:on 980122,discovered That One of Ice Condenser Flow Passages Contained Large Amount of Frost & Ice.Caused by Inadequate Maint & Surveillance Practices.Completed Detailed Mapping & Quantification of Flow Passage Blockage| ML17334B780 |
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| Site: |
Cook  |
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| Issue date: |
05/15/1998 |
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| From: |
Schoepf P INDIANA MICHIGAN POWER CO. |
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| Shared Package |
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| ML17334B779 |
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| References |
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| LER-98-004, LER-98-4, NUDOCS 9805220073 |
| Download: ML17334B780 (8) |
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Similar Documents at Cook |
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text
HRC FORH 366 (5-92)'.S.
kUCLEAR REGULATORY COMMISSIOH
. LICENSEE EVENT REPORT (LER)
PPROVED BY OHB Ho. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER
RESPONSE
To COMPLY MITH THI IHFORMATION COLLECTION REOUEST: 50.0 HRS.
FORIIAR COMMENTS REGARDlkG BURDEN ESTIMATE To TH INFORMATION AND RECORDS MANAGEMEHT BRANCH (HNB 7714),
U.S.
kUCLEAR REGULATORY COMMISSION/
MASHINGTON, DC 20555-0001, AND TO THE 'PAPERMOR REDUCTION PROJECT (3150.0104),
OFFICE 0
MANAGEMENT AHD BUDGET MASHINGTON DC 20503.
FACILITY NAHE (1)
Donald C. Cook Nuclear Plant - Unit 1 DOCKET NUMBER (2) 50-315 Page 1 of6 TITLE (4)
Inadequate Maintenance and Surveillance Practices Result in Restricted Ice Condenser Flow Passages EVENT DATE 5
LER NUMBER 6
T DATE 7
REPOR OTHER FACILITIES INVOLVED 8 MONTH OAY 01 22 YEAR YEAR 98 98 SEQUENTIAL NUMBER 004 REVISION NUMBER 02 MONTH 05 DAY YEAR 15 98 FACILITY NAME Cook Unit 2 FACILITY NAME DOCKET NUMBER 50-316 DOCKET HUHBER OPERATING MDDE (9)
POMER LEVEL (10)
TH S REPORT IS SUBMITTED PURSUAN'I 20.2201(b) 20.2203 a
1 20.2203(a)(2)<< )
20.2203 a
2 ii 20.2203(a)(2)<< ii) 20.2203(a)(2)<<v) 20.2203(a)(2)(v) 20.2203(a)(3)<<)
20.2203 a
3 ii 20.2203(a)(4) 50.36 c 1
50.36(c)(2) 50.73(a) (2)<<)
X 50.73<a)<2)<<I)
LICENSEE CONTACT FOR THIS LER 12 50 ~73(a)(2) << I I )
50.73 a
2 iv 50'3(a)(2)(v) 50.73 a
2 vii 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.?3(a)(2)(x)
To THE REOUIREHENTS OF 10 CFR Check one or mar 73.71(b)
- 73. 710 OTHER (Specify in Abstract batch and in Text, kRC Form 366A)
HAME Mr. Paul Schoepf, Safety Related Mechanical Engineering Superintendent TELEPHONE NUMBER (Include Area Code) 616/465-5901, x2408 COMPLETE ONE LINE FOR EACH COMPONEHT FAILURE DESCRIBED Ik THIS REPORT
CAUSE
SYSTEH COHPONEHT MANUFACTURER REPORTABLE To NPRDS
- )%jw",:.Fig
CAUSE
SYSTEH COMPONENT MANUFACTURER REPORTABLE To NPRDS SUPPLEHEHTAL REPORT EXPECTED 14 YES (lf yes, ccnptcta EXPECTED SUBHISSION DATE).
X Ho EXPECTED SUBHISS ION DATE (15)
MONTH DAY YEAR ABS'TRACT (Limit to 1400 spaces, I:a., approximately 15 single-spaced typciiritten tines)
<16)
On January 22, 1998, with Unit 2 in Mode 5, while personnel were touring the Unit 2 containment, it was noted that one of the ice condenser flowpassages contained a large amount of frost and ice. A subsequent inspection of the ice condensers for both units identified that there were restricted flow passages in each unit's ice condenser bays, primarily in radial rows adjacent to the containment wall. As the Technical Specifications define more than one restricted flowpassage as evidence of abnormal degradation, this was determined to constitute an unanalyzed condition. An ENS notification was made on January 28, 1998 at 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br /> under 10CFR50.72(b)(2)(ii), as an unanalyzed condition found while the reactor was shutdown.
The root cause of this condition ftas been attributed to inadequate ice condenser maintenance practices which resulted in the blockage forming, in combination with an ineffective surveillance, which did not provide early detection of the blocked flow passage condition to allow timely corrective actions. A decision has been made to completely thaw both units ice condensers in order to address a variety of issues identified during the current unit outages.
Flow passages willbe confirmed dear at the conclusion of planned work. Maintenance and surveillance practices are being reviewed to ensure they adequately support ice condenser operability. These reviews willbe completed and appropriate improvements in maintenance practices and surveillances willbe implemented prior declaring either unit's ice condenser operable.
Detailed mapping and quantification of the flow passage blockage has been completed.
This information was transmitted to Westinghouse for assessment of the impact on ice condenser and containment operability. It was concluded that the ice condensers in both units were considered operable relative to the 15 percent ice blockage criteria. Therefore, this condition was determined to be of minimal safety significance, and the health and safety of the public was never jeopardized.
