ML20198B151

Forwards Insp Activity Plan for Next 6 Months & Plant Issues Matrix.Infor Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite

ML20198B151
Person / Time
Site:	Davis Besse
Issue date:	12/02/1998
From:	Kozak T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Jeffery Wood CENTERIOR ENERGY
References
NUDOCS 9812180078
Download: ML20198B151 (29)

Text

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l nur UNITED STATES

( / o g NUCLEAR REGULATORY COMMISSION 1 8 o REGION 111

.g g 801 WARRENVILLE ROAD LISLE, ILLINOIS 60532 4351 i

%,***** j December 2, 1998 Mr. John K. Wood

.Vice President - Nuclear l

Davis-Besse Nuclear Power Station l l Centerior Service Company - 1 5.501. North State Route 2 I Oak Harbor, OH 43449 I

SUBJECT:

MID-YEAR INSPECTION RESOURCE PLANNING MEETING - DAVIS BESSE Dear Mr. Wood.

, . On November 4,1998, the NRC staff held an inspection resource planning meeting (IRPM).

l The IRPM provided a coordinated mechanism for Region lli to adjust inspection schedules, as l needed, prior to the conclusion of the Plant Performance Review cycle in April 1999.

Enclosure 1 to this letter advises you of our planned inspection effort for the next 6 months at Davis Besse.

l This attached information is provided to minimize the resource impact on your staff and to allow l for scheduling conflicts and personnel availability to be resolved in advance of inspector arrival l 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.

Encio,9ure 2 contains a historical listing of plant issues, referred to as the Plant issues Matrix l (PIM), that was considered during the IRPM. .The PIM includes only items from inspection t

reports or other docketed correspondence between the NRC and Centerior Service Company.

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9812180078 981202 l PDR ADOCK 05000346

G PDR I

J. Wood I We willinform you of any changes to the inspection plan. If you have any questions, please l contact me at 630-829-9866.

l Sincerely, I i

1

/s/ S. DuPont for l

Thomas J. Kozak, Chief Reactor Projects Branch 4 Docket No.: 50-346 License No.: NPF-3 l

Enclosures:

1. Inspection Plan

2. Plant issues Matrix <

cc w/encls: J. Statz, Senior Vice President - Nuclear J. Lash, Plant Manager J. Freels, Manager, Regulatory Affairs M. O'Reilly, First Energy '

State Liaison Officer, State of Ohio R. Owen, Ohio Department of Health C. Glazer, State of Ohio Public '

Utilities Commission 1 DOCUMENT NAME: .:G:\DAVi\lNSPPLN7.DAV l To receive a copy of thle document. Indicate in the bon 'C' = Copy without ettechrnent/ enclosure *E* = Copy with attachmsnt/ enclosure

• N* = No copy OFFICE Rlll 6 Rlli C NAME DuPont:dpY KozakMN

> DATE 11//98 d/S$ 11//98 /2N#

OFFICIAL RECORD COPY r

l

j J. Wood i Distribution:

- RPC (E-Mail)

Project Mgr., NRR w/encls J. Caldwell, Rlll w/encls C. Pederson, Rill w/encis l B. Clayton, Rlll w/encls SRI Davis-Besse w/encls DRP w/encls

! TSS w/encls

~ DRS (2) w/encls Rlli PRR w/encls PUBLIC IE-01 w ' lencls Docket File w/encls GREENS j IEO (E-Mail)

DOCDESK (E-Mail) l l.

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I $

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Davis Besse j INSPECTION / ACTIVITY PLAN IP -Inspection Procedure l Tl- Temporary Instruction l Core - Minimum NRC Inspection Program (mandatory all plants)

Regional Initiative - Discretionary inspections NUMBER OF TYPE OF INSPECTION NRC INSPECTION /

/ TITLE / PROGRAM INSPECTORSI PLANNED ACTIVITY-l ACTIVITY AREA INDIVIDUALS DATES COMMENTS IP83750 Operational 1 February 1 - 5, Core Radiation Exposure 1999 IP62707 Maintenance Risk 3 February 15 - 19, Regional inspection 1999 initiative @

IP82301 EP Exercise 4 N ay 3 - 7,1999 Core l Tl2515/140 Periodic Verification 2 May 4-6,1999 Regional i of MOV Capability Initiative @

@ Evaluation of risk associated with and control of on-line maintenance activities

@ Followup inspection of Generic Letter 96-05 for rion-JOG plant.

1 l

l 3

PLANT ISSUES MATRIX '3 888 Davis-BCssa .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* , bg. ming Date = *10/1/1997* , Ending Data = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 1 10/16/1998 Strength IR 98015 NRC Plant 1C The annual audit; of the EP program were very detailed, comprehensive, Support and met the requirements of 10 CFR 50.54(t). Surveillance reports reviewed were comprehensive and well detailed. The overall audit program was excellent.

2 10/16/1998 Positive IR 98015 NRC Plant 1C The EP program reporting structure continued to be effective. '

Support Management support for the emergency preparedness program was evident, as indicated by the demonstrated capabilities during the recent i tomado event and continued improvement in the program, training, and equipment.

3 10/16/1998 Positive IR 98015 NRC Plant 1C The EP training program appeared effective. Selected key Emergency Support Response Organization (ERO) personnel demonstrated good working knowledge of emergency responsibilities and procedures. The licensee was proactive in identifying and immediately correcting four ERO personnel's training needs. Emergency response organization personnel '

self-contained breathing apparatus qualifications included sufficient numbers of personnel from each department and were appropriately tracked.

4 10/16/1998 Positive IR 98015 NRC Plant 1C The inspected emergency response facilities were found in an exce!!ent ,

Support state of operational readiness. Equipment, supplies, and prompt alert and notification system sirens were well-maintained. The weekly pager testing and semi-annual augmentation testing was effective. Very good procedures provided for semiannual augmentation drilis and included critaria for their evaluation.

5 10/16/1998 Positive IR 98015 NRC Plant 1C Overall, the EP program had been maintained in an effective state of Support operational readiness. Management support to the program was apparent and interviewed key emergency response personnel demonstrated a good working knowledge of responsibilities and emergency procedures.

6 10/14/1998 Negative IR 98014 NRC Maintenance 2A The inspectors concluded that, by not using a foreign material exclusion boundary around the open EDG lube oil system during the online outage, the licensee was vulnerable to foreign material entering the system which could eventually effect EDG operability.

i Page 1 of 25 t

PLANT ISSUES MATRIX "' S8' Davis-Bsssa .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date" , Beginning Data = *10/1/1997* , Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 7 10/14/1998 Positive IR 98014 NRC Maintenance 2A On!ine safety equipment outages were performed well and in accordance with procedures. An increase in the CCW system outage scope was handled well and safety-related equipment was retumed to service well within the allowed outage time.

8 10/14/1998 Negative IR98014 NRC Engineering 4B The inspectors concluded that a human error, while calculating thermal performance data for CCW Heat Exchanger #2 and not actual heat exchanger degradation, resulted in the apparent failure of the thermal t performance test.

9 10/14/1998 Positive IR 98014 NRC Operations SA During preparations for the online emergency diesel generator (EDG) #1 ,

maintenance outage, an operator identified that removing EDG #1 from service would render both boric acid addition tank pumps inoperable.

