IR 05000327/2005009
| ML052520427 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/09/2005 |
| From: | Cahill S Reactor Projects Region 2 Branch 6 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-05-009 | |
| Download: ML052520427 (26) | |
Text
September 9, 2005
SUBJECT:
SEQUOYAH NUCLEAR POWER PLANT - NRC PROBLEM IDENTIFICATION AND RESOLUTION (PI&R) INSPECTION REPORT 05000327/2005009 AND 05000328/2005009
Dear Mr. Singer:
On August 12, 2005, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Power Plant, Units 1 and 2. The enclosed inspection report documents the inspection findings, which were discussed on August 12, 2005, with Mr. R.
Douet and other members of your staff.
The inspection was an examination of activities conducted under your license as they relate to the identification and resolution of problems, and compliance with the Commissions rules and regulations and with the conditions of your operating license. Within these areas the inspection involved examination of selected procedures and representative records, observations of activities, and interviews with personnel.
On the basis of the sample selected for review, overall the team concluded that problems were being properly identified, documented, evaluated, and corrected. However the team identified several isolated examples where corrective actions did not appear appropriate, were not accurately documented, or were not completely carried out. The team observed that the quality of Problem Evaluation Report documentation has improved since the last NRC biennial PI&R inspection. The team did observe that there continues to be some lingering technical problems with the electronic document management eCAP program, more than a year after it was placed in service.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Stephen J. Cahill, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket No.:
50-327, 50-328 License No.:
Enclosure:
Inspection Report 05000327/2005009 and 05000328/2005009 w/Attachment: Supplemental Information
REGION II==
Docket Nos:
50-327, 50-328 License Nos:
05000327/2005009 and 05000328/2005009 Licensee:
Tennessee Valley Authority (TVA)
Facility:
Sequoyah Nuclear Plant Location:
Sequoyah Access Road Soddy-Daisy, TN 37379 Dates:
July 25, 2005 - August 12, 2005 Inspectors:
C. Julian, Team Leader M. Speck, Resident Inspector K. VanDoorn, Senior Reactor Inspector B. Holbrook, Senior Reactor Inspector J. Wiebe, Senior Reactor Inspector, RI Approved by:
S. Cahill, Chief Reactor Projects Branch 6 Division of Reactor Projects
Enclosure
SUMMARY OF FINDINGS
IR 05000327/2005009, IR 05000328/2005009; 07/25/2005 - 08/12/2005; Sequoyah Nuclear
Power Plant, Units 1 & 2; Problem Identification and Resolution.
The inspection was conducted by three Region II reactor inspectors, a resident inspector, and one Region I reactor inspector. No findings were identified during this inspection.
Identification and Resolution of Problems The team determined that the licensee was identifying plant deficiencies at an appropriately low level and effectively entering them into their corrective action program. The team also determined that the licensee was prioritizing and evaluating issues properly. The team identified several isolated examples where corrective actions did not appear appropriate, were not accurately documented, or were not completely carried out. Overall, the team found the effectiveness of corrective actions to be acceptable. The team observed that the quality of Problem Evaluation Report (PER) documentation has improved since the last NRC biennial PI&R inspection, but further improvements could be made. There continue to be lingering technical problems with the Electronic Corrective Action Program (eCAP) electronic document management program more than a year after it was placed in service. The team concluded, however, that the licensee was generally providing an effective corrective action program.
On the basis of interviews conducted during this inspection, the inspectors determined that workers at the site felt free to put safety concerns into the corrective action program. The inspectors concluded that the employee Concerns Resolution program was functioning acceptably but the inspectors observed that there was a work backlog.
REPORT DETAILS
OTHER ACTIVITIES (OA)
4OA2 Identification and Resolution of Problems
a.
Effectiveness of Problem Identification
- (1) Inspection Scope The team reviewed items selected across the span of plant activities to determine if problems were being properly identified, characterized, and entered into the corrective action program for evaluation and resolution. Specifically, the team reviewed approximately 425 problem evaluation reports (PERs) from 11,080 that had been issued during the inspection review period of September 1, 2003, to June 30, 2005. The team examined PERs and work orders (WOs) associated with the Reactor Protection System, Emergency Core Cooling System, Residual Heat Removal System, Ice Condenser System, Emergency Gas Treatment System, Radiation Monitoring System, 480V and 6.9kV Shutdown Power System, and the Main Control Room, 6.9 kV Shutdown Board Room, and Electric Board Room Air Conditioning Systems. The team reviewed PERs associated with radiological protection and emergency preparedness events, problems, and deficiencies. The team reviewed operating experience resolution documents, and employee Concerns Resolution activities. The team also reviewed licensee corrective action trend reports, PER effectiveness reviews, as well as Nuclear Assurance department audits and surveillances from the review period. The team evaluated these items to determine the licensees threshold for identifying problems.
The team conducted system walkdowns to verify that observed problems were being properly identified. All members of the team also attended the licensees various Plan of the Day and Management Review Committee meetings to observe how site management implemented the initial phase of the corrective action program.
- (2) Issues The team determined that the licensee was effective at identifying problems at an appropriately low threshold and entering them into the corrective action program. Only in the System Status Report for Emergency Gas Treatment System, were two instances identified where repetitive equipment problems did not result in the initiation of a PER.
However, these problems were already being addressed.
The inspectors observed that there are lingering technical problems with the new eCAP computerized corrective action system which have not been corrected despite repeated attempts for over a year. The system is cumbersome and not everyone in the plant can initiate a PER due to the lack of computer access, passwords, and training on operating the system. The licensee also stated that they are considering implementing a process for initiating an anonymous PER. Although a paper PER initiation form can be printed, there are no paper forms readily available and no locations or drop boxes to deposit a completed form.
b.
