LER-2077-051, License Event Report 1977-051-00 Re Bus Y-01 Load Modification |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2552077051R00 - NRC Website |
|
text
.~
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 November 1, 1977 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - ER-77 BUS Y-01 LOAD MODIFICATION Attached is a reportable occurrence for the Palisades Plant involving tne addition of a new load to Bus Y-01.
The event was not classified as report-able until October 24, 1977.
David P Hoffman Assistant Nuclear Licensing Administrator CC:
ASchwencer, USNRC Nov 3 1977
LICENSEE EVENT REPORT Palisades CONTROL BLOCK: I I I I I I 1..._......... __..__.,__...__.___,6 [PLEABE PRINT ALL IREGUliRED 11\\lFORMAYUONJ LICENSEE NAME
@12] IMI rlPIAIL 11 I 7
8 9 14
@I!]caN~ I* I *I 7 8 57 58 REPORT TYPE.
~
59
EVENT DESCRIPTION
LICENSE LICENSE NUMBER TYPE Io Io 1-1 o I ol o lo lo 1-1 o Io I 1411!1!1!11 15 25 26 30 REPORT SOURCE LlJ 60 OOCKET NUMBER lo l5 IOl-lol215 l51 EVENT OATE IOl9l21717171
~
68 69 74 EVENT TYPE Io I 3 I 31 32 REPORT DATE 1111101117171 75 80 lol2I I Following a loss of site power resUlting in loss of security door operation, the se-j 80 to Bus Y-01/EDG without all required admin conj 7
~ 9 lol31 I curity door power source was shifted 7
8 9 80 lol41 I trols.
7 8 9 The added load was less than 1 percent of EDG capacity; loss of redundancy I 80 lol5l I not threatened.
Event nonrepetitive.
Reportable per Technical Specification I
7 8 9 loisl I 6.9.2.b.3 and not classified as a reportable occurrence until Oct 24, 80 1977.
I 7
8 9 SYSTEM CODE
@0 I EIB I
CAUSE
CODE COMPONENT CODE W
lzlzlzlzlzlzJ 7
8 9 10 11 12 17 CAUSE DESCRIPTION PRIME COMPONENT SUPPLIER UJ 43 COMPONENT MANUFACTURER I z I 9 I 9 I 9 I 44 47 (LER 77-5l'J30 VIOLATION l!.J 48 Iola! I The load was added prior to receipt of a load st.udy, due to misinterpretation of I
7 8 9
~ I instructions to complete the modifications left over from 1976.
80 Upon discovery of I
-.7 89 12@1 I the lo~d addition, load estimates were made and deemed acceptable.
7 8 9 80 The load ( contd)j 80 EE]
7 8
rn 7
8 METHOD OF FACILITY STATUS
% POWER OTHER STATUS DISCOVERY l_gJ I 0 I 0 I 0 I l.._ __
_.;.N/_A_~I w 9
10 12 13 44 45 FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY lzJ W
l....._ __
--'N""""/-=A __
____.I 9
10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
~I olol ol W N/A 7
8 9 11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
DISCOVERY DESCRIPTION I Post Outage Review 46 LOCATION OF RELEASE N/A 80 80 80
~
10101 OI
~N_/_A _______________________
___J 7
8 9 11 12 80 PROBABLE CONSEQUENCES
~
N/A 7
8 9 80 LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
[fil I zl
~~N~/=A~~~~~~~~~~~~~~~~~~~~~~~~~~~__J 7
8 9 10 80 PUBLICITY lill)
N/A 7
8 9 ADDITIONAL FACTORS
~
I Cause Description Contd.
~9 ITJfil I to be acceptable.
7 89 80 study completed on October 19, 1977 showed the loading. I 80 I
80
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000255/LER-2077-001, License Event Report 1977-001-00 Control Rod Drive. Due to Seal Leakage Problems, CRDM No 4 Is Being Considered Inoperable | License Event Report 1977-001-00 Control Rod Drive. Due to Seal Leakage Problems, CRDM No 4 Is Being Considered Inoperable | | | 05000255/LER-2077-004, License Event Report 1977-004-00 Discharge Cooling Water Above 5oF Limit | License Event Report 1977-004-00 Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2077-006, License Event Reports 1977-006-00 & 1977-008-00 Control Rod Misaligned | License Event Reports 1977-006-00 & 1977-008-00 Control Rod Misaligned | | | 05000255/LER-2077-009, License Event Report 1977-009-00 Re Discharge Cooling Water Above 5oF Limit | License Event Report 1977-009-00 Re Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2077-010, License Event Report 1977-010-00 Re Four PCP Loss of Flow | License Event Report 1977-010-00 Re Four PCP Loss of Flow | | | 05000255/LER-2077-012, License Event Report 1977-012-00 Re Boric Acid Tank Leak | License Event Report 1977-012-00 Re Boric Acid Tank Leak | | | 05000255/LER-2077-014, License Event Report 1977-014-00 Re Discharge Cooling Water Above 5oF Limit | License Event Report 1977-014-00 Re Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2077-015, License Event Report LER 1977-015-00 & LER 1977-016-00 Re Discharge Cooling Water Above 5oF Limit | License Event Report LER 1977-015-00 & LER 1977-016-00 Re Discharge Cooling Water Above 5oF Limit | | | 05000255/LER-2077-017, And LER 1977-017-00 Technical Specifications Limits on Sodium | And LER 1977-017-00 Technical Specifications Limits on Sodium | | | 05000255/LER-2077-018, Leak in Diesel Generator Coolant Switch | Leak in Diesel Generator Coolant