ML20196J194
| ML20196J194 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/01/1998 |
| From: | Skinner P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| References | |
| NUDOCS 9812090280 | |
| Download: ML20196J194 (13) | |
Text
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i
! December 1, 1998 i
l i
Southern Nuclear Operating Company, Inc. [
ATTN: Mr. D. N. Morey Vice President P.O. Box 1295 l l
Birminghem, Al35201 i
SUBJECT:
INSPECTION PLAN - FARLEY PLANT r
i Dear Mr. Morey- i On November 2,1998, the NRC staff completed an inspection resource planning meeting. i The staff conducted this review for all operating nuclear power plants in Region 11 to develop an i integrated inspection plan. We conducted this meeting in lieu of the semiannual Plant t Performance Review, which the staff has moved to Febiuary 1999 because of the agency's (
shift to an annual Senior Management Meeting cycle.
t 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 l 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 l effort on the resolution of open inspection items. Therefore, we may conduct additional i 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.
l 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.
i Enclosure 2 contains a historical listing of plant issues, called the Plant Issues Matrix (PIM).
l 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 if !
l in the public document room. I l
i I l
L 9812090280 981201 ~
PDR G ADOCK 05000348 I PDR i l / \
LIJ e,
t i !
t SNC 2 I We will inform you of any changes to the enclosed inspection plan. If you have any questions,
! please contact me at 404 562-4520.
i ,
}
Sincerely, j (Original signed by Pierce H. Skinner) ,
i l Pierce H. Skinner, Chief !
l Reactor Projects Branch 2 i Division of Reactor Projects :
L- Docket Nos. 50-348,50-364 ,
License Nos. NPF-2 and NPF-8 ,
Enclosures:
- 1. Inspection Plan ;
i
- 2. Plant issues Matrix !
cc w/encis:
M. J. Ajtuni, Licensing I l
Services Manager, B-031 Southern Nuclear Operating Company, Inc.
l l 42 Inverness Center Parkway l
Birmingham, AL 35201-1295 j
R. D. Hill, Jr. ;
General Manager, Farley Plant !
Southern Nuclear Operating - !
Company, Inc.
l P. O. Box 1295 Birmingham, AL 35201-1295 l
J. D. Woodard Executive Vice President Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Birmingham, AL 35201-1295 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, AL 36130-1701 l i
- cc w/encls cont'd
- (See Page 3)
?
l f
.i
S l
SNC 3 cc w/encls: Continued M. Stanford Blanton Balch and Bingham Law Firm P. O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201 Chairman Houston County Commission P. O. Box 6406 Dothan, AL 36302 Distribution w/encis:
L. Plisco, Rll P. Skinner, Hil J. Zimmerman, NRR PUBLIC NRC Resident inspector U. S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, AL 36319 A
Orr CE MDRP Ril;MS RIJ:p3S R @ R f , p_
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NGMTURE \ (g#1 NAME CWRapyka KEM l gig [g AMilble L gN (Vp PFredricksoff Q
KLan(M DATE COPY?
11/ K J1/3c/98 ,11/ 3V98 g g /98 J1/?f)/98 11/ /98 11/ /98 YES NO \ YEJ NO /lYES NO /YES ) / NO V YES) NO YES NO YES NO OFFICIAL RECORD COPY DOCUMC)fr NAME. G:\F LEt\PPRFAR. WPM
-l FARLEY INSPECTION PLAN i
INSPECTION NUMBER OF PLANNED INSPECTION :
PROCEDURE / TITLE / PROGRAM AREA INSPECTORS DATES TYPE OF INSPECTION - COMMENTS ,
TEMPORARY !
