhaust Filters Failed to Meet Tech Spec Requirements ML20085L7901975-01-14014 January 1975 AO 50-267/74/24:on 741222,static Seal on C-2101 (Helium Circulator C) Released During Removal of Temporary Jumpers.Caused by Jumper Across Logic Circulator a Coming in Contact W/Station Ground ML20086B0501974-12-23023 December 1974 AO 50-267/74-23:on 741211,engine a of Standby Diesel Generator 1-A Declutched & No Alarms Annunciated.Caused by Cylinder Air Pressure Decay Due to Dirt Under Solenoid Valve Seat.Change Notice 11 Re in-line Filters Approved ML20086B0641974-12-19019 December 1974 Telecopy AO 50-267/74-23:on 741211,diesel Engine a of Standby Generator 1-A Declutched 1976-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997 Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co ML20141K9961997-05-0505 May 1997 Safety Evaluation Supporting Amend 89 to License DPR-34 ML20140E1121997-04-10010 April 1997 Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20134D1661997-01-30030 January 1997 Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) ML20137S6111996-12-31031 December 1996 Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 ML20134G6401996-10-29029 October 1996 Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E ML20134G6171996-10-29029 October 1996 Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results ML20134G7271996-10-29029 October 1996 Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J ML20134G6861996-10-29029 October 1996 Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G ML20134G6321996-10-26026 October 1996 Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D ML20133D7831996-10-22022 October 1996 Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 ML20116A4661996-07-19019 July 1996 Fsv Final Survey Exposure Rate Measurements ML20112J6861996-05-31031 May 1996 June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531 ML20112C1531996-05-17017 May 1996 Fsv Final Survey Exposure Rate Measurements ML20101G5521996-03-21021 March 1996 Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept ML20097E3201996-01-31031 January 1996 Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation ML20095K4131995-12-26026 December 1995 Rev 3 to Decommissioning Plan ML20095H7211995-12-20020 December 1995 Revs to Fort St Vrain Decommissioning Fire Protection Plan Update ML20095K9751995-12-15015 December 1995 Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 ML20096C1671995-12-13013 December 1995 Rev 4 to Decommissioning Fire Protection Plan ML20094M1651995-11-30030 November 1995 Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation ML20092F3461995-09-14014 September 1995 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/ ML20137H3531994-12-31031 December 1994 Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses ML20137S2331994-12-31031 December 1994 Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 ML20029C6031993-12-31031 December 1993 1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr ML20058Q3791993-12-21021 December 1993 Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20045B3641993-06-30030 June 1993 June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning. ML20045A4291993-06-0303 June 1993 LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr ML20077D1631993-05-10010 May 1993 Enforcement Conference, in Arlington,Tx ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20128D7191992-12-0101 December 1992 Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20127F5691992-11-0303 November 1992 Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34 ML20101E5761992-05-31031 May 1992 Monthly Defueling Operations Rept for May 1992 for Fort St Vrain ML20096E8221992-04-30030 April 1992 Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/ ML20095E9601992-04-17017 April 1992 Rev to Fort St Vrain Proposed Decommissioning Plan ML20100R7431992-03-31031 March 1992 Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/ ML20090L0621992-02-29029 February 1992 Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1 ML20092D0081992-01-31031 January 1992 Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station ML20102B2241992-01-22022 January 1992 Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122 ML20094N6701991-12-31031 December 1991 Public Svc Co Annual Financial Rept for 1991 ML20091J6251991-12-31031 December 1991 Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ ML20094D6711991-11-30030 November 1991 Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1 ML20090M1871991-11-20020 November 1991 FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan ML20086D6891991-11-15015 November 1991 Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20085N1451991-11-0505 November 1991 Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085H6611991-10-10010 October 1991 Assessment of Mgt Modes for Graphite from Reactor Decommissioning ML20091D7671991-10-0101 October 1991 Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ 1997-07-01
[Table view] |
Text
~+ -
Q O h&EUau>u public service company oe conorado P. O. Box 361, Platteville, Colorado 80651
~o . ,\
Nh/} ? yt -
~
l November 9, 1976 Q.W,sggo,,_, Fort St. Vrain
%',yy**: Unit No.1
%- . - P-76248
.,s
$r - u ;-
Mr. E. Morris Howard, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement Suite 1000 Arlington, Texas 76012 REF: Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Howard:
Enclosed plear,e find a copy of Abnormal Occurrence Report No. 50-267/
74/20A, Final Supplement, submitted per the requirements of the Tech-nical Specifications.
