ML17265A758
| ML17265A758 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/29/1999 |
| From: | Marilyn Evans NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-98-02, NUDOCS 9910050212 | |
| Download: ML17265A758 (31) | |
Text
September 29, 1999 Dr. Robert C. Mecredy Vice President, Ginna Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
MID-CYCLEPLANT PERFORMANCE REVIEW (PPR) - GINNA
Dear Dr. Mecredy:
On September 16, 1999, the NRC staff completed the mid-cycle Plant Performance Review (PPR) of Ginna Nuclear Power Plant. The staff conducted these reviews for all operating nuclear power plants to integrate performance information and to plan for inspection activities at your facility over the next six months.
The focus of this performance review was to identify changes in performance over the past six months, and to allocate inspection resources accordingly.
We did not identify any areas in which your performance warranted additional inspection beyond the core inspection program.
Based on this review, we plan to conduct only core inspections at your facilityover the next six months and to continue our emphasis in the area of root cause and human performance evaluations, as discussed in our April 9, 1999, letter forwarding the results of the last full PPR.
Also, as is the case with all pressurized water reactors, we plan to follow up on your response to Generic Letter 98-02, "Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition."
Enclosure 1 contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIM), that were considered during this PPR process to arrive at an integrated review of licensee performance trends.
The PIM includes items summarized from inspection reports or other docketed correspondence between the NRC and Rochester Gas and Electric Corporation from October 1, 1998 to September 30, 1999. As noted above, greater emphasis was placed on those issues identified in the past six months during this performance review. The NRC does not attempt to document all aspects of licensee programs and performance that may be functioning appropriately.
Rather, the NRC only documents issues that the NRC believes warrant management attention or represent noteworthy aspects of performance.
This letter advises you of our plans for future inspection activities at your facilityso that you will have an opportunity to prepare for these inspections and to provide us pit) feedback on any planned inspections which may conflict with your plant activities. Enclosure 2 details our inspection plan through March 2000 to coincide with the scheduled implelaentation ofthe revised reactor oversight process in April2000. Resident inspections are not listed due to their ongoing and continuous nature.
'3i9'i00502i2 9'gi0929 PDR ADQCK 05000244 8
PDR OFFICIAL RECORD COPY
Robert C. Mecredy Ifcircumstances arise which cause us to change this inspection plan, we willcontact you to discuss the change as soon as possible.
Please contact me at (610) 337-5224 with any questions you may have.
Sincerely, Original Signed by:
Michele G. Evans, Chief Projects Branch 1
Division of Reactor Projects Docket No. 50-244 License No. DPR-18
Enclosures:
- 1. Plant Issues Matrix
- 2. Inspection Plan cc w/encls:
P. Wilkens, Senior Vice President, Generation Central Records (7 copies)
P. Eddy, Electric Division, Department of Public Service, State of New York C. Donaldson, Esquire, State of New York, Department of Law N. Reynolds, Esquire F. WilliamValentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority
0
Robert C. Mecredy
'istribution w/encls H. Miller, RA/J. Wiggins, DRA (1)
A. Blough, DRP W. Lanning, DRS R. Crlenjak, DRP B. Holian, DRS DRS Branch Chiefs D. Screnci, PAO M. Evans, DRP D. Chawaga, DRP W. Cook, DRP R. Junod, DRP B. Norris, DRS T. Moslak, DRS P. Frechette, DRS D. Silk, DRS DRS File Region I Docket Room (with concurrences)
PUBLIC NRC Resident Inspector Nuclear Safety Information Center (NSIC)
Distribution w/encls: (VIAE-MAIL)
W. Travers, EDO S. Collins, EDO Zwolinski, NRR B. Boger, NRR R. Borchardt, OE (2)
M. Tschiltz, Rl EDO Coordinator E. Adensam, NRR W. Dean, Chief, NRR/DISP/PIPB G. Tracy, Chief, OEDO/ROPMS T. Boyce, NRR/DISP/PIPB G. Vissing, NRR R. Correia, NRR DOCDESK Inspection Program Branch, NRR (IPAS)
DOCUMENT NAME: G:>BRANCH15PPR899$ GINNAMID-CYCLEPPRLTR.WPD
, To receive a copy ofthis document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N"= No copy OFFICE NAME DATE RI/DRP WCook 09
/99 RI/DRP RI/DRP ABlough MEvans 0
99 09/
/99 OFFICIALRECORD COP
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1 of 17 09/29/1 999 09:21:1 4 IR Report 3 Region I
GINNA Enclosure 1
United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Date Source Functional Template Area ID
'Type Codes Item Title Item Description 08/08/1 999 1 S99 006 Prl: OPS NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 1A Sec: 2B Ter: 3A Good plant staff response to the UE.
The plant staff performed well in response to an Unusual Event deda red after a small fire occurred while disassembling abandoned equipment in the auxiliary building. Poor work planning directly contributed to the event, in that, no potential combustion concerns were identified or evaluated prior to this maintenance activity, even though a plasma are (open flame) cutting tool was used.
08/08/1999 1999006 Prl: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 1C Sec: 3A
. Ter:
Operator walkaround and challenge program effective.
Overall, the operator workaround and challenge program has been effective in identifying and resolving potential operational problems. The inspector identified two equipment deficiencies that had not been evaluated as operator workarounds, one ofwhich was subsequently evaluated to be an operator challenge and properly dispositioned by the licensee.
06/24/1999 1999005 Prl: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC NEG Prl: 2B Sec: 3A Ter Root cause determinations generally satisfactory, but some reluctance to explore human performance aspec RG&E's root cause determinations were generally satisfactory.
Increased emphasis on improving the human performance evaluation portion of the root cause determination was noted. However, the effectiveness of this effort was not yet apparent, as plant events directly attributed to personnel error continued to occur.
In addition, weaknesses in licensee evaluation of an excessive overtime issue were observed.
The team also noted several examples of problems, not specifically related to human performance issues, which were not fullyanalyzed or evaluated during the root cause determination process to fullyassess all contributing factors. (Section 07.3) 06/24/1 999 1 S99005 Prl: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 2B Sec:
Ter:
Adequate Corrective Action Program.
Through the corrective action program, RG8 E identified problems at a low threshold, and appropriately prioritized the resulting action requests.
Root cause evaluations and development of corrective actions were performed.
adequately.
