ML20196J218
| ML20196J218 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/01/1998 |
| From: | Skinner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Beasley J SOUTHERN NUCLEAR OPERATING CO. |
| References | |
| NUDOCS 9812090283 | |
| Download: ML20196J218 (18) | |
Text
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December 1, 1998 Southern Nuclear Operating Company, Inc.
ATTN: Mr. J. B. Beasley, Jr., Vice President P.O. Box 1295 Birmingham, Al 35201-1295
SUBJECT:
INSPECTION PLAN - VOGTLE PLANT
Dear Mr. Beasley:
On November 2,1998, the NRC staff completed an inspection resource planning meeting.
The staff conducted this review for all operating nuclear power plants in Region ll to develop an integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant Performance Review, which the staff has moved to February 1999 because of the agency's shift to an annual Senior Management Meeting cycle.
This letter advises you of our planned inspection effort resulting from the inspection planning meeting. We have provided it to minimize the resource impact on your staff and to allow for scheduling conflicts and personnel availability to be resolved before the inspector's arrival onsite. Enclosure 1 details our inspection plan for the next 4 months. We have provided the rationale or basis for each inspection outside the core inspection program so that you are aware of the reason for emphasis in these program areas. Resident inspections are not listed due to their ongoing and continuous nature.
During this scheduling cycle, we will continue to focus some of our discretionary inspection effort on the resolution of open inspection items. Therefore, we may conduct additional inspections, which are not listed on Enclosure 1, to close open inspection items that are ready to be resolved. We will notify you at least 3 weeks before the start of these inspections.
The NRC's general policy for reactor inspections is that we will announce each inspection, unless announcing the inspection could compromise the objectives of the inspectors.
Therefore, we may not have included some specific inspections on Enclosure 1, such as in the security and radiological protection areas, and these inspections may not be announced.
Enclosure 2 contains a historical listing of plant issues, called the Plant issues Matrix (PIM).
The PIM includes only items from inspection reports or other docketed correspondence between the NRC and Southern Nuclear Operating Company, Inc. This material will be placed in the public document room.
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9812090283 981201 PDR G ADOCK 05000424 PDR y J t{ %
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We will inform you of any changes to the enclosed inspection plan. If you have any questions,
_ please contact me at 404-562-4520.
' Sincerely, (Original signed by Pierce H. Skinner) i l
Pierce H. Skinner, Chief Reactor Projects Branch 2 ;
Division of Reactor Projects Docket Nos. 50-424,50-425 License Nos. NPF-68 and NPF-81 f t
Enclosures:
- 1. Inspection Plan
- 2. Plant Issues Matrix ;
e cc w/encis: ;
J. D. Woodard Executive Vice President Southern Nuclear Operatirig Company, Inc.
P. O. Box 1295 i Birmingham, AL 35201-1295 ,
J. T. Gasser General Manager, Plant Vogtle l Southern Nuclear Operating Company, Inc.
P. O. Box 1600 Waynesboro, GA 30830 l
J. A. Bailey Manager-Licensing Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Birmingham, AL _35201-1295 Director, Consumers' Utility Counsel Division Governor's Office of Consumer Affairs 2 M. L. King, Jr. Drive !
- Plaza Level East; Suite 356 Atlanta, GA 30334-4600 I
cc w/encls cont'd: (See Page 3) '
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- . . -. - - . . - _ ~ - , . - . . _. -.-.-. . -.-
j -SNC 3 ,
cc w/encls: Continued Office of Planning and Budget Room 615B 270 Washington Street, SW Atlanta, GA 30334 f Office of the County Commissioner Burke County Commission
.Waynesboro, GA 30830 l' Director, Department of Natural Resources l 205 Butler Street, SE, Suite 1252 i Atlanta, GA 30334 Manager, Radioactive Materials Program Department of Natural Resources l
i 4244 International Parkway Suite 114 Atlanta, GA 30354 Attorney General !
Law Department '
132 Judicial Building ;
Atlanta, GA 30334 i
Program Manager !
Fossil & Nuclear Operations l
Oglethorpe Power Corporation :
2100 E. Exchange Place
!- Tucker, GA 30085-1349 Charles A. Patrizia, Esq. !