Also, please find enclosed one copy of the Licensee Event Report for Abnormal Occurrence Report No. 50-267/74/20A.
A Very truly yours, y - '4Y Frederic E. Swart Nuclear Production Manager FES/alk cc: Mr. Roger S. Boyd % <-- %
G w., =
N- -
! 8311170090 761109 l PDR ADOCK 05000267 l S PDR l',1,bbO l
l
. , . A i 1
. U '
i:t: ot T DAtr: ho .v mber 4, 1976 An! 01;'. i!. OCCUlu:Cr:ct 7'i/20 s.
p:rge 1 of 3 l a
OLCUwe.t.'CE IW1 E. Eommber 16 197'-
l i
i rui:T ST. VRAl'! !!UCD:/ " Gi !r.HATI::G STATIO :
PUliiJC SI:!fi ICS CO;D i:;Y OF col.OHalM
- P. O. h05 3;>l Pl.AfTEVILLE, COLot3DO 80651 i
i REPO;.f ;;0 50-267/74/20.i i
1 Final Supple.,ent j
1Dr.NIlriCAT10;I UF CCannI;ct :
On Svturday, ro"e.mber 16, 1974, during leu power phyn i c.s testin;, i t v:ri found th::t a emiflict enis ted 1 e taean LCO 4. 2. 31 and *.C0 4. 4.1 of I he Techn i c.>l
] Specifications. IWeeuse of r.:act:>r conr:Itions niid the und to continu" t esting,
! it una decided to ;;o with the coisture limits os u hi t e d .i n 1.00 4. 2.11 and d is:tre the n mi t ms of LCO 's.4.1 cnd to notify and resolve t he confilet .nc soon as por:ible with the !:uelcar R :;ulatory Cemd:,:i.on. This vonld be dr-fined as au chnarical occurrence, per 2.lb of the Te chr.ical 1 pacificat iva...
i f.0"D*T10::S PRIOt;
'10 OCCU;mF.XCC-i X St e:rd.v Stalw P oer. --._Rwtina S!.etde ' '
llot Shutdrwn _ _ Routine Load Change
, Cold Shutdown X Other (specify) i i
1:cCueling Shutdown Low Power llot Physics
! Routine Startup Tests The major plant parametern at the' tirac of the event were as follows:
Power RTR 10'7. - 5 x 10~3.7 Power ELECT' N/A ' MWc '
Secondary Coolant ' - Pressure N/A psig l
, . Ternperature .
N/A *F-Flow N/A #/hr.
i .
- i. Primary Coolant Pressure 80 - 270 poig l
, Core Inlet Temperature 110' '*F:
l Core Outlet Temperature- l'10 *F l
-Flow 100,000 #/hr.
l i
\ '
, 6.. - .I - - - ,
~
AP.iNP?iAf, OCCt1FCIM '/ 4/?!)A 1 pa y,e 2 of 3 i DESCla i'TICM OF UCCim.:t! :
i j l're p._ rat i or.a for ri:nn to;; pa. t 1 of Startup Te st A- L to del et n.:nc t he :. ermhir F p re:. sitie coef ficie::t of renetivi ty vert in proces:.. Th ia t ent re<!uired th.
reactor t o be crit ical while prinary coolan t p essure va varied while naic-j L ai n ia-; the recet or c ritic.il bj cont rol rod mova:Nnt.
