ML20134H604

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FOIA Request for List of Violations Since 930101 to Present, at All Nuclear Power Plants Managed by Entergy,Inc in La
ML20134H604
Person / Time
Site: River Bend, Waterford  Entergy icon.png
Issue date: 09/05/1996
From: Griffin S
AFFILIATION NOT ASSIGNED
To: Grimsley D
NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML20134H596 List:
References
FOIA-96-376 NUDOCS 9611140174
Download: ML20134H604 (51)
v • d • e


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September 5,.1996 Mr. Donald Grimley, Director Freedom of Information Act Requests U.S.

Nuclear Regulatory Commission Washington, D.C.

20005 REQUEST FOR INFORMATION:

Please send a list of all violations since January 1st, 1993 to the present, at all nuclear power plants which were and/or are managed by Entergy, Inc., in Lousiana.

Very truly yours,

(.Ad dLA- [$

Susan B. Grffin, Chenango North Energy Awareness Group t

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FOIA-96-376 Attached is a report on the violations issued for the Riverbend and Waterford reactor licensees from January 1993 thru September 1994. The NRC has a contractor who is checking the quality of all data in the Inspection Followup System, the computerized data system that has the information from which the attached was obtained. They have determined that about 18% of all inspection records are missing from this Inspection Followup System. Moreover, the contractor has determined that even when records are not missing, they may contain errors, particularly in the date listed for issuance, in the listed severity (i.e., Severity 1 [the highest] thru Severity 5 [the lowest]) of the violation, and in the title and text / status that describes the violation. These latter errors average 2% for dates and about 33% of the records for title and text / status. It is not known what percentages actually apply for the Riverbend or Waterford records. The NRC contractor will be fixing these errors. However, the fixes will not be made--assuming the NRC contractor meets its current schedule-- (1) until January 1997 for inspection reports and associated violations issued from January 1993 thru September 1993, and (2) until March 1997 for inspection reports and associated violations issued from October 1993 to September 1994. 1

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER BANNER PAGE TIME: 10:19:44 REPORT BY SITE PAGE: 1 REGION: 0 SITES: DOCKETS: EA-CASE: ABBR NAME NUMBER NAME NUMBERS WAT WATERFORD ALL r ORGANIZATION: EMPLOYEES: CODE NAME ID NAME ALL

    • ALL EMPLOYEES **

j REPORT ON: ALL FROM DATE: 01/01/1993 TO DATE: 09/30/1994 INSPR-NO: ALL ITEM TYPE: DEV, NCV, VIO CAUSE CD: A SEVERITY CD: A STATUS: ALL FUNCTIONAL AREA: ALL REACTOR TYPE: POWER ENFORCEMENT IND. ALL COMMENT TEXT IS REQUESTED i I i L h L

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 ffi4(j10:19: 4 E. GREHER REPORT BY SITE g SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS WAT3 I 92-027 01 VI^ 4/1 MS 02/01/93 C 02/11/93 01/20/94 4205 ERF 93-016 TITLE: INADEQUATE CORRECTIVE ACTIONS PROC NUMBER: 92702 COMMENTS: CONTRARY TO CRITERION XVI OF APPEN B TO 10CFR50 AND THE LICENSEE'S APPROVED QUALITY ASSURANCE PROGRAM DESCRIPTION, REV 5 WHICH REQUIRE THAT MEASURES BE ESTABLISHED TO ASSURE THAT CONDITIONS ADVERSE TO QUALITY ARE PROMPTLY IDENTIFIED AND CORRECTED, THE CORRECTIVE ACTIONS TAKEN IN RESPONSE TO VIO 50-382/8941-02 WERE INADEQUATE IN THAT THEY DID NOT CONTAIN DETAILS CORRECTIVE ACTIONS IN RESPONSE TO VIO 382/9201-01 WERE INADEQUAT IN THAT THE LIST OF ALL AFFECTED CONTROLLED DRAWINGS WAS NOT UP-DATED EACH TIME A TEMPORARY ALTERATION WAS INSTALLED OR REMOVED. WAT3 I 93-010 01 VIO 4/1 SEC 05/04/93 C 05/13/93 12/30/94 4250 TIP 94-021 TITLE: INADEQUATE FIRE WATCH PATROLS PROC NUMBER: 71707 i COMMENTS: ))RARY TO TS 6.8.1F WHICH REQUIRES WRITTEN PROCEDURES BE ESTABLISHED, IMPLEMENTED, AND MAINTAINED COVERING IMPLEMENTATION OF THE FIRE PROTECTION PROGRAM. THE FIRE WATCH PATROL WAS INAD-EQUATE IN THAT PERSONNEL FAILED TO OBSERVE THE AREA FOR FIRE HAZARDS, AND IN THAT THE TIME DURATION THAT PATROL PERSONNEL WERE IN THESE ROOMS WAS INSUFFICIENT OF OBSERVE THE AREA FOR FIRE HAZARDS. WAT3 I 93-016 01 VIO 4/1 SAQV-O 06/09/93 C 07/08/93 01/20/94 4205 ERF 93-034 TITLE-FAIL TO ENTER OFF-NORMAL PROCEDURE / IMMOVABLE CEA PROC NUMBER: 61726 COMMENTS: CONTRARY TO TS 6.8.1.C WHICH REQUIRES WRITTEN PROCEDURES BE ESTA BLISHED, IMPLEMENTED,AND MAINTAINED COVERING SURVEILLANCE AND TE ST ACTIVITIES OF SAFETY-RELATED EQUIPMENT, OPERATORS FAILED TO R EFER TO OFF-NORMAL PROCEDURE UPON DETERMING THAT PART-LENGTH CEA 28 WAS IMMOVABLE DURING THE PERFORMANCE OF SURVEILLANCE PROCEDUR E WAT3 I 93-019 01 VIO 4/1 OPS 07/20/93 C 08/19/93 04/12/94 4250 ERF 94-005 TITLE: FAIL TO LOCK VALVE EGA-1528/VIO OF TS 6.8.1.A PROC NUMBER: 71707 COMMENTS: CONTRARY TO ADMIN PROC OP-100-009, REV 11 " CONTROL OF VALVES AND BREAMERS," REQUIRING THAT VALVES AND BREAKERS LISTED IN ATTACHMENTS 6.1, 6.2 AND 6.3 SHALL BE LOCKED IN THE SPECIFIED POSITION WITH LOCKS OR POSITIVE LOCKING DEVICES, VALVE EGA-1528 WAS FOUND TO BE UNLOCKED IN THE OPEN POSITION. WAT3 I 93-021 01 NCV OPS 10/13/93 C 11/18/93 10/13/93 4613 SPM 93-021 TITLE: FAIL TO REVISE SHIFT SUP'S EMERG PLAN IMPL PROCEDURES PROC NUMBER: 2515/117 i - - ~ ~ - - - - - -.

.t ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM D g jj (l / / E GREHER REPORT BY SITE PAGE-3 r SITE:. WAT' WATERFORD ~! UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT' DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS .............................................................................._.............................-.....-~.------------- WAT3 I 93-022 01-VIO 4/4 RADCON 06/24/93 C 07/08/93 10/15/93 4304 LTR 93-030 I TITLE: FAILURE TO SAMPLE WASTE STREAM ANNUALLY PRG3 NUMBER: 86750 COMMENTS: CONTRARY TO TS 6.13.1 WHICH REQUIRES ANNUAL ANALYSIS BE PERFORME D ON THE WASTE STREAMS, IT WAS DETERMINED THAT THE CHEMICAL VOLU ,l v" CONTROL SYSTEM FILTER SAMPLES WERE NOT COLLECTED AND SUBMITTE t0R OFFSITE ANALYSIS BETWEEN NOV 1990 AND AUG 1992.. u L WAT' I 93-023 02 NCV OPS 09/08/93 C 09/28/93 09/08/93 4205 93-023 1(LE: VID OF TS 6.8.1 - REPAIR OF WRONG VALVE WITH WA PROC NUMBER: 71707 WAT3 I 93-025 01 VIO 4/1 ETS-0 OS/28/93 0 11/18/93 4610 i TITLE: FAILURE TO IMPLEMENT PROCEDURES PROC NUMBER: 92701 ( COMMENTS: CONTRARY TO W3 PROCEDURE UNT-005-002 WHICH STATES THAT i EMPLOYEES ARE RESPONSIBLE FOR

  • REPORTING AND IDENTIFYING AB-r NORMAL CONDITIONS UPON OBSERVATION AND INITIATING A CONDITION t

IDENTIFICATION TO OBTAIN RESOLUTION. CONDITIONS ADVERSE TO QUALITY SHALL ALSO BE FURTHER IDENTIFIED AS A NCI." LICENSEE FAILED TO INITIATE NONCONFORMING CONDITION IDENTIFICATIONS FOR t OUT-OF-TOLERANCE AS-FOUND SET PRESSURES. WAT3 I 93-027 02 NCV MS 10/07/93 C 11/18/93 10/07/93 4205 93-027 I TITLE: LACK OF REQUIREMENT IN PROCEDURES PRGC NUMBER: 92701 = WAT3 I 93-029 02 VIO 4/1 SAQV-O 10/28/93 C 11/16/93 02/16/95 4610 PMQ 95-011 TITLE: INADEQUATE PROCEDURE PROC NUMBER: 38701 WAT3 I 93-030 01 VIO 4/4 RADCON 10/15/93 C 11/18/93 05/05/94 4640 LTR 94-010 p TITLE: FAILURE TO IMPLEMENT PROCEDURES PROC NUMBER: 83750 COMMENTS: CONTRARY TO SEC 7.E,(4) 0F APPEM)IX A OF REG GUIDE L.33, REV 2 WHICH LISTS RADIATION PROTECTION PROCEDURES FOR CONTAMINATION CONTROL. 1) NO NASAL WIPES WERE OBTAINED FROM INDIVIDUALS WHO WERE IDENTIFIED AS HAVING FACIAL CONTAMINATION; 2) FINAL SURVEYS l CONDUCTED OF INDIVIDUALS WITH SKIN CONTAMINATION REPORTED THE t RESIDUAL CONTAMINATION FOLLOWING DECONTAMINATION AS "<1000 CPM", I l INDICATING THAT THE INDIVIDUALS MAY HAVE BEEN RELEASED WITH SKIN .l CONTAMINATION GREATER THAN-100 CPM / PROBE AREA: 3) THE DATES AND t, TIMES THAT RESURVEYS WERE CONDUCTED FOLLOWING DECONTAMINATION OF INDIVIDUALS WERE NOT DENOTED. f WAT3 I 93-030 02 NCV RADCON 10/15/93 C 11/18/93 10/15/93 4304 LTR 93-022 TITLE: DELINQUENT IN PERFORM OF INVENTORIES OF RAD SOURCES PROC NUMSER: 83750 t f I e l 5 .[