Man apement awareness of and involvement in the corrective action process was well evident.
Feedback mechamsms used to assess corrective action effectiveness were adequate.
Corrective actions were developed and implemented in a timely manner.
Although a formal problem trending process did not exist, efforts for improvement were noted. The corrective action program was determined to be satisfactory overall. (Section
- 07. 1 )
06/24/1999 1999005 Prl: OPS NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Satisfactory threshold for problem identification and resolution.
The Ginna Action Report (AR) program for problem identification and documentation and the Work Request/Trouble Report system were used satisfactorily to document plant deficienciesfissues.
The established threshold for issuing an AR was found to be appropriate, and it was apparent that management had effectively communicated their expectations to the staff concerning the use of the AR system.
(Section 07.2) 06/27/1 999 1 999004 Dockets Discussed:
05000244 GINNA Pri: OPS Sec: MAIN T NRC NEG Prl: 2B Sec: 3A Ter:
Operations personnel responded well to an unanticipated rod withdrawal, but the work package preparation Operations personnel responded well to an unanticipated automatic withdrawal of control rods during maintenance on the nudear instrument current comparator drawer N48. Work package preparation and review for this work activity was poor, as it did not anticipate the need for control rods to be placed in manual. Additionally, Instrumentation and Control techniaans exhibited a knowledge weakness by indicating that the comparator drawer work would not impact control rod motion. (04. 1 )
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Page:
2 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Template Item Title ID Type Codes Item Description
'7/22/1999 199840342 Pri: OPS Licensee LER Sec: ENG Dockets Discussed:
05000244 GINNA Prl: 5A ACTUATIONSOF CONTROL ROOM EMERGENCY AIRTREATMENTSYSTEM DUE TO INVALIDCAUSES Sec: 5C LER 1998403, revision 2, adequately described the licensee's response and analysis of invalid control room emergency air treatment system actuations.
The plan to replace the control room radiation monitoring system with Ter" more reliable equipment was an appropriate resolution to a longstanding problem.
05/16/1999 1999OO3 Prl: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC NEG Prl: 1A Sec: 3A Ter:
Human performance error caused April23 automatic shutdown.
A human performance error resulted in an automatic reactor shutdown from 35% power on April23, 1999. The licensee effectively evaluated the trip for its principle root causes prior to unit restart. An event investigation was appropriately initiated to examine additional human performance issues related to the event.
05/16/1999 1999003 Prl: OPS Sec: MAINT Dockets Discussed:
05000244 GINNA NRC POS Prl: 1A Effective Identification and resolution offailed RPS bistable (caused April27, 1999 scram).
Sec:
The licensee effectively identified and corrected a failed reactor protection system bistable which resulted in an automatic reactor shutdown on April27, 1999. Operator response to this plant transient was good.
Ter:
04/04/1999 1999002 Pri: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Prl: 1A Operators respond well.
Sec:
Control room operators responded well to anomalous plant conditions and performed well in controlling the plant during the shutdown and cooldown for a scheduled refueling outage.
Ter:
04/04/1999 1999002 Pri: OPS Sec: MAINT Dockets Discussed:
05000244 GINNA
'RC NEG Prl: 1C Progress made in system configuration control, but problems continued.
Sec: 2A The licensee made progress in improving system configuration controls, and the training conducted for licensed operators on past configuration control problems was a good initiative. However, several configuration control deficiencies occurred during the current refueling outage which indicate ongoing problems still existed in this area.
The new issues were entered into the licensee's corrective action program.
Dockets Discussed 05000244 GINNA 02/21/1999 1999001 Prl: OPS NRC
~
POS Prl: 1A New fuel receipt inspection Sec:
Sec: 3A Receipt inspection of new fuel was thorough and well controlled.
No notable discrepancies were noted on any of the fuel assemblies or in the licensee's documentation.
Ter:
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3 of 17 09/29/1 999 09:21:14 IR Report 3 Region I
GINNA Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX
'y Primary Functional Area/Issue Date Template Item Title ID Type Codes Item Description Dockets Discussed 05000244 GINNA 02/21/1999 1999001 Prl: OPS NRC POS Pri: 1B Operator performance during planned transients Sec:
Sec:
Operator performance during planned offsite electrical distribution system reconfigurations and normal down-power operations throughout the inspection period was good.
Ter.
02/21/1999 199900141 Pri: OPS Sec: MAINT Dockets Discussed 05000244 GINNA NRC NCV Pri: 1C Sec: 5A Ter. 5C Ineffective corrective action led to Inadvertent dilution event.
Several operational events occurred due in part to ineffective coordination and communication between operations and other organizations that were previously unidentified, and therefore not corrected, and which contributed to a reactor coolant system dilution event. Additionally, the dilution event investigation did not meet administrative requirements for timeliness, thoroughness, or sequestering of investigation personnel which contributed to inaccuracies in the investigation and the lack of an exact root cause.
However, the licensee initiated corrective actions to address deficiencies in the investigation, and in coordination and communications between operations and other departments.
Dockets Discussed 05000244 GINNA 01/10/1999 1998013 Prl: OPS NRC POS Prl: 1B Operator peformance during Power reduction Sec:
Sec:
Operations personnel performed well in during a power reduction to repair a service water leak in a main feed pump lube oil cooler. Operator perfonnance throughout the inspection period was good.
Ter:
11/29/1998 1998012 Dockets Discussed:
05000244 GINNA P~: OPS Sec:
NRC POS Pri: 1A Sec:
Ter.
Operator performance during requal was good.
The requalification written examination for licensed operators was adequate.
Job performance measures reviewed had been recently enhanced and were of good quality. Simulator scenarios were particularly effective in evaluating operator performance in that they exercIsed both the Functional Restoration and Emergency Contingency Action Procedures.
Operator performance during the requalification was good.
Dockets Discussed 05000244 GINNA 11/29/1998 1998012 Prl: OPS NRC POS Pri: 1B Operator response to partial loss of offsite power.
Sec:
Sec:
Operations personnel performed well in response to an unexpected partial loss of offsite power. The licensee effectively identified the cause of the loss, and restored power from the offsite circuit in a timely manner.