j LCO 4.2.11 stated that belou 725* P care outlet te:mer.st ure, 5,000 p;mv moin-4 t ure was alloued in the prie:try coolant. LCO 4.'i.1, Tabic 4.4-1, i ten 4, j a ta t t. t he ruxinam .settin:;a of the high .lcul and icop noistura conttors, 500 pra and 100 pp z, re spcet tvely, and aMo uteten that tharr a r n ., pi: r-j uiss ib h bypae + c"nditions of t he h!nh runt.c r on it m s ,
', The d t.u pr.l e t na is t u re mon i tors had beca ci.t; in an ' apparently du to a c. c. i t ar.cuut of r.ois ture t hat had acct./.ulated in the sa..:pic lines during the Ic ,
perioJ of re.;ctor sl.utdown. cpuricu; t rips vere being rect ived which enn <A reactor neran.
Itcrase t he reactor tenpaature van 1< , abeur 110* l , and r.oisturt J eeel ehet t 140 pt.1, it uas perr.insible to operate t he re e.c t .o . To allow opern: ion of LLe t eatt er, the dew point noi ct ure riunitor outputs vere ' bypam::1 and 1.e t point: raised t o approximately 3.000 pra and 1,000 pp.n on t he h Igh rnnge and loop nanitora, respectively.
i A note to this et t eet was put in tbc stat ion lug,-- along uith a comment LI:at we vould contact AEG-DOL as soon as possible tc clear up the d increpancy. -
3 This vas done on Monday norning, November 13, 1974.
Operation of the reactor continued at pours as high as 5 x 10 D power.
At no time was the moisture level in the primary coolant above 150 ppmv or the temperature above 130*F.
1 APPARENT CAUSE j -OF OCCURPINCE: - Design Unusual Service Cond.
4 including Environment l
, Manufacture Component Failure Installation /Const.- X- Other. (specify)-
Operator- Discrepancy between two Tech.
Procedure Spec.'LCO's, and the decision i
to continue operat ion using the -
4 limits of only. ons.
v .
. P l.
w s
- - - w- y - =- 7 y p- - - -w +- --. y- y, - p. m e- p
,, r\
.)
. , :OiT 9 ? ::::Fi;ie; ::t ;. 7(, f t),\
P. e,s i .it 'l
/ : . 4 75 (::
,,'L...
T: . .i ..c; r i c:d Fpe el f I c.u 1."-c e 1. . c a .' . t .Sou; by 1 i.!ia ch:1 g - i: 1.t >
.. j te; t prior to L cuance , to t.. i n b' meannt conj! t i< .
ac t .i..l ly e: pe rie .> ..I durits; tlw plai r 1:ot I' lou icsts aasi t: *aunecru for heron c a r', i .L e ,i .t..! ;ie ., t e ; . c..i.ed t er: ;i. + o r;:. In the presenc. e r r . i l e t. o r s . An
.;de rpu. t . ar: h of the Techul eal .;,ic ci f i c a tine fo r o t h" r i.(..i's wh i ch rr b .' ..f f e et d ca apparen tly 1.a t r:ade.
.. . ' 1 the rea t or operr.t t. n pir.ce r l eve la and t c: ;'arat e. e: t h-c ro act< d : b. t e:n t a r c. . e . rn;ih t i . , f o :! , or bn: nab'e ] c.:it ; ng, vir :.
t; r."am t . At no L i:a :is t .e ! lih i.d ..a f. . ' o f t h.: pr' l i -.
e:
s.. ..
- i. *
i
! Fe' 4 :
i on J:!.3 t o t h e Fo r t Ft. i' rain Techn ced b; s -i fi ca:. tc. . : evi:.< d Sc . i<c.
