ML17261A799
| ML17261A799 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/15/1988 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8901040088 | |
| Download: ML17261A799 (43) | |
Text
g 5 OEC1988 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN:
Mr. Robert C. Mecredy General Manager Nuclear Production 49 East Avenue Rochester, New York 14649 Gentlemen:
Subject:
Self Assessment Initiatives Region 'I is aware that many licensees have implemented or are planning
'to conduct self-assessment programs to enhance their awareness of the effectiveness of activities that could affect safe plant operations.
NRC fully supports-such initiatives and is interested in factoring consideration of such programs i.nto our inspection program planning for future SALP cycles.
To that end, I request that you provide the NRC, via the Senior Resident Inspector, your current schedule including dates and topics for self-assessment activities.
Additionally, at future SALP management
- meetings, we request that you provide your best estimate for self assessment activities to be conducted in the next SALP period.
In this way, we will better be able to schedule our inspection activities avoiding conflicts and making more productive use of available inspection resources.
This request does not constitute a regulatory requirement, but rather it is made in an attempt to enhance NRC's inspection process by giving appropriate consideration to licensee self-assessment initiatives.
Should you have any questions regarding this request, please feel free to contact either me or the responsible Region I DRP Branch or Section Chief
'or your facility.
Thank you for your cooperation with us in this matter.
Sincerely, am n,
rector Division of Reactor Projects I
~/
OFFICIAL RECORD COPY SCHED LTR 0034.0.0 10/19/88 8S'01040088 881215 PDR ADQCK 05000244 G
PNV
P tQ QE
Rochester Gas and Electric Corporation 2
N 15 OEC888 CC:
Harry H. Yoigt, Esquire Central Records (4
copies)'irector, Power Division State of New York, Department of Law W. Russell, RA B. Boger, NRR Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York bcc:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief C. Stahle, PM, NRR Robert J.
- Bores, DRSS S. Ebneter, ORSON T. Martin, ORSON DRP Branch Chiefs G. Kelly, TSS OFFICIAL RECORD COPY SCHED LTR 003S.O.O 10/19/88
Ps g Ae
Distribution Sheet ipse Distri59.txt il, Priority: Normal From: Elaine Walker Action Recipients:
RidsNrrPMGVissing RidsNrrDlpmLpdi1 Internal Recipients:
RidsOgcRp RidsNrrDripRexb RidsEdoMailCenter OE
~ILK CENTER COlllmiSSTO ACRS Copies:
0 0
OK OK OK 0
OK 0
OK Paper Copy Paper Copy Paper Copy Paper Copy External Recipients:
NOAC INEEL Marshall Paper Copy Paper Copy Total Copies:
6 Item: ADAMS Package Library: ML ADAMS"HQNTAD01 ID: 003695377
Subject:
Plant Performance Review - Ginna Letter Body:.
ADAMS DISTRIBUTION NOTIFICATION.
Electronic Recipients can RIGHT CLICKand OPEN the firstAttachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003695377.
Page 1
Distri59.txt lE40 - Systematic Assessment of Licensee Performance (SALP) Report Docket: 05000244 Page 2
0
March 31, 2000 Dr. Robert C. Mecredy Vice President, Ginna Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
SUBJECT:
PLANT PERFORMANCE REVIEW-GINNA
Dear Mr. Mecredy:
The purpose of this letter is to communicate the NRC's assessment of Ginna performance and to inform you of our planned inspections at the facility. On February 24, 2000, we completed a Plant Performance Review (PPR) of Ginna Station. We conducted this review to develop an
. integrated overview of the safety performance of the plant. We used the results of the PPR in planning and allocating inspection resources and as an input to our senior management meeting (SMM) process.
This PPR evaluated inspection results and safety performance information for the period from January 16, 1999, through January 31, 2000, but emphasized the last six months to ensure that our assessment reflected your current performance.
Our previous summary of plant performance at Ginna was provided to you in a letter dated April 9, 1999.
The NRC has been developing a revised reactor oversight process that will replace our existing inspection and assessment processes, including the PPR, the SMM, and the Systematic Assessment of Licensee Performance (SALP). We recently completed a pilot program for the revised reactor oversight process at nine participating sites and are making necessary adjustments based on feedback and lessons learned.
We plan to begin implementation of the revised reactor oversight process industry-wide on April2, 2000.
This PPR reflects continued NRC process improvements as we make the transition into the revised reactor oversight process.
The following summary of plant performance is organized differently from our previous performance summaries.
Instead of characterizing qur assessment results by SALP functional area, we organized the results into the strategic performance areas embodied in the revised reactor oversight process.
In assessing your performance, we have considered the historical performance indicator data that you submitted in January 2000 in conjunction with our inspection results.
The results of this PPR were used to establish the inspection plan in accordance with the new risk-informed inspection program (consisting of baseline and supplemental inspections).
Although this letter incorporates some terms and concepts associated with the'new oversight process, it does not reflect the much broader changes in inspection and assessment that will be evident after we have fully implemented our revised reactor oversight process.
g(- j Loot<<~~
Q,f qpg-NLQD34 I~~7 OFFICIAL RECORD COPY Lkr-kLoo'h >q1rk<
I E: 40
0 0
I
~ gI'll
Robert C. Mecredy During the last six months of the assessment period, Ginna operated at or near full power. We have not identified any significant performance issues in any of the strategic performance areas (reactor safety, radiation safety, and safeguards) during this assessment period and observed that Ginna continued to operate in a safe manner.
Ginna plant operators exhibited effective day-to-day operations of the unit and appropriate response to unplanned events.
Plant operations were effectively supported by the maintenance and engineering department staffs. Human performance was improved and the corrective action program was adequately implemented.
No significant performance issues were noted in the implementation ofthe emergency preparedness program. As a result, only normal baseline inspections are currently planned in the reactor safety strategic performance area.
We identified no significant performance issues in either the radiation safety or safeguards strategic performance areas.
As a result, only normal baseline inspections are currently planned in these areas.
\\
, Enclosure 1 contains a historical listing of plant issues, referred to as the Plant Issues Matrix (PIM), that were used during this PPR process.to arrive at our integrated view of your performance trends:
The PIM for this assessment is grouped by the prior SALP functional areas of operations, maintenance, engineering, and plant support, although the future PIM willbe organized along the cornerstones of safety as described in the revised reactor oversight process.
The PIM includes items summarized from inspection reports or other docketed.
correspondence between the NRC and Rochester Gas and Electric Corporation regarding Ginna. We did not document all aspects of licensee programs and performance that may be functioning appropriately.