~eosmoovs weosxs PDR ADQCK 050003XS 8
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PDR
HRC FORK 366A U.S ~
NUCLEAR REGULATORY CDMKISSIOH LICENSEE EVENT CONTINUATION PPROVED BY OMB NO. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER
RESPONSE
TO COMPLY liITH THIS INFORMATION COLLECTION REOUEST: 50.0 NRS.
FOR'WARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMEHT BRANCH (MNBB 7714), U.S.
NUCLEAR REGULATORY COMMISSION/
WASHINGTON, DC 20555 0001, AND TO THE PAPERWORK REDUCI'ION PROJECT (3150-0104),
OFFICE OF MANAGEHENT AND BUDGET WASHINGTON DC 20503.
FACILITY NAME 1
Cook Nuclear Plant - Unit 2 TEXT (if core sPace is required.
use additional NRC Fons 366A's) (17)
DOCKET NUMBER 2
50-315 LER NUMBER 6
YEAR SEOUEHTIAL REVISION 98
004
02 PAGE 3
2 OF 6 C
Unit 1 was in Mode 5, Cold Shutdown Unit 2 was in Mode 5, Cold Shutdown On January 22, 1998, with Unit 2 in Mode 5, while NRC and AEP personnel were touring the Unit 2 containment, it was noted that one of the ice condenser flowpassages contained a large amount of frost and ice. A subsequent inspection of the ice condensers for both units identified that there were restricted flowpassages in each unit's ice condenser bays, primarily in radial rows adjacent to the containment wall. As the Technical Specifications (T/S) define more than one restricted flow passage as evidence of abnormal degradation, this was determined to constitute an unanalyzed condition. An ENS notification was made on Janua(y 28, 1998 at 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br /> under 10CFR50.72(b)(2)(ii), as an unanalyzed'condition found while the reactor was shutdown.
'ach ice condenser consists of 24 bays containing 81 ice baskets per bay, covering an arc of 300 degrees in the containment structure.
Each ice basket is approximately 12 inches across and 48 feet long, filled with borated ice.
The flowpassages in between the ice baskets must be kept clear of obstruction to assure even steam flowthrough the ice beds during a post-accident period.
T/S surveillance 4.6.5.1.b.3 requires a once per 18 month verification, "by visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on the top deck floor grating, on the intermediate deck and on flow passages between ice baskets and past lattice frames is restricted to a nominal thickness of 3/8 inches.
Ifone flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visually inspected.
If these additional flow passages are found acceptable, the surveillance program may proceed considering the'single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser."
The T/S surveillance of ice condenser flow passages is implemented via procedure 12 EHP 4030 STP.250, "Inspection of Ice Condenser Flow Passages."
Flow passage surveillances were performed during the current unit outages at the beginning and conclusion of initialwoik in each ice condenser.
These inspections, performed by contract personnel, did not identify the existence any abnormal ice build up in the flow passages.
An NRC inspector subsequently identified a blocked flow passage in late January, 1998. As a result of the inspector finding, a 100%
flow passage inspection was subsequently performed ln each unit. A preliminary calculation was done to estimate the flow passage blockage on a bay-by-bay basis.
The average flow passage blockage was estimated to be 10.7%
in Unit 1 and 11.5% in Unit 2. Also, the 100% flowpassage inspection revealed that some of the flow passages included in the earlier inspections and documented as being clear were subsequently determined to be blocked. A formal calculation was later done to determine the blockage on a bay-by-bay basis, and this information was transmitted to Westinghouse for analysis.
HRC FORM 366A U.ST NUCLEAR REGULATORY COMMISSION LICENSEE EVENT CONTINUATION PPROVED BY OMB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER
RESPONSE
TO COMPLY HITN THIS INFORMATION COLLECTIO}i REQUEST: 50.0 HRS.
FORliARD COMHEHTS REGARDIHG BURDEN ESTIMATE TO TNE IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNBB 7714), U.S.
NUCLEAR REGULATORY COMMISSION, IIASNINGTON, DC 20555.0001, AND TO THE PAPERNORK REDUCTION PROJECT (3150 0104),
OFFICE OF MANAGEMEHT AND BUDGET liASHINGTON DC 20503.
FACILITY NAME 1
Cook Nuclear Plant - Unit 2 TEXT (if aore space is required.
use additional NRC Fons 366A's) (17)
DOCKET NUMBER 2
50-315 LER NUMBER 6
YEAR SEQUENTIAL 98
004 REVISION 02 PAGE 3
3OF6 The root cause of this condition has been attributed to inadequate ice condenser maintenance practices which resulted in the formation of flow passage blockage, in combination with an ineffective surveillance which did not provide early detection of the blocked flow passage condition to allow timely corrective actions.
Inadequate ice condenser maintenance refers to practices which both contribute to formation of frost and ice in flow
- passages, and which do not result in effective clearing of deposits following maintenance or when otherwise identified. The following maintenance related factors are considered to be contributors to the formation of frost and ice in ice condenser flow passages.
Ice condenser doors are frequently opened for personnel or equipment access during maintenance periods, and doors which do not seal tight in the closed position, allow heat and humidity to enter the ice condenser.
Lower ice condenser access doors are also left open during portions of outages, enclosed in tenting, to accommodate the passage of vacuum hoses used for ice bed maintenance.