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER REPORT BY SITE 10:19:4 f[M(: SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING EA/ NBR NOV-ID TYPE EA ......____-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS ABBR WAT3 I 93-031 01 VIO 4/3 SEC 11/05/93 C 11/18/93 04/29/94 4300 TKD 94-009 TITLE: FAIL TO SEARCH HAND-CARRIED ITEMS ENTERING PA PROC NUMBER: 81700 COMMENTS: CONTRARY TO SECURITY PROCEDURE PS-011-102, REV 13, " PERSONNEL ACCESS AND EXIT " WHICH REQUIRES, IN PART, THAT PRIOR TO ENTERIN G THE PROTECTED AREA THE INDIVIDUAL'S HAND-CARRIED ITEMS SHOULD BE PLACED ON THE CONVEYOR BELT FOR PURPOSES OF HAVING THEM SEARCHED BY MEANS OF THE PACKAGE X-RAY EXAMINATION DEVICE. ITEM S THAT ARE TOO LARGE OR OTHERWISE CANNOT BE SEARCHED BY THE X-RA Y EXAMINATION DEVICE SHALL BE PHYSICALLY SEARCHED BY SECURITY PERSONNEL. A HAND-CARRIED ITEM ENTERED THE PROTECTED AREA WITHOU T BEING SEARCHED BY THE X-RAY EXAMINATION DEVICE OR BEING PHYSI-CALLY SEARCHED BY A SECURITY OFFICER, VAT 3 I 93-032 01 VIO 4/1 OPS 11/29/93 C 01/13/94 12/30/94 4250 TIP 94-021 TITLE: VALVE CMU-1131 LEFT IN OPEN POSITION PROC NUMBER: 71707 COMMENTS: CONTRARY TO TS 6.8.1, WHICH REQUIRES, IN PART, SAFETY-RELATED ACTIVITIES BE COVERED BY WRITTEN PROCEDURES, VALVE CMU-1131 WAS OPENED AND LEFT IN THE OPEN POSITION. AS A RESULT OF THIS MISA-LIGNMENT, THE AUTOMATIC MAKEUP SYSTEM FOR THE SAFETY-RELATED WET COOLING TOWER BASINS DID NOT FUNCTION AS DESIGNED, ALLOWING THE LEVEL OF THE BASINS TO DECREASE TO A POINT BELOW THE TS REQUIRED MINIMUM LEVEL. WAT3 I 93-033 02 VIO 3/1 OPS 10/26/93 C 01/13/94 10/25/94 4250 ERF 94-019 TITLE: FAILURE TO RESTORE CS-12SA TO OPERABLE STATUS PROC NUMBER: 93702 WAT3 I 93-033 03 VIO 3/1 SAQV-0 10/26/93 C 01/13/94 10/25/94 4250 ERF 94-019 TITLE: FAILURE OF CS-125A IN TRAIN A TO OPEN ON DEMAND PROC NUMBER: 93702 WAT3 I 93-034 02 VIO 4/4 RADCON 01/20/94 C 02/03/94 07/05/94 4640 ERF 94-011 TITLE: IMPROPER ENTRY INTO RADIOLOGICAL RESTRICTED AREA PROC NUMBER: 61726 COMMENTS: CONTRARY TO TS 6 8.1 WHICH REQUIRES, IN PART, THAT ACCESS TO RADIATION AREAS AND THE IMPLEMENTATION OF AN ALARA PROGRAM BE COVERED BY RADIATION PROTECTION PROCEDURES, A MAINTENANCE TECHNI CIAN MADE ENTRIES INTO THE OVERHEAD OF THE RADIATION CONTROLLED AREA WITHOUT CONTACTING HEALTH PHYSICS PERSONNEL PRIOR TO MAKING ENTRIES. WAT3 I 93-035 01 VIO 4/1 ETS-0 03/04/94 0 03/15/94 4610 TITLE: INADEQUATE DESIGN CONTROL PROC NUMBER: COMMENTS: CONTRARY TO CRITERION III 0F APPENDIX B TO 10 CFR PART 50

jf((jfl/fg/$6 ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM E. GREHER REPORT BY SITE PAGE: 5 SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP RE60RT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS [ ............./..NBR WHICH STATES. IN PART, THAT DESIGN CON'ROL MEASURES SHALL PROVIDE FOR VERIFYING OR CHECKING THE >DE70ACY OF DESIGN BY USE OF ALTERNATE OR SIMPLIFIED CALCULAiIGN METHODS OR BY THE PERFORMANCE OF A SUITABLE TESTING PROGPAM, MEASURES WERE NOT ESTABLISHED TO VERIFY THE SUITABILITY OF APPLICATION OF MATERI-ALS, PARTS, EQUIPMENT. AND INSTALLATION PROCESSES FOR REPLACE-MENT OF SAFETY-RELATED VALVE OPERATORS WITH NONSAFETY-RELATED VALVE OPERATORS. WAT3 I 93-035 02 VIO 4/1 ETS-0 03/04/94 C 03/15/94 07/10/95 4250 ERF 95-005 TITLE: INADEQUATE CORRECTIVE ACTIONS FOR VALVE LEAKAGE PROC NUMBER: 71707 COMMENTS: CONTRARY TO CRITERION XVI 0F t.PPENDIX B TO 10 CFR 50 AND LICENSEE'S APPROVED QUALITY ' SSURANCE PROGR AM DESCRIPTION, REV 5 WHICH REQUIRE THAT MEASURES BE ESTABLISHED TO ASSURE THAT CONDI. i TIONS ADVERSE TO QUALITY ARE PROMPTLY IDENTIFIED AND CORRECTED, CORRECTIVE ACTIONS FOR SEAT LCAKAGE HAD NOT YET BEEN IMPLEMENTED . ALSO CORRECTIVE ACTIONS WERE INADEQUATE TO PREVENT THE FAIL-URE OF THE MAIN STEAM DRIP POT MOTOR-OPERATED DRAIN VALVE TO CLOSE DURING PERFORMANCE OF SURVEILLANCE PROCEDURE BECAUSE OF INTERFERENCE BETWEEN THE VALVE ACTUATOR DECLUTCH LEVER AND AN ADJACENT SUPPORT. j WAT3 I 94-003 01 VIO 4/1 MS 05/04/94 C 05/26/94 10/23/95 AS30 KDW 95-019 l TITLE: UNQUAL RECEIPT INSPECTOR /QA FAIL TO REVIEW CHANGES PRCC NUMBER: 60705 COMMENTS: CONTRARY TO TS 8.8.1 REQUIRING WRITTEN PROCEDURES BE ESTAB-LISHED, IMPLEMENTED, AND MAINTAINED COVERING REFUELING OPERA-TIONS, A LICENSEE INSPECTOR WHO HAD NOT RECEIVED REQUIRED RE&P TRAINING, WAS NOT CERTIFIED, AND WHO HAD NOT BEEN PLACED ON THE FUEL RECEIPT INSPECTION SCHEDULE, PERFORMED INSPECTIONS: LICENSEE ASSURANCE OF FUEL RECEIPT INSPECTOR TRAINING AND CERTI-FICATION PRIOR TO THE ASSIGNMENT AND SCHEDULING OF A LICENSEE INSPECTOR TO PERFORM INSPECTIONS WAS NOT OBTAINED: PROCEDURE UNT-007-006 WAS INADEQUATE TO PRECLUDE THE INTRODUCTION OF FOREIGN MATERIAL INTO THE SPENT FUEL POOL AREA. WAT3 I 94-003 02 VIO 4/1 MS 05/04/94 0 05/26/94 4630 TITtE: FAILURE TO CONTROL APPROVED DESIGN BASIS PROC NUMBER: 60705 i l C0hMENTS: CONTRARY TO CRITERION 10 0F APPENDIZ A TO 10 CFR PART 50, REACTOR DESIGN. REQUIRING THAT THE REACTOR CORE SHALL BE DE-SIGNED WITH APPROPRIATE MARGIN TO ASSURE THAT SPECIFIED ACCEPT-l ABLE FUEL DESIGN LIMITS ARE NOT EXCEEDED DURING ANY CONDITION OF l NORMAL OPERATION, INCLUDING THE EFFECTS OF ANTICIPATED OPERATION

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER REPORT BY SITE ffy(:,10:19: 4 SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS

....-----------------------.---...------.-------------.-..........---------------------------------------------~~' ----

AL OCCURRENCES, THE MEASURES ESTABLISLED FOR ASSURING THE DESIGN BASIS WERE INADEQUATE, IN THE NRC-APPROVED BURNUP FOR THE SPECI-FIED ACCEPTABLE FUEL DESIGN LIMITS WAS EXCEEDED IN BOTH CYCLES 4 AND 5 REACTOR CORE DESIGNS AS WELL AS IN THEIR OPERATIONAL CYCLES. WAT3 I 94-003 03 VIO 4/1 MS 05/04/94 C 05/26/94 10/23/95 4630 KDW 95-019 TITLE: UNAUTHORIZED MOVEMENT OF SPENT FUEL PROC NUMSER: 92701 COMMENTS: CONTRARY TO CRITERION V, APPENDIX B, 10 CFR 50 REQUIRING IN PART THAT ACTIVITIES AFFECTING QUALITY SHALL BE PRESCRIBED BY DOCUMENTED INSTRUCTIONS, PROCEDURES. OR DRAWINGS APPROPRIATE TO THE CIRCUMSTANCES AND SHALL BE ACCOMPLISHED IN ACCORDANCE WITH THESE INSTRUCTIONS, PROCEDURES, OR DRAWINGS. CONTROLS OVER THE SPENT FUEL HANDLING MACHINE ACTIVITIES WERE NOT PRESCRIBED BY DOCUMENTED INSTRUCTIONS OR PROCEDURES. WAT3 I 94-003 05 NCV MS 05/04/94 C 05/26/94 05/04/94 4630 94-003 TITLE: INCORRECT PLACEMENT OF FUEL ASSEMBLY PROC NUMBER: 60705 WAT3 I 94-003 06 NCV MS 05/04/94 C 05/26/34 05/04/94 4630 94-003 TITLE: FAIL TO NOTIFY SHIFT SUPV 0F REFUELING DISCREPANCY PROC NUMBER: 60705 WAT3 I 94 005 01 VIO 4/1 ETS-0 04/12/94 C 04/19/94 12/30/94 4250 TIP 94-021 TITLE: TEMPORARY SHIELDING CONSTRUCTION PROC NUMBER: 71707 COMMENTS: CONTRARY TO CRITERION V 0F APPENDIX B TO 10 CFR PART 50 WHICH REQUIRES THAT ACTIVITIES AFFECTING QUALITY BE PRESCRIBED BY DOC-UMENTED INSTRUCTIONS OR PROCEDURES OF A TYPE APPROPRIATE TO THE CIRCUMSTANCES AND THAT THE INSTRUCTIONS OR' PROCEDURES INCLUDE APPROPRIATE QUANTITATIVE LR QUALITATIVE ACCEPTANCE CRITERIA FOR DETERMINING THAT IMPORTANT ACTIVITIES HAVE BEEN SATISFACTORILY ACCOMPLISHED, ADMINISTRATIVE PROCEDURE HP-001-114 REV. 4 " INSTALLATION OF TEMPORARY LEAD SHIELDING " WAS NOT APPROPRIATE IN THAT THE PROCEDURE DID NOT INCLUDE ADEQUATE ACCEPTANCE CRI-TERIA. WAT1 I 94-006 01 VIO 4/1 ETS-0 05/06/94 0 05/26/94 4600 TITLE: REVIEW OF TUBE EXAMINATION DATA PROC NUMBER: 73755 COMMENTS: CONTRARY TO LICENSEE CONTRACTS W-1033-0002 AND W=1003-0006 THAT REQUIRE SUPPLIER TO MAINTAIN AND COMPLY WITH A QUALITY ASSURANCE PROGRAM THAT COMPLIES WITH APPENDIX B TO 10 CFR 50 WHICH STATES, IN PART, " ACTIVITIES AFFECTING QUALITY SHALL BE PRESCRIBED BY DOCUMENTED INSTRUCTION