The inspectors concluded that while the work support center missed this fact, the operator exhibited a good questioning attitude and prevented the licensee from unnecessarily entering a TS-required shutdown limiting condition for operation.

10 10/14/1998 Positive IR 98014 NRC Operations 5B The licensee met the Technical Specification (TS) requirement to conduct Company Nuclear Review Board (CNRB) meetings twice per calender year. The CNRB members were thoroughly prepared for the September 1998 meeting, discussed recent plant issues, and provided an independent assessment and recommendations on the resolution of the items discussed. The inspectors concluded that the CNRB was effectively used to provide an independent review and audit of designated activities.

11 10/14/1998 Positive IR 98014 NRC Engineering 5B The inspectors observed the management review committee appropriately categorize and assign Potential Condition Adverse to Quality Reports (PCAORs) and the PCAOR review board appropriately assess proposed corrective actions. The station review board effectively reviewed Priority 1 and Priority 2 PCAORs and a revision to the Offsite Dose Calculation Manual. The licensee satisfied TS 6.5.1 requirements for the station review board .

Page 2 of 25

x PLANT ISSUES MATRIX S8' Davis-B:::ssa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Beginning Date = *10M/1997* , Ending Date = *10/30n998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 12 9/30/1998 Positive IR 98016 NRC Plant 1C The calibration and test program for the portal and whole body Support contamination monitors, and the small article and tool monitors was genera!!y sound and implemented in accordance with station procedures.

Monitor alarms were set at levels consistent with industry practice, and instrument sensitivity and alarm operation was routinely verified. A deficiency was identified with the calibration acceptance criteria specified in the procedure for the small article monitors.

13 9/30/1998 Positive IR 98016 NRC Plant 1C ALARA plans and practices were effective in reducing doses during the Support eleventh refueling outage. Outage dose goals were achieved as a result of more effective work processes, and enhanced use of remote monitoring and communications equipment.

14 9/30/1998 Positive IR 98016 NRC Plant 1C Staff response to the June 24,1998, condensate demineralizer resin Support intrusion into the steam generators was appropriate. Increased management attention ensured that the staff's actions were timely and consistent, and frequent coordination with vendor personnel ensured that the licensee's actions and long term recovery plans were technically sound.

15 9/30/1998 Positive IR 98016 NRC Plant 1C Radiological controls for a containment entry during power operations on Support September 1,1998 were property established and effectively implemented. The pre-job briefing was thorough, worker's roles and responsibilities were clearly communicated and relevant information was obtained and exchanged in accordance with procedure. The radiation protection (RP) staff's response to a worker skin contamination that '

occurred during the entry was prompt and appropriate.

16 9/30/1998 Positive IR 98016 NRC Plant 1C The licensee effectively implemented an extemal dosimetry quality control Support (OC) program, and continued to maintain good oversight of the dosimetry processor. Periodic QC checks were performed to ensure the accuracy of processed dosimetry, and anomalous results were evaluated in accordance with station procedure. '

17 9/30/1998 Positive IR 98016 NRC Plant 1C The program for the unconditional release of materials from radiologically Support restricted areas was consistently implemented by the RP staff. However, portions of the procedure goveming the program were unclear and inconsistent with station practices.

Page 3 of 25

PLANT ISSUES MATRIX "' ' 888' Davis-Besse Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Beginrdng Date = *10/1/1997* , Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 18 9/30/1998 Positive IR 98016 NRC Plant 1C The station's neutron energy spectrum was evaluated, and the survey Support and extemal dose monitoring programs were adjusted to ensure worker dose from neutron radiation was accurately determined. Administrative dose levels were established to maintain dose ALARA, and controls were effective in maintaining worker dose, including the dose to declared pregnant workers, within regulatory limits.

19 8/14/1998 Positive IR 98011 NRC Operations 1C SC The NRC team concluded that management was committed to making the corrective action program effective. Significant management time was expended prior to meetings to ensure the Potential Conditions Adverse to Quality Reports (PCAORs) addressed the full scope of each issue. Management support for the initiation of PCAORS was also good.

20 8/14/1998 Positive IR 98011 NRC Engineering 4C Based upon review of selected 10 CFR 50.59 screening documents and safety evaluations, the NRC team concluded that performance in this area was good. The screenings and evaluations were thorough and accurately reflected the licensee's methodology for assuring deviations from design, as defined in the Updated Safety Analysis Report did not impact plant safety.

21 8/14/1998 Positive IR 98011 NRC Operations SA The NRC team concluded that the licensee effectively captured the scope of the identified problems and resolved issues through the Potential Conditions Adverse to Quality Reports (PCAORs). However, more consideration could be given concerning Probabilistic Risk Assessment when categorizing PCAORs such as the station blackout breaker failure PCAOR.

22 8/14/1998 Positive IR 98011 NRC Operations SA The audit activities by the Independent Safety Evaluation Group and Quality Assurance were effective, straight forward, and supported by the line organization. The issues identified by the audit group were supported by the line management and appropriate corrective actions were taken.

23 8/14/1998 Positive IR 98011 NRC Operations SA SC The NRC team concluded that the corrective action process at Davis-Besse was proactive and effective. Enhancements and improvements continued to be made in identification, resolution, and prevention of problems. The threshold for identifying problems was appropriately low and root cause evaluations were thorough Page 4 of 25

PLANT ISSUES MATRIX "' ***

Davis-Bassa .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Begirnng Date = *10/1/1997* , Ending Data = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 24 8/14/1998 Positive IR 98011 NRC Operations SB The assignment of root cause analysis responsibility to the line organization and having management oversight early in the Potential Conditions Adverse to Quality Reports (PCAORs) process was an improvement in the root cause evaluation process. The team found that recent root cause analysis reports were thorough and effective.

25 8/14/1998 Positive IR 98011 NRC Operations SB The operating experience program effectively assessed operating experience, informed the proper personnel of the assessments, generated technically sound corrective actions when appropriate, and correctly implemented the actions.

26 8/14/1998 Positive IR 98011 NRC Operations SC The licensee staff supported the corrective action process and recognized the program as an effective way to resolve issues.

27 8/7/1998 Negative IR 98013 NRC Operations 1A Overall, the inspectors concluded that operators exhibited appropriate knowledge and control during the relatively high number of startups and shutdowns that occurred during the inspection period. However, appropriate attention to detail was not displayed when a reactor operator did not verify that a turbine generator lift oil pump had started after he turned the switch to on and when operators missed an opportunity to determine that the actual Axial Power Shaping Rod (APSR) position was not consistent with the position assumed in the estimated critical position (ECP) calculation. In addition, a turbine trip occurred when reactor operators could have been better prepared to synchronize the turbine to the grid after a forced outage.

28 8/7/1998 Negative IR 98013 NRC Operations 1C The inspectors determined that operations personnel did not recognize that Technical Specification (TS) 3.0.5 was entered when the emergency power supply for control room emergency ventilation (CREVS) Train 1 was inoperable coincident with CREVS Train 2 being inoperable. The apparent cause was a lack of written guidance pertaining to the complex relationship between the operability of station vent stack radiation monitors and CREVS operability. No violation occurred because of the short duration (13 minutes) of the condition.