The situation is worsened by the extra humidity in containment during refueling outages, particularly during summer months. This contributes to frost and ice formation on laNcework and in the flow passages.
Ice also accumulates between ice baskets and lattices during basket filIactivities, which contributes to frost and ice blockage in the flow passages.
Ice may be deposited on latticework during fillingof ice baskets.
Plastic bags are
~
normally placed in the flow passages between adjacent baskets as a means to contain the ice in the basket being filled. However, because the basket and the lattice structure are so close together, the bags do not prevent some ice from accumulating between the basket and the lattice. Normal practice is to clear this ice following ice basket maintenance.
The ice condenser design provides forwall defrosts to clear ice and frost buildup. Ice condenser maintenance strategies have not effectively utilized defrosts to clear blockage near the ice condenser walls. Sublimation and transport of ice occurs from one area of the ice condenser to another.
This generally occurs from the radial row 9, the row next to the crane wall,'oward radial row 1, the row adjacent to the outside wall of containment.
Temperature gradients within the ice bed are considered to be contributors to the ice sublimation and transport.
Temperature gradients occur when air handler units are not in service due to failure or planned maintenance.
Finally, maintenance of ice condenser air handler units, which help achieve uniform temperature distribution in the ice condenser, has not been optimized. The air handler units occasionally malfunction, indicating that preventive maintenance improvements are warranted.
Additionally, corrective repairs to these units were not always given a high priority within the work control process.
The flow passage blockage documented in this report is considered to be the result of a combination of these factors.
For example, the priority assigned to corrective maintenance on air handler units was reviewed.
Itwas noted that corrective maintenance on air handler units typically receive a relatively low priority for completion, given that failure of an air handler does not directly result in any Inoperability of equipment.
With regard to the addition of humidity to the ice condensers, at the time the noted condition was identified, both units had been in extended outages approaching six months in duration, during which significant work was performed in the ice condensers.
This work required frequent opening of ice condenser doors for personnel and equipment access, which contributes to humidity in the ice condenser.
Finally, numerous ice baskets were emptied and refilled during these outages, which had the potential to result in the accumulation of ice on latticework during basket filling.
NRC FORH 366A U.S.
NUCLEAR REGULATORY COMHISSIOH LICENSEE EVENT CONTINUATION PPROVED BY OMB NO. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER
RESPONSE
TO COMPLY lilTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORIIARD COMMENTS REGARDIHG BURDEH ESTIHATE TO THE INFORMATION AND RECORDS MANAGEMENT BRAHCH (MNBB 7714),
U.ST NUCLEAR REGULATORY COMMISSIOH,
'WASHIHGTON, DC 20555.0001, AND To THE PAPERWORK REDUCTION PROJECT (3150-0104),
OFFICE OF MANAGEMENT AND BUDGET IIASHINGTON DC 20503.
FACILITY NAME 1
Cook Nuclear Plant - Unit 2 TEXT (If core space is required.
use additional NRC Fons 366A's) (IT)
DOCKET NUMBER 2
50-315 YEAR 98 LER NUMBER 6
SEQUENTIAL REVISION 004
02 PAGE 3
4OF6 C
I A final maintenance consideration involves the use of defrosts to control ice buildup. The ice condenser design includes provisions for both floor and wall defrosts.
These design features were not effectively utilized during the current outages to control the buildup of frost and ice in areas adjacent to walls.
Surveillance activities have not been effective in consistently identifying blocked flowpassages.
Ineffective sulveillances contributed to this event in that they did not provide early detection of the blocked flow passage condition to allow timely corrective actions.
This is supported by differing results from recent surveillances performed in proximity to one another.
Ice condenser surveillance deficiencies, which contributed to this event, include lack of a T/S definition of what level of flow passage blockage results in an inoperable ice condenser. Other deficiencies included lack of guidance on required qualifications for personnel performing ice condenser flow passage sulveillances, lack of guidance on quality techniques to be used and lack of guidance on the use of lighting aids during inspections.
As previously noted the T/S surveillance of ice condenser flow passages is implemented via engineering procedure 12 EHP 4030 STP.250, "Inspection of Ice Condenser Flow Passages."
Flow passage surveillances were performed during the current unit outages at the conclusion of initialwork in each ice condenser.
These inspections, performed by contract personnel, did not identify the existence of any abnormal ice build up in the flow passages.
Subsequent inspection revealed that some of the flow passages included in the earlier inspections and documented as being clear were subsequently determined to be blocked. This points to ineffectiveness of the initial surveillances in detecting the flow passage blockage.
T/S surveillance 4.6.5.1.b.3 requires a once per 18 month verification, "by visual inspection ofat least two flow passages per ice condenser bay, that the accumulation of frost or ice on the top deck floor grating, on the intermediate deck and on flow passages between ice baskets and past lattice frames is restricted to a nominal thickness of 3/8 inches.
Ifone flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visualiy inspected.
If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser."
While the T/S define that more than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser, the T/S do not state what amount of flowpassage blockage renders the ice condenser inoperable.
In response to previous instances of flow passage blockage, a blockage limitof 15% of the total upward flowarea was determined based on the analysis performed for the Unit 1 Reduced Temperature and Pressure program.
- However, procedure 12 EHP 4030 STP.250 does not provide the detailed information necessary to determine the percentage of flow passage blockage, nor does it define the inspection acceptance criteria to ensure that the 15 percent ice condenser flow blockage limitis not exceeded.