Paul, Hastings, Janofsky & Walker 10th Floor I 1299 Pennsylvania Avenue i Washington, D. C. 20004-9500 Senior Engineer - Power Supply i Municipal Electric Authority !
of Georgia 1470 Riveredge Parkway NW Atlanta, GA 30328-4684 Distribution w/encts:
L. Plisco, Ril P. Skinner, Ril !
Distribution w/encls cont'd: (See Page 4) i f
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SNC 4 Distribution w/9ncis: Continued D. Jaffe, NRR PUBLIC NRC Senior Resident inspector U.S. Nuclear Regulatory Commission 8805 River Road WaynesborO, GA 30830 I
OFFICE Iq:DRP R1J@S Ril;D,RS J Rlifppg /f[ hil:Dffff, SIGNATURE
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VOGTLE -
INSPECTION PLAN !
t INSPECTION NUMBER OF PLANNED INSPECTION PROCEDURE / TITLE / PROGRAM AREA INSPECTORS DATES TYPE OF INSPECTION - COMMENTS
- TEMPORARY INSTRUCTION 82701' Emergency Preparedness 2 January,1999 Core Program 81700 Security 4 January,1999 Core Program 84750/86750 Rad. Protection, Waste 1 February,1999 Core Program Treatment, Effluent and Transportation 83750 Rad. Protection, 1 March,1999 Core Program Occupational Radiation .
Exposure !
92903 Engineering 1 March,1999 Regional Initiative - Followup Open items 73753 Inservice inspection 1 March,1999 Core Program i t
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PLANT ISSUES MATRIX by SALP Functional Atea VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES
- OPERATIONS" ' l 9/26/1998 Positive ENG IR 98-07, O1.2 NRC Operator actions to initiate a Unit 2 manual reactor tnp on August 24 prior to 1 234 5 automatic protection actuations were proactive. The rapid identification and response to decreasing steam generator level was indicative of good operator performance. The hcensee's root cause investigation and subsequent corrective AOOOOO actions for a Unit 2 rnanual reactor tnp on September 4 were thorough and 8 O addressed the cause of the trip. Operations personnel were prepared for the possible loss of feedwater and responded in a tnriety and appropriate manner. The c0 00O preparation, rapid identification and response to the event was an indication of good performance by the operating crew.
9/16/1998 VIO 98-06 03.1 NRC Operatens personnel did not adequately review procedures and TS prior to entry 1 234 5 into the LCO for containment ventilation isolation instrumentaten.
A 0000O B 00000 cO 000 6/27/1998 VIO IR 98-05 03.1,08.1 NRC Two examples of operator Failure to Comply with Technical Specification (TS) 3.0.4. 1 234 5
- 1) Contrary to TS 3 0 4 Unit 2 entered Mode 4 without meeting TS 3 d.12. which requires two relief vatves to be operable. Only one power operated rehef valve was operable when the mode change was made. 2) Contrary to TS 3 0.4, Unit 2 entered AOOOOO Mode 2 without the turbine trip function operable as required by TS 3.3 2-1. B OOOOO cO 000 6/27/1998 Positive ENG IR 98-05,01.1 NRC Performance following a plant transient. Operators correctly used Emergency 1 234 5 I Operating Procedures and took appropriate actions following a reactor trip and safety injection on Unit 2. The Root Cause investigation adequately determined that A OOOOO incorrect tao settings for instantaneous overcurrent relays was the cause of the trip.
Plant recovery actions were comperhensive and restart activities were well controlled B OOOOO and coordinated-cO OOO 5/16/1998 Positive IR 98-04 (E1.1) LICENSEE The identification by a Plant Equipment Operator of a degraded condition associated 1 234 5 with the Unit 1 Train B Sequencer was an example of good attention to detail.
A 00000 s00000 cO 000 Enclosure 2 FROM 10/1/1997 TO: 11/25/1998 Page 1 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998 m
_ _ _ _ _ _ _ _ _ _ _ _ _ m _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURGY(s) ID'd ISSUE (s) SMM CODES 5/16/1998 Negative IR 98-04 (O4.1) NRC Operations personnel performance dunng Emergency Diesel Generator surveillance 1 234 5
- ? sting represented a weakness in the licensee's planning and preparation pnor to commencement of the surveillance activsty. AOOOOO s00000 cO 000 5/?S/1998 VIO IR 98-04 (O3.2) NRC Personnel failed to properly maintain control of materials inside the spent fuel pool 1 234 5 Zone il foreign material exclusion (FME) area, in that, they failed to property tog equipment that entered and exited the zone. A violation was identified for this failure to follow FME procedure requirements.
A OOOOO OOOOO cO 000 5/16/1998 Positive IR 98-04 (01.2) NRC The operators properly responded to a Unit 2 automatic reactor trip that occurred as 1 234 5 a result of a lightning stnke to the 500 krfovolt transmission line. Plant recovery actions were comprehensive and restart activities were well controlled and coordinated.