INSTRUCTION
, = 92904 Fire Protection Followup 1 January,1999 RegionalInitiative 37550 Engineering 3 February,1999 Core Program 37550 Engineering 3 March,1999 Core Program 81700 Security 4 March,1999 Core Program 83750 Rad. Protection 1 March,1999 Core Program r
I Enclosure 1
__ _. ._ _ . _ ...__._.m_ _ - . _ . _ _ _ _ _ ___.___._ . . _ ._.__________m___._ _ __ ..___ _ ,______ _ _ _ .___ _ ___m ____u______________.__--,_.~c- -
. _ - - . * -.---.,,.e-. -.m. =- +- -
Page: 1 of 9 Date: 11/25/1998 United States. Nuclear Regul:t:ry Comm. c in Time:20:39 ,,
Region Il PLANT 12 SUE MATRIX FARLEY By Primary Functional Area Functional Template
- Date Source Area ID Type CMes item Description 10/30/1998 1998003 Pri: ENG )HC STo Prl:4B Changes, tests and experiments were property screened for 10 CFR 50.59 applicabihty. and adequately evaluated to ensure an unreviewed safety question (USO) did not exist.
Sec: See:
Ter:
10/22/1.98 136 Pri: ENG NRC LIC Prl:4B Technical content of the initial license amendment (U1 - #136, and U2 - #128) request to revise and relocate TS Pressure-Temperature curves was not complete. Important information needed to approve this amendment was tacking.
Sec: Sec:4C Also, the licensee did not clearly justify the liberty they took in deviating from methodologies referenced in their submittals.
Ter-06/29/1998 1998005-01 Pri: ENG NRC NCV Pri:4C Licensee determined that the service water lines were moderate energy lines; therefore, flooding due to line breaks was not required to be analyzed.
Sec: Sec:SA '
Ter SC 07/11/1998 1998004-04 Pri: ENG NRC NCV Prl:4A Use of norH:onservative fluid temperatures in the Component Coohng Water and Spent Fuel Pool pipe stress analysis calculations.
See: Sec:4B Ter:
07/01/1998 1998003-04 Pri: ENG NRC VIO IV Pri: 3A The onginal safety assessment for LER 97-10 failed to address the safety consequences of the possible inability to achieve and maintain the plant in a safe shutdown condition.
Sec: OPS Sec: 5B Ter:
05/30/1998 1998003 Pri: ENG NRC STR Pri: 4C Licensee had established suitable programmatic guidance to ensure that the regulatory requirements of 10 CFR 50.59 I Sec: would be met by the various onsite and offs;te organizations. Training of safety evaluation preparers and reviewers was Sec: adequate. Personnel preparing and reviewmg safety evaluations were quahfiea.
Ter:
05/30/1998 1998003 Pri: ENG NRC WK Pri:4C Documentation that addressed the 10 CFR 50.59 USQ cnteria in several safety evaluations lacked specificity and very few of the safety evaluation forms provided any direct evidence of a cross-disciplinary review.
Sec: Sec: 3A Ter:
04/11/1998 1998002 Pri: ENG NRC NEG Pri:2A A Deficiency Report dated 9/16/97 identified leakage on the 1B RHR pump but the leakage was not included in total primary leakage. The hcensee initially did not use any type of measuring device to accurately quantify the leakrate. Also, the See: See: 3A primary leakage procedure did not provide specific directions to evaluate teaks under actual operatirg conditions. i Ter: 5B ltem Type (Comphance. Followup,Other), From 10/01/1997 1o 11/25/1998 Enclosure 2
P 2 of 9 -
Date: 11/25/1998 United States Nuclear Regul t ry Comm.emn Time: iO:39:n ,
P.e, ion i: PLANT 12 SUE MATRIX FARLEY By Primary Functional Area Functional Template Date Source Area ID ' Type Codes item Description 02/21/1998 1998001 Prl: ENG NRC POS Pri:4A The licensee's self-initiated safety system assessment of the containment ventilation and spent fuel pool systems were thorough and effective in identifying design discrepancies and weak areas.
Sec: Sec: 5A Ter: 5B 12/29/1997 1997014-05 Pri: ENG NRC VIO IV Pri:2A The TDAWFP pump went stack was not housed in a Cat 1 structure to protect against tomado generated missles.
Sec: Sec:4A Ter: 1C 11/17/1997 1997011-02 Pri: ENG NRC VIO IV Pri:1C Inservice testing (IST) program did not include revese flow testing of the turbine-driven auxiliary feedwater (TDAFW) pump discharge check valve.