Procedure 12 EHP 4030 STP.250 also excepts hoarfrost deposits from inspection of frost and ice buildup in the flow passages.
Hoarfrost is frost that can be easily wiped away by hand..
This exception is based on a 1988 T/S Interpretation, which concluded that hoarfrost extending beyond 3/8 inches in length is not considered as blockage in the flow passage.
However, T/S 4.6.5.1.b.3 states that "frost or ice" in the flow passages greater than a nominal thickness of 3/8 inches is the critical dimension for determining flow passage blockage.
There is no discussion in the 7
HRC FORH 366A U.S.
NUCLEAR REGULATORY COHHISSIOH LICENSEE EVENT CONTINUATION APPROVED BY OHB NO. 3150-0104 EXPIRES 5/31/95 ESTIHATED BURDEN PER
RESPONSE
TO COHPLY MITH THIS IHFORHATIOH COLLECTIOH REQUEST: 50.0 HRS.
FORMARD COHHENTS REGAROIHG BURDEN ESTIHATE TO THE IHFORHATION AND RECORDS HANAGEHEHT BRANCH (HNBB 7714),
U.ST NUCLEAR REGULATORY COHHISSIOHg MASHIHGTON, DC 20555.0001, AND TO THE PAPERMORK REDUCTION PROJECT (3150-0104),
OFFICE OF HAHAGEHENT AND BUDGET MASHINGTOH DC 20503.
FACILITY NAHE 1
Cook Nuclear Plant - Unit 2 TEXT (ifsore space is required.
use additional NC Fons 366A's) (17)
DOCKET NUHBER 2
50-315 LER NUHBER 6
YEAR SEQUENTIAL REVISION 98
004
02 PAGE 3
5OF6 T/S permitting hoarfrost. As a result of this interpretation, condition reports were not written on hoarfrost blocked flow
- passages, which contributed to limited awareness of the trending toward more significant flow passage blockages.
The flow passage surveillance procedure also does not give guidance on how flowpassages are selected for inspection.
Past practice has been for the system engineer to select flow passages for inspection based on judgement.
Procedural guidance was not available to accomplish random inspections in combination with inspection of areas most likelyto exhibit problems based on past experience.
Another weakness noted in the surveillance procedure was the lack of guidance on required qualiflcations for personnel performing the flow passage inspections, and also lack of guidance on the use of quality techniques such as dual concurrent verification. The most recent surveillances were performed by contract personnel, who may have only received general training on ice condenser maintenance activities, and the procedure allowed for a single individual to perform the surveillance.
A final weakness noted in procedure 12 EHP 4030 STP.250 was the lack of detailed guidance on the use of lighting aides during the inspection. The flow passage inspection procedure states as a prerequisite that "Portable lights to inspect the ice condenser passages willbe obtained as necessary." The procedure does not specify the light conditions that must be met to visually inspect the flow passages.
Following this event, both ice condenser maintenance and surveillance practices and historical information were reviewed to determine causes for the formation of the blockage, and for the failure to detect the blockage during ice condenser flow passage surveillances.
Ev This event is reportable under 10CFR50.72(b)(2)(ii), as an unanalyzed condition found while the reactor was shutdown and was reported via ENS notification on January 28, 1998 at 1706 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.49133e-4 months <br />.
As a result of the 100 percent inspection, a formal calculation was performed to determine the percent blockage of
'ach ofthe 48 bays.
This calculation indicated that the blockages for Unit 1 ranged from 6.7 percent to 18.8 percent per bay, and the blockages in Unit 2 ranged from 4.1 percent to 17.4 percent.
Ten bays were found with blockage greater than 15 percent.
This formal calculation replaced the preliminary calculation that had only estimated the blockage.
The results of the formal calculation were sent to Westinghouse for analysis of the impact on ice condenser and containment operability.
Based on this data, and by utilizing a lumping" method, which combines several bays, Westinghouse determined that the highest calculated blockage percentage was less than 12.5 percent per lumping for Unit 1 and less than 14.0 percent per lumping for Unit 2. Therefore', Westinghouse concluded that the ice condensers in both units were considered operable relative to the 15 percent flow passage blockage criteria.
Therefore, this condition was determined to be of minimal safety significance, and the health and safety of the public was never jeopardized.
HRC FORM 366A U.S.
NUCLEAR REGULATORY COMMISSION LICENSEE EVENT'ONTINUATION PROVED BY OMB HO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER
RESPONSE
TO COHPLY iiITH THIS INFORMATIOH COLLECTIOH REQUEST: 50.0 HRS.
FORiiARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MHBB 7714), U.S.
NUCLEAR REGULATORY COMMISSIONS WASHINGTON, DC 20555-0001, AHD TO THE PAPERWORK REDUCTION PROJECT (3150 0104),
OFFICE OF MANAGEMEHT AND BUDGET IIASHINGTOH DC 20503.
FACILITY NAME 1
Cook Nuclear Plant - Unit 2 DOCKET NUMBER 2
50-315 LER NUMBER 6
YEAR SEQUEHTIAL 98
004 REVISION 02 PAGE 3
6OF6 TEXT (if more space is required.
use additional HRC Form 366A's) (17)
Both units'ce Condensers willbe thawed during the current outages'to address a variety of issues.
Flow passages willbe confirmed clear of blockage at the conclusion of planned work.