Prioritization and Evaluation of Issues
- (1) Inspection Scope The team reviewed Procedure SPP-3.1, Corrective Action Program, Revision 8, Business Practice document BP 250, Corrective Action Program Handbook, Revision 8, and various other supporting documents to determine the various licensee requirements for prioritizing and evaluating issues. The team then reviewed selected PERs to ensure that PER level classifications, operability determinations, reportability determinations, degraded and non-conforming condition determinations, cause evaluations, and selection of proper corrective actions were consistent with the significance of the problem described. The team reviewed a sample of PERs as described in paragraph a(1) above. The team also reviewed a sample of PERs associated with NRC findings, non-cited violations of regulatory requirements, and Licensee Event Reports issued during the selected review period. Specific items reviewed are listed in the attachment.
- (2) Issues The team determined that PER level classifications were consistent with established procedures and that licensee audits and self-assessments generally confirmed that conclusion. The team further determined that operability, reportability, degraded or non-conforming condition determinations and cause evaluations were also consistent with SPP-3.1.
At one Management Review Committee (MRC), meeting inspectors observed that PER 86552 contained an unclear problem description of corroded sump pump isolation valves in the Essential Raw Cooling Water (ERCW) intake structure. The MRC downgraded the PER from level C to D and returned it for revision due to a mis-stated operability concern. When the PER subsequently passed through MRC again, the inspectors observed that the problem description was clearer but still incorrectly listed the valves as part of the ERCW system when they should be part of the floor drain system.
Inspectors concluded that various problems with electrical circuit breaker performance still need attention. The inspectors observed a root cause critique meeting for level B PER 80797 on continuing performance problems with various kinds of electrical circuit breakers. This PER was initiated by the Nuclear Safety Review Board pointing out the need to take a broad look at circuit breaker problems. The inspectors observed that the Sequoyah Root Cause Analysis Grading Checklist was not directly applicable to the Common Cause analysis technique used on this PER. The licensee recognized this and was considering implementing a checklist for this technique.
The inspectors observed that there had been many time extensions granted on PER actions in the past. The licensee had recently recognized this and revised procedures to require an escalating level of approval for successive extensions.
PER 78863 identified the need for multiple changes to Abnormal Operating Procedures (AOPs) for loss of offsite power discovered during an Emergency Preparedness training exercise of March 17, 2005. The actions to complete the procedure changes had been extended to September 16, 2005. The inspectors questioned if changes to important procedures, such as AOPs, should take so long to complete. Operations management indicated that the procedure change would be rescheduled for early completion.
c.
Effectiveness of Corrective Actions
- (1) Inspection Scope The team reviewed the same selected sample of PERs to verify that the specified corrective actions were effective in fixing the problems described. The team also reviewed documented results of MRC effectiveness reviews for completed PERs and observed an MRC effectiveness review meeting and a Plant Health committee meeting.
Specific items reviewed are listed in the attachment.
- (2) Issues Based on a review of numerous corrective action plans and their implementation, the team found, for the most part, that the licensees corrective actions were effective.
Effectiveness reviews and audits were generally of good depth and correctly identified issues similar to those raised during previous NRC inspections. However, the team did identify several corrective action deficiencies.
The Electronic Corrective Action Program (eCAP) system has problems with filing attachments to PERs. This causes the system not to be able to retrieve attachments and thus lose prompt access to documentation of corrective actions. The problem has been documented since 8/12/2004 (PER 66958) and was originally scheduled for correction 3/31/2005. Several attempts have been made to fix the problem but were not completely successful. This deficiency can cause the staff to lose confidence in the system and not provide attachments to PERs. NRC expressed similar concerns with the TVA eCAP problems in the last Watts Bar PI&R inspection report, 50-390/2005006, dated March 17, 2005.
The inspectors observed several examples of unclear, incomplete, or inaccurate documentation in PERs. There were similar comments in the last NRC Sequoyah PI&R inspection report 50-327,328/2003009, issued 10/24/03. However the inspectors noted that there had been improvements in documentation quality since the last inspection and improvement could be seen between 2003 and 2005 vintage PERs:
a. PER 71060 was written for a failure to immediately borate when a boron concentration reduction occurred following entry into Mode 6. This is related to Licensee Event Report (LER) 1-2004-002. The documentation of the corrective action taken to prevent recurrence was so general that one could not tell what procedure changes were made.
b. PER 20212 dealt with an unsuccessful attempt to start an ERCW pump for post-maintenance testing (PMT) following circuit breaker and control switch replacement.
The PER documentation did not describe the troubleshooting, repairs or resolution of the problem. The inspectors learned that actual work included visual inspection and extensive troubleshooting, work instruction revisions, a second PMT that failed, and additional technical support and troubleshooting. Finally, a replacement breaker was installed and tested successfully.
c. PER 80535, identified a problem with a Unit 1 reactor trip breaker that, when given a close signal, attempted to close then immediately opened. The Root Cause Analysis identified that two different breakers had exhibited similar failures in the same breaker cubicle during three different outages (2000, 2004, and 2005). These causes had not been definitely corrected, the PER was still open, and additional troubleshooting activities were scheduled during the 2006 spring outage. The breaker is meeting its design safety function to open and is being tested bimonthly. The inspectors noted that the review and analysis did not contain any assessment or discussion on the important operational implications of the breakers ability to close when needed. Under certain plant conditions, the reactor trip breakers must be closed before the operators can re-set the safety injection block signal and feedwater isolation signals. Engineering personnel informed the inspectors that these actions were discussed and assessed during the PER review but that the discussions were not documented.