Ter:
11/29/1998 199801241 Pri: OPS NRC IFI Sec:
Dockets Discussed:
05000244 GINNA Prl: 1A Sec: 3A Ter:
Inadvertent dilution event human performance evaluation results Operations personnel responded well to an inadvertent dilution of the reactor coolant system when a mixed bed demineralizer with new resin was prematurely placed in service. At the conclusion oftte inspection period, the licensee was investigating the cause(s) of this event..
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4 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ Issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 10/30/1998 1998301 Pri: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 1C Sec:
Ter.
3 ROs and a SRO upgrade passed all portions of exam.
Three Reactor Operators (RO) and a Senior Reactor Operator Upgrade (SROUf passed ail portions of the initial license examination.
The applicants performed satisfactory on the written and simulator portions of the examination.
The applicants were well prepared for the examination, indicating that the facilityevaluated the knowledge and ability of each candidate in an effort to determine their readiness to sit for an initial NRC, RO and SROU examination.
Crew communications, control board awareness,'and crew briefings were good.
10/18/1998 1998011 Pri: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 1A Sec: 3A Ter.
Human performance eval for 8/17 inadvertent rod insertion was effective.
The human performance evaluation conducted in response to the August 17 inadvertent automatic insertion of control rods was effective in identifying procedural deficiencies and recommending appropriate inter4epartmental communications enhancements.
However, the licensee's overall corrective action response to this event to date, was weak, in that similar recent operational events were not assessed for broader human performance issues and trends.
10/18/1998 1998011 Pri: OPS Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 1A Sec: 3A Ter:
NSARB professionally conducted.
The quarterly meeting of the Nuclear Safety and Audit Review Board was professionally conducted with good indepth discussions.
The outside board members were active in the discussions and had a positive impact on the board's deliberations, and ail members displayed a good questioning attitude. The independent safety oversight function of the board was successfully accomplished.
08/06/1999 1999007 Pri: MAINT NRC POS Sec: ENG Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Failure rate of low-voltage breakers at Glnna higher than the indusby failure rate, PMs improved.
The failure rate of the low-voltage circuit breakers at Ginna was higher than the generic industry failure rate due to previous inadequate root cause analyses and corrective actions to address the repeated breaker failures. The licensee recognized these breaker issues and had established reasonable goals to improve breaker performance.
The preventive maintenance procedures were improved. The material condition of the breakers was good.
08/06/1999 1999007 Prl: MAINT NRC POS Sec: ENG Dockets Discussed:
05000244 GINNA Prl: 2B Sec: 4C Ter:
PM program on lowvoltage DB series circuit breakers improved.
The preventive maintenance program procedures for low voltage DB series circuit breakers had been improved and were found satisfactory.
The licensee had made good progress in the breaker preventive maintenance activities, and had developed an appropriate plan for future breaker maintenance.
08/06/1999 1999007 Pri: MAINT NRC POS Sec: ENG Dockets Discussed 05000244 GINNA Prl 5A Sec: 5B Ter: 5C Extensive troubleshooting, root cause evaluations, and corrective actions appropriate.
The licensee completed extensive troublesho'oting for the recent circuit breaker failures. The corrective actions taken and the root cause evaluations completed for the breaker failures were appropriate.
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5 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ Issue Date Template Item Title ID Type Codes Item Description 08/08/1999 1999006 Pri: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter.
Maintenance and surveillance activities were appropriately conducted.
Observed maintenance and surveillance activities were accomplished in accordance with procedural requirements.
The post-maintenance testing was adequate to demonstrate the operability of equipment prior to its return to service. Test procedures contained adequate details for accomplishing test requirements.
Testing was performed by knowledgeable personnel, and test instrumentation was properly calibrated.
Good troubleshooting and corrective actions were taken in response to a wiring problem identified during reactor trip breaker testing.
Dockets Discussed 05000244 GINNA 08/08/1999 1999006 Prl: MAINT NRC POS Pri: 2B Sec:
Sec: 3A Ter:
Maintenance rule expert panel critical of plant systems performance.
Members of the maintenance rule expert panel were open in their discussions, exhibited good participation, and provided critical evaluations and oversight of plant systems performance.
06/27/1999 1999004 Pri: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA P~: 1C Sec: 3A Tel".
Conduct of maintenance activities was good.
Observed maintenance activities were accomplished in accordance with procedural requirements.
The licensee's ost maintenance testing was adequate to demonstrate the operability of equipment prior to it's return to service.
est procedures contained adequate details for accomplishing test requirements.
Testing was performed by knowledgeable personnel, and test instrumentation was properly calibrated.
(M1.1) 06/27/1999 1999004 Prl: MAINT NRC POS Sec: ENG Dockets Discussed:
05000244 GINNA Pri: 2A Sec: 4C Ter: 5C Good staff response to A EDG output breaker failure.
The licensee took proper actions following discovery ofthe failed emergency diesel generator output breaker to troubleshoot, identify, and correct the breaker failure mechanism.
The licensee's broader corrective actions to review all breaker maintenance procedures for adequacy with the vendor was considered a good initiative. (M2.2) 06/27/1999 1999004 Prl: MAINT NRC NEG Sec: OPS Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Circuit 767 cable replacement went well, but the potential adverse work activity coordination was poor.
Offsite power circuit 767 cable replacement was successfully performed in a timely manner.
However, the licensee ~
demonstrated poor work coordination when activities outside the protected area, which could adversely impact the availability of the in-service offsite power circuit, were not suspended until after work on circuit 767 was commenced and after being brought to the licensee's attention by the inspectors.
(M2.1) 05/16/1999 1999003 Pa: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 1C Sec: 3A Ter.
Maintenance and Surveillance observations all positive.
Observed maintenance and surveillance activities were accomplished in accordance with procedure requirements, except for missing signatures in the procedure used to replace the delta temperature math module. That incident was properly entered into the licensee's corrective action system for resolution. The licensee's post-maintenance testing was adequate to demonstrate the operability of equipment prior to its return to service
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6 of17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE INATRIX By Primary Functional Area/ Issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 05/16/1999 1999003 Pri: MAINT NRC NEG Sec: OPS Dockets Discussed:
05000244 GINNA Prl: 1C Sec: 3A Ter.
Sucessful RTD replacement, but poor PORC oversight to ensure root cause ld'd.
The licensee successfully replaced failed resistance temperature detectors (RTDs) in the reactor coolant system, and operations personnel performed well in conducting a controlled drain<own and refillof the reactor coolant system to accommodate the replacement.
