ML20199A576
| ML20199A576 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/29/1998 |
| From: | Graves D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Randolph G UNION ELECTRIC CO. |
| References | |
| NUDOCS 9901130067 | |
| Download: ML20199A576 (16) | |
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,r'g-UNITED STATES NUCLEAR REGULATORY COMMISSION
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Garry L. Randolph, Vice President and L Chief Nuclear Officer .
Union Electric Company.
P.O. Box 620 Fulton, Missouri 65251
SUBJECT:
INSPECTION PLANNING REVIEW (IPR)- CALLAWAY PLANT
Dear Mr. Randolph:
~ On December 2,1998, the NRC staff completed a unique inspection Planning Review (IPR) of Callaway Plant. The staff normally conducts Semiannual Plant Performance Reviews for all i operating nuclear power plants to develop an integrated understanding of safety performance
- and adjust inspectiot resources. However, due to the suspension of the Systematic
- Assessment of Lice' 'e Performance process, we implemented an abbreviated inspection Planning Review ft ant issues and to develop inspection plans. The IPR for Callaway Plant
' involved the particim.. ion of both the Reactor Projects and the Reactor Safety divisions in evaluating inspecho results and safety performance trends for the period April 23 to October 28,1998.
Based on this review, inspection resources have been prioritized and scheduled. in addition to core inspections, a Temporary Instruction, Tl 2515/140, " Periodic Verification of Design Basis Capability of Safety-Related Motor Operated Valves," will be conducted at your facility.
Enclosure 1 contains an historical listing of plant issues, referred to as the Plant issues l I
l Matrix (PIM),That was considered during this IPR process to arrive at an integrated view of licensee performance trends. The PIM includes only items from inspection reports and other docketed correspondence between the NRC and Union Electric Company. The IPR may also
- have considered some predecisional and draft material that does not appear in the attached PIM,-including observations from events and inspections that had occurred since the last NRC f inspection report was issued, but had not yet received full review and consideration. /
Enclosure 2 is a general description of the PIM table labels. This material will be placed in the NRC Public Document Room. [ ]
Thic !ctter !ce 31iccc you of Our pMnimd inspeciion effort resulting from the Callaway Plant IPR. It 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.
' Enclosure 3 details our inspection plan for Callaway Plant over the next 8 months. The l rationale or basis for each inspection outside the core inspection program is provided so that you arc aware of the reason for emphasis in these program areas. Resident inspections are
- not listed because of their ongoing and continuous nature. We willinform you of any changes to the inspection plan.
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l 9901130067 981229
-PDR '
ADOCK 05000483
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- Union Electric Company ;
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If you have any questions, please contact me at (817) 860-8148.
Sincerely, h
.D id N. Graves, Acting Chief -
Project Branch B ,
Division of Reactor Projects Docket No. 50-483 License No. NPF-30
Enclosures:
)
- 1. Plant issues Matrix
- 2. General Description of PIM Table Labels:
- 3. Inspection Plan cc w/ enclosures:- J Professional Nuclear Consulting, Inc. :
19041 Raines Drive :
Derwood, Maryland 20855 John O'Neill, Esq.
1Shaw, Pittman, Potts & Trowbridge i 2
2300 N. Street,'N.W.
Washington, D.C. 20037 H. D. Bono, Supervising Engineer l Quality Assurance Regulatory Support
- Union Electric Company P.O. Box 620 Fulton, Missouri 65251 Manager - Electric Department Missouri Public Service Commission 301 W. High P.O. Box 360 Jefferson City, Missouri 65102
- . Ronald A. Kucera, Deputy Director l- Department of Natural Resources
, . P.O.~ Box 176
' Jefferson City, Missouri 65102 4
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Union Electric Company Otto L. Maynard, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411
. Burlington, Kansas 66839 Dan 1. Bolef, President Kay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, Missouri 63130 Lee Fritz, Presiding Commissioner Callaway County Court House 10 East Fifth Street Fulton, Missouri 65151 Alan C. Passwater, Manager Licensing and Fuels
' AmerenUE One Ameren Plaza 1901 Chouteau Avenue P.O. Box 66149 St. Louis, Missouri 63166-6149 .
J. V. Laux, Manager Quality Assurance Union Electric Company P.O. Box 620 Fulton, Missouri 65251 Jerry Uhtmann, Director State Emergency Management Agency P.O. Box 116
' Jefferson City, Missouri 65101
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- E-Mail report to T. Frye (TJF) .
- E-Mail report to D. Lange (DJL)'-
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. Project Engineer (DRP/B) ' RIV File :
Branch Chief (DRP/TSS) Carol Gordon ]
Records Center, INPO 1 The Chairman (MS: 16-G-15) '
Deputy Regional Administrator C. A. Hackney, RSLO i Commissioner Dicus . B. Henderson, PAO i x Commissioner Diaz. B. Murray, DRS/PSB Commissioner McGaffigan . SRis at all RIV sites
. Commissioner Merrifield :
W. D. Travers, EDO (MS: 17-G-21) I L . Associate Dir. for Projects,'NRR . !
- l. Associate Dir. for insp., and Tech. Assmt, NRR .!
[ - M. Gray, NRR Project Manager (MS: 113-E-16) i i
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Union Electric Company DEC 2 91998
- E-Mail report to T. Frye (TJF)
. E-Mail report to D. Lange (DJL)
- E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK) ,
' E-Mail report to Richard Correia (RPC) -
l E-Mail report to Frank Talbot (FXT) j I
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bec distrib. by RIV: i Regional Administrator Resident inspector i i DRP Director DRS-PSB Branch Chief (Drip /B) MIS System i Project Engincer (DRP/B) RIV File Branch Chief (DRP/TSS) Carol Gordon The Chairman (MS: 16-G-15) Records Center, INPO Deputy Regional Administrator _ C. A. Hackney, RSLO Commissioner Dicus . B. Henderson, PAO Commissioner Diaz B. Murray, DRS/PSB Commissioner McGaffigan SRis at all RIV sites
- Commissioner Merrifield
- W. D. Travers, EDO (MS: 17-G-21)
Associate Dir for Projects, NRR Associate Dir. for Insp., and Tech. Assmt, NRR ,
SALP Program Manager, NRR/lLPB (2 copies)
W. H. Bateman, NRR Project Director (MS: 13-E-16)
M. Gray, NRR Project Manager (MS: 13-E-16)
DOCUMENTNAME: G:\DRPDIR\lPR\CWY
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ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 10/08/98 NCV IR 98-22 SELF OPS 1A in violation of Technical Specification 6.8.1.a. a reactor opnrator failed to properly implement the procedure for raising pressure in safety injection accumulator Tank C. As a result, the accumulator was inoperable for approximately 15 minutes. The licensee discussed the event with the operator, identified procedure and labeling enhancements and proposed additional corrective actions. This nonrepetitive, licensee-identified and corrected violation is being treated as a noncited violation. consistent with Section Vit.B.1 of the NRC Enforcement Policy.