Switch | | | 05000255/LER-2077-019, Stuck Discharge Check Valve for Service Water Pump P7C | Stuck Discharge Check Valve for Service Water Pump P7C | | | 05000255/LER-2077-022, And LER 1977-022-00 Discharge of Cooling Water Above Limit | And LER 1977-022-00 Discharge of Cooling Water Above Limit | | | 05000255/LER-2077-023-43, Result of Pressure Loss from Waste Gas Decay Tank T-101A | Result of Pressure Loss from Waste Gas Decay Tank T-101A | | | 05000255/LER-2077-024-03, Inoperable Condition of the Primary Data Logger Typer During Power Operation | Inoperable Condition of the Primary Data Logger Typer During Power Operation | | | 05000255/LER-2077-025-01, Backup Heat Tracing Circuit Being Out of Service for Period of 40 Days | Backup Heat Tracing Circuit Being Out of Service for Period of 40 Days | | | 05000255/LER-2077-027-03, Main Steam Line Hydraulic Shock Suppressor Failure | Main Steam Line Hydraulic Shock Suppressor Failure | | | 05000255/LER-2077-028-03, Failure of MOV-3011 to Open | Failure of MOV-3011 to Open | | | 05000255/LER-2077-029-03, Safety Injection Tank Level Exceeding Technical Specifications Limits | Safety Injection Tank Level Exceeding Technical Specifications Limits | | | 05000255/LER-2077-031-03, Primary Coolant System Leakage | Primary Coolant System Leakage | | | 05000255/LER-2077-034, Corrected LER 1977-034-00 to Clarify Leakage Testing & LER 1977-041-00 to Identify Proper Cause Description of Low Fuel Inventory | Corrected LER 1977-034-00 to Clarify Leakage Testing & LER 1977-041-00 to Identify Proper Cause Description of Low Fuel Inventory | | | 05000255/LER-2077-038, License Event Report 1977-038-00 Re Abnormal Degradation of Containment Boundary | License Event Report 1977-038-00 Re Abnormal Degradation of Containment Boundary | | | 05000255/LER-2077-039, License Event Reports 1977-039-00 Re Violation of Containment Building Integrity & 1977-040-00 Re Violation of Safety Injection Tank Level | License Event Reports 1977-039-00 Re Violation of Containment Building Integrity & 1977-040-00 Re Violation of Safety Injection Tank Level | | | 05000255/LER-2077-040, Corrected Licensee Event Report 1977-040-00 Re Safety Injection Tank Level | Corrected Licensee Event Report 1977-040-00 Re Safety Injection Tank Level | | | 05000255/LER-2077-042, License Event Reports 1977-042-00 & 1977-043-00 Re SG Level Indication and PCS Flow Detection | License Event Reports 1977-042-00 & 1977-043-00 Re SG Level Indication and PCS Flow Detection | | | 05000255/LER-2077-044, License Event Report 1977-044-00 Re Turbine Load Limiter Switch | License Event Report 1977-044-00 Re Turbine Load Limiter Switch | | | 05000255/LER-2077-045, License Event Report 1977-045-00 Re Containment Building Isolation Valves | License Event Report 1977-045-00 Re Containment Building Isolation Valves | | | 05000255/LER-2077-046, To Replace Improper Terminology Seal Bladder with Term Seal Ring, LER 1977-046-00 & LER 1977-048-00 Re Service Water Pump Check Valve Failure | To Replace Improper Terminology Seal Bladder with Term Seal Ring, LER 1977-046-00 & LER 1977-048-00 Re Service Water Pump Check Valve Failure | | | 05000255/LER-2077-047, License Event Report 1977-047-00 Re Loss of Off-Site Power | License Event Report 1977-047-00 Re Loss of Off-Site Power | | | 05000255/LER-2077-050, License Event Report 1977-050-00 Re Excessive Leakage from Containment Purge Valve | License Event Report 1977-050-00 Re Excessive Leakage from Containment Purge Valve | | | 05000255/LER-2077-051, License Event Report 1977-051-00 Re Bus Y-01 Load Modification | License Event Report 1977-051-00 Re Bus Y-01 Load Modification | | | 05000255/LER-2077-053, License Event Report 1977-053-00 Re Iodine Removal System | License Event Report 1977-053-00 Re Iodine Removal System | | | 05000255/LER-2077-055, License Event Report 1977-055-00 Re Loss of Off-Site Power | License Event Report 1977-055-00 Re Loss of Off-Site Power | | | 05000255/LER-2077-056, License Event Report 1977-056-00 Re Gaseous Waste Discharge | License Event Report 1977-056-00 Re Gaseous Waste Discharge | | | 05000255/LER-2077-057, Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus | Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus | | | 05000255/LER-2077-062, License Event Report 1977-062-00 Re Iodine Removal System Naoh Tank (T-103) | License Event Report 1977-062-00 Re Iodine Removal System Naoh Tank (T-103) | | | 05000255/LER-2077-064, License Event Report 1977-064-00 Re HPSI Pump P-66B | License Event Report 1977-064-00 Re HPSI Pump P-66B | | | 05000255/LER-2077-065, License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation | License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation | |
|