ML20198B153
| ML20198B153 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/02/1998 |
| From: | Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 9812180080 | |
| Download: ML20198B153 (51) | |
Text
.,..
.-_-am
. _ _. _ _. __._._.~
,e t
- g' 9'o,,
e4 UNITED STATES NUCLEAR REGULATORY COMMISSION 8
REGION lli o
g-j tiO1 WARRENVILLE ROAD LISLE, ILLINOIS 60532-4351 n
\\ **** e t
Decender 2,1998 Mr. Oliver D. Kingsley President, Nuclear Generation Group Commonwealth Edison Company ATTN: Regulatory Services Executive Towers West til 1400 Opus Place, Suits 500 1
Downers Grove, IL 60515
SUBJECT:
MID-YEAR INSPECTION RESOURCE PLANNING MEETING - LASALLE
Dear Mr. Kingsley:
On November 4,1998, the NRC staff held an inspection resource planning meeting (IRPM).
The IRPM provided a coordinated mechanism for Region lit to adjust inspection schedules, as needed, prior to the conclusion of the Plant Performance Review cycle in April 1999. of this letter advises you of our planned inspection effort for the next 6 months at
. LaSalle.
This attached information is provided to minimize the resource impact on your staff and to allow
. for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival onsite..The rationale or basis for each inspection outside the core inspection program is provided so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature. contains a historicallisting of plant issues, referred to as the Plant issues Matrix (PIM), that was considered during the IRPM. The PIM incluoes only items from inspection reports or other docketed correspondence between the NRC and Commonwealth Edison
' Company.
l f
l l
1 l
9912180080 981202 PDR ADOCK 05000373 l
G PDR L
f
O. Kingsley We willinform you of any changes to the inspection plan. If you have any questions, please contact me at 630-829-9631 Sincerely,
/s/,G. E. Grant Geoffrey E. Grant, Director Division of Reactor Projects j
Docket Nos.: 50-373; 50-374 License Nos.: NPF-11; NPF-18
Enclosures:
1.
Inspection Plan 2.
Plant issues Matrix cc w/encis:
D. Helwig, Senior Vice President H. Stanley, PWR Vice President C. Crane, BWR Vice President R. Krich, Regulatory Services Manager
)
D. Greene, Licensing Director DCD - Licensing F. Dacimo, Site Vice President T. O'Connor, Station Manager P. Bames, Regulatory Assurance Supervisor R. Hubbard M. Aguilar, Assistant Attorney General State Liaison Officer Chairman, Illinois Commerce Commission DOCUMENT NAME: G:/LASA/INSPPLN7.LAS l
To receive e copy of this document, indicate in the box *C' = Copy without attachment / enclosure "E" = Copy with attachment / enclosure j'
'N' = No copy l
OFFICE Rill V
Rlli
./
Rlli l
NAME Hills:co d n}
Lanksbury"d w Grant (hDN
/
DATE 12/C/98 12/3/98 12/@/9f ) [
S OFFICIAL RECORD COPY l
I l'
.a.
ag.
O. Kingsley Distribution:
SAR (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encls J. Caldwell, Rill w/encls
..C. Pederson, Rlll w/encls B. Clayton, Rill w/encls.
SRI LaSalle w/encls -
DRP w/encls TSS w/encls DRS (2) w/encls Rlll PRR w/encls PUBLIC IE-01 w/encls Docket File w/encls GREENS LEO (E-Mail)
DOCDESK (E-Mail)
\\
\\
90033 pQd ',
QE5 DEI 1
LaSalle INSPECTION / ACTIVITY PLAN IP - Inspection Procedure Ti - Temporary Instruction Core - Minimum NRC Inspection Program (mandatory a!) plants)
Regional Initiative - Discretionary inspections NUMBER OF TYPE OF INSPECTION NRC INSPECTION /
/
TITLE / PROGRAM AREA INSPECTORS /
PLANNED DATES ACTIVITY-ACTIVITY INDIVIDUALS COMMENTS IP83750 Operational Radiation Protection 2
January 11 -15,1999 Core IP82701 EP Program 1
February 16 - 19,1999 Core Various Operational Readiness 5
March 29 - April 2,1999 Regional Initiative
- IP37550 Eng. & Material Condition Assess 3
April 5 - 23,1999 Regional Initiative
- IP84750 Effluents and Effluent Monitors 1
April 5 - 9,1999 Core IP81700 Security 1
April 5 - 9,1999 Core
- Regionalinitiatives reflect previous performance concerns and planned stanup of Unit 2 after an extended outage.
PLANT ISSUES MATRIX 1/20/1998 LaSalla search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = *SALP* ; sALP Area = *AllMuftipie'. Beginning Date = *10/1/1997* ; Ending Date = *10r20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
7/16/1998 Positive IR 98011 NRC All/ Multiple 3A The licensee's actions to address management expectations were implemented in accordance with the LaSalle Restart Action Plan with the goal of a step change in human performance. The licensee met this goal and continued to implement actions to communicate expectations to the plant staff and ensure the workers' understanding of the expectations.
Plant personnel were cognizant of management's expectations.
2 7/16/1998 Positive IR 98011 NRC All/ Multiple SA The licensee had programs for monitoring plant performance and took action to address adverse performance trends. Workers were conscientious of management expectations for safety and icentified potentially adverse conditions. In addition, plant personnel reported issues using the corrective action program to identify their concems, as specified by the licensee's corrective action program.
3 7/16/1998 Positive IR 98011 NRC All/ Multiple SC Station management coordinated the resolution of significant issues in an acceptable manner. Justifications for the deferral of specified operator work-arounds, temporary alterations, and control room distraction work requests beyond restart were reviewed by the inspectors and were adequate, and decisions made by management during meetings regarding the resolution of plant issues were conservative.
4 7/16/1998 Positive IR 98011 NRC All/ Multiple SC The licensee effectively implemented the step in the LaSalle Restart Action Plan to regularly communicate the status of the restart plan and system readiness reviews. Plant issues and corrective actions for the issues were effectively communicated by station management and were understood by station personnel.
5 6/5/1998 Positive IR 98012 NRC All/ Multiple SA Appropriate mechanisms were in place for self-assessment and quality assurance activities and a number of plant and organizational problems were being identified.
6 6/5/1998 Positive IR 98012 NRC All/ Multiple SA 5B SC The corrective action program at LaSalle was acceptable. improvements were noted in identification, resolution, and prevention of problems.
7 6/5/1998 Negative IR 98012 NRC All/ Multiple SB Corrective action to prevent recurrence and previous event reviews for recently completed root cause analyses appeared in some instances to be too narrowly focused. In one instance, a root cause analysis did not consider the programmatic aspects of the issue and in another instance, the written root cause report could not be properly assessed without discussions with the responsible investigators.
i Page 1 of 4 i
PLANT ISSUES MATRIX 1/20nss8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area = *AWMultiple*, Beginning Date = *10/1/1997* ; Ending Data = *10/20/1998*
DATE l TYPE SOURCE ID BY l SALP SMM CODES DESCRIPTION 8
6/5/1998 Positive IR 98012 NRC All/ Multiple 58 The root cause analysis process had improved since the start of 1998.
This improvement was due, in part, to new standardized corrective action procedures that resulted in better documentation of root causes and corrective actions and reduction of repeat events due to more effective corrective actions.
9 6/5/1998 Positive IR 98010 NRC All/ Multiple SC Licensee management review committees, such as the Safety Review Board, Plant Operations Review Committee, and Event Screening Committee, were cognizant of significant issues occurring at LaSalle Station and were properly addressing the resolution of the issues. Issues which required management attention were effectively communicated at 1
the committee meetings.
10 6/5/1998 Positive IR 98010 NRC All/ Multiple SC The licensee's Restart Action Plan actions implemented to address programs and processes to assist plant management in maintaining an awareness of significant plant issues that could impact safe plant operations appeared to be effective. Licensee management appeared to be cognizant of day-to-day issues, adequately cornmunicated the issues, and addressed the issues to ensure that problems were resolved.
11 6/5/1998 Positive IR 98010 NRC All/ Multiple SC The licensee was making progress toward implementation of action plans in support of improving management's ability to coordinate resolution of significant issues. Safety significant operator work arounds (OWAs) were scheduled for resolution prior to restart and progress was being reviewed by the licensee weekly. Deferred OWAs associated with the main control room were minor and were scheduled for resolution post restart. Temporary alterations had closure plans that had been evaluated against the licensee's restart criteria.
12 6/5/1998 Positive IR 98012 NRC All/ Multiple SC The inspectors concluded that the licensee made reasonable progress toward addressing 10 CFR 50.54(f) commitments discussed in the March 28.1997, letter to the NRC. The company wide procedure standardized and more clearly delegated responsibilities relating to problem identification, operating experience and self assessment.
Page 2 of 4
PLANT ISSUES MATRIX iir20/1988 LcSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area = *AWMultiple', Beginning Date = *10/th997* ; Ending Data = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 13-6/5/1998 Positive IR 98010 NRC All/ Multiple SC The licensee implemented actions for establishing objective criteria to determine if operator work-art 'inds (OWA) and main control room work requests would be included in the outage scope. Documentation reviews performed by the licensee were adequate and used to develop the outage plan. Management adequately identified and prioritized significant issues.
14 3/10/1998 Negative IR 98004 Licensee All/ Multiple 3A A recent increase in the rate of licensee event free clock resets involved both errors in implementing administrative aspects of the maintenance work process and radworker practices.
15 3/10/1998 Negative IR 98004 NRC All/ Multiple 3A Although licensee actions regarding personnel performance had been implemented, inspectors noted a recent decline in this area, necessitating se'.eral resets of the licensee's station event free clock in a relatively short time period. (Events occurred in the maintenance and plant support areas.)
16 3/10/1998 Negative IR 98004 NRC All/ Multiple SC Concems involving repeat events due to inadequate corrective action implementation were confirmed by additional examples in the licensee's perf0rmance imcking. (Recent events occurred in the engineering and maintenance areas.)
17 1/26/1998 Misc MR 3-98-0004 Licensee All/ Multiple Personnel in several senior plant management positions were changed including the Site Vice President, Station Manager, Operations Manager, and Restart Manager.
=
Page 3 of 4
GENERAL DESCRIPTION OF PIM TACLE LACELS A counter number used for NRC intemal editing.
The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actual date is not known, use the date DAM the issue was identified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event Report.
ID LY Identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and All/ Multiple (i.e., more than one SALP area affected).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Details of the issue from the LER text or from the IR Executive Summaries.
TYPE ITEM CODE NOTES SEN!OR MANAGEMENT MEETING CODES DEV Deviation from NRC Requirements Eels are apparent violations of NRO 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements thr.t are being considered for A - Normal EEP Escalated Enforcement issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the General Statement of Policy and C - Programs and Processes Procedure for NRC Enforcement Action Licensing Licensing issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscellaneous (Emergency Preparedness Finding, etc.)
However, the NRC has not reached its final A - Equipment Condition NCY Non-Cited Violation enforcement decision on the issues B - Programs and Processes Negative Individual Poor Licensee Performance identified by the Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Pe:formance may be modified when the final decisions A - Work Performance are made. Before the NRC makes its B - Knowledge, Skills, and Abilities Strength Overall Strong Licensee Performance enforcement decrsion, the licensee will be C - Work Environment URl" Unresolved Inspection item provided with an opportunity to either VIO/SL-I Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VI'.WSL-li Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-lil Notice of Violation - Severity Level 111 conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
" URis are unresolved iterns about which C - Programs and Processes d determin Weakness Overall Weak Licensee Performance 5
Prob!em Identification and Resolution:
e ue n s o9 acceptable item, a dev:ation, a A - Identification ID BY nonconformance, or a violation. However, B - Analysis the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PiM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other Identification unknown Page 4 of 4 l
PLANT ISSUES MATRIX
"' " 888 LaSalb Search Sorted by Date (Descerx!ing) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area =
- Operations *, Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
8/31/1998 Negative IR 98019 NRC Operations 1A Some configuration control issues continued to challenge station personnel such as an open main steam line drain valve during reactor vessel hydrostatic testing and closed instrument air isolation valves to the I
high radia ion sample system. None of the instances of deficient configuration control were safety significant. The licensee was cognizant i of the configuration control problems and implemented corrective actions to address the concerns.