Maintenance and surveillance practices willbe reviewed and revised as necessary to ensure they adequately support ice condenser operability. These reviews willbe completed and appropriate improvements in maintenance practices and surveillances willbe implemented prior declaring either unit's ice condenser operable.
Items, which willbe specifically covered in these reviews, include consideration of possible improved methods and controls for reducing ice condenser door openings. (I.e. use of air locks for personnel passage or addition of penetrations for hoses rather than doors).
Priorities assigned to maintenance of air handler units willbe revisited, to ensure this equipment receives the proper attention for corrective mainteT)ance.
Preventive maintenance activities for air handlers willalso be reviewed and revised as necessary to ensure appropriate activities are being pro-actively performed for these units.
Techniques for inspecting and clearing flow passages following basket fillingactivities willalso be reviewed and revised as necessary to ensure any residual ice is removed from latticework following ice basket maintenance.
Finally, ice condenser defrosts willbe revisited, to ensure there is guidance on when and how to control frost and ice accumulation before it becomes significant.
With regard to ice condenser surveillances, a wholesale review of all ice condenser surveillance procedures is being performed for both units. Items being considered in this review include the basis for procedure acceptance
- limits, guidance for performing surveillances, the use of margins to T/S limits, and required qualifications and quality techniques for personnel performing the surveillances.
This review willbe performed on all ice condenser surveillance procedures, including flow passage surveillance procedures Finally, the aforementioned T/S interpretation on what constitutes flow passage blockage willbe reviewed. The basis for the T/S willbe reviewed for possible revision to clarify what constitutes unacceptable flow passage blockage.
The ice condenser surveillance program reviews willbe completed, and improvements incorporated into surveillance procedures prior to declaring either unit's ice condenser operable.
ail C
Not applicable 315/83-099-00 316/85-013-00 315/87-013-00 315/88-002-00 Ev t
315/88-007-00 316/88-005-00 316/88-015-00
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| 05000315/LER-1998-001, :on 980104,containment Air Recirculation Sys Flow Testing Results Indicated Condition Outside Design Basis.Caused by Mispositioned Valve Actuator.Corrected Actuator to Valve Orientation |
- on 980104,containment Air Recirculation Sys Flow Testing Results Indicated Condition Outside Design Basis.Caused by Mispositioned Valve Actuator.Corrected Actuator to Valve Orientation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-002, :on 980108,discovered Several Broken Master Relay (MR) Covers Inside Ssps Logic Cabinet.Caused by Past Practice of Removing MR Covers to Perform Time Response Testing.Replaced All Unnacceptable Ssps MRs |
- on 980108,discovered Several Broken Master Relay (MR) Covers Inside Ssps Logic Cabinet.Caused by Past Practice of Removing MR Covers to Perform Time Response Testing.Replaced All Unnacceptable Ssps MRs
| 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)(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)(A) | | 05000316/LER-1998-002-01, :on 980224,determined That PORV Inoperability Resulted in Condition Outside Design Basis.Caused by Communication Failure.Procedures Revised |
- on 980224,determined That PORV Inoperability Resulted in Condition Outside Design Basis.Caused by Communication Failure.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)(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) | | 05000316/LER-1998-003, :on 980304,two Pressurizer Safety Valves Failed to Lift within Setpoint Tolerance.Caused by Setpoint Drift.Valves Were Retested & Adjustments Were Made to Lower Setpoints |
- on 980304,two Pressurizer Safety Valves Failed to Lift within Setpoint Tolerance.Caused by Setpoint Drift.Valves Were Retested & Adjustments Were Made to Lower Setpoints
| 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-003, :on 980107,missed Procedure Step Resulted in Esfa & RPS Actuation Occurring.Caused by Personnel Error. Work on Ssps Stopped & High Priority Job Order Initiated to Restore Ssps to Normal |
- on 980107,missed Procedure Step Resulted in Esfa & RPS Actuation Occurring.Caused by Personnel Error. Work on Ssps Stopped & High Priority Job Order Initiated to Restore Ssps to Normal
| 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) 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) | | 05000316/LER-1998-004-01, :on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made |
- on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000316/LER-1998-004, :on 980319,determined That Ice Condenser Bypass Was Potentially in Excess of Design Basis Limit.Caused by Lack of Understanding.Known Degraded Conditions Resulting in Divider Barrier Pass Being Corrected |
- on 980319,determined That Ice Condenser Bypass Was Potentially in Excess of Design Basis Limit.Caused by Lack of Understanding.Known Degraded Conditions Resulting in Divider Barrier Pass Being Corrected
| 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) | | 05000315/LER-1998-004, :on 980122,discovered That One of Ice Condenser Flow Passages Contained Large Amount of Frost & Ice.Caused by Inadequate Maint & Surveillance Practices.Completed Detailed Mapping & Quantification of Flow Passage Blockage |
- on 980122,discovered That One of Ice Condenser Flow Passages Contained Large Amount of Frost & Ice.Caused by Inadequate Maint & Surveillance Practices.Completed Detailed Mapping & Quantification of Flow Passage Blockage