29 8/7/1998 Positive IR 98013 NRC Maintenance 2A SC The inspectors concluded that station management effectively prioritized items that were operator burdens, such as control room annunciators that were locked in due to a discrepant material condition, during plan of the ,

day meetings.

Page 5 of 25

PLANT ISSUES MATRIX **8' Davis-B3ssa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Beginning Date = *10/1/1997* ; Ending Date = *10/3(V1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 30 8/7/1998 Positive IR 98013 NRC Maintenance 28 After the inspectors identified a control room instrument was indicating low, maintenance personnel determined that the instrument was able to be calibrated to the low end of the band; however, they replaced the square root extractor for the instrument in order to calibrate to the middle of the band. The inspectors concluded that maintenance personnel were proactive when they replaced the square root extractor for the instrument.

31 8/7/1998 Positive IR 98013 NRC Maintenance 2B SC The outage manager developed a comprehensive plan to address existing plant issues, including correcting a faulty indication for Control Rod 4-6, cleaning Loop 1 waterboxes, installing a furmanite injection plug for leaking Pressurizer Spray Valve RC-2, and repairing deficiencies previously identified on the main transformer during the forced outage to address chemistry issues. The inspectors concluded that the outage was well planned and included effective management involvement with the work activities.

32 8/7/1998 Negative IR 98013 NRC Maintenance 3A 2B The inspectors determined after the loss of offsite power on June 24, that "

emergency diesel generator (EDG) #1 Test Switch TS-3 was out of position, which resulted in a temporary loss of important EDG parameter local indications. The root cause was that an electrician performed an inadequate review cf maintenance work order paperwork when work was suspended for the night. No corrective action document was generated to further address the concern until July 25, after the inspectors brought the matter to the EDG engineer's attention.

33 8/7/1998 Negative IR 98013 NRC Maintenance 3r. .o Maintenance personnel bypassed the operations work control unit review chain when performing weekly maintenance on the station vent stack radiation monitors. This did not meet plant management's expectation for the control of work and contributed to the failure to recognize entry into TS 3.0.5.

34 8/7/1998 Positive IR 98013 NRC Engineering 48 The Station Review Board and the Management Review Committee were effective in ensuring that Potential Condition Adverse to Quality Reports were appropriately prioritized, assigned to the right organization, and resolved as scheduled.

Page 6 of 25

PLANT ISSUES MATRIX "' S8' Davis-Basco Search Sorted by Date (Descerdng) and SMM Codes (Ascerdng): Search Column = *Date* ; Beginning Date = *10/1/1997* , Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 35 8/7/1998 Negative 198013 NRC Engineering 4C The inspectors determined that actual APSR position (15 percent) did nc*

match the ECP calculated position (30 percent) during a reactor startup.

The apparent root cause was that a reactor engineer in the control room exhibited a lack of attention to detail when the ECP was calculated.

Additionally, the lack of a procedural requirement to ensure that the actua!

APSR position matched the ECP position was a weakness. The proposed changes to plant procedures should prevent recurrence. The effect of the error had no impact on safety.

36 8/7/1998 Positive IR 98013 NRC Engineering SC The inspectors reviewed plant engineering efforts to address problems with the integrated control system and to track maintensnce activities pertaining to the service water intake structures. The inspectors determined that the integrated control system engineer and his backup effectively troubleshot and supervised repairs of a problem with the integrated control system and that they took proactive measures to tune the system and replace components in order to obtain better system performance. Further, the service water system engineer was in the field providing effective oversight and guidance for contractor and plant maintenance staff ouring intake crib repairs, intake canal sitt level determinations, and service water pump house structures cleaning activities.

37 8/7/1998 Positive IR 98013 NRC Plant SC The licensee took conservative actions to address the relatively high Support secondary side sulfate concentrations caused by a resin intrusion by voluntarily shutting down the reactor and performing multiple steam generator fill, soak and drains. The sulfate levels were reduced below administrative levels and the plant was subsequently retumed to full power.

38 6/29/1998 URI 1R 98012 NRC Operations 1B The NRC team concluded that operators generally effectively tracked and met Technical Specification requirements throughout the event. One unresolved item conceming invoking 10 CFR 50.54x was identified URI 50-346/98012-01 Page 7 of 25

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PLANT ISSUES MATRIX Davis-Besse .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date" . Beginning Date = *10/1/1997* . Ending Data = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 39 6/29/1998 Positive IR 98012 NRC Operations 1B As the operators teamed of the severe storm in the area, they executed their responsibilities in a professional, business-like manner. Their communication practices, annunciator response, procedural compliance, and panel monitoring were good. The command and control during and following the event was excellent. The operators' actions were effective in ensuring the plant was in a safe condition. The crew's event response indicated they were well trained for such an event.

40 6/29/i998 Positive IR 98012 Self- Operations 1B All known equipment anomalies and storm damage which occurred were Revealed documented and entered into the licensee's corrective action program.

The NRC team concluded that the licensee performed a methodical, comprehensive review of the event and its consequences. Repair activities were professionally accomplished and at no time did it appear that workers were schedule-driven.

41 6/29/1998 Misc IR 98012 NRC Operations 1B Although the National Weather Sentice issued a severe thunderstorm waming approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to the tornado touchdown onsite, the s% tion was not formally notified of the approaching storm. The inspectors' prior experience has shown that nuclear stations located in NRC Region 111 generally rely on load dispatchers for notification of severe storms but have rarely been tormally notified of approaching severe storms. The inspectors concluded that an effective system for notifying stations of severe storms should allow for better preparation for possible storm consequences, such as a loss of offsite power.

42 6/29/1998 Positive IR 98012 NRC Plant 1B 1C The licensee's emergency response and outage organizations provided Support appropriate safety focus for the station personnel during the resolution of storm damage and equipment issues. The teamwork displayed by the organizations indicated that they had been well trained for such an event.

43 6/29/1998 Positive IR 98012 NRC Plant 1C The NRC team concluded that the plant staff appropriately classified a Support tomado striking the facility as an Alert in accordance with the emergency plan. Due to the severe weather, which damaged communications lines and caused hazardous road conditions near the plant, several steps of the emergency plan were not completed within the expected time frame.

However, the inspectors concluded that the delay did not impact the operators' ability to safely control the plant Page 8 of 25

PLANT ISSUES MATRIX u/ /i998-Davis-Bossa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beg <nning Date = *10/1/1997* ; Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 44 6/29/1998 Negative IR 98012 Licensee Engineering 4B SC The resolution of technical issues was generally performed in a thorough fashion. However, engineers did not obtain the necessary information from those involved when Circuit Breaker ABDC1 failed to c!ose which led to an inaccurate resolution of the issue. This was identified in the licensee's management review of the startup issues and resolved prior to plant restart activities.

45 6/24/1998 Positive IR 98013 NRC Operations 1B The inspectors determined that operators maintained the plant in a safe condition, were in control of important plant parameters, and that no equipment failure challenged the safe shutdown capability of the plant after a tomado had caused a loss of offsite power and a reactor trip on June 24.