2 8/31/1998 Negative IR 98019 NRC Operations 1A The quality of three-way communication between control room operators and field personnel during RCIC system testing was not consistent.
3 8/31/1998 Positive IR 98019 NRC Operations 1A The RCIC system testing during the Unit 1 startup was performed in a controlled manner by operators. The pre-job brief for the RCIC testing was thorough and operators used three-way communication consistently with each other within the control room. Operators accurately followed procedures and were attentive during RCIC pump performance testing.
4 8/31/1998 Positive IR 98019 NRC Operations 1A Operators performed well during the startup of Unit 1. Operatort, controlled Unit 1 startup activities and performed their duties in a deliberate manner. Operators maintained a questioning attitude, conducted professional shift briefings, and for the most part, met management expectations for communication and log keeping. Senior reactor operators ensured a professional atmosphere was maintained in the control room.
5 8/31/1998 Positive IR 98019 NRC Operations 18 Several equipment problems required operator attention and operators responded appropriately to the problems. In particular, the licensee took
~
appropriate, conservative action in shutting down the plant to address intermediate range monitor failures, failures during testing of the reactor core isolation cooling (RCIC) pump mechanical overspeed trip function, and flow control valve circuitry noise problems in the reactor recirculation system.
6 8/19/1998 Positive IR 98019 NRC Operations 1B Operators followed procedures in taking manual control of feedwater during a transient caused by a feedwater control system failure.
Operators also appropriately initiated a manual reactor scram when a pre-established reactor vessel water level limit was reached during the r
Page 1 of 13
PLANT ISSUES MATRIX 1/20/1998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" ; SALP Area =
- Operations *, Beginning Date = *10/1/1997*. Ending Date = *10/20/1938*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 7
8/17/1998 LER LER 373/98013 Self-Operations 1C Reactor water cleanup isolation system spurious isolations were received Revealed when an isciation valve was opened while placing the system in service and on another occasion when the regenerative heat exchanger shell side relief valve lifted during system warming. Plant procedures did not provide for an adequate fill ar;d vent of the system resulting in the first occurrence and inappropriately directed closure of a valve which trapped water in portions of the system resulting in the second occurence.
8 8/8/1998 NCV IR 98019 Licensee Operations 1A SA A licensed reactor operator became overly focused on control rod movements to support a plant heatup. Although he performed the appropriate surveillance, he failed to properly record the data or mark associated charts for reactor temperature and pressure data which was contrary to procedural requirements. The licensee identified the issue and operations management initiated prompt and conservative corrective 4
action.
9 7/29/1998 LER LER 373/98012 Self-Operations 1C During testing on the shutdown unit after initiating a manual scram, an Revealed unexpected automatic scram occurred from high scram discharge volume level. Following the manual scram, the operator had reset the scram signal after verifying the scram discharge volume high level alarm was not in. However, this action had been taken too early which resulted in the setpoint being reached in the seconds after the verification had been performed but before the reseting the scram. The applicable procedure was inadequate because it did not provide guidance to bypass the scram discharge volume high level interlock expect when the alarm was in.
10 7/22/1998 URI 1R 98019 NRC Operations 1A SB The inspectors identified an improperly installed lock and chain on a low pressure core spray system manual isolation valve which would not have prevented repositioning of the valve. The 5censee implemented immediate corrective actions to properly secure the lock and chain.
However, the licensee did not perform a review of the cause of the inappropriately locked valve until the inspectors requested the results of the licensee's review.
11 7/21/1998 NCV IR 98019; LER Self-Operations 1A inadequate command and control by the Unit Supervisor, poor 373/98009 Revealed communications between operations control room personnel, and incomplete work planning resulted in the unexpected start of the 1B emergency diesel generator. The response of operations personnel to the emergency diesel generator start was appropriate and the corrective actions were adequate.
Page 2 of 13
PLANT ISSUES MATRIX 1 /20/1 e 8 LaSalle Search Sortet by Date (Descending) and SMM Codes (Ascending): Search Colornn = *SALP". SALP Area =
- Operations *, Beginning Date = *10/1/1997* ; Erdng Data = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 12 7/21/1998 Positive IR 98015 NRC Operations 1C The licensee developed an adequate power ascension plan for Unit 1 restart. Testing, staffing, procedures, management review and oversight, and a process for problem resolution were adequately identified within the plan.
13 7/21/1998 Positive IR 98015 NRC Operations 1C The operating shift staffing met the requirements of Technical Specifications and administrative procedures. The licensee required a substantial amount of operator overtime to complete complex plant evolutions. Licensee management had implemented adequate procedures to limit and control overtime usage.
14 7/21/1998 Positive IR 98015 NRC Operations 1C Station administrative procedures appeared adequate to maintain configuration control after initial system lineup and operation. A walkdown of the low pressure core spray system indicated that administrative procedures controlling system configuration were r
adequately implemented. The licensee system lineup schedule indicated I
that all safety-related systems would be properly aligned prior to Unit 1 startup.
15 7/21/1998 Negative IR 98015 NRC Operations 1C The practice of excluding the unit supervisor and nuclear station i
operators from the shift briefing contributed to an operating crew inadvertently pumping potentially contaminated liquid waste from the turbine building fire sump to the clean waste water treatment system.
16 7/21/1998 Positive IR 98015 NRC Operations 3A Operator communications, control of on-shift duties, plant operator control board awareness and the process of controlling plant status to identify the operability of safety-related systems and components were adequate.
The operating crews conducted thorough and effective pre-job briefs, responded appropriately to annunciators, and operator panel walkdowns identified trends and abnormal conditions.
17 7/21/1998 Negative IR 98015 Licensee Operations 3A Human performance errors resulted in the issuance of a Unit 2 stator water cooling out-of-service for maintenance on Unit 1.
r Page 3 of 13
PLANT ISSUES MATRIX LaScib Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area = " Operations
- Beginning Date = *10/1/1997* ; Ending Data = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 18 7/21/1998 Negative IR 98015 NRC Operations 3A Several events occurred involving inadequate equipment control due to human performance issues. Licensae management was aware of the problems and was implementing corrective actions. For example, on one occasion a licensed operator operated the wrong equipment by placing the reactor building exhaust fan control switch into the pull-to-lock position. On another occasion, a licensed operator secured the drywell depressurization following testing by shutting a valve from the control room while a non-licensed operator was trying to control the depressurization rate by throttling a different valve in the field. On another occasion, the unit supervisor and nuclear station operator were t
not aware that the turbine building fire sump pumps were tumed off because potentially contaminated water had been drained to the sump.
Consequently, after the sump high level alarm sounded the operators tumed the pumps on and pumped the potentially contaminated liquid to the clean water treatment system.
19 7/21/1998 Positive IR 98015 NRC Operations 3A Based on a review of the administrative procedures and logged events, the standards and implementation of control room and in-plant log keeping were adequate.
20 7/21/1998 Positive IR 98015 NRC Operations 3A The conduct of operations crew shift tumovers was adequate. The team obsented several shift tumovers which were consistently conducted in a formal rnanner and in accordance with operating procedures. The communication of plant status, planned evolutions, priorities, and expectations during shift tumover and shift briefings was adequate.
21 7/21/1998 Positive IR 98015 NRC Operations 3B The licensee conducted operator training at an acceptable level to provide i operators with the skill and knowledge necessary to operate systems modified during the Unit 1 outage.
22 7/21/1998 Positive IR 98015 NRC Operations 3B Station management communicated expectations to station personnel, and station personnel were knowledgeable of management's expectations regarding procedure adherence. Station personnel adhered to procedural requirements. No deficiencies regarding procedure adequacy were identified.
Page 4 of 13 i
x. _. :.
PLANT ISSUES MATRIX
' /20/1998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area = 'Operatiens*, Beginning Date = *10/1/1997*. Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 23 7/21/1998 Positive IR 98015 NRC Operations SA The Operations Restart R9adiness Assessment was comprehensive and accurately identified the performance areas needing improvernent and corrective actions. The Restart issues ReW: Committee and Corporate Nuclear Review Board reviews of the restart readiness assessment were effective in assessing station performance and recognizing areas that required additional station management attention.
24 7/21/1998 Positive IR 98015 NRC Operations SA SC The Integrated Operations Performance Review process was effective in observing, identifying, and correcting performance that did not meet station standards. The conclusion was based on a review of previous evolution observation summaries and observed performance during the i
Unit 1 drywell pressurization test.
25 7/16/1998 Positive IR 98011 NRC Operations 1A 3A Operations performance was acceptable. Control room personnel communicated effectively and followed procedures in most instances.
Ucensed operators ensured correct contingency actions were discussed during a heightened-level-of-awareness briefing prior to an emergency core cooling system response time test. A non-licensed cperator took appropriate actions after discovering a strainer actuator was removed from an out-of-service released by maintenance personnel.
26 7/16/1998 Positive IR 98019 NRC Operations 1B Operations personnel responded appropriately to the trip of a reactor recirculation pump during a reactor vessel hydrostatic test, the failure of the other reactor recirculation pump to start, and the subsequent excessive reactor coolant system cooldown. The cooldown had minimal safe:y significance because the operators restored the cooldown rate to within acceptable limits in accordance with the applicable Technical t
Specification limiting condition for operations action statement.
27 7/16/1998 Positive IR 98011 NRC Operations 1C The licensee effectively implemented LaSalle Restart Action Plan activities in support of pre-startup testing. The licensee was developing a Power Ascension Plan which would address the restart and power ascension process and initiated the IOPR process to evaluate readiness for restart, both of which appeared appropriate. Testing and procedure revisions required for restart had been identified by the licensee and were either completed or scheduled in the Unit 1 integrated restart schedule.
Page 5 of 13 I
PLANT ISSUES MATRIX 11/20/1998 LaSalb search sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *sALP* ; SALP Area =
- Operations *, Beginning Date = *10/1/1997*. Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 28 7/16/1998 Negative IR 98011 Licensee Operations 3A Operators made minor errors during the inspection period. Although the errors did not result in any safety consequences, they did present challenges to plant configuration control. For example, a licensed control room operator operated an incorrect switch prior to maintenance on a ventilation fan, and operations personnel established an OOS on the incorrect unit for stator cooling system maintenance.
29 7/16/1998 Negative IR 98011 NRC Operations SA The inspectors identified a few performance deficiencies during the IOPR which were not observed by the licensee. However, the problems did not detract from the overall critical review of the plant performance during the Division I and 11 response time tests.
30 7/16/1998 Positive IR 98011 NRC Operations SA The licensee's Integrated Operations Performance Reviews (IOPR) conducted during the Division I and 11 response time tests were, with few exceptions, critical of plant personnel performance and provided an adequate assessment of the integrated plant performance during those plant evolutions.
31 7/6/1998 Positive IR 98016 NRC Operations 1C The reactivity manipulation plan was properly developed and was consistent with NRC policy. The decision not to use non-licensed operators to perform reactivity manipulation during the initial criticality and plant heat up demonstrated an appropriate safety focus.
32 7/6/1998 Positive IR 98016 NRC Operations 3A Operator performance in the simulator had improved over the last 18 months. This assessment was based on the licensee's use of consistent evaluation standards and challenging examinations with significantly increased pass rates. The performance improvement in staff crews was not as marked as for the operating crews.
33 7/6/1998 Positive IR 98016 NRC Operations 3B 1C The licensee's efforts to improve operator training, and conduct additional training as part of its restart action plan have been good. The licensee's significant events and startup training, which was still in progress, was appropriate prior to plant restart. The licensee's evaluation of operator performance in the simulator was critical and thorough.
Page 6 of 13
.. =... =.
=-
-=
PLANT ISSUES MATRIX M/20/1998 LaSalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP'. SALP Area = " Operations *. Beginning Date = *10/1/1997*. Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 34 6/5/1998 Negative IR 98010 NRC Operations 1A 3A The inspectors identified that control room operators were not aware of the reason a reactor water cleanup system containment isolation annunciator was in an alarm status. In another instance identified by the inspectors, an equipment operator provided incorrect information during a shift briefing with regard to the operability status of an emergency diesel generator. Other operating personnel present did not notice or correct the erroneous information.
