text
ACCELERATED D'<TRIBUTION DEMONSATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9202060515 DOC. DATE: 92/01/30 NOTARIZED:
NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION SWANK,D.A.
Washington Public Power Supply System BAKER,J.W:
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET "F,
05000397
SUBJECT:
LER 92-001-00:on 920102,high pressure core spray declared-inoperable due-to battery inoperability.Caused by
'nstructional presentation deficiencies in TS requirements.
Notes were added to surveillance procedure.W/920131 ltr.
DISTRIBUTION CODE: IE22T
" COPIES RECEIVED:LTR 'J ENCL j SIZE:
TITLE: 50.73/50.9 'Licensee Event Report (LER), Incident Rpt, etc.
/
NOTES:
D RECIPIENT ID CODE/NAME PD5 LA ENG, P. L.
'I lITERNAL: ACNW AEOD/DOA AEOD/ROAB/DS P NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB I'TERNAL EG &G BRYCE g J ~ H NRC PDR NSIC POORE,W.,
COPIES LTTR ENCL 1
1 1
1 2
2 1
1 2
2 1
1 1
1
,2 2
1 '1 1
1 1
1 3
3
~ 1 1
1 1
RECIPIENT ID CODE/NAME PD5 PD ACRS AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/DSg;SgAB QQ1 REG,~ E~
RGN5
- --- ="01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
D D
R D
.S NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOiVI P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
D D
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 33 ENCL 33 I
4 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ 3000 George Washington Way
~ Richland, Washington 99352 Januarv 31, 1992 G02-92-030 Docket No. 50-397 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.92-001
Dear Sir:
Transmitted herewith is Licensee Event Report No.92-001 for the WNP-2 Plant.
This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to.preclude recurrence.
Very truly yours, J. W. Baker (M/D 927M)
WNP-2 Plant Manager
Enclosure:
Licensee Event Report No.92-001 Mr. John B. Martin, NRC - Region V Mr. C. Sorensen, NRC Resident Inspector (M/D'901A)
INPO Records Center - Atlanta, GA Ms. Dottie Sherman, 'ANI Mr. D. L. Williams, BPA (M/D 399)
NRC Resident Inspector - walk over copy r
9202060515 920130 PDR ADOCK 05000397 PDR
(~(g7gy zg
ICENSEE EVENT REPORT (L FACILITY NAME (1) ashin ton Nuclear Plant - Unit 2 TITLE (4)
High Pressure Core Spray Inoperable Due To Battery Inoperability DOCKET NUMB R
(
)
0 5
0 0
0 PAGE (3) 3 9
7 I
OF 4
EVENT DATE 5
LER NUMBER (6 REPORT DATE 7
OTHER FACILITIES INVOLVED 8
MONTH DAY YEAR YEAR
SEQUENTIAL
- -; NUHBER EVISION HONTM DAY YEAR FACILITY NAHES NUHBER DOCKET NUHBERS(5) 0 5 0 0
I 0
2 9
2, 0
0 I
0 0
0 I
3 0
9 2
050 OPERATING MODE (9)
THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREHENTS OF 10 CFR ir: (Check one or more of the following) (11)
I POWER LEVEL (io) 20.402(b) 20.405(a)(1)(i) 20.405(a)(1)(ii) 20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 20.405(C) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 77.71(b) 73.73(c)
THER (Specify in Abstract below and in Text,NAME LICENSEE CONTACT FOR THIS LER 12 D.A. Swank, Compliance Engineer TELEPHONE NUHBER REA CODE 5
0 9
7 7
4 4
5 1
COMPLETE ONE LINE FOR EACH COHPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEH COHPONENT MANUFACTURER EPORTABLE 0 NPRDS
CAUSE
SYSTEM COHPONENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
YES (if yes, co iete EXPECTED SUBHISSION DATE) X NO EXPECTED SUBHISSION MONTH DAY YEAR ATE (15)
BsTRAGT (16)
On January 1, 1992 Plant electrical maintenance technicians performed Technical Specification required battery checks on the Division 3 High Pressure Core Spray (HPCS) battery.
