ML20099H376
| ML20099H376 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/31/1984 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20099H350 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8411280131 | |
| Download: ML20099H376 (970) | |
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RIVER BEND STATION DETAILED CONTROL ROOM DESIGN REVIEW i
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SUMMARY
REPORT i -
i 5 METHODOLOGY AND APPROACH i
- HUMAN ENGINEERING DISCREPANCY RESULTS 4
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- O October,1984 t
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t GULF STATES UTILITIES COMPANY k
- O 8411200131 841031
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RIVER BEND STATION 1 GULF STATES UTILITIES COMPANY !
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TABLE OF CONTENTS PAGE VOLIME I - MITIDDOUXN AND APPICACH E-1 EX ECUT I VE S UMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-1 SECTION 1.0 M ETHODOLO GT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-1 1.1 P l a nn i ng Ph a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1.1 P r og r a m P l a n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....:.......... 1 -1 1.1.2 Ma nag emen t a nd s ta t t i n9 . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1. 3 Rev iew Team S t r uc tu re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.1.4 Rev iew Te am Ac t iv it ie s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.1.5 Rev iew Te am Or i en ta t ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-5 1.2 Re v i e w P h a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.2.1 Ope ra tor In te rv iew s a nd H is tor ic a l Rep or t Rev iew . . . . . . 1-6 1.2.2 Con tr ol Room S u rv ey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-11 1.2.3 System Functions Review a nd Task Analys is. . . . . . . . . . . . . 1-11 1.2.3.1 Purpose...................................... 1-13 1.2.3.2 Sy stem Fu nctions Descr iptions . . . . . . . . . . . . . . . . 1-13 1.2.3.3 Sc ena r io Dev elopmen t . . . . . . . . . . . . . . . . . . . . . . . . .
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\_ ' 1.2.3.4 Res idual Task Id entification. . . . . . . . . . . . . . . . .
1-13 1-17 1.2.3.5 Task Analys is Worksh eet Developmen t. . . . . . . . . . 1-22 1.2.3.6 Ta sk A na lys is Da taba s e . . . . . . . . . . . . . . . . . . . . . . . 1-24 1.2.3.7 Contr ol Room Inv en tor y . . . . . . . . . . . . . . . . . . . . . . . 1-24 1.2.3.8 Videotape Data Analys is Me th od ology. . . . . . . . . . 1-25 1.2.4 Verification of Task Performance capabilities.. .. . .. . .
1-27 1.2.5 Validation of EOPs a nd Control Room Functions. . . . . . . . .
1-43 1.1 Asse ssmen t a nd Implemen ta tion Phase . . . . . . . . . . . . . . . . . . . . . . . . . .
1-43 1.1.1 HED Ca t eg or i z a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1 -50 1.1.2 RED Resolution........................................
1-54 1.3.3 Implem en ta t ion S ch edu le . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Ve r i fication of De s ig n Impr ovemen ts . . . . . . . . . . . . . . . . . . . 1-54 1.3.4 1-55 1.3.5 Onqoing Human Fac tor s Maintena nce Plan. . . . . . . . . . . . . . . .
1-63 1.4 D oc u me n ta t i on Ph a s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-63 1.4.1 Re f e r e nc ed D ocu m en ta t ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-64 1.4.2 Rev ie w Doc u men ta t ion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-64 1.4.3 Da tab a se Ma nag em en t Sy stem . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-65 1.5 Contr ol Room /S imula tor Di f f e renc es S tu dy . . . . . . . . . . . . . . . . . . . . .
1-65 1.5.1 C ompa r i no n M e th od . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
1-67 1.5.2 Simulator /Contr ol Room Di f f e rence Result s. . . . . . . . . . . . . 1-69 1.5.3 Significance of Control Room /SipJiator Dif fe rences... . 1-70 1.5.4 R ec omme nd ed Ac t ion s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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GULF STATES UTILITIES CCHPANY RIVER BEND STATION O
PAGE SECTION 2.0 IMPLEMEN TATION SCIIE DULE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1 HED Cor re c t ion Sch edu l e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2 Op en IE D Re s ol u t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.3 Op en Items f or Fu tu re As se ss men t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 SECTION 3.0 QUALITY ASSURANCE P ROGRAM AND AUDITS . . . . . . . . . . . . . . . . . . 3-1 3.1 OA Proiect D r m ahi r a c . .................................... 3-1 1.2 QAAudit..................................................... 3-1 3.3 NRC In-Progress Audit........................................ 3-2 SECTION 4.0 DTTEGRATION OF DCIOR WITH O'I1tER SUPPLEMDIT 1 TO NUREG-07 37 ACTIVITIES 4.1 Eme rg ency Op e ra t ing P r oc edu re s (I . C.1) . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2 Sa f e ty Pa rame te r D isplay Sy stem (I . D.2) . . . . . . . . . . . . . . . . . . . . . . 4-1 4.3 Eme rg ency Resoonse Fac ilit ie s (III . A.l .2 ) . . . . . . . . . . . . . . . . . . . . 4-4 4.4 Reg u la t ory Gu id e 1. 9 7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4 4.5 T r a i n i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-4 SECTION 5.0 REFE RDI CE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 SECTION 6.0 StNMARY REPORT ADDENDUM............................... 6-1 APPDIDIX A RESUES OF ORIGINAL BWROG SURVEY TEAM APPENDIX D REStNES OF DCRDR TEAM APPDIDIX C DOCUMENTATION FORMS APPENDIX D DOCtMENTATION LOG APPENDIX E SYSTEM DESCRIPTIONS APPDIDIX F OPERATING SEQUDICE DESCRIM' IONS APPDIDIX G OA PROJECT PROCEIXJRES VOLtMR II - IRMAN DiGINEERING DISCREPANCY RESULTS SECTION 7.0 REV I EW FI ND IN GS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 7.1 P r f or i ty I If E D s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-2 7.2 P r f or i ty I I IIE D s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-3 7.3 P r i or i t y I I I IIED s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-4 7.4 Priority IV IIEDs...................................... 7-5 7.5 Open IIEDs............................................. 7-6 O
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GIVC CEND STATION GUTP STATES ITPILITIES COMPANY l EXECUTIVE SU9tARY E.0 INTRODUCTION _
Gulf States Utilities Comoany (GSU) has recognized the need to improve the man-machine interf ace in the River Bend Station (RBS) Main Control Room and has focused an ef fort toward that goal. A BWROG Control Room Survey program was performed in a orelimirary review of the RBS Main Control Room panels af ter they mre assembled in the General Electric (GE) manufacturing f acility in San .Tose in August 1981. We Boiling Water Reactor Owner'c Group (P'moq)
Generic Program Plan addressing the Planning and Review chases of a Detailed Control Room Design Review (DCIOR) was submitted to the Nuclear Regulatory Conrninston by the InmOG (Reference A) . The t#tC approved the BWROG Control Room Survey program as an acceptable approach to the Planning and Review phases of the DCRDR. The requirements for corducting a DCRDR are included in N'JREG-0737 Suoplement 1 (Reference B) . This program plan submittal describes the plan which GSU will follow to conduct a DCRDR in accordance with the requirements of References B and C.
E.1 MANAGEMENT REVIEW CYCLES FOR RBS DCTOR_
GSU recognized the importance of maragement involvement in the DCRDR aM developed a program to ensure proper management attention to its various activities.
The ultimate responsibility for the DCRDR resided with the RBS plant Manager. To ensure that he remsined informed and involved, the revi6w team leader reported directly to him. This created a good flow of comunications hatwen the DCBDR team as management. In adaition, the review team leader submitted monthiv status reports to the Plant Manager, with copies to all management, engineering, operations and licensing personnel involved with the DORD R.
The review team lesier qave neveral presentations to both the Vice President and 9enf or Vice President of the RDS Nuc1 car Croup. Wese presentations ranqr=1 from a general overview arri progress status of the DCHDR to npecific j
toolco nuch as team mamtne qualifications.
The pnq Proiect Engineer was responsible for approving the corrective actions renulting from the DCTOR. Formerly, he was the Pome Generation Control Complex Supervisor who developed the schedule that the DCRDR team followed.
!!o is very familiar with the control room design and the various aspects of performing a DCRDR. One of the team members worked directly for the Project Engineer, ensuring that he remained informed. When the recommendations for corrective action were finalised for a group of ITEDs (i.e., Priority f1's),
they mre submitted to the Project Engineer for approval.
The PGO: Supervisor in responsible for imlementing the corrective actions.
This person was a member of the DCTOR team and was actively involved in the verification, assessment, arvi corrective action phases of the DCRDR. This involvemant will assist in the implementation of IIED cor rective actions.
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GUI? STATES UTILITIES COMPANY RIVER BEND STATION E.2 OVERIIP,4 E.1.1 Durnone The outoose of the D?RDR was tot
- 1) Review an1 evaluate the control room workspace (Figure E-1) and remote shutdown nanel, instrumentation, controls and other equipment from a human factors engineering viewpoint, taking into account both system demanis and operator capsbilities.
- 2) To identify, assess and implement control room design enhancements an1 modifications to correct items which are safety-related or otherwise substantially impact the potential for operator error, particularly in preventing or coping with energency situations.