35 6/5/1998 Positive IR 98010 NRC Operations 1A 3A Operations personnel performance was adequate. Control room personnel observed by inspectors generally maintained accurate records, effectively communicated, and followed procedures.
36 6/5/1998 Positive IR 98010 NRC Operations 1A 3A The 1 A residual heat removal pump performance test was acceptable and conducted in a competent, professional manner by the operators who also exhibited strong control over the testing evolution. Operators adhered to procedural and Technical Specification requirements.
37 6/5/1998 Positive IR 98012 NRC Operations SB The root cause investigation for the May 5th valve manipulation outside the out-of-service (OOS) event was good. The root cause investigation was prompt, thorough, and showed good use of root cause investigation techniques. The report was well written and its conclusions were technically sound.
38 6/5/1998 Positive IR 98012 NRC Operations SC Programs that implement operating experience contained sufficient responsiveness and appeared to have mechanisms to notify and train s
appropriate personnel on the issues. A weakness that the licensee had identified with GE's distribution of SALs was corrected by the licensee.
39 5/10/1998 LER LER 373/98002 Licensee Operations 1C A licensed operator identified that during past practice EDGs were not being declared inoperable during quarterly tests when engine cooling was i
isolated. This was caused by procedural deficiencies.
Page 7 of 13
PLANT ISSUES MATRIX M/20/1998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area = " Operations *, Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 40 4/25/1998 Negative IR 98010 Licensee Operations 1A 3A A licensed operator withdrew a control rod an extra two steps instead of reinserting it because he did not perform an adequate self-check. There was no safety consequence to the operator's error because there was no fuel in the reactor vessel. The operator did not immediately recognize this as an error because he did not consider the withdrawn control rod to be "mispositioned* as specified in the licensee's abnormal operating procedures. He was not focused on the importance of personnel performance or reactivity control concepts. The licensed operator was complacent due to the fact that there was no fuel in the reactor and was t
not sensitive to the activity that he was performing.
41 4/23/1998 VIO/SL-IV IR 98010 Self-Operations 1A 3A Operators failed to follow independent verification requirements when Revealed removing out-of-service tags associated with control room ventilation system dampers. This failure contributed to removal of the incorrect tags and operation of the incorrect dampers, and resulted in a violation. In addition, communications meetings with operating crews to discuss the event were ineffective as indicated by interviews in which operators i
continued to misinterpret the independent verification requirements.
42 4/22/1998 Negative IR 98009 Licensee Operations 1A Operations department personnel continued to struggle with some personnel performance problems which resulted in minor operational events. For example, insufficient controls placed on a temporary alteration for a main turbine mechanical trip valve linkage and a lack of questioning attitude by contract workers and a field engineer resulted in unauthorized removal of that temporary alteration. In addition, inadequate communication between operators resulted in deficier;t monitoring of operating equipment, contributing to an overflow of the makeup demineralized water system.
43 4/22/1998 Positive IR 98009 NRC Operations 1A Inspectors observed that operations personnel were knowledgeable of plant and equipment status, maintained accurate records, effectively communicated operational information, and operated equipment in accordance with approved procedures.
44 4/10/1998 LER LER 373/98011 Licensee Operations SA The licensee identified a past inappropriate practice of not declaring fira pumps inoperable when their control switches were in the "OFF" position during testing with an operator assigned to continuously monitor and start the pumps if required. As a result, Technical Specification required special reports were not always submitted.
Page 8 of 13
.... = x. =
PLANT ISSUES MATRIX LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP" ; SALP Area = " Operations * ; Beginning Date = *10/1/1997* ; Ending Date = *10/20/1996*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 45 3/26/1998 Negative IR 98009 Self-Operations 1A 1C 2B The operators did not meet licensee management expectations, resulting Revealed in an unexpected automatic reactor water cleanup system isolation while placing the residual heat removal system in service following maintenance. Specifically, operators did not anticipate the impact of the current reactor water cleanup system configuration and modifications on this evolution. Operating procedures did not wam operators of a potential for a reactor water cleanup system isolation under these conditions. In addition, inspectors identified that instrumentation used by operators during this evolution was not calibrated.
46 3/25/1998 Negative IR 98009 Licensee Operations 1C After identifying a standby gas treatment system valve in the incorrect position, the licensee determined that the electronic work control system database contained numerous locked valve position discrepancies. The inspectors concluded that not all fields in the database had been validated against approved modifications and procedures. The licensee initiated appropriate corrective actions to resolve this configuration control issue.
47 3/10/1998 Positive IR 98004 NRC Operations 1A Inspectors observed operations personnel following plant procedures and being attentive to plant conditions and equipment status during routine activities observed during the resident inspection period.
48 2/27/1998 NCV IR 98004 NRC Operations 1A SC 7ue to a personnel error, the licensee had not properly addressed an existing station procedure goveming operational experience reviews while instituting a related corporate Nuclear Station Work Procedure.
49 2/13/1998 Negative IR 98004 NRC Operations 1A The deletion of several Technical Specification clarifications was not communicated to operations personnel in a timely manner. (No actual j
consequences resulted.)
50 2/11/1998 NCV IR 98004 NRC Operations SC The licensee's corrective actions to previous locked valve program implementation problems were not complete. Specifically, the licensee had decided to no longer implement program requirements for an 18-month locked valve checklist verification but had not made the corresponding revision to the program.
51 2/10/1998 Positive IR 98004 NRC Operations SC The licensee's actions to address an improperly engaged locking device on a suppression pool side test tcp upstream isolaticavalve were thorough and appropriate. For example, the licensee verified the position of all locked valves in all operable systems.
Page 9 of 13
PLANT ISSUES MATRIX
"/20ii998 LaSalb Search Sorted by Dato (Descending) and SMM Codes (Ascending): Search Column = "SALP", SALP Area = " Operations * ; Beginning Dale = *10/1/1997*, Erdng Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 52 2/6/1998 Positive IR 98004 NRC Operations 18 The licensee's response to the loss of two offsite power lines was good and operators performed well during the event.
53 1/20/1998 Negative IR 97022 NRC Operations 1A The inspectors identified that in a few instances shift managers were it' attentive in implementing the administrative requirements controlling shift tumover. In one instance, this resulted in the shift manager not being fully aware of inf;rmation communicated through the Daily Orders.
Also, operations department management was not maintaining Daily Orders as recommended by procedure.
54 1/20/1998 Positive IR 97022 NRC Operations 3A Overall, operations personnel were attentive to plant systems and followed plant procedures.
55 1/8/1998 Positive IR 97022 NRC Operations SB The Corrective Action Review Board (CARB) was performing wellin reviewing root cause investigations and the associated corrective actions. The effective CARB oversight and the increasing CARB acceptance rate for root cause investigations (51% to 95% since September 1997) indicated that the corrective action program was improving.
56 12/4/1997 VIO/SL-IV 1R 97020 NRC Operations 4B 3A The inspectors identified a violation involving the failure of operations personnel to ensure that all operatiblity evaluations remained on file in the control room. The unavailability of one operability evaluation resulted in an unnecessary entry into a Technical Specification limiting condition for operation action statement. Engineering personnel were removing the evaluations in anticipation of a procedure change that had not yet been implemented. Engineering personnel demonstrated a lack of questioning 4
attitude regarding the operationalimpact of removing operability evaluations.
57 10/31/1997 Positive IR 97016 NRC Operations 3A Based on routine inspector observations of control room activities, operators were attentive to the main control room panels, knowledgeable of various system configurations, and aware of activities in the plant.
Shift pre-briefs were of high quality and effective in communicating plant conditions.
58 10/31/1997 Positive IR 97016 NRC Operations SA The licensee's out-of-service (OOS) error performance indicator accurately reflected the status of significant OOS errors and personnel responsib!e for the indicator were knowledgable of the OOS program prob! ems. Also, corporate and site management responded as directed by procedure to address the OOS errors at LaSa!!e.
Page 10 of 13
.1.-..-_
= = = = = = - - -
PLANT ISSUES MATRIX
' "8 LcSalb Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = "SALP*, SALP Area = "Operatiorm*, Beginning Date = *10/1/1997* ; Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES!
DESCRIPTION 59 10/31/1997 Positive IR 97016 NRC Operations 5B SC 2A The licensee initiated appropriate immediate corrective actions to investigate and address equipment failures involving an emergency diesel generator failure to start and two breaker failures (0 emergency diesel generator output breaker for Unit 2 and Unit 1 Division ill supply breaker from the system auxiliary transformer.) in the first instance, the licensee enhanced the EDG starting procedure by adding an operator to improve communications and other steps to ensure the EDG was running before operators could take manual control of the fuel system. For the first breaker failure, the licensee identified binding of the cubicle mounted breaker position switch linkage. For the other breaker failure, the licensee sent the breaker to General Electric for analysis.
60 10/31/1997 Positive IR 97016 NRC Operations SC 28 The licensee's completed and planned actions for protecting emergt.. cy sources of cooling water and critical plant system from cold weather were adequate. An example was installation of an air sparger designed to prevent buildup of ice on submerged protions of the intake structure. The inspectors considered the licensee's use of previous plant experience in formulating its cold weather plans (such as adding additional heating equipment to the plant) to be a good initiative.
61 10/20/1997 Negative IR 97017 NRC Operations 1C Inspectors identified several deficiencies for administering and evaluating job performance measures. Issues pertained to not peforming job performance measures during requalification training (only used during annual operating exam); and poor validation and coordination of simulator job performance measures which caused exam difficulties; and a lack of formalincorporation of training on conduct of operation, management expectations, and use of adminstrative procedures into the requalification program.
62 10/20/1997 Positive IR 97017 NRC Operations 3A 3B While observing control room activities, NUO examiners noted that control room operators demonstrated appropriate knowledge of plant conditions and equipment status, proper access control, and proper communications.
63 10/20/1997 Positive IR 97017 NRC Operations 3B Licensed operator requalification programs were implemented in accordance with 10 CFR part 55 requirements. Examination material and operator evaluations prepared and performed by the training staff were, in general, considered satisfactory. Administration and evaluation of scenario performance were good.
Page 11 of 13
PLANT ISSUES MATRIX-
""' 8" -.
LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascereng): Search Column = "SALP" ; SALP Area = ' Operations * ; Beginning Date = *10/1/1997* ; Erdng Date = *10/20/1998*
[ #_
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 64 10/20/1997 Negative IR 97017 NRC Operations 3B During ti.e requalification examination on dynamic simulator scenarios, NRC examiners noted that some operators displayed performanca weaknesses. Command and control, use and familiarity of emergency operating procedures, classification of emergencies, and three way communications were at times weak. For example, because of a lack of attention to EOP parameters, two crews in different scenarios failed to direct emergency depressurization at the proper times. Individual operator diagnostic skills were marginal. Examples included failure to i
terminate and prevent feedwater injection when required, failure to identify standby liquid control pump was running with no injection, failure to identify a RHR pump was running with no injection, and failure to restore a CRD pump to operation when required. Overall operator performance of job performance measures was marginal. For example, one operator could not find the actual in plant control room EOP locker.
A number of operators had problems with the remote shutdown panel task. (Based upon observation of two operating crews.)
k Page 12 of 13
11/20/1996 GENERAL DESCRIPTION OF PIM TABLE LABELS A counter number used for NRC intemal editing.
The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actual date is not known, use the date DAM the issue was identified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event Report.
ID CY identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Suppo-t and All/ Multiple (i.e., more than one SALP area affected).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Details of the issue from the LER text or from the IR Executive Summaries.
