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CATEGORY 1
.I REGULATORY INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9807080027 DOC.DATE:'98/07/01 NOTARIZED: NO DOCKET FACXL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AYAH.NAME AUTHOR AFFILIATION SCHOEPF,P.
Indiana Michigan Power Co'.
SAMPSON, J.R.
Indiana Michigan Power Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 98-017-01: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 tc refurbishment activities have begun.W/980701 ltr.
DISTRIBCTION CODE: IE22T COPIES RECEIVED:LTR 1
ENCL J SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD/SPD/RAB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.,
NRC PDR COPXES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME STANG,J AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB NRR/DSSA/SRXB RGN3 FILE 01 LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1
1 1
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N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 23
American Electric Pow~
Cook Nuclear Plant One Cook Place Bridgman, MI49106 6164655901 AMERICAN ELECTRIC POWER July 1, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:
'In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event
<<h fll ig i
ig 1
i<<d.'8-017-01 Sincereiy,
~ Qv~
J. R. Sampson Site Vice President lmbd Attachment C. J.
Paperiello (Acting), Region ill J. R.
Sampson P. A.
Barrett S. J.
Brewer R.
Whale D.
Hahn Records Center, INPO NRC Resident Inspector 9807080027 98070i PDR AGOG@ 05000$ i5 S
PDR
NRC Form 366
'I (4-95)
U.S. NUCLEAR REGULATORYCOMMISSION LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
API'ROVEDSY OMB NO. M504)I04 EXPNIES OU$0III ESTNATEO BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATIONCOLLECTION REOUEST: 50.0 HRS. REPORTED lESSONS LEARNED ARE eCORPPORATEO UITO THE UCENSSIG PROCESS ANO FED SACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTSIATE TO THE UIFDRMATIDNAND REcoRDs MANAGEMENTsRANcH IT4 FSS). U.s. NUclEAR REGULATORY COMMISSION. WASHNGTON.
OC
$05550001, AND 1'0 THE PAPERWORK REDUCTION PROJECT ($150010I). OFFICE OF MANAGEMENTAND BUDGET.WASHNGTOILOC $050$
FACILITYNAME(I)
TITLE(4)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(3) 50-315 PAGE (3) 1 of5 Debris Recovered from Ice Condenser Represents Unanalyzed Condition EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIESINVOLVED(8)
MONTH 03 DAY 27 YEAR YEAR 98 98 SEQUENTIAL NUMBER 017 REVISION NUMBER 01 MONTH DAY YEAR 07 01 98 A ILI NAM Cook - Unit 2 A ILI NAM NUMB 50-316 D
CKET NUMBER OPERATING MODE (9) 50.73(a)(2)(i) 20.2203(a)(2)(v) 20.2201 (b)
THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR (I: (Check one or more) (11) 50.73(a)(2)(viii)
POWER LEVEL(10) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(U) 20,2203(a) (2)(III) 20.2203(a)(2)(iv) 20.2203(a)(3)(i) 20.2203(a)(3)(ti) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)
LICENSEE CONTACT FOR THIS LER (12) 5o.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)(x)
OTHER 73.71 Yn Aberraot below or n NRC Form 366A NAME TELEPHONE NUMBER(Indude Area Code)
Mr. Paul Schoepf, Safety Related Mechanical Engineering Superintendent 616/465-5901, x2408 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
YES (IfYes, complete EXPECTED SUBMISSION DATE).
X NO EXPECTED SUBMISSION DATE (15)
N H OAY Abstract (Limitto 1400 spaces, I.e., approximately 15 single-spaced typewritten lines) (16)
On March 27, 1998, debris was found in a sample of ice from the Ice Condenser System. The Unit 1 Ice Condenser was then completely thawed and three 55-gallon drums of debris were collected. The debris could have blocked flow through Ice Condenser floor drains and Containment Recirculation Sump screens, which represents an unanalyzed condition. An ENS notification was made on March 27, 1998, in accordance with 10CFR50.72(b)(2)(i) for an unanalyzed condition, and this LER is submitted in accordance with 10CFR50.73(a)(2)(ii)(A) for an unanalyzed condition.