46 6/24/1998 Positive IR 98015 NRC Plant 1C Tne emergency plan was effectively implemented during the June 24, l Support 1998, tomado event, which was properly classified as an Alert. Delays in completion of initial offsite notifications and facility staffing were attributed to the severe weather conditions. Station personnel responded well to this event.

47 6/23/1998 Positive IR 98009 NRC Operations 1A Effective communications and thorough control room briefs during plant restart following the refueling outage were noted. The activities were carefully controlled 48 6/23/1998 Positive IR 98009 Self- Operations 1A A power reduction to repair a main feed pump was well planned and Revealed controlled with effective management oversight 49 6/23/1998 NCV IR 98009 Licensee Operations 3A The inspectors concluded that, on two separate occasions, operators performed actions without management approval when faced with unanticipated circumstances. In the first case, an operator did not follow an emergency diesel generator (EDG) operating procedure when he improperly opened a bus tie breaker. This deenergized a 4160-volt safety-related bus and momentarily overloaded EDG#2. In the second case, after an operator closed the wrong low pressure injection system suction valve, recovery actions were taken without control room supervisor approval. In both instances, operators did not meet management's expectations. (NCV 50-346/98009-01(DRP))

Page 9 of 25

PLANT ISSUES MATRIX S8' Davis-B:ssa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Beginning Date = *10/1/1997 . Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 50 6/23/1998 VIO/SL-IV IR 98009 NRC Engineering 4A The inspectors found several unscreened openings around the base of the emergency sump screen enclosure that could permit particles of 1 sufficient size into the sump during recirculation following a loss-of-coolant accident to potentially plug containment spray nozzles. The design basis requirement of protecting the spray nozzles from plugging was not translated into the emergency sump design and is a design control violation (VIO 50-346/98009-03(DRP))

51 6/23/1998 NCV IR 98009 Licensee Engineering 4C The licensee performed a change to the protective relay design of a safety-related 4160-volt breaker without properly establishing the suitability of the change, which is a non-cited violation of design control (NCV 50-346/98009-05(DRP)).

52 6/23/1998 Negative IR 98009 NRC Maintenance SA Management's expectation to promptly generate a potential condition adverse to quality report (PCAOR) was not met following the inspectors'  !

discovery of an improperly installed wafer check valve, a valve used to ensure effective emergency ventilation system operation. Although the check valve was promptly re-installed correctly, a PCAQR documenting this condition was not written until the inspectors brought the issue to management's attention a week later 53 6/23/1998 Positive IR 98009 Licensee Engineering SC The licensee implemented an effective and methodical approach to identify and comprehensively resolve deficiencies in the actuation logic i surveillance test program in response to Generic Letter 96-01, " Testing of :

Safety-Related Logic Circuits" r

54 6/17/1998 VIO/SL-IV IR 98008 NRC Plant 1C A violation was identified for not disclosing specific information required Support for unescorted access authorization background investigations.

Inspection followup items were noted for inaccurate or incomplete information in some background investigation case files, and some materials, not identified in the security plan, being exempt from search prior to entering the protected area. Protected area entry controls for personnel, vehicles, and material were effective. (violation 98008-01) 55 6/17/1998 Negative IR 98008 NRC Plant 1C An inspection followup item was identified in reference to actions required Support to increase the protecticn for an active barrier within the Vehicle Barrier System (VBS). Security equipment observed during the inspection was operable and functioned as designed. (IFl 98008-04)  ;

Page 10 of 25

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PLANT ISSUES MATRIX **8 Davis-Bassa .

Search Sorted by Date { Descending) and SMrA Codes (Ascending): Search Column = *Date" , Beginning Date = *10/1/1997* . Ending Date = *1(V30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 56 6/17/1998 Positive !R 98008 NRC Plant 1C 3B Security officers and supervisors were very knowledgeable of duty Support responsibilities and no deficiencies were noted during post visits and interviews. Security force performance was very good and consistent 57 6/17/1998 Positive IR 98008 NRC Plant 1C SC The self-assessment efforts were varied and effective in identifying Support problems and performance trends, except for the background investigation related violation and issues addressed in Section S1.

Finding results were effectively monitored, tracked, and resolved 58 6/11/1998 Positive IR 98010 NRC Plant 1C Radiological effluent releases were well controlled and effluent monitoring {

Support was conducted consistent with the Offsite Dose Calculation Manual (ODCM) and Updated Safety Analysis Report. The total released activity and associated dose remained low and were well below regulatory limits.

One recurrent problem was identified with documentation errors in the i ODCM and effluent release reports.

59 6/11/1998 Positive IR 98010 NRC Plant 1C The radioactive waste (radwaste) packaging and transportation program Support was technically sound and program oversight was good. Radwaste shipments were appropriately classified, manifests were completed in accordance with regulatory requirements, and training was provided for personnelinvolved in packaging and shipping. A scaling factor program ,

for classifying waste streams was applied consistent with regulatory guidance; however, program implementation was not govemed by station procedure to ensure its consistent application.

60 6/11/1998 VIO/SL-IV IR 98010 NRC Plant 1C Audit and surveillance activities conducted by the licensee were adequate '

Support to assess the radiological effluent monitoring and control program, the ODCM and the packaging and transport of radwaste. However, a violation was identified conceming the failure to audit the PCP and the implementation of procedures for processing radwastes as required by  :

Technical Specification.

(Violation 50-346/98010-01) 61 6/11/1998 Positive IR 98010 NRC Plant 1C Radioactive material and radwaste storage containers were maintained in Support good physical condition, were properly labeled, and storage areas were posted and controlled in accordance with regulatory requirements. A radioactive materials management inventory system adequately tracked material movement at the site.

Page *.1 of 25 i s

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PLANT ISSUES MATRIX Davis-B3ssa Seardi Sorted by Date (Descending) and SMM Codes (Ascending): Searen Column = *Date" ; Beginning Date = "10/1/199T . Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 62 6/11/1998 Positive IR 98010 NRC Plant 1C The station and control room emergency ventilation systems were Support maintained in good condition and associated air filtration / adsorption tests and surveillances were performed as required. System engineers maintained good oversight and closely tracked system maintenance activities and performance history.

63 6/11/1998 Negative IR 98010 NRC Plant 1C The solid waste processing systems were as described in the Updated Support Safety Analysis Report (USAR). The Process Control Program (PCP) was consistent with the waste streams described in the USAR and was implemented by knowledgeable staff in accordance with station procedure. However, a weakness was identified with the development of

, the PCP, conceming the frequency that dewatered wet wastes were sampled and verified to ensure that regulatory limits for free standing i liquid were met, and that all pertinent 10 CFR 61.56 requirements were addressed.

64 6/11/1998 Positive IR 98010 NRC Plant 2A The effluent process radiation monitors were operab!e and well Support maintained. One poor practice was identified conceming a lack of review of instrument and Control technicians in the performance of monitor calibrations.

65 5/12/1998 Positive IR 98005 NRC Operations 1A The licensee appropriately considered shutdown risk before scheduling activities affecting the operation of the decay heat removal system and during reactor vessel draining activities. Generally, the operators used good communication techniques and had appropriate control of the drain i down evolution. Procedures regarding reduced inventory and mid-loop  ;

operations met the intent of Generic Letter 88-17,

• Loss of Shutdown '

Cooling" ,

66 5/12/1998 Negative IR 98005 NRC Operations 1A 3C Poor communication among control room personnel regarding a redundant valve controller failure occurred while lowering reactor vessel water level.