E.2.2 Objectiven The objectives of the DCR3R were:
- 1) To identify improvements in the control room / operator interf ace which had the potential to reduce the probability of error, norticularly with regard b) preventing or coping with emergency situations.
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- 2) To evaluate any identified problems and te establish relative priorities ani corrective action plans eccording to specific evaluation criteria.
- 1) To verify that each selected design improvement provided the necessary correction an1 would be introduce 1 in the control room without creating unacceptable human enginnering dincrepancies (IIEDs) boiause of significant centribution to increased risk, unreviewed safety quantionn or situationg in which a temocrary reduction in safety could occur.
- 4) To coordinate improvements with changes resulting from other humin f actors /emrgenet response improvements.
E.2.3 Dancription of n?RDR Activition To achieve the objectives of the DCM1F, a number of activities were co9oleted. A flowchtet showing the interrelationship 1 of the DCIOR activition is presente1 in Piqure U-2.
The DCnDR was split into nix phases completal e Pla nning e peview l e A1sessmont an1 Implementation l e Documentation lll l
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i' ' I GENERAL AHRANGEMENT -
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CONTHOL DUILDING RIVER BEND STATION -
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RIVER BEND S1RTION GtLP TI%TES IFFILITIES COMPANY O
v DCRDR Pienning N EI and Review Team PLANNING Preparation if 1 i 1981 BWROG CR Survey Program Checklist & Results Control Room Operating Experience Survey Review lf k bob A .
PHASE 11 Systems Descriptions REVIEW t Task Analysis Based on EOPs e
O Verification of I&C Requirements Validation of Control Room Functions U
/L Assessment of HEDs PHASE 111 ASSESSMENT AND k IMPLEMENTATION HED Correction /
Implementation Scheduling I f t
a PHASEIV Preparation of DCRDR Summary DOCUME NTATION !
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Figure E-2. Flowchart of DC10R Activities E-4
RIVER EEND STATION GULF STATES UTILITIES COMPANY 77
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Ongoing e Imolementation e Maintenance A brief synoosis of these activities follows.
E.2.4 D1anning Phase The planning phase commenced with the establishment of the BWROG Control Room Improvements Committee in January 1980. We planning phace was described in detail in Reference A. The planning for outstaMing activities is detailed in this report (see Section 1.1) .
E.2.5 Review Phase The review phase consists of a control room survey coMucted by a multidisciplinsey team to compire the characteristics of the control room with appropriate human engineering design guidelines, an operating experience review (including documentation and op?rator interviews) and function / task analysis of Emergency Operating Procedures (EOPs) . 'Phe review phase of the DCRDR for RD9 was performed in accordarce with the BWROG methodology for the coerator interview, control room survey, arr! survey supplement as described in Sections 1.2.1 and 1.2.2 of the report. We system functions review aM task analysis, verification, aM validation portions of the review phase were p)
(, conductad as described in Sections 1.2.1, 1.2.4, and 1. 2.5 respectively.
Thirteen panels wre reviewd during the 1981 original survey by operations ani enginearing personnel from three utilities, a human f actors specialist from the Massachusetts Institute of Technology, aM representatives from the Nuclear 9 team Suoply System (NSSS) veMor aM the architect /enginear. We scone of this preliminary review was defined so as to be commensurate with the current manuf acturing status of the control canels, concentrating primarily uoon canel design, instrumentation aM hardware. Since the panels were staged in the f actory at the time of the survey, it was rot possible to evaluate some noctions of the BW90G Control Room Survey checklists. These sections were listed in a BWROG Summary Report that was submitted to GSU in December 1981.
The BWROC Summary Report provided a comolete list of items for which main control room mo<lifications or enhancements should be assessed, and listed favorable aspects of the main control room design that were noted by the team. The items that remained in the review phase wre completing the BWROG checklist aM its suoplement, the operating experience review, aM performing function arvl task analysis for the EOPs (see Section 1.2) .
The DCRDR project surveyed all panels from the preliminary BWROG control room survey a9 wall as appilcable panels insta11M since 1981 in the main control rnom, A nystem functions aM task analysis was completed for selected emrgency omrating sequences to exercise all system functions aM associated opera tor tasks. The results of the task analysis were compared with the in-olace inventory of controls and displays in the control room to assure that the control room sunoorts the Emergency Operating procedures (EOPs) arri to (v)
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';ULF S1ATES UrILITIES COMPA'W RIVER BEND STATION O
lientify missing disolays or controls. With regard to the operating experience review (which is a part of the review phase for an operating plant), operator exoerience on the simulator was substituted for operator experience in the main control room because of the RBS construction status.
The identified findings from this phase were dien written up as HEDs.
E.2.6 Assessment and Implementation Phase During the assessment phase, identified HEDs were evaluated with regard to their probability for causing ooerator error and their potential impact of the error on safe plant operation (Sec tion 1.3) . As a result of this evaluation, each RED w.s assigned a criticality rating of 1, 2, 3, or 4. Recommendations for corrective action were then developed for each HED and submitted to GSU management for approval. Consideration was given to correction by enhancement, design modifications, procedure and training improvements ard the capabilities of other emergency response improvements, (e.g. , safety parameter disolay system).
Once the RED corrective actions were approved, an HED implementation schedule was developed ba sed on criticality rating ani type of correction to be narformed as shown below:
E nha ncemen t s All enhancements (Criticality Rating 1 through 4) shall be implemented prior O
to exceeding 5% of full oower rating.
Moli ficat ions Criticality Rating Sch edu le 1 Prior to Fuel Load (Current Schedule - April 1985) 2 Prior to exceeding 5% of full Power Rating (Current Schedule June 1985) 3 Prior to exceeding 5% of full Poder Rating 4 During ist Refueling Outage These corrective actions will be integrated and correlated with other NUREG-0737 Supplement 1 Emergency Response Improvement Actions.
The results of the DCRDR activities are contained in this summary report.
Sections 1 through 6 outline the methodology ani approach used in accomplishing DCPDR, and Section 7 contains the HED results. Some items , such as HVAC, communications and lighting could not be completely evaluated due to their construction status. These items will be evaluated when their installation is complete an1 the results will be documented in an addendum to this repor t.
G90 has implemented an ongoing human f actors program to give continuing attention to human f actors engineering in the main control room and remote E-6
RIVER BEND SMTION GULF 9mTES tfrILITIES COMPANY O
shutdown panels. This will ensure that future design mcdifications do rnt ;
violate the human factors design conventions that have been established.
E.3 DEFINITIONS Emergency Operating Procedures (EOPs) - Plant procedures driving the operator actions necessary to m*.tigate the consequences of transients and accidents that cause plant parameters to exceed reactor protection setpoints, engineered safety feature setpoints, or other appropriate technical limits.
Emergency Procedures Guidelines (EPG's) - Guidelines developed from system analysis of transients and accidents that provide sourd technical bases for plant-specific EOP's.
Function (Subfunction) - A kind of activity (or a static role) performed by one or more system conatituents (people, medianism, structures) to contribute to a larger activity 4 goal state.
Function / Functional Analysis - The examination of system goals to determine what functions they require. Also, examination of the required functions with respect to available manpower, technology ard other resources, to determine how the functions may be allocated and executed.
Function Allocation - The distribution of functions among the human ard automated constituents of a system.
Human Factors Engineering (HFE) - The science of optimizing the performance of human beings in man-machine systems. More narrowly, the science of design of equipment for ef ficient use by human beings (also known as bioengineering, biotechnology, engineering psychology, ergonomics, and human engineering) .
Human Engineering Discrepancy (HED) - A characteristic of the existing control room that does rot comply with the human engineering criteria used in the ecntrol room rurvey.
Quality Class 1 (S af e ty-Rela ted ) - Plant systems, por tions of systems, structures and equipment whose failure or malfunction could cause a release of radioactivity in excess of those limits specified in 10CFR100. Quality Class 1 includes equipment which is vital to a safe shutdown of the plant, the removal of decay ard sensible heat, or equipment which is necessary to mitigate consequences to the public of a postulated accident. This class includes ASME Code Class 1, 2, & 3 items fabricated 3rd installed under ASME Section III. Also included in this class are any activities or services that affect the safety function in the design, operation ard maintenance of safety-relatecl structures, systems or components.
Quality Class 2 (Impor tant to Reliability) - Non-safety-related plant systems, portions of system, structures, and equipment essential for the reliable generation of electric oower, but which are not essential for a safe s hu tdo wn. Failure of this equipment could result in a loss of power generation ard/or challenge safety-related systems, but w)uld not endanger public safety. Equipment ard systems which contain radioactive mate'ials, but p/
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GULF 9 PATES ITPILITIES COrtPANY RIVER BEND SMTION O
whose failure could rot release quantities suf ficient to exceed limits specified in 10CFR20, are includai in this category.
NorE We term " essential for the reliable generation of electric powr" refers to components whose f ailure would result in the halt of electric power generation af ter a priod of approximately eight hours or less.
Quality Class 3 (Non-Saf e ty-Rela ted ) : Plant systems, por tions of systems, structures, and equipment which are rot essential for reliable generation of electric power an$ which do rot contain radioactive material or whose failure could rot result in the release of radioactive material.
