ML17329A255: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(3 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 11/15/1991
| issue date = 11/15/1991
| title = LER 91-007-01:on 910819,shutdown Rods Mispositioned During Attempt to Move Control Rods Due to Malfunction of Multiplexing Relay in Rod Control Sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 Ltr
| title = LER 91-007-01:on 910819,shutdown Rods Mispositioned During Attempt to Move Control Rods Due to Malfunction of Multiplexing Relay in Rod Control Sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 Ltr
| author name = BEILMAN T P, BLIND A A
| author name = Beilman T, Blind A
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ACCELERATED D14TRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9111200330 DOC.DATE: 91/11/15 NOTARIZED:
{{#Wiki_filter:ACCELERATED D14TRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M AUTH.NAME AUTHOR AFFILIATION BEILMAN,T.P.
ACCESSION NBR:9111200330               DOC.DATE:   91/11/15   NOTARIZED: NO         DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana                 M 05000315 AUTH. NAME           AUTHOR AFFILIATION BEILMAN,T.P.         Indiana Michigan Power Co.
Indiana Michigan Power Co.BLIND,A.A.
BLIND,A.A.           Indiana Michigan Power Co.
Indiana Michigan Power Co.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000315
RECIP.NAME           RECIPIENT AFFILIATION


==SUBJECT:==
==SUBJECT:==
LER 91-007-01:on 910819,shutdown rods mispositioned during attempt to move control rods due to malfunction of multiplexing relay in rod control sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL L SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T-INTERNAL: ACNW AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D LB8D1 REG 02 RGN3 FILE 01 EXTERNAL: EGGG BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DOA AEOD/ROAB/DS P NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPBll NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
LER   91-007-01:on 910819,shutdown rods mispositioned during attempt to move control rods due to malfunction of multiplexing relay in rod control sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 ltr.
PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 Indiana Michigar~Power Company~Cook Vuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 November 15, 1991!Ni>54&"4 R~f CH$6RF>>P'O'M'CR United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.59 entitled Licensee Event Re ort S stem following report is being submitted:
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER),
91-007-0l Sincerely, the A.A.Blind Plant Manager AAB:sb Attachment c;D.H.Williams, Jr.A.B.Davis, Region III E.E.Fitzpatrick P.A.Barrett B.F.Henderson R.F.Kroeger B.Walters-Ft.Wayne NRC Resident Inspector T.Colburn-NRC J.G.Keppler M.R.Padgett G.Charnoff, Esq.D.Hahn INPO S.J.Brewer/B.P.Lauzau B.A.Svensson"-cry f i""00330 9 l 1:I<>F.+DOCK 0500v31.>F'DR NRC PDRM366 (669)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT ILER)APPROVEO OMB NO.31504)104 E XPIR ES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 60.0 HRS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F630), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.
ENCL L    SIZE:
OC 20555, AND TO THE'APERWORK REDUCTION PROJECT (3)600104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.
Incident Rpt, etc.
DC 20503.FACILITY NAME (I)DOCKET NUMBER (2)PA E D.C.Cook Nuclear Pl ant-Uni t 1 0 5 0 0 0 3 1 5 1 oF0 3 Shutdown Rods Mispositioned During Attempt To Move Control Rods Due To Malfunction Of Multi lexin Rela In The Rod Control S stem MONTH DAY YEAR YEAR EVENT DATE (5I LER NUMBER (6)SEQUENTIAL NUMBER REPORT DATE (7)YEAR REY0N MONTH OAY NVMBEII DOCKET NUMBER(SI 0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED I~)0 819 91 91 007 0'111 15 9 1 0 5 0 0 0 OPERATING MODE (6)POWER LEYEL 1 0 0 8!C.e~0 THE REQUIREMENTS OF 10 CFR (): (Cnectt one or more ol rhe followfnp)
NOTES:
(11 THIS REPORT IS SUBMITTED PURSUANT T 50.73(el(2)(le)50,73(e l(2)(e)50,73(el(2)(rN) 50.73(e I (2)I T)I I)I A I 50.73(el(2)(xlEI(B)50.73(~l(2)(el 20A02(B)20A05(~)(1)(0 20.405(el(II(E I 20A05(el(1)(IIII 20A05 le)(I I (ix)20AOS(el(II(x) 20A05(c)50M(c)(I I 50.36(cl(2)
RECIPIENT              COPIES            RECIPIENT         COPIES ID CODE/NAME           LTTR ENCL        ID  CODE/NAME      LTTR ENCL PD3-1 LA                     1    1      PD3-1 PD              1    1 COLBURN,T-                   1    1 INTERNAL:   ACNW                         2    2      AEOD/DOA              1    1 AEOD/DS P/TPAB               1    1      AEOD/ROAB/DS P        2    2 NRR/DET/ECMB 9H             1    1      NRR/DET/EMEB 7E        1    1 NRR/DLPQ/LHFB10              1    1      NRR/DLPQ/LPEB10        1   1 NRR/DOEA/OEAB                1    1      NRR/DREP/PRPBll        2    2 NRR/DST/SELB 8D              1    1      NRR/DST/SICB8H3       1    1 LB8D1          1    1      NRR/DST/SRXB 8E       1    1 REG              02        1    1    RES/DSIR/EIB           1    1 RGN3      FILE    01        1    1 EXTERNAL: EGGG BRYCE,J.H                3    3      L ST LOBBY WARD       1    1 NRC PDR                      1    1    NSIC MURPHY,G.A         1   1 NSIC POORE,W.                1     1     NUDOCS FULL TXT        1   1 NOTE TO ALL "RIDS" RECIPIENTS:
X 60.73(e)(21(1) 50.73(e)(2)(4) 50.73(e)(2)(IIII LICENSEE CONTACT FOR THIS LER (12I 73.71(B)73.71(c)OTHE R (Specify in AOrrrect Below emf ln yexr, Hf(C Form 366A)NAME T.P.Beilman-Maintenance Superintendant TELEPHONE NUMBER AREA CODE 61 646 5-5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYS'EM COMPONENT MANUFAC TURER EPORTABLE TO NPRDS~%mZ ynr CAUSE SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS E A RLY C34 6 N iI"+VI"e&#xc3;~pj~So.,',II,, x..',$9 Ski"%~a@~;,;,k~'Pg SUPPLEMENTAL REPORT EXPECTED l14)YES llf yN.COmplete EXPECTED SVBEIISSIOIY fJA Ml NO ABSTRACT ILlmfr to te00 rpecer, l.e..epproxlmetely fifteen rinple.recce typewritten liner)(16)EXPECTED SUBMISSION DATE I15)MONTH DAY YEAR This revision provides informaeion on the results of the root cause analysis and corrects the Failed Component Identification information.
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
On August 19, 1991, during routine surveillance testing of the full length rods, Control Bank A was ordered into the core by the Rod Control System but appeared not to move into the core by observation of the Analog Rod Position Indication.
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR               31   ENCL   31
Further positioning of Control Bank A resulted in an Urgent Alarm being received.Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm and it was reset.The rods were moved per the test requirements and the surveillance compleeed.
At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shuedown Bank A, Group 2 in relation to pre-surveillance readings.At 1305 hours the flux mapping system was used to determine that the 4 rods of Shutdown Bank A, Group 2 were inserted approximately 6 steps into the core.Further eroubleshooting of the Rod Control System discovered a failure of the 2AC Power Cabinet Multiplexing Relay, MXR-1.It was replaced and proper operation of the Rod Control Syseem was verified.The misaligned rods of Shutdown Bank A were brought out to the top of the core and normal operation resumed at 1605 hours.I NRC Form 366 (669)
NRC FORM 366A (6691 U.S.NUCLEAR REGULATORY COMMISSIO LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROV E'D OMB NO, 31500104 E XPI R E 6 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLl.FCTION REQUESTI 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-5301.U.S.NUCLEAR AEQUI.ATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PRO4ECT l315001041, OFFICE OF MANAGEMENT AND BUDGET.WASHINGTON, OC 20503.FACILITY NAMK (I)DOCKET NUMBER (21 LER NUMBER (61 PAGE (31 D.C.Cook Nuclear Plant-Unit 1 TEXT///mors sPsssis ssEIIiNd, IIss sdd/0'oIIE/
NRC%%dmI 366A'4/<<2(Y EA R"Q'.6 0 5 0 0 0 315 9]SEQUENTIAL P/'+NUMB E II.<BX 0 0 II 6 V IS I 0 N NUMEEII 01 02 0 3 Conditions Prior to Occurrence Unit One in Mode One at 100 Percent Rated Thermal Power.Descri tion of Event On August 19, 1991, during routine surveillance testing of the full length control rods, Control Bank A was ordered 8 steps into the core by the Rod Control System (EIIS/AA)but appeared not to move into the core by observation of the Analog Rod Position Indication.
Control Bank A was ordered another 2 steps into the core, leaving both group demand counters at 218 steps.The bank was ordered out of the core 4 steps and an Urgent Alarm was received.Further movement of the rods was discontinued pending investigation of the alarm.It was then noticed that Group 2 remained at 218 steps.The shutdown margin was then verified to known plant conditions at the time.Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm but it was noted that Power Cabinet 2AC (EIIS/AA-JX) vas selecting Shutdown Bank A instead of Control Bank A.As it was presumed to be selected by the control room, the alarm was reset and the rods were moved per the test requirements and the surveillance completed.
Subsequent discussions with control room personnel indicated that no other rod bank had been selected.At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shutdown Bank A, Group 2 in relation to pre-surveillance readings.At 1305 hours the flux mapping system was used to determine that the 4 rods of Shutdown Bank A, Group 2 vere inserted approximately 6 steps into the core and entry into Technical Specification