Rather, we only documented issues that we believe warrant management attention or represent noteworthy aspects of performance.
In addition, the PPR may also have considered some pre-decisional and draft material that does not appear in the attached PIM, including observations from events and inspections that had occurred since our last inspection report was issued, but had not yet received full review and consideration.
We will make this material publically available as part of the normal issuance of our inspection reports and other correspondence. lists our planned inspections for the period April 2000 through March 2001 at Ginna to allow you to resolve scheduling conflicts and personnel availability in advance of our inspector
. arrival onsite.
Since many of the inspections at Ginna and at the other Region I facilities during this period involve a team of inspectors, our ability to reschedule inspections is limited.
Therefore, we request you inform us as soon as possible of any scheduling conflicts.
The inspection schedule for the latter half of the period is more tentative and may be adjusted in the future due to emerging performance issues at Ginna or other Region I facilities. Routine resident inspections are not listed due to their ongoing and continuous nature.
0
\\
i
Robert C. Mecredy 3
We willihform you of any changes to the inspection plan. Ifyou have any questions, please contact me at (610) 337-5224.
Sincerely,
/RA/
Michele G. Evans, Chief Projects Branch 1
Division of Reactor Projects Docket No. 05000244 License Nos. DPR-18
Enclosures:
- 1. Plant Issues Matrix
- 2. Inspection Plan Docket No. 05000244 License No. DPR-18 cc w/encis:
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. William Valentino, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority
Robert C. Mecredy Distribution w/encls:
H. Miller, RA/J. Wiggins, DRA (1)
A. Blough, DRP W. Lanning, DRS R. Crlenjak, DRP B. Holian, DRS D. Screnci, PAO N. Sheehan, PAO M. Evans, DRP DRS Branch Chiefs (5)
W. Cook, DRP NRC Resident Inspector S. Chaudhary, DRS B. Norris, DRS T. Moslak, DRS P. Frechette, DRS D. Silk, DRS M. Oprendek, DRP R. Junod, DRP Region I Docket Room (with concurrences)
PUBLIC Nuclear Safety Information Center (NSIC)
Distribution w/encls (VIAE-!NAIL):
W. Travers, EDO S. Collins, NRR J. Zwolinski, NRR B. Boger, NRR R. Borchardt, OE (2)
J. Shea, Rl EDO Coordinator Chief, NRR/DIPM/IIPB(RIDSNRRDIPMLIPB)
Chief, OEDO/ROPMS E. Adensam, NRR (RIDSNRRDIPMLPDI)
G. Vissing, NRR W. Scott, NRR J. Wilcox, NRR DOCDESK Inspection Program Branch, NRR (IPAS)
DOCUMENT NAME: S:hFEBRUARY2000 PPR<GINNA PPR letter 3-28-00.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI /DRP RI/DRP RI/DRP NAME WCook MEvans RCrlenjak DATE 03/pf/00 03/~00 03 00 OFFICIALRECORD COPY
Page:
1of19 03/29/2000 07:00:32 IR Report 3 Region I
GINNA Date Source Functional Area Enclosure 1
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 Tel".
01/23/2000 1999012 Pri: OPS NRC POS Pri: 3A Sec:
Sec:
Conduct of operations was professional and safety-conscious.
In general, the conduct of operations was professional and safety~nscious. The cold weather inspection program was effectively implemented to ensure systems, structures, and components important to the safe operation of the reactor plant were adequately protected from freezing. The weekly walkdown cheddist, performed on January 9, 2000, effectively verified the required freeze protection measures were in place. The cold weather waikdown procedure was adequately written and provided dear guidance to the user (Sections 01.1 and 02.1).
01/23/2000 1999012 Pri: OPS NRC NEG Sec: MAINT Dockets Discussed:
6 05000244 Ginna Prl: 3A Sec:
Ter.
Testing of Sl accumulator isolation valves not initiallyconservative.
The change in philosophy pertaining to testing of the safety injection accumulator isolation valves quarterly vice in cold shutdown (resulting in at power testing) was not rigorously challenged within the organization. Though not prohibited, the decision to test the valves quarterly would have increased to a small extent the overall plant risk with no added safety benefit. The decision, rooted in a narrowly focused interpretation of the guidance contained in NUREG-1482, Guidelines for Inseivice Testing at Nudear Power Plants, was subsequently reversed when challenged by the inspectors (Section 01.2).
01/23/2000 1999012 Pri: OPS NRC POS Sec: MAINT Dockets Discussed:
05000244 Ginna Pri: 3A Sec: 5C Ter:
Corrective actions to improve configuration controls and human performance have been effective.
The inspectors concluded that RG&E's corrective actions to prevent recurrence of configuration control and human performance errors (inspector follows item 05000244/199701041) were adequate. Though not entirely successful in preventing r~rrence, performance has improved and station management has continued to maintain improvement In human performance a priority (Section 08.1).
Dockets Discussed 05000244 Ginna 12/12/1999 1999011 Pri: OPS NRC POS Prl: 1A Sec:
Sec: 2A Ter. 2B System configuration and material condition was good.
The preferred and standby auxiliary feedwater (SAFW) systems were capable of performing their-safety functions.
Overall material condition of the systems was good.
However, RG&E personnel did not properly update an associated system alignment procedure to reflect current SAFW system configuration (Section 02.1).
Dockets Discussed:
05000244 Ginna Ter.
12/12/1999 1999011 Pri: OPS NRC POS Prl: 1A Sec:
Sec: 3A Conduct of operations was professional and safetywonsclous.
In general, the conduct of operations was professional and safety~nscious.
Ginna's plant operations review committee thoroughly evaluated two emergent plant issues, and recommended sound corrective actions. The action report screening committee appropriately reviewed other plant Issues that were documented through the corrective action program (Sections 01.1 and 07.1).
10/31/1999 1999009 Pri: OPS NRC POS Pri: 1A Operator response to a service water leak inside containment was good.
Sec:
Sec: 3A Operators responded well to a service water leak Inside containment and an unexpected loss of pressurizer proportional heaters.
(02.1 and M2.1)
Dockets Discussed 05000244 Ginna item Type (Compliance,Foliowup,other), From 01/16/1999 To 01/31/2000
Page:
2of19 03/29/2000 07:00:32 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 10/31/1999 1999009 Pri: OPS Sec:
Dockets Discussed:
05000244 Ginna NRC POS Prl: 2B Sec: 3A Ter.
Effective training provided to licensed operators.
Overall, RG&E personnel were effectively providing training for ficensed operators and evaluating their performance.
The licensed operator requalification training program met regulatory requirements with no significant weaknesses identified.