System (Subsystem) - An organization of interdependent human-equipment constituents that work together in a patte rned manm r to mcomplish some purpose.
System Function Analysis - The determination 'of system functions required to meet system goals.
Task (Subtask) - A specific action, performed by a single system constituent, Inrson or equipment, that contributes to the accomplishment of a function.
Task Analysis - The systematic process of identifying ard examining operator tasks in orde r to identify corditions ard information ani control requirements associated with the performance of a task. In the DCRDR context, task analysis is ussi to determine the irdivicilal tasks that must be completed to allow successful emergency operation. In addition, this activity can verify and validate the match of information available in the main control room to the information requirements of the emergency operating tasks.
Validation - The process of determining whether the main control room operating crew can ef fectively perform their functions given the control room instrumentation ard controls, procedures, an$ training. In the DCBDR cor. text, validation imolies a dynamic performarce evaluation.
Verification - The prccess of determining whether instrumentation, controls, ard other equipment are available to meet the specific requirements of the ermegency tasks prformed by operators. The control rocn survey ard task analysis are verification mtivities, checking the nsin control rocn match to the human ope rator.
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- ' RIVER BEND STATION GULF STATES UTILITIES COMPANY
! ' l.0 METHODOLOGY 1.1 PLANNING PHASE 1.1.1 Prooram Plan 4
The Detailed Control Room Design Review (DCRDR) Planning Phase began %e Program with the development of a Program Plan for the River BeM Station (RBS) .
Plan was submitted to NRC for review in January 1984. %e DCRDR Activities outlined in the Program Plan are shown in Figure 1.1-1.
NRC review cmunents were received on April 25, 1984. Se cements indicated j
that the " planned control room design review generally meets the intent of 4 NUREG-0737, Supplement 1.
j An in-progress audit was conducted by NRC at RBS on July 23-27, 1984 to review all DCRDR elements and clarify the methodology used to conduct the task l
i analysis phase.
f f
The results of the audit were favorable ard indicated that the RBS DCRDR should meet all NUREG-0737, Supplement I requirements.
1.1.2 Management and Sta ffing The ultimate responsibility for the RBS DCRDR resided with the RBS Plant O Ma nage r . We day-to-day conduct of the review was the responsibility of the DCRDR review team. The 1981 main control room survey was led by the BWROG Control Room Survey Team; Appendix A contains the resumes of the BWROG survey
- l team. Remaining DCRDR activities were managed by the review team leader. We
' review team leader reported progress of the DCIOR to the Plant Manager on a monthly basis. Wis provided the necessary management attention to ensure that the DCRDR objectives were met and that the efforts are integrated with overall emergency response inprovements. %e DCRDR team required interaction with other organizations within Gulf States Utilities Canpany. The review 4
I team leader had the authority to assure fceedon of the DCRDR team operation.
Areas included weres j!
J e Access to information (records, documents, plans, procedures, drawings, etc.)
e Access to all required facilities l
e Access to any personnel with useful or necessary information e Access to support services e Freedom to dccument dissenting opinions 1.1.3 Review Team Structure The review team was a multidisciplined team of individuals with the wide range of skills necessary to perform the design review. We core review team, O
l-1 l
I
,_._.,_,--,___..._____.-,___._-_,,m,,- _ , w.., ._,m... .w, v m.,,m.,,,. __ ,-. __- - ,,,,, _ ._,_ ~ ,w_.-,__-,,,m.. ,rr-
GILF STATES UTILITIES CCHPANY RIVER BEND STATION A
O DCRDR Pianning PHASEI and Review Team p g Preparation h
1981 BWROG CR Survey Program Checklist & Results I
Control Room Operating Experience Survey Review t t RBS FSAR PHASE 11 Systems Descriptions REVIEW k
Task Analysis Based on EOPs Verification of I&C Requirements V
Validation of Control Room Functions V
h Assessment cf HE Ds PHASE Ill ASSESSMENT AND IMPLEMENTATION f
HE D Correction /
Implementation Scheduling V
h PHASE IV Prepantion of DOCUMENTATION DCRDR Summery Report p
Figure 1.1-1. Flowchart of DCBDR Activities (shows BWROG CR Survey Program Plan Incorporation) l 1-2
1 RIVER BEND STATION GUIE STATES UTILITIES COMPANY O
O consisting of members from GSU and General Physics Corporation (human factors consultant) included the following personnels.
e Review Team Leader e General Physics Lead Human Factors Specialist 4 e Senior Reactor Operators Supporting personnel to the core team were available as needed.
1.1.3.1 Review Team Leader i
The review team had the review team leader as its key person. H is individual
- provided the administrative and technical direction for the project and had responsibility for the project. Access to information, facilities an$ individuals providing useful or necessary input to the team was coordinated by the Review Team Leader. Because of the detailed knowledge of RBS systems arr! methois, this individ2al provided a cohesive force for the various GSU department personnel ard vendor organizations employed at RBS.
It was the responsibility of the Review Team Leader to resolve differences in human f actors opinions on methodology, tedinique, review findings, assessment, ard hTD corrective actions that dissent with the majority opinion of the DCRDR Review Team. We Review Team Leader was assisted in the performance of his function by the General Physics Lead Human Factors Specialist.
O 1.1.3.2 General Physics Lead Human Facters Specialist (HPS)
The General Physics lead human factors specialist worked closely with the review team throughout each phase of the control room review and provided the team with i
human factors technical leadership. We human factors specialist coordinated all activities from a human f actcrs perspective ard verified that task performance i
quality was maintained at a level necessary for a valid and comprehensive review.
4 1.1.3.3 Senior Reactor Ooerators (SROs)
Several SROs from GSU served as m mbers of the ccre review team. The SRO's assisted in identifying coerator task ard served as the review team experts on the operational constraints for manipulations of plant systems.
s 1.1.3.4 Supporting Personnel l
l In addition to the personnel described in Sections 1.1.3.1 to 1.1.3.3 above, the j support of additional personnel was utilized as necessary. We support included the
- following personnel
- e General Physics Proiect Director The Project Director was responsible for ensuring the assignment of qualified people to the project, obtaining support from corporate
' resources, ard providing overall direction to the project. He was also responsible for directing the GP project staff and for ensuring excellence
. ph I of work performed. He provided additional human factors support to the review team as needed.
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, _ , . _ _ _ - , , _ . - . . - _ _ , _ , _ _ , , . . _ _ - , _ _ . .,,,..p,. .
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GULF STATES UTILITIES COMPANY RIVER BEND STATION 9
e Systems Design Consultant General Electric, the systems design consultant ard nuclear steam supply system (NSSS) verdor, was consulted as appropriate for review of DCRDR matters related by NSSS design.
e Instrue.entation a rd Controls (I&C) Engineer An I&C engineer provided advice to the team on I&C issues during the main control room survey, assessment of HEDs ard the development of recommendations for corrective actions.
e Licensing Engineer The GSU Licensing Engineer provided advice to the team on safety / licensing incues throughout the process. This included review and concurrence with the RBS Program Plan ard Summary Reports.
e Operations Specialist An Operations Specialist suoported the review team in the identification of operating sequences, task analysis, and verification ard validation phases, o Human Factors Specialist Additional Human Factors Specialists in addition to the core team members were available to support the DCBDR phases as needed.
e Arch itect/Enqineer (A/E) Consultant The A/E consultant from Stone ard Webster Engineering Corporation (SWEC) was consulted in matters related to A/E design.
e Ouality Assurance Engineer The GP Quality Assurance Engineer was responsible for reviewing project prcx:edures ard conducting audits during the course of the DCBDR.
e Training Soecialist/ Instructor The training specialist supported the review team in identification of simulator / main control room differences, systens review ard task analysis, HED assessment ard recommendations for corrective actions.
1.1.4 Review Team Activities The initial development of methcdology for the review was performed urder the BWROG as discussed in Reference A. 'Ihe methcdology for the assessment of HEDs described in this report was developed by the review team. The review team participated with GSU management in establishing the overall plan ard schedule 1-4 l
a ; 4 u. # m; .u.4 4 -- .
RIVER f.END STATION GUTF STATES UTILITIES CGtPANY O We review team performed the outstarding activities and f for the DCER.
i integrated all action items. Se review team was responsible for the preparation of all reports related to the DCER ard ensured that appropriate reports were submitted to GSU management for review ard approval.
1.1.5 Review Team Orientation The initial BWROG review team received their orientation by attending a BWROG Control Room Survey Workshop on October 8-15, 1980. Topics covered included control room design review objectives, human factors principles, BWROG Otecklist, operating experience review, task analysis ard simulator survey performance exercises. A familiarisation with the main control room panels was performed when the survey conumenced.
' A second BWROG Control Room Survey Workshop, attended by the 1983 GSU DCRDR l
team members, was held on October 18-20, 1983. Topics covered included human factors principles, NUREG-0737-Supplement 1, NRC Generic Letter 83-18, BWROG Control Room Survey development afd methcdology, decklist supplement, operating experience review update, task analysis on emergency operating procedures ard simulator performance exercises on the decklist supplement aid task analysis.