The root cause of debris in the Ice Condenser was determined to be poor work practices, with contributing causes of written communications and supervisory methods. To insure all debris is removed, both units'ce Condensers will be carefully inspected following the complete thaw of ice. The Ice Condenser worker training program willbe overhauled and video inspections of ice baskets willbe performed, Ice Condenser Foreign Material Exclusion and task standards will be revised, and oversight responsibility of Ice Condenser work willbe transferred from Engineering to the Maintenance Department to access a larger staff skilled in production supervision.
The quantity of debris is negligible compared to the mass of ice in the Ice Condenser, and is not a threat to Ice Condenser performance. However, taken in aggregate, the additional debris from the Ice Condenser would have exacerbated the fibrous material condition described in LER 50-315/97-024, further degrading the ability of the Containment Recirculation Sump to perform its function.
NRC FORM 366 (4-95)6 (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION, FACILITYNAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 50-315 YEAR 98 LER NUMBER (6)
SEQUENTIAl NUMBER 017 REVISION NUMBER 01 PAGE (3) 2of5 TEXT (Ifmore spaceis required, use edditionel copies ofNRC Form (366A) (17)
CONDITIONS PRIOR TO EVENT
Unit 1 was in Mode 5, Cold Shutdown Unit 2 was in Mode 5, Cold Shutdown
DESCRIPTION OF EVENT
The primary function of the safety-related Ice Condenser system is the absorption of thermal energy released abruptly in the event of a Loss of Coolant Accident (LOCA) or Main Steam Line break (MSLB) inside Containment, to limitthe initial peak Containment pressure. The system consists of a completely enclosed annular compartment located around approximately 300 degrees of the perimeter of the Containment. The main part of the Ice Condenser is a mass of sodium tetraborate ice stored inside the compartment. The sodium tetraborate solution produced by the melting ice absorbs and retains iodine released during the accident and serves as a heat transfer medium and neutron poison for reactivity control following the postulated design basis incident (LOCA). The total ice mass provides sufficient heat removal capability to condense the steam released during a LOCAor a MSLB event. The Ice Condenser plays no role in the normal operation of the plant.
Accomplishment of the function of the Ice Condenser system depends upon the quantity and distribution of the ice mass within the Ice Condenser. The ice mass is contained within an array of 1944 ice baskets. Eighty-one ice baskets, arranged in a 9 by 9 grid, are located in each of the 24 bays of the Ice Condenser. The ice baskets are 48 feet tall with an approximate diameter of 12 inches. The vertical portion of the basket is substantially open to accommodate heat transfer.
The borated water from the melted ice passes through the Ice Condenser floor drains and into the Containment Recirculation Sump.
The Containment Recirculation Sump is located in the basement of the lower Containment, and collects water from the Reactor Coolant System, the Containment Spray System, and the Ice Condenser for the Emergency Core Cooling System (ECCS) pumps during the recirculation phase following a LOCA. The Recirculation Sump screen prevents debris from flowing into the ECCS pump suctions during recirculation. The vertical screen and an outer trash rack are designed to prevent missiles and other debris from entering the ECCS pump suction piping.
Inspection of a filter in the system used to melt ice obtained from a sample of 110 Unit 1 and five Unit 2 ice baskets revealed the presence of debris. The nature and volu'me of debris found from both units was such that the potential existed to block flow through the Ice Condenser floor drains and Containment Recirculation Sump screens.
Flow blockage of the Containment sump screens would reduce the amount of borated water available for long term reactor core and Containment cooling, and represents an unanalyzed condition.