Sec: See:48 Ter: SA 11/17/1997 1997011-04 Pri: ENG NRC VIO IV Pri: 1C Lack of a service test program for the TDAFW pump uninteruptible power supply (UPS) battery to ensure required duty cycles would be met.
Sec: Sec: 2A Ter:4B 11/17/1997 1997011-05 Prl: ENG NRC VIO IV Prt:4C Design control measures did not ensure that ca!culations were verified and controlled adequately.
Sec: Sec: 3A Ter:
11/17/1997 1997011-06 Pri: ENG NRC VIO IV Prl:4B Adequate corrective actions were not taken to resolve differences between plant procedures and CCW system P&lDs identified by a licensee 1990 self-assessment.
Sec: Sec:4C Ter: SC 11/17/1997 1997011-07 Pri: ENG NRC VIO IV Pri:48 Surveillance testing acceptance enteria for the auxihary building vital 125 VDC batteries were revised without recognizing that they exceeded TS requirements.
Sec: Sec:4C Ter: 5A 11/17/1997 1997011-03 Prl: ENG NRC VIO IV Pri:2A Inappropriate IST acceptance enteria for forward flow testing of a TDAFW check valve and failure to follow drawings in the installation of Unit 2 TDAFW battery structural / electrical components.
Sec: MAINT Sec: 2B Ter:3A Item Type (Compliance, Followup,Other), From 10/01/1997 To 11/25/1998
Page: 3 of 9 Date: 11/25/1998 United States Nuclear Regul t:ry Comm.ccian Time: 10:39:ii ,
Region n PLANT ISSUE MATRIX FARLEY By Primary Functional Area Functional Templete Date Source Area ID Type Codes item Description 10/18/1997 1997011 Pri: ENG NRC NEG Prt:4B Resolution of UFSAR discrepancy #089, of the UFSAR Revenfication Program, was not thorough and used non-conservatrve calculations.
Sec: Sec:4C Ter: SC 10/18/1997 1997011 Pri: ENG NRC POS Prl:2A Licensee actions to assess and correct corroded conditions of the serva water discharge piping were prompt and effective.
Sec: Sec:4B Ter: SC 10/18/1997 1997011 Prl: ENG NRC POS Pri:4B NRC staff determined that SNC's compensatory measures, reporting, and safety assessment ir: response to GL 95-05 were Sec: OPS See:4C Ter: SC 10/06/1997 1997010-08 Pri: ENG NRC VIO IV Prt:4A installation of Half-hour Kaowool Fire Barriers Without Appendix R Exemption.
Sec: PLTSUP Sec4B Ter: 5A 07/11/1998 1998004 Pri: MAINT NRC STR Pri:3A Maintenance and surveillance testing activities were generally crmducted in a thorough and competent manner by qualified individuals in accordance with plant procedures and work instructions. Close coordination was maintained with the main Sec: OPS Sec:2B control room during surveillance testing activities. (Also IR 98-01,02,03,05)
Ter: 3B 05/30/1998 1998003 Pri: MAINT NRC POS Pri: 5B The corrective actions following several dropped rod events appeared to be comprehensive and effective, pending completion of the licensee's root cause determination.
Sec: See: SC Ter:
05/30/1998 1998003 Pri: MAINT NRC NEG Pri:2B The licensee issued a procedure that permited the use of high temperature liquid penetrant outside the allowable temperature range of 60 F to 125 F without f:rst qualifiying the procedure as required by the ASME Boiler and Pressure Sec: ENG Sec:4B Vessel code.
Ter:
04/11/1998 1998002 Pri: MAINT NRC POS Pri:3A Meam Safety Valve testing was performed by knowledgeable contractor personnel with oversight by the assigned lic owe personnel. Technicalissues were resolved promptly and conservatively.