S. PROCEDURE

S. OR DRAWINGS, OF A TYPE AP-

1 ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER REPORT BY SITE 10:19:44 [fy[;: SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABER EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS ......-..........--....-----....... --.......................................--..--..--.......----------------------~~-------~~~- PROPRIATE TO THE CIRCUMSTANCES AND SHALL BE ACCOMPLISHED IN AC-CORDANCE WITH THESE INSTRUCTIONS, PROCEDURES, OR DRAWINGS": ROBOTIC FIXTURES USED DURING RF06 IN 1994 WERE NOT PRESCRIJED BY DOCUMENTED INSTRUCTIONS, PROCEDURES, OR DRAWINGS; POSITIVE VISUAL TUDE IDENTIFICATION WAS NOT CONSISTENTLY PERFORMED DURING RF05 IN 1992. WAT3 I 94-007 02 VIO 4/1 MS 04/26/94 0 05/05/94 4610 TITLE: FAILURE TO PROVIDE ADEQUATE PROCEDURE PROC NUMBER: 82700 COMMENTS: CONTRARY TO TS 6.8.1.A WHICH REQUIRES THAT MAINTENANCE THAT CAN AFFECT THE PERFORMANCE OF SAFETY-RELATED EQUIPMENT SHOULD BE PER FORMED IN ACCORDANCE WITH WRITTEN PROCEDURES APPROPRIATE TO THE i CIRCUMSTANCES, MECHANICAL MAINTENANCE PROCEDURE MM-003-041. "FIV E YEAR EMERGENCY DIESEL GENERATOR INSPECTION," DID NOT PROVIDE INSTRUCTIONS TO CLEAN AND LUBRICATE THE FUEL INJECTOR PUMP MOUNT ING FASTENERS. WAT3 I 94-008 01 VIO 4/4 OPS 06/03/94 C 06/21/94 12/30/94 4250 TIP 94-021 TITLE: FAILURE TO FOLLOW RWP REQUIREMENTS PROC NUMBER: 71707 COMMENTS: CONTRARY TO HP-001-110, REV 13 " RADIATION WORK PERMITS,' WHICH STATES. IN PART. THAT INDIVIDUALS WORKING UNDER A RWP ARE RE-SPONSIBLE FOR REVIEWING. OBSERVING AND ABIDING BY THE RWP AND THE RADIOLOGICAL SIGNS POSTED WITHIN THE RADI0 LOGICALLY CONTROL-LED AREA, AN OPERATOR WAS INSIDE A POSTED CONTAMINATED AREA WITH OUT A FULL SET OF PROTECTIVE CLOTHING AS REQUIRED BY THE RWP_ WAT3 I 94-009 01 NCV SEC 04/29/94 C 06/28/94 04/29/94 4300 TKD 94-009 TITLE: SEARCHES OF MATERIALS ENTERING PA BY VEHICLE PROC NUMBER: 81700 WAT3 I 94-011 01 NCV OPS 07/05/94 C 07/14/94 07/05/94 4250 ERF 94-011 TITLE: FAILURE TO ADEQUATELY REVIEW TS REQUIREMENTS PROC NUMBER: 92901 WAT3 I 94-013 02 VIO 94-105 3/1 ETS-0 06/30/94 C 07/05/94 07/10/95 4250 ERF 95-005 TITLE: ALLOWED OUTAGE TIME FOR SBVS & CVAS EXCEEDED PROC NUMBER: 92700 COMMENTS: CONTRARY TO TS 3.6.6.1 AND TS 3.7.7 THE ALLOWED OUTAGE TIME OF 7 DAYS FOR SBVS AND CVAS WAS EXCEEDED. SBVS TRAIN A AND B WERE INOPERABLE SINCE THE DC WAS INSTALLED ON 1/28/93. CVAS TRAINS A AND B WERE INOPERABLE SINCE THE DC WAS INSTALLED ON 3/26/93 AND 4/13/94, RESPECTIVELY. NOV AND PROPOSED IMPOSITION OF CIVIL PENALTY - (01013) WAT3 I 94-013 03 VIO 94-105 3/1 ETS-0 06/30/94 C 07/05/94 07/10/95 4250 ERF 95-005 TITLE: FUEL MOVED WITH FHBVS INOPERABLE PROC NUMBER: 92700 ..---,-----______--._-----,--__-z.-..-- . - - ~ - - - -.

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DjhEg / 9jj / E. GREHER REPORT BY SITE PAGij 8 SITE: WAT WATERFORD UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ ORG NO EMP INSPECTION REPORTS .... -.....--.-----.---.-------....---.........--.---......--..-....----..---...../ACT* COMMENTS: CONTRARY TO TS 3.9.12 REQUIREMENTS, FUEL WAS MOVED IN THE SPENT FUEL POOL DURING REFUELING OUTAGE 6 WITH FHBVS INOPERABLE, NOV AND PROPOSED IMPOSITION OF CIVIL PENALTY (01023] WAT3 I 94-013 06 VIO 94-105 3/1 ETS-0 06/30/94 C 07/05/94 07/10/95 4250 ERF 95-005 TITLE: FAILURE TO REVIEW DESIGN CHANGES / FAIL TO TEST PROC NUMBER: 92700 COMMENTS: CONTRARY TU 10 CFR PART 50, APPENDIX B. CRITERION III WHICH RE-QUIRES THAT DESIGN BASIS FOR SYSTEMS ARE CORRECTLY TRANSLATED INTO SPECIFICATIONS, DRAWINGS, AND INSTRUCTIONS AND THAT DESIGN CONTROL MEASURES BE ADEQUATE TO ASSURE PROPER SYSTEM OPERATION, THERE WAS INADEQUATE REVIEW OF THE DESIGN MODIFICATION THAT RE-PLACED THE TEMPERATURE CONTROLLER, INADEQUATE POSTMAINTENANCE TESTING OF THE NEW TEMPERATURE CONTROLLER, AND FAILURE TO PER-FORM AN ADEQUATE SURVEILLANCE TEST TO VERIFY THAT THE VENTILA-TION SYSTEMS WOULD REMAIN OPERABLE FOLLOWING A LOOP. NOV AND PROPOSED IMPOSITION OF CIVIL PENALTY - (01033] NAT3 I 94-015 01 VIO 4/1 OPS 08/05/94 C 09/06/94 02/16/95 4250 ERF 94-022 TITLE: INADEQ CONFIGURATION DOCUMENTS /POSSITVE REACTIVITY ADDI PROC NUMBER: 71707 COMMENTS: CONTRARY TO SITE DIRECTIVE W4.201, SECTION 3.4, " CONFIGURATION MANAGEMENT," WHICH REQUIRES, IN PART. THAT PLANT CONFIGURATION DOCUMENTS SPECIFYING OPERATIONS, MAINTENANCE. TESTING, INSTALLA-TION, PROCUREMENT AND TRAINING REQUIREMENTS ARE UPDATED AND MAIN TAINED CONSISTENT WITH THE PLANT DESIGN, 1] THE FLOW DIAGRAM FOR THE CHEMICAL AND VOLUME CONTROL SYSTEM DID NOT SHOW ALL LETDOWN RADIATION MONITOR PURGE CONNECTIONS, AND 2) THE COMPONENT C00LIN G WATER SYSTEM FLOW DIAGRAM DID NOT SHOW ALL THE VALVES IN THE SYSTEM. %AT3 I 94-024 01 ' VIO 4/1 OPS 09/30/94 C 10/27/94 04/13/95 4250 ERF 95-003 94-019 TITLE: RCS DILUTION DUE TO INATTENTION TO DETAIL PROC NUMBER: 92901 ' COMMENTS: CONTRARY TS 6.8.1.A AND REG GUIDE 1.33. ITEM 3.N. THAT REQUIRE IN PART. THAT THE LICENSEE ESTABLISH PROCEDURES FOR OPERATION OF THE CHEMICAL AND VOLUME CONTROL SYSTEM (INCLUDING THE LETDOWN / PURIFICATION SYSTEM), FOLLOWING THE ESTABLISHMENT OF PRIMARY MAKEUP WATER FLOW FOR A BLENDED MAKEUP TO THE VOLUME CONTROL TAN K, A LICENSED REACTOR OPERATOR FAILED TO START THE DESIRED BORIC ACID PUMP AND ESTABLISH BORIC ACID FLOW. i; ~ WAT3 I 94-024 02 VIO 4/1 OPS 09/30/94 C 10/27/94 04/13/95 4250 ERF 95-003 TITLE: FAIL TO NOTIFY CONTROL ROOM SUPERVISOR /TS 6.8.1.A PROC NUMBER: 92901 COMMENTS: CONTRARY TO TS 6.8.1.A AND REG GUIDE 1.33, REV 2 ITEM 1.B.

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 pfMfl10:19;4 E. GREHER REPORT BY SITE SITE: WAT WATERFORD LNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSE00T CLSOUT CLSOUT UPDATING ._______......._______..__._..._____-NBR SUPLMNT AREA EVENT DT DATE PR '.*ACT* ORG NO EMP INSPECTION REPORTS EA/ NBR NOV-ID TYPE EA ABBR WHICH REQUIRE, IN PART, THE LICENSEE TO SPECIFY THE AUTHORITIES AND RESPONSIBILITIES FOR SAFE OPERATIFN AND SHUTDOWN OF THE FACILITY, 11 A NUCLEAR PLANT OPERATOR AliED TO INFORM THE CONTROL ROOM SUPERVISOR OF A POSITIVE REACTIVITY ADDITION AND THE SUBSEQUENT ADDITION OF 150 GALLONS OF BORIC ACID THAT CAUSED THE 1EACTOR COOLANT SYSTEM COLD LEG TEMPERATURE TO DROP; AND 2) THE GN-DUTY CONTROL ROOM SUPERVISOR FAILED TO STOP A RINSE OF ION CXCHANGER C WHEN ENCOUNTERING PRCBLEMS WITH BORIC ACID MAKEUP FLOW AND MAINTAINING VOLUME CONTROL TANK LEVEL WITH THE CHEMICAL AND VOLUME CONTROL SYSTEM. WAT3 I 94-024 03 VIO 4/1 OPS 09/30/94 C 10/27/94 07/10/95 4250 ERF 95-005 TITLE: INADEQUATE POST-MAINTENANCE TEST PROC NUMBER: 92901 COMMENTS: CONTRARY TO TS 6.8.1.A AND REG GUIDE 1.33, REV 2 ITEM 9.A. WHICH REQUIRE, IN PART, THAT MAINTENANCE TAHT AFFECTS THE PER-FORMANCE OF SAFETY-RELATED EQUIPMENT SHOULD BE PROPERLY PRE-PLANNED AND PERFORMED IN ACCORDANCE WITH WRITTEN PROCEDURES. DOCUMENTED INSTRUCTIONS, OR DRAWINGS APPROPRIATE TO THE CIRCUM-STANCES. THE INSPECTORS DETERMINED THAT PLANNING PERSONNEL FAILED TO PROPERLY PRE-PLAN A POST-MAINTENANCE TEST BECAUSE THE PERSONNEL FAILED TO IDENTIFY THE SPECIFIC STEPS NEEDED TO ASSURE THAT THE MAINTENANCE CORRECTED THE ORIGINAL CONDITION. N'3T E : DEFINITION FOR CHARACTER PRECEEDING REPORT NO: I = INSPECTION REPORT NUMBER E = EA NUMBER (ENFORCEMENT / NOV ITEM) IFS NUMBER, NUMBER USED TO IDENTIFY NON-INSPECTION ITEMS N = T;3TAL OPEN ITEMS==============>> S

