LER-2076-028, License Event Report 1976-028-00 Re Rod Sequencer Operation |
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| 2552076028R00 - NRC Website |
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t consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 September 9, 1976 Mr James G Keppler Office of Inspection & Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR PALISADES PLANT - ER-76-28 ROD SEQUENCER OPERATION Attached is a reportable event related to the Palisades Plant.
David A*Bixel Assistant Nuclear Licensing Administrator SEP 13 i976
'l
- - ICENSEE EVENT CONTROL BLOCK:._I ---1._..___.___.__--J.__.I [PLEASE PRINT ALL REGUIRED INFORMATKllll]
1 6
LICENSEE NAME
@El I Ml rl PIAI LI ii 7
B 9 14 LICENSE NUMBER 10101-10101010101-10101 15 25 LICENSE TYPE 14111111111 26 30 EVENT TYPE Io 11 1 31 32 REPORT TYPE.
REPORT SOURCE OOCKl;T NUMBER EVENT OATE REPORT OATE
@ill CONT I.__.____, w L!J 1015101-101215151 1018121617161 IOl9IOl917161 7
B 57 5B 59 60 61 BB 69 74 75 BO
EVENT DESCRIPTION
I 80 I
10'21 I This event. qccnrred qn 7
8 9 8-23-76 but was not classified as a reportable event until At about 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> with all rods withdrawn, an operator attempted to lolsl I 8-26-76.
7 8 9 lol41 I insert Group 4 rods using the 1;manual sequential mode."
80 It was observed that Group I 80 7
8 9 This overlap is not designed to occur until Group 4 has been in-lol5113 also moved.
7 8 9 lol61 I serted to 51" above the bottom of the core.
The system was (see Line I
- 18) (ER-76-28) 8l 7
8 9 SYSTEM
CAUSE
COOE COOE COMPONENT CODE
@E]IRIBI lLJ lrlNlslTIRIDI 7
B 9 10 11 12 17 CAUSE DESCRIPTION PRIME COMPONENT SUPPLIER w
43 COMPONENT MANUFACTURER IF111.2101 44 47 80 VIOLATION L!J 48 lol0I I Preliminary investigation at the time of occurrence did not disclose the source of 7
B 9 lolsl lthe problem.
The following morning the system was found to operate normally in
. 7 8 9 l1lol !modes and the previous evening's problem could not be duplicated.(see attached 8 9 FACILITY METHOD OF STATUS
% POWER OTHER *STATUS DISCOVERY EID w I 0 I 0 I l I 11..--__
N_A __
__.I
~
7 8
9 10 12 13 44 45 CONTENT FORM OF ACTIVITY RELEASED rn w 7
8 9
OF RELEASE AMOUNT OF ACTIVITY W
~' _______
N_A __ -'---~
10 11 44 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
~lololol W 7
8 9 11 12 13 PERS'ONNEL INJURIES NUMBER
DESCRIPTION
45 NA EE] I o I o I ol NA DISCOVERY DESCRIPTION NA 46 LOCATION OF RELEASE NA 80 a11 I 80 sheet}
I 80 80 80 80 7
8 9 11 12 80 PROBABLE CONSEQUENCES
~
I None.
Power level and rod motion was too small to cause undesirable effects.
7 8 9
. 80 LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
~~
NA 7
8 9 10 80 PUBLICITY EIZl None.
7 8 9 ADDITIONAL FACTORS E@ I operated satisfactorily in the "manual group" mode during this period of time.
7 8 9 ITlfil 7
8 9 80 I
80 80
LER 76-28 Palisades (Continued From Line 10)
The system has continued to operate properly until the present time and consequently we are unable to determine the cause of the problem.
We plan to exercise the asso-ciated relay from the computer terminal during the next scheduled outage in an attempt to duplicate this problem.
If this attempt fails and no hardware dis-crepancies are found, the computer program will be reviewed for any oversight which may have permitted the problem to occur.
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799 ROOSEVELT HD SL EN ELL y N I IL
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©8/27/76 1549 8/27/76 i97b UUGcJ8 THIS TLX CONF'IftMS TELEPHONE NOTIF'ICATYON OF K BAKER~ NRC INSPECTO!'it~
AT r~945 AUGUST 26.1>
1976 OF POSSIBLE PRO BY G B SLADEP ACTING PLANT SUPER HJTEMDENT o
. (
IMPROPER C~ SEQUENCER OPERATION AT APPROXIMATELY 15©@ AUGUST 23 0 1976 WITH ALL RODS WIT~DRAWN GROUP 4 SELECT LIGHT ENERGIZED WHEN GHOUP 3 WAS Sf:LECTEDo RODS.WERE NOT MOVED SEQUENTIALLY IN THIS CONDITION..