Sec: Sec: 2B Ter* 3B ltem Type (Compliance.Folicwup,Other), From 10/01/1997 To 11/25/1998
Page: 4 of 9 . Date: 11/25/1998 United States Nucle:r Regul t:ry Comm.ers:n Time: 10:39:21 ,
Region n PLANT ISSUE MATRIX FARLEY By Primary Functional Area Functional Template Date Source Area ID Type Codes item Description 0.7121/1998 1998001 Pri: MAINT NRC POS Prl: 2A Surveillance testing of the 2A Containment Spray pump was adequately performed and the personnel demonstrated caution while trying to determine source and extent of the system vibrations.
Sec: OPS Sec: 3A Ter: SB 01/10/1998 1997015-02 Pri: MAINT NRC NCV Pri:3A Craft personnel failed to sign-in on the Personnel and Materia! Accountabihty Log when working in the controlled refuehng area boundary as required by plant procedure.
Sec: Sec: 1C Ter: 3C 11/29/1997 1997014 Pri: MAINT NRC STR Pri:2B Corrective actions to address mu!tiple pre-action sprinkler system failures identified in 1996 have been comprehensive, thorough, and successful. An adddional corrective action plan was initiated to resolve the small number of remaining Sec: Sec: failures.
Ter:
11/29/1997 1997014 4 2 Pri: MAINT NRC NCV Pri: 3A During observations of work on safety related equipment, maintenance personnel were not signing off completed steps of "Continous Use" procedures.
Sec: Sec: 3C Ter:
11/29/1997 1997014-04 Pri: MAINT NRC NCV Pri:3A During maintenance activities, both trains cf automatic Service Water isolation to the Turbine Building were rendered Sec: OPS Sec: 3C Ter:
10/18/1997 1997011 Pri: MAINT NRC POS Pri: 3A Maintenance and testing activites associated with the replacement of Unit 2 pressurizer pressure transmitter (PT 456) were well controlled, performed in accordance with plant procedures and work instructions, and accomphshed without incident.
Sec: OPS Sec: 3B Ter: 2B 10/17/1998 1998006 Prl: OPS NRC NEG Pri: T The minor departure process lacked pre-implementation independent review by system specialists, quality assurance, and the onsite safety committee. The lack of these revews contnbuted to an error in developing a minor departure.
Sec: Sec: SA Ter:
10/17/1998 1998006 Pri: OPS NRC STR Pri:1A Operator response to abnormal and routine plant conditions was strong including a Unit 1 automatic reactor trip, a startup of Unit 1 following a steam generator tube repair activity, a shutdown of Unit 1 for refuehng, and Unit 2 partial loss of cooling to Sec: Sec:18 the reactor coolant pumps.
Ter: 3A Item Type (Compliance. Followup.Other), Fr m 10/01/1997 To 11/25/1998
Page: 5 of 9 Date: 11/25/1996 United Statea Nucl:Cr Regul tsry Commiri:n Time: 20:39;is Region ii PLANT ISSUE MATRIX FARLEY By Primary Functional Area Functional Template Date Source Area 30 Type Codes item Description 10/17/1998 1998000-01 Prl: OPS NRC NCV Pri: 1C Operations staff failed to assemble the fire brigade as required by AOP-29 0 for hydrogen stack fires on three seperate occassions.
Sec: PLTSUP Sec: 3A Ter:
08/29/1998 1998005 Prl: OPS NRC POS Prl:1A The licensee adequately prepared for and satisfactorily conducted Unit 1 mid-Icop operations. Alllevelindicators were operable and closely monitored by the operators. (Also IR 98-03)
Sec: See: 1C Ter: 3A i
08/29/1998 1998005 Pri: OPS NRC POS Pri: 1B Response to Unit 1 Circulating Water Pump trip and Component Cooling Water heat exchanger tube leak was prompt, demonstrated good plant awamess, and was well coordinated. Supervisory command and control was evident.
Sec: See: 3A Ter: SA 08/29/1998 1998005 Pri: OPS NRC POS Pri: 1C The heensee appropriately and conservatively responded to steam generator tube leakage including enhanced training and plant procedure revisions.