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-004-02, Forwards LER 98-004-02,providing Results of Analyses Performed by W.Ler Is Being Reduced from 7 Pages to 6 Due to Transferring Details of Root Cause Section to Cause of Event, Section | Forwards LER 98-004-02,providing Results of Analyses Performed by W.Ler Is Being Reduced from 7 Pages to 6 Due to Transferring Details of Root Cause Section to Cause of Event, Section | | | 05000315/LER-1998-005, :on 980122,missing Screws from Ice Condenser Ice Basket Coupling Rings Resulted in Potentially Unanalyzed Condition.Caused by Failure in Shear Due to Overload During Basket Weighing Process.Melted Out Condensers |
- on 980122,missing Screws from Ice Condenser Ice Basket Coupling Rings Resulted in Potentially Unanalyzed Condition.Caused by Failure in Shear Due to Overload During Basket Weighing Process.Melted Out Condensers
| 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) | | 05000316/LER-1998-005-01, :on 980715,potential for HELB to Degrade Component Cooling Water Sys Was Noted.Investigation & Analysis of Signficance of Event Is Continuing.Method May Be Developed to Protect CCW Pump Area |
- on 980715,potential for HELB to Degrade Component Cooling Water Sys Was Noted.Investigation & Analysis of Signficance of Event Is Continuing.Method May Be Developed to Protect CCW Pump Area
| 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) 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) | | 05000315/LER-1998-006, :on 980225,ice Basket Weighing Option Resulted in Potential Unanalyzed Condition Due to Lack of Technical Basis for Option.Caused by Failure to Maintain Design Basis for Ice Condenser.Revised Plant Procedure |
- on 980225,ice Basket Weighing Option Resulted in Potential Unanalyzed Condition Due to Lack of Technical Basis for Option.Caused by Failure to Maintain Design Basis for Ice Condenser.Revised Plant Procedure
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(b)(2)(ii) | | 05000315/LER-1998-007, :on 980211,ice Condenser Weights Used to Determine TS Compliance Were Not Representative.Caused by Mgt Methods.Ice Condensers for Both Units Will Be Melted Out & Reloaded W/Fresh Ice |
- on 980211,ice Condenser Weights Used to Determine TS Compliance Were Not Representative.Caused by Mgt Methods.Ice Condensers for Both Units Will Be Melted Out & Reloaded W/Fresh Ice
| 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 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000316/LER-1998-007-01, :on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With |
- on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With
| 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) 10 CFR 50.73(a)(2) | | 05000315/LER-1998-008, :on 980112,inadequate Contractor Control During Maint & Surveillance Activities Resulted in Ice Basket Damage.Procedures Used to Guide Maint & Surveillance Activities Have Been Upgraded & Rewritten |
- on 980112,inadequate Contractor Control During Maint & Surveillance Activities Resulted in Ice Basket Damage.Procedures Used to Guide Maint & Surveillance Activities Have Been Upgraded & Rewritten
| 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) | | 05000316/LER-1998-008, :on 980112,damaged Ice Condenser Ice Basket Removed from Unit 1 Ice Condenser.Caused by Inadequate Control of Contractors & Inappropriate Maint.Damage Beyond Threshold Will Be Repaired & Replaced |
- on 980112,damaged Ice Condenser Ice Basket Removed from Unit 1 Ice Condenser.Caused by Inadequate Control of Contractors & Inappropriate Maint.Damage Beyond Threshold Will Be Repaired & Replaced
| 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)(B) 10 CFR 50.73(a)(2)(1) | | 05000315/LER-1998-009, :on 980217,HR SR Not Being Met Resulted in Condition Prohibited by Ts.Caused by Inadequate Surveillance Procedure.Procedures Revised |
- on 980217,HR SR Not Being Met Resulted in Condition Prohibited by Ts.Caused by Inadequate Surveillance Procedure.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(A) | | 05000315/LER-1998-010, :on 980303,ice Condenser Intermediate Deck Doors Structural Discrepancies Were Noted.Caused by Failure to Follow Procedures.Removed All Intermediate Deck Door Frames & Support Beams & Reassembling Parts |
- on 980303,ice Condenser Intermediate Deck Doors Structural Discrepancies Were Noted.Caused by Failure to Follow Procedures.Removed All Intermediate Deck Door Frames & Support Beams & Reassembling Parts
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) | | 05000315/LER-1998-011, :on 980305,steel Containment Liner Pitting Was Is Excess of Design.Caused by Lack of Procedural Controls. Seals Were Removed,Containment Liner Plate Was Prepared & Coated & New Seals Applied |
- on 980305,steel Containment Liner Pitting Was Is Excess of Design.Caused by Lack of Procedural Controls. Seals Were Removed,Containment Liner Plate Was Prepared & Coated & New Seals Applied
| 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) | | 05000315/LER-1998-012, :on 980305,discovered That 1/4 Inch Particulate Retention Requirement Had Not Been Maintained in Containment Recirculation Pump.Caused by Incompleted Design Change.Will Correct Condition Under New Design Change |
- on 980305,discovered That 1/4 Inch Particulate Retention Requirement Had Not Been Maintained in Containment Recirculation Pump.Caused by Incompleted Design Change.Will Correct Condition Under New Design Change
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-013, :on 980306,improper Splice Configurations for Power Operated Relief Valve Limit Switches Resulted in Unanalyzed Condition.Caused by Inadequate Guidance in Installation Documents.Evaluation Performed |