NRC inspectors observed several examples of corrective actions that do not appear appropriate or had not been completely executed:
a. PER 24617 dealt with a turbine building sump discharge effluent radiation monitor RM-90-212 being found during surveillance to have its trip point set too high by a factor of 100. PER action 24617-003 directed Chemistry to include this occurrence in the Annual Effluent Report to the NRC due to the radiation monitor being inoperable for greater than 30 days as required by Technical Specification 6.8.4.f.1 and Offsite Dose Calculation Manual (ODCM) 1.1.1. However the Action Taken description states, Evaluation of setpoint error and corresponding releases indicated that no ODCM violations occurred. Monitor was determined NOT to be inoperable for greater than 30 days based on evaluation. Monitor was inoperable for approximately 2 days during functional evaluation.
The ODCM requires reporting an inoperability of greater than 30 days or a failure to take grab samples during the inoperablility (ODCM deviation). The Action Taken states that an evaluation found that the monitor was only inop for two days but did not include an explanation of the basis for reaching that conclusion. The licensee could not locate any other documentation that indicated why the issue was not reportable. The licensee initiated PER 87449 promptly to investigate this matter and to take corrective action.
b. B Level PER 77234 concerns a Unit 2 reactor trip caused by maintenance workers inadvertently tripping two circuit breakers by dropping a panel cover. Action Description 77234-023 directs issue a Site-Wide Briefing to reinforce managements expectations for incorporating tribal knowledge into procedures using this event as an example of where incorporating tribal knowledge could have prevented a plant event. The Action Taken just re-states the Action Description and the Action Attachment File Name states Bulletin-PentaGen-Industrial Safety Performance 051905. The inspectors reviewed the attached Bulletin and found that it dealt with accident prevention and did not address management expectations for incorporating tribal knowledge into procedures.
Therefore the directed action was not accomplished. The licensee initiated PER 87502 to correct this issue.
c. PER 31322, was initiated to address an operating experience issue from Browns Ferry that identified a problem with General Electric HFA relay coil spools that were subject to aging with portions breaking off and potentially keeping the relay from performing its safety function. The closed PER did not document how the work was completed or its current status. In response to inspectors questions about the current work status, the licensee identified that Action Item 8 had been closed even though nine compartments on shutdown board 1B-B had not been inspected. Also, Action Item 10, to initiate WOs to replace any HFA relay whose coil spool was not made of Tefzel or initiate preventive maintenance items to periodically inspect non-Tefzel coil spools, was closed with work not completed. The licensee initiated PER 87474 to correct these problems.
d. PER 66228, identified a problem with a Unit 2 6.9kV breaker indicating light for RHR pump 2B. The indicating light being extinguished meant that contacts on the control switch were open and the RHR pump breaker would not close on demand. The PER indicated that the lack of light indication for the breaker did not draw operators attention to the fact that there was a problem. The inspectors noted that a previous PER, 27270, dated October 2003, was to review operating experience from Browns Ferry that stressed the importance of understanding breaker light indications, breaker switch positions, and the interrelationship with respect to breaker operability. One action for PER 27270 was to revise breaker inspection procedures to verify switch position, but the PER took no action on communicating the importance of breaker light indications. The operating experience information was not communicated to plant staff which could have prevented the event described in PER 66228.
e. PER 76030, dated February 2005, identified that the high-power trip setpoints for both units were changed in midsummer 2004 and some alarm response procedures were not updated. PER 62131, dated May 2004, identified the same apparent problem.
One action for PER 62131 was to evaluate for possible procedure/simulator impacts and revise accordingly. The PER closure documentation contained no attachment that could be used to verify that the action was completed correctly. The PER was closed in August 2004, with apparently some actions not completed.
f. PER 21094, identified a problem with missing records associated with licensed operator reactivation prior to assuming duties. A PER action was to review licensee procedures and make revisions necessary to correct the problem. The action was closed stating that the records were left in an empty office and lost but that procedures in place were adequate and no revisions were needed.
The problem occurred due to not following the procedures for the control of the documents but no further action was taken to prevent recurrence.
The inspectors did not identify any more than minor equipment performance issues from the above described deficiencies.
d.
Assessment of Safety-Conscious Work Environment
- (1) Inspection Scope The team reviewed numerous audits, assessments, PERs, WOs, and other corrective action documents and held discussions with numerous personnel at various levels in the organization to assess if a work environment existed that was conducive to the identification of nuclear safety issues. Inspectors also examined the licensees employee Concerns Resolution Program records and discussed the program with the implementer to determine if issues affecting nuclear safety were being appropriately addressed.
- (2) Issues The team determined that workers at the site felt free to raise safety concerns.
Personnel stated that they do not hesitate to raise nuclear safety issues to their management without fear of retaliation by their management. The wide spectrum of PER documented issues supported this conclusion. The team had no indication during this inspection of individuals being inhibited from identifying problems using the corrective action process.
Inspectors concluded that the Concerns Resolution Program was functioning acceptably, but that there was a backlog of work to be done in the program. There were no technical safety issues identified that were lingering without attention in the program.
The inspectors reviewed the last two Nuclear Assurance (NA) assessments of the CAP program performance. The management organization is appropriately responding to NA by initiating PERs and taking corrective actions.