Program content was balanced and incorporated risk insights, and met the needs of the operators.
Evaluations of simulator scenarios and job performance measures by the training department staff and operations department managers were objective and thorough. Training on plant speciTic and selected industry events was well prepared and presented.
(05.1)
Dockets Discussed 05000244 Ginna 10/31/1999 1999009 Prl: OPS NRC POS Pri: 2B Sec:
Sec: 3A Ter.
Nuclear Safety Audit and Review Board provided good Insights to line management.
The Nudear Safety Auditand Review Board convened in accordance with station guideHnes, and its board members provided good insights to line management and sufficiently challenged the manner in which station activities were being performed.
(07.1) 09/19/1999 1999008
-. Pri: OPS Sec: ENG Dockets Discussed:
05000244 Ginna NRC POS Prl: 2B Sec:
Ter.
Good licensee response to Westinghouse tech bulletin on DB-50 breakers.
The licensee responded well to a Westinghouse technical bulletin indicating that DB-50 circuit breakers may fail to dose, ifrequired, during a seismic event.
Placing this issue on the operator workaround list until modiTications to the breakers were completed and expanding the review of potential breaker susceptibHity to DB-25 and DB-75 breakers were good initiatives.
(02.1)
Dockets Discussed:
05000244 Ginna Ter.
09/19/1999 1999008 Pri: OPS NRC POS Pri: 1A Sec: MAINT Sec: 2B Adequate implementation of protective tagouts process.
The licensee adequately implemented the tagout processes and has taken proper action to enter longstanding tagouts into their corrective action program for resolution. A sample of tagouts inspected in the plant were determined to have been hung in accordance with the tagging requirements.
The inspectors identified some minor administrative discrepancies with tagging documentation that were appropriately entered into the licensee's corrective action program for resolution.
(02.2)
Dockets Discussed:
05000244 Ginna
.~Jr. 3A 08/08/1999 1999006 Pri: OPS NRC POS Prl: 1A Sec:
Sec: 2B Good plant staff response to the UE.
The plant staff performed well in response to an Unusual Event declared 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 yctivity, even though a plasma arc (open flame) cutting tool was used.
08/08/1999 1999006 Prl: OPS NRC POS Sec:
Dockets Discussed:
05000244 Ginna Pri: 1C Sec: 3A Ter.
Operator walkaround and challenge program effective.
OveraH, the operator workaround and chaffenge 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 of which was subsequently evaluated to be an operator challenge and properly dispositioned by the licensee.
Item Type (Compliance,Foffowup,Other), From 01/16/1999 To 01/31/2000
Page:
3of19 03/29/2000 07:00:32 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 Typo Codes Item Title Item Description 06/24/1999 1999005 Pri: OPS NRC Sec:
Dockets Discussed:
05000244 Ginna NEG Prl: 2B Sec: 3A Ter.
Root cause determinations generally satisfactory, but some reluctance to explore human performance aspects 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) 06/24/1999 1999005 Pri: OPS Sec:
Dockets Discussed:
05000244 Ginna NRC POS Pri: 2B Sec:
Ter:
Adequate Corrective Action Program.
Through the corrective action program, RG&E identiTied problems at a kiwthreshold, and appropriately prioritized the resulting action requests.
Root cause evaluations and development of corrective actions were performed adequately.
Management awareness of and involvement in the corrective action process was well evident.
Feedback mechanisms 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)
Dockets Discussed 05000244 Ginna 06/24/1999 1999005 Prl: OPS NRC POS Pri: 2B Sec:
Sec: 3A Ter:
Satisfactory threshold for problem Identification and resolution.
The Ginna Action Report (AR) program for problem IdenNication and documentation and the Work Request/Trouble Report system were used satisfactorily to document plant deficiencies/issues.
The established threshold for issuing an AR was found to be appropriate, and itwas apparent that management had effectively communicated their expectations to the staff concerning the use of the AR system.
(Section 07.2) 06/27/1999 1999004 Prl: OPS Sec: MAINT Dockets Discussed:
05000244 Ginna NRC NEG Prl: 2B Sec: 3A Ter:
Operations personnel responded weil 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 nuclear 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 technicians exhibited a knowledge weakness by indicating that the comparator drawer work would not impact control rod motion. (04.1) 07/22/1999 199800302 Pri: OPS Licensee Sec: ENG Dockets Discussed:
05000244 Ginna LER Prl: 5A Sec: 5C Ter:
ACTUATIONSOF CONTROL ROOM EMERGENCY AIRTREATMENTSYSTEM DUE TO INVAUDCAUSES LER 1998003, 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 more reliable equipment was an appropriate resolution to a longstanding problem.
05/16/1999 1999003 Dockets Discussed:
05000244 Ginna Pri: OPS Sec:
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 ffcensee 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. (02.2) Reference LER 9947 and LER 9947, suppl 01 ~ reviewed and dosed in IR 9S48, section 08.2 Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000
Page:
4of19 03/29/2000 07:00:32 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 Ter.
05/16/1999 1999003 Pri: OPS NRC POS Prl: 1A Sec: MAINT Sec:
Effective identification and resolution of failed RPS bistable (caused April27, 1999 scram).
The licensee effectively identified and corrected a failed reactor protection system bistable which resulted In an automaticreactorshutdownonApiil27,1999.
Operatorresponsetothisplanttransientwasgood.
(02.3) Reference LER 9948, reviewed and dosed in IR 9948, section 08.3.
05/21/1999 199940640 Dockets Discussed:
05000244 Ginna Pri: OPS Sec: MAINT Licensee LER Pri:
VALVE IN UNEXPECTED POSITION RESULTS IN START OF TURBINE-DRIVENAUXIUARYFEEDWATER PUMP a Sec:
lnadeveitant start ofTDAFWP was a self~vealing event caused by aninadequate test procedure and poor communications betweeen personnel Involved with the test.
Reference IR 9948, section 08.1.
04/04/1999 1999002 Pri: OPS NRC POS Pri: 1A Operators resPond well.
Sacr Sec:
Control room operators responded well to anomalous plant conditions and performed well h controlling the plant during the shutdovm and cooldown for a scheduled refueling outage.
Dockets Discussed 05000244 Ginna Dockets Discussed 05000244 Ginna 04/04/1999 1999002 Pri: OPS NRC NEG Pri: 1C Sec: MAINT Sec: 2A Ter:
Progress made in system configuration control, but problems continued.
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 degciencies occurred dyring the current refueling outage which indicate ongoing problems still existed in this area.
The nevussues were. entered kito the licensee's orrective action program.
