Similar Documents at Surry |
---|
Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18151A2861998-01-26026 January 1998 SPS Unit 2 ISI Summary Rept for 1997 Refueling Outage ML18151A3111997-07-21021 July 1997 Inservice Inspections Abstract of Exams. ML18151A4381996-08-0808 August 1996 Form NIS-1 Owner Rept for ISI, Required by Provisions of ASME Code ML18152A1901995-12-31031 December 1995 Vepc SPS Units 1 & 2 1995 Annual SG ISI Rept. ML18151A2811995-12-27027 December 1995 Form NIS-1 Owner Rept for Inservice Insps, as Required by Provisions of ASME Code Rules ML18151A2281995-06-0707 June 1995 NIS-1 ISI Summary Rept for June 1995. ML18151A2241994-05-24024 May 1994 ISI Summary Rept for 1994 Refueling Outage ML18153A8731994-02-23023 February 1994 Annual Steam Generator ISI Rept. ML18151A2781993-11-10010 November 1993 IST Program Plan for Pumps & Valves Third Insp Interval 940510-20051, Rev 0 ML18151A2221993-05-0606 May 1993 Refueling Outage 2nd Interval,3rd Period Isi. ML18153D2381993-02-0909 February 1993 Annual SG Inservice Insp Rept. ML18151A2051992-07-15015 July 1992 ISI Rept for Surry Power Station Unit 1 for 1992 Refueling Outage,2nd Interval,3rd Period. ML20094H0271991-12-31031 December 1991 1991 Annual Steam Generator Inservice Insp Rept ML18151A1591991-09-0505 September 1991 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, Second Interval,Second/Third Period. ML18151A1561991-03-12012 March 1991 Inservice Insp Summary Rept for 1990 Refueling Outage. W/910312 Ltr ML18153C5481991-02-25025 February 1991 Annual Steam Generator Inservice Insp Rept. ML18153C1391990-03-0808 March 1990 Suppl to Inservice Insp Rept,Consisting of NIS-2 Forms for Stud & Nut Replacement ML20011D3861989-11-27027 November 1989 Inservice Insp Rept of Surry Nuclear Power Station Unit 2, 2nd Interval,2nd Period. ML18153B6251989-03-0101 March 1989 1988 Annual Steam Generator Inservice Insp Rept. ML18151A2531988-10-10010 October 1988 Inservice Insp Summary Rept of Surry Power Station. ML18130A4441987-04-0101 April 1987 Rev 1 to Surry Power Station Unit 2 Inservice Insp Program, Interval 2,830501-930501. ML20205J9641987-03-30030 March 1987 Suppl to Owners Rept for Inservice Insps & Exams, Conducted on 850625-861202.Exam Resulted in Total of One Nozzle Weld Being Reported on Basis of Procedure Recording Criteria ML18130A4401987-03-27027 March 1987 Rev 3 to Surry Power Station Unit 1 Inservice Insp Program, Interval 2,821222-921222. ML18150A5201986-12-31031 December 1986 1986 Annual Steam Generator Inservice Insp Rept,Eddy Current Exam. ML20205F5081986-11-14014 November 1986 Inservice Insp Rept of Surry Nuclear Power Station,Unit 1 ML18139B5571981-08-31031 August 1981 Inservice Insp Rept on 800920-810705.Exam Procedures Were Approved Prior to Exams & Certification Documents Re Personnel,Equipment & Matls Were Reviewed & Determined to Be Satisfactory ML18139B5551981-07-31031 July 1981 Inservice Insp Rept on 810301-0705.Exams Conducted to Review Exam Zone within Geometric,Metallurgical & Physical Limitations.No Indications Found to Be Recordable ML20087B7671975-11-25025 November 1975 Inservice Insp Program,Refueling Outage 2. Insp Verified Integrity of Sys & Components ML20086Q1781975-06-15015 June 1975 Preliminary Results of Inservice Insp Program,Refueling Outage 1. No Significant Deficiencies Identified 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
[Table view] |
Text
.