Sec: PLTSUP Sec: 3B Ter-05/30/1998 1998003 Pri OPS NRC POS Pri:1A Mode transitions, initial startup and power ascension following refueling were well controlled and performed in a conscientious and conservative manner. (Also IR 97-03,97-06,98-02,96-15)
See: Sec: 2A Ter: 3A 05/30/1998 1998004 Prt: OPS NRC POS Pri: 1 A Operator attentiveness to MCB alarms and changing plant conditions were excellent. Operators were consistently aware of plant status and ongoing work activities. Onshift SRO command and control, and Ops management oversight remained at a Sec: Sec: 3A high level. (Also IR 97-15,14,10.08,06,05,98-01,98-02,03)
Ter:
04/11/1998 1998002 Pri: OPS NRC NEG Pri:2A The assigned priontization did not ensure that freeze protection equipment for safety-related equipment was corrected or compensated for in a timely manner. The guidance in the Cold Weather Contingencies procedure did not distinguish Sec: MAINT Sec:2B between safety and non-safety related freeze protection circuits. (Also IR 96-15,97-14)
Ter: 1C 04/11/1998 1998002-01 Prl: OPS NRC NCV Pri:3A The Shift Supervisor failed to use Emerge 9cy Response Procedure placekeeping aids during response to a manual reactor trip initiated for a dropped control rod. This was previously identifed as a negative training issue. ,
Sec: PLTSUP See: 1B Ter:
Item Type (Compliance, Followup,Other), From 10/01/1997 To 11/25/1998 i
w ___ ,. _ - - . - - - . - - - , -. - . . . - , - , - - - - - - - ---
4 Paged 6 of 9 Date:11(25/1998 United States Nucirr Regul:t:ry Commiaa.:n Time:io:ss:ii Region Il PLANT ISSUE MATRIX FARLEY By Primary Functional Area Functional Template Date Source Area ID Type Codes item Description 03/08/1998 1998002 Prl: OPS NRC POS Prl: 1B Licensee response to elevated river levels due to heavy rain was appropriate. Sufficient preparations were made and necessary equipment obtained as conditions worsened.
Sec: MAINT Sec: 10 Ter:
02/21/1998 1998001-01 Pri: OPS NRC NCV Prl:3A Conduct of Operations procedure required oncoming system operators to walkdown all areas unter their responsibihty after completing tumover. Observations of and interviews with system operators found they were only touring areas identifed on Sec: Sec: SA the data loggers or as directed by the M.* Control Room. Since the data loggers did not address all areas under the opeators "esponsibihty, many areas we 9 not routinely toured.
L 02/11/1998 1998001 Pri: OPS NRC POS Pri: 3A Plant operators performed well dunng on-line replacement of the 1B Main Feedwater Regulating Valve control driver card.
The Shift Supervisor maintained command and communications with the operators and technicians during the power Sec: MAINT Sec: 1B reduction and card replacement. Troubleshooting activities correctly diagnosed the problem with the control dnver card.
Ter:
01/10/1998 1997015-01 Pri: OPS NRC NCV Pri:2A THE CONTAINMENT AIR COOLER CONDENSATE LEVEL MONITORING (CCLM) SYSTEM WAS INOPERABLE (DUE TO MISPOSITIONED VALVES) WHILE THE CONTAINMENT ATMOSPHERE GASEOUS AND PARTICULATE RADITION Sec: ENG Sec: 2B MCNITORING SYSTEMS (R-11 AND R-12)WERE SIMULTANEOUSLY INOPERABLE. THIS CONSTITUTED A CONDITION PROH:BITED BY TS. The procedures for the entmnt air cooler cond level monitoring (CCLM) system failed to Ter:4B list the throttled position for the drain valves rendering the CCLM inoperable.
11/29/1997 1997014-01 Pri: OPS NRC NCV Prl:2B Major portions of" Extreme Cold Weather Contingencies" were not complete prior to below freezing temperatures, including operations and maintenance responsibdties.
See: MAINT Sec: 3C Ter:
10/18/1997 1997011 Pri: OPS NRC POS Pri:1C Operations management implemented prompt and effective compensatory measures (i e., reduced RCS activity limit) to address safety concerns regarding a projected increase in end-of-cycle SG conditional tube leakage.