09/26/98 POS 1R 98-21 NRC OPS 1A 1B Operator response to an equipment failure, which caused a pressure transient and damaged valves in the boron thermal regeneration system, and the subsequent reduction of volume control tank level was good. Operators quickly diagnosed the event and took actions which minimized the loss of water from the chemical and volume control system. The licensee successfully repaired the damaged valves and restored the system to service.
09/26/98 POS tR 98-21 NRC OPS 1A 1B Control room operator response to the loss of main feedwater pump automatic speed control was very good.
The operators quickly recognized the condition and took manual control of the main feedwater pumps. Operators quickly restored steam generator water level to the programmed band.
09/04/98 POS IR 98-20 NRC OPS SA SB SC Condrtions adverse to quality were generally being appropriately identified, evaluated and corrected .
09/04/98 NEG 1R 98-20 NRC OPS 1A SC The occurrence of mispositioned components, however, continued to be a problem for which the corrective action process had not been effective. Because of the continuing identification of tagging errors, corrective actions for workman's protection assurance performance deficiencies had not improved performance in this area.
08/15/98 NCV IR 98-12 LIC OPS 1C in violation of Technical Specification 6.8.1.a, the licensee failed to establish a procedure requirement to isolate the reactor water makeup system during natural circulation shutdown as a result of incomplete procedure reviews for an intemal commitment. The licensee took corrective actions to address this issue. This violation was treated as a noncited violation in accordance with Section Vll.B.1 of the NRC Enforcement Policy.
07/22/98 NEG IR 98-12 NRC OPS 1C 3B On July 22.1998, the temperature of the ultimate heat sink pond approached the Technical Specification limit of 90*F. Operator knowledge of procedure steps associated with ultimate heat sink pond operating temperature limits was weak. Equipment operator logs had conflicting guidance between temperature limits stated in the logs and the normal operating procedure.
07/04/98 POS IR 98-11 NRC OPS 1A Control room decorum and professionalism were well-maintained. Distractions were minimized. Operators displayed proper communications. Control room togs were property maintained. Shift briefings appropriately covered upcoming events and evolutions.
05/23/98 POS IR 98-08 NRC OPS 1A The licensee effectively prepared for and implemented mid!oop operation during Refueling Outage 9.
October 28,1998 1 Callaway Plant
ENCLOSURE 1-
- PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM
, , CODE 05/23/98 URI 1R 98-08 NRC OPS 1C 3C An unresolved item was identified regarding inconsistencies between the Final Safety Analysis Report and the Emergency Operating Procedures describing the procedure and steps to transfer the suction of the emergency core cooling systems and the containment spray system from the refueling water storage tank to the containment recirculation sump following a loss of coolant accident.
05/23/98 POS 1R 98-08 NRC OPS 1A The licensee's communications, command and control, and cross-checking were thorough during fuel movement in Refueling Outage 9. The licensee effectively implemented foreign material exclusion controls around the refuel and spent fuel pools.
04/30/98 NCV IR 98-21 LIC OPS 1A 1B in violation of Technical Specification 3.0.4, the licensee failed to ensure operability of the turbine-driven auxiliary LER 98- feedwater pump prior to entering Mode 3. This occurred as a result of a deficient Mode 4 to Mode 3 checklist.
005 The licensee revised the checklist to ensure the system was in the proper lineup for plant startup. This was a noncited violation.
04/19198 POS IR 98-08 LIC OPS 3A Control room operators demonstrated attentiveness to plant parameters by immediately recognizing and responding to an inadvertent transfer of water to the chemical and volume control system from the refueling cavity.
04/11/98 POS 1R 98-03 NRC OPS 1A 1C The licensee's preparations for entering mid-loop operation were good. The licensee complied with the recommended actions in NRC Generic Letter 88-17,' Loss of Decay Heat Removal" The licensee's preparations appropriately addressed shutdown risk, time to boil calculations, decay heat removal system availability, electrical p aver, reactor coolant system water level and temperature indications, and containment closure.
04/04/98 POS 1R 98-03 NRC OPS 1A Control room communications, briefings, supervisory control, and self-checking were very good during the plant shutdown and cooldown in preparation for Refueling Outage 9.
02/18/98 NEG IR 98-01 SELF OPS 1A 2B 3A An equipment operator opened an incorrect breaker to a nonsafety-related motor control center while hanging tags. The operator immediately reclosed the breaker without prior control room authorization. The failure to open the correct breaker was due to personnel error. The immediate re-closing of the breaker was a poor practice. The control room operators' response to this event was good.
01/21/98 POS 1R 98-01 NRC OPS 5B SC The licensee exhibited the proper enforcement perspective when responding to the simultaneous inoperability of auxiliary / fuel building emergency exhaust system fi!!er adsorber Unit B and Emergency Diesel Generator A. The licensee requested and received a Notice of Enforcement Discretion. This item was the subject of a special inspection. See IR 50-483/9802.
01/17/98 POS IR 97-21 NRC OPS SA An operations department self-assessment report had good observations, conclusions, and recommendations.
01/15/98 NCV IR 98-03 LIC OPS 1A 1C Licensee Event Report 98-002 repohed the failure to maintain the position of the reactor building equipment LER 98 hatch missile shield within the design basis during past refueling outages. This violation was not cited, consistent 002 with Sechon VII.B.1 of the NRC Enforcement Policy.