====3.0.3 began====
Indiana Michigar~
at this time.The flux mapping system was also used to verify.that any other banks involved with Power Cabinet 2AC vere not misaligned, The banks checked were Control Bank A, Control Bank C and also Shutdovn Bank A, Group 1.At 1403 hours reactor power reduction began and an Unusual Event was declared.Further troubleshooting of the Rod Control System discovered a failure of the 2AC Power Cabinet Multiplexing Relay, MXR-1 (EIIS/AA-RLY).
Power Company    ~
It was replaced and proper operation of the Rod Control System was verified.When tested later on the bench, the relay exhibited fluctuating coil circui,t readings out of the circuit.Notification of the event was made on the ENS at 1500 hours.Each of the misaligned rods of Shutdown Bank A was brought out to the top of the core, one at a time, while verifying that reactivity changes remained within limits.The Unusual Event was terminated at 1605 hours.Further research was conducted as to the possibility of the root cause being due to the Stationary B Firing card and/or the Signal Process card.Based on the available information and the satisfactory operating results since the event, the intermittent failure of MXR-1 is believed to be the cause of failure.
Cook Vuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901
NRC FORM 366A (649)u.s.NUCLEAR REGuLATORY COMMISSIO LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMS NO,31504i04 EXPIRES,'4/30/92 tSTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS iNFORMATION COLLECTION REOVEST'00 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGtMENT BRANCH IP-530), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555.AND TO 1HE PAPERWORK REDUCTION PROJECT 13')504'l04).
                                                                      !Ni>54&"4 R~f CH$ 6RF>>
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.
P'O'M'CR November 15, 1991 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland          20852 Operating Licenses DPR-58 Docket No. 50-315 Document        Control Manager:
DC 20503.FACILITY NAME I'I)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEGUENTIAL NUMSEA AEVISION NUMBER PAGE 131 D.C.Cook Nuclear Plant-Unit 1 TEXT///mdip 44444/4/Pi/uiipd, u44 dddicidnu//YRC Fomi 366A3)117) o s o o o 315 91 0 0 7 01 03 OF Cause of Event The rod misalignment was due to failure of the Multiplexing Relay, MXR-1, in Power Cabinet 2AC which allowed Shutdown Bank A, Group 2 to move while Control Bank A was selected.nal sis of Event Technical Specification 3.1.3.4 addresses the situation of only one shutdown rod below the insertion limit of 228 steps (fully withdrawn).
In accordance with the criteria established by 10 CFR 50.59 entitled Licensee Event Re ort S stem              the following report is being submitted:
As four shutdown rods were below this limit and required entry into Technical Specification 3.0.3, this event is considered to be reportable pursuant to 10CFR50.73(a)(2)(i)(B) as an operation prohibited by the Plant's Technical Specifications.
91-007-0l Sincerely, A. A. Blind Plant Manager AAB:sb Attachment c;      D. H.      Williams, Jr.
Safety consequences of the event were evaluated and determined to be insignificant.
A. B. Davis, Region E. E. Fitzpatrick III P. A. Barrett B. F. Henderson R. F. Kroeger B. Walters  Ft. Wayne NRC    Resident Inspector T. Colburn - NRC J. G. Keppler M. R. Padgett G. Charnoff, Esq.
Flux mapping measurements taken prior to the event (August 6, 1991)shows the following:
D. Hahn INPO S. J. Brewer/B. P. Lauzau B. A. Svensson
1)Margin in Heat flux hot channel factor 20.6X 2)Margin in Nuclear enthalpy hot channel factor 7.6X 3)Margin in Allowable power level 9.7X These margins can easily accommodate possible increase in peaking factors due to insertion of shutdown bank A by six steps.Also, a review of the Reload Safety Evaluation indicates an excess shutdown margin of 1817 pcm.This excess offsets any reduction in the shutdown margin due to insertion of Shutdown Bank A by six steps.Corrective Aetio Multiplexing Relay MXR-1 of Power Cabinet 2AC was replaced and proper operation of the Rod Control System was verified.The misaligned rods of Shutdown Bank A were then brought out to the proper position at the top of the core, one at a time.Subsequent use of the control rods to complete planned shutdown activities and routine surveillance testing has been satisfactory with no similar problems occurring.
" - cry f i""00330    9 l 1:I < >
Faile Co o t d ti atio Unit One Rod Control System, Power Cabinet 2AC, Multiplexing Relay MXR-1 Plant Designation:
F.  +DOCK    0500v31.>
2-RCS-2AC, 2A1EZl Manufacturer:
F'DR
C.P.Clare and Company Model: HG3A-1004 EIIS Code: AA-RLY Previous Similar Events None}}
 