ATTACHMENT 1 NIS-2 FORMS
( ';:/(H)::E: 1,'.:,0:;:91 9(H):;:()::;:
PDR ADOCK 0!50002:::0 G! PDC
\
FORM N1S*2 OWNER'S REPORT OF REPAIR OR REPLACEMENT
- ATTACHMENT 2 Al Requir,d by th1 Prowi1ion1 of ASME Cod, Stc'tion XI
... ,. Own,r Virginia Power ~~-~t~i-1~7_._&:. . . .,_______~
P.O. Box 26666 Sh"'------0'--------
i,.ocs,nai
- 2. Plant Surry Power Station IN~
p,o. Box 315 Surry. YA 23883 Wo,k ,,rformtd _ Se
~_,Y...A_.................111...r_______
,...,.. _ 38000, :i' 211:r 111e11ew°'t&fliu1-,.o-.Joe.Nt..11C.
. "same
,. ld1~tlfication of Syntm fa) Applic1bl1 Constn.ictlon Codi tltt, :831-1 (ay,.. "z::'..
1i67 Edltloft,.... H___A ___ Addendt, Code C... _ _.,N"""'A_____
5.
(bt Applic1bl1 Edition of Section XI Utilized for Rep1in or R1pl1e1rn1nu - 11..BD. waa Addenda, Codt Caset ....N...A.____
I. Identification of Companentl Re;,1irtd or R1pl1C9d, and Replacwmtnt Componenu Narnt of N1mt of Mfn. Str. . Nat1. CAN Other v,., Repaired, ASME Code Component Mfr. No. Id. No. ldtntl- B1111t ,.,p11C9d, rumped No. f"c1tion
- -,11 or Nol
- - 1-.e,~ k::.. _.._ ~-A , ., ~
,) ~ud S
~J ;(.l.. ..-5 - - - ~~r~.d
,, ,,,.J{J (
I.
I. (
CERTIFICATE OF COMPLIANCE Wt certif\' that the n1t1mtnU made In this r,por, 111 correct and thil__.# __'E.'<...
'C'en;;;.;;...c&=a.Wf....,,f...,'.v'__
,_r' _ _ _ conform1 to Section XI of lhl ASME Code.~ ~ I ftOMOllt~
Sitntd V*C~&r1ff/
~ or 0...-1 ISI TIii PIii!
~ 2 , II £:5 CERTIFICATE OF INSPECTION I, 1h1 undtr1i,gl\1d, holdi"t I valid commission luuld by the N1tlonal Board of loller 1nd P'rnau,w V111el lnap,c1on ind 1h1 Srate Ot ,,oviftc,of. YA, .~mplpvtd a,., HS a* J&I co I .,
Hartford I CT I hlVI inS,:,t<lfd the oiee\o..C.t>Meu IRtp *'11) o, r
lllt:ii*c*- "'Pl demi~ in thil Report OIi //- 9 .11~
111d 11111 that to 1ht btn of rny kno ...1,dgt 111d belief, this. repair or replacement h11 bttn connructtd In 1cc:ord1n~ with Section XI of tht ASME Code. ly 1igl\it19 thia urtific.111, ntithtr the lr11pec1or nor hia ,rnploytr makt1 an\' warr1nty, uprened or implitd, conc1r~
ing lht rtp1ir or 11plec1mt"t drscribflf in thia Atport. Funh1rmor1, n1ith11 tht ln&PtCIOt nor hia employer 1h1II be li1bl1 in 1ny inanntt for tn\' personal injury or proper,y Datt //- j- 8'~
dfj*Jf
~~ ~
- ' : ' ? f ~ i 1 i n g from or connected witll tllia Commiuiona J) I) 24101 In~*;:,::
~ 5:L(:)
ClftlOKIOI\ CSiatt. '"'--*.Ill*'-'~
'°lot11: Svpplernenial ah .. n 1.. form of 11111, ehlch*, or drewl11111 mew be u .. d prowld*d UI 1111 II IX 1ft. X 11111.o 121 lnform,1lon In ,,."'. 1 t111ovgfl
- 011 tllh dne repor, It lrw:lud*d on Heh ehNt, e11d 131 ..ell ellNt II nwrnbe***
on* tl'le """'be' of ehNII 11 recorded II the toD of 1h11 for""
L *_, ., ) "\ I>*
e FORM NIS*2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Atquired by the Prori1ion1 of ASME Code Section XI
...,. 0wner Yicgjnia Power P.O. Box 26666
°'" ,a !.u In Sh NI ot_ ___,,,_ _ _ __
Plant Surry Power StatJOD
.~
2.