October 28,1998 2 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 12/06/97 NEG 1R 97-20 SELF OPS 1A 2A 3A An equipment operator exhibited poor work practice and damaged an essential service water motor-operated valve actuator. The operator used a wrench on the handwheel in an attempt to manually open the valve. The valve was already open.
12/06/97 POS IR 97-20 NRC OPS 1A 2B 3A Operators maintained a heightened state of awareness to plant parameters during remodeling of the control room. There was minimal impact on shift crews during the remodeling. The work was performed when the on-line maintenance risk was low.
10/25/97 POS IR 97-17 NRC OPS 1A 3A Contro! room operator shift turnovers and briefings were good.
10/21/98 POS 1R 98-22 LIC MAINT 2A 4C Overall, observed material condition and housekeeping were very good. The licensee corrected a material condition concem regarding high temperature on a main transformer bushing. No significant material condition concems arose during the plant power reduction and subsequent increase. The licensee also idenhfied a material condition deficiency regarding degradation of essential service water Pump A and initiated appropriate corrective actions.
10/02/98 POS IR 98-18 NRC MAINT 2B Material condition of the essentiai service water system was good. System walkdowns combined with a review '
of Suggestion / Occurrence / Solution Reports, Maintenance Rule reports, and system health reports indicated that the essential service water system was in good material condition.
08/15/98 POS IR 98-12 NRC MAINT 2B The Predictive Program Summary report provided a useful tool for licensee personnel to summarize predictive program results. Certain equipment problems were discussed; the licensee has either resolved the problems or defined a clear path to resolution. There were no operability or safety concerns.
08/15/98 POS IR 98-12 NRC MAINT 2A 28 Material condition was good based on the work backlog and plant tours. There were only 63 outstanding nonoutage corrective maintenance work requests. This was an improvement from the approximate 400 nonoutage corrective maintenance work requests that existed in early 1995. A small number of minor oil and water leaks were evident. The leaks were previously identified by the licensee and were included in the licensee's maintenance program.
08/15/98 NEG IR 98-12 NRC MAINT 3A 3C Maintenance and health physics planning for an at-power reactor building entry was weak. There was confusion conceming the appropriate measures to minimize heat stress, and one person required assistance to leave the reactor building. Personnel did not know the exact location of equipment which contributed to longer stay times.
The work scope for the entry had increased; however, planning and coordination were not thorough.
Maintenance personnel were unsure of the sequence of work to be performed and how health physics coverage was to be provided. The licensee conducted a thorough critique and identified a number of suitable corrective actions.
07/10/98 NEG IR 98-15 NRC MAINT 4C With some exceptions, the resolution of circuit breaker issues expressed in NRC generic communications, industry operating experience reports, and vendor letters was marginal. Seven service advice letters and two information notices were incorrectly reviewed for plant applicability.
October 28,1998 3 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 07/10/98 NEG IR 98-15 NRC MAINT 3C Procedures and communication paths for informing the licensee's staff about operating experience and vendor-supplied information were not appear consistently applied. The team determined that this shortcoming was conducive to less than optimum coordination, duplication of effort for communications dealing with the same subject but from different sources, and an obstacle for important information to reach the appropriate or cognizant staff.
07/10e38 POS 1R 98-15 NRC MAINT 2A The switchgear and surrounding areas were in good visual material condition with no deficiencies identified.
07/10/98 NEG 1R 98-15 NRC MAINT 3A The calculation of direct current control circuits
- voltage drop lacked the normal rigor involving design inputs for safety-related calculations. The team was assured by a preliminary calculation that all equipment associated with the breaker close and trip circuits would have voltage above the required minimur i-allowed voltage.
07/10/98 POS IR 98-15 NRC MAINT 4C The licensee's functional determination of the safety-related GE Magne-Blast breakers was acceptable; however, breakers were overdue for overhaul or refurbishment. The licensee's action plans for overhauling and upgrading safety-related breakers were adequate and deviations from vendor recommendations were adequately justified.
The licensee's preventive maintenance for Magne-Blast breakers was generally acceptable.
07/04/98 POS IR 98-11 NRC MAINT 2A 28 Material condition was good. The percentage of the total power generation for Cycle 9 that was lost due to maintenance-related causes was about 1 percent. This was below the licensee's goal of 2 percent and below the industry median for plants in the United States. The licensee operated the plant with a " black board" in the control room during most of the current inspection report period.
05/02/98 NCV IR 98-21 LIC MAINT 2B 48 in violation of Technical Specification 3.2.5, the licensee failed to calibrate the feedwater temperature detectors LER 98 used to calculate reactor coolant system flow rate. The licensee determined that personnel misinterpreted the 004 associated surveillance procedure. The licensee revised the procedure to ensure the calibration would be performed within the required time frame. The licensee determined that past ilow rate calculations were acceptable because conservahve calibration uncertainties were already included in the surveillance procedure.
This was a noncited violation.
04/30/98 POS IR 98-09 NRC MAINT 2B The procedures and records for inservice inspections, examiner qualifications, and repair and replacement of ASME Code Class 1,2, and 3 components that the inspector reviewed were good, and indicated that the inservice inspection program was being appropriately implemented.
04/19/98 VIO IR 98-08 SELF MAINT 1A An inadvertent transfer of 600 gallons of refueling cavity water to the chemical and volume control system was SLIV due to personnel error. Workman's protection assurance tagging was inadequate. Licensee personnel failed to follow the requirements of procedure APA-ZZ-0310.
04/17/98 POS la 98-05 NRC MAINT 28 3B 5A Refueling Outage RF9 eddy current examination acquisition and analysis activities appeared effectively controlled, with good overall contractor performance noted.
October 28,1998 4 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID WA TEMPLATE ITEM CODE 03/03/98 POS IR 98-02 NRC MAINT 4B 4C The licensee's prucess for implementing Technical Specification amendments was well-defi cHj and thorough, although the licensee's failure to maintain all records associated with one license amendment package was identified.