NRC PDRM366                                                                  U.S. NUCLEAR REGULATORY COMMISSION (669)                                                                                                                                                  APPROVEO OMB NO. 31504)104 E XPIR ES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 60.0 HRS, FORWARD LICENSEE EVENT REPORT ILER)                                                                  COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555, AND TO THE'APERWORK REDUCTION PROJECT (3)600104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.
FACILITY NAME (I)                                                                                                                              DOCKET NUMBER (2)                              PA E D. C. Cook              Nuclear Pl ant - Uni t 1                                                                                  0 5 0          0      0    3 1 5      1    oF0      3 Shutdown Rods Mispositioned During Attempt To Move Control Rods                                                                                Due To Malfunction Of Multi lexin Rela In The Rod Control S stem EVENT DATE (5I                      LER NUMBER (6)                            REPORT DATE (7)                              OTHER FACILITIES INVOLVED I~ )
MONTH    DAY    YEAR    YEAR            SEQUENTIAL            REY0N MONTH            OAY          YEAR            FACILITY NAMES                              DOCKET NUMBER(SI NUMBER            NVMBEII 0    5  0    0    0 0      819 91 91                                007                0    '111 15                          9 1                                                          0    5  0    0    0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CFR (): (Cnectt one or more                            ol rhe followfnp) (11 OPERATING MODE (6)                    20A02(B)                                    20A05(c)                                50.73(el(2) (le)                                    73.71(B)
POWER                          20A05( ~ ) (1)(0                            50M(c) (I I                            50,73(e l(2)(e)                                    73.71(c)
LEYEL 1  0 0              20.405(el(II(E I                            50.36(cl(2)                            50,73(el(2)(rN)                                    OTHE R (Specify in AOrrrect Below emf ln yexr, Hf(C Form 20A05(el(1)(IIII                      X    60.73(e)(21(1)                          50.73(e I (2) I T)I I) IA I                        366A) 8!C.              e~
20A05 le) (I I (ix) 20AOS(el(II(x) 50.73(e)(2)(4) 50.73(e)(2)(IIII 50.73(el(2) (xlEI(B) 50.73( ~ l(2)(el LICENSEE CONTACT FOR THIS LER (12I NAME                                                                                                                                                                TELEPHONE NUMBER T. P. Beilman                -  Maintenance Superintendant AREA CODE 61 646                    5- 5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC            EPORTABLE                ~%mZ CAUSE  SYS'EM    COMPONENT                                                                            CAUSE SYSTEM  COMPONENT MANUFAC.            EPORTABLE TURER            TO NPRDS      ynr                                                                      TURER            TO NPRDS E      A        RLY                    C34            6          N      iI"+VI"e
                                                                                  &#xc3;  ~
pj~
Ski"%
So  .,',II,, x..',$ 9                                                                              ~a@~;,;,k~'Pg SUPPLEMENTAL REPORT EXPECTED l14)                                                                                            MONTH      DAY      YEAR EXPECTED SUBMISSION DATE I15)
YES llfyN. COmplete EXPECTED SVBEIISSIOIY fJA Ml                                      NO ABSTRACT ILlmfr to te00 rpecer, l.e.. epproxlmetely fifteen rinple.recce typewritten liner) (16)
This revision provides informaeion on the results of the root cause analysis and corrects the Failed Component Identification information.
On  August 19, 1991, during routine surveillance testing of the full length rods, Control Bank A was ordered into the core by the Rod Control System but                                                                                          appeared not to move into the core by observation of the Analog Rod Position Indication.
Further positioning of Control Bank A resulted in an Urgent Alarm being received.
Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm and            it surveillance compleeed.
was reset.                  The rods were moved per the test requirements and the At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shuedown Bank A, Group 2 in relation to pre-surveillance At 1305 hours the flux mapping system was used to determine that the 4readings.                                                                                  rods of Shutdown Bank A, Group 2 were inserted approximately 6 steps into the core.
Further eroubleshooting of the Rod Control System discovered a failure of the 2AC Power Cabinet Multiplexing Relay, MXR-1. It was replaced                                                                                                    operation of the Rod Control Syseem was verified. The misaligned rodsandofproper                                                                          Shutdown Bank A were brought out to the top of the core and normal operation resumed at 1605 hours.                                                                                                                                                                                  I NRC Form 366 (669)
 