  • IF ITEM IS OPEN, PROJECTED CLOSEOUT DATE IS REPORTED T3TAL OPEN REPORT SEQUENCES====>>

S IF ITEM IS CLOSED, ACTUAL CLOSEOUT DATE IS REPORTED

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP $YSTEM DATE: 10/31/96 E. GREHER BANNER PAGE TIME: 10:30:00 REPORT BY SITE PAGE: I REGION: O SITES: DOCKETS' EA-CASE: ABBR NAME NUMBER NAME NUMBERS RBS RIVER BEND STATION ALL ORGANIZATION-EMPLOYEES: CODE NAME ID NAME ~' ~~~~ kLL Eh LL EMPLOYEES ** REPORT ON: ALL FROM DATE: 01/01/1993 TO DATE: 09/30/1994 INSPR-NO: ALL ITEM TYPE: DEV, NCV, VIO CAUSE CD: A SEVERITY CD: A STATUS: ALL FUNCTIONAL AREA: ALL REACTOR TYPE: POWER ENFORCEMENT IND: ALL COMMENT TEXT IS REQUESTED k .~. n

+.- i .I 4 ITEM DETAIL REPORTS ' IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 a 'E. GREHER. REPORT BY SITE 10:30:0 pfy(! SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY' SALP REPORT / STS -CREATE -CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP. INSPECTION REPORTS ....--.....--. -------.---..----.---------................----............----------......------------------~~---- -------~~~-~~- L QBS1 I 92-034 Ol' VIO 4/1 01/08/93 C ' 0?/20/93 a9/27/93 4204 WKS 93-023 TITLE: . FAILURE TO MEET A LIMITING CONDITION FOR OPERATION PROL NUMBER: 92702 COMMENTS: CONTRARY TO TECHNICAL SPECIFICATION 3.0,4 AND TECHNICAL SPECIFIC i ATION 3.7.3, ON NOVEMBER 25, 1992. THE LICENSEE ENTERED A SPECIF L IED CONDITION WHEN THE LIMITING CONDITIONS FOR OPERATION WERE NO T MET, IN THAT REACTOR PRESSURE WAS INCREASED TO GREATER THAN 15 0 PSI WITH THE REACTOR CORE ISOLATION COOLING SYSTEM INOPERABLE. I L QBS1 I 92-034 02 VIO 4/1 '01/08/93 C- 01/20/93 09/27/93 4204 WKS 93-023 j TITLE: SAILURE TO PERFORM ACTION STATEMENT REQUIREMENTS PROC NUMBER: 92702 e COMMENTS: CONTRARY TOTECHNICAL SPECIFICATION 3.3.1 TABLE 3.3.1-1 AND TECH NICAL SPECIFICATION 3.3.7.6, ON DECEMBER 6, 1992, THE REACTOR OP ERATOR FAILED Tn LOCK THE REACTOR MODE SWITCH IN THE SHUTDOWN PO 1 SITION AFTER ENTERING INTO OPERATIONAL CONDITION 3. WITH ALL CHA NNELS OF THE INTERMEDIATE RANGE AND SOURCE RANGE MONITORS INOPER } ABLE. F RBS1 I 92-034 03 VIO 4/1 01/08/93 C 01/20/93 09/27/93 4204 WKS 93-023 TITLE: FAILURE TO IDENTIFY A CONDITION ADVERSE TO QUALITY PROC NUMBER: 92702 QBS1 I 92-035 01 VID 4/3 SEC 03/05/93 C 03/23/93 11/09/93 4204 WKS 93-026 TITLE: FAILURE TO COMPLY WITH PROCEDURE TPP-7-018 ' PROC NUMBER:'92702 6 COMMENTS: CONTRARY TO RBS PHYSICAL SECURITY PLAN, CHAPTER 3. SECTION 3.4, ON JANUARY 24 1992, UNESCORTED ACCESS WAS NOT IMMEDIATELY SUSPENDED WHEN AN INDIVIDUAL'S GENERAL EMPLOYEE TRAINING EXPIRED AND THE INDIVIDUAL UNSUCCESSFULLY ATTEMPTED REQUALIFICATION. [ 1 SUBSEQUENTLY. THE INDIVIDUAL INAPPROPRIATELY GAINED ACCESS TO t THE PROTECTED AREA ON DECEMBER 4, 16, AND 17,'1992. ALSO. ON DECEMBER 3, 7, 10, 17, AND 21, 1992, ANOTHER INDIVIDUAL WHOSE GENERAL EMPLOYEE TRAINING HAD EXPIRED ON NOVEMBER 30, 1992, INAPPROPRIATELY GAINED ACCESS TO THE PROTECTED AREA. RBS1 I 92-035 03 NCV 03/05/93 C 05/21/93 03/05/93 4204 92-035 TITLE: FAILURE TO POST NOV PER 10CFR19.11 PROC NUMBER: RBS1 I 93-002 02 VIO 4/3 02/26/93 C 03/09/93 11/22/94 4640 TKD 94-023 i TITLE: FAILURE TO FOLLOW DRILL PROCEDURE PROC NUMBER: [ COMMENTS: CONTRARY TO SECURITY PROCEDURE PSP-4-5-1 ON JULY 27, 1992, LICEN SEE PERSONNEL FAILED TO NOTIFY THE APPROPRIATE PERSONNEL THAT A DRILL WAS BEING CONDUCTED. FURTHER, DURING TEST DRILLS, LICENSE E PERSONNEL FAILED TO ADEQUATELY SEARCH A PACKAGE THAT PENETRATE r L i f -s t I i i i p' i h l

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 pfM[j10:30:0 E. GREHER REPORT BY SITE 3 SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS D THE PROTECTED AREA. RBS1 I 93-002 03 VIO 4/3 02,26/93 C 03/09/93 02/04/94 4304 ADE 94-005 TITLE: INADEQUATE PROTECTION OF SAFEGUARDS INFORMATION PROC NUMBER: COMMENTS: CONTRARY TO 10 CFR 73.21 ON JANUARY 2, 1992, THE LICENSEE INTROD UCED A SAFEGUARDS INFORMATION DEOCUMENT INTO THE WORK REQUEST SY STEM WITHOUT MARKING OR PROTECTING IT AS SAFEGUARDS INFORMATION. FURTHER ON APRIL 16, 1992, A COPY OF THE PHYSICAL SECURITY PLA N WAS LEFT UNATTENDED ON A DESK OUTSIDE THE PROTECTED AREA FOR A BOUT 5 MINUTES. RBS1 I 93-002 04 VIO 4/3 02/26/93 C 06/03/93 02/04/94 4304 ADE 94-005 TITLE: PHYSICAL SECURITY PLAN CHANGE SUBMISSIONS PROC NUMBER; QBS1 I 93-002 05 NCV 02/26/93 C 06/03/93 05/17/93 4304 93-002 TITLE: PHYSICAL SECURITY PLAN CHANGE SUBMISSIONS PROC NUMBER: RBS1 I 93-004 06 NCV 05/11/93 C 06/03/93 05/11/93 4611 MUR 93-004 TITLE: FAILURE TO PROPERLY EVALUATE TEST DATA PROC NUMBER: RBS1 I 93-005 01 VIO 4/1 04/30/93 C 06/03/93 08/08/94 4240 WKS 94-015 TITLE: FAILURE TO CONDUCT ADEQUATE RETEST PROC NUMBER. RBS1 I 93-005 02 VIO 4/1 04/30/93 C 06/03/93 08/08/94 4240 WKS 94-015 TITLE: SURVEILLANCE PROCEDURE TECHNICALLY INADEQUATE PROC NUMBER: RBS1 I 93-005 04 NCV 04/30/93 C 06/03/93 04/30/93 4204 WKS 93-005 TITLE: FAILURE TO PROVIDE ADEQUATE PROCEDURES PROC NUMBER: 93702 RBS1 I 93-005 05 NCV 04/30/93 C 06/03/93 04/30/93 4204 WKS 93-005 TITLE: FAILURE TO MEET REPORTING REQUIREMENTS PROC NUMBER. 93702 RBS1 I 93-008 01 VIO 4/3 SEC 04/02/93 C 06/04/93 02/04/94 4304 ADE 94-005 TITLE: FAILURE TO MAINTAIN KEYCARD ACCOUNTABILITY PROC NUMBER: COMMENTS: CONTRARY TO THE PHYSICAL SECURITY PLAN, KEYCARDS WERE DISPLAYED AS BEING IN THE PROTECTED AREA WHEN THE BADGES WERE IN THE SECUR ITY BADGE RACKS. KEYCARD INVENTORY DID NOT IDENTIFY THE DISCREP ANCY IN THE KEYCARD ACCOUNTABILITY PROGRAM. RBS1 I 93-008 02 VIO 4/3 SEC 04/02/93 C 06/04/93 11/22/94 4640 TKD 94-023 l TITLE. FAIL TO MAINTAIN UNINTERRUPTIBLE POWER TO SECURITY SYST PROC NUMBER: COMMENTS: CONTRARY TO THE PHYSICAL SECURITY PLAN. THE UNINTERRUPTIBLE POWE 3 i m

5 ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 pfM((10: 30:0 E. GREHER REPORT BY SITE SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP RElaRT / STS CREATE CLOSE00T CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS R SYSTEM WAS IN MANUAL BYPASS. THEREBY ELIMINATING UNINTERRUPTI BLE POWER FOR THE SYSTEM. RBS1 I 93-008 04 NCV SEC 04/02/93 C 06/04/93 04/02/93 4304 ADE 93-008 TITLE: ISSUING WRONG BADGE PROC NUMBER: RBS1 I 93-008 05 NCV SEC 04/02/93 C 06/04/93 04/02/93 4304 ADE 93-008 TITLE: ACCESS AUTHORIZATION PROGRAMS PROC NUMBER: RBS1 I 93-010 03 NCV OPS 06/22/93 C 08/05/93 06/22/93 4204 WKS 93-010 TITLE: SCRAMMING THE WRONG CONTROL ROD PROC NUMBER: RBS1 I 93-012 01 VIO 4/4 RADCON 04/30/93 C 06/04/93 03/29/95 4640 JLN 95-009 TITLE: I%ILURE TO DESIGNATE QUALIFIED RAD PROGRAM DIRECTOR PROC NUMBER: COMMENTS: CONTRARY TO TS REQUIREMENTS FOR THE DIRECTOR-RAD PROGRAMS, THE N EW DIRECTOR DID NOT MEET OR EXCEED THE QUALIFICATIONS OF REG GUI DE 1.8 SEPTEMBER 1975. RBS1 I 93-012 02 VIO 4/4 RADCON 04/30/93 C 06/04/93 07/29/93 4304 93-012 TITLE: VIOLATION WITHORAWN PROC NUMBER: 83750 COMMENTS: CONTRARY TO REQUIREMENTS IN TS 6.8.1 A. LICENSEE DID NOT POST A HIGH RADIATION AREA SUCH THAT THE AREA WAS COMPLETELY ENCLOSED B Y A PHYSICAL BARRIER. RBS1 I 93-012 03 VIO 4/4 RADCON 04/30/93 C 06/04/93 03/29/95 4640 JLN 95-009 TITLE. INADEQUATE LABELING OF RADI0 ACTIVE MATERIALS PROC NUMBER: COMMENTS: CGNTRARY TO 10 CFR 20.203(F) REQUIREMENTS, INSPECTORS FOUND TWO BAGS CONTAINING RADI0 ACTIVE MATERIAL THAT HAD NOT BEEN LABELED. RBS1 I 93-012 04 NCV 04/30/93 C 06/04/93 04/30/93 4304 AIG 93-012 TITLE: FAILURE TO PERFORM PERSONAL CONTAMINATION MONITORING PROC NUMBER. RBS1 I 93-014 01 VIO 4/3 SEC 05/17/93 C 06/04/93 11/22/94 4640 TKD 94-023 [ TITLE: IMPROPER DISCHARGE OF FIREARM PROC NUMBER: RBS1 I 93-017 01 VIO 4/1 ETS-0 07/23/93 C 08/31/93 06/28/94 4240 94-013 TITLE: T.S. 6.9.3.2 VOILATION ON CORE CALCULATIONS PROC NUMBER: 37001 COMMENTS: CONTRARY TO T.S. 6.9.3.1&2. THE MINIMUM CRITICAL PWR. RATIO VALUE OF 1.18 DOCUMENTED IN THE CORE OPERT. LIMITS RPT. FOR RELOAD 4, CYCLE 5, DATED 8/28/1992, WAS DETERMINED USING ANALYTICAL METHODS OTHER THAN THOSE DOCUMENTED IN THE LATEST VER. NEDE-24011-P-A AS REVIEWED & APPROVED BY NRC. i l e - nw,