4OA6 Meetings
Exit Meeting Summary
On August 12, 2005, the inspectors presented the inspection results to Mr. R. Douet and other members of his staff, who acknowledged the findings. The inspectors asked the licensee whether any of the material examined during the inspection should be considered proprietary. No proprietary information was identified.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee personnel
- T. Cosby, Maintenance Support Manager
- R. Douet, Site Vice President
- M. Gillman, Operations Manager
- J. Hamilton, Site Support Manager
- Z. Kitts, Licensing Engineer
- D. Kulisek, Plant Manager
- B. Marks, Manager, Emergency Services
- J. McGuire, Program Manager, Nuclear Assurance
- R. Newby, Concerns Resolution Manager
- P. Pace, Licensing and Industry Affairs Manager
- M. Palmer, Outage and Scheduling Manager
- K. Parker, Maintenance and Modifications Manager
- R. Richie, Chemical/Environmental Manager
- R. Rogers, Engineering Manager
- P. Sawyer, Radiation Protection Manager
- J. Smith, Site Licensing Supervisor
J. Thomas Design Engineering Manager
- K. Whittenburg, Communications Consultant
NRC personnel
- S. Cahill, Branch Chief, Region II
- S. Freeman, Senior Resident Inspector, Sequoyah
LIST OF DOCUMENTS REVIEWED
PERs Initiated as a Result of this Inspection
86775 Tin Whiskers, clarify attachment to PER 81118
87474 - HFA relays
87449 - Effluent report
87502 - Unit 2 trip
87672 - EGTS recurrence issues
85151 - OPS re-activation of licensing documentation
87933 - Inadequate documentation for PER 70987
Selected Problem Evaluation Reports (PERs)
86945 Grid disturbance resulting in electrical power swings on both Units
15702 Problem concerning logging EDGE unavailability time
25083 Unexpected results during molded case breaker testing
27050 Visual inspection of an HFA relay problem
27673 Root causes of PER 02-0125591 and 02-010111 were graded as 78%
31869 Unit 2 tripped
33629 PER incorrectly closed
2131 Annunciator response procedures not revised
63941 Procedure deficiency for jumper removal
65735 Molded case circuit breaker aging problem
228 Organization and management decisions - Siemens breakers
67963 PER effectiveness review
70383 CAP timeliness and quality
70384 PER quality not meeting goals
70385 Extent of condition and similar events
2939 Review of PER closure during the U1C13 outage
76030 Setpoint change to high power trips
79197 PER closure problems
298 PER closure problems
86522 ERCW sump valves are rusted
80518 Unit 1 reactor trip
80733 Maintenance and mods adverse trend on CAP performance
80797 NSRB issued PER to review breaker programs
85145 PER classification problems
85620 Organizational trust, response to Self Assessment SQN-SIT-05-006
85622 Questioning attitude, response to Self Assessment SQN-SIT-05-006
01192 Actions taken have been ineffective to address CAP weaknesses
27168 Local leak rate test failures
27976 Raw Cooling Water Booster Pump failures
31540 Poor scheduling lead to challenges to defense in depth
68805 Tolerance for degraded equipment conditions
81669 Divider Barrier Seal cut
81686 Local leak rate test failures
83084 Outage clearance problems
PERs Reviewed associated with NRC Identified Items
20373 1B centrifugal charging pump tagged out of service when ERCW 1B header was
tagged, NCV 2003/006-05
20585 Work week manager failed to update PSA color, NCV 2003/006-05
21094 Problem with licensed operator reactivation paperwork, NCV 2003/006-03
2355 PORV block valves on both units were closed with EWR and no risk assessment, NCV
2003/006-04
24833 Draindown of Unit 2 RCS to the midloop condition, NCV 2003/006-06
26422 Unit 1 generator tripped while performing main turbine overspeed test, NCV 2003/006-
63941 Jumper left in circuit following maintenance, LIV 2004-03
64477 Failure of Unit 2 LCP protection set 4 rack 13, Eagle 21 malfunction, NCV 2004/004-001
218 Unexpected loss of VCT level on Unit 1, NCV 2004/004-003
2-013504 Wrong oil added to 2A-A ERCW strainer, LIV 2003-06
2-013637 Wrong oil placed in 2A-A ERCW strainer, LIV 2003-06
03-011298 Wrong oil added to 2A-S TDAFW pump, LIV 2003-06
03-009567 Wrong oil in DG 1A2 Engine, LIV 2003-06
61626 BB Electric Board Room chiller trip due to unauthorized work, NCV 2004/003-001
60182 NRC identified improper storage of ISFSI components on pad, NCV 2004/009-001
66902 Missed opportunity to identify cracks on aux bldg crane, NCV 2004/009-002
20732 & 20588 Inservice Inspection procedure did not adequately address gaps and
clearances for supports, NCV 2003/006-02
224 & 27268, RWST level instruments failed high due to freezing, NCV 2003/006-08 and
LER 2-2003-002
PERs Reviewed Associated With LERs
234 U2 Reactor trip when breakers inadvertently tripped, LER 2-2005-001
80518 U1 Reactor trip on Auto Stop Oil failure, LER 1-2005-001
71060 U1 boron low in Mode 6, LER 1-2004-002
33325 & 33278 Reactor Trip inadvertent main transformer sudden pressure relay operation,
LER 1-2004-001
Audits, Self-Assessment
Nuclear Assurance Assessment Report NA-CH-03-001, Corrective Action Program
Nuclear Assurance Assessment NA-CH-04-003, TVAN Corrective Action Program
Nuclear Assurance Quarterly Oversight Report-August 21 through December31, 2004, and
Annual Assessment of Quality Assurance Program Implementation Effectiveness