03/29/1999 199940240 Pri: OPS Sec:
Dockets Discussed:
05000244 Ginna Licensee LER Pri:
SURVEILLANCENOT PERFORMED, DUE TO PERSONNEL ERROR, RESULTED IN VIOLATIONOF TS Sec:
ucensee kfentified suivellance oversight, caused by operator error. TS surveillance violation not subject to formal enforcement action. Reference IR 9942 Section 08.1.
02/21/1999 1999001 Pri: OPS NRC POS Pri: 1A New fuel receipt inspection Sec:
Sec: 3A Receipt inspection of new fuel was thorough and weil controlled. No notable discrepancies were noted on any of the fuel assemblies or in the licensee's documentation.
Dockets Discussed 05000244 Ginna Item Type (Compliance,Folkiwup,Other), From 01/16/1999 To 01/31/2000
Page:
5of19 03/29/2000 07:00:32 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 02/21/1999 1999001 Pri: OPS
~ NRC POS Sec:
Dockets Discussed:
05000244 Ginna Pri: 1B Sec:
Ter:
Operator performance during planned transients Operator performance during planned offsite electrical distribution system reconfigurations and normal dower operations throughout the inspecbon period was good.
02/21/1999 199900141 Pri: OPS NRC NGV Sec: MAINT Dockets Discussed:
05000244 Ginna Prl:1C Ineffective corrective action led to inadvertent dilution event.
Sec: 5A Ter. 5C 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 coohnt system di1ution 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 defidencies in the investigation, and in coordination and communications between operations and other departments.
01/23/2000 1999012 Prl: MAINT Sec: OPS Dockets Discussed:
05000244 Ginna NRC POS Prl: 1A Sec:
Ter.
Appropriate performance of maintenance and surveillance testing.
Personnel effectively performed the observed maintenance and surveiiance activities in accordance with a pproved procedures.
Emergent maintenance activities associated viith an instrument air leak on a main feedwater regulating valve positioner were adequately evaluated and properly executed (Sections M1.1 and M2.1).
Conduct of surveillance procedure PT-16Q-T, AuxTiiaiyFeedwater Turbine Pump OperabTiity, was well coordinated, properly controlled, and adequately demonstrated the ability of the turbine driven auxiliary feedwater pump to provide feedwater to the steam generators.
However, the Inspectors noted that the test sequence did not perform the stroke time test of the turbine steam admission valves in the as-found condition with no pre-test stroMng as required by IP-IIT-2, lnservice Testing Program for Pumps and Valves, (Section M1.2).
11/23/1999 199901241 Pri: MAINT NRC NCV Sec: ENG Dockets Discussed:
05000244 Ginna Pri:
Sec:
Ter.
OPENING CONTROL ROOM VENTILATIONSYSTEM FOR FILTER REPLACEMENT RESULTED IN PLANTBEING 0 Maintenance activities on the control room ventihtion system placed the plant outside its design basis during numerous occasions partially because system design Information was not properly incorporated into maintenance procedures.
This violation of NRC requirements was norHxted. Additionally, the root cause analysis presented in the associated licensee event report was narrowly focused since it did not address potential human performance deficiencies.
RG&E's immediate and planned corrective actions were adequate (Sedion M8.1).
Dockets Discussed 05000244 Ginna 12/12/1999 1999011 Pri: MAINT NRC POS Prl: 2B Sec:
Sec: 3A Ter.
Licensee personnel effectively performed selected maintenance and testing activities.
RG&E personnel effectively performed selected maintenance and surveillance activities in accordance with approved procedures and station requirements (Section M1.1).
Dockets Discussed 05000244 Ginna 12/12/1999 1999011 Pri: MAINT NRC POS Pri: 2B Sec:
Sec: 3A Ter.
Corrective maintenance on the control room vent system was adequate.
Immediate and planned corrective actions for a previously identified deMency h the control room ventilation system were adequate (Section M8.1).
Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000
Page:
6of19 03/29/2000 07:00:32 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 10/31/1999 1999009 Prl: MAINT NRC'OS Prl: 2A Maintenance staff effectively repaired reclrc fan cooler and pressurizer heater problem.
Sec:
Sec: 3A Maintenance personnel effectively repaired a leaking containment recirculation fan cooler, and a faulty pressurizer heater control cabinet. (02.1 and M2.1)
Dockets Discussed 05000244 Ginna Dockets Discussed 05000244 Ginna 09/19/1999 1999008 Prl: MAINT NRC POS Prl: 1A Sec: OPS Sec: 2B Ter: 3A Observed maintenance and surveillance activities appropriately performed.
Observed maintenance activities were accoinpiished in accordance with procedural requirements.
The licensee's postmaintenance testing was adequate to demonstrate the operability of equipment prior to its return to service. Test procedures contained adequate details for accompflshing test requirements.
Testing was performed by knowledgeable personnel, and test instrumentation was properly calibrated.
(M1.1)
Dockets Discussed 05000244 Ginna 09/19/1999 1999008 Prl: MAINT NRC POS Prl: 3A Sec: OPS Sec: 2A Ter:
Effective Identificatlon and resolution of CR ventilation problem.
The licensee effectively identified a deficiency in a flexible suction joint for the control room ventilation system air intake fan. The temporary modification performed on the system adequately corrected the deficiency and was completed in a timely manner.
(M2.1) 09/19/1999 199900841 Dockets Discussed:
05000244 Ginna Prl: MAINT Sec: OPS NRC NCV Pri: 1A BREACH OF OVERTIME REQUIREMENTS FOR ONCITE PERSONNEL Sec: 2B Ter:
The licensee's control of maintenance worker overtime authorization and use during the March 1999 refuel outage was poor, as demonstrated by the failure of a had technician to obtain prior written approval, as required by station procedure.
The licensee entered this Issue into their corrective action program for resolution and committed to improve the effectiveness and implementation of existing overtime guidance.
This failure to followstation procedures was treated as a no~ted violation.
(M7.1) 08/06/1999 Dockets Discussed 05000244 Ginna 1999007 Pri: MAINT NRC POS Prl: 2B Sec: ENG Sec: 3A Ter.
Failure rate of low-voltage breakers at Ginna higher than the industry failure rate, PMs iinproved.
The failure rate of the hw-voltage circuit breakers at Ginna was higher than the generic industry failure rate due ta previous inadequate root cause analyses and corrective actions to address the repeated breaker failures. The hcensee recognized these breaker issues and had established reasonable goals to knprove breaker perfonnance. The pteventiva maintenance procedures were improved. The material condition of the breakers was good.
Dockets Discussed 05000244 Ginna 08/06/1999 1999007 Pri: MAINT NRC POS Prl: 2B Sec: ENG Sec: 4C Ter.