03/03/98 VIO IR 98-02 NRC MAINT 2B 4B 4C The licensee failed to demonstrate during the 30-day implementation period of Technical Specification SLIV LEP 98 Amendment 118 that either train of the auxiliary!!uel building emergency fi!!er system adsorber would meet the ED 001 new requirements of Technical Specification 4.7.7.b.2. The licensee believed they did not have to demonstrate compliance with the requirements of Technical Specification Amendment 118 during the implementation perie1 because they had satisfactory test results using prior test acceptance criteria. This reasoning was incorrect and resulted in the licensee not recognizing that both trains of the emergency exhaust system were inoperable when enforcement discretion was requested. As a result, an incomplete notice of enforcement discrv. ion was requested by the licensee and granted by the NRC.
01!17/98 LIK IR 97-21 NRC MAINT 2A 5A Overall, the plant material condition was good. However, there were weaknesses in the licensee's identification of emergent material condition deficiencies. The inspectors identified four examples of material deficiencies that were not identified by licensee per:;onnel during tours.
01/17/98 POS IR 97-21 NRC MAINT SA A maintenance departme it self-assessment was thorough. The assessment team identified strengths and opportunities for improvement.
12/17/97 LER LER 97- LIC MAINT 28 Licensee eng;neers determined that the surveillance test of safety related logic circuits did not provide circuit 005 overlap ve6fication of the P-11 permissive circuit. P-11 reinstates the safety injection function on low pressurizer or main steam line pressure on pressure increases, and allows blocking of the safety injection function when decreasing RCS pressure. LER was revised on 8/22/97 to include identi*ation of incomplete circuit testing of the main steam isolation valve bypass valves. LER was revised on 10/1/C to include identification of the failure to completely test load shedder and emergency load sequencing contacts that inhibit the non-sequenced buto-start signals of several safety-related pumps during surseillance testing. LER was revised again on 10/17/97 to incorporate two additional surveillance testing deficiencies. The LER was revised on 11/10/97 to incorporate contacts in the emergency diesel generator trip bypass circuitry that had not been previously adequately tested.
LER was revised on 12/19/97 to include identification of additional deficiencies in completeness of surveillance testing. The LER was revised on 1/15/98 to include the identification of additional deficiencias regarding insufficient overlap betweeen test procedures.
12/06/97 NCV IR 97-20 LIC MAINT 2B Licensee Event Report 50-483/97-002 reported that containment isolation valves in the containment hydrogen LER 97- control sy tem were not properly tested in accordance with Technical Specification 4.6.3.1. This item was 002 identifieo oy the licensee on 3/17/97.
11/18/97 NCV 1R 98-01 LIC MAINT 2B Certain portions of logic circuits in the solid state protedion system were not being adequately tested by LER 97- procedures. The circuits included the source range automatic P-10 block, feedwater isolation on P-14 steam 010 generator hi-hi level, and feedwater isolation on a safety injection signal The cause was determined to be inadequate vendor information regarding testing methodology.
October 28,1998 5 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 10/29/D7 VIO iR 97-20 NRC h'AINT 28 3A A preventive maintenance test on Emergency Diesel Generator A was not property controlled. A d:fferential SLIV LER 97- pressure gauge remained installed after the test was compiete.
011 10/14/97 NCV IR 98-08 LIC MAINT 2A The licensee failed to vent the safety-related centrifugal charging pumps, as a result of misinterpretation of LER 97 Technical Specification requirements. The licensee took corrective actions to address this issue; therefore, a 009 noncited violation was issued, as allowed by Section Vll.B.1 of the Enforcement Policy.
10/12/97 VIO IR 97-17 SELF MAINT 2B 3A Control room operators performed a slave relay test procedure for the auxiliary / fuel building emergency exhaust SLIV ventilation system Train B out-of-sequence and resulted in tripping the fan breaker.
10/02/98 VIO IR 98-18 NRC ENG 4A The load flow voltage drop calculation was not checked properly and included an incorrect assumption. >
SLIV Emergency diesel generator load growth was not properly monitored and evaluated as required by procedure.
These failures to follow design control pocedures were determined to be a violation of 10 CFR Part 50, Appendix B, Criterion V, " Procedures, Instructions and Drawings." No response is required for this violation.
10/02/98 STR 1R 98-18 NRC ENG 4A Procedurai guidance was in place to ensure that changes to the plant were properly evaluated in accordance with
'.he requirements of 10 CFR 50.59, " Changes. Tests and Experiments," and to appropriately update the Final Safety Analysis Report. The safety evaluations reviewed were well documented and properly concluded that no unreviewed safety questions existed.
10/02/98 NCV 1R 98-18 LIC ENG 4B The failure to test the pressurizer safety valve balancing devices in accordance with Technical Specification 4.0.5 i LER 98- is a violation. This nonrepetitive, licensee-identified and corrected violation is being treated as a noncited 007 violation consistent with Section Vll.B.1 of the NRC Enforcement Policy .
10/02/98 STR IR 98-18 NRC ENG 4A The team concluded that effective procedural controls were in place to ensure that affected calculations were reconciled when new or revised calculations were generated.
10/02/98 URI 1R 98-18 NRC ENG 4A One unresolved item was identified concerning design changes made to bypass torque switches, originally installed M safety-related mote %perated valve control circuits to prevent overtorque dunng valve closure. The licensee committed to perform additional review to confirm the adequacy of their current design.
10/02/98 VIO IR 98-18 NRC ENG 4A The failure to provide adequate procedures for operations logging practices and failure to prescribe preventive 3L IV maintenance instructions for switchyard voltage indicators, which were needed to assure operation in an analyzed condition, resulted in multiple failures to evaluate potentially inoperable offsite power supplies. These fadures to provide adequate procedures were determined to be a violation of Technical Specification 6.8.1. No response is required for this violation.
October 28,1998 s Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 10/02/98 STR 1R 98-18 NRC ENG 4A The design and testing of the essential service water system were consistent with applicable licensing, design, and operations documents. While, the licensee had not initially established a clear analytical basis for system operability with a degraded pump, testing practices were aggressive and the licensee had proactively scheduled pump replacement as needed. Subsequent analysis confirmed that the as-found design was acceptable over the full range of allowed pump degradation.