A two-day DCRDR Team orientation workshop was held onsite in the RBS Training Center on January 26-27, 1984. Se workshop covered general human factors n priniciples ard history, DCRDR requirements ard guideline documents,All ardcore the
\J specific Program Plan methcdologies to be used on the RBS project.
DCRDR team members ard many of the supporting members attended the orientation course.
I A brief orientation to the plant, previous survey results afd plans for outstarding work in the main control room was held when the performance of the checklist ard checklist supplement cor.inenced. Se close coordination between l
the plant ard consultant personnel on the team allowed any additional orientation needs which arose to be met on an as-needed basis.
1.2 REVIEW PHASE The DCRDR for RBS was performed according to the review procedures described below.
The procedures used for the operating experience review, historical report i
review ard contrcl roan survey were transmitted to the NRC by Reference A ard I approved by the NAC in Reference C. One of the comments in Reference C was that the plant-specific program plan should document the number ard extent of
' plant personnel participation. Appendices A ard B irdicate the plant l personnel participation in both the original survey ard the DCER.
1.2.1 Operator Interviews ard Historical Report Review l
1.2 .1.1 Operator Interviews The puroose of the operator interview is to obtain direct operator input to N aid in identifying potential or actual deficiencies in the control room layout I
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GULF STATES UTILITIES CCNPANY RIVER BEND STATION O
or design or in operating procedures that result in confusion (mental activities), difficulty (manual activities) or distraction (the environment) .
Using the questionnaire in Apperdix C, interviewers asked operators to respond in writing based on their operational experience ard knowledge of the RBS main control room or RBS simulator. Interviewees retained a copy of their ccepleted questionnaire forms ard reviewed them with a survey team member during a later oral interview. If additional space was needed, an attachei comment form was used. Five operators covering a range of experience, edtration, ability and physical size were interviewed. In addition, several RBS simulator training instructors were interviewed.
We interviews were conducted by members of the DCBDR team with backgrourd or experience in operations ard engineering or design with a position conducive to a free flow of information. Each oral interview took one to two hours.
Following the interviews, the survey team consolidated the information obtained and analyzed it to help identify specific areas of concern for detailed analysis during the DCRDR assessment phase.
1.2.1.2 Historical Report Review Review of Licensee Event Reports (LERs) of operating plants have resulted in identifying possible human f actcr s design considerations that may have contributed to operator error s. We BWROG DCRDR survey program recommends review of LERS during the last two years of plant operations for use as a source in identifying the HEDs.
Due to the construction nature of RBS ard the unavailability of LERs, a procedure was followed to extract the necessary information from plants that are similar in design and in control room arrangement to RBS. The plants that were chosen for the Historical Review were Mississippi Power ard Light Cmpany's Grard Gulf Nuclear Station, Pennsylvania Power and Light Company's Susquehanna Steam Electric Station and Commonwealth Edison Company's LaSalle Station. LERs sorted by personnel ard procedure problems were obtained from INPO for review.
The LER database was examined by a human factors engineer to determine if any LERs described human f actors issues. This list was then routed to RBS management to determine their applicability to the RBS main control room. All LERs that were found to be applicable to RBS were defined as HEDs ard were subsequently entered as such into the DCRDR database for analysis durir.g the assessment phase.
1.2.2 control Room Survey The purpose of the control room survey is to identify the characteristics of important controls and displays, the usefulness of audio ard visual alarm systems, olant status information previded, the control room layout ard environment, and other areas of human f actors engineering that potentially g impact cperator effectiveness. his is accomplished by conducting a W systematic cmparison of existing control room inventory against human
)
1 1-6 )
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RIVER BEND STATION GUT.P STATES UTILITIES CGlPANY
%,/
for the DCER. We review team performed the outstanding activities and integrated all action items. We review team was responsible for the preparation of al.1 reports related to the DCER afd ensured that appropriate reports were submitted to GSU management for review and approval.
1.1.5 Review Team Orientation The initial BWROG review team received their orientation by attending a BWROG Control Room Survey Workshop on October 8-15, 1980. Topics covered included control room design review objectives, human factors principles, BWROG Checklist, operating experience review, task analysis ard simulator survey performance exercises. A familiarization with the main control room panels was performed when the survey commenced.
A second BWROG Control Room Survey Workshop, attended by the 1983 GSU DCRDR team members, was held on October 18-20, 1983. Topics covered included human factors principles, NUREG-0737-Supplement 1, NRC Generic Letter 83-18, BWROG Control Roan Survey development ard methoiology, checklist supplement, operating experience review update, task analysis on emergency operating procedures ard simulator performance exercises on the diecklist supplement ard task analysis.
A two-day DCRDR Team orientation workshop was held onsite in the RBS Training Center on Jarmary 26-27, 1984. We workshop covered general human facters priniciples ard history, DCRDR requirements ard guideline documents, and the n specific Program Plan methodologies to be used on the RBS project. All core Q DCRDR team members ard many of the supporting members attended the orientation course.
A brief orientation to the plant, previous survey results ard plans for outstarding work in the main control room was held when the performance of the checklist ard checklist supplement ccanenced. We close coordination between the plant ard consultant personnel on the team allowed any additional orientation needs which arose to be met on an as-needed basis.
1.2 REVIEW PHASE The DCRDR for RBS was performed according to the review procedures described below.
The procedures used for the operating experience review, historical report review ard control room survey were transmitted to the NRC by Reference A ard approved by the NRC in Reference C. One of the cmunents in Reference C was that the plant-specific program plan should document the number ard extent of plant personnel participation. Appendices A ard B indicate the plant personnel participation in both the original survey ard the DCER. l 1.2.1 Operator Interviews ard Historical Report Review i 1.2.1.1 Ooerator Interviews l
The puroose of the operator interview is to obtain direct operator input to N aid in identifying potential or a:tual deficiencies in the control room layout J
1-5
GULF STATES UTILITIES C04PANY RIVER BEND STATION O
or design or in operating procedures that result in confusion (mental activities) , difficulty (manual activities) or distraction (the environment) .
Using the questionnaire in Appendix C, interviewers asked operators to respond in writing based on their operational experience ard knowledge of the RBS main control room or RBS simulator. Interviewees retained a copy of their empleted questionnaire forms ard reviewed them with a survey team member during a later oral interview. If additional spar e was needed, an attachei comment form was used. Five operators covering a range of experience, education, ability and physical size were interviewed. In addition, several RBS simulator training instructors were interviewed.
The interviews we re conducted by members of the DCIDR team with background or experience in werations ard engineering or design with a position conducive to a f ree flow of information. Each oral interview took one to two hours.
Following the interviews, the survey team consolidated the information obtained and analyzed it to help identify specific areas of concern for detailed analysis during the DCRDR assessment phase.
1.2.1.2 Historical Report Review Review of Licensee Event Reports (LERs) of operating plants have resulted in identifying possible human f actor s design considerations that may have contributed to operator error s. The BWROG DCRDR survey program recommends review of LERs during the last two years of plant operations for use as a source in identifying the HEDs.
Due to the construction nature of RBS and the urnvailability of LERs, a procedure was followed to extract the necessary information from plants that are similar in design ard in control room arrargement to RBS. 'Ihe plants that were chosen for the Historical Review were Mississippi Power and Light Canpany's Grard Gulf Nuclear Station, Pennsylvania Power ard Light Company's Susquehanna Steam Electric Station and Commonwealth Edison Company's LaSalle Station. LERs sorted by personnel ard procedure problems were obtained from INPO for review.
The LER database was examined by a human factors engineer to determine if any LERs described human f actors issues. This list was then routed to RBS maragement to determine their applicability to the RBS main control room. All LERs that were found to be applicable to RBS were defined as HEDs ard were subsequently entered as such into the DCRDR database for analysis during the assessment phase.
1.2.2 Control Room Survev The purpose of the control room survey is to identify the characteristics of important controls and displays, the usefulness of audio ard visual alarm systems, olant status information provided, the control room layout ard environment, and other areas of human f actors engineering that potentially impact @erator effectiveness. This is accomplished by conducting a systematic comparison of existing control room inventory against human 1-6
RIVER BEND STATION GULF STATES UTILITIES COtPANY p
V engineering guidelines. We ultimate objective is to identify potential modifications of the operator - control room interface which will reduce the potential for human error.
1.2.2.1 BWROG 1981 Survey The procedures used in conducting the RBS DCRDR survey followed the BWROG control room quidelines of Reference A. We survey was conducted by the review team using checklists developed by the BWROG. Supplemental information was provided in the BWROG workshop to give additional guidance to the review team members in completing the checklista. Each checklist item was presented in the form of a question for consideration by a survey team member.
Following that question was a series of numbers in which the specific item beirg reviewed was evaluated. The first set of numbers (4, 3, 2,1, 0) indicated the degree of compliance wherein (4) indicated no compliance, (3) indicated somewhat in compliance, (2) irdicated mostly in compliance, (1) indicated full empliance, ard (0) indicated the specific question being considered was not applicable or could not be considered at this time. As each specific question was evaluated, the team member (s) actually doing the evaluation of that question irdicated the relative degree of compliance by circling the applicable number.