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER REPORT BY SITE p[y(j10:30:00 SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS .................. - -......... - - -.. - -......................................................................... - -. - - - - - ~ ~ ~ ~ - - - - - - - RBS1 I 93-018 01 VIO 93-167 3/1 MS 06/29/93 C 09/02/93 09/13/94 4610 MUR 94-016 TITLE: MSIV B STUCK OPEN - INOPERABLE PROC NUMBER: 93702 COMMENTS: CONTRARY TO T.S. 6.8.1/A.P. ADM-0015/STP-051-0201, ON 2-27-1993 & 4-1-1993 ADM-0015 WAS NOT PROPERLY IMPLEMENTED DURING PERFORMANCE STP-051-0201. SPECIFICALLY, THE SHIFT SUPERVISOR AND CONTROL OPERATING FOREMAN SIGNED THE PROCEDURE AS COMPLETE. WHEN THE ACCEPTANCE CRITERIA STEP 7.4.5 HAD NOT BEEN MET FOR MSIV 1821*A0VF0228. CONTRARY TO T.S. 3.4.7, 2-27 THRU 4-18-1993. WITH THE PLANT IN OPERATIONAL COND. 1.2. & 3 MAIN STEAM LINE ISOLATION VALVE IB21*A0VF0228 NOT OPERABLE (VALVE WOULD NOT CLOSE) & ACTIONS DESCRIBED T.S. 3.4.7 NOT TAKEN. RBS1 I 93-018 02 VIO 93-167 4/1 MS 06/29/93 C 09/02/93 09/13/94 4610 MUR 94-016 TITLE: MSIV B STUCK OPEN - POOR MAINTENANCE PROC NUMBER: 93702 COMMENTS: CONTRARY TO TS 6.8.1/RG 1.33/ CMP-9141, ON 4-23-1993, MAINTENANCE ON SAFETY-RELATED MSIV 1821*A0VF0228 WAS NOT PERFORMED IN ACCORDANCE WITH WRITTEN PROCED. AND DOCUMENTED INSTRUCTIONS APPROPRIATE TO THE CIRCUMSTANCES. CMP-9141 USED FOR DISASSEMBLY WITH THE VALVE IN OPEN POSITION. SUCH THAT SEVERAL ACTIONS TAKEN BY PLANT MECH. DURING DISASSEMBLY WERE NOT PROVIDED FOR/ CONTRARY TO RE

Q. PROCEDURE

ON 5-11-1993 DURING REASSEMBLY OF SAFETY-RELAT. MSIV 1821*A0VF022A. MAINT. NOT PERFORM. ACCCRD. W/MWO R159695 STEP 59, 11" STROKE LENGTH NOT ENSURED, NOR REQ. VALVE ADJ. PERFORMED PER STEPS 43-48 0F APPLICABLE MANUAL. RBS1 I 93-020 01 VIO 4/1 OPS 08/17/93 C 08/31/93 09/16/94 4250 WKS 94-018 TITLE: DIVISION I/II EMERG. CORE COOLING SYS. DECLARED INOPER. PROC NUMBER: 71707 COMMENTS: 93022ARY TO T.S. 3.0:3/3.5.1, ON 6/30/1993 4:13 AM, WHILE THE PLANT WAS IN OPERTIONAL COND. 1, RHR PUMP A WAS DECLARED INOPERABLE WHILE HIGH PRES. CORE SPRAY WAS INOPERABLE. THIS. REMAINED IN EFFECT 'TIL 5:56 AM. WHEN RHR PUMP A RETURNED TO OPERABLE STATUS. NO ACTION TAKEN TO ENTER / COMPLY W/T.S. 3.0.3 DURING THAT PERIOD. [ RBS1 I 93-020 02 VIO 4/1 MS 08/17/93 C 08/31/93 09/16/94 4250 WKS 94-018 TITLE: LACK OF INDEPENDENT VERIF. OF VALVE SWITCHES PROC NUMBER: 61726 COMMENTS: CONTRARY TO S.T.P. STP-503-5403, REV. 6A. 12/7/1992, e ~

0 ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE 10/31/96 pfM(._10:30:0 E. GREHER REPORT BY SITE 6 SITE: RBS RIVER BEND STATION UNIT-RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS ..............................................................._...................................-..---------------------~~----- THE INDEPENDENT VERIFICATION THAT THE INOPERATIVE INHIBIT PUSHBUTTON HOLDDOWN TEST FIXTURE WAS REMOVED FROM SOURCE RANGE MONITOR A WAS NOT PROPERLY EXECUTED, THE FIXTURE WAS STILL INSTALLED WHEN EQUIP. DRAWER WAS OPENED ON 4/17/1993. RBS1 I 93-023 01 NCV MS 09/27/93 C 10/07/93 09/27/93 4204 WKS 93-023 TITLE-MISSED SURVEILLANCE - SCHEDULING ERROR PROC NUMBER: 93702 RBS1 I 93-024 01 VIO 4/3 SEC 08/31/93 C 09/07/93 11/22/94 4640 TKD 94-023 TITLE: APPARENT VIOLATION ON EVENT NOTIF TIMELINESS PROC NUMBER: 81700 COMMENTS: SAFEGUARDS INFORMATION RBS1 I 93-024 02 VIO 4/3 SEC 08/31/93 C 09/07/93 02/04/94 4304 ADE 94-005 TITLE: PENETPATION DETECTION RESPONSE PROC NUMBER: 81700 COMMENTS: SAFEGUARDS INFORMATION RBS1 I 93-024 03 VIO 4/3 SEC -08/31/92 C 09/07/93 11/22/94 4640 TKD 94-023 TITLE: FAILURE TO PROTECT SAFEGUARDS INFO. PROC NUMBER:. 81810 COMMENTS: SAFEGUARDS INFORMATION RBS1 I 93-024 06 VIO 93-071 3/3 PLTSUP 08/31/93 C 05/12/94 il/22/94. 4640 TKD 94-023 TITLE: UNATTENDED & NOT LOCKED SAFEGUARDS INFORMATION PPOL NUMBER: 81810 COMMENTS: 01013 - SAFEGUARDS INFORMATION WAS UNATTENDED AND WAS NOT LOCKED IN A SECURITY STORAGE CONTAINER. A SAFE CONTAINING SAFEGUARDS DOCUMENTS WAS FOUND UNLOCKED IN A BUILDING OUTSIDE THE RBS r PROTECTED AREA. ? RBS1 I 93-024 07 VIO 33-071 3/3 PLTSUP 08/31/93 C 05/12/94 11/22/94 4640 TKD 94-023 TITLE: NON-SECURED SAFEGUARDS INFORMATION PROC NUMBER. 81810 COMMENTS: 01023 - SEPT. 25, 1992, FOUR DRAFT SAFEGUARDS INFORMATION DOCUMENTS WERE DISCOVERED IN A STORAGE ROOM OUTSIDE THE PROTECTED AREA AND WERE NOT STORED IN A LOCKED SECURITY STORAGE CONTAINER. THESE DOCUMENTS HAD BEEN UNSECURED FOR APPROX. 7 MONTHS. RBS1 I 93-024 08 VIO 93-071 3/3 PLTSUP OC/31/93 C 05/12/94 11/22/94 4640 TKD 94-023 TITLE: VITAL AREA BARRIER DEGRADED.- THUMBLATCH PROC NUMBER: 81018 COMMENTS: 02013 - DECEMBER 6 - 10, 1991, A PERS0' NEL DOOR TO A VITAL ISLAND WAS DEGRADED BY THE INS ~ALLATION OF A THUMBLATCH THAT PERMITTED INDIVIDUALS TO TRAVERSE FROM A PROTECTED AREA TO A VITAL AREA OF THE PLANT WITHOUT THE USE OF BREACHING TOOLS OR .m = - m y v ,w-

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 pjM((10:30:0 E. GREHER REPORT BY SITE SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ______.__-ID TYPE _____... ____-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS EA/ NBR NOV EA ABBR HIGH EXPLOSIVES-FURTHERMORE, THE LICENSEE DISCOVERED THAT THE VITAL AREA BARRIER WAS DEGRADED ON DECEMBEP 10., 1991 BY INSTALLATION OF THE THUMBLATCH, BUT DID NOT RE ORD THE EVENT IN THE SAFEGUARDS EVENT LOG UNTIL DECEMBER 13, 1991, A PERIOD IN EXCESS OF 24 HOURS. RBS1 I 93-024 09 VIO 93-071 4/3 PLTSUP 08/31/93 C 05/12/94 11/22/94 4640 TKD 94-023 TITLE: INADEQUATELY SECURED MANHOLE COVERS PROC NUMBER: 81018 COMMENTS: 03014 - MARCH 3-10, 1992, THE LICENSEE FAILED TO MAINTAIN POSTED COMPENSATORY MEASURES CONSISTING OF POSTING ADDITIONAL SECURITY PERSONNEL FOR FIVE MANHOLE COVERS WHICH HAD BEEN IDENTIFIED ON MARCH 2, 1992, AS HAVING BEEN INADEQUATELY SECURED. RBS1 I 93-024 10 VIO 93-071 4/3 PLTSUP 08/31/93 C 05/12/94 11/22/94 4640 TKD 94-023 TITLE: NO POSITIVE ACCESS CONTROL OF VITAL ISLAND PORTAL PROC NUMBER: 81018 COMMENTS: 04C.4 - ON DECEMBER 10, 1991 A DOOR TO A VITAL ISLAND WAS FOUND UNLOCKED (A THUMBLATCH HAD BEEN INSTALLED ON THE PROTECTED AREA SIDE OF THE DOOR), AND THE LICENSEE DID NOT POST A NUCLEAR SECURITY OFFICER AT THE VITAL ISLAND PORTAL i i TO PROVIDE POSITIVE ACCESS CONTROL FOR TWO HOURS AFTER i SECURITY MANAGEMENT WAS NOTIFIED OF THIS CONDITION. { RBS1 I 93-024 11 VIO 93-071 4/7 PLTSUP 08/31/93 C 05/12/94 11/22/94 4640 TKD 94-023 TITLE: SAFEGUARDS INFORMATION NOT DESTROYED BY DATE INDICATED PROC NUMBER: 81810 i COMMENTS: 05014 - ON SEPTEMBER 25, 1992 OR SHORTLY THEREAFTER, THE LICENSEE DISCOVERED THAT RECORDS INDICATING THE DESTRUCTION OF CERTAIN DOCUMENTS CONTAINING SAFEGUARDS INFORMATION WERE INACCURATE IN THAT THE DOCUMENTS WERE FOUND ON THAT DATE AND HAD NOT BEEN DESTROYED. THESE RECORDS ARE MATERIAL BFCAUSE THEY RELATE TO THE PROTECTION OF SAFEGUARDS INFORMATION. RBS1 I 93-025 03 VIO 4/1 MAINT 01/07/94 C 05/12/94 01/17/95 4250 TXS 94-017 TITLE: QUALITY ACTIVITIES LACKED INSTR., PROCED., & DRWGS. PROC NUMBER: 93802 COMMENTS: 01044 -A PROCEDURE COULD NOT BE PERFORMED IN ACCORDANCE WITH THIS APPROVED PROCEDURE, WHICH HAD BEEN ISSUED FOR IMPLEMENTATION, BECAUSE THE TEST REQUIRED THE PERFORMANCE OF 14 DIFFERENT OPERATIONS WITHIN 30 SECONDS, WHICH WAS PHYSICALLY IMPOSSIBLE. 01054 - A CHANGE TO THIS PROCEDURE WAS MADE, ON JANUARY 29, 1990 USING A SURVEILLANCE TEST COMMENT CONTKOL FORM, WHICH WAS PROHIBITED BY ANOTHER PROCEDURE. ~n.-