p,~ .
P,O, Box 315 Surry, YA 23883
- 2. Work Performed ......._._r&we b'(_Y...A ........"'...c....,,._....,...
,..,.., _____ 38QQQ U'()if1
,-.pe .. ~""" '*o-. .- 111e.-.
C
. ..same ldentlf"ication of Srnem R!,4¢ ~ot+dt!:'Z::::
- I. Cal Applicabl, Connrvctlon Code 831-1 11 67 r~__
Editlon..... A______ Addcnde, Code ea,., __ NA____
Cb) Applicable Edition of Section XI Utilized for R,p1it1 or Fleplecementa - 11..80. wan Addenda, Code Ca.n _..[i...A.____
- Name ofIdentification of Co,nc,on,nu Flepair,d or ReplaC9d, end Replacement Compon1n11 Name of Min. Ser. -Nat'L CRN Other Year lllepairld, ASMECodl t-ioG111nt Mfr. No. Id. No. ldtntl- 111111 lllepltctel. l'8ms,ed No. recetion OI (Yno, NoJ lhplac:emtnl
'.l.1 .,_ .IAdr - - - - l ..~C-SII" 1.f'-r-1 (.
- ~~4J.c.&) Alo 1.
Olhtr 0 CERTIFICATE OF COMPLIANCE
.,,6 CERTIFICATE OF INSPECTION I, IN undersigned, holdiAt I valid commission 1ssutd by the N11lonal loard of Boner and Pr111u" V11MI lnspecton and Ult Sutt 0t Prov inn of VA e
- employtd bf uso* I& I co e ef Hartford. CT. ha** iftlPt<lld lht R~e l"'=e f1et.,t l"c~"'lalo< ~:111c*,..."llai ducribedin this Repof10ft / ~- 3(
- 11..fi al'ld na11 lhtt 10 1111 ben of my knowltd91 111d belitf, this ttp1ir or rtpl1c1man1 h11 been connrvc11d In 1cCD1d1nce with Section XI of th1 ASME Codi. Ir 1i911ing this c,r,ific.111, neither the ln~c:t=: l"..oi Mi fmploylt tn1kt1111y w1rr1nty, upr111ed or lmpl~d. conctrfto i"t lh1 rrp1ir or r,pl,cemcnt d,scribe4 in this Atpo,t, F11t1hermor1, 111ith1t the lnapfftor nor his emplorer a~n be liable in any """""
for eny personal injury or property d a ~ s r . f ~
- i n t from or connec11d witJI lhit lnc,ectiOI\. _
0111 Jo .. '3t-'S1 ~~ ~ Commiuion1 WCJ?oo~ Vq.6':(~
""IPKloi, cs.. ,** ~*-"'"-' IOIIII
""*R: SvpplelT\af\l.al '""" In form ef 11111, thUh*, er dr1wlt1pa mer be uHd p*o*ld*d CH 1IH Ill 1>6 lfto X II Ill..
l:IJ lftforlftetlo11 In '""" 1 111ro.1ffl 4 011 thl1 d111 rapon 11 lr,clvd*d en uch '""'* ,,,., Ill ucll 1hNI It 11umbe***
en*** """'bl' et,,. .. ,. 11 record~ 111h1 100 of dll1 fer,