AOOOOO OOOOO c0 000 5/16/1998 VIO IR 98-04 (01.1) NRC Licensee operators did not fully understand the intent of opening the three letdown 1 234 5 onfice isolation valves when the plant was in a water solid condition dunng heatup from refueling outage 2R6. A violation was identified for failure to follow procedures as a result of operating in this condition without all of the valves in the required open AOOOOO position. B OOOOO cO 000 4/18/1998 NCV IR 98-03; 98-03-02 (O4.1) SELF A non-cited violation was identifed for failure to follow the Unit 2 Engineered Safety 1 234 5 Features Actuation System test procedure. The operations test coordinator performed a step out of sequence from the procedure that resulted in the inadvertent AOOOOO resetting of the required safety injection actuation signal OOOOO cO 000 4/18/1998 Negative IR 98-03 (O2.2) NRC Unit 2 containment closecut following refueling outage 2R6 was adequate; however. 1 234 5 some debns was identifed following the licensee's containment closeout inspection.
The amount of debris found would not have challenged containment sump performance.
AOOOOO sOOOOO cO 000 C/18/1998 Negative IR 98-03 (O2.1) NRC Several discrepancies were identifed in the licensee's implementation of foreign 1 234 5 material exclusion (FME) controls around the refueling cavity dunng Unit 2 core offload activites. The licensee adequately resolved these discrepencies and improvement was noted in FME controls during core reload.
AOOOOO OOOOO c0 000 FROM.10/1/1997 TO: 11/25/1998 Page 2 of 13 FOR PUBLIC RELEASE Last Updated: 9C6/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES G18/1998 Positive IR 98-03 (O2.1) NRC 2R6 refuehng activities were performed in a controlled manner and in accordance 1 234 5 with procedures. A thorough event revew was performed for gripping a fuel assembly by its hold-down springs during core unload. The licensee's corrective actions were comprehensive ^
A OOOOO OOOOO c0 000 4/18/1998 Positive MAINT IR 98-03 (01.2) NRC The decision to nanually trip Unit 2 while shutting down for refueling outage 2R6 was 1 234 5 justified based on the observed rod position discrepancies between Digital Rod Position Indication and the demand position step counters. The root ca ass of th control malfunction was adequately determined and corrected prive k mit AOOOOO OOOOO c0 000 4/18/1998 Positive IR 98-03 (01.1 and 01.3) NRC Managment's direct involvement in contingency plan walkdowns and the heightenec 1 234 5 awareness of the operating staff to the contingency plans during periods of increased risk during refueling outage 2R6 was a strength. AOOOOO s00000 c0 000 3/7/1998 Positive IR 98-02 (O4.1) NRC The operators property responded to a voltage transient on Channel 1,125 VAC vital 1 234 5 ins'rument panel. Abnormal operating procedures were entered and property followed. A failed 7300 process instrument power supply was identified as the root cause of the voltage transient.
AOOOOO OOOOO cO 000 3/7/1998 VIO MAINT IR 9842; VIO 98-02-01 LICENSEE A violation for failure to follow procedures was issued for a Unit Shift Supervisor who 1 234 5 (O2.1) fai8ed to recognize and enter a Limiting Condition for Operation for scheduled heater maintenance that rendered Control Room Emergency Filtration System Train B AOOOOO inoperable. The operator did not futty understand the Control Room Emergency Filtration System design and the impact that humidity control heater maintenance B OOOOO had on system operabihty prior to authonzing the work.
cO OOO 1/24/1998 Positive IR 97-12 (O2.1) NRC The component cooling water system on both units was determined to be properly 1 234 5 ahgned and was being adequately maintained to ensure rehability.
A00000 s00000 cO 000 1/24/1998 NCV IR 97-12; NCV 97-1241; NRC A non-cded violation was identifed for an operator failure to follow the actions of an 1 234 5 (01.2) Alarm Response Procedure (ARP) for a turbine building HVAC control room alarm.
This occurred as a result of personnel lack of sensitivity to control room alarms on secondary plant equipment and was considered an isolated incident.
AOOOOO OOOOO c0 000 FROM 10/1/1997 TO: 11/25/1998 Page 3 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VGGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/24/1998 Negative IR 97-12 (01.1) NRC Inconsistencies were observed in the levi i < quality in the performance of short 1 234 5 releif tumovers for the various operator pos: tons. Shift supervision and operations management expectations for short relief tumovers vaned and were not clearty AOOOOO dehneated.
OOOOO cO 000 92/13/9997 Positive IR 97-11 (OS.1) NRC The licensee's program for operator requalificafion, specifically the implementaten of 1 25 4 5 segment examinations, met the established program and procedure requnements.
Requalificaten procedures adequately addressed the vanous aspects of segment AOOOOO examinatens to effectively administer exams and implement remedial training as deemed appropriate. B OOOOO cO 000 12/93/1997 Negative MAINT 1R 97-11 (O4.1) NRC A Unit 2 reactor power chart recorder, NR-45, was not operating property and had 1 234 5 not been identifed by operators. The malfunctioning chart recorder conditen had gone undetected and corrected for approximately 32 days and was an example of inattenten to detail on the part of the control room reactor operators.