PM program on low voltage DB series circuit breakers improved.
The preventive maintenance program procedures for hw 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.
Item Type (Compfiance,Fotlowup,Other), From 01/16/1999 To 01/31/2000
1 I'
' I II
Page:
7 of 19 03/29/2000 07:00:32 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 Descriptlon 0&/06/1999 1999007 Dockets Discussed:
05000244 Ginna Pri: MAINT Sec: ENG NRC POS Prl: 5A Sec: 5B Ter. 5C Extensive troubleshooting, root cause evaluations, and corrective actions appropriate.
The licensee completed extensive troubleshooting for the recent circuit breaker failures. The corrective actions taken and the root cause evaluations completed for the breaker faliures were appropriate.
08/08/1999 1999006 Pri: MAINT Sec:
Dockets Discussed:
05000244 Ginna NRC POS Prl: 2B Sec: 3A Ter.
Maintenance and surveillance activities were appropriately conducted.
Observed maintenance and surveillance activities were accomplished in accordance viith procedural requirements.
The postmaintenance 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 identiTied during reactor trip breaker testing.
08/08/1999 1999006 Pri: MAINT NRC POS Pri: 2B Maintenance rule expert panel critical of plant systems performance.
Sec:
Sec: 3A 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.
Dockets Discussed 05000244 Ginna Dockets Discussed 05000244 Ginna 06/27/1999 1999004 Pri: MAINT NRC POS Prl: 1C Sec:
Sec: 3A Ter.
Conduct of maintenance activities was good.
Observed maintenance activities were accomplished in accordance with procedural requirements.
The licensee's post maintenance testing was adequate to demonstrate the operability of equipment prior to it's return to service. Test procedures contained adequate details for accomplishing test requirements.
Testing was performed by knowledgeable personnel, and test instrumentation was properly calibrated.
(M1.1)
Dockets Discussed 05000244 Ginna 06/27/1999 1999004 Pri: MAINT NRC POS Pri: 2A Sec: ENG Sec: 4C Ter. 5C Good staff response to,A EDG output breaker failure.
The licensee took proper actions following discovery of the failed emergency diesel generator output breaker to troubleshoot, identify, and correct the breaker failure mechanism.
The Scensee's broader corrective actions to review all breaker maintenance procedures for adequacy with the vendor was considered a good Initiative. (M2.2)
Dockets Discussed 05000244 Ginna 06/27/1999 1999004 Pri: MAINT=
NRC NEG Prl: 2B Sec: OPS 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 coukf adversely impact the availability of the in-service offsite power circuit, were not suspended until aRer work on circuit 767 was commenced and after being brought to the licensee's attention by the inspectors.
(M2.1)
Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000
$1 Cg II
Page:
8of19 03/29/2000 07:00:32 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 Item Title ID Type Codes Item Description 07/15/1999 199941040 Pri: MAINT Self LER Sec: ENG Dockets Discussed:
05000244 Ginna Pri:
RADIATIONMONITORALARM,DUE TO HIGHER THAN NORMALRADIOACTIVEGAS CONCENTRATION, RESULT Sec:
High radiation alarm due to actual condition, however, the licensee identiTied that the alarm setpoint was overly conservative.
Reference IR 9948, seciton 08.4.
Ter.
Dockets Discussed:
05000244 Ginna 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. (M1.1)
Ter:
05/16/1999 1999Q03 pri MAINT NRC POS Prl: 1C Maintenance and Surveillance observations all positive.
Sec:
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 05/16/1999 1999003 Pri: MAINT Sec: OPS Dockets Discussed:
05000244 Ginna NRC NEG Prl: 1C Sec: 3A Tel:
Sucessful RTD replacement, but poor PORC oversight to ensure root cause id'd.
The licensee successfully replaced failed resistance temperature detectors (RTDs) in the reactor coohnt 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. (M2.2) 04/04/1999 1999002 Prl: MAINT Sec:
Dockets Discussed:
05000244 Ginna NRC POS Prl: 1C Sec:
Tel".
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/Q4/1999 1999002 Prl: MAINT NRC POS Pri: 1C Sec: ENG Sec: 3A Ter.
Dockets Discussed 05000244 Ginna 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.
r Item Type (Compffance,Foitowup,Other), From 01/16/1999 To 01/31/2000
l I+
f r
tf~
I f
~
e
Page:
9of19 03/29/2000 07:00:32 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 04/04/1999 1999002 Pri: MAINT NRC POS Pri: 1C Sec: ENG Sec: 3A Ter.
ISI activities well planned and implemented.
lnseivice 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 weil 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.
05/13/1999 1999405OI Pri: MAINT Sec: OPS Dockets Discussed; 05000244 Ginna Licensee LER Pri:
Sec:
Ter:
UNDERVOLTAGESIGNALON SAFEGUARDS BUS DURING TESTING RESULTS IN AUTOMATICSTART OF "B"EM Seff identifying event resulting from a cognitive personnel error during testing.
Reference IR 9943, section 08.3.
05/12/1999
-19994044)0 Prl: MAINT Sec: ENG Dockets Discussed:
05000244 Ginna Licensee LER Prl:
CONTAINMENTRECICULATIONFAN MOISTURE SEPARATOR VANES INCORRECTLY INSTALLEDRESULTS IN U Sec:
ucensee identified problem caused by manufacturing error. Reference IR 9943, section 08.2.
Ter.
Dockets Discussed:
05000244 Ginna Ter:
02/21/1999 1999001 Prl: MAINT NRC POS Pri: 1C Sec:
Sec:
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 backhg of maintenance rule items for review.
02/21/1999 1999001 Pri: MAINT Sec:
Dockets Discussed:
05000244 Ginna NRC POS Prl: 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 faffures 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 veriTication of breaker condition during maintenance.
Dockets Discussed 05000244 Ginna 02/21/1999 1999001 Pri: MAINT NRC POS Pri: 3A Sec:
Sec: 2B Ter.
Maintenance and surveillance work Controlled procedures were used at lob sites.
The procedures were up to date and were properly used by technicians hvotved in maintenance and sunrefflance 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.
Item Type (Compliance,Foliowup,Other), From 01/16/1999 To 01/31/2000
Page:
10of19 03/29/2000 07:00:32 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 Ter.
02/21/1999 1999001 Pri: MAINT NRC POS Pri: 3A Sec:
Sec: 2B 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 perfonnance of safety functions during this activity was deficient in that no overall change in core damage frequency was identiTied.