Nuclear Assurance Quarterly Oversight Report - January 1 through April 19, 2005
Nuclear Assurance Oversight Report for the Period of January 1, 2005 through March 31, 2005,
NA-SQ-05-03
Nuclear Assurance TVAN-Wide-Audit Report NO. SA0304
Self-Assessment, SQN-SIT-03-006, Corrective Action Program
Self-Assessment, SQN-SIT-05-007, Corrective Action Program - Focused on NRC Module
Self-Assessment Final Report, SQN-OPS-04-001, Corrective Action Program Effectiveness in
Operations
Nuclear Assurance-Oversight Report for Period August 21, 2004 through December 31, 2004,
NA-SQ-05-01
Nuclear Assurance Assessment - NA-SQ-04-02
CRP-LIA-04-001, 2004 Operating Experience Program Self-Assessment
OIG Audit Report 2004-036F, Concerns Resolution Program-TVA Nuclear 2004
OIG Audit Report 2004-036F, Concerns Resolution Program-Sequoyah Nuclear Plant 2004
Sequoyah response to Nuclear Assurance Assessment NA-CH-04-003
Self Assessment SQN-SIT-05-006, Evaluation of SQN Nuclear Safety Culture
PERs Reviewed for System 099, Reactor Protection System
17029 Unit 2 bypass RTB failed during testing
19974 Unit 1 inaccurate work document
20404 Unit 2 feedwater regulating valve did not respond as expected during a test
20734 Unit 2 RTB problem
24747 Unit 2 entered AOP, due to Eagle 21 malfunction
25088 Reactor trip and feedwater isolation signal generated during testing
25427 Spare RTB tripped during testing
25444 Unit 2 trip breaker contact alignment problem
27381 Missed a procedure step during testing
27717 Unit 2 circuit board failure
33629 PER 25088 closed in error and new PER generated
34368 Eagle 21 failure
60449 Unit 2 TSP failure
60452 Unit 2 TSP alarm
60456 Unit 2 protective set IV TSP failure
64396 Unit 2 LCP card failure
64477 Unit 2 LCP card failure
69045 New EPT board failure
69367 Unit 1 universal board failure
70900 A reactor trip breaker would not close
70711 Unit 2 TSP card failures
70741 Unit 1 TSP failure in rack 1-R-7
71617 Unit 2 protective set 3 trouble flashing
71845 Unit 2 wrong circuit board installed
2765 Unit 2 protective set 3 LCP failure
2771 Unit 2 protective set 3 lockup
80113 Question concerning LCO during WO process
80535 A reactor trip breaker opens
80555 Switch left in wrong position during work
80683 Reactor trip breaker failure to latch
Work Orders Reviewed for System 099
98-4568 Reactor trip bypass breaker repair
99-3192 RTB problem
00-1462 RTB solenoid sticking
00-1924 RTB damage found
00-9854 RTB has missing parts
01-7600 Modify RPB control relay
01-9478 Repair RTB latch
2-3927 Replace RTB arc suppressor
03-4021 RTB has low trip force
03-19348 Work on a breaker 52H switch
04-72378 Repair Unit 2 Eagle 21 malfunction
04-782116 Unit 2 eagle 21 malfunction
04-782150 Repair TSP failure
04-782797 Install Unit 2 circuit board
04-783480 Unit 2 LCP failure
PERs Reviewed for System 201, Low Voltage Power
25639 Board transfer problem
26135 During racking a shutdown board breaker, charging motor would not stop running
27538 Review of arc flash requirements and time to operate breakers per EOPs
33759 Damaged flood barrier around electrical board
60871 Arc flash tool concern
294 A breaker failed an overload test
2706 2B 480v ERCW MCC alternate feeder breaker not functional
63737 480v shutdown board loading
67779 Energized drop cord
67793 Methods to track Technical Specification 3.8.3.1 and 3.8.3.3 entries
68985 Breaker failure
68987 Missed functional failure and potential for others
69465 Inspection identified a damaged breaker
69817 Fan labeling and noun name problems
265 Possible PCB residue
71165 Problem determining operability of offsite power
71328 Foreign material in a breaker compartment
2696 Water coming in through conduit
75566 Incorrect breaker labeling
76066 Breakers exceeded an inspection extension date
77476 Shutdown board 1A2A load swing
81675 CRDM breaker 2B tripped
Work Orders Reviewed for System 201
00-1924 Perform inspection of a breaker
00-2017 Inspect breaker for damage
00-2144 A breaker tripped free on closing
00-2444 Inspect the breaker to determine cause of failure
00-9482 Remove parts from spare RTB and install on Unit 2 spare RTB
00-9854 Breaker damage found during inspection-repair
01-7600 Modify DB-50 breaker
01-9478 Replace breaker catch mechanism
PERs reviewed for System 202, Medium Voltage Power
1786 Problem with transformer sprinkler light indications
6132 Problem with transformer sprinkler light indications
220 Problem with transformer sprinkler light indications
19987 Review the ability to wave end device testing following maintenance
212 ERCW pump motor tripout alarm
2002 Problem with transformer sprinkler light indications
2700 Received motor tripout on pump P-B ERCW
24587 Annunciator setpoint problem
24704 Lighting board transfer switch problem
25017 6.9kv shutdown breaker racking problem
25108 Increased number of reportable safety system actuations
25636 6.9kv breaker trip
26036 Control wire strands not under a set screw
26037 Breaker not meeting response time
26624 Spare breaker acceptance criteria failure
27059 Problem with transformer fire protection light indications
34116 ERCW MB pump trip
60198 Missing part on a shutdown board breaker
60199 Siemens breaker problems
64539 Fuse clip problem
65059 Unit 2 ERCW MCC breaker fail to close