A OOOO O g O OOO cO 000 12/13/1997 Positrve IR 97-11 (O3.2) NRC Freeze protection and heat tracing equipment was capable of performing its intended 1 234 5 function and was being maintained in better condition from previous inspections in 1996 The improved system conditions were the result of the licensee's efforts to closeoua previoasty identified problem areas.
AOOOOO OOOOO c0 000 12/13/1997 Postve ENG IR 97-11 (01.3) NRC The control logic design of dual function valves allow the capability to close these 1 234 5 valves remotely with a Safety injection signal present. Adequate instructions in Emergency Operating Procedures and adequate operator training was provided to A OOOOO ensure that personne! property operate dual functon valves as naeded during design bases events. B OOOOO cO 000 12/13/1997 NCV IR 97-11; NCV 97-11-01 NRC A non-cited violation was identifed for failure to follow the standing order procedure 1 234 5 (01.2) preventing non-heensed operators from being assigned multiple dedicated duties, e g , fire bngade team response and closure of a Resdual Heat Removal drain AOOOOO valve. It was determined that there was adequate avail ability of other operators onsite to respond to events. B OOO cO 000 11/1/1997 Positive MAINT IR 97-10 (O8 2) NRC The hcensee's implementation of a new program to clean the containment prior to 1 234 5 the performance of a closeout exit inspecten adequately addressed previously identrfed weaknesses in the containment closeout program. The increased AOOOOO emphasrs that the licensee placed on material control within containment during refuehng outage 1R7 schewed successful results. B OOOOO c0 000 0 'OM.10/1/1997 TO.11/25/1998 Page 4 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID*d ISSUE (s) SMM CODES 11/1/1997 Weakness IR 97-10 (O3.2) NRC The operations crew failed to recognize that a emergency core cooling system 1 234 5 (ECCS) valve mis-positioning on Unit 1 resulted in a Technical Specification Limiting Condition for Operation for an inoperable ECCS condition. This error was the result of a cognitive personnel error.
AOOOOO OOOOO cO 000 11/1/1997 Weakness ENG IR 97-10 (O3 2) NRC Several plant events and incidents resu'ted from inadequate surveillance and/or 1 234 5 startup procedures. A weakness was identifed for multiple examples of a failure to property review procedure revisions which resutted in the procedure errors. AOOOOO B 00000 cO 000 11/1/1997 VIO MAINT IR 97-10 VIO 97-10-01 NRC A violation was identifed for imp:Oper control and alignment of emergency desel 1 234 5 (O2.2) generator 480-volt area heater breakers The cause of this mis-positioning was licensee failure to follow electncal system lineup procedure. AOOOOO B 00000 cO 000 11/1/1997 Positive IR 97-10 (01.1) NRC Plant rr.anagement's conservative decision making was demonstrated when the 1 234 5 licensee elected to avoid a fuelert midloop during refueling outage 1R7.
A00000 B 00000 cO 000 10/21/1997 Negatrve IR 97-10 (016). LER 1- SELF The failure to block a containment radiation monitor during control rod drive shaft 1 234 5 97-9 removal from containment resulted in an inadvertent engineered safety features actuation when a containment isotation signal was generated The incident was AOOOOO i ed by poor work practices and poor communications associated with the work OOOOO cO 000 10/21/1997 Weakness IR 97-10 (01.5) SELF An inadvertent dilution event cccurred during activities to flush a chemical volume 1234 5 anu control system mixed bed demineralizer resulting in a power increase from 2% to 4 6%. Poor work practces and communications by operatiotis personnel in conjunction with the use of out-dated bcron samples of the boric acid tank A OOOOO concentration contnbuted to the incdent. B OOOOO cO 000 10/19/1997 Positive IR 97-10 (01.4); LER 1 NRC Initiating a manual reactor trip from Mode 3 in response to a Digital Rod Positen 1 234 5 97-10 Indication (DRPI) problem was rppropriate during startup testing on Unit 1. The root cause was determined to be a failed detector / encoder card associated with DRPl. AOOOOO B 00000 cO 000
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MAINTENANCE -l FROM.10/1/1997 TO: 11/25/1998 Page 5 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 9/26/1998 VIO ENG NOV 98-07-01, M1.2 NRC A failure to include adequate instructions in a design package resulted in a 1 234 5 significant impact to the function of Diesel Generator 1 A .