- DETAILS WILL RE PROVIDED IN SUBSEQUENT REPORTo J G LEWIS/F G.BUTLER PALISADES PLANT CONSUMERS POWER COMPANY
~:n \\*J
\\f.IU ASCY. 111 HEA AUG 3 0 1976
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| 05000255/LER-2076-001, Licensee Event Report ER-76-01 - Sirw Vent Plugged | Licensee Event Report ER-76-01 - Sirw Vent Plugged | | | 05000255/LER-2076-002, Licensee Event Report ER-76-02 - Rps/Sis - Ps Out of Calibration | Licensee Event Report ER-76-02 - Rps/Sis - Ps Out of Calibration | | | 05000255/LER-2076-003, Licensee Event Report ER-76-03 - CCW P52-C Inboard Bearing Failed While Preventative Maintenance Was Being Performed on CCW Pump P52-A | Licensee Event Report ER-76-03 - CCW P52-C Inboard Bearing Failed While Preventative Maintenance Was Being Performed on CCW Pump P52-A | | | 05000255/LER-2076-004, Licensee Event Report ER-76-04 - MSIV Closure Set Point Was Found Below Tech Spec Limit of Greater than 500 Psia on Two Instruments | Licensee Event Report ER-76-04 - MSIV Closure Set Point Was Found Below Tech Spec Limit of Greater than 500 Psia on Two Instruments | | | 05000255/LER-2076-006, Licensee Event Report ER-76-06 - Several CRDM Inner Bearing of Clutches Would Not Rotate When Turned by Hand or a Number of Others Did Not Rotate Freely | Licensee Event Report ER-76-06 - Several CRDM Inner Bearing of Clutches Would Not Rotate When Turned by Hand or a Number of Others Did Not Rotate Freely | | | 05000255/LER-2076-007, Licensee Event Report ER-76-0087: Reactor Protective System, Main Steam Flow Transmitter Was Found Out of Tolerance During Surveillance Testing, & Transmitter Could Not Be Recalibrated | Licensee Event Report ER-76-0087: Reactor Protective System, Main Steam Flow Transmitter Was Found Out of Tolerance During Surveillance Testing, & Transmitter Could Not Be Recalibrated | | | 05000255/LER-2076-008, Licensee Event Report ER-76-008, Gaseous Release, Which Was Caused by Operational Error, Not Released Above Permissible Levels | Licensee Event Report ER-76-008, Gaseous Release, Which Was Caused by Operational Error, Not Released Above Permissible Levels | | | 05000255/LER-2076-009, Licensee Event Report ER-76-009, Containment Spray, a Condition Leading to Operation in a Degraded Mode | Licensee Event Report ER-76-009, Containment Spray, a Condition Leading to Operation in a Degraded Mode | | | 05000255/LER-2076-010, Licensee Event Report ER-76-010, During Testing, the Charging Pump, P55-A, Failed to Perform Properly | Licensee Event Report ER-76-010, During Testing, the Charging Pump, P55-A, Failed to Perform Properly | | | 05000255/LER-2076-012, Licensee Event Report ER-76-0102, for Long-Term Cooling Qualification, Two Valves, CV-2113 & CV-2115, Associated with Charging System, May Not Meet Code Requirement | Licensee Event Report ER-76-0102, for Long-Term Cooling Qualification, Two Valves, CV-2113 & CV-2115, Associated with Charging System, May Not Meet Code Requirement | | | 05000255/LER-2076-013, Licensee Event Report ER-76-013, Discharge of Cooling Water Above 5oF Limit | Licensee Event Report ER-76-013, Discharge of Cooling Water Above 5oF Limit | | | 05000255/LER-2076-014, Licensee Event Report ER-76-14, Relating to Removing Diesel Generator from Service, Advising, Corrective Action Will Be Completed About 8/1/1976, Not by 7/1/1976 as Transmitted on 5/25/1976 | Licensee Event Report ER-76-14, Relating to Removing Diesel Generator from Service, Advising, Corrective Action Will Be Completed About 8/1/1976, Not by 7/1/1976 as Transmitted on 5/25/1976 | | | 05000255/LER-2076-017, License Event Report 1976-017-00 Re Failure of RPS Matrix Relays | License Event Report 1976-017-00 Re Failure of RPS Matrix Relays | | | 05000255/LER-2076-021, Licensee Event Report ER-76-21 - Containment Purge Supply Valve, a Condition Leading to Operation on a Degraded Mode | Licensee Event Report ER-76-21 - Containment Purge Supply Valve, a Condition Leading to Operation on a Degraded Mode | | | 05000255/LER-2076-023, Corrected Licensee Event Report ER-76-23: Changing Typographical Error of Event Report No. ER-76-03 to ER-76-23 - Dealing with CCW Pump P-52-C, Inboard Bearing Failure | Corrected Licensee Event Report ER-76-23: Changing Typographical Error of Event Report No. ER-76-03 to ER-76-23 - Dealing with CCW Pump P-52-C, Inboard Bearing Failure | | | 05000255/LER-2076-024, Licensee Event Report ER-76-24 - Exceeding Pdil Limits, Which Will Be Resolved Through Clarification of Present Plant Technical Specification | Licensee Event Report ER-76-24 - Exceeding Pdil Limits, Which Will Be Resolved Through Clarification of Present Plant Technical Specification | | | 05000255/LER-2076-025, Licensee Event Report ER-76-25 - Hydrogen Recombiner, a Condition Leading to Operation on a Degraded Mode | Licensee Event Report ER-76-25 - Hydrogen Recombiner, a Condition Leading to Operation on a Degraded Mode | | | 05000255/LER-2076-026, Licensee Event Report ER-76-26 - Plant Discharge Temperature Increased More Rapidly than Expected | Licensee Event Report ER-76-26 - Plant Discharge Temperature Increased More Rapidly than Expected | | | 05000255/LER-2076-027, Licensee Event Report ER-76-27 - Containment Purge Supply Valve | Licensee Event Report ER-76-27 - Containment Purge Supply Valve | | | 05000255/LER-2076-028, License Event Report 1976-028-00 Re Rod Sequencer Operation | License Event Report 1976-028-00 Re Rod Sequencer Operation | | | 05000255/LER-2076-029, License Event Reports 1976-029-00, 1976-030-00, & 1976-031-00 Re Control Rod Drives | License Event Reports 1976-029-00, 1976-030-00, & 1976-031-00 Re Control Rod Drives | | | 05000255/LER-2076-033-01, Low D-C Voltage | Low D-C Voltage | | | 05000255/LER-2076-034, License Event Reports 1976-034-00 & 1976-035-00 Re Discharge Cooling Water Above 5oF Limit | License Event Reports 1976-034-00 & 1976-035-00 Re Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2076-036, License Event Report 1976-036-00 Re Containment Air Locks | License Event Report 1976-036-00 Re Containment Air Locks | | | 05000255/LER-2076-037, License Event Report 1976-037-00 Re Out-of-Spec Point of Neutron Monitor Channel C | License Event Report 1976-037-00 Re Out-of-Spec Point of Neutron Monitor Channel C | | | 05000255/LER-2076-038, License Event Reports 1976-038-00, 1976-039-00, 1976-040-00, & 1976-042-00 Re Discharge Cooling Water Above 5oF Limit | License Event Reports 1976-038-00, 1976-039-00, 1976-040-00, & 1976-042-00 Re Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2076-041, License Event Report 1976-041-00 Re Chlorine Discharge Limit Exceeded | License Event Report 1976-041-00 Re Chlorine Discharge Limit Exceeded | | | 05000255/LER-2076-043, License Event Report 1976-043-00 Re Leak in Charging Pump Suction Line | License Event Report 1976-043-00 Re Leak in Charging Pump Suction Line | | | 05000255/LER-2076-044, License Event Report 1976-044-00 Re Drift of Reactor Protection System Steam Generator Low Level Trip Set Point | License Event Report 1976-044-00 Re Drift of Reactor Protection System Steam Generator Low Level Trip Set Point | | | 05000255/LER-2076-045, License Event Report E1976-045-00 Re Failure of DBA Sequencer to Operate | License Event Report E1976-045-00 Re Failure of DBA Sequencer to Operate | | | 05000255/LER-2076-046, Re Chemicals Passed Through Neutralizer Tank Into Plant Discharge Structure | Re Chemicals Passed Through Neutralizer Tank Into Plant Discharge Structure | |
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