Following the number irdicating the degree of compliance for each item being evaluated was a predetermined number ranging from one to three which irdicated O the relative importance of that item with respect to the potential for causing or contributing to operator error. A (3) irdicated high potential for operator error , a (2) irdicated moderate potential, ard a (1) indicated low potential. In the final evaluation of each item conside red, it was the product of the degree of empliance multiplied by the potential for operator error that determined if the consideration of corrective action is justified.
Following each checklist item was space for the person performing the evaluation to enter coments. For each specific checklist item, these coments identifed items or emponents for non-compliance, the scope of review, or any qualifying statement judged to be appropriate to the evalu ation . If, for example, a large number of ccaponents are reviewed ard only a few were non-compliance, these were specifically noted in the comment space ard the general rating was "mostly compliance." To provide additional documentation, still photcqraphs were taken of majcr items or components of non-empliance such as mimic layouts, control / display groupings, labelling systems or equipment locations. These photographs are cross-referenced to the specific checklist item by a notation in the coment space. Due to the importance of comments in the evaluation, additional comment forms were attached for more detail when necessary.
Since the RBS control panels were staged in the f actory at the time of the 1981 survey, it was not possible to evaluate sc.ne sections of the BWROG Control Room Survey Checklists. In addition, che to the manuf acturing status of the control panels durin7 the survey, several panel inserts ard significant instrumentation wre rot installed at the time of the survey. These were p listed in Appendix A of the 1981 RBS Control Room Sumary Report.
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GULF SIATES UTILITIES COMPANY RIVER BEND S' RATION O
The 1981 survey concentrated primarily upon the following areas:
o Panel Layout and Design o Instrumentation ard Hardwa re o Annuncia tor s o Emergency Procedure Instrumentation Each of these control room survey areas ard the general recommendations for enhancements are listed below:
1.2.2.2 Panel Layout and Design
- 1. Many back panels have controls ard displays mounted above ard below recommenied heights.
- 2. The dimensions of panel 680 are not optimized for a seated operator.
- 3. In many instances, functional groupings of controls and displays could be enhanced with demarcation lines and summary labels.
- 4. Some aspects of ndnde layout could be improved. Flowpaths should be readily apparent, crow 3ing avoided, symbology ard color coding cons istent.
The panel color code should be improved and consistently apolied.
O 5.
- 6. Labels should be more succinct.
- 7. A hierarchical labeling system should be instituted.
1.2.2.3 Instrumentation a nd Hardwa re
- 1. Control room indicators and recorders should be reviewed ba determine which would benefit from the addition of marking or color coding to indicate normal ard abnormal ranges.
- 2. Non-standard indicator scales should be avoided.
- 3. Iarger indicators should be considered for some parameters on panel 680.
- 4. Some indicator labels should be cor rected, indicating the cor rect units.
- 5. Labels for pen recorders should clearly specify the input point assigned each pen.
- 6. Multi-point recorders should be used only where such a format is applicable. Where used, consideration should be given to more widespread application of point select and fast speed capabilities.
- 7. A lamp test feature should be considered. f 1-8
GULF SmTES ITPILITIES COMPANY RlVER BEND SMTION f' T 5 ?
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- 8. Shape coding of switch handles should be considered.
- 9. Emergency switches should be clearly marked.
1.2.2.4 Annuncia tor s
- 1. We usability of the annunciator system could be improved by prioritizing alarms, segregating informational and advisory displays, clarifying ambiguous legends ard providing an alpha-numeric code for window id enti fication.
- 2. Larger lettering should be used on panel 680 annunciator windows.
- 1. A first-out feature should be provided.
1.2.2.5 Emergency Procedure Instrumentation
- 1. Annunciator legends should clearly specify the function of the alarm.
Redundant annunciators should be avoided.
- 2. Indicators aM recorders should be provided with range markings identifying action levels addressed in emergency procedures.
- 3. Certain modifications of display methods and formats could enhance the effectiveness of the control room as an operator aid during transient cond i tions.
- 4. Some information potentially useful to the operator is not available in the main operating area of the control room.
- 5. Some modification of instrumentation may be necessary to enable the operator to evaluate the state of the plant in accordance with certain considerations addressed in the guidelines.
1.2.2.6 BWBOG 1983 Survev Checklist and Checklist Sunplement The suoplement is intended to augment Revision 1 of the BWROG Control Room Survey Program dated 1/1/81. It is to be included as part of the Control Room Review Checklists to further document proposed main control roon improvements. We additional items listed in the s@plement have been drawn j
from human engineering guidelines reconsnended in NUREG-0700 ard verified through considerable experience of the BWBOG survey teams.
I Major sections of the supplement checklists are identified by letters correspording to section designations used in the original decklists. In order to differentiate between the two numbering systems, aM "S" prefix has been assigned to ead s@plement item. We s@plement decklist sections are:
SA. Panel Layout ard Design SB. Instrumentation and Hardware SC. Annunciator s pU SD. Computer s 1-9 1
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1 GULF STATES UTILITIES C04PANY RIVER BEND STATION O
SE. Proc edu res SP. Control Room Environment SG. Maintenance ard Surveillance Due to the preliminary nature of the RBS panels in 1981 ard the resultant number of changes that have since occurred, the DCIDR survey was performed completing both the main BWROG checklist ard the supplemental checklist for all the applicable panels. In addition, the rennte shutdown panels we re reviewed using the BWROG survey checklists. Guidelines were also reviewed in NUREG/CR-3696, " Potential Human Factcrs Deficiencies in the Design of Local Control Stations ard Operator Interface in Nuclear Power Plants."
1.2.2.7 Evaluation Methods Checklist evaluations were performed on a panel-by-panel basis, Checklist Sections A, B, ard C being completed separately for every panel. Each checklist item was evaluated by means of two numerical ratings: (1) a "compliarr:e factor" irdicating the degree to which the panel under consideration couplies with that criterion, ard (2) a " potential for error factor" representing the relative likelihocd that non-ccepliance with that checklist item could cause or contribute to operator error.
A graded system of compliance evaluations was employed because a simple yes/no judgement of design ccnpliance with a given human factors stardard may provide only limited information when a wide spectrum of actual design effectiveness is possible. Werefore, each panel was rated on a scale of one to four for each checklist item. "One" irdicated full compliance with a given criterion on the panel being reviewed, "two" indicated that the criterion has been "mostly" ccuplied with, "three" irdicated "somewhat" ccepliance, ard "four" indicated total non-ccnpliance. A "zero" signified that the criterion is not applicable to that panel.
The " potential for error factor" was preassigned for each checklist item, based on the work of a task force consisting of approximately thirty Genera 1 Electric ard utility engineers from a wide variety of disciplines. Each item was irdeperdently evaluated by each task force member, based upon his own knowledge ard experience. From this data base, a final value was assigned based upon the statistical f requency distribution of the ratings.
Each rating factor was reviewed ard approved by the Control Room Improvements Committee of the BWROG. %e resulting f actcrs ranged from one to three, "three" indicating "high" potential for operator error , "two" a " moderate" potential, ard "one" a " low" potential for causing or contributing to operator error.
These two rating factors, the degree of compliance assigned by the survey team, ard the predetermined potential for error, were multiplied together to obtain a final Evaluation Product. Dese Evaluation Products were then utilized to provide a cutof f point to determine if a diecklist iten became an HED.
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GULF STATES ITTILITIES COMPANY RIVER BEND STATION The checklist was completed as follows:
x Compliance Factor 4 Evaluation Product = Potential for Error 3 = High 4 = No 2 = Moderate 3 = Somewhat 1 = Low 2 = Mostly 1 = Fully 0 = NA We resultant evaluation products are shown in Table 1.2-1 below:
TABLE 1.2-1 POTENTIAL FOR ERROR 1 2 3 0 0* 0* 0*
i 1 1* 2* 3*
)
1 COMPLIANCE I
FACTOR 2 2 4 6 3 6 9 O I3 4 4 8 12 Note: *Not addressed as HEDs since checklist item was fully compliant (i.e, l
equal to a 1 or a 0) .
Thus, all evaluation products with a canpliance factor greater than "1" were l
addressed in the HED Assessment Phase.
l 1.2.3 System Functions Review ard Task Analysis 1.2.3.1 Purpose 4
i The purpose of the System Functions Review and Task Analysis portion of the i
{
DCIDR is to determine the input and output requirements of the control room crew for emergency coeration ard to ensure that required systems can be
! ef ficiently and reliably operated urder the corditions of emergency operation by available personnel. %is was accomplished by performing an analysis of l tasks contained in the RBS Emergency Operating Procedures (EOPs) .
l The steps that make un the System Functions Review and Task Analysis are shown in Figure 1.2-1 a nd a re described below.
1
- O l-11 i
GULF SIATES UTILITIES COMPANY RIVER BEND S'IATION O
Identify Plant Safety-Refsted Systems and Functions lf Define Representative Scenarios and Related EOPs for Analysis 1f identify Residual Tasks lf Develop Task Analysis Worksheets 1I Conduct Wa'kthroughs of Scenarios 1I Verify Task Performance Capabilities Y
Validate Control Room Functions i
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9 Figu re 1.2-1. Systems Functions Review aryl Task Analysis Steps 1-12
Gt1LP STATES UTILITIES COMPANY RlVER BEND S1RTION 7~
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1.2.3.2 System Functions Descriptions Plant systems ani subsystems in the RBS control room that the operator munt access during emergency operations were identified. Existing plant documentation (i.e., River Bend FSAR) relating to safety systems served as a crime information source. Figures 1.2-2 and 1.2-3 are lists of the River Bend Station safety-related ard non-safety-related systems respectively.