A O O- O O O s00000 cO 000 9/16/1998 Positive OPS IR 98-02 M1.1, M1.2,98- NRC Maintenance and Surveillance activities were generally completed by personnel that 1 234 5 06, 98-05.98-03 were knowledgeable of the assigned task. Procedures were present at the work location and being followed Procedures provided sufficient detail and gudance for the intended activites~
AOOOOO OOOOO cO 000 5/16/1998 Positive OPS IR 98-04 (M1.2) NRC The hcensee's initial response to the identification of errors in the Emergency Core 1 234 5 Cooling System (ECCS) accumulator level indications were appropriate. Calibration procedures were revised and compensatory actions were taken. A OOOOO s00000 cO 000 4/18/1998 VIO IR 98-03, VIO 98-03-04 NRC A violation was identified involving the failure to follow inservice inspection (ISI) 1 234 5 (M1.4) procedures resulting in the inadequate pre-cleaning of a safety injection weld prior to performing liquid penetrant test of a safety enjection weld The root cause ws.s lack of attention to detail by the ISI examiner.
AOOOOO OOOOO c0 000 4/18/1998 NCV IR 98-03; NCV 98-03-03 LICENSEE A non-cited violation was issued for Instrumenation and Control technician failure to 1 234 5 (M1.3) follow a sequencer calibration procedure resulting in the incorrect landing of a jumper that prevented an auxiliary component coohng water pump from auto-starting durin9 Engineered Safety Features Actuation System testing.
AOOOOO OOOOO cO 000 3/7/1998 NCV IR 98-02; NCV 98-02-04 LICENSEE A non-cited violation was issued for two examples identifed by the licensee where 1 234 5 (M8.1,M8 2); LERs 98- Technical Specification surveillance procedures did not property test instrumentation, 02,-03 including: 1) the turbine inp and feedwater isolation signal from the SSPS circuits.
and 2) the core exit temperature indication signal to the remote shutdown panets.
AOOOOO The identificaton of the failure to property test the core exit temperature signal was an example of good attention to detail and questioning attitude on the part of aOOOOO Instrumentation and Control technicians. 000 c0 1/30/1998 Positive MAINT IR 98-01(M1.7) NRC For Maintenance Rule (a)(2) systems, structures, and components (SSCs), industry- 1 234 5 wide operating experence had been considered, where pradical, and operating data had been property captured. Performance enteria had been estabhshed, suitable trending had been performed, and corrective actions were taken when SSCs fai:ed t AOOOOO meet performance critena or experienced failures. B OOOOO cO 000 FROM.10/1/1997 TO.11/25/1998 Page 6 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/30/1998 Positive MAINT IR 98-01(M1.6) NRC The heensee considered safety in establishment of Maintenance Rule goals and 1 234 5 momtonng for the (a)(1) systems and components reviewed Also, corrective actions, goals, and monitonng were generally adequate for the (a)(1) SSCs
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AOOOOO sOOOOO cO 000 1/30/1998 Negative ENG 1R 98-01(M1.4) NRC Maintenance Rule program procedures did not contain sufficent detail to clearty 1 234 5 desenbe the requirements for balancing reliabihty and unavailabshty for nsk-sgnificant systems, structures, and components (SSC1). AOOOUO B 00000 cO 000 1/30/1998 Negative MAINT IR 98-01(M1.3) NRC The Maintenance Rule procedure covering the periodic assessnents was vague and 1 234 5 ed not provide details in the arean of. (1) review of effectiveness of corrective actions, and (2) optimizing availasihty and reliabihty for Structures, System, and AOOOOO Components in gereral, operating experience was being properly captured, and industry-wide operating experience was considered, as appropriate. B OOOOO cO 000 1/24/1998 Negative IR 97-12 (M1.1) NRC Maintenance activites on a spent fuel pool coohng pump did not meet the licensee's 1 234 5 normal level of performance, in that there were numerous difficultes and maintenance rework involved. Activites were not properly scoped prior to work commencement. The lack of maintenance personnel experence contnbuted to AOOOOO pump assembly difficettes. There was poor coordination and communication sOOOOO between the hcensee and vendor. OOO cO 1/24/1998 Negative IR 97-12 (M1.1) NRC Two radioactive spills occurred dunng auxikary building floor drain tank cleaning i 234 5 activites. The spills resu!ted from personnel not fully understarding the configuration and hmitatrons of the vendor supphed cleaning equipment that was AOOOOO
"d s0000O c0 000 12/13/1997 DEV IR 97-11; NOD 97-11-03; LICENSEE A Notice of Deviation was issued for the hcensee's failure to ever test a reactor 1 23 5 LER 97-007 (M8 2) coolant pump circuit breaker per the requirements of Technica: Requirements Manual 13 8.1, Containment Penetration Conductor Overcurrent Protection Devices. A OOOOO The UFSAR did not hst a circuit breaker number for the breaker installed in the reactor coolant pump bft oil pump penetration and was subsequent!y overlooked B DDDOO when the surveillance pmcedure for testing the breakers was initially developed-cO OOO 11/1/1997 Positive IR 97-10 (M15) NRC Unit 1 spht pin replacement and Steam Generator #4 tubesheet rework activites 1 234 5 dunng refueling outage 1R7 were supported by appropriate evaluations and controlled by well wntten procedures and hghly trained and motivated individuals. A OOOOO B 00000 cO 000 FROM 10/1/1997 TO 11/25/1998 Page 7 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 Q
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/1/1997 Weakness IR 97-10 (M1.3) NRC The licensee's programmatic coverage of arc strikes was considered a weakness, in 1 234 5 that, the present program excluded requirements for the repair of arc strikes. Arc strikes can harbor minute cracks, porosity, hard zones and chemical heterogeneity. AOOOOO B 00000 cO 000 11/1/1997 NCV IR 97-10, NCV 97-10-02 NRC A non-cited v.olation was identifed for an inservice inspection examiner's fadure to 1 234 5 (M1.3) follow a magnetic particle examination procedure during a weld examination.