65164 Shutdown board breaker for ERCW P-B failed to close
65825 1B-B containment spray pump breaker failure
71149 Unit 1 start bus failed to transfer
71485 Unit 1 containment spray breaker problem
71724 Breaker problems
2085 Unit 1 shutdown board 1A-A test breaker failure
74489 Relay target amp setting different from setting sheet
78029 6.9 kv common board loss of control power
78171 A Siemens breaker failed receipt inspection
78968 Spare breaker has missing parts
81618 6.9kv bus bolts over torqued
2016 Unit 2 6.9 kv breaker trip
2999 Breaker B-026 discrepancies found during shop inspection
84070 Diesel generator cable to shutdown bus exceeded test requirements
85306 Bus 1A 6.9kv normal feeder breaker trip coil problem
Work Orders Reviewed for System 202
2-968 ERCW pump breaker and hand switch replacement
2-5453 ERCW pump breaker and hand switch replacement
2-5817 Problem with transformer sprinkler light indications
2-14218 Check problem with transformer sprinkler light indications
2-32078 Check problem with transformer sprinkler light indications
03-14877 Troubleshoot transformer sprinkler light indications
03-22002 Check problem with transformer sprinkler light indications
04-770593 ERCW pump breaker problem
04-771281 Troubleshoot lighting board switch problem
04-774689 Repair breaker missing parts
04-780278 Swap Unit 1 6.9 kv breaker on shutdown board 1A-A
04-782385 Investigate Unit 1 containment spray breaker trip
05-770340 Replace defective lugs and missing retainers
05-772819 Work on control power converter
05-774663 Investigate breaker trip
PERs Reviewed for System 63, Safety Injection System
23817 U2C12 containment debris
81304 U2C13 containment debris
81555 Debris in U2 SG#4 enclosure
20584 U2C12 debris inside polar crane wall
31497 Worker signed on to only 1 of 2 necessary clearances to replace U2 RWST heaters
268 RWST level enclosure deficiencies
31517 inadvertent water transfer from U1 RWST to U2 RWST
83459 SI pump reliefs leaking
23110 1BB SI pump failed Section XI test
75483 Boric acid on SI pump seal areas
70762 Borated water leak 1-VLV-63-557
27978 Borated water leak 1-VLV-62-720
244 Borated water leak 2-FCV-63-152
20916 Borated water leak 2-VLV-63-615
20674 U2 forced outage leakage exam observations
20569 Borated water leak 2-FCV-63-26
34063 Borated water leak1-FCV-63-157
71038 Borated water leak 1-VLV-63-553
31880 Borated water leak 2-FCV-63-25
70761 Borated water leak 1-FCV-63-70
69773 Borated water leak 2-FCV-63-48
85481 Injection valve packing leakage
2645 Injection valve packing leakage
63984 Injection valve packing leakage
2738 Injection valve packing leakage
34063 Injection valve packing leakage
28067 Injection valve packing leakage
20689 Injection valve packing leakage
252 Borated water leak work order problems
231 Grinnell valve stem nuts loose
2716 Repeat maintenance of mechanical seals
77826 Solenoid valves having abnormally high usage
73869 Numerous areas of missing insulation
71445 Containment sump flow isolation valve would not open
2135 2B Pen room cooler low flow
PERs Reviewed for System 74, Residual Heat Removal System
21077 Borated water leak 2-FCV-74-24
31321 Borated water leak 2-VLV-74-531
74809 Borated water leak Various Valves
74493 Borated water leak Various Valves
20571 Pre-RHR outage borated water leak
20159 Output of temp monitor unstable
84378 ECCS pump room floor clogged weep holes
31417 Failed to enter LCO on both RHR pumps
24872 RCS temp increased above 285 degrees after RHR placed in service
17056 RHR heat-up rate exceeded 100 degrees
20487 RHR operating procedure question
21148 Failed to enter LCO when placing RHR in service
20546 U2C12 ice condenser debris
27960 U2 debris found inside polar crane wall
68650 Low ERCW flow in 2A RHR pump room cooler
2604 2A RHR pump abnormal noise
27603 Section of Unit 2 penetration room flooded
27625 Water flowing from 2A RHR heat exchanger room floor drain
71004 Design temperature limit changed
71522 Valve manipulations caused contamination outside posted area
PERs Reviewed for System 311, Control Building HVAC System
21010 MCR chiller operability delayed
84079 A Shutdown Board Room chiller compressor tripped
61083 1A 480V Board Room chiller tripped/lost freon
68950 B Shutdown Board Room chiller failed to restart
71484 A Shutdown Board Room chiller TCV failed
73841 B Shutdown Board Room tripped/TCV failed
68613 Shutdown Board Room AHU fan motors failed
263 2A 480V Board Room AHU fan vibration
71838 B Shutdown Board Room inoperable
69078 Six MR functional failures on SDBR chillers
280 Wrong fuses in B SDBR chiller control panel
69780 PM revisions without System Engineering review
77888 A Electric Board Room chiller vibrations
2115 Low flow on B CREVS
70358 B MCR chiller high pressure oil hangers
70135 B MCR chiller tripped
19740 B MCR chiller maintenance extended six times
235 B MCR chiller maintenance extended
74332 Maintenance not performed in assigned frequency
76159 B MCR chiller AHU dampers bound
27878 MCR unnecessary LCO/MR time
252 Installation of ground on MCR chiller control system
63168 Incorrect train identification
64547 Ground wires not installed in chiller mod
63102 Transformer leads for chiller control panel mod are mislabeled
63094 Clearance tag on incorrect valve