09/26/98 NEG IR 98-21 NRC ENG 4C The licensee failed to revise three component cooling water system valve surveillance procedures and to make associated revisions to the work control process in a timely manner following implementation of Technical Specification Amendment 113.
07/04/98 POS IR 98-11 NRC ENG 4B The inspectors concluded that the formal safety evaluation for the continuous addition of ammonia hydroxide to the reactor coolant system was comprehensive. Plant and precedure changes discussed in the evaluation were implemented. The licensee followed the modification process when actions were initiated to improve the continuous addition pump's design fo!!owing implementation of the modification.
05/23/98 POS IR 98-08 NRC ENG 4B Plant modifications were well designed and property implemented. The modifications included installing a new essential service water pump, replacing essential service water valves, modifying the containment recirculation sump valves, and modifying the main feedwater regulating and bypass valves.
05/20/98 LIC NRR NRC ENG 4C Weak licensee performance identified regarding Electrosfeeve Tech Spec Amendment request submittals. NRC WK Letter letter dated 5/20/98 assessed licensee performance as follows: " Based on our review of various submittals . the staff has some concerns with the completeness, technical adequacy and accuracy of these submittals. Several of your submittals were incomplete in that they either neglected to answer questions raised in a RAI, or they indicated that information was not yet developed and therefore was not submitted. Yet in both cases, the questions raised and information requested were not provided to the staff at a later time, unti! formally requested a second time by the staff. In addition, some of the technical responses to issues raised in RAls were technically inadequate, mainly with respect to nondestructive examination issues. In some cases, regulatory requirements were not addressed and in other cases the technical basis provided to address technical issues was inadequate.
Lastly, questions have been raised by the staff regarding the quality of the electrositseve vendor's and your quality assurance review of submittals made to the sta#. The staff has identified several examples, two of which were documented in the staff's December 18,1997, RAI, of inaccurate data being supplied to the staff in electrosleeve submittals. Union Electric's performance in tnis regard must be improved, or the staff will not be able to continue its review of the electrosleeving application."
05/13/98 LIC NRR NRC ENG 4C Negative performc.nce related to Technical Specification Amendment request dated August 8,1997 and followup NEG Letter ;etters. Amendment requested that tolerance on Main Steam Safety Valves be increased from +1%/-1% to +3%/-
1%. In docketed letter to the licensee dated May 13,1998. NRC staff stated " Union Electric did not account for the test uncertainty in its safety analysis, and did not provide the staff with an adequate regulatory basis to allow excluding the test instrument uncertainty."
October 28,1998 7 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM
, CODE 04/17/98 POS IR 98-05 !!RC ENG 2B 5A The use of the plus point probe was viewed as an indicator of management support for examination initiatives that would provide for early detection of degradation.
04/17/98 POS IR 98-05 NRC ENG SC The licensee appropriately responded to areas of weakness in the eddy curren' data analysis guidelines that were identified during a prior NRC inspection.
04/11/98 NCV IR 98-03 LIC ENG 2B 4B SC The licensee's review of 7162 preventive maintenance tasks for impact on equipment operability was extensive POS and thorough. The licensee identified 18 tasks that did not receive required formal safety evaluations. The licensee revised the tasks to eliminate the need to perform the evaluations. This violation was not cited, consistent with Section Vll.B.1 cf the NRC Enforcement Policy.
02/16/98 VIO IR 98-01 SELF ENG 2B 4A 48 Engineering department personnel failed to prepare an adequate modification package for a core drillin an SLIV auxiliary building concrete wall. During performance of the work, licensee personnel drilled into a 13.8 kV cable.
There was no personnel irjury. There was no significant impact on plant operation. The cable's protective devices tripped the supply brealeer. The licensee's investigation and proposed corrective actions were good.
12/18/97 NEG Letter NRC ENG 4C Negative performance noted in that the licensee approved and provided poor quality subm.ttal to the statt. NRC letter requesting additionalinformation dated 02/18/97 identifies quality deficiencies as follows: "Two examples of incorrect data being supplied to the NRC staff were recently identified. The NRC staff identified errors in Table 1.2 of the September 10,1997 submittal. In addition, the licensee notified NRC staff in the September 10,1997 submittal that some data previously submitted to NRC staff was incorrect."
12/11/97 NEG IR 97-19 NRC ENG 3B 4B A weakness was identified with respect to certain engineering staff knowledge of rod swap methodology 12/11/97 POS IR 97-19 NRC ENG 4B The actions taken in response to the axial offset anomaly were conservative and in accordance with regulatory requirements.
12/06/97 STR 1R 97-20 NRC ENG 1A 3A 4B Modifications to the unit vent flow transmitter, the emergency diesel generator lube oil and jacket water temperature control valves, and the control room were generally well-planned and executad. The unit vent flow transmitter modification corrected a longstanding operator workaround.
10/25/97 POS IR 97-17 NRC ENG 4B The licensee's evaluation of the impact of changing the control rod insertion 1 mits was thorough.
10/15/98 POS IR 98-23 NRC PS 1C 3B 3C The process for augmenting the emergency response organization was significantly improved by issuing pagers 1 to all emergency response personnel.
10/15/98 NEG IR 98-23 NRC PS 1C 3C Drill frequencies were not clearly described in the emergency plan and implementing procedures.
10/15/98 STR 1R 98-23 NRC PS 1C 3B 3C Management has increased its support of the emergency preparedness training program by increasing the number of training drills. Program visibility and credibility have improved.
10/15/98 POS 1R 98-23 LIC PS 1C 5A The emergency preparedness dri!! program was unstructured and poony contro!!ed and documented in the past; however, program shortcomings were recognized and appropriate improvements were planned or in progress.
October 28,1998 8 Callaway Plant
ENCLOSURE 1 PLANTISSUES MATRIX
. CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 09/18/98 POS IR 98-19 NRC PS 1A 1C in general, an effective ALARA program was implemented. The 1998 exposure goal of 15 person-rem was aggressive and on targot. However, the ALARA coordinator had not fo!! owed the procedural requirements for the review of 120 of the 147 ALARA suggestions submitted in 1998. The station's 3-year exposure average of 149 person-rem for 1997 was a little above the industry average; however, it has continuM to trend downward.