A00000 B 00000 cO 000 11/1/1997 NCV ENG IR 97-10, NCV 97-10-03 NRC A non-cited violation was ident: fed for maintenance calibration procedures 1 234 5 (M8.1) implemented during the outage that left instrument setpoints outside the inp setpoints stated in the Techrscal Specifications. This condition resulted for the licensee's mis-interpretation of Technical Specifications.
AOOOOO OOOOO cO 000 11/1/1997 Streng+h OPS IR 97-10 (M1.6) NRC Troubleshooting efforts implemented during outage work involved the proper 1 234 5 personnet, procedures and work orders were developed in a timely manner, and actnnties performed were in accordance with procadure guidance. AOOOOO B 00000 cO 000 ENGINEERING" l 6/27/1998 Weakness IR 98-05, O1.1 NRC Design documentation results in plant transient and trip. A weakness in desgn 1 234 5 documentation resu!*ad in incorrect instantaneous overcurrent relay tap settings which let to a loss of power to all four reactor coolant pumps. Also. a review of a similar industry event did not identrfy the potential for a rapid plant cooldown as a AOOOOO resuft of current system configuration and recent design changes completed on the B OOOOO sir operated steam supply valves to the moisture Separator / Reheaters-cO OOO 5/16/1998 Positrve IR 98-04 (E1.1) NRC Engineering and instrumentation and Control personnel support in addressing the 1 234 5 degradation was aggressive and timely. A temporary modification implementation to restore the sequencer to operation was propedy prepared and reviewed. AOOOOO B 00000 cO 000 4/18/1998 NCV IR 98-03, NCV 98-03-05 LICENSEE A non-cited violation was identified for an ;nadequate engineenng temporary test 1 234 5 (E3.2) procedure to retest the sequencer engineered safeguards feature actuation system (ESTAS) actuation signal to an auxiliary component cochng water pump. The A OOOOO procedure was inadequate, in that, as wntten, the pump did not receive the correct start signal and other ccmpcaents actuated unexpectedly. B OOOOO cO 000 FROM.10/1/1997 TO: 1h25/1998 Page 8 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES G18/1998 Positive IR 9843 (E1.1) NRC Electncal modifications on Unit 2 involving the 125-Volt DC ground detection system. 1 234 5 emergency desel generator fuse protecten, and Class 1E switchgear were being performed in accordance with the design change control program. The matenal AOOOOO conditen of the completed work was good. Overati, the desen change packages and the 10 CFR 50.59 sakty evaluaton were adequate. eOOOOO c0 000 3/7/1998 Negative IR 98-02 (E3.1) NRC Yhe inspectors identifed that a Deficiency Card (DC) failed to address all the 1 234 5 problems associated with a breaker failure that occurred during refuehng outage 1R7. Phile the system engineer demonstrated effective review of work activity AOOOOO invobie@ his area of responsibinty by identifying the need for the DC several rnonths afte .m failure, the DC was not comprehensive or complete. O OOOOO cO 000 1/30/$998 Weakness MAINT IR 98-01(E4.1) NRC The lack of check or oversyht of the system engineer's decisions relative to 1 234 5 functional failure ca3s was cons <!ered to be a procedural weakness in the Maintenance Rule program implementation- AOOOOO s00000 cO 000 1/30/1998 Strength MAINT IR 98-01(E4.1) NRC Effective integration of assigned system engineers in the process for imp;ementation 1 234 5 of the Maintenance Rule (MR) program was a major contribtning factor to the program effect!veness. Thrs was considered a strength in the MR program implementation.