The decision was made to completely thaw both units'ce Condensers to address a variety of issues, including the existence of debris in the ice bed. The thaw of the Unit 1 Ice Condenser was completed in late May, 1998, and thaw of the Unit 2 Ice Condenser is scheduled to begin in July, 1998.
I The type of debris found in the Unit 1 Ice Condenser includes a variety of materials, such as:
tape (including complete rolls) coat plastic banding ice basket coupling screws and screw heads ice basket cruciforms rope gloves plastic wrap cloth nuts 8 bolts wire rags(4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITYNAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 50-315 YEAR LER NUMBER (6)
SEQUENTIAL NUMBER REVISION NUMBER PAGE (3) 3of5 98 017 01 TEXT (ifmore space is required, use additional copies ofNRC Form (366A) (17)
DESCRIPTION OF EVENT (cont'd) flashlights and batteries plastic tubes from tube lights wood paper small hand tools (such as wrenches) larger tools (such as pneumatic vibrators, weigh rigs, and metal bars used to maintain the ice bed).
While some minor amounts of debris are still being removed from the Unit 1 Ice Condenser, an estimate of the volume of material was three 55-gallon drums, based on visual surveys of removed material and walk downs of the Ice Condenser.
It was further estimated that five cubic feet of material removed from the Unit 1 Ice Condenser was considered transportable to the Containment Recirculation Sump (items such as paper, tape, cloth, rope, etc). However, it should be noted that most of the material considered transportable to the Containment Recirculation Sump remained in the ice baskets following the Unit 1 Ice Condenser thaw.
The Unit 2 Ice Condenser thaw has not started, but the types and quantities of debris are expected to be similar due to
. similar maintenance practices for the two Ice Condensers.
CAUSE OF EVENT
The cause of the debris in the Ice Condenser was poor work practices. Foreign material entered the ice bed as a result of poor work practices during plant construction, initial ice load, or during subsequent surveillance and maintenance activities, which did not preclude entry of material into the ice bed.
A contributing cause was poor written communications. Strict standards and procedures did not exist to control foreign material during initial ice load or during subsequent maintenance activities on the ice bed.
Another contributing cause was poor supervisory methods resulting in ineffective contractor control. Contract personnel have historically performed most work inside the Ice Condenser under the supervision of personnel in the Engineering department. Training for contract ice crew personnel stressed the importance of Ice Condenser cleanliness, and there is evidence that workers understood this, however supervisory oversight was not effective in converting this knowledge into adequate worker performance.
ANALYSISOF EVENT On March 27, 1998, an ENS notification (EN 33975) was made in accordance with 10CFR50.72(b)(2)(i), for a condition found while the reactor was shutdown, which ifit had been found while the reactor was operating, could have resulted in the plant being in an unanalyzed condition. This LER is therefore submitted in accordance with 10CFR50.73(a)(2)(ii)(A), for an unanalyzed condition.
I The safety significance of debris in,the ice bed was considered in a 1984 Westinghouse report, which outlined the primary threats caused by debris. The significance can be summarized as, "any accumulation of debris is unacceptable ifit prevents the ice condenser system from operating at its minimum required capacity. This can happen ifdebris reduces the ice inventory below the minimum required, ifit prevents the proper flowof steam through the ice bed, or ifit unacceptably reduces the heat transfer from steam to the ice,...debris must not have an unacceptable impact on the operation of the emergency core cooling system and/or the Containment spray system."(4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.s. NUCLEAR REGULATORY COMMISSION'ACILITY NAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 50-315 YEAR 98 LER NUMBER (6)
SEQUENTIAL NUMBER 017 REVISION NUMBER 01 PAGE (3) 4of5 TEXT (ifmote space is te quite d, use additional copies ofNRC Form (366A) (1 7)
ANALYSISOF EVENT (cont'd)
Following the melt of the Unit 1 ice, itwas confirmed that the quantity of debris in the ice was noteworthy, comprising an estimated volume of three 55-gallon drums, with an estimated 5 cubic feet of the debris being potentially transportable from the ice baskets to the Containment Recirculation Sump.