Several cells were found to have electrolyte levels below the Technical Specification defined Limitvalue.
The battery was still Operable since the levels were above the Allowable Value level.
Water was added to the cells prior to the required check of other cell parameters.
When the other parameters were checked on January 2, the specific gravity readings of three of the 58 cells were below the Allowable Value.
The HPCS battery, HPCS Diesel Generator, and HPCS system were declared inoperable and the NRC was verbally notified per the requirements of 10CFR50.72(b)(2)(iii)(D). The battery was placed on an equalize charge and by 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> on January 3, 1992 the battery parameters were back within the Limitarid Allowable Value ranges and the battery-, HPCS, and HPCS Diesel Generator were declared Operable.
he root cause of this event was instructional presentation deficiencies in that the Technical Specification requirements are not clearly worded and the procedure did not provide clear guidance on the Technical Specification requirements.
Further corrective actions include: 1) notes were added to the surveillance procedure relative to the Limit and Allowable Values; 2) this LER willbe reviewed during the next Operator requalification cycle; and 3) written guidance willbe provided to clarify the Technical Specification requirements.
he low specific gravity readings were a result of stratification and did not significantly affect battery performance.
Therefore, this event was not safety significant and did not pose a threat to the health and safety of Plant personnel or the public.
LICENSEE EVENT REPORT R)
TEXT CONTINUATION FACILITY NAME (I)
Washington Nuclear Plant - Unit 2 DOCKET NUMBER (2) 0 5
0 0
0 3
9 7
LER NUHBER (8)
Year Number Rev.
No.
92 001 '0 PAGE (3) 2 F
4 TITLE (4) High Pressure Core Spray Inoperable Due To Battery Inoperab>>ty di i Plant Mode - 1 (Power Operation)
Power Level -100%
Event Descri tion On January 1, 1992 Plant'electrical maintenance technicians performed procedure PPM 7.4.8.2.1.20, Weekly Battery Checks.
Plant Technical Specification 4.8.2.1.a requires that on a weekly basis the designated pilot cells of the Division 3 High,Pressure Core Spray (HPCS) battery (HPCS-B1-DG3) be checked for the Category A parameters (electrolyte level, specific gravity, and cell float voltage for each of the pilot cells), and that the total battery terminal voltage be verified.
These checks were made and the battery parameters met the required specifications.
As a conservative
- measure, although required only quart'erly by the Technical Specifications, the procedure also requires a check of the electrolyte level in the remaining cells, a Category B parameter.
This check identified several cells with electrolyte level at or below the Technical Specification defined Limitvalue, but in all cases above the Technical Specification defined Allowable Value of the top of the cell plates. At 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> on January 1, 1992 the Shift Manager conservatively declared the Division 3 battery inoperable.
Upon further review the Shift Manager correctly determined that a Note in Technical Specification Table 4.8.2.1-1 states:
For any Category B parameter(s) outside the limit(s) shown, the battery may be considered OPERABLE provided that the Category B parameters are within their allowable values and provided the Category B parameter(s) are restored to within limits within 7 days.
Since the observed levels were within their Allowable Values, the battery was declared Operable at 0718 hours0.00831 days <br />0.199 hours <br />0.00119 weeks <br />2.73199e-4 months <br />. This Note implies, although it is not clearly stated, that the Category B parameters, cell electrolyte level, voltage, and specific gravity for each of the connected cells, should be verified to be within their Allowable Value range for each of the cells when any of the cell parameters are outside of the Limitrange.
No time restriction for completion of this verification is provided in the Note.
The Shift Manager called for immediate corrective action for the low electrolyte level condition and at approximately 0818 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br /> Plant electrical maintenance technicians completed adding water to the low cells in the Division 3 battery to return them to within the Limitrange.
On January 2, 1992 Plant Maintenance Engineering personnel reviewed the activities of the day before and found that the requirement to verify each of the Category B parameters for each of the connected cells had not yet been performed.
Immediate performance of these verification checks revealed that three of the 58 cells of the Division 3 battery had specific gravity readings which were greater than.02 lower than the average ofall the connected cells.
These specific gravity readings were outside the Allowable Value and Limit ranges.