NRC FORM 366A                                                                U.S. NUCLEAR REGULATORY COMMISSIO (6691                                                                                                                          APPROV E'D OMB NO, 31500104 E XPI R E 6 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER)                                                INFORMATION COLl.FCTION REQUESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION                                                  AND REPORTS MANAGEMENT BRANCH IP-5301. U.S. NUCLEAR AEQUI.ATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PRO4ECT l315001041, OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, OC 20503.
FACILITY NAMK (I)                                                                  DOCKET NUMBER (21                    LER NUMBER (61                            PAGE (31 Y EA R "Q'.6 SEQUENTIAL    P/'+ II6 V IS I 0 N NUMBE II    .<BX NUMEEII D. C. Cook              Nuclear Plant - Unit                    1 0  5  0  0    0  315 9]                0 0                    01 02                0 3 TEXT /// mors sPsssis ssEIIiNd, IIss sdd/0'oIIE/ NRC %%dmI 366A'4/ <<2(
Conditions Prior to Occurrence Unit      One      in      Mode One          at      100 Percent Rated Thermal Power.
Descri tion of Event On    August 19, 1991, during routine surveillance testing of the full length control rods, Control Bank A was ordered 8 steps into the core by the Rod Control System (EIIS/AA) but appeared not to move into the core by observation of the Analog Rod Position Indication. Control Bank A was ordered another 2 steps into the core, leaving both group demand counters at 218 steps. The bank was ordered out of the core 4 steps and an Urgent Alarm was received. Further movement of the rods was discontinued pending investigation of the alarm.
noticed that Group 2 remained at 218 steps.                                                The shutdown margin was then It was then verified to known plant conditions at the time.
Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm but it was noted that Power Cabinet 2AC (EIIS/AA-JX) vas selecting Shutdown Bank A instead of Control Bank A. As it was presumed to be selected by the control room, the alarm was reset and the rods were moved per the test requirements and the surveillance completed. Subsequent discussions with control room personnel indicated that no other rod bank had been selected.                                                                              At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shutdown Bank A, Group 2 in relation to pre-surveillance readings.
At 1305 hours the flux mapping system was used to determine that the 4 rods of Shutdown Bank A, Group 2 vere inserted approximately 6 steps into the core and entry into Technical Specification 3.0.3 began at this time. The flux mapping system was also used to verify. that any other banks involved with Power Cabinet 2AC vere not misaligned,                                 The banks checked were Control Bank A, Control Bank C and also Shutdovn Bank A, Group 1. At 1403 hours reactor power reduction began and an Unusual Event was declared.
Further troubleshooting of the                                 Rod Control System discovered a failure of the 2AC Power Cabinet                       Multiplexing Relay, MXR-1 (EIIS/AA-RLY). It was replaced and proper operation of the Rod Control System was verified. When tested later on the bench, the relay exhibited fluctuating coil circui,t readings out of the circuit.
Notification of the event was made on the ENS at 1500 hours. Each of the misaligned rods of Shutdown Bank A was brought out to the top of the core, one at a time, while verifying that reactivity changes remained within limits. The Unusual Event was terminated at 1605 hours.
Further research was conducted as to the possibility of the root cause being due to the Stationary B Firing card and/or the Signal Process card. Based on the available information and the satisfactory operating results since the event, the intermittent failure of MXR-1 is believed to be the cause of failure.
 