AOOOOO OOOOO cO 000 1/30/1998 Posdive OPS IR 98-01(Mt.5) NRC The licensee *s process for ensuring that entical safety functions were available during i234 5 planned outages was adequate. The approach for assessing the nsk-impact to maintenance actrvities, was good. AOOOOO e00000 cO 000 1/30/1998 Negative OPS IR 98-01(M1.2) lFi 98 NRC A sensitivity analysis had not been performed to determine if Maintenance Rule 1 234 5 01 reliability enteria were conserving the assumptons in the Probahstic Risk Assessment,. A OOOOO s00000 cO 00G 1/24/1998 Positive OPS IR 97-12 (E1.1): LER 98- LICENSEE The hcensee's short term correctNe actons for degraded conditions associated with 1 234 5 02 the Emergency Desel Generator (EDG) exhaust system were satisfactory. Concrete debns that had fallen into the EDG exhaust piping was removed. AOOOOO s00000 c0 000 FROM.10/1/1997 TO.11/25/1998 Page 9 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 11/1/1997 Weakness IR 97-10 (E8.3) NRC A weakness was identifed in the area of deficiency conf revew process for the lack 1 234 5 of clear guidance for the determination of Maintenance Preventable Functional Failures. AOOOOO s00000 c0 000 91/1/1997 Weakness IR 97-10 (EB.1) NRC The licensee's revew for Licensee Event Report (LER) 50-424/96-005 was not 1 234 5 adequate in that it did not Mentify the full scope of the Eaton Cabe splicing discrepancy issue. AOOOOO s00000 cO 000 11/1/1997 VIO IR 97-10; VIO 97-10-04 NRC A violation was identifed for the failure to adequately implement corrcctnre actions 1 234 5 (E3.1) for a previous violation involving weaknesses in the APEX computer code user manual that is used for manual calculations of estimated entical position. Corrective actions were not completed in a timely raanner due to resource hmitations.
AOOOOO OOOOO cO 000
-PLANT SUPPORT ' ~" ~ l 9/16/1998 VIO 984)6 S3.1 NRC The inspectors concluded that personnei responsible for escorting the visitors did not 1 234 5 futty understand their responsibilites.
A00000 s00000 cO 000 9/16/1998 VIO 98-06 Rt.1 NRC This was an isolated incident and not indicative of a programmatic weakness in the 1 234 5 control of locked high radiation areas. The licensee identifed a weakness in their routiee preventive maintenance program for locked high radiation area doors. AOOOOO B 00000 cO 000 6/27/1998 Positive IR 98-05. R1.2 NRC Effectnnness of the As Low As Reasonably Achevable (ALARA) Programs. The 1 234 5 heensee was effectively maintaining programs for controlhng radiation exposurers ALARA and continued to be effectrve in conto!hng overall collective dose. All AOOOOO personne! radiation exposures during 1998 to date were below regulatory limits.
OOOOO cO 000 6/27/1998 Positive IR 98-05, R1.1 NRC Performance of radiological control activities. The licensee continued to meet 10 1 234 5 CFR 20 requirements for personnel monitoring, control of radioactive material, and radiological postings of radiation area and high radiation areas. AOOOOO s00000 cO 000 FROM.10/1/1997 TO 11/25/1998 Page 10 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 6/26/9998 Negatue IR 9811, P4.2.b.1,4.2.b 4 NRC Performance dunng biennial emergency exercise. The utihzatron of the shift 1 234 5 technical advisor functional responsibility did not p ovide for an independent engineering assessment of piant conditions. There was good interface between hcensee staff and offsite agencies, representatwes dunng Emergency Operations AOOOOO Facihty brefing sessions, but interaction outside of the brefings was restrained. B OOOOO cO 000 6/26/1998 Positive IR 98-11, P4 2 b 2, NRC Performance during biennial emergency exercise. Command and contro8 of 1 234 5 4.2.b 3,4 2.b 4,4.2 b.5 Technical Support Center (TSC) operations were preficient. Accident management and mitigation efforts were adequate in scope and effective in their implementation-The Operations Support Facihty staff effectively managed to support the repair tasks AOOOOO directed by the TSC. A thorough post exercise entique process was followed by an B OOOOO outstanding management presentation that summarized the most signiftcant exercise observations. The Emergency Operations Facility staff functioned effciently in cO OOO 6/26/1998 FesitNe OPS 1R 98-11. P41. 4.2 b.1 NRC Performance during bennial emergency exercise. The scenario was effective for 1 234 5 teshng the integrated emergency response capability for the onsite and offsite emergency organizatnon. The simulator control room operating crew property AOOOOO analyzed plant conditions and responded with timely and correct actions.