02/21/1999 1999001 Dockets Discussed:
05000244 Ginna Pri: MAINT Sec:
Pri: 3A Plant scaffolds NRC POS I
Sec: 3B Plant scaffolds appeared to be well designed and constructed in accordance viith 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.
02/21/1999 1999001 Pri: MAINT NRC POS Prl: 5A A EDG synchronization selector switch deficiency IdentiTicatlon Sec:
Sec: 5B The licensee effectively identified a deficiency in the synchronization selector switch for the Awmergency diesel generator.
Sending the replaced switch to a materiais laboratory for analysis was a good Initiative.
Dockets Discussed 05000244 Ginna Dockets Discussed:
05000244 Ginna Ter:
01/23/2000 1999012 Prl: ENG NRC POS Prl: 4B Sec:
Sec:
RGE response to GL 98-02 was acceptable.
RG&E determined that Ginna station was vulnerable to an event referenced in generic letter (GL) 9802, Loss of Reactor Coolant Inventory and Associated Loss of Emergency Mitigation Functions White in a Shutdown Condition, and took acceptable corrective actions.
RG&E's response to GL 98-02 was timely and complete (Section E2.1).
12/12/1999 1999011 Pri:ENG NRC POS Prl:4B Engineeringstaffappropriatelydevelopedandevaluatedamodtothecontrolroomenvelope.
Sec:
Sec: 4C Engineering department personnel appropriately developed and evaluated a modification to the control room envelope (Section E2.1).
Dockets Discussed:
05000244 Ghna Dockets Discussed:
05000244 Ginna Ter: 4C 10/31/1999 1999009 Pri: ENG NRC POS
. Pri: 4A Sec:
Sec: 4B Engineering personnel maintained proper controls over a plant modification.
RG&E engineering personnel maintained proper controts over a permanent plant modifcation throughout the development, implementation, and testing stages.
Maintenance activities associated with the modification were well coordinated.
(E2.1)
Item Type (Compliance,Foliowup,Other), From 01/18/1999 To 01/31/2000
Pago:
11of19 03/29/2000 07:00:32 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 Codos Item Description 09/19/1999 1999008 Prl: ENG Sec: MAINT Dockets Discussed:
05000244 Ginna NRC POS Pri: 3A Effective ldentiTication and resolution of missing baseplate bolt.
Sec: 4B
'The ticensee effectively identiTied and corrected a deficiency with the Wesidual heat removal pump after discovering one'baseplate floor bolt missing. The engineering analysis performed adequately verified pump operabitity. (E2.1) a 09/22/1999 199941140 Prl: ENG Licensee LER Sec: MAINT Dockets Discussed:
05000244 Ginna Pri: 4A SMALLBREACH IN VENTILATIONSYSTEM RESULTS IN PLANTBEING OUTSIDE DESIGN BASIS Sec: 4B Ter.
RG&E determined the most likely cause of the event was a heavy load being placed on the flexible duct work.
Additional corrective actions include a detailed examination of the damaged duct work following replacement during the next refueling outage.
RG&E's immediate and planned corrective actions were adequate.
Closed in IR 99-11.
08/06/1999 1999007 Prl: ENG
~
Sec:
Dockets Discussed:
05000244 Ginna NRC POS Prl: 3A
- Engineering staff effective ln Identifying and resolving technical issues.
Sec: 4B Engineering had been effective in identifying and properly resolving technical issues.
In addition, tho design control, temporary modification, and corrective action procedures provided appropriate guidance for identiTication and resolution of technical issues.
08/06/1999 1999007 Prl: ENG NRC POS Prl: 3A Engineering backlog effectively managed.
Sec:
Sec: 4B Engineering baddogs were being managed effectively. The new work planning and tracking program being implemented was an enhancement for engineering workload management.
Dockets Discussed 05000244 Ginna 08/06/1999 Dockets Discussed:
05000244 Ginna 1999007 Prl: ENG NRC Sec:
POS Prl: 3A Self-assessments had meaningful findings and results.
Sec: 5A The setfassessment performed by Ginna persortnel in the area of records management produced meaningful findings for improvement.
The independent assessments performed by outside contract organizations contributed signTiicant findings regarding specific technical areas+~e assessments were in<epth and of high technical quality, and were conducted using developed plans, wittf'corrective actions initiated on all findings and recommendations.
Overall, the licensee had a good self assessrpegA program.
Dockots Discussed 05000244 Ginna 08/06/1999 1999007 Pri: ENG NRC POS Pri: 4A Sec:
Sec: 4C Ter.
Design data forsystems 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. Tho design data for the design change modifications were controlled, documented and incorporated into the appropriate design documents.
Set point evaluations were thorough, ia4epth, and technically sound.
Item Type (Compfiance,Foltowup,Other), From 01/16/1999 To 01/31/2000
Page:
12 of 19 03/29/2000 07:00:32 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 08/06/1999 1999007 Prl: ENG NRC POS Pri: 4B Sec:
Sec: 4C Ter:
TMs were properly prepared and documented.
The temporary modiTications were properly prepared and documented in accordance with the station procedures.
The.
evaluation, installation, post-modiTication test requirements and safety reviews provided by engineering presented adequate technical basis for the modiTications. There were no longstanding temporary modifications at Ginna.
08/06/1999 1999007 Pri: ENG Sec:
Dockets Discussed:
05000244 Ginna NRC POS Pri: 4B Sec: 4C Ter.
Safety evaluations well written.
Safety evaluation/review procedures were welkvritten documents that provided adequate guidance to determine ifa proposed activity could be impleinented 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 ofa safety evaluation was also good. Process controls were in place to ensure changes to the plant were reflected in design documents.
Dockets Discussed:
05000244 Ginna Ter:
08/06/1999 1999007 Pri: ENG NRC POS Pri: 4C Sec:
Sec:
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 foliowmeetings and the system engineering group had resulted in improved communication of engineering information to other departments at the site.
08/06/1999 1999007 Pri: ENG NRC POS Pri: 5A QA audits thorough In the engineering area.
Sec:
Sec: 4C The quality assurance audits were thorough and iiHIepth, and resulted in good findings regarding engineering and procurement activities. The licensee adequately addressed the audit findings.
Dockets Discussed 05000244 Ginna 08/06/1999 199900741 Pri: ENG NRC NCV Sec:
Dockets Discussed:
05000244 Ginna Prl: 4B Sec: 4C Ter.
Incorrect input for MOVweak link analysis.
Design change modiTications were properly designed and implemented.
Affected documents were appropriately updated to capture and preserve the changes ln 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 cakutations 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 motoraperated valve weak link analysis. while the other involved not promptly implementing setpoint changes.