NRC FORM 366A                                                             u.s. NUCLEAR REGuLATORY COMMISSIO (649)                                                                                                                     APPROVED OMS NO,31504i04 EXPIRES, '4/30/92 tSTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER)                                            iNFORMATION COLLECTION REOVEST'00 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION                                              AND REPORTS MANAGtMENTBRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO 1HE PAPERWORK REDUCTION PROJECT 13')504'l04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.
FACILITY NAME I'I)                                                               DOCKET NUMBER (2)                   LER NUMBER (6)                 PAGE  131 YEAR      SEGUENTIAL     AEVISION NUMSEA       NUMBER D. C. Cook                 Nuclear Plant - Unit                   1       o  s  o  o  o  315 91              0 0    7          01 03        OF TEXT /// mdip 44444 /4 /Pi/uiipd, u44 dddicidnu//YRC Fomi 366A3)117)
Cause         of Event The rod misalignment was due to failure of the Multiplexing Relay, MXR-1, in Power Cabinet 2AC which allowed Shutdown Bank A, Group 2 to move while Control Bank A was selected.
nal sis of Event Technical Specification 3.1.3.4 addresses the situation of only one shutdown rod below the insertion limit of 228 steps (fully withdrawn). As four shutdown rods were below this limit and required entry into Technical Specification 3.0.3, this event is considered to be reportable pursuant to 10CFR50.73(a)(2)(i)(B) as an operation prohibited by the Plant's Technical Specifications.
Safety             consequences                 of the event were evaluated and determined to be insignificant.                       Flux mapping measurements taken prior to the event (August 6, 1991) shows the                     following:
: 1)           Margin in Heat flux hot channel factor                                     20.6X
: 2)           Margin in Nuclear enthalpy hot channel factor                                 7.6X
: 3)           Margin in Allowable power level                                               9.7X These margins can easily accommodate possible increase in peaking factors due to insertion of shutdown bank A by six steps. Also, a review of the Reload Safety Evaluation indicates an excess shutdown margin of 1817 pcm. This excess offsets any reduction in the shutdown margin due to insertion of Shutdown Bank A by six steps.
Corrective Aetio Multiplexing Relay                         MXR-1       of Power Cabinet 2AC was replaced and proper operation of the Rod Control                         System was verified. The misaligned rods of Shutdown Bank A were then brought out to the proper position at the top of the core, one at a time. Subsequent use of the control rods to complete planned shutdown activities and routine surveillance testing has been satisfactory with no similar problems occurring.
Faile Co o t d ti atio Unit One Rod Control System, Power Cabinet                                       2AC,   Multiplexing Relay           MXR-1 Plant Designation: 2-RCS-2AC, 2A1EZl Manufacturer:                                 C.P. Clare and Company Model:                                       HG3A-1004 EIIS Code:                                   AA-RLY Previous Similar Events None}}

Latest revision as of 05:56, 29 October 2019

LER 91-007-01:on 910819,shutdown Rods Mispositioned During Attempt to Move Control Rods Due to Malfunction of Multiplexing Relay in Rod Control Sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 Ltr
ML17329A255
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 11/15/1991
From: Beilman T, Blind A
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-007, LER-91-7, NUDOCS 9111200330
Download: ML17329A255 (5)
v • d • e


Text

ACCELERATED D14TRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9111200330 DOC.DATE: 91/11/15 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH. NAME AUTHOR AFFILIATION BEILMAN,T.P. Indiana Michigan Power Co.

BLIND,A.A. Indiana Michigan Power Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-007-01:on 910819,shutdown rods mispositioned during attempt to move control rods due to malfunction of multiplexing relay in rod control sys.Multiplexing Relay MXR-1 of Power Cabinet 2AC replaced.W/911115 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TITLE: 50.73/50.9 Licensee Event Report (LER),

ENCL L SIZE:

Incident Rpt, etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 COLBURN,T- 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPBll 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 LB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG 02 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL: EGGG BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

Indiana Michigar~

Power Company ~

Cook Vuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901

!Ni>54&"4 R~f CH$ 6RF>>

P'O'M'CR November 15, 1991 United States Nuclear Regulatory Commission Document Control Desk Rockville, Maryland 20852 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.59 entitled Licensee Event Re ort S stem the following report is being submitted:

91-007-0l Sincerely, A. A. Blind Plant Manager AAB:sb Attachment c; D. H. Williams, Jr.

A. B. Davis, Region E. E. Fitzpatrick III P. A. Barrett B. F. Henderson R. F. Kroeger B. Walters Ft. Wayne NRC Resident Inspector T. Colburn - NRC J. G. Keppler M. R. Padgett G. Charnoff, Esq.