All three of these cells had water added to them the previous day.
The Division 3 battery was declared inoperable at 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> on January 2, 1992.
LICENSEE EVENT REPOR R)
TEXT CONTINUATION FACILITY NAME (1)
Washington Nuclear Plant - Unit 2 DOCKET NUMBER (2) 0 5
0 0
0 3
9 7
LER NUMBER (B)
Year Number Rev.
No.
92 001 00 PAGE (3) 3 F
4 TiTLE (4) High Pressure Core Spray Inoperable Due To Battery Inoperabihty I
Immediate C rrec ive Action Upon finding the low specific gravity readings, the Division 3 battery was placed on an equalize charge to promote mixing within each cell, Both HPCS and the HPCS Diesel Generator, in addition to the HPCS battery, were declared inoperable.
The HPCS system was left in a standby status and was available ifrequired., The appropriate Technical*
Specification action statements were complied with.
I Since HPCS is a single train safety system, this event constituted a'condition that alone could have prevented the fulfillmentof the safety function of a system needed to mitigate'the consequences of an accident, a four-hour verbal.
notification was made to the NRC at 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> pursuant to the requirements of 10CFR50.72(b)(2)(iii)(D).
On January 3, 1992 at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> the Division 3 battery Category B parameters were rechecked and were all'found to be within the Allowable Value and Limit ranges.
Battery HPCS-Bl-DG3 was declared operable and the action statements were exited.
Further Evaluation and orrective Action P
A.
Further Evaluation Since HPCS is a single train safety system', this event constituted a condition that alone could have prevented the fulfillmentof the safety function of a system needed to mitigate the consequences of an accident.
This LER is submitted per the requirements of 10CFR50.73(a)(2)(v)(D).
It appears from the information available that the observed low specific gravity condition was due to the addition of water to the cells only one day prior to the readings being taken.
The battery manufacturer states that after adding water, mixing within the cells may take several weeks ifthe battery is on a float charge.
However, as long as the cell level before the water addition is above the top of the plates, the addition of water does not significantly alter the performance of the cell.
- - PPM 7.4.8.2.1.20 has a limitation in the front of the procedure to address failure to meet the Category A limits, but did not specifically address the Category B Limits and Allowable Values, Additionally, there were no notes in the body of the procedure pertaining to the limitation or providing guidance on what to do in the event the Category A,or B parameters fall outside the Technical Specification Limits or Allowable Values.
The root cause of this event was instructional presentation deficiencies in that the Technical Specification requirements contained in Note 2 ofTable 4.8.2.1-1 are not clearly worded and the procedure did not provide sufficient guidance on the Technical Specification requirements.
LICENSEE EVENT REPORT
)
TEXT CONTINUATION FACILiTY NAME (1)
Mashington Nuclear Plant - Unit 2 DOCKET NUM8ER (2) 0 5
0 0
0 3
9 7
Year LER NUMBER (8)
Number Rev.
No.
PAGE (3) 92 001 '0 TITtE (4) High Pressure Core Spray Inoperable Due To Battery Inoperabi ity 4
F 4
B.
I. rther C rrective Action 1.
The weekly battery testing procedure was changed to include notes in the body of the procedure relative to the Category A and B parameters.
2.
This LER willbe reviewed during the next Licensed Operator Requalification training cycle.
3.
Written guidance willbe'provided to clarify the Technical Specification requirements.
~f%
1 The low specific gravity readings observed were. a result of adding water to the cells. At no time was the level in any cell below the top of the plates.
The manufacturer of the batteries states that operational performance is only marginally effected by low electrolyte level so long as the level is maintained above the top of the plates.
In addition, the battery performance is not significantly effected by the addition of water to a cell where electrolyte level is above the plates prior to the addition. The average specific gravity of a cell is independent of the degree of mixing and, as verified by specific gravity testing on January 3 after mixing had occurred, the average specific gravity in the cells was acceptable.
The observed low specific gravity condition was actually only temporary stratification due to the addition of water.
Although technically inoperable, the HPCS system was maintained in its normal standby status and was available for service ifrequired.