The Plant Operations Review Committee's initial recommendation to dose the RTD leakage ACTION Report (994751) without completing a root cause determination was an example of ineffective corrective action.
04/04/1999 1999002 Prl: MAINT Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 1C Sec:
Ter:
Systematic work practices and good quality repairs.
The licensee exercised systematic work practices and achieved good quality repairs during preventive maintenance inspections of plant equipment and circuit breakers.
Controlled procedures were in use at maintenance job sites, were up to date and were properly utilized by technicians involved in the outage work. The inspectors observed good personnel and plant safety practices during the maintenance work. A lower threshold for operability considerations during breaker maintenance had improved licensee identification and resolution of breaker problems.
04/04/1999 1999002 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 1C Sec: 3A Ter:
Significant programmatic improvement In the area of FME.
The licensee made significant programmatic improvements in foreign material exclusion (FME) controls, and took actions to formally incorporate previous weaknesses into their corrective action process.
During the current refueling outage, the licensee was able to identify causes for all of the FME incidents that had occurred to date, initiated corrective actions to recover the material ~ and implemented additional controls to prevent further occurrences.
04/04/1999 1999002 Prl: MAINT NRC POS Sec: ENG Dockets Discussed 05000244 GINNA Pri: 1C Sec: 3A Ter:
Good system testing activity conduct.
Test activities involving safety injection accumulator check valves, emergency diesel generators, and the residual heat removal system were well controlled, and the systems were satisfactorily tested to assure operability prior to being returned to service.
04/04/1999 1999002 Prl: MAINT Sec: ENG Dockets Discussed:
05000244 GINNA NRC POS Pri:1C Sec: 3A Ter:
ISI activities well planned and Implemented.
Inseivice inspection (ISI) activities were well planned and implemented by qualified personnel in accordance with approved procedures.
Inspector observation of nondestructive testing in progress showed that the ISI work was conducted with proper oversight by RG&E staff and the results were well documented.
The inspections observed were thorough and of sufficient extent to determine the integrity of the components inspected.
Problems were evaluated and effectively addressed in accordance with Code requirements.
02/21/1999 1999001 Pri: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 1C Sec:
Ter:
Maintenance rule expert panel Individuals on the maintenance rule expert panel asked probing questions and demonstrated a good understanding of the maintenance rule. However, no regular schedule existed for expert panel meetings, which resulted in a backlog of maintenance rule items for rewew.
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7 of 17 09/29/1 999 09:21:14 IR Report 3 Region I
'INNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 02/21/1999 1999001 Pri: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 2A Ter:
Maintenance backlog reduced The circuit breaker maintenance program for the low-voltage circuit breakers was significantly improved, and the corrective actions taken to address the recurring breaker failures were effective. The root cause analyses performed to address the breaker failures were comprehensive.
Revised maintenance procedures were clear, and detailed.
The licensee's recent practice of using reduced-control-voltage testing was good and provided a better vedfication of breaker condition during maintenance.
02/21/1999 1999001 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 3A Sec: 2B Ter:
Maintenance and surveillance work Controlled procedures were used at job sites. The procedures were up to date and were properly used by technicians involved in maintenance and surveillance work. The inspectors observed good personnel and plant safety practices.
Equipment tested met the acceptance criteria specified for operability. The acceptance criteria bases reviewed were adequate.
02/21/1999
'999001 Prl: MAINT NRC Sec:
Dockets Discussed:
05000244 GINNA POS Prl: 3A Sec: 2B Ter:
Offsite power cable replacement The cable replacement for offsite power circuit 751 was successfully performed in a timely manner.
However, the licensee's analysis to determine the effect on the performance of safety functions during this activity was deficient in that no overall change in core damage frequency was identified.
02/21/1999 1999001 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 3A Sec: 3B Ter:
Plant scaffolds Plant scaffolds appeared to be well designed and constructed in accordance with procedural requirements.
However, some confusion among the maintenance staff appeared to exist regarding the need for seismic scaffolding in areas of the turbine building near high energy piping.
Dockets Discussed 05000244 GINNA 02/21/1999 1999001 Prl: MAINT NRC POS Pri: 5A Sec:
Sec:5B Ter:
A EDG synchronization selector switch deficiency Identification The licensee effectively identified a deficiency in the synchronization selector switch forthah~ency diesel generator.
Sending the replaced switch to a materials laboratory for analysis was a good initiative-01/10/1999 1998013 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 2B Sec: 3A Ter: =
Controlled procedures used during maintenance and surveillance Controlled procedures were used at job sites.'he procedures were up to date and were properly used by technicians involved in maintenance and surveillance work. The inspectors observed good personnel and plant safety practices.
Equipment tested met the acceptance criteria specified for operability. The acceptance criteria bases reviewed were adequate.
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8 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ Issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 01/10/1999 1998013 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 5C Ter. 3A Circuit breaker maintenance The circuit breaker maintenance program for the low-voltage circuit breakers was significantly improved, and the corrective actions taken to address the recurring breaker failures were effective. The root cause analyses performed to address the breaker failures were comprehensive.
Revised maintenance procedures were dear, and detailed.
The licensee's recent practice of using reduced~ntrol-voltage testing was good and provided a better verification of breaker condition during maintenance.
01/10/1999 1998013 Dockets Discussed:
05000244 GINNA Prl: MAINT Sec:
NRC POS Pri: 3A Sec: 5B Ter. 5C Service water repairs The licensee completed an effective modification and timely repairs to restore service water (SW) valves and piping at the component cooling water and spent fuel pool heat exchangers to within allowables specified by the Code of the American Society of Mechanical Engineers.
However, the system conditions (heavy throttling, cavitation, and fluidjet impingement) that caused significant valve and pipe damage were not alleviated to prevent a recurrence over thq long term. The licensee's plans to conduct further inspections and evaluations of the SW system configuration were adequate to determine necessary long term corrective actions.
11/29/1998 1998012 Pri: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter.
Maintenance performance was good.
Controlled maintenance procedures were used at job sites. The procedures were up to date and were properly used by technicians involved in maintenance and surveillance work. The inspectors observed good personnel and plant safety practices.
Equipment tested met the acceptance criteria specified for operability. The test acceptance criteria bases reviewed were adequate, with only minor discrepancies noted.