TYPE ITEM CODE NOTES SENIOR MANAGEMENT MEETING CODES DEV Deviation from NRC Requirements
- Eels are apparent violations of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal EE!*
Escalated Enforcement Issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C-Programs and Processes Procedure for NRC Enforcement Action Licensing Licensing issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscellaneous (Emergency Preparedness Finding. etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-Cited Violation enforcement decision en the issues B Programs and Processes Negative Individual Poor Licensee Performance identified by the Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Performance may be modified when the finsi decisions A - Work Performance are made. Before the NRC makes its Strength Overall Strong Licensee Performance B - Knowledge, Skills, and Abilities enforc6 ment decision, the licensee will be C - Work Environment URl" Unresolved Inspection item provided with an opportunity to either VIO/SL-1 Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-III Notice of Violation - Seventy Level lli conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
" URis are unresolved items about which C - Programs and Processes e
Weakness Overall Weak Licensee Performance 5
Problem Id cation and Resolutiort e
e in so a
acceptable item, a deviation, a ID BY nonconformance, or a violation. However, B - AnaD's the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other Identification unknown Page 13 of 13
PLANT ISSUES MATRIX n/20n998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Maintenance *, Beginning Date = *10/1/1997*. Ending Date = *10/20/199 DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
8/31/1998 Positive IR 98019 NRC Maintenance 2A Housekeeping was acceptable. The inspectors identified fewer housekeeping deficiencies during this inspection period, indicating that housekeeping improved from the previous inspection period. The equipment in the drywell was in acceptable condition for operations and the drywell was clean and generally free of debris. Deficiencies that were identified by the inspectors were minor and corrected by the licensee.
2 8/31/1998 Negative IR 98019 NRC Maintenance 2B 3A The licensee's approach to troubleshooting of the 1 A eactor recirculation pump slow speed breaker and problems encountered during RCIC overspeed testing was initially narrow in scope and not well planned.
Although the licensee eventually resolved the issues, the licensee's approach unnecessarily protracted the repair process and resulted in additional failed tests. The licensee recognized this problem and was taking additional actions to improve the implementation of troubleshooting activities.
3 8/31/1998 Positive IR 98019 NRC Maintenance 3A in general, the licensee's performance of maintenance and surveillance activities was satisfactory. For example, troubleshooting and repair of the control system for the turbine driven reactor feedpumps was well implemented with a comprehensive plan and knowledgeable personnel.
4 8/31/1998 Misc IR 98019 NRC Maintenance 3A The overall amount of maintenance rework was just slightly above the licensee's goal but most recently was on an increasing trend. Associated deficiencies, with only a couple of recent exceptions such as a failed intermediate range monitor, 'Nere typically of minor significance.
5 7/21/1998 Positive IR 98015 NRC Maintenance 2A The operator workaround backlog had been reduced significantly and did l not contain any items which represented restart issues.
6 7/21/1998 Positive IR 98015 NRC Maintenance 2A The material condition of Unit 1 was good as indicated by system walkdowns, plant walkdowns, and document reviews.
7 7/21/1998 Negative IR 98015 NRC Maintenance 2A A number of material condition and housekeeping deficiencies were identified. However, these deficiencies were reir. vely minorin nature.
8 7/21/1998 Positive IR 98015 NRC Maintenance 2A The team reviewed deficiencies that had been identified for resolution and verified that none of the deficiencies reviewed were safety significant or collectively represented a concem for system startup and operation.
9 7/21/1998 Positive IR 98015 NRC Maintenance 2B Equipment deficiencies were property controlled and degraded equipment was adequately scheduled and tracked for repair.
Page 1 of 11
PLANT ISSUES MATRIX
*8 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP'. SALP Area = " Maintenance *, Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATEl TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 10 7/21/1998 VIO/SL-IV IR 98015; LER NRC Maintenance 28 Manual fire protecti >n isolation valves associated with five charcoal filter 373/08008 bed deluge systems were not cycled within the 12 month period required by Technical Specifications. (These valves were left closed and not tested because of the risk of water intrusion into the charcoal beds.) After modifications in 1996 adding second isolation valves in these systems, the licensee didn't recognize them as now testable and change the testing 1 program accordingly.
11 7/21/1998 Positive IR 98015 NRC Maintenance 2B Work package quality was adequate to support the planned maintenance activities.
12 7/21/1998 Positive IR 98015 NRC Mair.tenance 2B The changes made by the licensee to surveillance test and startup procedures were technically appropriate and adequate to support p! ant restart.
13 7/21/1998 Positive IR 98015 NRC Maintenance 2B SC The implementation of the System Readiness Review Board (SRRB) was effective. In particular, the SRRB members challenged the information presented on a number of occasions to ensure that decisions regarding the deferral and inclusion of items in Unit 1 forced outage L1F35 were appropriate.
14 7/21/1998 Positive IR 98015 NRC Maintenance 3A Observed maintenance activities were performed in accordance with the applicable work package instructions and maintenance department standards. Based on direct observation, maintenance workers demonstrated conservative decision-making when confronted with an unexpected situation. Specifically, the licensee halted installation of isolation and vent valves in the LPCS motor cooling water system after a maintenance worker identified water dripping on a welding machine from an unknown source.
15 7/21/1998 Negative IR 98015 NRC Maintenance 3A Work package quality feedback forms were not consistently used. These forms were provided to workers in the field to walkdown the work packages prior to the performance of non-emergent work. Four of five work packages reviewed did not have a completed form.
Page 2 of 11
11/20/1998 PLANT ISSUES MATRIX LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Maintenance *, Beginning Date = *10/1/1997* ; Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 16 7/21/1998 Negative IR 98015 NRC Maintenance 3A Four minor personnel errors indicated lapses in attention-to-detail and ineffective review and maintenance of completed surveillance test data.
For example, calculations of corrected differential pressure for compartments adjacent to the control room for the A train of the control room ventilation system were incorrect, although in the conservative direction. Additionally, an unanticipated response identified during a smoke detector surveillance test was not entered into the corrective action process.
17 7/21/1998 Positive IR 98015 NRC Maintenance 3A SA SC The quality of completed maintenance activities was adequate.
Performance monitoring of the reactor core isolation cooling (RCIC) and control room ventilation (VC) systems as required by the Maintenance Rule was verified to be adequate, and the licensee had taken adequate measures to improve VC and RCIC system performance. Additionally, a higher sensitivity to rework among the maintenance workers and the increased use of peer checking resulted in a lower rework rate.
18 7/21/1998 Negative IR 98015 NRC Maintenance 3B Maintenance workers, in general, were not aware that they had increased responsibility to ensure work was properly performed during priority work.
In these instances, the process bypassed some established controls..
19 7/21/1998 Positive IR 98015 NRC Maintenance SA The Maintenance Restart Readiness Assessments were comprehensive and accurately identified the performance areas needing improvement and corrective actions. The issues which were identified as a result of the self-assessments were appropriately categorized, and the corrective i
actions planned or implemented appeared adequate. The Restart issues Review Committee and Corporate Nuclear Review Board reviews of the restart readiness assessment were effective in assessing station performance and recognizing areas that required additional station management attention.
20 7/16/1998 Positive IR 98011 NRC Maintenance 2B The conduct of maintenance was acceptable and had improved in the areas of rework and the work scheduling process.
21 7/16/1998 Negative IR 98011 Licensee Maintenance 3A The licensee identified that a supervisor released an OOS on a non-safety related service water strainer for which work had not yet been completed.
Page 3 of 11
PLANT ISSUES MATRIX v2m8 LaSalb Search Softed by Date (Descending) and sMM Codes (Ascending): Search Column = "SALP" ; SALP Area =
- Maintenance" : Beginning Date = *10/1/1997". Ending Date = *10r"20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 22 6/5/1998 Positive IR 98010 NRC Maintenance 2B The licensee's assessment of work deferred beyond the outage completion date was accurate. Also, the system readiness review process provided additional verification of proper work categorization prior to Unit 1 restart.
23 6/5/1998 Positive IR 98010 NRC Maintenance 2B The licensee implemented daily outage management meetings at which various departments were we!I represented, and these meetings were effective in obtaining commitments for schedule development and implementation. The licensee reviewed all outstanding work and determined which corrective tasks required completion prior to Unit 1 startup. Also, the licensee's implementation of the online maintenance process was progressing as planned and appeared adequate to support the system tumover process and Unit 1 restart.
24 6/5/1998 Positive IR 08010 NRC Maintenance 3A The licensee's performance of plant maintenance and equipment testing was adequate. Operations, maintenance, and engineering personnel observed by the inspectors generally followed procedures, demonstrated knowledge of the maintenance work tasks and tests assigned, and practiced good three-way communications. The heightened level of awareness briefings conducted prior to the test activities were adequate and maintenance supervision was present while work was in progress.
25 5/18/1998 Negative IR 98010 NRC Maintenance 3A in two instances identified by the inspectors, maintenance personnel did not complete work package documentation as expected by licensee management. Personnel did not sign off the step as each step was corapleted in a work package and maintenance supervisors were not reviewing shift tumover sheets in the work packages. In addition, a i
maintenance supervisor did not verify that an out-of-service was in place before maintenance personnel performed work on the electro-hydraulic control system.
26 4/22/1998 Positive IR 98009 NRC Maintenance 28 Overall, maintenance procedures and documentation reviewed by inspectors were adequate.
27 4/22/1998 Positive IR 98009 NRC Maintenance 3A 3B Overall, maintenance and construction personnel observed by the inspectors adhered to procedures and were knowledgeable of their respective tasks.
Page 4 of 11
PLANT ISSUES MATRIX
' " "8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP", SALP Area = " Maintenance *, Beginning Date = *10/1/1997* ; Ending Data = *10?20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 28 4/8/1998 Negative 4/8/98 Public NRC Maintenance 2A The licensee categorized a considerable quantity of plant and equipment Meeting Summary deficiencies as non-outage and planned to complete them after startup.
Inspectors reviewed many of the items deferred until after startup, such as minor isolation valves leaking through, which are contained in the non-outage corrective maintenance work request backlog (approximated at currently 1100 per unit) and on an individual basis found none to be safety significant. In fact, the inspectors found the licensee's categorization of individual items included in the extended outage scope to be conservative. However, the potential adverse impact of a large amount of plant deficiencies on a relatively trouble-free startup and long operating run, which is the licensee's current goal, was of concem. The licensee had not yet generated specific plans on how it intends to approach the deferred items after startup at the same time it is dealing with any emergent work.
29 4/8/1998 Positive 4/8/98 Public NRC Maintenance 2B The licensee recently implemented schedule and planning process Meeting Summary changes in an attempt to address problems in this area which had been impeding the timely completion of material condition improvements.
30 4/3/1998 URI IR 98009 NRC Maintenance 2A SC Inspectors identified that the licensee planned to wait until after plant startup to resolve concerns regarding the potential of insulation on reactor building closed cooling water and primary containment ventilation chilled water piping to clog emergency core cooling system suction strainers.
This plan schedule was not conservative and the licensee subsequently decided to resc!ve the issue before startup.
31 4/1/1998 NCV IR 98009 Licensee Maintenance 3B 3A Human performance errors of minor significance occurred in the control and execution of some maintenance activities. A contractor inapriropriately performed control room ventilation system hanger work without proper authorization after a work package revision. In addition, maintenance personnel inadequately secured foreign material exclusion plugs on a reactor core isolation cooling system exhaust steam drain.
The errors were primarily the result of a lack of in-depth knowledge by the personnel performing the work activities.
32 3/11/1998 Positive IR 98009 NRC Maintenance 2A During the extended shutdown, the licensee had been implementing numerous material condition improvements. A number of the resulting system modifications, such as reactor water cleanup and ventilation system changes, had been quite extensive and exemplified a managen,ent commitment to fixing long-standing equipment pmblems.
Page 5 of 11
PLANT ISSUES MATRIX
'8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Maintenance *, Beginning Date = *10/1/1997* ; Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 33 3/11/1998 Misc 1R 98009 NRC Maintenance 2A 2B The licensee categorized a considerable nuantity of plant work as non-outage and plans to complete these activities after startup. Inspectors reviewed many of the items deferred until after startup which are contained in the non-outage corrective maintenance work request backlog, and on an individual basis found none to be safety significant. In fact, the inspectors found the licensee's categorization of individual items included in the extended outage scope to be consentative.
34 3/11/1998 Negative IR 98009 NRC Maintenance 2B Completion of maintenance work had been hampered by deficiencies in the scheduling and planning process. The licensee more recently implemented schedule and planning process changes in an attempt to address these problems.
i 33 3/10/1998 Negative IR 98004 NRC Maintenance 2A The inspectors identified continued problems with plant housekeeping including left over materials from maintenance activities, damaged lagging, and poor lighting.
36 3/10/1998 Negative IR 98004 NRC Maintenance 2A 3A Minor foreign material exclusion control problems, such as missing plugs on a drain collecting pot and poorly secured covers on a pipe during a valve replacement, were identified and subsequently addressed by the licensee.
