ML17325A754
| ML17325A754 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/23/1988 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 8805310195 | |
| Download: ML17325A754 (7) | |
Text
ACCELERATED DIRGBUTION DEMONST1%TION SYSTEM REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
CESSION NBR:8805310195 DOC.DATE: 88/05/23 NOTARXZED: NO DOCKET )g ACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit-1, Indiana 05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 05000316 AUTH.NAME AUTHOR AFFILIATXON GREENMAN,E.G.
Region 3, Ofc of the Director RECXP.NAME RECIPXENT AFFILIATXON ALEXICH,M.P.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele
SUBJECT:
Forwards AEOD input to SALP review of plant for Oct 1986-Feb 1988.
f DISTRIBUTION CODE:
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1 RECIPIENT ID CODE/NAME STANG,Z DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DXR 11 NRR/DREP/RPB 10
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UNITED STATES
'UCLEAR REGULATORY COMMISSION REGION III 199 ROOSEVELT ROAD GLEN ELLYNiILLINOIS 60'I 37 Docket No. 50-315 Docket No. 50-316 MAY23 $88 Indiana Michigan Power Company ATTN:
Mr. Milton P. Alexich Vice President Nuclear Operations Division I Riverside Plaza
- Columbus, OH 43216 Gentlemen:
The Office for Analysis and Evaluation of Operational Data (AEOD) provides Region III with a report describing observations from their review of licensee event reports.
The Region uses this data in support of the SALP process.
The enclosure provides the AEOD report for Donald C. Cook, Units I and 2
covering the SALP period from October I, 1986 to February 29, 1988.
This report is for information only.
AEOD reports will be routinely provided in the future as part of the SALP process.
0 Ji c,.~ -',~~~~
Edwa d G. Greenman, Director Division of Reactor Projects
Enclosure:
As stated cc w/enclosure:
W. G. Smith, Jr., Plant Manager
'I DCD/DCB"'.(RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen,'ichigan Public Service Commission EIS Coordinator, USEPA Region 5 Office Michigan Department of Public Health 8805310195 880523 PDR ADOCK 05000315 9
ENCLOSURE AEOD Input to SALP Review for O.C.
Cook Units I and 2
Indiana 5 Michigan Electric Coapany submitted about 50 reports for the two Donald C.
Cook Nuclear Plants, not including updates, in the assessment period from October I, 1986 to February 29, 1988.
Our review included the following LERs:
Unit I 86-021 to 86-024 87-001 to 87-023 88-001 Unit 2 86-028 to 86-031 87-001 to 87-015 88-001 The LER review followed the general instructions and procedures of NUREG-1022 and the findings and conclusions of this LER review are applicab'le to both units, Some of our findings are presented below:
Si nificant 0 eratin Events There were three events at Donald C. Cook Unit I and 2 that were identified as significant events by the AEOD screening and review process in the assess-ment period.
The significant operating events were:
I - LER 50-315/86-021 "Lack of Specificity in Technical Specification Requirements Resulted in Operation with Unanalyzed Emergency Core Cooling System Configuration (Residual Heat Removal)."
The licensee discovered an unanalyzed ECCS configuration relating to RHR crossover lines.
The issue was determined to be a generic Westinghouse plant problem.
Westinghouse performed an ECCS reanalysis which showed acceptable results.
Subsequently an Information Notice was issued.
2 - LER 50-315/86-024 "Engineered Safety Features Ventilation Fans Inoperable Due to Damper Misalignment."
As a result of operator error and an incorrect damper position indication, the plant experienced an eighteen minute period in which room cooling was lost to the containment spray pumps, the RHR pumps, the safety injection pumps, the charging pumps, the RHR heat exchangers and the containment spray heat exchangers.
Subsequent to the event, the licensee took corrective actions to eliminate many damper position indicator discrepancies that existed on Units I and 2.
3 - LER 50-315/87-013 "Ice Buildup in Ice Condenser Passages Due to Sublimation."
The plant experienced a degradation, of the ice condenser containment.
The problem was discovered during inspection of the flow passages of the containment on July I and 2, 1987, during cold shutdown.
Visual inspection discovered greater than 3/8 inch of ice buildup in a total of one hundred twenty-four flow passages in seven of the twenty-four ice bays.
Two similar but less severe ice condenser containment degradations had also been found to occur at Unit 2.
The first such event was on March 5 and 6, 1987 (LER 50-316/87-002).
The second event was on September 2,
1987 (LER 50-316/87-010).
Potential Accident Precursor In addition to the significant operating events described
- above, one event occurred on April 8, 1987 which is viewed by hEOD as a precursor to an accident.
The event was reported fn LER 50-315/87-005,
'Technical Specification Reactor Coolant System Pressure/Temperature Limits Exceeded As a Result of Personnel Error."
The event was a low temperature overpressurfzation that occurred about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after a reactor trip.
There was no damage to the plant.
- However, a
similar event occurring at a later time fn "reactor life" could have the potential for a severe and possible unanalyzed challenge to the RCS.
Similarly, if the Aprfl 8, 1987 event were not terminated when it was, a aire severe, and possibly unanalyzed challenge might have resulted.
This event indicates the need for increased utflfty attention to the areas of procedures, training and operations during plant shutdown.
AEOD notes that analyses beino performed by Brookhaven National Laboratory are finding that the risks during plant shutdown are comparable to those of power operation.
Such work is being done for RES as part of Generic Issue 99.
PNs Issued Durin the Assessment Period Six Preliminary Notifications of Events or Unusual Occurrences were issued for the two units at Donald C.
Cook during the assessment period.
They were:
Unit 1 PNO - III 130 Janitorial Morkers barred from site.
PNO - III 81 Earthquake PNO - III 100 Injured Worker Unit 2 PNO - III 32 Shutdown to Repafr SG tube leak(s)
PNO - III 98 Shutdown extended to repair minor valve leakage PXO - III 113A Defective reactor coolant pump hatch bolts Only one of the events described fn the PXs (PNO-111-87-98) was required to be reported as an LER.
An LER was submitted.
The content of the information fn the LER was in substantial agreement with the PN.
LER ualft The LERs adequately described the ma)or aspects of each event, including
~
component or system failures that contributed to the event and the significant corrective actions taken or planned to prevent recurrence.
The reports were thorough, detailed, fairly well written and easy to understand.
The narrative
3 sections typically included specific details of the event such as valve identi-fication numbers, aedel numbers,-number of operable redundant
- systems, the date of completion of repairs, etc..to provide a good understanding of the event.
The root causes of the events were identified.-
Nany LERs presented the event information in an organized pattern with separate headings and specific information in each section that led to a clear under-standing of the event information.
previous similar occurr ences were proper ly referenced in the LERs as applicable.
The updated LERs were adequate.