67 5/12/1998 VIO/SL-IV IR 98005 NRC Maintenance 28 The procedure used to fill the steam generator using a temporary manifold was not adequate to ensure all manifold valves used for this activity were contro!!ed. (Violation 346/98005-02) 68 5/12/1998 Positive IR 98005 NRC Maintenance 3A The inspectors concluded that refueling activities were performed in accordance with administrative procedures that provided multiple barriers l to ensure that fuel movements were performed as planned.

Page 12 of 25

PLANT ISSUES MATRIX *8' Davis-B;ssa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Colornn = "Date* - Beginning Date = *10/1/1997* , Erxfing Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 69 5/12/1998 Negative IR 98005 NRC Operations 3B During the transfer of radioactive water from the reactor coolant drain tank to the clean waste receiver tank, a degraded filter inlet isolation valve caused the water to be diverted to the miscellaneous waste tank.

Operators did not recognize the water diversion until approximately 8000 gallons had been transferred.

70 5/12/1998 Positive IR 98005 NRC Operations 3C The establishment of a work support center outside of the control room reduced the distractions and the administrative tasks that operators in the '

control room had previously been required to perform. The inspectors confirmed that the operators remained aware of plant activities.

71 5/12/1998 Negative IR 98005 Self- Maintenance 3C SB Several near-misses involving crane and rigging operations occurred in Revealed containment that jeopardized plant equipment and personnel safety. The licensee was addressing the collective significance of this issue. (NCV 346/98005-01.... Closed in report 50-346/98005) 72 5/12/1998 Positive IR 98005 NRC Engineering 4B The inspectors concluded that engineering personnel conducted a comprehensive inspection and evaluation of the effects of dust from sandblasting the shield building annulus on equipment in the affected rooms.

73 5/12/1998 Positive IR 98005 NRC Maintenance SA During main steam safety valve testing, valves found out-of-tolerance were reset. Even though the main steam headers remained operable, the licensee used the guidance of NUREG-1022," Event Reporting Guidelines for 10 CFR 50.72 and 50.73," to report an unusual number of valves outside setpoint tolerances. (NCV 346/98005-04... Closed in report 346/98005) 74 5/12/1996 Positive IR 98005 NRC Operations 5A The inspectors concluded the licensee effectively prepared for outage activities by scripting risk significant tasks.

75 5/1711998 Positive IR 98005 NRC Engineering SA The inspectors observed the meetings of the Station Review Board and Management Review Committee; and evaluated the activities of Quality Assessment personnel. Overall, these organizations and individuals were effective in their respective roles.

76 5/12/1998 Negative IR 98005 Self- Maintenance SC Two light fixtures were found broken which resulted in broken glass in the Revealed refueling canal and the spent fuel pool. This may have been prevented had the actions taken to address a 1996 audit finding been more comprehensive Page 13 of 25

PLANT ISSUES MATRIX "''*8

Davis-B sse Search Sorted by Date (Descending) and SMM Codes (Ascending): search Column = *Date* , Beginrnng Date = *10/1/1997* , Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 77 5/12/1998 Negative IR 98005 Licensee Operations SC A procedural weakness was identified in that a formal reactor coolant system inventory balance was not performed. This weakness could have been identified earlier if two information notices had been dispositioned more aggressively.

78 5/7/1998 Positive IR 98007 NRC Plant 1C The radiation protection department response to the breakthrough of Support resin from a purification demineralizer was good. The radiation protection staff effectively evaluated the changed radiological conditions fo!!owing the res:n breakthrough, and controlled access to affected areas without incident.

79 5/7/1998 Positive !R 98007 NRC Plant 1C The calibration and maintenance program for area radiation monitors was Support well implemented. One weakness was identified in that monitor performance data was not reviewed by the licensee, which may prevent early identification of problems 80 5/7/1998 Positive IR 98007 NRC P! ant 1C Overall the ALARA planning and controls for the refueling outage were Support good, but some examples of inaccurate or incomplete ALARA planning documentation were identified.

81 5/7/1998 Positive IR 98007 NRC Plant 1C The licensee's maintenance of records important for the safe Support decommissioning of the facility, as required by 10 CFR 50.75(g), was good.

82 5/7/1998 NCV IR 98007 Licensee Plant 1C One Non-Cited violation was identified for the failure to provide a Support continuous radiation protection escort prior to allowing an operator to enter an LHRA. The inspectors noted that the corrective actions for this violation were good and designed to prevent recurrence. f 83 5/7/1998 Positive IR 98007 NRC Plant 1C The inspectors observed good radiation protection technician work i Support coverage, control of high radiation areas (HRAs) and LHRAs, and verified that workers were knowledgeable of RP requirements. However, some problems were identified with the licensee's control of contaminated areas and with the control of hoses used in containment.

84 5/7/1998 Positive IR 98006 NRC Maintenance 2B Code repair work perforrned on the main steam isolation valve was well implemented with active technical vendor oversight.

85 5/7/1998 Positive IR 98006 NRC Maintenance 2B in general, licensee personnel and contracted personnel involved in flow assisted corrosion programs and ISI efforts appeared knowledgeable, well trained, and competent.

Page 14 of 25

PLANT ISSUES MATRIX "' ' **8 ~ '

Davis-Bossa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date' . Beginning Date = *10/1/1397* , Ending Date = *1000/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 86 5/7/1998 Positive IR 98006 NRC Maintenance 2B The addition of a ' data patrolman' to the s:eam generator eddy current examination team, in order to provide an additional quality assurance layer, demonstrated a thorough and rigorous effort to obtain quality data in this area important to safety.

87 5/7/1998 Positive IR 98006 NRC Maintenance 2B The licensee adequately demonstrated the ability to property implement ISI and flow assisted corrosion programs, including eddy current examinations of the steam generator tubes.

88 5/7/1998 Positive IR 98006 NRC Maintenance SA Technically, the most current technology and dispositioning protocols were used to assess and disposition the steam generator tubes.

Although not required until 1999, many of the good practices recommended by Electric Power Research Institute (EPRI) Pressurized Water Reactor Steam Generator Examination Guidelines, Revision 5, were implemented. The examination data was found to be in accordance with the applicable ISI procedures and American Society of Mechanical Engineers (ASME) Code requirements.

89 5/7/1998 Positive IR 98006 NRC Maintenance SB 28 Consistent with the components importance to safety, the licensee demonstrated an aggressive assessment of vendor code repair and ISI t contractor supplied procedures to assure that applicable ASME and regulatory requirements were met.

90 4/23/1998 VIO/SL-IV IR 98007 NRC Plant 1C Poor documentation of the ALARA planning for the respiratory protection Support controls and the failure to evaluate those ALARA controls implemented during the removal of steam generator mirror insulation, constituted another example of a violation of 10 CFR 20.1501(a)(2).