37 3/10/1998 Negative IR 98004 NRC Maintenance 28 Difficulties in effectively scheduling and planning work impeded timely completion of outage activities such as reactor water cleanup system modifications.
38 3/10/1998 Positive IR 98004 NRC Maintenance 3A Overall, maintenance activities observed by the inspectors during the resident inspection period were acceptable and in conformance with work package requirements and supervisors were present at the work locations.
39 3/10/1998 Positive IR 98004 NRC Maintenance SA 3A The inspectors reviewed selected 50.54(f) performance indicators and concluded that the percent of rework has been consistently declining (3%
to 1.6%) and accurately reflected the improving quality of maintenance activities at LaSalle.
40 3/3/1998 Positive IR 98004 NRC Maintenance 5B SC The licensee took appropriate actions to identify the root cause of SBM
[ switch board, miniature] control switch failures and to develop corrective actions.
Page 6 of 11 i
PLANT ISSUES MATRIX 1/20/1998 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP", SALP Area =
- Maintenance *, Beginning Date = *10/1/1997*, Ending Date = *10/20/1998 DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 41 3/3/1998 NCV IR 98009 Licensee Maintenance SC The licensee failed to implement adequate corrective actions for the June 1996 service water event when the licensee did not incorporate the structure safety classification list into the work package preparation process. As a result, maintenance personnel began work to install fire protection piping supports into a safety related auxiliary building ceiling using a non-safety related work package.
42 2/3/1998 NCV IR 98004 Licensee Maintenance SC 1A 2B The licensee did not implement adequate corrective actions for the failure to test the manual backwash function of the residual heat removal service water strainers. In September 1996, during the NRC service water system inspection, the inspectors identified that the manual testing of the residual heat removal service water strainer backwash function was not performed as required by the Technical Specifications. On February 3, 1998, the licensee identified that, due to a personnel error involving a lack of understanding of inservice testing requirements, procedure changes requiring performance of manual testing of the strainer backwash function had not been implemented.
43 1/31/1998 Misc EN 33944 Self-Maintenance 2A 5B A steam tunnel check damper, designed to close on a high energy line Revealed break in the steam tunnel, failed to close upon shutdown of the reactor building ventilation system. The licensee later determined on 3/23/98 that the damper closing springs had been replaced with the wrong size (insufficient closing force) in the early 1990s. The vendor catalogs (Vulcan) of various vintages identified different forces for the same part number.
44 1/23/1998 Positive IR 97022 nRC Maintenance 3A The inspectors observed several Technical Specification surveillance tests. All tests were performed in an acceptable manner with no personel performance or Technical Specification conformance concems identified by the inspectors.
45 1/23/1998 Negative IR 97022 NRC Maintenance 3A 2A Poor cleanup following maintenance activities resulted in housekeeping deficiencies. In addition, the inspectors concluded that insufficient attention-to-detail by non-licensed operators and an ineffective housekeeping area owner program resulted in housekeeping deficiencies in the reactor building not being identified or corrected.
Page 7 of 11
PLANT ISSUES MATRIX
"' SS8 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP', SALP Area =
- Maintenance *, Beginning Date = *10/1/1997*, Ending Date = *10/2o/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 46 1/16/1998 Strength IR 98002 NRC Maintenance 2B SC The maintenance rule program was well-implemented. This conclusion was based on a determination that proper monitoring of systems and components was being accomplished. No violations of 10 CFR 50.65 were identified. The team noted strengths in the quality of the implementing procedure, the functioning of the present expert panel, the computer-based maintenance rule trat. king program, and the staff's positive approach to program implementation. The team also noted that aggressive corrective actions, taken in response to industry operating experience and a self-assessment, by both the LaSalle and corporate maintenance rule staff, played a significant role in preparing the program for the NRC inspection.
47 1/16/1998 Positive IR 98002 NRC Maintenance SA 3A The industry operating experience review program was well-organized and properly linked to the maintenance rule program. System engineers were clearly using industry experience information and generally understood the need to incorporate it into the maintenance rule program.
48 1/6/1998 LER LER 374/98001 Self-Maintenance 2A SB A broken solder joint located on a circuit board inside the reactor Revealed protection system motor-generator set cabinet caused tripping of the 2B RPS MG set output breaker and numerous RPS alarms and primary containment isolation system isolations. The solder connection did not appear to be the original factory solder job but the licensee could not find any maintenance history which involved work on this connection.
49 11/12/1997 VIO/SL-IV IR 97020 NRC Maintenance 3A SC 2B The inspectors identified two violations which resulted in the improper installation of a test valve assembly on an emergency diesel generator. A work planner failed to follow adminstrative maintenance process requirements to ensure the associated work package incorporated information from the vendor manual. In addition, the licensee had not taken adequate corrective actions following previous similar problems in December 1996.
50 11/7/1997 Negative IR 97019 NRC Maintenance 1C There continued to be examples where problems with the station work planning and scheduling process had a negative impact on station dose.
One particular example was the inability to schedule and perform a chemical decontamination of the reactor water cleanup system, which could have resulted in significant exposure savings.
Page 8 of 11
PLANT ISSUES MATRIX M/20/1998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Coiurnn = *SALP". SALP Area = " Maintenance". Beginning Date = *10/1/1997*. Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 51 11/5/1997 LER LER 373/97037 Licensee Maintenance SA 2B The.icensee identified an incorrect acceptance criteria in the surveillance procedure for the Divisions I and 2 diesel generator load sequence timer for the RHR A and B pumps. This had existed since 1982.
52 10/31/1997 Positive IR 97016 NRC Maintenance 3A The inspectors observed several surveillance actitivities (3) and the surveillance tests were conducted in an acceptable manner and no L
concerns with personnel performance were identified.
53 10/31/1997 Positive IR 97016 NRC Maintenance 3A 1C During observation of three maintenance activities, the inspectors determined that, overali, maintenance work was performed satisfactorily 1
and in accordance with appropriate work procedures, inspectors i
observed good coordination among involved departments. Involved personnel were knowledgable of the equipment operation, design, and work documents.
54 10/20/1997 LER LER 373/97038 Licensee Maintenance SA 2B During a review for GL 96-01, " Testing of Safety System Logic Circuits,"
the licensee identified that the operability of the trip / interlock functions was not verified during channel calibration surveillance testing of several hydrogen recombiner temperature and pressure switches.
55 10/14/1997 LER LER 373/97036 Licensee Maintenance SA 2B During a review of proposed post-maintenance testing, the licensee identified that the plant's method of performing channel functional tests on '
MOV thermal overload circuitry did not always check the entire thermal overload bypass channel. (The contact was allowed to be closed by a jumper versus actuating the associated relay.) This was caused by incorrect guidance provided by engineering and maintenance in 1989.
56 10/8/1997 LER LER 373/97034 Licensee Maintenance SA 2B During a review of test data, the licensee identified that non-conservative methods had been used during surveillance testing to verify that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> maintenance interval rating of 2860 kw. It did not account for loads that were not running during the test and did not account for worst case operating parameters of the loads.
57 10/7/1997 LER LER 373/97042 Self-Maintenance 2A 5B While investigating the failure of the Unit 1 system auxiliary transformer Revealed feedbreaker to Division 111 bus 143 to close, the licensee determined the cause to be lack of lubrication on the lower link pin bushings. The PM procedure and vendor technical manual, although addressing lubrication of other components did not specify lubrication requirements for this part of the breaker. As a result, Division 3 for both units was declared inoperable.
Page 9 of 11
PLANT ISSUES MATRIX LaSalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area =
- Maintenance * ; Beginning Date = *10/1/1997* : Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 58 10/7/1997 LER LER 373/97035 Licensee Maintenance SA 2B in followup to a Quad Cities issue, the licensee identified that surveillance testing for weekly channel calibration of APRM flow biased simulated therrnal power upscale had not been performed in accordance with Technical Specifications. Specifically, a channel adjustment recirculation drive flow was performed at 25 percent power instead of the required prior to Operational Condition 1.
t Page 10 of 11
11/20/1998
' GENERAL DESCRIPTION OF PIM TAZLE LABELS A count;r number used for NRC intemal editing.
DAM The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actual date is not known, use the date the issue was identified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event ReporL ID BY Identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and All/ Multiple (i.e., more than one SALP area affected).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Details of the issue from t5e LER text or from the IR Executive Summaries.
i TYPE ITEM CODE NOTES SENIOR MANAGEMENT MEETING CODES,
DEV Devietion from NRC Requirements Eels are apparent violations of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal EEP Escalated Enforcement issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Procedure for NRC Enforcement Action Licensing Licensing issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscellaneous (Emergency Preparedness Finding, etc.)
However, the NRC has not reached its final A - Equipment Condition i
NCV Non-Cited Violation enforcement decision on the issues B - Programs and Processes Negative Individual Poor Ucensee Performance identified by the Eels and the PIM entries 3
Hinnan Performance:
Positive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance are m de. Before the NRC makes its B - Knowledge, Skills, and Abilities Strength Overall Strong Licensee Performance enforcanent decision, the licensee will be C Work Environment URI**
Unresolved Inspection item provided with an opportunity to either VIOISL-I Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering /Desir-VIOISL-Il Notice of Violation - Severity Level II (2) request a predecisional enforcement A - Design VIOfSL-Ill Notice of Violation - Severity Level lli conference.
B - Engineering Support VIO/SL-IV Notice c! Violation - Severity Level IV
" URis are unresolved items about which C - Programs and Processes Weakness Overall Weak Licensee Performance 5
Pro m ication and Resolution:
wh e o
es sa acceptable item, a deviation, a ID BY nonconformance, or a violation. However, B - Anafysis the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., eauipment breakdown) conclusions are made.
Other Identification unknowT Page 11 of 11
PLANT ISSUES MATRIX
2 ' SS8 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area =
- Engineering *, Beginning Date = *10/1/1997* : Ending Data = *10f20/1998*
1 DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION
[.
i 1
8/31/1998 Negative IR 98019 NRC Engineering 3A The inspectors identified that during the performance of pressure regulation system startup testing, the test director directed an operator to place a switch in the OFF position which was out-of-sequenco with the goveming procedure steps. The test procedure was designated as a continuous use procedure; however, the test director and the operator failed to adhere to the licensee's requirement to perform continuous use procedural steps in the sequence written and did not obtain a temporary procedure change. There was no actual consequence to this action.
2 8/31/1998 URI 1R 98019 Licensee Engineering 3A in one instance, involving reactor recirculation flow control valve hydraulic lines, the licensee's resolution to Generic Letter 96-06 issues was not timely due to the deficient communications between a contractor and licensee personnel. In another instance, involving residual heat removal shutdown cooling suction piping, the licensee identified that calculations for a modification associated with Generic Letter 96-06 assumed an incorrect piping configuration.
3 E31/1998 NCV IR 98019 Licensee Engineering 3A 5A SC The licensee identified that a Qualified Nuclear Engineer had provided an incorrect flow value used to establish the setpoints for the average power range monitor flow biased scram and rod block and the rod block monitor rod block. The licensee's response was timely and appropriate and the safety significance of the incorrect setpoints was minimal.
4 8/31/1998 Negative IR 98019 NRC Engineering 48 The inspectors identified that operators relied upon an unofficial contro:
room file of operability evaluations which was not maintained current.
5 8/31/1998 NCV IR 98019 NRC Engineering SA The licensee identified that the source range monitor neutron count rate required by Technical Specifications for withdrawal of control rods during eartup was not conservative with respect the current plant design. The licensee took interim actions to ensure an appropriate count rate during Unit 1 startup and planned to submit a Technical Specification amendment request to resolve the issue. The licensee's failure in 1990 to derive the associated Technical Specification requirement from the
. analyses and evaluation included in the Updated Final Safet/ Analysis Report is a Non-Cited Violation.
6 7/21/1998 Positive IR 981015 NRC Engineering 4B The engineering department response to an emergent problem regarding the susceptibility of radiation monitor power supplies to voltage surges was effective.
Page 1 of 8
PLANT ISSUES MATRIX n/20/ima LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP*, SALP Area =
- Engineering *, Beginning Date = *10/1/1997*. Ending Date = *1C/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 7
7/21/1998 Positive IR 98015 NRC Engineering 4B 3A The operability evaluations reviewed were of good quality and provided adequate technical justification for the conclusions.