D. Hahn INPO S. J. Brewer/B. P. Lauzau B. A. Svensson

" - cry f i""00330 9 l 1:I < >

F. +DOCK 0500v31.>

F'DR

NRC PDRM366 U.S. NUCLEAR REGULATORY COMMISSION (669) APPROVEO OMB NO. 31504)104 E XPIR ES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 60.0 HRS, FORWARD LICENSEE EVENT REPORT ILER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555, AND TO THE'APERWORK REDUCTION PROJECT (3)600104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME (I) DOCKET NUMBER (2) PA E D. C. Cook Nuclear Pl ant - Uni t 1 0 5 0 0 0 3 1 5 1 oF0 3 Shutdown Rods Mispositioned During Attempt To Move Control Rods Due To Malfunction Of Multi lexin Rela In The Rod Control S stem EVENT DATE (5I LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED I~ )

MONTH DAY YEAR YEAR SEQUENTIAL REY0N MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(SI NUMBER NVMBEII 0 5 0 0 0 0 819 91 91 007 0 '111 15 9 1 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T0 THE REQUIREMENTS OF 10 CFR (): (Cnectt one or more ol rhe followfnp) (11 OPERATING MODE (6) 20A02(B) 20A05(c) 50.73(el(2) (le) 73.71(B)

POWER 20A05( ~ ) (1)(0 50M(c) (I I 50,73(e l(2)(e) 73.71(c)

LEYEL 1 0 0 20.405(el(II(E I 50.36(cl(2) 50,73(el(2)(rN) OTHE R (Specify in AOrrrect Below emf ln yexr, Hf(C Form 20A05(el(1)(IIII X 60.73(e)(21(1) 50.73(e I (2) I T)I I) IA I 366A) 8!C. e~

20A05 le) (I I (ix) 20AOS(el(II(x) 50.73(e)(2)(4) 50.73(e)(2)(IIII 50.73(el(2) (xlEI(B) 50.73( ~ l(2)(el LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER T. P. Beilman - Maintenance Superintendant AREA CODE 61 646 5- 5901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC EPORTABLE ~%mZ CAUSE SYS'EM COMPONENT CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE TURER TO NPRDS ynr TURER TO NPRDS E A RLY C34 6 N iI"+VI"e

à ~

pj~

Ski"%

So .,',II,, x..',$ 9 ~a@~;,;,k~'Pg SUPPLEMENTAL REPORT EXPECTED l14) MONTH DAY YEAR EXPECTED SUBMISSION DATE I15)

YES llfyN. COmplete EXPECTED SVBEIISSIOIY fJA Ml NO ABSTRACT ILlmfr to te00 rpecer, l.e.. epproxlmetely fifteen rinple.recce typewritten liner) (16)

This revision provides informaeion on the results of the root cause analysis and corrects the Failed Component Identification information.

On August 19, 1991, during routine surveillance testing of the full length rods, Control Bank A was ordered into the core by the Rod Control System but appeared not to move into the core by observation of the Analog Rod Position Indication.

Further positioning of Control Bank A resulted in an Urgent Alarm being received.

Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm and it surveillance compleeed.

was reset. The rods were moved per the test requirements and the At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shuedown Bank A, Group 2 in relation to pre-surveillance At 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> the flux mapping system was used to determine that the 4readings. rods of Shutdown Bank A, Group 2 were inserted approximately 6 steps into the core.

Further eroubleshooting of the Rod Control System discovered a failure of the 2AC Power Cabinet Multiplexing Relay, MXR-1. It was replaced operation of the Rod Control Syseem was verified. The misaligned rodsandofproper Shutdown Bank A were brought out to the top of the core and normal operation resumed at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />. I NRC Form 366 (669)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSIO (6691 APPROV E'D OMB NO, 31500104 E XPI R E 6 I 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLl.FCTION REQUESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP-5301. U.S. NUCLEAR AEQUI.ATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PRO4ECT l315001041, OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON, OC 20503.

FACILITY NAMK (I) DOCKET NUMBER (21 LER NUMBER (61 PAGE (31 Y EA R "Q'.6 SEQUENTIAL P/'+ II6 V IS I 0 N NUMBE II .<BX NUMEEII D. C. Cook Nuclear Plant - Unit 1 0 5 0 0 0 315 9] 0 0 01 02 0 3 TEXT /// mors sPsssis ssEIIiNd, IIss sdd/0'oIIE/ NRC %%dmI 366A'4/ <<2(

Conditions Prior to Occurrence Unit One in Mode One at 100 Percent Rated Thermal Power.

Descri tion of Event On August 19, 1991, during routine surveillance testing of the full length control rods, Control Bank A was ordered 8 steps into the core by the Rod Control System (EIIS/AA) but appeared not to move into the core by observation of the Analog Rod Position Indication. Control Bank A was ordered another 2 steps into the core, leaving both group demand counters at 218 steps. The bank was ordered out of the core 4 steps and an Urgent Alarm was received. Further movement of the rods was discontinued pending investigation of the alarm.

noticed that Group 2 remained at 218 steps. The shutdown margin was then It was then verified to known plant conditions at the time.