4 . .1 ! an ' T.:ble 4 . 4.1. Yi. > ne t;n,1:.t o f t he hi: r:re. r: , ; n t u re i .n n i t o
. c.h a .' g_ t' to ' 6 /"l' ::nd < 2 7'? fo r I he lo p , - . : ure t.;cn i t o r: .
4 , .: : a t.he dinecer:.ncy be ttecen Ta'31s !. 4.1 a w' LW 4. 2,11.
I:o it. ': U o ' c acrec tive .u tic. . i s cu t it ip:'u d or rergel red.
. . , . . . .1ai1in . .u.1/a:
. . _ . . . a. L3. .-( 8:
. ru. t:.3 u .t nH:a .cl.3 :
1Nof1O PROGR.i?"LiTiC IMPACT:
None CODE IMPACT:
None Subr:1Ltted by: '!1 J _,( A ' ,.sVkf] , j-7 l l- d$ f4
- 11. W. Ilillydrd, Jr. p Technical Services Supervisor
_/ 7 I;cviewed by: Qih). b. ..wT.
- 11. Larry Egey {
Superintendent, Operations Approved by: 3 74 > .51.
, Frederic E. Swart j-l Nuclear Product.fon MJ[ nager l
l l i l
i l
O LICENSEE EVENT REP CONTROL ,BLOCC l l l l l l l [PLEASE PRINT ALL REQUIRED INFORMATION) 1 6 NAME LCENSE NUMBER E T E O1 Ic 10 I e I S I vl il I 0101-10101010101-10101 I 411111210 l l 01 il 7 89 14 15 25 26 30 31 32 CATEGORY T SU OOCKET NUMBER EVENT DATE REPORT OATE hCON'T lM lI l 7 8 57 58 W 59 W60 l0 l5 l0 l-l 0 l 2 l 6 l 7l 61 68 l1l1l1l6l7l4l 69 74 l 1l 1l O! 9l 7l 6l 75 80 EVENT DESCRIPTION 35 l During low power physics tests it was found that a conflict existed between two l 7 89 80 3E l Technical Specifications on moisture limits. Moisture monitors bvoassed and noisture !
7 89 80 3E l monitored to assure compliance with one Technical Specification. }
7 89 80 38 l l 7 89 80 HG l (AO 74/20A) l 7 89 m, 80 E COE COMPONENT CODE MANUFAC AER VCLATON 3[ lClJl lDj 7 89 10 11 lXlXl Xl Xl Xl Xl 12 17 W43 lzl9l9l9]
44 ' 47 lN l 48 CAUSE DESCRIPTION UE l One moeci fi cn r inn allnued 9. 000 PPMV ani seitra nther n11nued 500 nnmv nn hioh rmnen nnd! - ~
7 89 80 3E l 100 ppciv on low range. Technical Specifications changed to indicate dewpoint I 7 89 80 DE le-ngrne,,rg. I STA % POWER OTHER STATUS OS VERY DISCOVERY OESCRsPTON 1
7 8 9 d 1010101 l 10 12 13 l 45h 44 46 iN/A 80 l
R LEA EO OF EL ASE AMOUNT OF ACTIVITY LOCATON OF RELEASE 3E Iz l 1_z_J l N/A l lN/A I 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUVSER TYPE DESCR!PTON DE b 10 lO 1 LzJ l m I 7 89 11 12 13 00 PERSONNEL INJURIES NUMBER DESCRIPTON 3[ l 0l 0l 0l l N/A I 7 89 11 12 80 OFFSITE CONSEQUENCES
]E l N/A l 7 89 80 LOSS OR OAMAGE TO FACIUTY TYPE DESCRIPTON QW 7 89 l N/A 10 80 l
PUBLICITY
@ l N/A l 7 89 80 ADDITIONAL FACTORS DE l N/A l 7 89 80
$l . # l PAME: I Affl -
- PHONE: (303) 785-2253 H. W. Hillyard, Jr. / / cro ess.esT