Descriptions of the functions for each of the systems identified above were prepared. These system descriptions included e The function (s) of the system e Under what conditions the system is used e A brief explanation of how the system operates The description of systems functions in this manner served as a reference base for subsequent task analysis. In addition, the systens list was used to assist in the selection of operating scenarios for each walk-thrcugh.
1.2.3.3 Scenario Development The BWROG Emergency Procedures Guidelines ard the list of RBS safety-related systens were used bo define a set of scenarios which adequately sample various emergency conditions ard the plant systems ard system functions used in those
(~' conditions. 'Ihe related RBS plant-specific EOPs we re identified as well in this step.
The scenarios selected for task analysis are listed in Table 1.2-2. In addition, a brief narrative description of each scenario (Appendix F) was preoared that established the limits and conditions of the events to be a nalyz ed. The descriptions included:
e Initial plant conditions e Sequence initiator e Progression of action e Final plant conditions e Maior systems involved 1.2.3.4 Residual Task Identi fication Residual operator tasks (unique tasks) from the plant-specific EOPs not cove red in the scenarios we re identified and later analyzed for associated information and control requirements. The analysis of residual tasks were done to ensure that all operator interfaces had been examined even if those interfaces were not exercised in the sample of emergency scenarios selected for validation. Verification of equipment availability ard suitability were performed for these residual tasks as well as for tasks embedded in the emergency scenarios.
O l-13
GULF STATES (frILITIES CDMPANY RISFER BEND STATION O
- 2. Emergency Core Cooling Systems (ECCS , Ats , HPCS , LPCS , RHRl)
- 3. Containment and Reactor Vessel Isolation Control (CRVICS)
- 4. Main Steam Isolation Valve Positive Leakage Control (MSIV)
- 5. Standby Gas Treatment System (SBGT1
- 6. Containment Canbustible Gas Control (CCGC) 7 Reactor Plant Ventilation System (HVRl)
- 8. Residual Heat Removal - Suppression Pool Cooling Mode (RHR2)
- 9. Standby Service Water (SWP1)
- 10. Control Building Ventilation (HVC)
- 11. Standby Service Water Pump House Ventilation System (SSW-HVAC) 12 Auxiliarv Building Ventilation System (HVRS)
- 13. Fuel Building Ventilation System (HVR6)
- 14. Reactor Core Isolation Cooling System (RCIC) 15 Residual Heat Removal System (RHR3)
- 16. Standby Liquit Control System (SLC) 17 Remote Shutdown System (RSS)
- 19. Safety Related Display Instrumentation (SRD) 19 Recirculation Pump Trip (RP) 20 Leak Detection System (LDSI)
- 21. Neutron Monitoring System (NNG)
- 22. Radiation Monitoring System (RMSI)
- 23. Fuel Pool Cooling System (FPCCS)
- 24. Penetration Valve Leakage Control System (PVLCS)
- 25. Rod Pattern Control System (RPCS)
- 26. Safety Relief Valves (SRV) 27 Control Building Chilled Water (HVK) 28 Standyby Power Support Systems (EGA, EGF) 29 Diesel Generator Building Ventilation System (HVP)
- 31. Diesel Generators (DG A&B)
- 32. Hydrogen Recombiner System (H3)
- 33. Annulus Mixing Subsystem (HVR4)
- 34. Nuclear Steam Supply Shutof f System (NSSSS)
Fiq ure 1.2-2. River Bend Station Safety-Related Systems (Reference PSAR Section 7.1.1)
O l-14
GULF STATES tyrILITIES COMPANY RIVER BEND STATION v
- 1. Annulus Pressure Control System (APCS)
- 2. Nuclear Boiler Instrumentation (B21)
- 3. Condensate Demineralizer System (CND) 4 Condensate System (CNM)
- 5. Condensate Storage, Makeup and Transfer System (CNS)
- 6. Hydrogen Purge System (CPP)
- 7. Control Rod Drive Hydraulic System (CRDH)
- 12. Generator Mydrogen Seal Oil System (GMD)
- 13. Gland Seal and Exhaust System (GSS)
- 14. Containment /Drywell Purge System (HVR2)
- 15. Containment Cooling System (HVR3)
- 16. Instrument Air System (IAS) 17 Main Steam System (MS)
- 18. Offgas System (OFG)
- 19. Rod Control & Information System (RCIS)
- 20. Reactor Recirculation System (RCS)
- 21. Process Radiation Monitoring System (RMS2)
- 22. Reactor Plant Camponent Cooling Water System (RPCCW)
- 23. Reactor Water Cleanup System (RWCU) 24 Normal Service Water Systsc (SWP2)
- 25. Main Turbine Lube Oil System (TML)
- 26. Turbine Plant Camponent Cooling Water System (TPCCW)
Figure 1.2-3. River Bend Station Non-Safety-Related Systems O
l-15 l
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GUrE STATES UTILITIES COMPANY RIVER BEND STATION O
TABLE 1.2-2 RIVER BEND DCRDR/EOP VALIDATION OPERATriG SCENARIOC FOR RSK ANALYSIS D*RDR Scemrios A. Inadequate Core Cooling B. Loss of Coolant Accident (LOCA)
C. Main Steamline Break D. Anticipated Transient Without Scram (ATWS)
E. Remote Shutdown 5:OP Validation (Prelimina ry) Scena rios F. Inability to Determine Water Level G. Alternate Coolant Injection / Steam Cooling H. Stuck Open Relief Valve I. Radioactivity Release J. Secondary Containment Temperature Abnormal K. Secondary Containment Radiation Levels Abnormal L. Secondary Containment Water Level Abnormal M. Core Cooling Without Level Restoration N. ATWS Residual
- 0. Primary Containment Temperature ard Pressure Abnormal P. FPCC Residual O
l-16
RIVER BEND STATION GULF STATES UTILITIES COMPANY
,b 1.2.3.5 Task Analysis Worksheet Develonment Task Analysis Worksheets (see Figures 1,2-4 ard 1.2-5) were developed that indicate the operational steps required in each scerario along with the appropriate information ard control requirements, means of operation, ard I&C present on the control bmeds. We operator tasks were analyzed using plant-specific EOPs as a starting point. Se Task Analysis Worksheets were prepared in the following manner:
- 1. Discrete steps in the RBS EOPs ard correspording EPGs were identified in order of performarce. Rese steps were recorded in the " Procedure Number" column of the Task Analysis Worksheet, ard branching points noted depending on the plant transient being analyzed in the " Scenario Response" column. Note that there may have been more tasks subsequently identified in Step 2 helow than there were procedural steps. In this case, a dash was entered in the column when no explicit procedure step was present in the EOPs ard/or EPGs.
- 2. A brief description of the operator's tasks (in order of procedural steps) was recorded in the " Tasks / Subtasks" column of the Task Analysis For m. Note that there are many more tasks described than are explicitly called out in the procedural step. All tasks, both explicit ard implicit, were documented by SRO subject matter experts ard General Physics human f actors specialists using plant-specific EOPs, EPGs, ard A RBS FSAR.
b 3. We operator decisions ard/or actions that are linked to task performance we re noted in the " Decision ard/or Contingent Action Requirements" column . System functional response is described when appropriate in this c olumn. This set of data also includes branchirG points in the EOPs that determine the outcome of the operating sequence.
- 4. Input ard Output requirements for successful task performance are noted in the "Information ard Control Requirements" column in Figure 1.2-4.
These are typically pirameters, components or precedural information that are necessary for operators to adequately assess plant corditions or system status (e.g., reactor vessel water level, hot leg temperature, reactor coolant system flow, pressurizer pressure, etc.) .
Relevant characteristics for parameter readings or control selection were noted by the Subiect Matter Expert (SME) in the "Information ard Control Requirements Column" in Figure 1.2-4. Primary sources of information ard control requirements for each task were noted on the form in Figure 1.2-6.
We interrelationship between Figure 1.2-4, Task Analysis Worksheet, ard Figure 1.2-6, Sources of Information ard Control 'lequirements Form, is shown in Figure 1.2-7.
- 5. Once the Tasks, Decision Requirements, ard Information ard Control requiremer.ts wr.re specified, the specific instrumentation ard controls (IGC) that the operator required per procedural step were documented.
All I&C needed to either (1) initiate, maintain or remove a system from service, (2) confirm that an appropriate system response has or has not
' occur red , i .e . , f e edb ack , or (3) make a decision regarding plant or 1 -1"1
GULF STATES UTILITIES COMPANY RIVER BEND S'IATION O
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RIVER BEND STATION GULP STATES ITTILITIES CCMPANY
- 1. SCENARIO - operating scenario name ard identifier (ID) .
- 2. PIOCEDURE NO. (RIVER BEND /EPG)
- procedure step number for RIVER BEND EOPs (Emergency Operating Procedures) and for the Boiling Water Reactor Owners Croup generic EPGs (Emergency Procedure Guidelines) .