Ter: SC l
10/18/1997 1997011 Pri: OPS NRC POS Pri:1A Engineering test procedure (ETP-3607) for fully withdrawing Unit 2 control rods to a new position was well wntten and .
controlled. The evolution was conducted in a smooth ar'd deliberate manner, t See: ENG Sec: 1C Ter:4B 10/17/1998 1998006 Pri: PLTSUP NRC NEG Prl: 3A Two instances of inattentive Secunty Guards were observed. These apoeared to be isolated cases.
Sec: Sec: 3C Ter:
r item Type (Compliance. Followup,Other), From 10/01/1997 To 11/25/1998
United States Nucle r Regul:t ry Commirinn M if $
- Region 1: PLANT ISSUE MATRIX FARLEY By Primary Functional Area Functional Template Date Source , Area ID Type Codes item Description 07/11/1998 1998004 Pri: PLTSUP NRC POS Pri:3A A reactor vessel specimen transfer from the Spent Fuel Pool to the transfer cask was property executed and adequately planned. Personnel wee property trained and brefed. Conducting the transfer underwater significantly reduced Sec: Sec: 28 accumulated dose.
Ter:
07/01/1998 1998003-07 Prl: PLTSUP NRC VIO IV Prl:3A The failure te include a documented process in access control procedures for contractors to timely inform the Security Department of terminated individuals contnbuted to a violation for failure follow procedure to immediately terminate eight Sec: Sec: 28 individuals' unescorted access.
Ter 05/30/1998 1998003 Pri: PLTSUP NRC STR Pri:3A Worker Shallow Dose Equivalent (SDE) exposures resulting from personnel contamination events and work activites during refueling activities were evaluated property. Controls for minimizing workers'intemal exposure during refueling activities See: Sec: 5B were effecbve. Respiratory protection training. fit tests, medical qualifications, and equipment status met 10 CFR 20.1703 requirements. The Health Physics (HP) and Dosimetry (DOS) observation program continued to be implemented effectively Ter: 38 and contributed to the reduced personnel errors. (Also IR 97-14) 05/30/1998 1998003 Prl: PLTSUP NRC STR Pri:3C Emergency Response Facilites (ERFs) were well-equipped and operationally ready to support an emergency response.
Emergency response personnel were adequately trained and responded appropriately to a scheduled dnll. The emergency Sec: See: declaration on March 8,1998, was made in accordance with the Emergency Plan.
Ter.
05/30/1998 1998003 Prl: PLTSUP NRC POS Pri:2A The evaluated Radiation Monitor System (RMS) equipment was installed property and the reviewed detector calibratens and functional tests were conducted in accordance with and met procedural,10 CFR Part 20, and Offsite Dose Calculation Sec: MAINT Sec:2B Manual (ODCM) requirements Ter:
03/23/1998 1998001-08 Pri: PLTSUP NRC VIO IV Pri:3A During observed maintenance activites in contaminated aress, the inspectors witnessed several examples of improper contamination control pratices. Workers removed PCs outside the contaminated area boundary and breached the boundary Sec: MAINT Sec: 3B during work.
Ter.1C 02/21i1998 1998001 Pri: PLTSUP NRC NEG Pri: 2A Additional pre-action sprinkler system failures indicate that prior corrective actions were not completely effective.
Sec: ENG Sec: 5B Ter: SC 02/21/1998 1998001 Pri: PLTSUP NRC POS Pri: 2A immed: ate corrective actions for pre-action fire protection sprinkler system failures were prompt and conservative.
Sec: MAINT Sec:2B Ter.
It m Type (Compliance, Followup,Other), From 10/01/1997 To 11/25/1998
Page: 8 of 9 Date: 11/25/1998 United States NucleIr Regul;,.t:ry Commi s : n Tim.: 10:39:is '
Region 11 PLANT ISSUE MATRIX FARLEY By Primaty Functional Area Functional Template Date Source Area ID Type Codes Item Description s
02i21/1998 1998001 Pri: PLTSUP NRC POS Pri:3B The heensee's requalr!ication program complied with the requirements and standards of plant procedures as well as the requirements of 10 CFR 55.59 for the areas inspected. The hcensee developed and administered simulator examinations Sec: OPS Sec: 1C that effectively identified areas in need of improvement Ter:
02/21/1998 1998001 Prl: PLTSUP NRC POS Pri:2A Licensee actions in response to SAER HP, Chemistry and Radwaste audit findings were thorough and appropriate.
