|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20199A6621999-01-0505 January 1999 Special Rept:On 981230,hi Range Noble Gas Monitor Was Inoperable for Greater than Seven Days.Cause Unknown. Preplanned Alternate Method of Monitoring Appropriate Parameters within 72 H Was Established ML20058H6851990-11-14014 November 1990 Special Rept:On 901024,high-range Noble Gas Monitor Inoperable for More than 72 H ML20207L8191988-10-12012 October 1988 Special Rept:On 880913,high Range Noble Gas Effluent Monitor Detector Failed Due to Water Intrusion Into Detector Well. on 880915,spare Detector Installed & Tested,Resulting in Discovery That Source Check Circuit Not Operating Properly ML20151U8361988-08-11011 August 1988 Ro:On 880715,discovered That Fission Chamber Containing 4 Uci U-235 & 0.05 Uci U-238 Missing.Accountability Program Upgraded to More Rigorously Incorporate Small Quantities of non-fuel SNM ML20197E7171988-06-0303 June 1988 Special Rept:On 880426,diesel Fire Pump Selector Switch Placed to Off Position Defeating Auto Start Feature of Pump for More than 7 Days.Temporary Change to Battery Test Procedure Restored Battery Svcs Prior to Operability ML20055A6771982-05-26026 May 1982 Telecopy Message of Ro:On 820525,multiple Minor Through Wall Tube Leaks Discovered in B Heating & Cooling Hx,Initially Reported 820526.HX Valved Out of Svc Pending Completion of Repairs ML20054F7681981-06-15015 June 1981 Telecopy Message of Ro:On 820611,electrical Fire in turbine- Generator Exciter Forced Shutdown of Reactor.No Radiological Release or Injuries to Employees.Fire Controlled in 1/2-h. Extensive Damage to Exciter Brushers ML20151C1901976-01-20020 January 1976 RO P-1-76:on 760119,inadequate Design Pressure Ratings Found on Relief Switches DPS-9051 & 9052,transmitter PT-173 & Reactor Protection Containment Pressure Switches PS-664,665, 666 & 667.Caused by Inadequate Design Specs ML20126E3471966-08-0909 August 1966 Ro:On 660808,after Reactor Trip Due to Lightning,Turbine Generator Did Not Trip & Continued to Carry Facility Power from Residual Steam in Primary Sys,Reducing Reactor Pressure.Caused by Bypass Valve Malfunction 1999-01-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C3031999-09-28028 September 1999 Annual Rept of Facility Changes,Tests & Experiments ML20199A6621999-01-0505 January 1999 Special Rept:On 981230,hi Range Noble Gas Monitor Was Inoperable for Greater than Seven Days.Cause Unknown. Preplanned Alternate Method of Monitoring Appropriate Parameters within 72 H Was Established ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML20198K6611998-12-24024 December 1998 Safety Evaluation Supporting Amend 120 to License DPR-6 ML20154E0371998-09-30030 September 1998 Safety Evaluation Accepting Request for Exemption from Certain Portions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities & Reduce Scope of Onsite EP as Result of Permanently Shutdown ML20154E0581998-09-30030 September 1998 Safety Evaluation Accepting Licensee Request from Exemption from Certain Portions of 10CFR50.47(b) ML20198K0091998-09-18018 September 1998 SER Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Big Rock Nuclear Plant ML20217N2131998-04-24024 April 1998 Brpnp Zircaloy Oxidation Analysis ML20216K0011998-04-16016 April 1998 Safety Evaluation Approving Licensee Request Re Plant Training Program for Certified Fuel Handlers ML20217H4641998-03-26026 March 1998 Rev 2 to Post Shutdown Decommissioning Activities Rept (Psdar) ML20202G1941998-02-12012 February 1998 Rev 7 to Updated Final Hazards Summary Rept for Big Rock Point Plant ML20154A7591997-10-0808 October 1997 10CFR50.59 Annual Rept of Facility Changes,Tests & Experiments, Since 971008 ML20216E4731997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Big Rock Point Plant ML20141J8731997-08-14014 August 1997 Safety Evaluation Supporting Amend 119 to License DPR-6 ML20210H5601997-07-31031 July 1997 Monthly Operating Rept for July 1997 for Brpnp ML20148T4901997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Big Rock Point Nuclear Plant ML20148N9251997-06-0606 June 1997 Rev 18 