11/29/1998 1998012 Pri: MAINT NRC NEG Sec: ENG Dockets Discussed:
05000244 GINNA Prl: 2B Sec: 3A Ter.
Troubleshooting of CR rad monitors.
The licensee's efforts to troubleshoot and repair control room radiation monitors were initiallyunsuccessful and hindered by the lack of consideration of a previously discovered equipment nonconformance item and with difficulties in procuring spare parts.
11/29/1998 199801242 Pri: MAINT Licensee NCV Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Missed surveillance ofth CV hydrogen recombiners.
The licensee's discovery of an improperly performed ITS surveillance reflected a good and detailed review of a previous outage work package..Although both hydrogen recombiners were determined to be operable, the missed surveillance represented a condition prohibited by the ITS. This license identified and corrected violation of ITS surveillance requirements was of minimal safety consequence and is being treated as a Non-Cited Violation (NCV),
consistent with Section VII.B.1 of the NRC Enforcement Policy (NCV 50-244/98-1242).
10/18/1998 1998011 Prl: MAINT NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 3A Sec:
Ter.
Good maintenance performance observed.
Controlled procedures were used at rpaintenance job sites, were up to date, and were properly used by. technicians involved in maintenance and surveillance work. The inspectors observed good personnel and plant safety.gractices.
Equipment tested met the acceptance criteria specified for operability. The acceptance criteria bases reviewekessa adequate, with only minor discrepancies noted.
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9 of 17 09/29/1 999 09:21:1 4 IR Report 3 Region I
GINNA Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Template Item Title ID Type Codes Item Description Dockets Discussed 05000244 GINNA 10/18/1998 1998011 Pri: MAINT NRC pOS Prl: 3A Effective preventive measures used during BAST level instrumentwork.
Sec:
Sec: 1C The preventive measures utilized to avoid inadvertent grounding of lifted leads were ineffective during the installation of a bistable for the boric acid storage tank level instrument.
Ter:
Dockets Discussed:
05000244 GINNA 10/18/1998 1998011 Prl: MAiNT NRC POS Pri: 3A Maintenance tech effective problem identification on A-service water pump breaker.
Sec:
Sec: 5A Maintenance technicians effectively identified problems with the A-seivice water pump circuit breaker following refurbishment by Westinghouse.
The licensee also displayed a good effort in working with Westinghouse to correct Ter.
the noted deficiencies.
08/06/1999 1999007 Prl: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 3A Engineering staff effective in Identifying and resolving technical issues.
Sec: 4B Engineering had been effective in identifying and properly resolving technical issues.
In addition, the design control, temporary modification, and corrective action procedures provided appropriate guidance for identification and Ter:
resolution of technical issues.
08/06/1 999 1 999007 Dockets Discussed:
05000244 GINNA Pri: ENG Sec:
NRC POS Pri: 3A Engineering backlog effectively managed.
Sec: 4B Engineering backlogs were being managed effectively. The new work planning and tracking program being implemented was an enhancement for engineering workload management.
Te r.
08/06/1999 1999007 Prl: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 3A Sec: 5A Ter. 5B Self-assessments had meaningful findings and results.
The self-assessment performed by Ginna personnel in the area of records management produced meaningful findings for improvement.
The independent assessments performed by outside contract organizations contributed significant findings regarding spe~dfic technical areas.
The assessments were inMepth and of high technical quality, and were conducted using developed plans, with corrective actions initiated on all findings and recommendations.
Overall, the licensee had a good self assessment program.
08/06/1999 1999007 Pri: ENG NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 4A Sec: 4C Ter:
Design data for systems and associated modifications were consistent with license basis.
The design data for the systems and components and for the design change modifications were consistent with the Ginna licensing and design bases as specified in the technical specifications, and the UFSAR. The design data for the design change modifications were controlled, documented and incorporated into the appropriate design documents.
Set point evaluations were thorough, in4epth, and technically sound.
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10of17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Functional Date Source Area Template ID Type Codes Item Title Item Description 08/06/1999 1999007 Prl: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 4B Sec:4C Ter:
TMs were properly prepared and documented.
The temporary modifications were properly prepared and documented in accordance with the station procedures.
The evaluation, installation, postmodification test requirements and safety reviews provided by engirteering presented adequate technical basis for the modifications. There were no longstanding temporary modifications at Ginna.
08/06/1999 1999007 Prl: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC POS Pri: 4B Sec: 4C Ter:
Safety evaluations well written.
Safety evaluation/review procedures were well-written documents that provided adequate guidance to determine ifa proposed activity could be implemented without prior NRC approval. With some minor exceptions, the completed safety evaluations were comprehensive and thorough. The safety evaluation training provided to technical personnel was good. The plant operation review committee's review of a safety evaluation was also good. Process controls were in place to ensure changes to the plant were reflected in design documents.
08/06/1999 1999007 Prl: ENG NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 4C Sec:
Ter.
Plant change process procedures good.
The plant change process procedures provided appropriate guidance to the engineers for dissemination of design Information. The implementation of the modification-follow-meetings and the system engineering group had resulted in improved communication of engineering information to other departments at the site.
Dockets Discussed 05000244 GINNA 08/06/1999 1999007 Prl: ENG NRC POS Pri: 5A Sec:
Sec:4C Ter:
QA audits thorough in the engineering area.
The quality assurance audits were thorough and in4epth, and resulted in good findings regarding engineering and procurement activities. The licensee adequately addressed the audit findings.
08/06/1999 199900741 Prl: ENG NRC Sec:
Dockets Discussed:
05000244 GINNA NCV Pri: 4B Sec: 4C Ter:
incorrect input for MOVweak linkanalysis.
Design change modifications were properly designed and implemented. Affected documents were appropriately updated to capture and preserve the changes in the design basis documents.
The safety evaluations provided sufficient bases to demonstrate that no unreviewed safety questions were involved in the modifications. The design change documents were well written and thorough. Supporting calculations generally presented good technical bases.
The setpoint changes were adequately evaluated and properly implemented.
However, two NCVs were identified by the NRC, one involved an incorrect design input to an motor-operated valve weak link analysis, while the other involved not promptly implementing setpoint changes.
08/06/1999 1999007-02 Prl: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC NCV Prl:4B Sec: 4C Ter. 5C Untimely corrective actions for instrument setpolnt changes.