8 7/21/1998 Positive IR 98015 NRC Engineering 4B SC Overall, the modifications reviewed were properly designed, installed, and tested, in particular, the team considered the modifications reviewed for the control room ventilation, auxiliary electric equipment room ventilation, and residual heat removal systems to provide good technical resolution of the original construction deficiencies in these systems.
9 7/21/1998 Strength IR 98015 NRC Engineering 4C The implementation of the system functional performance review program was particularly good.
10 7/21/1998 Positive IR 98015 NRC Engineering 4C The licensee was effectively controlling the engineering request backlog.
11 7/21/1998 Positive IR 98015 NRC Engineering SA SC The Engineering Restart Reariiness Assessment was comprehensive and accurately identified the performance areas needing improvement and corrective actions. The issues which were identified as a result of the self-assessments were appropriately categorized, and the corrective actions planned or implemented appeared adequate. The Restart issues Review Committee and Corporate Nuclear Review Board reviews of the restart readiness assessment were effective in assessing station performance and recognizing areas that required additional station management attention.
12 7/16/1998 Positive IR 98011 NRC Engineering 5B The licensee performed an operability evaluation of the emergency core cooling system pumps to address a 10 CFR Part 21 report issued by Ingersoll-Dresser Pump Company. The evaluation was timely and was well written. The documentation clearly supportec the operability conclusions reached in the evaluation.
13 6/22/1998 LER LER 373/98006 Licensee Engineering SA While reviewing electrical drawings, engineers identified a local fire detection module in the standby gas treatment system that was in a harsh EQ environment but was not EQ qualified.
14 6/5/1998 Positive IR 98010 NRC Engineering 4A The inspectors determined that the reactor water cleanup modification was being implemented, although the critical control room drawings associated with the modification had not been appropriately maintained.
The licensee took actions to resolve the drawing issues identified and had previously initiated a review of the drawing change process.
Page 2 of 8
PLANT ISSUES MATRIX
"8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = "SALP*, SALP Area =
- Engineering *, Beginning Date = *10/1/1997* ; Ending Data = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 15 5/1/1998 Negative 5/1/98 Public NRC Engineering 4C An NRC engineering and technical support inspection completed on April Meeting Summary 21,1998, reflected an additional concem regarding the large amount of remaining work associated with various engineering programs such as setpoint control, fuse control, and inservice testing. Integrated oversight was questionable with respect to whether the licensee had clearly scoped -
out the full extent of needed actions including specific plans and resources, or analyzed the potential aggregate impact on plant operation, material condition, and design conformance.
16 4/16/1998 LER LER 373/98010 Licensee Engineering SA During a modification review, the licensee identified that incorrect range radiation detectors had been in service following modifications in 1994 to the control room ventilation system.
17 3/20/1998 LER LER 373/98005 Licensee Engineering SA While reviewing IST requirements for containment monitoring vives, engineers identified that the post-LOCA hydrogen / oxygen systeci sample valves had inappropriately never been treated as primary containment isolation valves.
18 3/19/1998 LER LER 373/98007 Licensee Engineering SA The licensee identified that during a postulated HELB inside the main steam tunnel, the reactor building exhaust isolation dampers would not close quickly enough to prevent overpressurization of the reactor building exhaust ductwork and downstream masonary plenum. There is safety-related control room HVAC equipment adjacent to the plenum.
19 3/10/1998 Positive IR 98004 NRC Engineering SA Program reviews in the engineering area performed by Quality and Safety Assessment Department personnel were thorough and identified many pertinent issues. (Reviewed programs included fire protection, environment qualification, Generic Letter 89-13 regarding service water, vendor equipment manual program, ASME code activities, and containment testing.) Findings resulting from the reviews were documented for resolution by station personnel. This conclusion was arrived at through reviews of identified issues and resolutions.
20 3/10/1998 Positive IR 98004 NRC Engineering SA 4B The inspectors reviewed selected 50.54(f) performance indicators and concluded that the temporary modification performance indicator accurately reflected the status of temporary modification resolution and adequate processes were in place to ensure goals would be achieved.
Page 3 of 8
PLANT ISSUES MATRIX i /2 m 8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *SALP', SALP Area =
- Engineering *, Beginning Date = *10/1/1997*. Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 21 3/10/1998 Positive IR 98004 NRC Engineering SA SC The licensee identified through a departmental self assessment that the engineering request screening process did not include a methodology to identify and evaluate potential operability issues associated with engineering requests. As a result of this concern, the licensee generated at least one additional formal operability evaluation. Corrective actions for this concem were appropriate. Engineering personnel have continued to identify engineering issues during system and program reviews.
22 3/6/1998 VIO/SL-!V IR 97023; LER NRC Engineering 4A Implementation of an LER action was deficient for a modification to install 373/96021 screens in the floor drain and equipment drain sumps to prevent foreign material from causing seat damage to the drywell equipment drain sump containment isolation valves. The design change package was canceled when the design change package paperwork could not be located and design dradgs were not updated to reflect installation of the modification.
23 3/6/1998 NCV IR 97023; LER Licensee Engineering SC 4A Inspectors verified that the licensee has replaced the RHR pump seal 373/96018 coolers that had previously been identified as not meeting design pressure requirements. (1996 issue) 24 2/10/1998 LER LER 373/98003 Licensee Engineering SA While analyzing a potential setpoint change, GE identified that the analysis for abnormal startup of an idle recirculation pump was not bounding.
25 1/16/1998 Positive IR 98002 NRC Engineering 3B System engineers interviewed by the maintenance rule inspection team were experienced and knowledgeable about their systems. System engineers were generally familiar with the maintenance rule program and were positive regarding implementation.
26 12/23/1997 LER LER 373/97045 Licensee Engineering SA 4A 2A The licensee identified that the thermal environmental qualification lives had expired for several components located in the Unit 1 and 2 post accident containment monitoring system. The qualified life calculation performed in 1984 was incorrectly based on ambient temperatures and did not consider heat generated with the components in a normal / standby energized condition.
Page 4 of 8
___- ~
PLANT ISSUES MATRIX 1 /20/1998 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *SALP* ; SALP Area =
- Engineering
- Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 27 12/18/1997 Positive IR 97018 NRC Engineering 4B The quality of recent operability evaluations was good (8 were reviewed) and, with one exception, provided the necessary technical justification to support the conclusions reached. (The exception involved the initial operability evaluation of a potential diesel generator cooling water piping waterhammer which stated that based on historical data this was not a credible event. However, the historical data did not reflect possible worse case design conditions.)
28 12/18/1997 Misc 1R 97018 NRC Engineering 4B 4C The vast majority of design change packages and engineering requests identified as restart-required during the system functional performance review process were similarly classified by licensee management.
Inspectors reviewed 9 of the 16 engineering requests and 7 of the 29 design change packages which had been subsequently re-categorized by licensee management. The inspectors found that for 7 of these engineering requests, the decision review process outlined in the Restart Project Management Program had not been followed, although inspectors agreed with the final categorization. In addition, due to a lack of attention to detail, two engineering requests had inappropriately not been coded as required for restart in the electronic work control system.
29 12/18/1997 Negative IR 97018 NRC Engineering SA Inspectors reviewod two licensee performance indicators. Performance indicator C-11, " Engineering Requests," was inaccurate and established goals for this indicator were not useful. In addition, the C.12,
" Engineering Requests Overdue," performance indicator had limited value since engineering requests extended prior to becoming overdue were not identified and the extension of engineering request due dates was not a controlled process. The licensee planned corrective actions to address these deficiencies.
30 12/18/1997 Positive IR 97018 NRC Engineering SA SC The Engineering Assurance Group (EAG) thoroughly and critically reviewed operability evaluations. In addition, EAG mentoring of engineering personnel was effective and EAG monthly performance indicators were an effective method to track and trend overall engineering quality. (These conclusion are based upon review of EAG oversight review records and interviews.) Some minor adminstrative weaknesses were noted.
Page 5 of 8
PLANT ISSUES MATRIX M/20/1998 LaSalle Search Sort ey Date (Descending) and SMM Codes (Ascending): Search Column = "SALP*. SALP Area r.
- Engineering *. Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 31 12/18/1997 Positive IR 97018 NRC Engineering SC 4A Licensee corrective actions for three design and testing problems were appropriate. These problems involved traversing incore probe system containment isolation valves which could possibly re-open following an isolation signal, a failure to perform containment isolation valve surveillance testing on the traversing incore probe system, and a source range monitor detector retract permit setpoint lower than required.
32 12/16/1997 LER LER 373/97046 Licensee Engineering SA 4A In followup to a system functional performance review finding, the licensee determined that the turbine building ventilation isolation darr pers would not close fast enough during a main steam high energy line break to keep pressure from exceeding the retaining capability of the turbine building exhaust tunnel. This condition could potentially impact upon the high pressure core spray electrical switchgear room and possibly spread to the other divisions'swicthgear rooms. The cause was an invalid assumption in the original calculations.
33 12/5/1997 LER LER 373/97044 Licensee Engineering SA 4A in followup to a system functional performance review finding that plant specific design basis calculations could not be found for the ADS accumulator capacity, the licensee calculated that the required capacity at the most limiting condition in the UFSAR may not be met. Later calculations showed the required capacity was met.
34 1i/25/1037 NCV IR 97020; LER NRC Engineering 5A 2B The licensee's identification of testing deficiencies involving the 373/97043 emergency diesel generators was positive and reflected an increased licensee focus on surveillance test procedure adequacy. (The test procedure did not verify operation of overcurrent relays that tripped the system auxiliary transformer feed breaker to the Division lil bus or that the EDG would continue to supply normal bus loads.)
35 11/20/1997 LER LER 373/97041 Licensee Engineering SA 48 Engineering personnel identified that on reactor startups prior to 1996, due to a misinterpretation of Technical Specifications, surveillances to verify adequate thermal limit margins had not been performed prior to exceeding 25 percent Rated Thermal Power.
36 10/24/1997 LER LER 373/97039 Licensee Engineering SA 4B Licensee identified that during previous outages that SRVs had been inappropriately removed with fuelin the vessel without an analysis of the' free ends of the SRV discharge pipes with regard to seismic loads. The original removal procedure had not been reviewed by engineering.
Page 6 of 8
PLANT ISSUES MATRIX
888 LCSolb Search Sorted by Date (Descending) and OMM Codes (Ascending): Search Column = *SALP', SALP Area =
- Engineering *, Beginning Date = *10/1/1997* ; Ending Date = *10/20/1998*
DATE TYPE' SOURCE ID BY SALP SMM CODES DESCRIPTION 37 10/24/1997 LER LER 373/97040 Licensee Engineering 5A 4B Licensee identified that attemate shutdown cooling flowpaths used since plant startup using RCIC and main steam lines had not been seismically analyzed when in a water filled condition.
38 10/23/1997 Strength IR 97013 NRC Engineering SA The inspector reviewed the licensee's System Functional Performance Review (SFPR) program and concluded that the number and significance of items identified during the reviews indicated that the program had been effective in identifying problems. Self-Critical 39 10/23/1997 Positive IR 97013 Licensee Engineering SA The inspector reviewed the licensee's assessment of the inservice testing (IST) program. The assessment identified programmatic problems which the licensee planned to address. Other/NA 40 10/23/1997 Positive IR 97013 NRC Engineering SA The inspector reviewed the licensee's implementation of the Engineering Assurance Group (EAG) function and concluded that the EAG thoroughly and critically reviewed 10 CFR 50.59 screenings and safety evaluations completed at'the station. Self-Critical 41 10/23/1997 Positive '
IR 97013 NRC Engineering SC The licensee's corrective actions to address a failure to revise relay setting order data sheets following a modification to the main feed breakers for 480 volt switchgear installed in May 1992 were adequate.
Other/NA 4
Page 7 of 8
11/20/1998 GENERAL DESCRIPTION OF PIM TAILE LACELS A counter number used for NRC intemal editing.
DATE The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actual date is not known, use the date the issue was ider tified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC inspection Report or LER for Licensee Event Report.
O CY Identification of who discovered the issue - see table.