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20140C8981997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Big Rock Nuclear Power Plant ML20138J0121997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Big Rock Point ML20137X0161997-04-18018 April 1997 Safety Evaluation Accepting Changes to Rev 17 of CPC Quality Program Description for Operational NPPs (CPC-2A) ML20137J9381997-04-0202 April 1997 Safety Evaluation Supporting Amend 118 to License DPR-6 ML20137P0391997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Big Rock Point Nuclear Plant ML20135F2361997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Big Rock Nuclear Plant ML20148N9181997-02-0101 February 1997 Rev 17 to CPC-2A, Quality Program Description for Operational Nuclear Plants ML20134H3691997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Big Rock Point Nuclear Plant ML20137F2101996-12-31031 December 1996 1996 Annual Financial Rept CMS Energy ML20133C5421996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Big Rock Point Nuclear Plant ML20135E5101996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Big Rock Point Nuclear Plant ML20134H3381996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Big Rock Point Nuclear Plant ML20211N1561996-10-0808 October 1996 Annual Rept of Facility Changes,Tests & Experiments, Consisting of Mods & Miscellaneous Changes Performed Since 961008 ML20128F9821996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Big Rock Point Nuclear Plant ML20059E8321993-12-31031 December 1993 Monthly Operating Rept for Dec 1993 for Big Rock Point Nuclear Plant ML20058K0931993-11-30030 November 1993 Monthly Operating Rept for Nov 1993 for Big Rock Point Nuclear Plant ML20058E8961993-11-29029 November 1993 1993 ISI Rept 3-1 Big Rock Point Plant, for 930626-0905 ML20058F3441993-11-22022 November 1993 Safety Evaluation Concurring W/Contractor Findings Presented in Technical Evaluation Rept EGG-RTAP-10816, Evaluation of Utility Responses to Suppl 1 to NRC Bulletin 90-01;Big Rock Point ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20058A1601993-11-15015 November 1993 Safety Evaluation Supporting Amend 112 to License DPR-6 ML20059J4531993-10-31031 October 1993 Monthly Operating Rept for Oct 1993 for Big Rock Point Nuclear Plant ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20057E1981993-10-0505 October 1993 Safety Evaluation Supporting Amend 111 to License DPR-6 ML20057E8341993-09-30030 September 1993 Monthly Operating Rept for Sept 1993 for Big Rock Point Nuclear Plant ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20056G9171993-08-31031 August 1993 Monthly Operating Rept for Aug 1993 for Big Rock Point Nuclear Plant ML20056E1661993-08-16016 August 1993 Safety Evaluation Supporting Amend 110 to License DPR-6 ML18058B8821993-06-15015 June 1993 Rev 13 to Quality Program Description for Operational Nuclear Power Plants. ML20128P5501993-02-18018 February 1993 Section 2.5 of Big Rock Point Updated Final Hazards Summary Rept ML20128F3511993-01-31031 January 1993 Monthly Operating Rept for Jan 1993 for Big Rock Point Nuclear Plant ML20128C4341993-01-29029 January 1993 Forwards Rev 3 to Updated Final Hazards Summary Rept ML20058L8721992-12-31031 December 1992 1992 Annual Rept,Cpc ML20127K8941992-12-31031 December 1992 Revised Pages to Graybook Rept for Dec 1992 for Big Rock Point Nuclear Plant 1999-09-28
[Table view] |
Text
, -_- . .. --. - .___- =~. , . . - . . . . - -
4~
g,, . v.....
, . , . , , n.1 pp.o 'g >
3' t- ::
'(3.h f r wu A9Cf NFEA '
, e * [1 +
Ia rt u
- 3 VU MVfJ ILL
(*r '
' tii.' fs< vilA349 '"i (936ACST)
Ilih VLE245(1019)(1-035941AD21)PD 01/21/76 1011
- N ;,' TLX CONSFOUEn JK!J . '
,,C ll - ?CZC ;":C DLY- J ACKSON !!ICHIG AN 1-21 _
- f;u P;iS US NUCLEAR RE30LATORY COM
- 11SSION I E ,
- (FOM1Ei,LY US. ATOMIC ENER1Y COM) ,
i! MR J 1 MEP"LER
. L !il t
799 ROOSEF.LT ROAD
- []$ 4 9L E'
- ELLYN, IL 66?137- i r ;r : . .
J
' '45 y THE FOLLO' DIN 1. VILL CONFInli THE TELECON BETVEEN D E DE M00it AUD- '
. . .' ;j .u, D HU'JTER AT 143 3 J A'!U *,3Y '20, 1976.
- 1 ts., t. .
- . +-
J. REDORT.90 P-1 DOCKET 50-155 '
p:.; - ,
e i 2 A . .. REPDET DATE 20-76 ea i 2! ,
1
[Qh i2m c ,y ..s
- t../ L<
8 .
i : -
f- ,
. .( - * :j .!