61460 Communications problem with digital controller
71435 Chiller terminals not identified
65752 Post testing maintenance deficiencies
65037 Work order not performed as scheduled
209 Chiller equipment failure during PMT
24594 Chiller electrical compartment missing covers
20192 Chiller oil cooler outlet temp high
68880 Clams in electric board room chiller
PERs Reviewed for System 313, Auxiliary Building HVAC System
67713 A Electric Board Room chiller freon leak
65727 BB Shutdown Board Room TCV failure
27995 480V Board Room supply fan 1A-2B high vibrations
64375 Shutdown Board Room 1BB AHU motor bearing functional failure
28393 Replace MCR A chiller oil cooler TCV
60826 Vital Bat Rm IV pressure greater than MCR
25392 High vibrations on 480V Board Room 2B-B AHU
77086 No alarm response procedures for digital chiller control mod
73354 Evaluate need for alarm response procedures
78475 2B 480V Board Room chiller tripped
77994 2B 480V Board Room chiller tripped
77314 2B 480V Board Room chiller inop
16383 Results of PER 981237 Effectiveness Review
69078 Trend PER for Shutdown Board Room chiller failures
67983 Safety related chiller resets
2864 Board jumper problem on chiller control upgrade
65198 Some CRDM A/C units have wrong bearings
66597 1B CRDM Air A/C unit compressors failed
20538 125 Volt Battery Room fan bad bearing
20342 Improper scheduling of preventive maintenance
61003 Water leaking from valve vault room to Aux Building
21061 Electric Board Room chiller freon leak
67964 Electric Board Room freon leak
21001 Shutdown Board Room chiller freon leak
25712 Auxiliary Building chiller tripped twice
20897 Shutdown Board Room chiller would not start
26777 480V Board Room chiller freon leak
PERs Reviewed for System 61, Ice Condenser System
17042/32518/71284/82389 Baskets weighed less than the minimum analytical limit
20546/21301/72053/72903/83064 Debris left in ice bed
20446 Condenser back draft damper found closed
20518 Ice basket damage was identified
20542 Condenser back draft damper annunciator came in and cleared
20630 Condenser back draft damper found closed
24195 Ice bed temperature switches in alarm
25087 Condenser back draft damper alarm
208 Check valve leak rate failure
25331 Glycol chiller disconnect switch found open
25463 Air handling defrost timers found improperly set
25608 Preventive maintenance scheduled after environmental qualification due date
25638 Glycol system valve stroke time greater than acceptable
27360 Glycol valves did not perform as required
29453 Floor monitoring cables not adequate for long term use
60749 Condenser back draft damper alarm
67190 Insulation degradation and corrosion
69493 Unplanned LCO for valve that would not stroke
69739 Glycol expansion tank low-low low level alarm
70871 Two Ice Condenser door seals have small tears
71380 Basket vertical ligaments broken
71441 Five baskets found heavy
71498 Boron from ice melt leaking through ceiling
71682 Ice bed temperature detectors damaged
236 Ice machine glycol cylinders excessive leakage
2626 Floor monitoring system alteration not properly documented
75098 Testing changes not adequately reviewed
2536 Borax solution does not meet acceptance criteria
2408 Craft not following procedure for packing ice
2409 Five baskets requiring servicing missed
2575 Yellow plastic used in Ice Condenser posed debris risk
269 Inlet door with incorrect hinge pin
PERs Reviewed for System 65, Emergency Gas Treatment System
00-007785 Annulus vacuum system recurrent damper problems
2-013522 Hole found in EGTS fan flexible discharge duct
03-010200 Problems with Unit 1 annulus fan dampers and annulus vacuum fan
03-010357 Unit 2 annulus vacuum fan indicating switch problem
03-010996 Duct access panel found unlatched
03-013356 Debris found in flow element
03-014018 Elapsed time meter failed
25191 Tear in EGTS ductwork
03-010769/04-000447/24360 Annulus pressure control degraded
03-011493/33963 Annulus vacuum fan flow switch problems
03-008880 Annulus vacuum fan suction dampers leaking air
234 Inappropriate use of 10 minute hold time for functional evaluation
PERs Reviewed for System 90, Radiation Monitors
233 Alarm 1-RA-400B Shield Bldg. Vent malfunction
245 Alarm 1-RA-400B Shield Bldg. Vent malfunction
03-15959 Alarm 1-RA-400B Shield Bldg. Vent malfunction
24617 0-RM-90-212A setpoint found at 7.40e+04 instead of 7.40e+2
26052 Maintenance Rule functional failure of 2-RM-90-400A, Shield Building Exhaust
70654 Minimum required sample flow rate could not be achieved
76916 Particulate filter not installed in 1-RM-90-400 as required
2707 During PMTs it was discovered that the suction isolation valve was closed
77446 During lifting clearance it was discovered that the suction valve was closed
84902 Maintenance Rule functional failure of 1-RM-90-400, Shield Building Exhaust
19759 Unplanned entry into ODCM 1.1.2 Action 42
20566 Rad Monitors 0-RA-134B and 141B inoperable and ODCM 1.1.1 action 32 entered
20925 Alarm 1-RA-400B Shield Bldg. Vent malfunction
21316 Shield Bldg Ventilation monitor sample pump trip
291 0-RM-90-126 declared inoperable due to rad monitor pump tripping
25543 Alarm 1-RA-400B Shield Bldg. Vent malfunction
26307 Alarm 1-RA-400B Shield Bldg. Vent malfunction
66167 2-RM-90-106 failed causing unplanned entry into LCOs 3.3.3.1 and 3.4.6.1.