SALP SALP Functional Area Codes - Engineering, Maintenance, Operations, Plant Support and All/ Multiple (i.e., more than one SALP area affected).
SMM CODES Senior Manager Meeting Codes - see table.
DESCRIPTION Detalis of the issue from the LER text or from the IR Executive Summaries.
TYPE ITEM CODE NOTES SENIOR MANAGEMENT MEETING CODES DEV Deviation from NRC Requirements
- Eels are apparent violations of NRC, 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal eel
- Escalated Enforcement issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Procedure for NRC Enforcement Action Licensing Licensing Issue from NRR (Enforcement Policy), NUREG-1600.
2 Material Condition:
Misc Miscellaneous (Emergency Preparedness Finding, etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-Cited Violation enforcement decision on the issues B - Programs and Processes Negative Individual Poor Licensee Performance identified by the Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance am made. Befom the NRC makes its Strength Overall Strong Licensee Performance B - Knowledge, Skills, and Abilities enforcement decision, tne licensee wi!! be C - Work Environment URl**
Unresolved Inspection item provided with an opportunity to either VIO/SL-1 Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-Ill Notice of Violation - Severity Level Ill conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
- UR!s are unresolved items about which C - Programs and Processes d ""
Weakness Overall Weak Licensee Performance 5
Pr m
n cation and Resolution:
e the ei e
sa acceptable item, a deviation, a ID BY nonconformance, or a violation. However, B - Analys.is the NRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-Revealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other Identification unknown Page 8 of 8
PLANT ISSUES MATRIX ir20/in8 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP* ; SALP Area =
- Plant Support', Beginning Date = *10/1/1997* ; Ending Date = *10/2o/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1
8/31/1998 Positive IR 98019 NRC Plant 3A Radiation protection (RP) personnel performed well during routine RP Support support activities. Technicians provided oversight for various maintenance and surveillance activities and ensured that plant personnel were cognizant of the radiological conditions while performing work in the plant.
2 8/10/1998 Negative IR 98019 NRC Plant 3A The inspectors identified one instance in which RP technicians were slow Support in posting a radiologically contaminated area and did not ensure formal control of the area to prevent personnel contaminations in the interim.
3 7/23/1998 NCV IR 98020 Licensee Plant 3A SA SC During an incident involving transfer of radioactive samples from the Support refuel floor, worker judgement was poor because work was conducted outside the known scope of of the as-low-as-is-reasonably-achievable (ALARA) plan, and continued even though the electronic dosimetry wom by the workers alarmed on several instances and other radiological problems occurred during the course of the work. Although the radiological work conditions were continually monitored by a radiation protection technician and job coverage was adequate to prevent an i
exposure in excess of regulatory limits, the problems with job planning and procedural adherence placed workers at increased radiological risk.
The licensee's investigation of the incident was timely and thorough, and corrective actions were adequate to address the apparent causes. No significant radiological consequences resulted from the incident.
4 7/16/1998 Positive IR 98018 NRC Plant 1C The licensee maintained administrative extemal dose levels to ensure Support that personnel doses were maintained as-low-as-reasonably-achievable (ALARA). Administrative dose controls were effective in maintaining personnel doses, and specified approvals were required to exceed administrative dose controls. The RP staff also effectively controlled doses to declared pregnant workers in accordance with NRC regulations and guidance.
5 7/16/1998 Negative IR 98018 NRC Plant 1C Procedural guidance with regard to air sampling was, in some instances, Support inconsistent with management expectations. For example, some procedures contained provisions for performing derived air concentration (DAC)-hour tracking for workers, even though radiation protection management prohibited this practice. Another procedure listed how to perform an optional field check of air samples but did not explain how this field check was to be used, in addition, there was no formal process for tracking lapel air samplers assigned to workers and associated results.
Page 1 of 11
PLANT ISSUES MATRIX 11/20/1998 LaSalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP" ; SALP Area = " Plant Support", Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 6
7/16/1998 Positive IR 98018 NRC Plant 1C 3A High and locked high radiation areas were controlled consistent with Support regulatory requirements and industry practice. During walkdowns, the inspectors observed workers using proper access control and significant recovery of some contaminated areas.
7 7/16/1998 Positive IR 98018 NRC Plant 1C 3A Air sampling was conducted consistent with industry practice and NRC Suppcrt regulations. Air sampling equipment was well maintained and air sampling activities were performed appropriately.
8 7/16/1998 Negative IR 98018 NRC Plant 3A Inspectors observed some problems with radiological housekeeping in Support that tools and materials from prior work activities were not removed from some locked high radiation areas.
9 7/16/1998 Positive IR 98018 NRC Plant SA The radiation protection staff properly implemented the extemal dosimetry Support quality control program. The licensee maintained National Voluntary Laboratory Accreditation Program accreditation in accordance with 10 CFR Part 20. In addition, periodic thermolumiscent dosimetry (TLD) quality control tests were performed, and the results were evaluated for long term biases or trends.
10 7/16/1998 Negative IR 98018 NRC Plant SA The licensee did not thoroughly investigate discrepancies between Support personal doses measured by TLD as compared to personal doses measured by efectronic dosimeters (EDs).
11 6/3/1998 Negative IR 98018 NRC Plant 5A SC Test documentation for the standby gas treatment system filter units Support indicated that damage was observed on the pre-filter and that the moisture seperator looked " bad," but had not documented any corrective actions. (These problems did not affect operability of the system).
12 5/26/1998 VIO/SL-IV IR 98018 Licensee Plant 1C Radiation protection personnel failed to establish appropriate controls to Support prevent two construction workers from entering an area within the Unit 2 A reactor water cleanup heat exchanger room, a locked high radiation area, that had not been radiobgically surveyed. The workers were not provided with a radiation monitoring device which continuous!y indicated the radiation dose in the area and were not accompanied by a health physics qualified indivual. The dose rates levels in the area were not established prior to the entry and were not known by the workers.
i Page 2 of 11
PLANT ISSUES MATRIX 11/20/1998 LeSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP" ; SALP Area =
- Plant Support' ; Beginning Data = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 13 5/11/1998 Positive IR 09018 NRC Plant 5B The licensee performed a thorough investigation of the source of Support irradiated metal found inside a Type B cask. Although the source of the metal and the duration that it was inside the cask were unknown, the inspectors determined that its presence would not have resulted in a significant health hazard during transport.
14 3/27/1998 NCV IR 98018 Licensee Plant 3A A contract engineer failed to obtain radiation protection department Support approval prior to moving a high radiation area barricade on the refuel floor resulting in a personnel contamination.
15 3/19/1998 Positive IR 98008 NRC Plant 2B The emergency response activities observed during an emergency Support exercise, with the exception of one exercise weakness, were effective.
Simulated events were accurately diagnosed, proper mitigation actions were perftrmed. State and local agencies were notified in a timely manner. Interfacility transfers of command and control of event response were orderly and timely.
16 3/19/1998 Positive IR 98008 NRC Plant 2B 3A An emergency exercise scanario was adequately challenging, and event Support classifications were based on plant conditions rather than an abnormal radioactive release. Overall exercise control was very effective.
17 3/19/1998 Negative IR 98008 NRC Plant 3A The untimely dispatch of " Urgent
- teams during an emergency exercise Support was an Exercise Weakness. Determination of SCBA qualifications for responders was weak.
18 3/19/1998 Positive IR 98004 NRC Plant 3A The Technical Support Center (TSC) staff's responses were competent.
Support The EALs were continuously reviewed to assure that the current event classification was correct. Thresholds for potential event escalation to higher classifications were identified and communicated to the staff. The TSC staff was effective in maintaining awareness of the emergency response and changing plant conditions.
19 3/19/1998 Positive IR 98008 NRC Plant 3A The overall performance of the Operational Support Center staff was Support adequate. All teams were given adequato pre-and post-dispatch briefings which emphasized the need for personal safety and maintaining low radiation exposures.
Page 3 of 11
=
PLANT ISSUES MATRIX
'1/20/1998 LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "SALP', SALP Area =
- Plant Support ; Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 20 3/19/1998 Positive IR 98008 NRC Plant 3A Emergency Operations Facility (EOF) responders effectively Support demonstrated their capabilities to perform their individual duties and to function as a team. The Manager of Emergency Operations correctly declared a General Emergency based on the degradation of the three
{
fission product barriers and the critena in the Station's EALs. An offsite protective action recommendation was communicated to State officials a!ong with this emergency reclassification within the required time limit.
21 3/19/1998 Positive IR 98008 NRC Plant 5A The licensee's assessment during an emergency exercise was in close Support agreement with the NRC eva'uation team's conclusions.
22 3/11/1998 Negative IR 98009 NRC Plant 3A 2A A lack of management attention contributed to various housekeeping Support deficiencies in high radiation areas of the plant, in addition, the inspectors identified an individual failing to self-check and read all radiological postings prior to entering an area being controlled as a high radiation area. The inspectors verified that high radiation area postings were adequate, however, the radiological protection greeter program was not effective in this instance.
23 3/10/1998 NCV IR 98004; LER Licensee Plant SA The licensee identified potential problems during a quality assurance 373/98004 Support review of the fire protection program at LaSalle. These issues included missed firewatches, the lack of coordination calculations, and a non-conservative fire stop justification. The licensee took appropriate corrective actions for the missed firewatches which were considered a non-cited violation. The other two issues remained under review by the licensee and inspectors.
24 2/27/1998 Positive IR 98007 NRC Plant 1C The security program was well implemented. Security management has Support been effective in completing program upgrades.
25 2/27/1998 Positive IR 98006 NRC Plant 1C The radiological environmental monitoring sampling and analysis program Support was well implemented, and the 1997 data showed that plant operations did not have a discemable radiological impact on the environment.
Page 4 of 11
PLANT ISSUES MATRIX
/20/1998 LeSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP* ; SALP Area = " Plant Support', Beginning Date = *10/1/1997* ; Ending Date = *10,*20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 26 2/27/1998 Positive IR 98006 NRC Plant 1C 2A Reactor water quality improved during the latter portion of the last Support operating cycle, primarily due to improved management of the condensate polishers. The installation and planned operation of the hydrogen injection system was well managed. The makeup water system was well maintained and the system effectively met plant needs for ultra pure water. The reliability and material condition of the system components was excellent, as evidenced by water quality data and system operating history.
27 2/27/1998 Positive IR 98006 NRC Plant 1C SB The radiological controls developed for the spent fuel pool inventory Support project were good, with appropriate consideration given to identifying potential hot particles. The as-low-as-reasonably-achievable plan for the project was generally sound and developed in accordance with procedure.
28 2/27/1998 Positive IR 98006 NRC Plant 1C 5B The as-low-as-reasonably-achievable plan for the spent fuel pool Support inventory project did not adequately incorporate lessons leamed from previous industry experience.
29 2/27/1998 Positive IR 98007 NRC Plant 3A Security force members were experienced and knowledgeable about their Support duties.
30 2/27/1998 Strength IR 98007 NRC Plant 3B The dedication, experience and program ownership of the security Support training staff and the demonstrated effectiveness of the contingency training were considered a program strength.
31 2/27/1998 Strength IR 98006 NRC Plant 3B 3A Chemistry personnel were knowledgable of their various responsibilities, Support demonstrated good ALARA practices and ownership of chemistry department activities, and conducted work in accordance with station procedures.
32 2/27/1998 Positive IR 98007 NRC Plant SA Salf-assessment activities in the security area were effective. The detail Support and quality of the audits and assessment reports were very good.
Findings represented valid issues and were good findings. The peer group assessment was a useful tool in identifying and obtaining corrective action on security issues.
Page 5 of 11
PLANT ISSUES MATRIX u/20ii w a LaSalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP*, SALP Area =
- Plant Support" Beginning Date = *10/1/1997". Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 33 2/27/1998 Positive IR 98006 NRC Plant SA 2A 1C The quality assurance / quality control (OC) and material condition of Support chemistry laboratory instrumentation were excellent, as evidenced by QC checks and QA intercomparison data. In addition, the material condition of the instruments was good and control of standards and reagents was effective.