09/18/98 NEG 1R 98-19 NRC PS 1C 2B The radiation protection audit and surveillance activities had not reviewed 18 of 59 radiation protection program elements in more than 25 months with the average time interval between reviews of approximately 41 months.
09/18/98 STR iR 98-19 NRC PS 1C in general, the extemaUintemal encsure control programs were effectively implemented. All radiation areas were properly posted. Proper thermoluminescent dosimeters were used for measuring neutron doses. Respiratory equipment was properly issued to qualified personnel Radioactive material, laundry, and trash containers were properly labeled, posied, and controlled. A good radioactive source inventory and leak test program was in place; however, source inventory results were not consistently record 0d. An effective portable radiation survey instrument calibration program was maintained. Radiological surveys property assessed personnel exposures.
09/18/98 POS IR 98-19 NRC PS 1C 2B Two operational radiation protection quality assurance surveillances were completed since May 1998, which provided management viith a good assessment of the areas reviewed. Overall, an adequate quality assurance audit program was maintained. No negative trends were identified during the review of radioiogical suggestion occurrence solution reports written since May 1998.
09/18/98 STR 1R 98-19 NRC PS 1C Housekeeping throughout the radiological controlled area was very good.
08/07/98 POS IR 98-17 NRC PS 1A 38 A strong solid radwaste and transportation training program was maintained. The instructor assigned to provide initial and contJing solid radwaste and transportation training had an extcasive practical and technical background in the above program areas. Lesson plans were organized, well written, and piant management was appropriately involved in the development and review of the plans.
08/07/98 POS 1R 98-17 NRC PS 1C Housele^ ping in the radwaste building was very good 08/07/98 STR 1R 98-17 NRC PS 1A 1C Overad, a good solid radioactive waste management program was in place. The licensee's radwaste minimization program was e'fectively imptomented. Since 1994, the total annual volume of solid radioactive waste generated has been reduced by approximr.tely 63 percent. A very good transportation progrun for radioactive waste and materials was maintained. Shipping documentation was crganized, easily retrievablo, and packages vere property prepared for shipment 08/07/98 POS IR 98-17 NRC PS SA An effective quality assurance program was in place. The biennial audit, when combined with survei!!ance reports, provided management with a good assessment of the solid radwaste and transportation programs. The licensee property assessed and captured recommendations from the departmen'self-assessment. No negativo trends were identified during the review of solid radwaste and transportation suggestion occurrence solution reports.
October 28,1998 9 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 08/04/98 VIO 1R 98-17 NRC PS 1A 3A A violation of 10 CFR 71.111 was identified because dry active waste was stored within 10 feet of a permanent SLIV structure contrary to procedural requirements. The procedural requirement was in place to address potential fire protection concerns. No response to this violation is required.
7/17/98 STR IR 98-16 NRC PS IA 1C Overall, good radiological and meteorological monitoring programs were implemented. Meteorological data recovery was greater than 90 percent from 1995 through 1997. Environmental air sampling stations were mr* vd at a high standard for both cleanliness and reliability. Excellent sampling and handling practices were ust : collecting environmental air samples.
07/17/98 POS IR 98-13 NRC PS 1A 2B Quality assurance oversight was effective. Audits were intrusive and thorough, providing management with a good assessment of the radiological effluent centrols program. Audit findings were properly documented, tracked in the station's Suggestion Occurrence Solution Reporting System and closed in a timely manner. Qual:ty assurance department surveillance reports were well written and properly assessed the program areas reviewed.
Suggestion Occurrence Solution Reports identified issues at the proper threshold to provide management with the tools needed to assess the program.
07/17/98 POS 1R 98-13 NRC PS 1A 2B An effective training program was in-place for personnel responsible for the effluent moniotoring program. Initial and continuing training program course materials were weil organized, covering the subject areas needed to accomplish the required tasks and help ensure that the organization's technical competence was maintained.
'7/17/98 POS 1R 98-16 NRC PS 5A Quality assurance audits and surveillances were performed by qualified personnel and were very comprehensive and effectively evaluated the radiological environmental monitoring program.
07/17/98 POS IR 98-13 NRC PS 1A 2B Housekeeping in the areas where effluent monitors and air cleaning systems were locatad was very good.
07/17/98 STR 1R 98-13 NRC PS 18 28 Overall, a good radioactive effluent monitoring program was maintained. A decreasing trend was noted in the radioactivity released through liquid effluents during 1996 and 1997. A good effluent monitor calibration and channel check program was in-place. Instrumentation used for analyzing effluent samples was properly maintained and calibrated. The engineering safety feature air filtration and adsorbtion units were property maintained. Good in-place filter and loboratory testing programs were implemented. System engineers responsible for the engineering safety feature filter ventilation systems were knowledgeable of their systems and appropriately involved in the filter testing program.
07/08/98 NEG IR 98-12 NRC PS 3B A worker was unaware of radiological conditions near the pump suction line in residual heat removal pump room A. The worker failed to review the radiological survey data prior to entering the work area. This was an additional example of previously cited violation 50-483/98-07-02 and is not being cited separately. The licensee's corrective actions for the cited violation were incomplete at the time this current violation was identified. The licensee will include corrective actions to this event in conjunction with corrective actions for the previous violation.
07/04/98 POS IR 98-11 NRC PS 1C 3A The licensee effectively prepared for and implemented the process for shearing radwaste filters. The licensee i effectively implemented ALARA work practices. Personnel dose for the project was below the licenseo's goal.
October 28,1998 10 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 07/02/98 NEG IR 98-14 NRC PS 1C 2A SC The need to perform additional NRC review of backup emergency operations facility capabilities was identified because a radio base station to ccmmunicate with offsite field monitoring teams was not available at the backup facility. The absence of a radio base station was identified by the licensee in March 1998 but was not corrected until the issue surfaced dunng this inspection.
07/02/98 NEG lR 98-14 NRC PS 1B 5A 5B Documer 9 m was incomplete or unclear for two unusual events. The emergency preparedness department (tid not participate in the formal event review process; therefore, the events were not properly used to assess and improve emergency plan implementation. The corrective acCon program procedure was revised to include emergency preparedness department participation in future assessments for events that involve emergency plan implementation.