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE 10/31/96 pfM(,10:30:0 E. GREHER REPORT BY SITE g SITE: RBS RIVLR BEND STATION UNIT RPT/ IFS / SEO-NO ITEM REF NBR / SEVERITY SALP RE"7RT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS -........... - - - - - - -. - -........... - -................ -.. - -...... - -.. - - _ _......................... - -.... - - - - - - - - - - - - - - - - - - - ~ ~ - - - RBS1 I 93-025 04 VIO 4/1 MA'NT 01/07/94 C 05/12/94 01/17/95 4250 TXS 94-017 TITLE: NONCGNFORMING CONDITIONS W/0 PROMPT ACTI N PROC NUMBER: 93802 COMMENTS: CONTAINMENT AIRLOCK DOOR SEALS SINCE 1985 AND HAS NOT TAKEN APPROPRIATE CORRECTIVE ACTIONS TO PRECLUDE REPETITION IN THAT THE SEALS HAVE FAILED AN AVERAGE OF FIVE PER YEAR SINCE 1985. 02074 - CONTINUED FAILURE OF THE FLOW SWITCHES IN THE SAMPLE LINES FOR RADIATION MONITORS AND DID NOT TAKE APPROPRIATE CORRECTIVE ACTIONS TO PRECLUDE REPETITION OF THE FLOW SWITCH FAILURES. RBS1 I 93-026 01 VIO 4/1 OPS 11/09/93 C 12/02/93 11/09/94 4250 WKS 94-019 TITLE: FAILURE TO PROVIDE PROCEDURES PROC NUMBER: 93702 COMMENTS. CONTRARY TO TS 6.8.1 THE MAIN CONTROL ROOM RADIATION MONITORING PANEL RM-11 ANNUNCIATOR DID NOT HAVE AN ALARM RESPONSE PROCEDURE FOR LIQUID RADIATION MONITOR RMS-RE108. CONSEQUENTLY, IMMEDIATE AND LONG RANGE OPERATOR ACTIONS WERE NOT ESTABLISHED FOR LIQUID RADIATION MONITOR RMS-RE108 WHEN IT ALARMED ON SEPTEMBER 7, 1993 INDICATING THAT AN UNEXPECTED RADI0 ACTIVE LIQUID DISCHARGE FROM THE MAIN COOLING TOWER WAS OCCURRING. RBS1 I 93-026 02 VIO 4/1 OPS 11/09/93 C 12/02/93 11/09/94 4250 WKS 94-016 TITLE: FAILURE TO INITIATE PROMPT CORRECTIVE ACTIONS PROC NUMBER: 93702 COMMENTS: CONTRARY TO 10 CFR 50, CRIT. XVI. ON SEPTEMBER 7, 1993 THE MAIN CONTROL ROOM OPERATORS FAILED TO PROMPTLY INITIATE MEASURES TO TERMINATE OR ADEQUATELY VERIFY THE VALIDITY OF THE MAIN COOLING TOWER RADIATION MONITOR RMS-R108 WHEN IT ALARMED DURING A LIQUID RADIOACTIVE WASTE DISCHARGE. THIS CONDITION HAD EXISTED FROM APPROXIMATELY 4:08 P.M. (CDT) UNTIL 6:42 P M., WHEN THE DISCHARGE WAS TERMINATED. CONSEQUENTLY, OVER 500,000 GALLONS OF WATER, WITH POTENTIALLY GREATER THAN EXPECTED RADIOACTIVITY, WAS DISCHARGED TO THE MISSISSIPPI RIVER. RBS1 I 93-027 02 VIO 4/1 MS 12/17/93 C 02/17/94 01/26/95 4250 WKS 94-022 TITLE: FAILURE TO CONDUCT POSTMAINTENANCE TESTING PROC NUMBER: 62703 COMMENTS: ON 10/27/93, THE LICENSEE PERFORMED MAINTENANCE ON THE POWER SUPPLY BREAKER FOR RESIDUAL HEAT REMOVAL B SHUTDDWN COOLING SUCTION VALVE 1E12*F006B BY ADJUSTING THE INSTANTANEOUS OVERCURRENT TRIP SETTING UNDER MAINTENANCE WORK ORDER R172573; HOWEVER, NO POSTMAINTENANCE TEST WAS SPECIFIED TO VERIFY AND DOCUMENT THAT THE BREAKER WOULD TRIP WITHIN DESIGN TOLERANCES. RSSI I 93-027 03 VIO 4/1 MS 12/17/93 C 02/17/94 03/10/95 4250 WKS 95-001 TITLE: FAILURE TO FOLLOW PROCED CONTROL SURVEILLANCE ACTIVITI PROC NUMBER: 61726

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM yA[Ej 1/j/6 E. GREHER REPORT BY SITE PAGE 9 SITE: RBS RIVER BEND STATI0H UNIT RPT/IF 2/ SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT %REA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS COMMENTS: THE FOLLOWING ARE TWO EXAMPLES OF WHERE PROCEDURES WERE NOT FOLLOWED IN THE PRESCRIBED SEQUENTIAL ORDER: 1) 10/20/93, DURING SURVEILLANCE TESTING IN ACCORDANCE W/STP-309-0203, THE OPERATOR SKIPPED FROM STEP 7.3.2.13 TO STEP 7.3.7 WITHOUT FIRST COMPLETING STEPS 7.3.2.14 THRU 7.3.6.5.

2) 10/27/93, DURING SURVEILLANCE TESTING OF DIVISION II LOW PRESSURE CORE SPRAY LINE FILL PUMP IN ACCORDANCE WITH STP-204-6302 THE OPERATOR WENT OUT OF SEQUENCE WHILE PLACING TEST GAUGES INTO SERVICE, FAILING TO PROPERLY CHECK AN EQUALIZER VALVE OPEN AND TO PROPERLY ELEVATE THE DIFFERENTIAL PRESSURE GAUGE AS REQUIRED BY SECT. 7.5 0F THE PROCEDURE.

RBS1 I 93-027 04 VIO 4/1 MS 12/17/93 C 02/17/94 01/26/95 4250 WKS 94-022 TITLE: FAILURE TO PROVIDE AN ADEQUATE PROCEDURE PROC NUMBER: 62703 COMMENTS: 10/27/93, STP-204-6302, WAS FOUND TO BE INADEQUATELY MAINTAINED IN THAT STEP 7.5 DID NOT PROVIDE INSTRUCTIONS FOR VENTING OF TEST GAUGES, AND RESTORATION OF INDEPENDENT VERIFICATION STEP 7.5.32 FAILED TO RESTORE VALVES 1RHS*V53 AND *V54 TO THE LOCKED CONDITION. RBS1 I 93-028 02 VIO 4/1 OPS 01/20/94 C 02/17/94 01/26/95 4250 WAS 94-022 TITLE: FAILURE TO IMPLEMNT PROMPT / EFFECTIVE CORRECTIVE ACTION PROC NUMBER: 93702 COMMENTS: THE LICENSEE FAILED TO IMPLEMENT EFFECTIVE MEASURES TO PREVENT RECURRENCE OF THE JUNE 30 EVENT AND ON NOVEMBER 4 WHILE THE PLANT WAS IN OPERATIONAL CONDITION 1, RESIDUAL HEAT REMOVAL PUMP B WAS DECLARED INOPERABLE WHILE HIGH PRESSURE CORE SPRAY WAS INOPERABLE. RBS1 I 93-028 03 VIO 4/1 MS 01/20/94 C 02/17/94 01/26/95 4250 WKS 94-022 TITLE: PROCEDURAL VIOLATION BY FOREMAN TO FOLLOW JOB PLAN PROC NUMBER: 62703 COMMENTS: MAINTENANCE THAT AFFECTED THE PERFORMANCE OF SAFETY-RELATED EQUIPMENT WAS NOT PERFORMED IN ACCORDANCE WITH WRITTEN PROCEDURE IN THAT: 1) 11/22/93, THE INSTRUCTIONS FOR THE WORK PERFORMED IN ACCORDANCE WITH MWO R137896 REQUIRED THAT THE FOREMAN CHECK AND INITIAL EACH INDIVIDUAL *S TRAINING MATRIX. THE INDIVIOUALS TRAINING MATRIX. 21 12/3/93. STEP 7 0F MWO R137897 REQUIRED AN INSPECTION OF THE MOTOR PINION AND KEY OF VALVE E22*MOVF012 FOR PROPER "AS-FOUND" INSTALLATION, USING CMP-1253 AND THE VENDOR TECHNICAL MANUAL WHICH REQUIRED THAT THE KEY BE SECURED IN POSITION BY STAKING THE END OF THE MOTOR SHAFT KEYWAY THE INSPECTION STEP WAS COMPLETED AND SIGNED OFF AS " SATISFACTORY" WHEN IN FACT THE MEY WAS NOT SECURED IN POSITION BY STAKING TIE