Sec: OTHER Sec: 2B Ter:
11/29/1997 1997014-06 Pri: PLTSUP NRC NCV Pri:3A HP personnel used the current date and time instead of the intake date and time to perform followup assessments of radionuclide intakes for two individuals. Reanalysis using the correct date and time did not significantty change the Sec: Sec:1C assessment results.
Ter:
t 11/29/1997 1997014-07 Pri: PLTSUP NRC NCV Pri: Equipment failures, poor procedures, and inadequate personnel followup were root causes for not taking routine grab samples when both Unit 2 gaseous and particulate radiation monitors were inoperable.
Ter:
11/29/1997 1997014-08 Pri: PLTSUP NRC NCV Pri: Individual failed to conduct required Emergency Preparedness equipment inventories and fals:iied the checklists to hide thrs failure.
Sec: Sec:
Ter:
11/17/1997 1997011-08 Prl: PLTSUP NRC VIO IV Pri: 1C Copies of the site security plan, contgency plan, and procedures were being stored in an unlocked drawer in the control room without maintaining positive control at all times Sec: Sec: 3A Ter: 5A 10/06/1997 1997010-05 Pri: PLTSUP NRC VIO IV Pri:2A Corrugated flexible steel tubing and plastic hose used in samipe lines for various plant vent and containmnet pugre particulate samplers instead of smooth stainiees steel tubing with minimum bend radii.
Sec: ENG Sec:4A Ter: SA litm Type (Compliance, Followup,Other), From 10/01/1997 To 11/25/1998
Page: 9 of 9 Date: 11/25/1996 United States Nucle:r Regulat:ry Comm.oci:n Time: iO:39;ii PLANT ISSUE MATRIX By Primary Functional Area Legend Type Codes: Template Codes: Functional Areas:
~~ '
~ ~~
- BU Bulletin ! [1 A ' ' Normal Operations { OPS.' ~ ~ ~ Operations
!CDR Construction ,
1B Operations During Transients { lMAINT Maintenance l DEV Deviation i l1C Programs and Processes { jENG Engineenng j
' eel Escalated Enforcement item ;2A Equipment Condition i :PLTSUP Plant Support llFI Inspector follow-up item , ;2B Programs and Processes , !OTHER Other i
' ~ ~~
jLER Licensee Event Report !3A Work Performance [
l LIC Licensing issue ;3B KSA ;
- MISC Miscellaneous 1 !3C Work Environment
,MV Minor Violation Design i f4A (NCV NonCited Volation l4B Engineering Support
- NEG Negative ! !4C Programs and Processes !
'NOED Notice of Enforcement Drscretion ;
SA Identification
'NON Notice of Non-Conformance .58 Analysis
.P21 Part 21 ,SC Resolution POS Positive ID Codes:
SGI Safeguard Event Report
-NRC' ~ NRC
- STR Strength '3,g gg URI Unresolved item
{Lcensee Licensee
- VIO Violation M'K Weakness ,
Eels are apparent violations of NRC Requirements that are being considemd for escatated enforcement action in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Action"(Enforcement Policy). NUREG-1600. However, the NRC has not reached its final enforcement decision on the issues identified by the Eels and the PIM entnes may be modifed when the final decisions are made.
URis are unresolved items about which more information is required to determine whether the issue in question is an acceptable item, a deviation, a nonconformance, or a violation. A URI may s.tso be a potential violation that is not likely to be considered for escalated enforcement action. However, the NRC has not reached its final conclusions on the issues, and the PIM entnes may be modifed when the final conclusions are made.
r item Type (Compliance Followup.Other), From 10/01/1997 To 11/25/1998
- - _. __ .. _ .-. _ . _ - _ _ - _ _ . _ _ . _ _ _. - - _ . _ _ . _ _