Therefore, this event involved no safety significance.
Similar Events
There have been no previous LERs involving low battery levels or specific gravity readings.
LER 90-017 documented the inoperability of the HPCS battery due to the cracked casing of a single cell.
EIIS Informa ion EII Reference
$yrLemm om onen Division 3 battery, HPCS battery, HPCS-B1-DG3 EI BTRY HPCS BG HPCS diesel Generator
(
EK DG
)l
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000397/LER-1992-001, :on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure |
- on 920102,high Pressure Core Spray Declared Inoperable Due to Battery Inoperability.Caused by Instructional Presentation Deficiencies in TS Requirements. Notes Were Added to Surveillance Procedure
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-002, :on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained |
- on 920113,determined That MSIV Leakage Control Sys Fan Testing Incorrectly Performed.On 920127, Determined That Setpoint for Pressure Switch Did Not Ensure Proper Sys Operation.Ts Waiver Obtained
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-003, :on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed |
- on 920123,circulating Fan CAC FN-1B Failed to Start During Performance of Surveillance Test.Caused by Tripped Overloads.Thermal Overloads Reset & Surveillance Test Performed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-004, :on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required |
- on 920227,noted Scram Discharge Vol Level Switches Not Tested Post Scram as Required.Caused by Testing Not Being Performed.Corrective Actions Were Not Required
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-005, :on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced |
- on 920219,thermal Overloads Prevented Motors from Performing Safety Functions.Caused by Misapplication of Design Inputs.Motors Replaced
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-006, :on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset |
- on 920220,reactor Bldg to Suppression Chamber Vacuum Breaker Setpoints Were Incorrectly Set.Caused by Analysis Deficiency.Setpoint Documentation Changed & Procedures Deviated & Setpoints Reset
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-007, :on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented |
- on 920225,both Divs of Primary Containment Atmosphere Control Hydrogen Recombiner Sys Inoperable & Plant Shutdown Initiated.Caused by Less than Adequate Design.Design Changes Implemented
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-008, :on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing |
- on 920301,standby Gas Treatment Sys Fan Flow Limiter Setpoint Error Identified.Caused by Analysis Deficiency.Investigation Into Instrument Setpoint Accuracy Ongoing
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-008-01, :on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations |
- on 920301,SGTS Fan Flow Limiter Setpoint Error Discovered.Caused by Analysis Deficiencies.Sgts Fan Flow Limiter Setpoint Changed & Rev 2 of Jco Approved W/New Offsite Dose Calculations
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) | | 05000397/LER-1992-009, :on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations |
- on 920302,determined That Containment Instrument Air Pressure Switch Setting Changes Required. Caused by Analysis Deficiency.Pressure Switches Were Reset in Accordance W/New Setpoint Calculations
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-010, :on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended |
- on 920303,standby Gas Treatment Differential Pressure Controller Setpoint Error Identified.Caused by Analysis Deficiency.Setpoint Methodology Program to Review Selected non-harsh Setpoints Extended
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-011, :on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed |
- on 920305,discovered That Method of CRD Hydraulic Isolation Did Not Meet TS Requirements.Caused by Less than Adequate Procedures Due to Omission of Relevant Info in Procedure.Exhaust Water Valve Closed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-012, :on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided |
- on 920318,determined That Removal of Access Plugs Over RHR Pump Rooms a & B Exposed Both Rooms to Potential Flooding from Common Source.Caused by Faulty Mgt Methods.Interim Guidance Provided
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-013, :on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared |
- on 920318,annunciator for RHR B/C VLV Open Permissive Found Lit & RHR Pressure Switch Found Isolated During Startup.Cause Not Determined.Pressure Switch Returned to Svc & Annunicator & Permissive Cleared
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) | | 05000397/LER-1992-014, :on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows |
- on 920326,920414 & 920512,engineers Identified TS Violations Associated W/Flow Measurements in Hpcs,Lpcs & RHR Sys,Respectively.Caused by Inadequate Design Analysis. Tests Performed to Verify Flows
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-015, :on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced |
- on 920413,unexplained Pressure Drop in ADS B Section of Containment Instrument Air Sys Header Occurred. Caused by Inadequate Written Procedures.Valve CIA-V-41B Inspected & PPM-8.9.130 Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-016, :on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified |
- on 920424,determined That RCIC Sys Not Adequately Transferred to Remote Shutdown Panel.Caused by Misapplication of Design Inputs.Power Supply for RCIC Control Sys (48-volt Dc) Will Be Modified
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-017, :on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required |
- on 920508,personnel Determined That Heat Removal Capability of Train a RHR Heat Exchanger Less than Design Allowable.Caused by Insufficient Monitoring of Plant Components.Corrective Actions Not Required
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | | 05000397/LER-1992-018, :on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided |
- on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting Provided
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-019, :on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented |
- on 920430,determined That Automatic Depressurization Sys Potentially Inoperable Due to Inadequate Installation Instructions of Solenoid Pilot Valve Power Cables.Design Change Implemented
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-020, :on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump |
- on 920508,discovered Low Elements for Low Pressure Core Spray Min Flow Control Not Properly Installed. Procedures Modified to Include Check of Instrument Startups Prior to Running Pump
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-021, :on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken |
- on 920513,discovered That Certain QC-2 Instruments Were Not Appropriately Isolated from QC-1.Caused by Less than Adequate Design.No Corrective Action Was Taken
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-022, :on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled |
- on 920514,plant Engineer Determined That Labyrinth Seals Installed in Replacement CAC Blowers Were Not Environmentally Qualified.Caused by Inadequate Work Practices & Procedures.Personnel Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-023, :on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted |
- on 930519,review of non-licensed Operator Tour Log Revealed Missed TS Surveillance & Fire Tour Data Due to Less than Adequate Work Practices.Investigation Into Event Expanded.No Violations Noted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-024, :on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled |
- on 920519,discovered Inadvertent Emergency Ventilation Actuation.Caused by Work Practices Being Less than Adequate.Technicians Were Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000397/LER-1992-025-01, :on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21 |
- on 920528,HPCS Pump Motor & Small Piece of Aluminum Upper Air Deflector Found Lodged in Motor Stator & Cracks Found in Deflector.Caused by Use of Improper Work Practices.Deflectors Replaced.Not Reportable Per Part 21
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) | | 05000397/LER-1992-025, :on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage |
- on 920522,during Insp of HPCS Pump Motor,Small Piece of Aluminum Upper Air Deflector Found Lodged Inside Motor Stator.Caused by Personnel Error.Evaluation of ECCS Will Be Performed to Prevent Future Damage
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-026, :on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function |
- on 920605,determined That Mo of RHR Train a May Have Prevented Full Closure of Drywell Spray Supply Valve.Caused by Inadequate Testing of Plant Equipment.Mo Repaired & Tested to Perform Design Function
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(8) | | 05000397/LER-1992-027, :on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled |
- on 920613,lack of Breaker Coordination Due to Instantaneous Trip Circuitry.Amptector Discriminator Circuit for Each of Six Feeder Breakers Disabled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-028, :on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised |
- on 920617,diesel Room Normal Air Handling Fans Precluded Performance of Required Design Function.Caused by Equipment Design Deficiency.Loop Test Procedure Will Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-029, :on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished |
- on 920624,RHR Shutdown Cooling Isolation Occurred & Shutdown Cooling Supply Line Inboard Isolation Valve Automatically Closed.Caused by Inadequate Personnel Work Practices.Shutdown Cooling Reestablished
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-030, :on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel |
- on 920630,containment Isolation Occurred, Resulting in Shutdown of nonsafety-related HVAC Equipment & Actuation of Containment Isolation Valves.Caused by Poor Work Place Layout.Event Reviewed W/Personnel
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-031, :on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour |
- on 920701,potential for Exceeding Continuous Rating of Divs I & II DG 1 & 2 Identified Due to Inadequate Circuit Electrical Separation.Caused by Design Deficiency. Items Placed on Hourly Fire Tour