(Same as NCV50-244/9947-01 text.)
Page:
11 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 08/06/1999 1999007-03 Pri: ENG NRC NCV Sec:
Dockets Discussed:
05000244 GINNA Pri: 5A Sec: 5C Ter.
Auxiliarybuilding postwcctdent environment.
The original auxiliary building post-accident environment calculation used non-conservative assumptions and was a nonwted violation (NCV) of 10 CFR 50, Appendix B, Criterion III, Design Control, which requires measures to provide for verifying and checking the adequacy of the design.
(Section E8.1) 08/06/1999 1999007-04 Prl: ENG Licensee NCV Sec:
Dockets Discussed:
05000244 GINNA Prl: 4B Sec: 4C Ter:
Steamline break mass and energy release analysis.
The failure to establish appropriate administrative controls over the supply of design inputs to vendors was a NCV of design control requirements contained in 10CFR 50, Appendix B, Criterion III. The licensee's immediate and long term corrective actions were comprehensive and were either completed or appropriately scheduled for completion in a reasonable time. (Section E8.5) 08/08/1999 1999006 Prl: ENG NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 4B Sec:
Ter.
Engineering staff response to algae Intrusion was good.
Engineering personnel performed well in response to an algae intrusion ofthe service water system.
The analysis performed for delta pressure limits on the emergency diesel generator (EDG) jacket water and lube oil coolers provided enhanced guidance to operations personnel for determining EDG operability.
06/24/1999 1999005 Prl: ENG NRC NEG Sec:
Dockets Discussed:
05000244 GINNA Prl: 4B Sec: 4C Ter:
Main steam non-return check valve calcs not conservative.
The assumptions, analytical methods, and calculations used by the licensee to declare the main steam non-return check valves operable may not be conservative and may not be applicable in all cases.
The licensee did not show that the uncertainty in the calculation is less than the available margin of torque needed to close the valve.
Therefore, operability of the main steam non-return check valves remains an open issue pending NRC review of additional information from RG&E. (Section E7.1)
Dockets Discussed 05000244 GINNA 06/24/1999 1999005 Prl: ENG NRC POS Prl: 4B Sec:
Sec: 3A Ter:
Operability determinations were generally acceptable.
In general, the operability determinations reviewed were acceptable.
A few of the operability determinations reached an appropriate condusion, but were not thoroughly documented.
One operability determination, regarding the main steam non-return check valves was inadequate.
(Section E7.1) 06/24/1999 1999005 Pri: ENG NRC POS Sec: MAINT Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Peer assisted self assessments were good.
The team concluded that the peer-assisted self-assessments were good; they included a strong independent perspective and numerous findings for improvement.
Corrective actions and program enhancements resulted from the assessments.
(Section E7.4
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12 of 17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Functional Template Date Source Area ID Type Codes Item Title Item Description 06/24/1 999 1 99900541 Pri: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC EEI Pri: 4B Sec: 4C Ter:
Potential USQ on changes made to main steam non-return check valve.
The team identified several inadequate safety evaluations related to changes made to the main steam non-return check valves. Specifically, the valves were changed from free swinging gravity dosing valves (as stated in the Updated Final Safety Analysis Report) to valves that required a substantial and increasing external force to close them, without addressing potential effects on steam generator integrity, containment integrity, steam generator tube integrity, reactor reactivity, or reactor vessel integrity. Other procedure changes failed to indude safety evaluations.
The team believes that changing the main steam non-return check valves to require a significant breakaway dosing torque represents an Unreviewed Safety Question.
This is an apparent violation of 10 CFR 50.59. (EEI 50-244/994)541).
The licensee did not agree that these changes introduced an Unreviewed Safety Question.
(Section E7.1 06/24/1999 1 99900542 Prl: ENG NRC Sec: MAINT Dockets Discussed:
05000244 GINNA URI
~ Pri: 1C Sec: 3A Ter:
Multiple examples of potential overtime limits being exceeded.
The inspectors identified multiple examples (April 1999) that appeared to exceed the overtime limits of the Technical Specifications.
Specifically, a maintenance technician substantially exceeded site overtime restrictions without the required written authorization. While exceeding overtime restrictions without the required authorization, the technician was involved in causing a reactor trip. This item remains unresolved pending further review by the NRC.
(URI 50-244/99-0542)
(Section E7.2)
Dockets Discussed 05000244 GINNA 06/27/1 999 1 999004 Prl: EN G NRC POS Pri: 4C Sec:
Sec:
Ter:
Engineering staff made progress to address instrument loop cal program weaknesses.
The licensee has made progress to address program weaknesses for total instrument uncertainty calculations on Improved Technical Specification related instruments.
(E8.1)
Dockets Discussed 05000244 GINNA 05/16/1999 1999003 Prl: ENG NRC POS Prl: 4B Sec:
Sec:
Ter:
Effective actions by licensee to address EDG delta peak firing pressure.
The licensee's actions were effective in reducing emergency diesel generator delta peak firing pressure and peak firing pressure to below the manufacturer's stated maximums.
05/16/1999 199900341 Prl: ENG NRC IFI Sec:
Dockets Discussed:
05000244 GINNA Prl: 4A Sec: 4B Ter:
Licensee challenged by RPS OP and OT delta temperature protection RTD mod.
The licensee was challenged with operational problems associated with a new plant modification that caused over-temperature and over-power delta temperature setpoints to drift. The licensee effectively identified and corrected some problems, and conservatively reduced reactor power white troubleshooting was in progress.
04/04/1 999 1 999002 Dockets Discussed:
05000244 GINNA Prl: ENG Sec:
NRC POS Prl: 4B Sec: 4A Ter:
Successful resolution of valve internals problems due to excessive throttling.
The licensee successfully resolved internal valve degradation that resulted from heavy throttling of a service water valve by replacing it with a smaller valve that was more resistant to erosion.
However, the system conditions that required heavy throttling of sewice water at the component cooling water heat exchangers were not yet resolved.
The licensee continued to evaluate the need to increase service water fiowto reduce siltation and erosion, and to maintain optimal componerit cooling water system temperatures.