- on 980306,improper Splice Configurations for Power Operated Relief Valve Limit Switches Resulted in Unanalyzed Condition.Caused by Inadequate Guidance in Installation Documents.Evaluation Performed
| 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)(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) | | 05000315/LER-1998-014, :on 980310,determined That Plant Had Operated in Unanalyzed Condition.Caused by Inadequate Interface with W Re Assumptions Used in Safety Analysis.Will Revise Functional Restoration Procedure FRZ-1.With |
- on 980310,determined That Plant Had Operated in Unanalyzed Condition.Caused by Inadequate Interface with W Re Assumptions Used in Safety Analysis.Will Revise Functional Restoration Procedure FRZ-1.With
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | | 05000315/LER-1998-014-03, Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed | Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed | | | 05000315/LER-1998-015, :on 980312,ice Weight Requirements Potentially Were Not Met Due to Nonconservative Assumption in Software Program.Update to Interim LER Will Be Issued by 980513 |
- on 980312,ice Weight Requirements Potentially Were Not Met Due to Nonconservative Assumption in Software Program.Update to Interim LER Will Be Issued by 980513
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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(s)(2) | | 05000315/LER-1998-016, :on 980323,re non-safety Related Cables Routed to Safety Related Equipment.Lers 98-016-00 & 98-016-01 Retracted |
- on 980323,re non-safety Related Cables Routed to Safety Related Equipment.Lers 98-016-00 & 98-016-01 Retracted
| 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) | | 05000315/LER-1998-017, :on 980327,debris Was Found in Sample Ice from Ice Condenser Sys.Caused by Poor Work Practices.Ice Condenser Has Been Completely Thawed & Inspection,Repair & Refurbishment Activities Have Begun |
- on 980327,debris Was Found in Sample Ice from Ice Condenser Sys.Caused by Poor Work Practices.Ice Condenser Has Been Completely Thawed & Inspection,Repair & Refurbishment Activities Have Begun
| 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 50.73(a)(2)(viii) | | 05000315/LER-1998-018, :on 980505,use of RCP Seals as Alternate Boron Injection Flow Path Resulted in Unanalyzed Condition.Caused by Maintaining Temp Above Recommended Max Temp.Westinghouse Has Provided Technical Input on Issue |
- on 980505,use of RCP Seals as Alternate Boron Injection Flow Path Resulted in Unanalyzed Condition.Caused by Maintaining Temp Above Recommended Max Temp.Westinghouse Has Provided Technical Input on Issue
| 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) | | 05000315/LER-1998-019-02, Forwards LER 98-019-02,which Provides Plant Test Data Gathered to Determine Error Associated W/Electric H Recombiner Temp Measurement Circuits.Changes to LER Are Marked W/Sidebar | Forwards LER 98-019-02,which Provides Plant Test Data Gathered to Determine Error Associated W/Electric H Recombiner Temp Measurement Circuits.Changes to LER Are Marked W/Sidebar | | | 05000315/LER-1998-019, :on 980320,determined That Electric Hydrogen Recombiner TS Surveillance Requirement 4.6.4.2.b.1 Was Not Met.Caused by Design Deficiency Due to Inadequate Design Change Mgt.Revised Procedures |
- on 980320,determined That Electric Hydrogen Recombiner TS Surveillance Requirement 4.6.4.2.b.1 Was Not Met.Caused by Design Deficiency Due to Inadequate Design Change Mgt.Revised Procedures
| 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) | | 05000315/LER-1998-020, :on 980408,noted Failure to Include Sodium Hydroxide in W Border Computer Program Used to Determine Ph in Containment Sump.Cause Indeterminate.Updated LER Will Be Submitted by 981001 |
- on 980408,noted Failure to Include Sodium Hydroxide in W Border Computer Program Used to Determine Ph in Containment Sump.Cause Indeterminate.Updated LER Will Be Submitted by 981001
| 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) | | 05000315/LER-1998-021, :on 980311,determined That Oil Pans Not Installed on RCP Motors Resulted in App R Noncompliance. Caused by Failure to Fully Implement App R Requirements.Will Updgrade Oil Leak Collection Sys |
- on 980311,determined That Oil Pans Not Installed on RCP Motors Resulted in App R Noncompliance. Caused by Failure to Fully Implement App R Requirements.Will Updgrade Oil Leak Collection Sys
| 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)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-022, :on 980415,postulated Failure of SAT N Regulator Was Noted.Caused by Failure to Perform Adequate SE for Procedure rev.10CFR50.59 Program Has Been Upgraded to Meet Current Industry Standards.With |
- on 980415,postulated Failure of SAT N Regulator Was Noted.Caused by Failure to Perform Adequate SE for Procedure rev.10CFR50.59 Program Has Been Upgraded to Meet Current Industry Standards.With
| 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) | | 05000315/LER-1998-023, :on 980416,potential Failure Due to Cross Train Routing of non-safety Related Cables Was Noted.Ler 98-023-00 & 98-023-01,retracted |
- on 980416,potential Failure Due to Cross Train Routing of non-safety Related Cables Was Noted.Ler 98-023-00 & 98-023-01,retracted
| 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) | | 05000315/LER-1998-024, :on 980417,allegation Concerning Accuracy of Ice Basket Weights Occurred.Allegation Has Been Investigated & Results of Investigation Will Be Provided to NRC by 980522 |
- on 980417,allegation Concerning Accuracy of Ice Basket Weights Occurred.Allegation Has Been Investigated & Results of Investigation Will Be Provided to NRC by 980522
| 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-025, :on 980424,plant Personnel Determined That Surveillance Requirements of Tech Specs 4.6.5.1.b.3 Were Not Met.Caused by Lack of Attention to Detail.Procedures Revised |