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-032, :on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters |
- on 920702,unplanned Actuation of ESF Component Occurred Due to Decrease in Reactor Water Level Resulting from Voided Feedwater Piping.Water Level Restored within Normal Operating Parameters
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000397/LER-1992-033, :on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel |
- on 920706 & 920711,determined That SRV Failed to Reseat at Required Pressure Per Ts.Caused by Two Adjusting Rings within SRV Found Set at Wrong Position. Training Will Be Provided to Shop Personnel
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-034, :on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked |
- on 920713,determined That Nonwater Tight Penetration Seals in ECCS Pump Rooms Could Result in Common Mode Failure from Flooding.Inadequate Penetration Seals in ECCS Pump Rooms Except for Door Seals Reworked
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-034-01, Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | Forwards LER 92-034-01,describing Identification of Addl Unqualified Penetration Seals in ECCS Pump Room & Providing Status of Penetration Seal Rework | | | 05000397/LER-1992-034-02, Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | Forwards LER 92-034-02.Supplemental Rept Describes Completion of Penetration Seal Rework & Changes to Flood Watch Requirements | | | 05000397/LER-1992-035, Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | Responds to NRC 920831 Request for Addl Info Re LER 92-035 on Inadequate Testing of Scram Discharge Vol Vent & Drain Valves.Improvements to Plant Evaluation Requests Underway & Incident Review Board Established in June 1992 | | | 05000397/LER-1992-035-01, Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | Forwards LER 92-035-01.Suppls Provides Details & Clarifications Requested in NRC .Futher Review Indicates That Changes to post-mod Testing Plan Were Contributing Cause for Event | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000397/LER-1992-036, :on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised |
- on 920719,primary Containment Lighting Circuit Not Deenergized as Required by Tech Specs.Caused by Technical Inaccuracy in Procedure for Plant Startup.Plant Startup Procedures & Drywell Entry Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-037, :on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures |
- on 920815,reactor Manually Acrammed Due to Indications of Core Instability.Caused by Unanticipated Interaction of Operating Conditions & Components.Revised Operating Strategies & Related Procedures
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-037-02, Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Trai | Forwards LER 92-037-02.Rev Provides Updated Info Re C/As for Manual Reactor Scram Due to Core Instability.Commitment to Obtain Amend to TS to Eliminate Requirements for Calculating T Deleted.Confusion Eliminated Through Training | | | 05000397/LER-1992-038, :on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training |
- on 921014,technicians Failed to Perform Main Condenser Offgas Sample Analysis Per TS 3.3.7.12,due to Personnel Error & Inadequate Work Mgt Methods.C/A Included Counseling,Equipment Repair & Further Training
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-039, :on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated |
- on 920921,RWCS Isolated on High Differential Flow While ROs Were Attempting to Place filter-demineralizer RWCU-DM-1B Back Into Service.Caused by Inadequate Mgt Methods.Degraded Equipment Repaired & Procedures Updated
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-040, :on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure |
- on 920930,determined That Start & Load Time for Standby & HPCS DG Not Measured During Monthly Surveillance Testing.Caused by Deficiencies in Mgt Methods. Expedited Effort Initiated to Amend Procedure
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-041, :on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed |
- on 921027,offsite Power Source Determined Inoperable During Brief Periods of Prior Operaton Due to Low Voltage Condition on 230 Kv Grid.Caused by Design Deficiency & Inadequate Mgt Methods.Ts Procedure Changed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000397/LER-1992-042, Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | Forwards Public Version of LER 92-042,Rev 0.Root Cause Is Inadequate Policy Re Free Release of Potentially Contaminated Liquids.Conclusions of Ongoing MORT Analysis Will Be in Suppl to LER | | | 05000397/LER-1992-043, :on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised |
- on 921202,determined That Discrepancy Existed Between Plant Procedures & Monitoring Range of RPV Instrumentation in MCR & at Remote Shutdown Panel.Caused by Insufficient Communication.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1992-044, :on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design |
- on 921208,HPCS Sys Pump Suction Valve Switchover Occurred,Due to Spurious Actuation of Either One or Both CST Pipe Break Detectors.Engineering Will Evaluate Replacement of Detectors & Alternate Design
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|