91 4/21/1998 VIO/SL-IV IR 98007 NRC Plant SA The licensee took appropriate actions to control exposure after workers Support encountered unsxpected, transient, high dose rates in the annulus area during incore detector movement. However, the failure to recognize this condition given known industry history and to establish appropriate controls was an example of a violation of 10 CFR 20.1501.

92 4/10/1998 Positive IR 98005 Self- Operations 1B 3B Operators reac:ed very well to an unexpected resin burst in the letdown Revealed system that plugged filters in the system and caused difficulty in controlling pressurizer level. The operators prevented resin from entering  ;

the reactor coolant system and appropriately tripped the reactor before the increasing water level could challenge the pressurizer code safety valves.

Page 15 of 25

PLANT ISSUES MATRIX ' SS8~

Davis-Besse .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/1997* - Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 93 3/31/1998 Positive IR 98004 Licensee Plant 1C The licensee continued maintaining proper control of radiological areas Support and proper control of personnel entering and exiting these areas.

94 3/31/1998 Positive IR 98004 NRC Plant 1C 5A The central and secondary alarm stations were staffed with attentive and Support knowledgeable personnel. The licensee appropriately identified and replaced degraded equipment with temporary equipment before the end of the inspection period.

95 3/31/1998 Negative IR 98004 NRC Engineering 4B Weak engineering support to maintenance activities led to the inadvertent ,

breach of the emergency ventilation system negative pressure boundary when workers drilled through a drain pipe imbedded in the decay heat removal heat exchanger room. Although no spread of contamination occurred, breaching the boundary exposed the workers to a potentially contaminated system. Clear guidance on the necessary drawings for the engineers to review before approving the drilling location was not readily available to the evaluating engineer due to this being an infrequently performed evolution. The plant response to the event was timely and adequate. The proposed corrective actions were acceptable.

96 3/31/1998 Positive IR 98004 NRC Engineering SA The inspectors observed activities of the licensee's offsite review committee. The inspectors concluded that the offsite review committee members effective!y communicated concems and suggestions with plant management.

97 3/31/1998 Positive IR 98004 Licensee Plant 5A SC Security management issued a memorandum to heighten security officer Support awareness following recent lapses in security guard attentiveness to their duties. These expectations were discussed during shift security tumovers. Security guard attentiveness improved subsequent to this action 98 3/31/1998 Positive IR 98004 NRC Engineering 5B The inspectors concluded that engineering personnel performed a thorough and detailed review of the concerns raised by Information Notice ,

97-90, "Use of Non-conservative Acceptance Criteria in Safety-Related Pump Surveillance Tests

• 99 3/31/1998 Positive IR 98004 Licensee Engineering SC The licensee was adequately addressing NRC and self-identified Updated Safety Analysis Report discrepancies.

I Page 16 of 25 '

h

PLANT ISSUES MATRIX ' SS8' Davis-Bacs3 .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* ; Beginning Data = *10/1/1997* . Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 100 3/27/1998 Positive IR 98004 NRC Operations 1A Implementation of the new work support center has significantly reduced distractions in the control room. Further, the administrative workload of the control room senior reactor operator has been reduced, allowing him to devote more of his attention towards supervising control room and shift personnel and towards observing the performance of piant equipment.

101 3/27/1998 Positive IR 98004 NRC Operations 1C Overall, observed simulator training was pertinent and effective towards providing assurance that operators were proficient to shut down the plant in an orderly manner.

102 3/27/1998 Positive IR 98004 NRC Operations SA The inspectors reviewed a Quality Assessment Audit Report that evaluated the effectiveness of control room activities. The inspectors concluded that the findings were generally consistent with observations made by the inspectors and that it had good scope and depth.

103 3/19/1998 Licensing 98NRRPM NRC Engineering 4C Licensing submittals by the licensees continue to be excellent. The licensing bases are thoroughly reviewed, the technical issues are addressed in-depth, and safety issues are appropriately dispositioned.

104 3/19/1998 Licensing 98NRRPM NRC Engineering 4C 3A Communications between Davis-Besse licensing staff and NRR continue ,

to be very effective. Some schedules slip on non-safety-significant issues due to the licensees' workload, though all safety issues are handled promptly.

105 2/26/1998 Positive IR 98003 NRC Engineering 4A Engineering was proactive in reviewing inspection findings at other nuclear sites for applicability to Davis-Besse and in reviewing original licensing review questions and answers to verify appropriate incorporation in the Updated Safety Analysis Report.

106 2/26/1998 Misc IR 98003 NRC Engineering 5B Engineering judgement proved to be correct concerning the structural adequacy of mounting brackets for the borated water storage tank level instrument.

107 2/26/1998 Negative IR 98003 NRC Engineering 5B There was a lack of significant progress on environmental qualification of support equipment in the emergency core cooling system rooms 108 2/26/1998 Positive IR 98003 NRC Engineering SB Timely and appropriate engineering evaluation of the seismic concem, for non-safety pressure gages tied to safety systems, facilitated prompt closure of this item.

Page 17 of 25

PLANT ISSUES MATRIX "' SS8 '

Davis-Bassa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* Beginning Date = "10/1/1997* , Ending Date = *10/30/1998"

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 109 2/18/1998 Positive IR 98002 NRC Operations 1A SA The inspectors observed that the plant was operated in a controlled, conservative manner. Plant issues that were identified were appropriately handled in accordance with the licensee's corrective action program or material deficiency program. Operators were knowledgeable of Technical Specification (TS) operability requirements and tagouts were implemented in accordance with the tagout procedure. Generally, the operators exhibited good knowledge of plant equipment status and property used plant operating procedures. Control room operators and equipment operators were observed to be adequately fulfilling their duties (Sections 01.1 and 04.1).

110 2/18/1998 Positive IR 98002 NRC Plant 1C 3A Overall, radiation protection activities relating to a diving activity in the Support spent fuel pool transfer canal and a high integrity container lift were performed in a professional, well planned manner (Section R1.1).

111 2/18/1998 Positive IR 98002 NRC Plant 1C 3B The fire brigada team effectively responded to a challenging drill scenario Support (3ection F4.1).

112 2/18/1998 Positive IR 98002 NRC Maintenance 2A 3A During surveillance activities, equipment was observed to perform as described by the Updated Safety Analysis Report. Maintenance personnel communicated adequately and adhered to procedure requirements while performing maintenance and survei!!ance activities.

The inspectors observed that oversight of maintenance activities was effective. Maintenance and survei!Iance testing activities were professionally conducted (Section M1.1).

113 2/18/1998 VIO/SL-IV IR 98002 Self- Operations 3A Plant cperations were impacted on two occasions when operators Revealed displayed a lack of attention to detail. The first example involved the inadvertent isolation of seal injection to all four reactor coolant pump seal packages due to an operator error. The second example involved the lifting of a letdown system relief valve due to an operator not performing a procedure in the correct sequence. These events are two examples of a violation of TS 6.8.1 (Section O1.2).

114 2/18/1998 Misc IR 98002 NRC Operations 3A The operations manager appropriately communicated physical fitness expectations to the operating crews after being notified by the inspectors that a shift supervisor stood watch with the medical condition of laryngitis (Section 06.1).