- on 980424,plant Personnel Determined That Surveillance Requirements of Tech Specs 4.6.5.1.b.3 Were Not Met.Caused by Lack of Attention to Detail.Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(B) | | 05000315/LER-1998-026, :on 980430,TS SR 4.6.5.1.b.2 Was Not Met.Caused by Failure to Accurately Transfer SR Into Plant Procedures. Software Used to Support Ice Condenser Surveillance Program Will Either Be Revised or Replaced |
- on 980430,TS SR 4.6.5.1.b.2 Was Not Met.Caused by Failure to Accurately Transfer SR Into Plant Procedures. Software Used to Support Ice Condenser Surveillance Program Will Either Be Revised or Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(1) | | 05000315/LER-1998-027, :on 980505,discovered Debris of Unknown Origin in West Containment Spray Header.Cause Indeterminate. Evaluation of Condition in Progress & Updated LER Will Be Submitted |
- on 980505,discovered Debris of Unknown Origin in West Containment Spray Header.Cause Indeterminate. Evaluation of Condition in Progress & Updated LER Will Be Submitted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-028, :on 980513,determined That TS Surveillance Requirements Not Met Due to Lack of Understanding of Staggered Test Basis. Caused by Lack of Specific Training. Periodic Change of Nuclear Plant Maint Sys |
- on 980513,determined That TS Surveillance Requirements Not Met Due to Lack of Understanding of Staggered Test Basis. Caused by Lack of Specific Training. Periodic Change of Nuclear Plant Maint Sys
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000315/LER-1998-029, :on 980422,SFP Ventilation Sys Was Noted Inoperable.Caused by Design Deficiency.Safety Evaluation Successfully Performed & Appropriate Surveillance Testing Completed |
- on 980422,SFP Ventilation Sys Was Noted Inoperable.Caused by Design Deficiency.Safety Evaluation Successfully Performed & Appropriate Surveillance Testing Completed
| 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) | | 05000315/LER-1998-029-01, Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed | Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed | | | 05000315/LER-1998-030, Re Incorrect Installation of Containment Spray Heat Exchanger.Ler 98-030-00 Retracted. with | Re Incorrect Installation of Containment Spray Heat Exchanger.Ler 98-030-00 Retracted. with | 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) | | 05000315/LER-1998-031, :on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing |
- on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
| 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) | | 05000315/LER-1998-031-01, Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed | Forwards LER 98-031-01,re Potential Common Mode Failure of RHR Pumps Due to Use of Inaccurate Values.Commitment Made by Util,Listed | | | 05000315/LER-1998-032, Forwards LER 98-032-00,originally Due on 980723.Additional Seven Days to Submit LER Was Granted by B Burgess of Region III | Forwards LER 98-032-00,originally Due on 980723.Additional Seven Days to Submit LER Was Granted by B Burgess of Region III | 10 CFR 21.21(c)(3)(ii) | | 05000315/LER-1998-033, :on 980611,H Recombiner Wattmeter Circuit TS SR Was Not Met.Caused by Inadequate TS SR Work Practices. Lessons Learned Document Was Issued to All Maint Personnel Involved W/Writing Surveillance Procedures |
- on 980611,H Recombiner Wattmeter Circuit TS SR Was Not Met.Caused by Inadequate TS SR Work Practices. Lessons Learned Document Was Issued to All Maint Personnel Involved W/Writing Surveillance Procedures
| 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) | | 05000315/LER-1998-034, :on 980623,flow Rates to Containment Spray Headers Were Potentially Lower than Design Basis Values. Declared Containment Spray Sys,Inoperable.Update Will Be Submitted by 981015 |
- on 980623,flow Rates to Containment Spray Headers Were Potentially Lower than Design Basis Values. Declared Containment Spray Sys,Inoperable.Update Will Be Submitted by 981015
| 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) | | 05000315/LER-1998-035, :on 980702,identified That Potentially Impacted Ability of Shock Absorbing Bumpers to Perform Intended Functions.Caused by Poor Work Practices.Bumpers Will Be Replaced by Newer Design Shock Absorber |
- on 980702,identified That Potentially Impacted Ability of Shock Absorbing Bumpers to Perform Intended Functions.Caused by Poor Work Practices.Bumpers Will Be Replaced by Newer Design Shock Absorber
| 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) | | 05000315/LER-1998-036, :on 980723,discovered That Flow Indicator Had Not Been Calibr at TS Required Frequency.Caused by Inadequate Work Practices.Action Request Has Been Written to Calibr Component on Refueling Outage Basis |
- on 980723,discovered That Flow Indicator Had Not Been Calibr at TS Required Frequency.Caused by Inadequate Work Practices.Action Request Has Been Written to Calibr Component on Refueling Outage Basis
| 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) | | 05000315/LER-1998-037-01, Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal | Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal | | | 05000315/LER-1998-037, :on 980812,ice Condenser Bypass Leakage Exceeds Design Basis Limit of 5 Square Feet Occurred.Caused by Lack of Understanding of Design Basis of Containment as Sys. Procedure Will Be Developed to Guide Insp.With |
- on 980812,ice Condenser Bypass Leakage Exceeds Design Basis Limit of 5 Square Feet Occurred.Caused by Lack of Understanding of Design Basis of Containment as Sys. Procedure Will Be Developed to Guide Insp.With
| 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) |
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