- 3. 'mSK/SIErmSK - a description of the crew member task / subtask in the operating sequence.
- 4. SCEN. RESP. - a notation designating decision points or branching information needed for correct task execution for the operating scenario (as defined in the operating scenario description) .
- 5. CREN NIDSER - the crew member who performs the task.
- 6. IDC - the location where the task is performed.
- 7. IBCISION AlW/OR ACTION REQUIRBRETS
- any contingent decision ard/or action requirements that are linked to task performance.
- 8. INPOIDEATION Alm CONTROL REQ.
- the information ard control requirements for successful task performance (derived independently of the actual I&C in the control room) . Noted in this column are (1) the system involved (2) the parameter, component in procedure needed ard (3) the relevant O characteristics of the parameter or component referenced for the operator to execute the task.
- 9. NEANS - the actual means (e.g. switch, meter, etc) used by operators to perform the task in the control room.
- 10. IEC IDENT. (PANEL /NO.) -
the actual instrumentation ard controls (I&C) identified from walkthroughs that the operators used to perform the task. ne IEC is uniquely identified using a PANEL number ard Equipment Number (NO.).
- 11. VERIFICATION (AVAIL./ SUIT.) - columns that irdicate the availability ard suitability of the Instrumentation ard controls (IEC) needed for task pe r formance. %ese columns would contain a "yes" or "no" answer which is arrived at through a Verification Process Flowchart. Entries that are a "no" are detailed further on an HED Suitability Assessment Form.
- 12. SPDS - the presence or absence of the IEC ard associated characteristics on the Safety Parameter Display System is noted in the "Y" or "N" columns.
- 13. COGEENTS - any ecmunents related to scenario execution, task performance, or the accompanying task requirement columns (the balance of the task analysis worksheet)
O Figure 1.2-5. Task Analysis Worksheet Fields (Columns) Definitions l 1-19 l l
gg smTES tyytLITIES CWU RIVER BEND g7ATION te ii sa 4 1 6 i ( 8 0 5 g 1 U i e o h i a z 8 5 4
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GtHE .TPATES UTILITIES CGIPANY RIVER EEND STATION O system status were listed. Se "Means" column refers to how the information ard control requirements are presented on the control boards (e.g . , switch , meter, etc.) . Se "IEC Identification" column provides the specific panel nusber ard identification number of the control or instrument. For each I&C (equipment) identified in this column, the equipment characteristics (parameter, range, units, scale, and/or control states) are noted on the form in Figure 1.2-8. The interrelationship between Figure 1.2-4, a Task Analysis Worksheet, ard Figure 1.2-8, I&C Equipment Otaracteristics, is shown in Figure 1.2-7. %ese characteristics are used in the Verification of ! IEC Availability and Suitability Phase of the DCER. , l It in isportant to note that Steps 1 through 4 are empleted on the Task Analysis Worksheet using irdeperdent sources of data (Figu- 1.2-4) other than i the actual IEC present in the control room. Step 5 essentially completes the first step in the verification process to identify whether or not the j necessary I&C for task performance is available in the control room. he remaining columns of the Task Analysis Worksheet were utili::ed during the Verification of Task Performance Capabilities, which is described in Section j 1.2.4. Rese columns are briefly described below: i 6. Verification column (used during VsV phase)
- " Availability" of the necessary I&C for successful operator task performance is noted by a check in this column; " Suitability" of the IEC 4
to meet the information ard control requirements of operator task is i noted by a check in this column. 1
- 7. Comments / Candidate HEDs Consnents or candidate HEDs can be noted in this column during any step of i
the Task Analysis of VEV phases. Data for HEDs will be entered on an HED form ard into the emputerized database, t l he Task Analysis Worksheet thus serves as the cmplete record of operator tasks, decisions, information and control requirements, and I&C availability ard suitability verification during the selected emergency operating sequences. his record is developed through the series of j steps described above. i j 1.2.3.6 Task Analysis Database i All task analysis data was entered into the River Bend DCRDR cguterized
- database. We forms that are used in collecting the data ares e Task Analysis Worksheet e Information and Control Requirement Sources e I&C Equipment Characteristics i
These forms collectively makeup the complete database fields that are defined for the rask Analysis, Verification ard Validation phases of the DCER. Se interrelationships between the discrete columns in the forms (database 1-22
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GULF STATES UTILITIES CCEPANY RIVER BEND STATION 4 fields) is shown in Figure 1.2-7. %e Task Analysis Worksheet is the master record of task data ard the verification phase decisions made about the task data afd associated I&C Equipment Garacteristics. In the canputerized database, each data field (column) is represented only once with all data being keyed to one -- more fields of the Task Analysis Wor k sh ee t. We other two forms are linked by either the Task Analysis Worksheet (TAW) Scenario a rd Task I.D. (see Information and Control Requirements Form) or by the I&C Equipment Identification columns (see I&C Equipment Garacteristics form) . We DCIUR team member can enter the database by referencing either the Scenario-Task ID or the IEC Identification (Panel No.) keys. In this way, the database allows flexibility to search both operator task data ard equipment data. 1.2.3.7 Control Room Inventory The function intended fcr a control room inventory in the DCRDR is to determine whether the instrumentation ard controls needed to suppcrt operation urder emergency conditions actually exist. (See INPO NITTAC Implementation Guideline.) This function was accomplished as part of the task analysis effort ard the related verification ard validation efforts. ne determination of Isc availability is described in Section 1.2.4.3, I&C Availability. Equipment characteristics associated with the I&C (Equipment) identified in the task analysis worksheet se re roted using the form in Figure 1.2-8. In addition, a canplete set of control board photographs was taken to provide an as-built inventory of the RBS instrumentation ard controls during the DCRD R. 1.2.3.8 Videotape Data Analysis Methcdology Videotapes of the control room crew performing the operating scenarios were taken in the River Berd Simulator. In analyzing the videotapes of the scenarice U t he DCRDR, the primary concerr was the recordirv3 of instruments i a ntrols used by the operators in each task. Each time an operator performed a di.s . att .. , 2n , (e.g., observing a meter, positioning a control, inf orming othei operatcrs of plant status) , the analyst filled in the Task Analysis Worksheet as described in the Systems Function Review ard Task Analysis Procedure. We fields ccrapleted in the videotape analysis were e Task performed l e Control room crew member e His lccation e Means used to perform the action (e.g., meter, discrete control, verbal, continuously variable control) e I&~ Identification numbers of all couponents used (includes Panel No. ard np . No. ) 1-24 i l
RIVER BEND STATION GULF STATES UTILITIES COMPANY we list of components actually used was detailed further on an Equipment Characteristics form (see Figure 1.2-8) . His form includes IEC characteristics associated with the IEC identified on the Task Analysis Worksheet as follows: e Display characteristics
- Range Units
- Scale type e Control characteristics States Direct /Irdirect once the task analysis data reduction was complete, any new tasks identified were subjected to analysis f a irdeperdent information ard control requirements by a subject matter expert (SME) . We SME did not see the actual I&C used by the operating crew.
The canpleted Task Analysis Forms were then ready to be used in the Verification of Availability and Suitability Phase of the DC10R. 1.2.4 Verification of Task Performance Capabilities 1.2.4.1 Purpose p() The purpose of the Verification of Task Performance Capabilities is to systematically verify that the instrumentation ard controls that were identified in the task analysis as being required by the operator ares e Present in the main control room o Effectively designed to support correct procedure performance 1.2.4.2 Meth od ology he Verification of Task Performance Capabilities utilized a two-phase aoproach to achieve the purpose stated above. In the first phase, the presence or absence of the instrumentation ard controls that were noted in the task analysis were confirmed. his was to be done by comparing the requirements in the "I&C Requirements" column of the Task Analysis Form to the actual I&C manipulated by the operator during the validation scenarios (see i Figure 1.2-9) . r 1.2.4.3 I&C Availability The presence or absence of required instrumentation ard controls were noted in j the " Availability" column of the Task Analysis Form. If it was discovered that required instrumentation ard controls were not available to the operator , [ any such occurrence was identified as an HED ard documented accordingly on an HED form. l O ; l 1-25 l
GUTE SLATES ITPILITIES COMPANY RIVER BEND S'IATION O Flow Chart of Decision Process foe Verifying Equipment Suitab4hty For every task in the task analys;s. ver-ify that the equipment specified is suitable to meet the demands of emer. genCy contingenCtes. CRITERIA FOR DECISIONS one, the equipment
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provide appropriate NO HF E/ CPS information/ feedback
- Information displayed to appropriate go, gg, modahty (visus! vs additory) I talk ?
8 Appropriate parameter displayed 8 Display of quantitateve and/or Qualite- any other tive information appropriate for task equipment Yg$ e Otscrete/ continuous control functions swailable which appropriate provides appropriate
- D4 splay of t'ead ieformation availatWe information/
when appropriate feedback ? YES p Does the eowepment provide actual
- NO system status information? II l&C *(direct) e Actual system' equipment status infor-rnation is provided ratner than mdirect isany inf ormation (e g , demand vs. va've other equipment posit.on for cont'ohers. d. rect vs m- YES avaitat8e that direct measure of flow m system 10001 provides appropriate information and reflects actual system NO status?