Page:
13of17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/Issue Date Functional Template Item Title Date Source Area ID Type Codes Item Description Prl: 1C Sec: 4B 04/04/1999 1999002 Prl: ENG NRC POS Sec: MAINT Dockets Discussed:
05000244 GINNA Ter. 4A Appropriate plant modifications and well implemented.
Plant modifications installed during the current refueling outage were good enhancements to the operation and reliabilityof plant equipment.
The installation packages reviewed contained detailed instructions and information for performing and documenting the modification work. The safety evaluations reviewed were adequate to demonstrate that the modifications did not represent any unreviewed safety concerns.
Dockets Discussed 05000244 GINNA 02/21/1999 1999001 Pri: FNG NRC POS Prl: 4B Temporary modifications Sec:
Sec:
The licensee's plan to remove 21 of the current 22 temporary modifications was a good initiative.
Ter:
01/10/1999 1998013 Pri: ENG Sec:
Dockets Discussed:
05000244 GINNA NRC NEG P": 1A Sec: 4B Ter:
ITS related plant Instrument operability Deficient conditions in some improved technical specification (ITS)-related plant instruments may not have been evaluated in a timely manner for operability under the existing administrative requirements.
The licensee developed an adequate plan to evaluate instruments and instrument loops related to ITS surveillance requirements that may need unceitamty calculations developed for operability determinations when the instruments are found out-of-specification.
Dockets Discussed 05000244 GINNA 11/29/1998 1998012 Pri: ENG NRC POS Prl: 2B 1997 self-assessment of SW system good.
Sec:
Sec: 5A Technical items from a 1997 self-assessment of the service water system were appropriately prioritized and addressed in the licensee's corrective action program.
Ter:
Dockets Discussed 05000244 GINNA 11/29/1998 1998012 Prl: ENG NRC POS Prl:.4B GL 89-13 program is closed.
Sec:
Sec: 4C The licensee established appropriate tests and maintenance tasks for service water system components consistent with the requested actions of NRC Generic Letter 89-13, "Service Water System Problems Affecting Safety-Related Equipment."
11/29/1998 199801243 Prl: ENG Sec: MAINT Dockets Discussed:
05000244 GINNA NRC IFI Prl: 2B Sec:
Ter:
RG&E to review prewonditioning of valves before IST testing.
The Inservice Test (IST) Program was well designed and implemented.
Program documents and implementing procedures were easy to use, technically correct, and updated to reflect industry developments.
Valves in the selected systems were tested in accordance with ASME Code requirements and NRC-approved relief requests.
Pre~nditioning of selected service water containment isolation valves prior to leakage testing may be inconsistent with industry guidance and is under review by the RG&E staff (IFI 50-244/98-12%3).
IST Program personnel were knowledgeable, and the condition monitoring program was effective. Discrepancies regarding program scope and testing of relief valves were of minor importance and were appropriately addressed by RG &E.
Page:
14of17 09/29/1 999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ Issue Date Functional Template Date Source Area ID Type Codes Item Title Item Description Dockets Discussed 05000244 GINNA 10/18/1998 1998011 Prl: ENG NRC POS Prl: 4B Improvement noted in the 50.59 process documentation.
Sec:
Sec: 4C The licensee had a strong 10 CFR 50.59 determination process in place. There had been a noticeable improvement in the quality ofthe documentation of the bases for evaluating the three criteria for an unreviewed safety question.
Ter:
08/08/1999 1999006 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Radwaste management and transportation programs were adequately implemented.
The radioactive waste management and transportation programs were adequately implemented as evidenced by a qualiTied staff carrying out detailed procedures.
Radioactive waste and other radioactive materials were properly characterized, dassified, packaged, and shipped.
The licensee was evaluating various technologies to process and ship for disposal contaminated filtermedia that was classified as containing greater than Type C concentrations of radioactive materials.
08/08/1999 1999006 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Tef:
Waste processing, handling, and shipping was well executed.
Waste processing, handling, and storage areas were orderly, and containers were properly labeled and secured.
A minor violation associated with the failure to post the waste evaporator room as a high contamination area was identified and included in RG&E's corrective action program.
Dockets Discussed 05000244 GINNA 08/08/1999 1999006 'rl:PLTSUP NRC POS Prl: 2B Sec:
Sec: 3A Ter.
Staff Involved with radwaste handling and shipping were well qualified and trained.
Personnel involved in waste handling and shipping activities have received the training required by NRC Bulletin 79-19 and 49 CFR 172, Subpart H. The staff was properly trained, qualified, and experienced.
08/08/1999 1999006 Pri: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 2B Sec: 3A Ter:
Appropriate quality control measures In the radwaste area.
Performance of radwaste management and shipping activities was effectively monitored and potential problem areas were elevated to the appropriate management level for resolution through various management controls, including audits, self-assessments, and quality control suiveillances.
06/27/1999 19990044)1 Pri: PLTSUP Sec:
Dockets Discussed:
05000244 GINNA NRC NCV Prl:
Sec:
Tel UNPLANNED RADIOLOGICALEXPOSURES Licensee management identified, atter the fact, a series of unplanned exposure events that were the result of deficiencies in the implementation of radiological controls, contrary to Improved Technical Specification 5.7.
In accordance with the established corrective action process, the licensee conducted a root cause assessment and completed (or planned) appropriate corrective actions to prevent a recurrence.
However, the corrective actions following the individual events were not effective, in that they did not prevent recurrence of the subsequent unplanned exposure events.
In addition, the overall series of events represented an indifference to proper-radiologicai controls and precautions on the part of the individual radiation workers, radiation protection. technicians, and direct supervision involved in the events.
The violation of Improved Technical Specifications was non~ted (R8.1)
Page:
15of17 09/29/1999 09:21:14 IR Report 3 Region I
GINNA United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/ Issue Date Date Source Functional Area Template ID Type Codes Item Title Item Description 05/16/1999 1999003 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 1C Sec: 3A Ter:
Radiological work controls during recent outage were appropriate.
Overall, the licensee's radiological work and boundary controls inside containment during the recent outage were effective in maintaining personnel exposures and contaminations at reasonably low levels. The pre-outage exposure and contamination goals were slightly exceeded at the end of the outage; however, the licensee maintained an acceptable level of oversight and control in this area.
04/04/1999 1999002 Pri: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 1C Sec: 3A
'.Ter:
ALARAprogram well implemented.