.t
=
i r*3 0CCU.17tENCE DATE 19-76 ,
o fg , ,5 . FACILITY - B13 ROCK POINT PLANT, CHARLEVOIX, IIICHIGEN . -l
- ,
- :5
- 4. IDENTIFICATION OF OCCURRENCE - CONTAIMMENT' PRESSURE ~AND
!I-l$ p VACUU:1 DEVICES I!"PRDPER APPLICATION.
191; i
- [-4 w y ,. 5. ; CONDITIO::S PRIOR TO OCCUTtnENCE - POVElt OPERATION - 145 t'L'T. l 4
r:: 'i . DESCf:IPTION OF OCCUnnZNCE DURIN3 REVIEN OF TESTING RE0VIRE-D NEUIS ASSOCI ATED '<.'ITH 10 CFR 50, APPENDIX J, THE TOLLO'.!IllG -IN-f.i STi:U'!E!iT AND CONTFs0LS WERE IDENTIFIED AS HAVIN3 ' INADEQUATE DESIGi!
DRESSURE RATINGS..
W In-j; i
t ~. i i Us i
' d, .,, i- .
.i
' IL.5 .
.i
' . (a;gj .
y,= [ '
4 THIS DOCUMENT CONTAINS :
POOR QlJAUTY PAGES o .
t l
f O.
M
{. : ! PT-173 - CONI A T Nl1: V/iCVUM TRANSNITTER
. . . , i.
L'F ,.
DP3- Je51, DDG-9052 - CONTAINi"ENT VACUUN RELIEF SUITCHES
- pp i n. f p s r/.t, , cA S , 6',5, 667 - REACTOR PROTECTION CONTAIN.':ENT PRESCUME
[. J 'i, .
W 1 TC C, f
I.[ . 6 7 ;E ;1G'hTION JF APPARENT CAUSE OF OCCURRENCE - INA DEQUt.T E deb 1':" ';"ECIF In ATIONS MEL ATED TO ORIGIN /il PLANT CONTAINi;ENT DESIGN i.- PRESOUF. Cf: ITED1A.
P( f 8. M!$ LYSIS OF OCCURRENCE - THE POCCIPILITY EXISTS THAT AUTO'MTIC CC' T AI' y"I Vt.CUU1 r.ELIEF FUNCTION VOULD NOT DE OPER ABLE IN THE
- .j
,i OCT DM CO'!:41 TIC'! SECAUSE DPS-9.151 ' AND DPS-9C52 VOULD NOT FUUCTIO:;
4 i
L '
8
(,
. 1:
r '
f _
r t.
L$ t."TE.1 BEI3 EXPOSED TO PRESSURES GREATER THAN 15 PSIG.
i ,_
- .n. PG-56r THr.0U'M 557 ARE DEEMED ADEQUATE FOR THEIR SCRAM ISOLATI0')
Fuf:CII0'! SI':CE IT OCCURS AT A PT.ESSUiG FAR LO'.'Eff THAN THE PRESSU.' E i- -
! vt!IC" "OULD A USE S ITCH DIS ABILITY. PT-173 UD'dLD PROBABLY RUMUEE F '
US!1 AND CAUSE A SMALL 3HEAK OF INTEGRITY FOLLOUING A CONTAIM-
"iT,E"I1:
(
Uf ;
P'.EG SUT.E A CC IDE'?I.
, .: i
- 9. COMEC1 IV? ACT10*! - PROCEDURAL CD'JTROLS TO ISOLATE PT-173 AND dos-9.%) /.Nn 'OS-9052 AND SUBSE9UENTLY RETuriN TO OPERATIOil AT
[l, ' ;;- P;;ESSJ:'ES LEOS THAM 13 PSIG ARE BEING DEVELOPED.
('.
(
( , 1e. FAILU9E DATA - PT-173 - BAILEY f1ETER BD- 1117 A t ,' " (, DPS-9251, 9C52 MERCOID DAV 533 , R2
.N
.t.
,-.c
' !J . .
L.: 'li [
l ', S P S- G G t. THROU3H 667 MERCOID DAV 23-153, R3/s I c.
L=p I: CC; C J HART;:AN
(.a [
p R B set' ELL,
(9 .C p CO DC U"E't 3 PO'.'ETr CO L. 4 J'IP 'd dICHISAM AVE ,
[ '. 41.L 'to .
g,
~
F .
, . v
[. t'd A C Y V HE A .j>' >' >.
i p 1976 y' 5 ,
e
.