Page 18 of 25

- - _ _ _ _ _ _ _ _ _ _ _ _ - . - _ -=_- - _ _

PLANT ISSUES MATRIX **8' Davis-Besse Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/1997* , Ending Data = *10r#d1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 115 2/18/1998 VIO/SL-IV IR 98002 NRC Operations 4C 3B The inspectors identified one violation of 10 CFR 50.72(b)(1)(ii)(B) where the licensee did not repcit to the NRC, within one hour of the discovery, that speed sensino circuitry for Emergency Diesel Generator #1 was not designed per the 10 CFR Part 50, Appendix R, design criteria for hot short protection, a condition outside the design basis of the plant (Section F8.1).

116 2/18/1998 Positive IR 98002 Licensee Engineering SA SC The licensee demonstrated an excellent questioning attitude regarding the configuration of a refueling drain canal valve, a valve whose open position ensured sufficient water supply to emergency core cooling system pump suctions during an accident. After determining that the valve was not in its locked valve program, the licensee immediately i entered containment, verified the valve was in the open position, locked the valve, and plans to enter it in the locked valve program (Section E8.2).

117 1/28/1998 Positive IR 97015 NRC Operations 2A Valve line-ups and major flow paths for both engineered safety features and important-to-safety systems were verified to be consistent with plant procedures / drawings and the Updated Safety Analysis Report (USAR).

Other/NA 118 1/28/1998 Positive la 97015 NRC Operations 2A 1B The inspectors observed that the operators maintained good control of the plant during a failure of the servo control valve for Turbine Control Valve No. 4. Teamwork / Skill Level 119 1/28/1998 Positive IR 97015 NRC Maintenance 2B The licensee removed from service the level controller for both the Train 1 Auxiliary Feed Pump and the Motor Driven Feed Pump for a maintenance outage. The inspectors determined that operations work control personnel were knowledgeable of the maintenance rule requirements associated with this work, and that risk was appropriately considered in the planning stages. Teamwork / Skill Level 120 1/28/1998 Negative IR 97015 NRC Operations 3A A reactor operator missed noticing that the computer display for Group 38, which indicates reactor core nuclear parameters and calculates secondary heat balance power, did not update for a 50-minute period because he became distracted with a problem on the Nuclear Operations Management System. Personnel Performance Deficiency Page 19 of 25

PLANT ISSUES MATRIX "'3 ' SS8' Davis-B3ssa Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = "Date* . Beginrnng Date = *10/1/1997* , Ending Data = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 121 1/28/1998 Positive IR 97015 NRC Operations 3A 1A Operations activities were conducted in a controlled, conservative manner. Shift briefs were thorough, operators had good knowledge of plant status and activities, and procedures were consistently complied with. Plant management was aware of and responded to operational issues in an appropriate manner. Involved Management 122 1/28/1998 Positive IR 97015 NRC Plant 3A 1C A thorough ALARA briefing was conducted for a containment entry to Support perform reactor coolant pump upper thrust bearing resistance temperature detector circuit modifications. General area radiation dose rate estimates closely matched those actually found in containment.

Radiation protection personnel provided excellent assistance and support for the entry team. Total dose received for the entry was low at about 10 millirem. Teamwork / Skill Level 123 1/28/1998 Positive IR 97015 NRC Engineering 3A 3B Once the turbine control valve servo control valve failure occurred, the plant engineering organization responded well 124 1/28/1998 Positive IR 97015 NRC Plant 3A SA The licensee's response to smoke from a faulted electrical generator for Support the elevator machinery room in the radiological restricted area (RRA) was done in accordar ce with plant procedures. The operators appropriately staffed the brigade, donned proper fire protection equipment and established good communication with control room personnel Following the event, the licensee appropriately initiated potential condition adverse to quality reports (PCAORs) to document concems regarding difficulty of personnel exiting the RRA due to smoke. Teamwork / Skill Level 125 1/28/1998 Positive IR 97015 NRC Engineering 3B Station Review Board members displayed good technical knowledge of the subject matter presented to them. Members solicited feedback from the sponsors of the documentation that was reviewed. The members requested additional information be provided when clarification or explanation was needed. Teamwork / Skill Level 126 1/28/1998 Negative IR 97015 NRC Maintenance SA 2B The inspectors found that surveillance procedures for smoke detectors installed in ventilation ducts were not written in accordance with the vendor's technical manual recommendations. Although the detectors were not required by 10 CFR Part 50, Appendix R, the licensee failed to meet management's expectations because a PCAOR was not initia!!y written to document this inconsistency until prompted by the inspectors.

Inadequate Procedure / Instruction Page 20 of 25

PLANT ISSUES MATRIX "'3 888 '

Davis-Besse Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date' , Beginning Date = *10/1/1997* Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 127 1/28/1998 Negative IR 97015 NRC Engineering 5B Plant engineering personnel missed an opportunity to predict a turbine control valve servo control valve failure. They were not aggressive in responding to a 30 megawatt load swing that had occurred the week before. Further, they did not gather and assess available information regarding the slow response of the turbine control valve found during previous testing. Consequently, the licensee reacted to the issue rather than managed it. Other/NA 128 12/17/1997 LER LER 97016 Licensee Operations 2B The refueling canal drain valve to the reactor cavity sump (DH92) was not locked open per the requirements of the procedure, Operation and Control of Locked Valves, to exclude it from the surveillance requirement for Emergency Core Cooling System and Containment Spray System flow path valves. The bypass valves (DH10 and DH26) for the reator coolant system to decay heat pump suction isolation valves were not included in the surveillance procedure to verify the ECCS flow path. Personnel Performance Deficiency f

129 12/10/1997 LER LER 97015 Licensee Engineering 4A i

A postulated hot short condition could cause a failure of the Emergency Diesel Generator (EDG) speed switch before the operator could manually disconnect the EDG tachometer control room circuitry from the EDG speed switch. Engineering / Design Deficiency 130 11/10/1997 Positive IR 97013 NRC Plant 1C Security personnel were observed to be performing their duties and Support access control equipment was observed to be operating in accordance with regulatory requirements. Teamwork / Skill Level 131 11/10/1997 Positive IR 97013 NRC Plant 1C Radiological conditions were properly communicated to plant personnel Support through postings, barriers and signs. Actual radiation conditions were verified to be consistent with radiation area postings. Teamwork / Skill Level 132 11/10/1997 Positive IR 97013 NRC Operations 2A "

Important-to-safety system lineups and major flowpaths were verified to be in conformance with plant procedures / drawings and the Updated Safety Analysis Report. Equipment material condition was excel lent in all cases. Teamwork / Skill Level Page 21 of 25

~

______u

PLANT ISSUES MATRIX "' SS8' Davis-Besse Search Sorted by Date (Descending) and sMM Codes (Ascending): Search Column = "Date* ; Beginning Date = *10/1/1997* . Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 133 11/10/1997 Positive IR 97013 NRC Operations 2A 3A The excellent material condition of the plant resulted in minimal operator challenges. Operators provided immediate response to plant annunciators and exhibited good adherence to procedures. On-shift communications were good. Tagouts provided adequate protection of equipment and personnel during maintenance activities. Involved Management 134 11/10/1997 Negative IR 97013 NRC Maintenance 2B The inspector noted that the implementing procedure for a technical specification surveillance test did not require that test data be recorded.