Initial troubleshooting of the Rod Control System found no reason for the Urgent Alarm but it was noted that Power Cabinet 2AC (EIIS/AA-JX) vas selecting Shutdown Bank A instead of Control Bank A. As it was presumed to be selected by the control room, the alarm was reset and the rods were moved per the test requirements and the surveillance completed. Subsequent discussions with control room personnel indicated that no other rod bank had been selected. At approximately 1200, a rod misalignment in Shutdown Bank A, Group 2 was suspected due to additional small amount of dilution required to keep thermal power at the pre-surveillance level and a decrease in the Analog Rod Position Indication for Shutdown Bank A, Group 2 in relation to pre-surveillance readings.

At 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> the flux mapping system was used to determine that the 4 rods of Shutdown Bank A, Group 2 vere inserted approximately 6 steps into the core and entry into Technical Specification 3.0.3 began at this time. The flux mapping system was also used to verify. that any other banks involved with Power Cabinet 2AC vere not misaligned, The banks checked were Control Bank A, Control Bank C and also Shutdovn Bank A, Group 1. At 1403 hours0.0162 days <br />0.39 hours <br />0.00232 weeks <br />5.338415e-4 months <br /> reactor power reduction began and an Unusual Event was declared.

Further troubleshooting of the Rod Control System discovered a failure of the 2AC Power Cabinet Multiplexing Relay, MXR-1 (EIIS/AA-RLY). It was replaced and proper operation of the Rod Control System was verified. When tested later on the bench, the relay exhibited fluctuating coil circui,t readings out of the circuit.

Notification of the event was made on the ENS at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. Each of the misaligned rods of Shutdown Bank A was brought out to the top of the core, one at a time, while verifying that reactivity changes remained within limits. The Unusual Event was terminated at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />.

Further research was conducted as to the possibility of the root cause being due to the Stationary B Firing card and/or the Signal Process card. Based on the available information and the satisfactory operating results since the event, the intermittent failure of MXR-1 is believed to be the cause of failure.

NRC FORM 366A u.s. NUCLEAR REGuLATORY COMMISSIO (649) APPROVED OMS NO,31504i04 EXPIRES, '4/30/92 tSTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) iNFORMATION COLLECTION REOVEST'00 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGtMENTBRANCH IP-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO 1HE PAPERWORK REDUCTION PROJECT 13')504'l04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME I'I) DOCKET NUMBER (2) LER NUMBER (6) PAGE 131 YEAR SEGUENTIAL AEVISION NUMSEA NUMBER D. C. Cook Nuclear Plant - Unit 1 o s o o o 315 91 0 0 7 01 03 OF TEXT /// mdip 44444 /4 /Pi/uiipd, u44 dddicidnu//YRC Fomi 366A3)117)

Cause of Event The rod misalignment was due to failure of the Multiplexing Relay, MXR-1, in Power Cabinet 2AC which allowed Shutdown Bank A, Group 2 to move while Control Bank A was selected.

nal sis of Event Technical Specification 3.1.3.4 addresses the situation of only one shutdown rod below the insertion limit of 228 steps (fully withdrawn). As four shutdown rods were below this limit and required entry into Technical Specification 3.0.3, this event is considered to be reportable pursuant to 10CFR50.73(a)(2)(i)(B) as an operation prohibited by the Plant's Technical Specifications.

Safety consequences of the event were evaluated and determined to be insignificant. Flux mapping measurements taken prior to the event (August 6, 1991) shows the following:

1) Margin in Heat flux hot channel factor 20.6X
2) Margin in Nuclear enthalpy hot channel factor 7.6X
3) Margin in Allowable power level 9.7X These margins can easily accommodate possible increase in peaking factors due to insertion of shutdown bank A by six steps. Also, a review of the Reload Safety Evaluation indicates an excess shutdown margin of 1817 pcm. This excess offsets any reduction in the shutdown margin due to insertion of Shutdown Bank A by six steps.

Corrective Aetio Multiplexing Relay MXR-1 of Power Cabinet 2AC was replaced and proper operation of the Rod Control System was verified. The misaligned rods of Shutdown Bank A were then brought out to the proper position at the top of the core, one at a time. Subsequent use of the control rods to complete planned shutdown activities and routine surveillance testing has been satisfactory with no similar problems occurring.

Faile Co o t d ti atio Unit One Rod Control System, Power Cabinet 2AC, Multiplexing Relay MXR-1 Plant Designation: 2-RCS-2AC, 2A1EZl Manufacturer: C.P. Clare and Company Model: HG3A-1004 EIIS Code: AA-RLY Previous Similar Events None

Retrieved from "https://kanterella.com/w/index.php?title=ML17329A255&oldid=1984039"