k l /j/6 ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DA E. GREHER REPORT BY SITE PAGE: 10 SITE: RBS RIVER BEND STATION 2 UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSE00T CLSOUT CLSOUT. UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS RBS1 I 93-028 04 VIO 4/1 MS 01/20/94 C O//22/94 23/10/95 4250 WKS 95-001 TITLE: INADVERTENT REACTOR WATER CLEANUP SYSTEM ISOLATION PROC NUMBER: 62703 COMMENTS: ON NOVEMBER 17, 1993, WHILE CONDUCTING TROUBLESHOOTING ACTIVITIES ON THE REACTOR CORE ISOLATION COOLING CONTROL CIRCUITS, THE WORK INSTRUCTIONS FAILED TO PROVIDE A STEP THAT WOULD PLACE THE APPROPRIATE SWITCH IN BYPASS TO PREVENT A REACTOR WATER CLEANUP SYSTEM ISOLATION. AS A RESULT, AN INADVERTENT REACTOR WATER CLEANUP SYSTEM ISOLATION OCCURRED. RBS1 I 93-030 02 - VIO 94-010 3/1 PLTSUP 02/01/94 C 02/17/94 01/17/95 4250 TXS 94-017 TITLE: FIRE PROTECTION REQUIREMENTS FAILURE PROC NUMBER: 92702 COMMENTS: DURING THE SAFE SHUTDOWN ANALYSIS THE LICENSEE IDENTIFIED THESE CONCERNS: 1) ASSOCIATED CIRCUITS, COMMON ENCLOSURE, 2) STANDBY SERVICE WATER COOLING TOWER FANS, 3) DIVISION III CONTROL CIRCUITS, 4) SERVICE WATER VALVES, 5) REMOTE SHUTDOWN PANEL, 6) REACTOR HIGH WATER LEVEL TRIP, 7) INSTRUMENT 10BING EVALUATION. THESE CONCERNS ARE CONSIDERED SPECIFIC EXAMPLES OF AN APPARENT VIOLATION INVOLVING A FAILURE TO ESTABLISH FIRE PROTECTION REO. TO PROTECT OR ENABLE OPERTION OF SAFE-SHUTDOWN EQUIPMENT TO SUCH A DEGREE THAT A FIRE IN THE AREA. IN THE ABSENCE OF ADDITIONAL EVALUATION OR MODIFICATION, COULD SO DAftAGE THAT EQUIPMENT THAT SHUTDOWN COULD NOT HAVE BEEN ACHIEVED AND MAINTAINED USING THE EQUIPMENT IDENTIFIED IN THE FIRE HAZARDS ANALYSIS. COMMENTS: 5 DIGIT CODE: 01013 RBS1 1 93-031 03 VIO 4/1 MS 03/30/94 C 05/12/94 03/10/95 4250 WKS 95-001 TITLE: FAILURE TO FOLLOW M&S PROCEDURES PROC NUMBER: 62703 COMMENTS: THREE EXAMPLES WERE IDENTIFIED AFFECTING SAFETY-RELATED MAINTENANCE ACTIVITIES: (1) INNER DOOR OF CONTAINMENT AIRLOCK l WAS NOT LOCKED AS REQUIRED, (2) STEPS IN A SURVEILLANCE TEST WERE PERFORMED OUT OF SEQUENCE, (3) TEST DATA WAS NOT RECORDED AS REQUIRED. RBS1 I 93-031 04 VIO 4/1 MS 03/30/94 C 05/12/94 03/10/95 4250 WKS 95-001 TITLE: INADEQUATE SLC PUMP SURVEILLANCE TESTING PROC NUMBER: 61726 COMMENTS-PR3CEDURE CONTRAST. ONE PROCEDURE REQUIRED THE PUMP TO BE RUN FOR A MINIMUM OF 5 MINUTES BEFORE TAKING DATA, WHILE ANOTHER REQUIRED THE PUMP TO BE RUN FOR 3 MINU.ES MAXIMUM AND TAKE THE DATA DURING THAT TIME. RBS1 I 93-031 05 NCV MS 03/30/94 C 05/12/94 03/30/94 4240 WKS 93-031 TITLE: LPRM BYPASS SWITCH NOT IN OPERATION PROC NUMBER: 92701 i L i .m

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DA(l /jo! E. GREHER REPORT BY SITE PAGE: 11 SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS RBS1 I 94-005 01 VIO 4/3 PLTSUP 02 04/94 0 02/17/94 4640 95-021 TITLE: FAILURE TO MAINTAIN UNINTERRUPTIBLE PWR TO SECU4ITY SYS PROC NUMBER: 81700 COMMENTS: THE INSPECTOR IDENTIFIED ON 01/13/94, THAT THE UNINTERRUPTIBLE POWER SYSTEM DOES NOT MEET THE PHYSICAL SECURITY PLAN REQUIREMENT IN THAT IT CONSISTS OF ONLY ONE DIESEL GENERATOR. RBS1 I 94-006 01 VIO 5/1 MAINT 05/06/94 C 05/12/94 05/03/95 4250 WKS 95-002 TITLE: NON-RCA PRESSURE GAUGE MISUSE: DIGITAL METER CALIBRATIO PROC NUMBER: 71707 COMMENTS: TWO EXAMPLES WERE IDENTIFIED IN WHICH MEASURING AND TEST EQUIP. HAD NOT BEEN HANDLED IN ACCORDANCE WITH THE ESTABLISHED CONTROLS (1) A PRESSURE GAUGE LABELED "NON-RCA" WAS FOUND STAGED FOR USE IN THE FUEL BUILDING WHICH WAS A RADI0 LOGICALLY CONTROLLED AREA (2) A DIGITAL METER WAS FOUND IN THE FUEL BUILDING 8 DAYS AFTER ITS CALIBRATION HAD EXPIRED. RBS1 I 94-006 02 VIO 4/1 ENG 05/06/94 C 05/12/94 01/12/95 4630 LEE 94-024 TITLE: SAFETY-RELATED VALVES AND PUMPS REMOVED W/0 CORR. ACT. PROC NUMBER: 73756 COMMENTS: FROM FEBRUARY 15, 1993 THROUGH JANUARY 23, 1994 THE LICENSEE REMOVED SAFETY-RELATED VALVES AND SAFETY-RELATED PUMPS FROM THE ALERT STATUS WITHOUT FIRST IMPLEMENTING CORRECTIVE ACTIONS OR PERFORMING AN ENGINEERING ANALYSIS TO DOCUMENT THE ACCEPTABILITY OF THE INSERVICE TEST RESULTS. RBS1 I 94-008 01 VIO 4/1 OPS 05/23/94 C 06/02/94 05/23/96 4250 WKS 96-003 TITLE: FAILURE TO PLACE BREAKER IN CLEARANCE SPECIF. POSITION PROC NUMBER: 71707 COMMENTS: ON APRIL 21, 1994, AFTER CLEARANCE RB-94-1573 WAS COMPLETED AND VERIFIED, DIVISION II STATION BATTERY BREAKER ENB* BAT 018 WAS FOUND OPENED BUT NOT RACKED OUT, AS REQUIRED BY THE CLEARANCE. RBS1 I 94-008 02 VIO 4/1 MAINT 05/23/94 C 06/02/94 05/03/95 4250 WKS 95-002 TITLE: FAILURE TO COMPLY WITH STP 257-4502 PROC NUMBER: 61726 COMMENTS: ON APRIL 14, 1994, LICENSEE PERSONNEL COMMENCED WITHOUT ENERGIZING THE CURRENT SOURCE, AS REQUIRED, AND FAILED TO ENERGIZE THE CURRENT SOURCE FOR AT LEAST 1 HOUR PRIOR TO USE AS REQUIRED. RBS1 I 94-008 03 NCV MAINT 05/23/94 C 06/02/94 05/23/94 4240 94-008 TITLE: BREACH OF SECONDARY CONTAINMENT INTEGRITY PROC NUMBER: 93702 QBS1 I 94-009 01 VIO 4/4 PLTSUP 06/17/94 C 06/30/94 03/29/95 46'40 JLN 95-009 TITLE: ACCESSIBLE AREA IN ANNULUS STEAM TUNNEL PROC NUMBER: 83750 m-

IVEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 ffMf{10:30: O E. GREHER REPORT BY SITE SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS --.............-------.---....-...--- ---....---------.-...............--........--... -------- -----..---------~~~---------------- COMMENTS: THE LICENSEE IDENTIFIED AN ACCESSIBLE AREA IN THE ANNULUS STEAM TUNNEL WITH DOSE RATES IN EXCESS OF 10 M'EM/HR WHICH WAS UNPOSTED. RBS1 I 94-009 02 VIO 4/4 PLTSUP 06/17/94 C 06/30/94 03/29/95 4640 JLN 95-009 TITLE: CREWS ENTERED HI RAD. AREA W/0 ALARMING DOSIMETERS PROC NUMBER: 83750 COMMENTS: THE INSPECTORS IDENTIFIED THAT TWO SEPARATE CREWS OF LOCAL LEAK RATE TEST WORKERS ENTERED A HIGH RADIATION AREA ON APRIL 18, 1994, WITHOUT ALARMING DOSIMETERS OR POSITIVE CONTROL BY A QUALIFIED RADIATION PROTECTION TECHNICIAN. RBS1 I 94-009 03 VIO 4/4 PLTSUP 06/17/94 C 06/30/94 03/29/95 4640 JLN 95-009 TITLE: CREW ENTERED RAD. CONTROL AREA UNINFORMED OF CONDITIONS PROC NUMBER: 83750 COMMENTS: ON APRIL 26. 1994 THE INSPECTORS IDENTIFIED THAT A CREW OF LOCAL LEAK RATE TEST WORKERS SELF ACCESSED INTO THE RADIOLOGICAL CONTROL AREA AND BEGAN WORK IN THE ANNULUS STEAM TUNNEL ON APRIL 18, 1994, WITHOUT REVIEWING APPLICABLE SURVEY DATA. OBSERVING LOCAL POSTINGS. OR DIRECTLY COMMUNICATING WITH RADIATION PROTECTION REGARDING THE RADIOLOGICAL CONDITIONS IN THE ANNULUS STEAM TUNNEL. RBS1 I 94-010 01 VIO 4/1 MAINT 05/26/94 C 06/02/94 06/09/95 4630 CKJ 95-018 TITLE: 2ND MPT ON CIRCUMFERENTIAL WELDS NOT DONE PROC NUMBER: 73753 COMMENTS: THE NRC INSPECTOR OBSERVED DURING MAGNETIC PARTICLE EXAMINATIONS ON CIRCUMFERENTIAL WELDS FWOO3 7 SWO32, THAT THE NONDESTRUCTIVE EXAMINATION TECHNICIAN DID NOT PERFORM THE REQUIRED SECOND EXAMINATION ON THE PORTION OF THE WELDS VISIBLE TO THE INSPECTOR RBS1 I 94-010 02 VIO 4/1 PLTSUP 05/26/94 C 06/02/94 06/09/95 4630 CKJ 95-018 TITLE: POOR HOUSEKEEPING IN THE SPENT FUEL POOL AREA PROC NUMBER: 73753 COMMENTS: HOUSEKEEPING PRACTICES, AS IMPLEMENTED BY ADMINISTRATIVE PROCEDURE AND GENERAL MAINTENANCE PROCEDURE DID NOT ASSURE THAT ONLY PROPER MATERIALS AND EQUIPMENT, PROCESSES AND PROCEDURES WERE UTILIZED. FOR EXAMPLE, ON APRIL 26, 1994, THE INSPECTOR FOUND PLASTIC BAGS, AN UNSECURED METAL CHAIR, TRASH, AND OTHER ITEMS IN THE SPENT FUEL POOL AREA. THE MATERIAL FOUND HAD THE POTENTIAL TO CAUSE DETRIMENTAL EFFECTS TO THE REACTOR FUEL IF ALLOWED TO ENTER THE SPENT FUEL POOL. RBS1 I 94-012 01 VIO 4/1 MAINT 07/05/94 C 08/09/94 06/05/95 4250 WKS 95-003 TITLE: 5 EXAMPLES WHERE ADEQUATE PROCEDUES NOT ESTAB./MAINT. PROC NUMBER: 93702 COMMENTS:

1. A PROCEDURE CONTAINED AN AMBIGU0US NOTE. WHICH SHOULD HAVE P

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM yA(l {j{l6 E. GREHER REPORT BY SITE PAGE: 13 SITE: RBS RIVER BEND STATION UNIT RPY/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSE00T CLSOUT CLSOUT UPDATING i ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REP 0 BEEN A PROCEDURE STEP WHICH RESULTED IN AN INADVERTENT ENGINEERED SAFETY FEATURE ACTUATION. 2. A PROCEDURE REQUIRED LIFTING A LEAD FROM A TERMINAL CONTAIN-ING TWO LEADS WITHOUT SPECIFYING WHATE TO DO WITH THE SECOND LEAD. BOTH LEADS WERE LIFTED AND TAPED TOGETHER, RESULTING IN AN UNEXPECTED BUS TRIP AND AUTOMATICE START OF THE DIESEL GENERATOR. 3. A PROCEDURE WAS NOT ESTABLISHED SO A SAFETY-RELATED, AIR-OPERATED VALVE WAS GAGGED SHUT BY APAYING A NITROGEN PRESSURE SOURCE AND NO PROCEDURAL CONTROLS WERE IMPLEMENTED TO PROVIDE OVERPRESSURE PROTECTION FOR THE VALVE. 4. A PROCEDURE DID NOT PROVIDE INSTRUCTIONS FOR PLACING THE STANDBY GAS TREATMENT SYSTEM IN STANDBY AFTER COMPLETION OF THE SURVEILLANCE TEST. 5. A PROCEDURE WAS NOT ACHIEVABLE BECAUSE THE INSTALLED CIRCUIT CONFIGURATION WAS NOT CONSIDERED WHEN INSTRUCTIONS WERE PROVIDED FOR INSULATION RESISTANCE TESTING. RBS1 1 94-012 02 DEV OPS 07/05/94 C 08/09/94 12/09/94 4250 WKS 94-021 TITLE: NO DOCUMENTATION SHOWING PERIODIC SAMP. LEAK TEST SYS. PROC NUMBER: 93702 COMMENTS: FROM INITIAL LICENSING ON NOV. 10 1985, UNTIL MAY 20, 1994, THERE WAS NO DOCUMENTATION OR OTHER EVIDENCE TO SHOW THAT PERIODIC SAMPLING OF THE LEAK TEST SYSTEM ON THE SPENT FUEL POOL LINER HAD BEEN IMPLEMENTED, RBS1 I 94-012 03 VIO 4/4 PLTSUP 07/05/94 C 08/09/94 06/05/99 4250 WKS 95-003 TITLE: WORKER ACCESSED RAD. CONTROL AREA W/0 READING REQ. PROC NUMBER-71707 COMMENTS: ON MAY 11, 1994, A CONTRACT QUALITY CONTROL INSPECTOR FAILED TO ADHERE TO THE REQUIREMENTS OF A PROCEDURE WHICH STATES, IN PART. THAT THE INSPECTOR LOGGED ON THE RADIOLOGICAL WORK PERMIT AND PROCEEDED T0 ENTER THE RADI0 LOGICALLY CONTROLLED AREA WITHOUT READING AND UNDERSTANDING THE REQUIREMENTS DELINEATED BY THE PERMIT. RBS1 I 94-012 05 NCV ENG 07/05/94 C 08/09/94 07/05/94 4240 WKS 94-012 TITLE: INOPERABLE RCS LEAKAGE DETECTION SYS. 0.C. 1,2,&3 PROC NUMBER: 93702 RBS1 I 94-012 06 NCV ENG 07/05/94 C 08/09/94 07/05/94 4240 WKS 94-012 TITLE: LACK OF PRIM. CONTAIN. INTEGRITY DURING REFUELING PROC NUMBER: 93702 KBS1 I 94-013 01 VIO 4/1 OPS 06/28/94 C 07/07/94 11/14/95 4250 WKS 95-024 95-018 TITLE: FAILURE TO ADHERE TO THE PROCEDURE PROC NUMBER: 92901 e e

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM D Ej g/jg/g6 E. GREHER REPORT BY SITE PAGE: 14 SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION REPORTS COMMENTS: ON MAY 5, 1994 A PROCEDURE WAS NOT FOLLOWED WHEN A CONTRACTED FUEL HANDLING CREW, UNDER THE DIRECT SUPERVISION OF AN ENTFRGY SENIOR REACTOR OPERATOR PERFORMED STEP 682 INSTEAD OF STEP 668. THIS FAILURE TO ADHERE TO THE PROCEDURE WAS SELF-EVIDENT WHEN PERSONNEL WITHDREW THE IRRADIATED FUEL ASSEMBLY FROM A CORE LOCATION AND ATTEMPTED TO TRANSFER IT TO AN UPPER CONTAINMENT POOL LOCATION, WHICH WAS ALREADY OCCUPIED. RBS1 I 94-015 01 VIO 4/1 MAINT 08/08/94 C 09/08/94 11/14/P5 4250 WKS 95-024 TITLE: 2 EXAMPLES OF INADEQUATE M&S PROCEDURES PROC NUMSLM: 93702 COMMENTS: TWO EXAMPLES OF INADEQUATE PROCEDURES WERE: 1) MAINTENANCE WORK ORDER DID NOT INCLUDE A STEP FOR THE INSTALLATION OF A JUMPER TO PREVENT THE INTERRUPTION OF A POWER SUPPLY NEUTRAL CIRCUIT DURING THE REPLACEMENT OF AN AGASTAT-RELAY, WHICH WOULD HAVE PRECLUDED AN ENGINEERED SAFETY FEATURE ACTUATION. 2) SURVEILL-ANCE TEST PROCEDURE, " DIVISION II REMOTE SHUTDOWN SYSTEM CONTROL CIRCUIT OPERABILITY TEST," DID NOT PROVIDE INSTRUCTIONS TO PREVENT AN ENGINEERED SAFETY FEATURE ACTUATION WHEN ISOLATING THE REACTOR PLANT COMPONENT COOLING WATER SYSTEM. RBS1 I 94-015 02 VIO 4/1 OPS 08/08/94 C 09/08/94 03/08/95 4620 TMG 95-006 TITLE: REACTOR MODE SWITCH OUT OF SHUTDOWN POSITION PROC NUMBER: 93702 COMMENTS: ON JUNE 10, 1994 THE REACTOR MODE SWITCH WAS OUT OF THE

  • SHUTDOWN" POSITION FOR APPROXIMATELY 4 HOURS. DURING A PERIOD WHEN BOTH DIVISIONS OF THE MANUAL SCRAM FUNCTIONAL UNIT WERE NOT OPERABLE.

RBS1 I 94-015 03 VIO 4/4 PLTSUP 08/08/94 C 09/08/94 03/29/95 4640 JLN 95-009 TITLE: UNMARKED BAG LEFT IN CONTAMINATION AREA-1000 MR/HR PROC NUMBER: 71707 COMMENTS: ON JUNE 2, 1994 A BAG WITHOUT A TAG OR LABEL WAS LEFT IN A CONTANIMATED AREA AND THE DOSE RATE OF THE BAG WAS 1000 MILLIREM PER HOUR ON CONTACT. 94-015 04 VIO 4/1 MAINT 08/08/94 C 09/08/94 01/09/96 4250 WKS 95-025 95-003 RBS1 TITLE: FAILURE TO PERFORM INDEP. VERIFICATION-LIFTED LEADS PROC NUMBER: 62703 COMMENTS ON JUNE 29, 1994 LICENSEE PERSONNEL IMPLEMENTING A MAINTENANCE WORK ORDER FOR THE REPLACEMENT OF A RELAY ON THE LOWER CONTAINMENT AIRLOCK FAILED TO PERFORM INDEPENDENT VERIFICATION OF THE LIFTED LEADS DURING THE RESTORA ION OF THE NEW RELAY. THE PERFORMER, IN LIEU OF THE INDEPENDENT VERIFIER, REMOVED THE LIFTED LEAD / JUMPER TAG UPON RESTORING THE CONNECTIONS. RBS1 I 94-018 01 VIO 4/1 MAINT 09/16/94 C 09/29/94 07/18/95 4250 WKS 95-004 TITLE: HPCS THERMAL RELIEF VALVE NEVER TESTED PROC NUMBER: 61726 6

ITEM DETAIL REPORTS IFS - INSPECTION FOLLOW-UP SYSTEM DATE: 10/31/96 E. GREHER REPORT BY SITE pfM(j10:30: SITE: RBS RIVER BEND STATION UNIT RPT/ IFS / SEQ-NO ITEM REF NBR / SEVERITY SALP REPORT / STS CREATE CLOSEOUT CLSOUT CLSOUT UPDATING ABBR EA/ NBR NOV-ID TYPE EA-NBR SUPLMNT AREA EVENT DT DATE PRJ/ACT* ORG NO EMP INSPECTION PEPORTS COMMENTS: ON AUGUST 18, 1994, A CONDITION ADVERSE TO QUALITY WAS NOT CORRECTED IN THAT THERMAL RELIEF VALVE 1E22*RCCO39 WAS NEVER TESTED BECAUSE OF A VALVE LINEUP ERROR taDE WHILE REVISING S SURVEILLANCE TEST PROCEDURE. RBS1 I 94-018 02 VIO 4/1 MAINT 09/16/94 C 09/29/94 07/18/95 4250 WKS 95-004 TITLE-RHR TEST VALVE LINEUP ALTERED-REMOVING PRESSURE PROC NUMBER: 61726 COMMENTS: ON MAY 15, 1994 THE SYSTEM TEST VALVE LINEUP WAS ALTERED, REMOVING TEST PRESSURE FROM THREE VALVES. THE PROCEDURE WAS SIGNED OFF AS HAVING SATISFACTORILY TESTED THE VALVES WHEN, IN FACT. THEY WERE NOT. RBS1 I 94-018 03 VIO 4/1 OPS 09/16/94 C 09/29/94 08/17/95 4250 WKS 95-005 TITLE: MS-PLCS VALVES IN WRONG POSITION PROC NUMBER: 61715 COMMENTS: ON JUNE 30, 1994, VALVE IMSI*V84 WAS FOUND IN THE OPEN POSITION AND VALVE IMSI*V85 WAS FOUND IN THE CLOSED FOSITION. THE SYSTEM OPERATING PROCEDURE REQUIRES THE POSITION OF VALVE IMSI*V84 TO BE CLOSED AND THE POSITION OF VALVE IMSI*V85 TO BE OPEN AFTER THE VALVE LINEUP IS COMPLETED. THE VALVE LINEUP WAS COMPLETED ON JUNE 26, 1994. RBS1 I 94-018 04 NCV MAINT 09/16/94 C 09/29/94 09/16/94 4250 WKS 94-018 TITLE: FAILURE TO ISOLATE RWCU < MINIMUM OPER. CHANNELS PROC NUMBER: 92700 NOTE: DEFINITION FOR CHARACTER PRECEEDING REPORT NO: I INSPECTION REPORT NUMBER. E = EA NUMBER (ENFOPCEMENT / NOV ITEM) = IFS NUMBER, NUMBER USED TO IDENTIFY NON-INSPECTION ITEMS N = hhikh'khkhkMh $===5E5=A===Y ' ~~~~[~~~"'"'h5F khkk~kS bPkh PRb3kbhkb bLbSkbbh bkhE kbRkPbRhkD L p ~ TOTAL OPEN REPORT SEQUENCES====>> 1 IF ITEM IS CLOSED, ACTUAL CLOSEOUT DATE IS REPORTED t Q .a - + x -, - _ _ - - _ _ _ - _ _ _ _ _ _ _ _. _ - - _ - _ - _ _ - _ _ _ _. _ _ _ _ - - _ _ _ _ - - - - _ _ _ _ _ - _ _ - _}}

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