Although this quantity of material is noteworthy given plant foreign material standards, this quantity of material is negligible compared to the quantity of ice resident in the ice beds. Given the small volume and weight of the debris compared to the volume and weight of the ice, the existence of this material is not considered a significant threat to Ice Condenser thermal performance.
The quantity of material is significant, however, from the perspective of potential threats to Containment Recirculation Sump blockage. Post-melt surveys of the Unit 1 Ice Condenser indicated that most debris was resident in the ice bed, and fell to the bottom of the basket during melting. For debris in the ice bed to threaten the Recirculation Sump:
- 1. The blowdown forces due to an accident would have to force the debris to travel up through the ice baskets, through the upper deck grating, and over to and down the refueling cavity drains; or,
- 2. The debris would have to travel out of the sides or bottoms ofthe ice baskets (through the 1" mesh), through the floor drain grating (1.75 inch openings), and through 12 inch flapper valve drains to the lower Containment.
Although both paths are somewhat tortuous, and there are no models to study debris transport for this type of material, if the noted quantities of debris are present, some would likely transport to the Recirculation Sump, reducing the flow area through the Recirculation Sump screens.
A previous Licensee Event Report (LER) (LER 50-315/97-024-04), addressed degradation of the Containment Recirculation Sump due to fibrous material found in Containment, which could potentially have caused excessive blockage of the sump screen. The issue of Containment Recirculation Sump screen blockage discussed in LER 97-024-04 is relevant to this LER because, taken in aggregate, the additional debris from the Ice Condenser would have exacerbated the condition described in LER 97-024, further degrading the ability of the Recirculation Sump to perform its function.
I
CORRECTIVE ACTION
The Unit 1 Ice Condenser has been completely thawed, and inspection, repair, and refurbishment activities have begun.
The Unit 2 Ice Condenser thaw is scheduled and willalso be followed by a number of inspection, repair and refurbishment activities. The thaw of each Ice Condenser includes removal of debris from the ice baskets and flow passages.
A detailed inspection will be performed of each Ice Condenser bay for cleanliness prior to refilling ice baskets in that bay. Production
. of ice and reload of ice into each Ice Condenser willbe strictly controlled to ensure that foreign material is not introduced into the ice beds during refill.
I To improve work practices, the training program for personnel performing work in the Ice Condenser is being overhauled.
Training willprovide focused information to raise the sensitivity ofworkers to foreign material, and to inform workers of new strict controls for foreign material in the Ice Condensers.
Avideo inspection willbe performed of baskets emptied for maintenance, prior to basket refillwith ice, which willafford an opportunity to identify any foreign material remaining in baskets after emptying. Additionally, a final inspection of emptied baskets willbe performed by QC personnel just prior to refill, which willprovide a final check of ice basket cleanliness.(4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITYNAME(1)
Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 50-315 YEAR 98 LER NUMBER (6)
SEQUENTIAL NUMBER 017 REVISION NUMBER 01 PAGE (3) 5of5 TEXT (Ifmore space is required, use additional copies ofNRC Form (366A) (17)
CORRECTIVE ACTION (cont'd)
To improve written communications related to the Ice Condensers, standards for control of foreign material within the Ice Condensers are being revised to invoke strict controls to preclude the entry of foreign material into the ice bed.
To address poor supervisory methods, responsibility for oversight of Ice Condenser, production workers is being realigned from the Engineering department to the Maintenance department. The Maintenance department has more production supervisors with the skills necessary to provide thorough supervisory oversight to workers compared to the Engineering department. Therefore, this realignment of responsibilities is expected to result in improved worker performance in foreign material control.
FAILEDCOMPONENT IDENTIFICATION Not Applicable
PREVIOUS SIMILAREVENTS
LE R 50-315/97-024-04 t'
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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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