"As LowAs Reasonably Achievable" (ALARA)program requirements were well developed, integrated in the work control process, and effectively implemented with respect to the in-service inspection of reactor components.
Dose levels received by individuals and work groups were closely monitored by the ALARAgroup. Dose information was provided to management for timely resolution of emergent issues, resulting in cumulative doses below estimates.
04/04/1999 1999002 Pri: PLTSUP NRC Sec:
Dockets Discussed:
05000244 GINNA POS Prl: 1C Sec: 3A Ter:
Radiological controls program was well implemented.
The radiological controls program was effectively implemented by qualified and experienced staff properly implementing detailed procedures and radiation work permits, appropriately monitoring personnel exposur'e
~ and adequately maintaining radiologically controlled areas.
Work performance standards were effectively monitored and reinforced by dose and frequent management and quality assurance oversight. Off-normal conditions were conservatively identified, appropriately evaluated, and resolved in a timely manner.
04/04/1999 1999002 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 1C Sec: 3A Ter.
Security and safeguards activities well conducted.
The licensee conducted security and safeguards activities in a manner that protected public health and safety in the areas of access authorization, alarm stations, communications, and protected area access control of personnel, packages and vehicfes.
Security facilities and equipment were well maintained and reliable and were able to meet the licensee's commitments and NRC requirements.
Security force members had the requisite knowledge to effectively implement the duties and responsibilities of their position(s).
04/04/1999 1999002 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl:1C Sec: 3A Ter:
Management support of the security program evident.
Management support was adequate to ensure effective implementation of the security program. The licensee's audits were comprehensive in scope and depth, that the audit findings were reported to the appropriate level of management, and that the program was being properly administered.
In addition, a review of the documentation applicable to the self-assessment program indicated that the program was being effectively implemented to identify and resolve potential weaknesses.
Dockets Discussed 05000244 GINNA 01/10/1999 1998013 Prl: PLTSUP NRC POS Pri: 3A Sec:
Sec:
Ter:
Severe Accident Mitigation Drill The Severe Accident Mitigation drillappeared well planned, with good coordination noted between personnel in the simulator and the Technical Support Center. Operator performance during the exercise was good.
Page:
16 of 17 09/29/1 999 09:21:1 4 IR Report 3 Region I
GINNA Date Source Functional Area United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Template Item Title ID Type Codes Item Description Dockets Discussed 05000244 GINNA 1 1/29/1 998 1 998012 Pri: PLTSUP NRC POS Pri: 2B RP controls and RP management oversight good.
Sec:
Sec:
Radiological controls and postings in the auxiliary building were adequate.
Radiation Protection management tours were effective in the identification and resolution of radiological deficiencies.
Ter:
10/18/1998 199801 'I Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Prl: 2B Sec:
Ter.
Adequate implementation of radiation monitoring system and instrument calibration programs.
The licensee established, implemented, and maintained an adequate radiation monitoring system program for radiological instrument calibrations and reliability, and performance tracking and trending. The ventilation system suiveillance program was adequate with respect to charcoal adsorption surveillance tests, HEPA mechanical efficiency tests, and air flowrate tests.
10/18/1998 1 99801 1 Prl: PLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec:
Ter:
The quality control program to validate measurement results for radioactive effluent samples was effective. The licensee also established and implemented an effective quality assurance audit of the radioactive effluent control program.
10/18/1998 199801 1 Prl: pLTSUP NRC POS Sec:
Dockets Discussed:
05000244 GINNA Pri: 2B Sec: 3A Ter:
Effective implementation of radwaste management and transportation programs.
The licensee effectively implemented radioactive waste management and transportation programs with an experienced staff who systematically adhered to clearly written and detailed procedures.
Radioactive waste and other radioactive materials shipped during the period of January through September 1998 were properly classified and packaged.
Areas containing radioactive wastes and contaminated materials were properly surveyed, posted, and controlled.
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17 of 17 09/29/1999 09:21:14 IR Report 3 United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area/Issue Date Legend Type Codes:
BU Bulletin CDR Construction DEV Deviation EEI Escalated Enforcement Item IFI Inspector follow-up item LER Licensee Event Report LIC Licensing Issue MISC Miscellaneous MV MinorViolation NCV NonCited Violation NEG Negative NOED Notice of Enforcement Discretion NON Notice of Non-Conformance OTHR Other P21 Part21 POS Positive SGI Safeguard Event Report STR Strength URI Unresolved item VIO Violation WK Weakness Template Codes:
1A Normal Operations 1B Operations During Transients 1C Programs and Processes 2A Equipment Condition 2B Programs and Processes 3A Work Performance 3B KSA 3C Work Environment 4A Design 48 Engineering Support 4C Programs and Processes 5A Identification 5B Analysis 5C Resolution ID Codes:
NRC NRC Self Self-Revealed Licensee Licensee Functional Areas:
OPS Operations MAINT Maintenance ENG Engineering PLTSUP Plant Support OTHER Other EEls are apparent violations of NRC Requirements that are being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action" (Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the EEls and the PIM entries may be
'odified when the final decisions are made.
URls are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation. A URI may also be a potential violation that. is not likelyto be considered for escalated enforcement action. However, the NRC has not reached its final conclusions on the issues, and the PIM entries may be modified when the final conclusions are made.
Page 1 of 1 09/28/1999 14:36:36 mts nspec on ctrvity i e Enclosure 2
GINNA Inspection / ActivityPlan 10/01/1999 - 03/31/2000 um ero Inspectors / Individuals anne a es Start End nspec ion Type IP 71001 IP 84750 IP 82301 IP 84750 IP 2515/142 IP 83750 Licensed Operator Requalification Program Evaluation Radioactive Waste Treatment, And ENuent And Environmental Monitoring Evaluation Of Exercises For Power Reactors Radioactive Waste Treatment, And ENuent And Environmental Monitoring Draindown During Shutdown and Common-Mode Failure (NRC GL 9842)
Occupational Radiation Exposure 10/04/1999 10/25/1999 11/15/1999 11/15/1999 12/13/1999 01/24/2000 10/08/1999 10/29/1999 11/19/1999 11/19/1999 12/17/1999 01/28/2000 Core Core Core Core Safety Issues Core is repo oes no in u e an a
ivi ies.
This ronnrt chnws nnlv nn-site and Announced insoection orocedures.
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