34 2/27/1998 Positive IR 98006 NRC Plant 5A SC A comprehensive chemistry self assessment program was developed Support and mcently implemented by the chemistry staff. The inaugural assessment was relatively broad in its scope and identified problems with the reliability of certain effluent radiation monitors, and the need for improvement in chemistry staff knowledge and skilllevels, and timeliness of preparing certain samples for off-site analyses. Corrective actions were tracked to ensure ar.,propriate resolution.
35 2/27/1998 Positive IR 98006 NRC Plant 5A SC 2A Chemistry QC data indicated operability problems with a number of in-line '
Support instruments; however, the chemistry staff effectively initiated a program to upgrade these monitors. In addition, the chemistry department oversight of the installation and management of the in-line instruments associated with the hydrogen water chemistry addition program was effective.
36 2/27/1998 Positive IR 98007 NRC Plant SC Revised post orders and instructions were clearly written and user Support friendly. This action completed corrective actions in response to a root cause investigation of security force performance events from January 1, 1995 through March 9,1996.
37 2/27/1998 Positive IR 98007 NRC Plant SC Security management responded aggressively to identified security force Support performance issues and effectively evaluated generic causes through the problem identification form process.
38 2/26/1998 Positive IR 98004 NRC Plant 3A The response by security force members to the discovery of an Support undeclared firearm and ammunition was professional and prevented an unauthorized firearm from entering the protected area.
39 2/15/1998 Positive IR 98006 NRC P! ant 5B SC 1C The licensee's response to a self-identified incident involving radioactive Support material found outside the RCA was prompt and aggressive, and included a comprehensive root cause evaluation immediate and short term corrective actions were appropriate. Self-identified weaknesses with the radioactive material control program and proposed long term corrective actions were being evaluated by station management.
Page 6 of 11
PLANT ISSUES MATRIX
"' " 8 LaSalb Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *SALP* ; SALP Area =
- Plant Support", Beginning Date = *10/1/1997* ; Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 40 1/31/1998 NCV LER 373/98001; Licensee Plant 5A 3A The licensee identified through a quality and safety assurance audit that IR 98004 Support two fire watch inspections were " intentionally" missed by a contract fire watch inspector. Further licensee review later identified a second fire watch inspector who had missed two fire watch inspections.
41 1/30/1998 Positive IR 98003 NRC Plant 1B SA In an actual emergency plan activation (3/11/1997 Unusual Event due to Support high cooling lake levels), the emergency plan was effectively implemented by conservative classification of the event, and the discretionary activation of the Technical Support Center. The event was reviewed according to the appropriate procedure, and responders were actively encouraged to provide critiques and suggestions to improve the emergency response program.
42 1/30/1998 Positive IR 98003 NRC Plant 1C 2A 3B The emergency preparedness program was adequately implemented. In Support particular, emergency response facilities, equipment, and supplies had been well maintained, management attention to the program was indicated, and interviewed emergency response personnel demonstarted competent knowledge of responsibilities and emergency procedures.
43 1/30/1998 Positive IR 98003 NRC Plant 3B Emergency preparedness training was effective, but tracking of Support completed training needed improvement. Intenriewed key emergency response personnel demontrated competent knowledge of responsibilities and emergency procedures. Training records indicated that the program for tracking emergency responder qualifications was generally effective except relative to training of maintenance personnel. The licensee had effectively addressed and corrected a number of issues identified in the EP self assessment which included the identification that maintenance personnel had not received training. Training modules were properly updated.
44 1/30/1998 Positive IR 98003 NRC Plant SA SC The licensee's 1997 emergency preparedness audits and surveillances, Support and the 1997 EP Program Self-Assessment Report were effective and satisfied the requirements of 10 CFR 50.54(t). The audit and program self assessment were excellent scope and depth. Identified issues were appropriately tracked and resolved. Problems had been properly entered into the Problem Identification Form system when considered to exceed the threshold for entrance to the system. Corrective actions on several PIFs remained to by fully determined.
Page 7 of 11
PLANT ISSUES MATRIX M/20/1998 LaSalla Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *SALP", SALP Area =
- Plant Support' ; Beginning Date = *10/1/1997*, Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 45 1/19/1998 Positive IR 98008 NRC Plant 3A
~ arcise performance in the Control Room Simulator (CRS) was Support effective. CRS staff conservatively classified plant conditions using the Emergency Action Levels (EALs) in a timely manner. The initial notifications to State and local agencies were completed within the regulatory time limits but were not immediate.
46 12/18/1997 Positive IR 97020 NRC Plant 1C 3C The licensee decontaminated reactor water cleanup system work areas Support which increased the licensee's ability to perform maintenance more efficiently.
47 12/17/1997 Positive IR 97021 NRC Plant 1C 3A Measures to control dose during the reactor water cleanup system project Support were effective. Overall, the ALARA plan and associated radiological controls were generally well implemented. Dose from rework was minimized for the project as a result of good planning and work crew coordination.
48 12/17/1997 Positive IR 97021 NRC Plant 1C 3A SA The ALARA plan for the reactor water cleanup system project was Support comprehensive and included the extensive application of lessons teamed I from previous, similar station and industry experience. The content of the.
ALARA plan demonstrated effective coordination between engineering I
and radiation protection staffs in the development of its scope and in initiatives for future dose reduction.
49 12/1/1997 VIO/SL-IV IR 97021 NRC Plant 3A Radiation worker performance and radiation protection oversight of Support contractor activities for the reactor water cleanup system project were generally good with some exceptions. The exceptions involved two occasions when contract workers failed to follow the instructions specified in the radiation work permit and contact the radiation protection staff prior to initiating certain potential high risk evolutions (cutting and grinding.)
Personnel contaminations resulted. One violation was identified with two examples for failure to follow station procedures.
50 11/30/1997 VIO/SL-IV IR 97020 NRC Plant 3A The inspectors identified a violation involving the failure to properly post a Support contaminated areas. The lack of a questioning attitude by a radiation protection technician and by two non-licensed operators resulted in contaminated liquids being vented into a plant drain trough which was not identified as contaminated.
51 11/7/1997 Positive IR 97019 NRC Plant 1C Effective ALARA controls were used during the emergency core cooling Support system (ECCS) strainer replacement with appropriate consideration given to controlling diving activities and hot particles. Involved Management Page 8 of 11
*8 PLANT ISSUES MATRIX LaScib Search Sorted by D0te (Descending) and SMM Codes (Ascending): Search Column = *SALP" -, SALP Area =
- Plant Support" : Beginning Date = *10/1/1997* : Ending Date = *10/20/1998*
DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 52 11/7/1997 Positive IR 97019 NRC Plant 1C Ongoing engineering evaluations to address station conformance to the Support design basis continued to result in emergent work and an associated increase in station dose. ALARA controls for these activities were good.
53 11/7/1997 Negative IR 97019 NRC Plant 1C 2A Implementation of the license's radiological respiratory control program Support was acceptable. Deficiencies in the respiratory protection training program were identified along with problems in the quality of the semi-annual surveillance checks of stored respirators. (Respiratory protection training lesson plans were of sufficient depth and scope to provide L
workers the necessary information to safety use this equipment.
However, the inspectors identified that trainees were not fully advised when they may seek relief during respiratory use. Inspectors also found several full face respirators in poor condition including one with a deteriorated valve gasket and another with a wom facial seal surface in the Turbine Building storage area.) Some examples of minor procedural deficiencies and the need for additional procedural guidance were also identified. (For example, one procedure did not provide clear direction for the frequency of medical re-evaluations for respirator users.) Other/NA 54 11/7/1997 Positive IR 97019 NRC Plant 2B 3A Implementation of the calibration and routine surveillance programs for Support the whole body contamination and small article monitors were good.
Monitor alarms were set at appropriate levels and acceptable instrument sensitivity and alarm operability was demonstrated. Worker compliance with monitor use requirements was good. Involved Management 1
55 11/7/1997 Positive IR 97019 NRC Plant 3A 1C Radiological controls and radworker performance were observed to be Support generally good during plant walkdowns of the turbine and reactor buildings. One instance involving a prob!em with contamination control was observed when a station laborer, while not wearing gloves, grasped the bottom of a mop and removed it from the handle prior to storage.
Teamwork / Skill Level 56 11/6/1997 Negative IR 97019 NRC Plant SA The radiation protection staff failed to inititate a problem identification Suppcii form after higher than expected dose rates were encountered while removing an IRM which prompted stoppage of the job and evacuation of the undervessel area.
Page 9 of 11 t
=
PLANT ISSUES MATRIX 1 /20/19M LaSalle Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colurnn = *SALP' ; SALP Area = " Plant Support' : Beginning Data = *10/1/1997* : Ending Date = *10r DATE TYPE SOURCE ID BY SALP SMM CODECII DESCRIPTION 57 11/6/1997 Positive IR 97019 NRC Plant SA 1C The ALARA planning and controls for removal of the intermediate range Support monitors / source range monitors (IRMs/SRMs) were good, with improvement noted in worker participation in the planning process. The root cause of a previous 1996 violation (failure to adequately determine the detectors' irradiation history) was effectively addressed.
58 10/31/1997 NCV IR 97016 Licensee Plant 3C SC The licensee did not have a procedure to ensure prescription eyewear Supoort was available for use with emergency breathing apparatus by licensed operators with a license condition requiring use of corrective eyewear when performing licensed duties.
59 10/31/1997 Positive IR 97016 NRC Plant SC 1C The licenseo also incorporated lessons leamed from previous Support maintenance activities into work planning and decontaminated the Division 11 RHR pump room. This improvement increased the licensee's ability to perform maintenance more efficiently.
l Page 10 of 11 l
~
- - - ~__
11/20/1988 GENERAL DESCRIPTION OF PIM TAILE LACELS A counter number used for NRC int; mal editing.
5 DME The date of the event or significant issue. For those items that have a clear date of occurrence use the actual date. If the actuci date is not known, use the date the issue was identified. For issues that do not have an actual date or a date of identification, use the LER or inspection report date.
TYPE The categorization of the issue - see the TYPE ITEM CODE table.
SOURCE The document that contains the issue information: IR for NRC Inspection Report or LER for Licensee Event Report.
ID BY Identification of who discovered the issue - see table.
SALP SALP Functional Area Ccdes - Engineering, Maintenance, Operations, Plant Support and All/ Multiple (i.e., more than one SALP area affected).
SMM CODES Senior Manager Meetiag Codes - see table.
DESCRIPTION Details of the issue from the LER text or from the IR Executive Summaries.
TYPE ITEM CODE NOTES SENIOR MANAGEMENT MEETING CODES DEV Deviation from NRC Requirements
- Eels are apparent violations of NRC 1
Operational Performance:
ED Escalated Discretion - No Civil Penalty requirements that are being considered for A - Normal eel
- Escalated Enforcement issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC with the " General Statement of Policy and C - Programs and Processes Procedure for NRC Enforcement Action" Licensing Licensing issue from NRR (Enforceraent Policy). NUREG-1600.
2 Material Condition:
Misc Misce!!aneous (Emergency Preparedness Finding. etc.)
However, the NRC has not reached its final A - Equipment Condition NCV Non-Cited Violation enforcement decision on the issues B - Programs and Processes Negative Individual Poor Licensee Performance identified by the Eels and the PIM entries 3
Human Performance:
Positive Individual Good Licensee Performance may be modified when the final decisions A - Work Performance Strength Overall Strong Licensee Performance am mah Befog,the NRC makes its B - Knowledge, Skills, and Abilities enforcement decision, the licensee will be C - Work Environment URl" Unresolved inspection item provided with an opportunity to either VIO/SL-1 Notice of Violation - Severity Level I (1) respond to the apparent violation or 4
Engineering / Design:
VIO/SL-il Notice of Violation - Severity Level 11 (2) request a predecisional enforcement A - Design VIO/SL-Ill Notice of Violation - Severity Level 111 conference.
B - Engineering Support VIO/SL-IV Notice of Violation - Severity Level IV
- URis are unresolved items about which C - Programs and Processes Weakness Overall Weak Licensee Performance 5
Pr blem Identincation and Resolution:
e h e
e sa acceptable item, a deviation, a ID BY nenconf rmance, or a violatio i. However, B - AnaI sis Y
the MRC has not reached its final C - Resolution Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entries may be modified when the final Self-R.vealed Identification by an event (e.g., equipment breakdown) conclusions are made.
Other identification unknown Page 11 of 11
.