07/02/98 POS IR 98-14 NRC PS 1C 3C 28 Overall, implementation of the emergency preparedness program was generally good. Emergency response facilities were operationally maintained, and appropriate equipment and supplies were readily available at the primary facilities. The emergency preparedness training program was property implemented. Emergency preparedness department staffing and supervision had stabilized. A full-time superintendent was named, and staffing levels and assignments were well defined. There was enough depth in the emergency response organization to ensure continuous staffing.
07/02/98 WK lR 98-14 NRC PS 18 3C 3B The second crew did not classify one of three events in a timely manner because an emergency operating procedure conflicted with an emergency implementing procedure. The procedure for emergency operating procedure usage stated that ernergency action level determination commences after exiting the reactor trip procedure. The classification procedure required classification when abnormal readings indicate an emergency situation has occurred. The first crew did not have the same problem because it entered the reactor trip procedure later in the scanario. The delayed classification was identified as a performance weakness.
05/23/98 POS 1R 98-08 NRC PS 3A Health physics personnel provided thorough coverage of the containmen recirculation sump inspections and reactor vessel upper intemals re-installation. The licensee implemented effective radiological controls.
05/01/98 POS IR 98-07 NRC PS SA One radiation protection department self-assessment was performed since January 1997. The assessment provided a very good evaluation of the areas reviewed, and appropriate recommendations were ident'ied for program improvements.
05/01/98 VIO IR 98-07 NRC PS 1A A violation of Technical Specification 6.11 was identified for the failure to properly label 36 bags SLIV (container / packages) of radioactive material with the appropriate radiological information to permit individuals handling tr using the containers to take precautions to avoid or minimize their exposure.
05/01/98 NEG IR 98-07 NRC PS SA Quality assurance audit teams were not comprised of personnel with strong radiation protection backgrounds in the areas being audited. The audits covered the appropriate program areas; however, they did not provide an in-depth review of the areas audited.
05/01/98 VIO IR 98-07 NRC PS 1A A violation of Technical Specification 6.11 was identified for the failure to conspicuously post a High Radiation SLIV Area.
October 28,1998 11 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 05/01/98 STR 1R 98-07 NRC PS 1A 1C A very good ALARA program was implemented. Effective chemistry shutdown plans and controls were in place which reduced steam generator channel head dose rates about 27 percent. Station management demonstrated their support for the ALARA program by delayir g the start of the refueling outage by 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in an effort to decontaminate the reactor coolant system and s educe the general area dose rates. The outage exposure goal of 185 person-rem was established using past best performance and industry experience in conjenetion with appropriate involvement by activity coordinators and the outage rNiew board.
05/01/98 POS IR 98-07 NRC PS 1A in general, the external exposure controls program was effectively implemented. Danger (locked) High Radiation Areas were properly controlled and posted. Station workers knew the proper response to electronic dosimeter alarms. Housekeeping was very good throughout the radiological controlled area. An effective intemal exposure controls program was in place. Continuous air monitors and HEPA filter ventilation were appropriately used to monitor and limit airbome exposures. The intemal dose assessment program was effectively implemented.
Personnel contamination incidents and events were property handled, and radiation protection personnel stationed at the radiological controlled area exit provided appropriate guidance to station workers who alarmed the personnel contamination monitors. Good controls were in place to prevent the spread of radioactive contamination.
04/30/98 POS IR 98-10 NRC PS 1C 38 Emergency response organization personnel were trained as described in the licensee emergency plan and training procedure. The qualifications of each duty section will be reviewed p::or to it assuming interim duty responsibilities. 3e training program will be enhanced by clarifying the process for use of drills / exercises for qualification purposes and by establishing controls over course content.
04/27/98 VIO IR 98-07 NRC PS 1A A violation of Technical Specification 6.8.1 was identified because workers failed to understand the SLIV restrictions /litaitations of the radiation work permit and did not maintain an awareness of the work area radiological conditions.
04/25/98 VIO IR p8-07 NRC PS 1A A violation of Technical Specification 6.11 was identified for the failure to property label 36 bags SL IV (container / packages) of radioactive material with the appropriate radiological information to permit individuals handling or using the containers to take precautions to avoid or minimize their exposure.
04/17/98 POS IR 98-05 NRC PS 2S The licensee has successfu!!y maintained iron transport to the steam generators at low levels since adoption in 1993 of ethanolamine for pH control.
04/15/98 VIO IR 98-13 NRC PS 1A 1C A violation of 10 CFR 20.1501(a) was identified invoMng the failure to perform radiological surveys prior to, or at SLIV the start of, grinding / needle gun work within the containment building.
October 28,1998 12 Callaway Plant
ENCLOSURE 1 PLANT ISSUES MATRIX CALLAWAY PLANT DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE 04/10/98 NEG IR 98-04 NRC PS 1A A discrepancy was identified in which requirements in a security procedure did not agree with requirements in the security plan. The " Compensatory Measures" security procedure specified, in part, that increased vehicle patrols may be used during periods of fog, rain or sun glare, to compensate for intruders that are not vistle at the perimeter zone by closed circuit television (CCTV) cameras. The security plan requires that a partial failure of the CCTV surveillance and assessment system be compensated by stationing members of the security force in position to observe the effected perimeter zones. There were no events identified which included implementation of this procedure.
04/10/98 NEG 1R 98-04 NRC PS 1C A program had not been established to load test the security diesel generator. In May 1997, the licensee committed to developing a procedure to loao test the security diesel generator; no completion date was established. The licensee was in the process of developing a load test procedure and conducting a load test by May 1998.
04/10/98 STR 1R 98-04 NRC PS 1A 1C Performance in the physical security area remained good with no trend changes. An effective testing and maintenance program was conducted and properly oocumented. Effective protected and vital area barriers and detection systems were maintained. The barriers and detection systems provided proper delay and detection to attempted unauthorized entry. A good program for reporting security events was in place. A comprehensive security training program had been implemented. An effective program to protect safeguards information was in place. Compensatory measures were properly implemented.