OOOOO cO 000 4/18/1998 VIO IR 98-03, VIO 98-03-06 NRC A violation was identifed involving a centractor failure to follow securRy plan and 1 234 5 (S31) secunty procedure requirements for maintaining proper contro! and visual contact of an escorted indrvidual. AOOOOO B 00000 cO 000 4/10/1998 Positwe IR 98-03. 97-09 NRC Radiation and contamination controls for routine and refuehng outage 2R6 were 1 2 34 5 appropriate and met apphcable UFSAR, Technical Specification, and 10 CFR 20 requirements. Worker doses from 2R6 were proper 1y evaluated. The reactor coolant AOOOOO system cleanup and refueling cutage 2R6 chemistry programs were appropriately managed and contnbuted to reduced dose rates. B OOOOO cO 000 1/24/1998 Positse IR 97-12 (F2.1) NRC Plant fire barrer penetration seal designs were property supported by seal testing 1 234 5 documentation, vendor data, installer qualifications and training recoids, and Quakty Assurance records. Fire barrer penetration seat engineenng evaluations for deviations satisfed Generic Letter 86-10.
AOOOOO OOOOO cO 000 1/24/1998 Strength IR 97-12 (F1.1 & F51) NRC The fire prevention program was effectively implemented. Personnel performance 1 234 5 during a Fire Bngade dril was very good The brigade leader effectwely performed dutes and good fire ground tactics and victim rescue operatiens were performed. AOOOOO B 00000 cO 000 FROM.10/1/1997 TO.11/25/1998 Page 11 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 33_g,, 93
% w m,r w ;
DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES 1/201998 Strength IR 97-12 (S2.1) NRC Secunty equipment testrng practces and apphcable procedures met the 1 234 5 requirements specifed in the Physical Secunty Plan. The dedicated secunty maintenance team was identifed as a strength. AOOOOO sD0000 cO 000 11/1/1997 NCV IR 97-10. NCV 97-1M)6 NRC A non-cited violation was ident: fed for a contract worker who alarmed the plant exit 1 234 5 (R3.1) radiological monitor, and subsequentiy performed a seff-decontamination and left the plant without having contacted Health Physics personnel and obtained proper authorization. This was attnbuted to a cognitive personnel error AOOOOO OOOOO cO 000 11/1/1997 Postve IR 97-10 (R1.1) NRC The removai and storage activites for the lower guide tube were well controlled. 1 234 5 coordinated, and in accordance with the vendor procedure. Worker precautions were appropriate. The licensee's awareness of radiological and personnel safety A OOOO O associated with this activity was identifed as a strength.
OOOOO cO 000 FROM.10/1/1997 TO: 11/25/1998 Page 12 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
VOGTLE 25-Nov-98 DATE TYPE (s) SEC.SFA SOURCE (s) ID'd ISSUE (s) SMM CODES SMM Template Codes: SALP Functional Areas: ID Code:
'}
~ ~
1 A' ' ' OPERATION PERFORMANCE - Normal Operations l : _ LICENSEE ' LICENSEE ~'
'1B OPERATION PERFORMANCE - Operations During Transents! ENG ENGINEERING NRC NRC 1C OPERATION PERFORMANCE - Programs and Processes MAINT MAINTENANCE 'SELF SELF REVEALED
'2A MATERIAL CONDITION Equipment Condition OPS OPERAT!CNS I 2B MATERIAL CONDITION - Programs and Processes PLT SUP PLANT SUPPORT 3A HUMAN PERFORMANCE Work Performance SAQV SAFETY ASSESSMENT & QV 3B HUMAN PERFORMANCE - KSA 3C HUMAN PERFORMANCE-Work Environment 4A ENGINEERING / DESIGN - Design 4B ENGINEERING / DESIGN - Engineenng Support 4C ENGINEERING / DES!GN- Programs and Processes SA PROBLEM IDENTIFfCATION & SOLUTION -Identification SB PROBLEM IDENTIFICATION & SOLUTION - Analysis SC PROBLEM IDENTIFICATION & SOLUTION - Resolution Eels are apparent violations of NRC requirements that are being considered for escalated enforcement action e.1 accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actien"(Enforcement Policy), NUREG-1600. However, the NRC has not reached its final enfostement decision on the issues identified by the Eels and the PIM entries may be modified when the final decisions are made. Before the NRC makes its enforcement decision, the licensee will be provided with an opportunity to either (1) respond to the apparent violation or (2) request a predecisional enforcement conference.
URis are unresolved i* ems at,out which more information is required to determine wtwther the issue in question is an acceptable item, a deviation, a nonconformance, or a violation.
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.
FROM.10/1/1997 TO: 11'255998 Page 13 of 13 FOR PUBLIC RELEASE Last Updated: 9/26/1998
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