Dockets Discussed 05000244 Ginna 08/06/1999 199900742 Pri: ENG NRC NCV Pri: 4B Untimely corrective actions for instrurgent~etpolnt changes.
Sec:
Sec: 4C (Same as NCV 50-244/994741 text.)
Ter. 5C Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000
Pago:
13of19 03/29/2000 07:00:32 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 Typo Codes Item Description 08/06/1999 199900743 Prl: ENG Sec:
Dockets Discussed:
05000244 Ginna NRC NCV Prl: 5A Auxiliarybuilding post-accident environment.
Sec: 5C The original auxiliary building post-accident environment calculation used non~nservative assumptions and was a no+cited 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 199900744 Pri: ENG Licensee NCV Sec:
Dockets Discussed:
05000244 Ginna Prl:4B Soc: 4C Ter.
Steamiino break mass and energy release analysis.
The failure to establish appropriate administrative controls over the supply of design inputs to vendors was a N&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) Reference LER 9941 and LER 9941, suppl 01; IR 9942, section E8.2.; and IR 9943, section E8.2; 08/08/1999 1999006 Pri: ENG NRC Sec:
Dockets Discussed:
05000244 Ginna POS Pri:4B Sec:
Ter.
Engineering staff response to algae intrusion was good.
Engineering personnel performed well in response to an algae intrusion of tho 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.
Dockets Discussed 05000244 Ginna 06/24/1999 1999005 Pri: ENG NRC NEG Pri: 4B Sec:
Sec: 4C Ter.
Main steam non-return check valve calcs not conservative.
The assumptions, analytical methods, and calculations used by the licensee to dedare the main steam non-return check valves operable may not be conservative and may not be applicable in all cases.
The fcensee did not show that the uncertainty in the calculation is less than the available margin of torque needed to dose the valve. Therefore, operaMity of the main steam norwetum check valves remains an open issue pending NRC review of additional information from RG&E. (Section E7.1)
Operability determinations were generally acceptable.
In general. the operability determinations reviewed were acceptable.
Afew of the operability determinations reached an appropriate condusion, but were not thoroughly documented.
One operability determination, regarding the main steam norwetum check valves was inadequate.
(Section E7.1)
Dockets Discussed 05000244 Ginna t
06/24/1999 1999005 Prl: ENG NRC POS Pri: 4B Sec:
Sec: 3A Ter.
Dockets Discussed 05000244 Ginna 06/24/1999 1999005 Prl: ENG NRC POS Prl: 2B Sec: MAINT Sec: 3A Tef:
Peer assisted self assessments were good.
The team conduded that the peer-assisted so!assessments were good; they induded a strong independent perspective and numerous findings for improvement.
Corrective actions and program enhancements resulted from tho assessments.
(Section E7.4 Item Typo (Compliance,Foiiowup,Other), From 01/16/1999 To 01/31/2000
Page:
14of19 03/29/2000 07:00:32 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 06/24/1999 199900541 Prl: ENG NRC EEI Sec:
Dockets Discussed:
05000244 Ginna Pri:4B Sec: 4C Ter.
Potential USQ on changes made to main steam non-return check valve.
The team klentified 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 nometum check valves to require a significant breakaway dosing torque represents an Unreviewed Safety Question.
This h an apparent viohlion of 10 CFR 50.59.
(EEI 50-244/994541).
The licensee did not agree that these changes introduced an Unreviewed Safety Question.
(Section E7.1) Reference LER 9943 and IR 9943, section 08.1.
06/27/1999 1999004 Prl: ENG NRC POS Pri: 4C Sec:
Sec:
Ter.
Dockets Discussed 05000244 Ginna 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 Pri: ENG NRC POS Pri: 4B Sec:
Sec:
Tel:
Effective actions by licensee to address EDG delta peak firingpressure.
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 199900301 Prl: ENG Sec:
Dockets Discussed:
05000244 Ginna NRC IFI Pri: 4A Sec: 4B Ter:
Licensee challenged by RPS OP and OT delta temperature protection RTD mod.
The bcensee was challenged with operational problems associated with a new plant modTiication that caused over-temperature and over~r delta temperature setpoints to drift. The licensee effectively identified and corrected some problems, and conservatively reduced reactor power while troubleshooting was in progress.
Reference LER 9949 and IR 9948, section 08.3 which dosed the LER.
Dockets Discussed 05000244 Ginna 04/04/1999 1999002 Prl: ENG NRC POS Pri: 4B Sec:
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 itwith a smaller valve that was more resistant to erosion.
However, the system conditions that required heavy throttling of service water at the component cooling water heat exchangeis were not yet resolved.
The licensee continued to evaluate the need to increase service water flow to reduce siltation and erosion, and to maintain optimal component cooling water system temperatures.
Dockets Discussed 05000244 Ginna 04/04/1999 1999002 Pri: ENG NRC POS Pri: 1C Sec: MAINT Sec: 4B Ter: 4A Appropriate plant modifications and well implemented.
Plant modiTications installed during the current refuefing outage were good enhancements to the operation and reliability of plant equipment.
The Installation packages reviewed contained detailed Instructions and information for performing and documenting the modiTication work. The safety evaluations reviewed were adequate to demonstrate that the modifications did not represent any unreviewed safety concerns.
Item Type (Compliance,Foliowup,Other), From 01/16/1999 To 01/31/2000
1II h
O
Page:
15of19 03/29/2000 07:00:32 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 02/21/1999 1999001 Pri: ENG NRC POS Pri: 4B TemPorary modifications Sec:
Sec:
The licensee's plan to remove 21 of the current 22 temporary modifications was a good initiative.
Ter.
12/12/1999 1999011 Pri: PLTSUP NRC POS Prl: 1C RGE maintained and implemented an adequate rad monitoring system cal program.
Sec:
Sec: 3A RG&E maintained and implemented an adequate radiation monitoring system calii>ration program and an effective surveillance test program for effluent air deaning systems (Section R2).
Dockets Discussed:
05000244 Ginna Dockets Discussed 05000244 Ginna 12/12/1999 1999011 Pri: PLTSUP NRC POS Prl: 2B Sec:
Sec: 3A Ter.
RGE maintained adequate radioactive liquid and gaseous effluent control programs.
RG&E maintained adequate radioactive liquid and gaseous effluent control programs.
The offsite dose calculation manual contained sufficient detail for acceptable implementation of the radioactive effluent control programs (Section R1.1).
12/12/1999 1999011 Pri: PLTSUP NRC POS Pri: 2B QA and self assessments of rad effluent controls were effecttve..