02/28/98 NEG IR 98-01 NRC PS 2B 3A 3B The licensee nearly failed to perform a prejob radiological survey for a residual heat removal pump surveillance test. Health physics personnel had not been notified that vibration readings would be taken on the pump motor greater than 8 feet above the floor. The quality of the health physics portion of the pre-job briefing was weak.
The communicatbns between an equipment operator and health physics personnel at the radiological controlled area access point was also weak.
02/28/98 NCV IR 98-01 LIC PS 1C 3A There were four examples of licensee personnef failing to properly log into the computer-based electronic dosimetry system prior to entering the rediologicaily controlled area. The personnel wore the correct dosimetry but inadvertently did not sign in under their own name. The licensee responded appropriately to each error.
11/20/97 POS IR 97-20 NRC PS 1A The licensee's response to a sc7urity threat was appropriate. Proper notifications were made and appropriate EN 33290 contingency actions were implemented. A Notification of Unusual Event was declared. On 12/4/97, the licensee PN IV-97 retracted the portion of the event notification related to 10 CFR 73.71 when it was determined that the threat was 069 noncredible.
10/31/97 NEG IR 97-18 NRC PS 1C The manua; transfer of emergency power from the diesel generators to the radio repeater for the on-site radio system had not been addressed in an implementing procedure.
10/31/97 STR 1R 97-18 NRC PS 1C A very good program for searching personnel packages and vehicles was maintained.
10/31/97 STR 1R 97-18 NRC PS 2A Very good radio and telephone communication systems were maintsined.
October 28,1998 13 Callaway Plant
r ENCLOSURE 1 PLANT ISS'.lES MATR?X CALLAWAY PLANT 2
DATE TYPE SOURCE ID SFA TEMPLATE ITEM CODE w
10/31/97 STR tR 97-18 NRC PS SA Security program audits and survei!!ances were thorough and excellent quality. !
10/31/97 STR 1R 97-18 NRC PS 1C The access authorization program was a strength in the overall security program.
I 10/25/97 POS IR 97-17 NRC PS 2A Matenal condition of equipment in the radwaste evaporator building was good. Housekeeping showed improvement.
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ENCLOSURE 2 GENERAL DESCRIPTION OF PIM TABLE LABELS Actual date of an event or significant issue for those items that have a clear date of occurrence, the date the source of the infonnation was issued (such as the LER date), or, for inspecten reports.
Date the last date of the inspechon period. If the event date is eartaer than the curaint assessment (plant performance review) period, the document issue daterend of inspection should be used and the event date documented in the ITEM DESCRIPTION column.
Type The categorization of the issue - see the Type item Code table.
SFA SALP Functional Area Codes: OPS for Operatons; MAINT for Maintenance; ENG for Engineenng and PS for Plant Suppor' Sources The document that contains the issue information 1R for NRC Insoecta Report; LER for Licensee Event Report; letter for NF.R letter.
D Identification of who discovered issue: NPC for NRC; LIC for ucensee; or SELF for Self identifying (events).
Assue Description Details of the issue from the LER text or from the IR Executrve Summaries.
Codes Template Codes - see table.
TYPE ITEM CODES TEMPLATE CODES EA Enforcement Acton Letter with Civd Penalty 1 Operational Performance: A - Normal Oper Lons; 8 - Operations Dunng Transents; and C - Prograrns ED Enforcement Descreton - No Civd Penalty .
l Overall Strong Licensee Performance 2 Material Conditen: A - Equipment Condite or B - Programs and Processes STR WK Overall Weak Ucensee Performance 3 Human Performance: A - Work Performance; B - Knowledge, Skills, and Abilites / Training C - Work Environment eel
- Escalated Enforcement item - Waiting Final NRC Action 4 Engineenn$ Design: A - Design; B - Engineenng Support; C - Programs and Processes VIO Votaten Level I, it. til, or IV Noncited Violaton 5 Problem identification and Resolutiorr A - Identificaten; B - Analysis; and C - Resolution NCV DEV Deviation from Licensee Commitment to NRC NorES:
EEis are either: (1) apparent violations of NFW requirements that are being considered for escalated enforcement action in s+v.hu POS Indrvidual Good inspecton Finding
' with the " General Statemerit of Policy and Procedure for NRC Enforcement Action * (Enforcement Policy). NUREG-1600, or (2) issues, NEG Individual Poor Inspection Finding which may represent a SL IV potential violaton, that remain open pending receipt of the licensee's corrective actons to detemune if an NCV or VIO exists. However, the NRC has not reached its final enforcement decision on the issues identified by the Eels and the PIM LER Licensee Event Report to the NRC entries will be modified when the final decisens are made. Before the NRC makes its deosen for escalated enforcement Pems, the licensee will be provided with an opportunity to either: (1) respond to the apparent violation or (2) request a predecisionaf enforcement URt ** Unresolved item from *mspectior: Report conference.
- -URis are unresolved items about which rnore information is required to determine whetree the issue in question is an acceptable item.
Miscellaneous - Ernergency P eparedness Finding (EP), s deviation, a nonconformance, or a violation. However, the NRC has not reached its final conclusions on the issues, and the PtM entries MISC Declared E1.. p-r, Nv ,v.Ju n e issue, etc. will be modified when the final conclusions are made.
.~o o ENCLOSURE 3
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CALLAWAY PLANT INSPECTION PLAN IP - Inspection Procedure Tl- Temporary Instruction Core Inspection - Minimum NRC Inspection Program (mandatory all plants)
Safety Initiative - Directed by Program Office INSPECTION - TITLE 1 MUMBER OF DATES TYPE OF INSPECTION / COMMENTS PROGRAM AREA INSPECTORS 81700 Physical Plant Security 1 2/8-12/99 Core inspection Tl 2515/140 Periodic Verification of Design-Basis 3 3/29-4/2/99 Safety intiative Capability of Safety-Related Motor-Operated Valves (GL 96-05) 82301 Evaluation of Exercises for Power 4 4/26-30/99 Core inspection Reactors 71001 Requalifcation Programinspection 2 5/17-21/99 Core inspection
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