This lack of documented test data prevented supervisory personnel from having the opportunity to verify that the acceptance criteria had been met. Inadequate Procedure / Instruction 135 11/10/1997 Positive IR 97013 NRC Maintenance 3A 2B Good communications between several depertments contributed in minimizing the #2 Emergency Diesel Generator unavailability time during a routine maintenance outage. Dieselload swings observed during post maintenance surveillance testing were corrected in a timely manner.

Appropriate housekeeping, foreign material exclusion, and fire protection measures were observed. Surveillance activities were performed in conformance with written instructions, and surveillance results satisfied regulatory requirements. Teamwork / Skill Level 13G 11/10/1997 Positive IR 97013 NRC Engineering 4B Operability recommendations were technical;y sound and consistent with regulatory requirements. Plant engineering personnel pursued corrective actions relating to degraded material conditions that atfected the operability of plant components in a timely manner. Teamwork / Skill Level 137 11/10/1997 Positive tR 97013 NRC Operations 5B Management Review Committee members effectively administered the initial categorization and assignment of Potential Condition Adverse to Quality Reports. Involved Management 138 10/10/1997 Positive IR 97012 NRC Plant 1C The post accident sampling system (PASS) was effectively maintained as Support required by technical specifications. Material condition and maintenance history was tracked, individuals were trained, and the PASS samples showed good agreement with reactor coolant system samples. One i inspecticn follow-up item was opened to evaluate the long term corrective actions for a PASS configuration which resulted in an alarm of the safety features actuation system radiation monitors. (Section R2.1)

Pag? 22 of 25

PLANT ISSUES MATRIX 898' Davis-B3sco .

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* , Beginning Data = *10/1/1997* , Ending Date = *10/30/1998*

1. DATE TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 139 10/10/1997 Positive IR 97012 NRC Plant 1C There was no discemable impact on the environment from p! ant Support operations. Specific aspects of the radiological environmental monitoring program, including material condition of air sampling equipment, and sample collection were appropriately implemented. (Section R1.3) 140 10/10/1997 Positive IR 97012 NRC Plant 1C The chemistry laboratory quality control program was effective, and Support ensured that the licensee could obtain accurate chemical and radiochemical analyses. (Section R7.1) 141 10/10/1997 Positive IR 97012 NRC Plant 1C The water chemistry of primary and secondary systems was well Support maintained and monitored. Levels of corrosive impurities were maintained below industry guidelines. (Section R1.2) 142 10/10/1997 Positive IR 97012 NRC Plant SC **

The corrective actions implemented to address a violation regarding the Support failure to appropriately post a radiation area were effective in preventing <

recurrence. (Section R8.3) 143 10/2/1997 LER LER 97013 Licensee Maintenance 2B The calibration test for the Safety Features Actuation System Channel 2 containment radiation instrument string was partially performed on June 6,1996. Upon completion of the test, the Test Cover Sheet was erroneously marked and the schedule was updated to indicate the test was performed to meet the turveillance test schedule, even though the '

test was not performed in its entirety. Personnel Performance Deficiency 144 10/1/1997 Negative IR 97009 NRC Plant 1A The inspectors were concerned that, given the normal duties of the Support assistant shift supervisor, the management decision to designate the control room assistant shift supervisor as the fire watch brigade captain, could result in delays in manning the fire brigade (Section F8.1),

inadequate Oversight 145 10/1/1997 VIO/SL-IV IR 97009 NRC Operations 1C The " Conduct of Operations

• procedure granted the shift supervisor unilateral authority to allow procedural steps to be performed out-of-order. The NRC identified that this authority did not conform to the .

requirements of Technical Specification 6.5.3.1.b in that for a procedure change, a second review and approval by another member of plant management staff was not specified in the procedure

,(Section 08.1). Inadequate Procedure / Instruction 146 10/1/1997 Positive IR 97009 NRC Plant 1C Plant personnel exhibited satisfactory adherence to radiation protection  !

Support program requirements (Section R1). Teamwork / Skill Level Page 23 of 25

PLANT ISSUES MATRIX *8' Dovic-Barse -

Search Sorted by Date (Descending) and SMM Codes (Ascending): Search Column = *Date* ; Beginning Date = *10/1/1997* : Ending Date = *10/30/1998*

1. DATE _

TYPE SOURCE ID BY SALP SMM CODES DESCRIPTION 147 10/1/1997 Positive IR 97009 NRC Operations 2A Material condition of engineered safety features and important-to-safety plant systems was excellent (Section O2.1). *"""""

148 10/1/1997 Negative IR 97009 NRC Maintenance 2B Leakage integrity of the Component Cociing Water system was not verified nor were applicable acceptance criteria established for leakage between the essential and non-essential portions of the system. At the conclusion of the inspection period, engineering personnel were evaluating the need for additional integrated system leakage rate testing (Section E3.1). Inadequate Oversight t 149 10/1/1997 Positive IR 97009 NRC Maintenance 28 Maintenance and surveillance activities observed or otherwise reviewed during the inspection period were conducted in accordance with plant precedures and applicable regulatory requirements (Section M1.1).

Teamwork / Skill Level 150 10/1/1997 Negative IR 97009 NRC Operations 3A "

Communications and documentation associated with a Limiting Conditions for Operation action that was required in response to an inoperable Reactor Protection System channel was inadequate (Section 01.2). Personnel Performance Deficiency ,

151 10/1/1997 VIO/SL-IV IR 97009 NRC Engineering SC Inadequate interim corrective actions were established to address a postulated worst case Circulating Water system linebreak. Although an analysis indicated that operators would have insufficient time to respond to the break and subrequent flooding conditions, no actions were taken to

• provide additional guidance for operator response or to extend the required operator response time. This situation was determined to be a i violation of 10 CFR Part 50, Appendix B, Criteria XVI, " Corrective Actions" l (Section E8.4). Inadequate Oversight l l

Page 24 of 25  !

11/30/1998' GENERAL DESCRIPTION OF PIM TABLE LABELS

1. 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 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 Support and All/Muttiple (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 eel

• Escalated Enforcement Issue - Waiting Final NRC Action escalated enforcement action in accordance B - During Transients LER License Event Report to the NRC w ene atement of Mcy and C - Programs and Processes Licensing Licensing issue from NRR Procedure for NRC Enforcement Action (Enforcement Policy), NUREG-1600. 2 Material Condition:

Misc Miscellar,eous (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 'ndividual 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 are made. Before the NRC makes its B - Knowledge, Skills, and Abilities enforcement decrs, ion, the licensee will be URI** Unresolved inspection item C -Work Environment 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-lit Notice of Violation - Severity Level til 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

• d "

wh th n st n is a 5 Problem Identification and Resolution:

acceptabla item, a deviation, a A - Identification nonconformance, or a violation. However, B - Analysis ID BY C - Resolution the NRC has not reached its final Licensee The licensed utility conclusions on the issues, and the PIM NRC The Nuclear Regulatory Commission entrics may be modified when the final Self-Revealed Identification byp event (e.g., equipment breakdown) conclusions are made.

Other Identification ; o.own Page 25 cf 25

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