Work Orders Reviewed for System 90
WO 04-772209 Take ambient temperature data on 1-RE-090-0400A power supply
WO 04-772210 Take ambient temperature data on 1-RE-090-0400A power supply
PERs Reviewed for Emergency Preparedness Issues
33682 Improvement items identified during the March 23, 2004 Orange Team REP drill
20576 The radio for REP communications located in the RADCON lab is not working
21057 HP Radio in the RadCon Lab had to be turned all the way up to be audible
205 Repeat problem with EPIP procedure revisions
03-010688 Problem with EPIP procedure revisions
236 Continued failure to repair REP radio
03-015918 REP Radio in RadCon Lab
25802 Issues identified during the 10/17/03 REP drill
26306 Issue identified during actual ALERT on 8/28/2003
220 Trend PER for Pager tests
61309 Set points on Post Accident Radiation Monitors are higher than the EAL values
78915 Chem Lab is without vital power in Loss of Offsite Pwr
Work Orders Reviewed for Emergency Preparedness Issues
TPS WO #03-046437-000-001 REP radio in RadCon lab malfunction
Exercise Evaluations Reviewed
REP Drill on 8/18/2004
Graded Exercise on 6/23/2004
Off-Year REP Exercise on 3/16/2005
PERs Reviewed for Radiation Control Issues
279 RadWorkers not following radiological controls during U2C12 outage
03-16521 Workers entered U-2 690' pipe chase on wrong RWP
244 Individual exited gatehouse and went home with Electronic Dosimeter
64393 Person crossed a Radiography Boundary during the initial set up phase
64734 Contaminated nylon sling found in the Service Bldg clean tool room
65650 Trend PER for not signing out on RWPs and not reporting dose rate alarms
68353 Worker failed to sign out on his RWP
71635 Employee received both a dose and a dose rate alarm and failed to exit area
71595 Worker exceeded his RWP dose limit
71524 Worker received dose rate alarm and failed to notice upon exiting the RCA
2323 Pallet of chain hoists with purple paint on the loading dock by the Laborer Shop.
74749 Worker received a dose rate alarm on his Electronic Dosimeter
75039 Possible trend of inappropriate release of material from the RCA
75400 Trend PER for radworker performance during outage
80415 Discovery of purple-painted tools in unauthorized areas of the plant
81947 Worker failed to notice dose alarm and leave the area
2833 Unexpected dose rates in the Unit 2 Annulus during fuel transfer
2998 Individual received 5 electronic dosimeter alarms and did not immediately report
83091 Individual was on the wrong RWP and received a dose rate alarm. He failed to notify
radiation protection of this alarm
211 Individual was on wrong RWP, received dose rate alarm and did not immediately notify
RadCon
PERs Reviewed For Operating Experience
25619 Generic operating experience review for inaccurate work documents
25625 Review Westinghouse Technical Bulletin 99-05, R1, Breaker Minimum Trip Force and
Seismic Enhancements
25865 Generic review of WBN PER
26602 Generic review of operating experience for logic power supply
270 Generic review of BFN PER breaker light indications
280 Review of General Electric Technical Information Letter 1378-1
31532 Generic review of NRC EN 40364
2154 Review of operating experience OE-18349, HFA relay cracking
63333 Review of operating experience OE-40804
65735 Review Westinghouse Technical Bulletin (TB-04-13) molded case circuit breakers
68143 Review Westinghouse Technical Bulletin TB-04-17, Tyco relay issues
69552 Generic Review of BFN PER
70310 Review of Westinghouse Info Gram, IG-04-6, RTB test pushbutton problems
70386 Generic review of WBN and BFN PERs
75417 Generic review of operating experience OE-19727
77817 Generic review of operating experience, labeling problems
274 Review of Watts Bar White finding for silting in raw water systems
Procedures, Instructions, Guidance Documents, and Operating Manuals
SPP-3.1, Corrective Action Program, Rev. 8
SPP-1.6, TVAN Self-Assessment Program, Rev. 12
SPP-7.1, On Line Work Management, Rev. 6
SPP-6.0 Maintenance and Modification, Rev. 2
SPP-6.1 Work Order Process Initiation, Rev. 4
SPP-6.6 Maintenance Rule Performance Indicator Monitoring, Trending, and
Reporting - 10 CFR 50.65, Rev. 8
SPP-7.0 Work Management, Rev. 1
SPP-9.0, Engineering, Rev. 3
BP 250 Corrective Action Program Handbook, Rev. 8
TI-4, Maintenance Rule Performance Indicator Monitoring, Trending, and Reporting - 10 CFR 50.65, Rev. 17
0-TI-SXX-000-001.0, Conduct of System Engineering
0-TI-SBR-000-001.1, Breaker Testing and Maintenance Program
0-TI-OPS-000-063.0, Sensitive Equipment Control
MMDP-1, Maintenance Management System, Rev. 8
NEDP-12, System Component Health, Equipment failure Trending, Rev. 5
NADP-3, Managing the Operating Experience Program, Rev. 6
NEDP-20, Conduct of the Engineering Organization, Rev. 6
Miscellaneous Documents Reviewed
CAP Self-Assessment SQN-SIT-05-007, list of PERs
CAP Top Ten Problem List and Actions
Checklist for proper PER closure
HFA Relay Action Plan for Inspection and Repair
System Status Report, System 099, Reactor Protection System
System Health Report Card, System 099, Year 2005
System Status Report, System 201, Low Voltage Power, July 19, 2005
System Health Report Card, System 201, Year 2005
System Status Report, System 202, Medium Voltage Power, July 19, 2005
System Health Report Card, System 202, Year 2005
System Health Report Cards and Status Report for System 65, Emergency Gas Treatment
System Health Report Cards and Status Report for System 61, Ice Condenser
Meeting Minutes for PER coordinator meetings dated April 19, 2005 and July 21, 2005
Technical evaluation for molded case circuit breakers (PER 65735)
Effectiveness Review for PER 32427
Lesson plan, OPL273C0507, Welcome to Requal
Operations Standing Order 04-008, Control of Equipment Dogging Devices
Triennial Audit Schedule, 2005-2007
Westinghouse Technical Bulletin, TB-04-17 (Tyco Relay Issue)
Transmission Information Notice 04-008, possible PCB on relays
Radiation Monitoring System Status Report dated July 1, 2005
Safety Injection Systems Health Report
Residual Heat Removal Systems Health Report
Air Conditioning and Chillers System Health Report
Preventable Functional Failure Data for Systems 63 (SI) and 74 (RHR)
Integrated Quarterly Trend Reports (2004-2005)
LIST OF ACRONYMS
Abnormal Operating Procedure
Corrective Action Program
Essential Raw Cooling Water
LER
Licensee Event Report
Management Review Committee
NA
Nuclear Assurance
NRC
Nuclear Regulatory Commission
Offsite Dose Calculation Manual
PER
Problem Evaluation Report
Problem Identification and Resolution
Post Maintenance Testing
Rev.
Revision
SPP
Standard Programs and Processes
TI
Technical Instruction
TS
Technical Specification
Tennessee Valley Authority
Updated Final Safety Analysis Report
Work Order