Sec:
Sec: 3A Quality assurance audit and seffwssessment programs for radioactive effluent control were effectively implemented.
The quality control program for analytical results was effective (Section R7).
Dockets Discussed 05000244 Ginna 12/12/1999 1999011 Prl: PLTSUP NRC POS Prl: SB RGE corrective measures to address a plant computer Issue were appropriate.
Sec:
Sec: 5C RG&E's corrective measures to evaluate and prevent unauthorized external access to onsite computer systems were appropriate (Section S8.1).
Dockets Discussed 05000244 Ginna 11/18/1999 "l999010 Prl: PLTSUP NRC POS Sec: OPS Dockets Discussed:
05000244 Ginna Pri: 2B Sec: 3A Ter.
Overall emergency response organization performance was good.
Based on the results of this inspection, it was determined that the overall performance of the emergency response organization demonstrated, with reasonable assurance, that onsite emergency plans are adequate and that the licensee is capable of implementing them. Simulated events were diagnosed accurately, emergency dechrations were timely and accurate, offsite agencies were notified in a timely manner, protective action recommendations were appropriate, and dose assessment activities were performed properly.
Item Type (Compliance,Foliowup,Other), From 01/16/1999 To 01/31/2000
1'I
Page:
16of19 03/29/2000 07:00:32 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 Item Title ID Type Codes Item Description Dockets Discussed 05000244 Ginna 11/18/1999 1999010 Prl: PLTSUP NRC POS Pri: 2B Sec: OPS Sec: 3A Ter.
Licensee critique was balanced.
At the formal critique, your staff identified issues, in addition to those identiTied by the NRC. The most signifcant issues identified are under consideration for indusion in the corrective action program.
Overall, the critique was balanced with positive and negative findings and was appropriately self~tical.
Dockots Discussed:
05000244 Ginna Ter.
10/31/1999 1999009 Pri: PLTSUP NRC POS Sec:
Sec: 3A Effective implementation of tho REMP and MMP.
RG&E effectively maintained and implemented the radiological environmental monitoring program.
Procedures and annual reports were adequate and contract laboratory oversight was effective. RG&E effect'Nely maintained the meteorological monitoring system operable, and properly performed channel calibrations and functional tests.
(R1.1 and R1.2)
Dockets Discussed 05000244 Ginna 10/31/1999 1999009 Prl: PLTSUP NRC POS 'ri:2B APProPriate quality assurance audits of the REMP and MMP Programs.
Sec:
Sec: 3A Quality assurance personnel appropriately conducted an audit of the radiological environmental monitoring program, and the audit findings were properly acknowledged in the corrective action program.
(R7.1)
. Ter.
Dockets Discussed:
05000244 Ginna Sec:
Sec: 3A Ter.
08/08/1999 1999006 Pri: PLTSUP NRC pOS Pri: 2B Radwaste management and transportation programs were adequately Implemented.
The radioactive waste management and transportation programs were adequately implemented as evidenced by a qualified staff canying 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 disposai contaminated filtermedia that was dassified as containing greater than Type C concentrations of radioactive materials.
Dockets Discussed 05000244 Ginna 08/08/1999 1999006 Pri: PI.TSUP, NRC POS Pri: 2B Waste Processing, handling, and shiPPing was well executed.
Sec:
Sec: 3A 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 kiduded in RG&E's corrective action program Dockets Discussed 05000244 Ginna 08/08/1999 1999006 Pri:PLTSUP NRC POS Pri:2B StaffinvolvodwithradwastehandlingandshiPPingwerewellquallfiedandtralnod.
Sec:
Sec: 3A 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.
Ter.
Item Type (Compliance,Foliowup,Other), From 01/16/1999 To 01/31/2000
f p 'gV Cg
Page:
17of19 03/29/2000 07:00:32 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 Ter:
08/08/1999 1999006 Pri: PLTSUP NRC POS Prl: 2B Sec:
Sec: 3A 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, induding audits, self-assessments, and quality control suiveillances.
06/27/1999 199900441 Prl: PLTSUP Sec:
Dockets Discussed:
05000244 Ginna
- NRC, NCV Prl:
UNPLANNED RADIOLOGICALEXPOSURES Sec:
Ter.
ucensee management identified, after the fact, a series of unplanned exposure events that were the result of defciencies 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 orrective 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 radiological 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 SpedTications was norHxted. (R8.1) 07/19/1999 199940140 Pri: PLTSUP Licensee Sec:
Dockets Discussed:
05000244 Ginna LER Pri:
SAFEGUARDS EVENT Sec:
Safeguards event.
Reference IR 9908, section S8.1.
Ter.
05/16/1999 1999003 Pri: 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 pr~utage 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 Sec:
Dockets Discussed:
05000244 Ginna NRC POS Pri: 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 dosely 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 Sec:
Dockets Discussed:
05000244 Ginna NRC POS Pri:.1C Sec: 3A Ter.
Radiological controls program was well iinplemented.
The radiological controls program was effectively implemented by quaMied and experienced staff properly implementing detailed procedures and radiation work permits, appropriately monitoring personnel exposure, and adequately maintaining radiologically controlled areas.
Work performance standards were effectively monitored and reinforced by dose and frequent management and quality assurance oversight. Off~rmal conditions were conservatively identified, appropriately evaluated, and resolved in a timely manner.
Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000
Page:
18of19 03/29/2000 07:00:32 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 04/04/1999 1999002 Prl: PLTSUP NRC POS Prl: 1C Sec:
Sec: 3A Ter.
Security and safeguards activities well conducted.
The Ecensee 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 vehides.
Secunty 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).
Dockets Discussed 05000244 Ginna 04/04/1999 1999002 Pri: PLTSUP NRC POS Pri: 1C Sec:
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.
Item Type (Compliance,Folhwup,Other),
From 01/16/1999 To 01/31/2000
l
Page:
19of19 03/29/2000 07:00:32 IR Report 3 United States Nuclear Regulatory Commission PLANT ISSUE MATRIX By Primary Functional Area / Issue Date Legend Type Codes:
BU Bulletin CDR Consbuction DEV Deviation EEI Escalated Enforcement Itein 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 Nonconformance OTHR Other P21 Part 21 POS Positive SGI Safeguard Event Report SIR 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 4B Engineering Support 4C Programs and Processes 5A identification 58 Analysis 5C Resolution ID Codes:
NRC NRC Self Self&evealed 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 h 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 modified when the final decisions are made.
URls are unresolved items about which more information is required to determine whether the issue in question ls 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 modTiied when the final condusions are made.
Item Type (Compliance,Followup,Other), From 01/16/1999 To 01/31/2000