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HF E/ OPS /l&C o Equipment provides appropriate pre- g, cision and range of control the equipment NO e Scaie units are constent with the de-gree of precision needed useable? I I Y
- Scale range spans the expected range of operational parameters HED e Values orsplayed are n a form immed -
YES stely useatde *4 con ers+on v U l I EQUIPMENT MEETS SulTABILITY REOutREMENTS l FOR TASK PERFORM ANCE ca.eito l Figure 1.2-9. Flow Chart of Decision Process for Verifying 9l: Equipment Suitability 1-26
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RIVER BEND STATION
' GULF STATES UTILITIES CGtPANY
'O he result of the verification of Isc availability was a main control room . inventory (in the Task Analysis Form column labelled "IsC Requirements") of t instrumentation aM controls needed to support operation under emergency ! cond itions. f 1.2.4.4 Isc Suitability E The second phase determined the human engineering suitability of the required l instrumentation and controls by comparing them against the criteria shown on Fiqure 1.2-9. For example, if a meter utilized in a particular procedure step existed in the main control roan, that particular meter was examined to j determine whether or not it had the appropriate range and scaling to support l the operater in the corresponding precedural step. If the meter characteristics were not appropriate, it was noted by placing a check in the "Not Fully Useable" column of the Equipment Suitability Form (see Figure 1.2-10). his type of occurrence was defined as an HED and documented accordingly on an HED form. If the equipment characteristics were appropriate then it was noted by j placing a check in the Suitability columri on the Task Analysis Form 1.2-4. T 1.2.5 Validation of EOPs and Control Room Functions /. i As will be discussed later in Section 4.1, GSU has successfully integrated the RBS EOP Validation Program with the DCER Validation of Control Roca Fu nctions. His provided a coordinated effort to accomplish these related activities. 1.2.5.1 Purpose a The purpose of the Validation of EOP and Control Room Functions step in the DCRDR process was to determine whether the functions allocated to the control room operating crew could be accomplished effectively within (1) the structure of the RBS specific EOPs and (2) the design of the main control room as it ex isted . Additionally, this step provided an opportunity to identify HEDs that may not have become evident in the static processes of the DCER, for 3 example, in the control room survey. The purpose ard obiectives of the EOP Validation Program are listed in NUREG-I 0899 (Reference Q) , Guidelines for the Preparation of Emergency Operating . Pr ocedu res. ] 1.2.5.2 Methololoav for DCRDR and EOP Validation ! This section provides an overview of the steps involved in the simulator j validation of EOPs ard Control Room Functions. First, scenarios were ! developed that challenge critical safety functions that must be restored using the peccedures. Secord, expected operata actions were delineated for each l scenario so that a hypothetical teglate was available for cogarison to what actually happened during the simulator run. Next, the scenario was simulated l and the operating crew used the EOPs to restore the plant to safe conditions. We operatcrs were then debriefed to provide an important source of information for evaluating the procedure set. Following the debriefing, operatms walked through the scenario in slower than real time to evaluate the O ! 1-27 1 1 i _ _ _ . - - - ~ _ - _ . _ . _ . . _ _ , _ - _. - _ _ _ _ _ _ _ _ _ ... _ __ - ..-.,, _ __. _ _ _. -
GULF STATES ITTILITIES COMPANY RIVER BEND SMTION O EQUIPMENT SUITABILITY HEDs Completed by: Date: gsc n,,,c, g,,. Not TAW REF. Status Equipment Info. not F uity Comments Appropr, ate No, E'"- Task i D. Ident. Useable Prowded O i Figu re 1.2-10. Equipment Sultability ED F2m 1-28
GULF STATES UTILITIES CCMPANY RlVER CEND STATION O operational aspects of the control room design. Se videotapes ard generated I documentation were then reviewed for dynamic performance problems ard procedural error. Procedural errors were written @ on procedure discrepancy forms for GSU resolution and dynamic control room hardware discrepancies were written @ as HEDs. We following sections provide further details of this process. 1.2.5.3 Methodoloov for Simulator Validation A scenario is a collection of selected pre-planned events used as a framework for validation. A scenario includes the initial plant corditions, action sequences ard expected outcane for a hypothetical plant emergency. To the extent possible, each scenario was plannel to include a unique set of paths through the EOPs in order to exercise as much of the procedures as possible, while some of the ebjectives of procedure verification / validation can be evaluated without reference to events, the usability of EOPs can only be fully evaluated in the context of successfully controlling emergency events. Thus, , scenarios were constructed to challenge the procedures based on selected events. 7 A systematic procedure for choosing events with which to construct a scenario provides greater assurance that a representative sampling of events has been chosen. One way to sample events is to select ones that challenge the peccedures to maintain critical safety functions of the plant. We metho3 ology presented in this section required the validation team to develop multiple scenarios each capable of challenging one or more of the critical safety functions addressed in the EOPs. He development of scenarios was a multistep process ard is described in the following paragraphs. The first step in the development of scenarios was to define which critical safety functions were to be challenged. Once the critical safety functions had been identified, the validation team defined the bourdary corditions within which the scenario would be exercised; specifically, the validation team defined the initial corditions ard final conditions of the scenario. Initial corditions were defined as those corditions existing (i.e., plant s tatus) inmediately prior to the event intended to challenge critical safety functions. Final corditions were defined as those corditions representing a safe ard stable plant. Restoration of the simulator to a state consistent with these final corditions was the ultimate criterion for validation. We next step involved analyzing the BWROG EPGs to identify those elements representing the desired final corditions. It was not necessary to identify initial conditions on the EPGs, as all EPGs are entered from the same element. We EPGs were further analyzed to define the hypothetical event path of the scenario in progressing from the initial to final conditions. This hypothetical event path was then highlighted on the EPGs. Finally, the progression of action ard scenario initiator (s) were defined. We progression of action is a chronological description of the events highlighted on the EPGs as well as anticipated operator actions. We scenario initiator (s) is that event which degrades plant status to a level requiring entry to the EPGs. O 1-29
GULF STATES ITTILITIES COMPANY RIVER BEND SMTION O Following development of scenarios by the validation team, scenarios were reviewed by River Bend sinulator instructors to ensure that simulator performance required by the scernrios was consistent with simulator capabilities (i.e., to ensare that simulator modeling was adequate to successfully exercise the acerario) . Where inconsistencies were noted, the scenario progression of action was modified as necessary, as were the segeunce initia tor (s) ard timing of malfunctions. It should be roted that these modifications did not redefine the scenarios; they only modified the specific simulatcc functions used to successfully implement the scenarios. 1.2.5.4 Delineation of Expected Operator Actions The scenarios developed by the validation team were of sufficient ccuplexity to require the use of multiple procedures to restore the plant to a safe and stable condition. Werefore, the validation team defined a path through the procedures which was consistent with the path defined on the EPGs. R ese specific procedural steps ard anticipated operator actions associated with these steps were documented to aid the validation team in evaluating the procedures against the validation criterion. It should be noted at this point , that each scenario was defined by a unique path through the EPGs ard a corresponding set of procedural steps. Prior to exercising the scenarios, it was recognized that at each branch point in the procedures, the operator was presented with one or more options. %e consequence of such options was that the operator's actual path through the procedures might differ fran the path defined by the validation team. Section 1.2.5.6 describes the procedure for dealing with such deviations. The format presented in Figure 1.2-4 was used by the validation team, both in defining the expected operator actions ard evaluating the scenario. W is format identified o A procedure set for the scenario ard specific steps from each procedure o Operator actions which follow an expected path through the scenario e Description of specific points at which differences between the control room ard simulator may inpact cperator performance (see Section 1.2.5.5 of this report) e Description of discrepancies between actual performance ard expected l performance e Categorization of discrepancies Following the ccupletion of simulator exercises, actual operation actions were ccupared with the EPG elements to identify any discrete EPG elements or groups of elements that had rot been exercised by scerarios. As appropriate, additional scenarios ard residual tasks were generated ard executed in the simulator to ensure that all EPG elements ard all procedure steps were evaluated . Residual tasks (i.e., those EPG elements not amenable to s imulation) were evaluated verbally. 1-30
GULF STATES ' UTILITIES CGEPANY RIVER EEND STATION t O 1.2.5.5 Evaluation of Simulator / Control Rom Differences I A cowarison was made between the simulator and the main control room and occumented in a report (Reference P) to determine significant differences that could affect the scenarios (See Section 1.5.3) . Differences in panel design l were noted, where appropriate, when operater actions were delineated so that attention eculd be given to the differences during the simulator runs and subsequent analysis. Photographs of the main control room panels were attached to the simulator panels at the appropriate locations to depict the dif fe rences. Operaters were familiarized with these differences prior to t performing each scenario. 1.2.5.6 Performance of Simulator Runs he operating crew chosen for the simulator runs was familiarized with the latest procedures through training. He crew was not briefed on the actual scenarios to be run. Se operators were, however, briefed on the purpose of the validation. It was made clear to them that it was not their performance < being evaluated, but the performance of the peccedures and hardware. Each scenario was simulated separately (in real-time) with a debriefing session and walkthrough after the run. During the run, validation team members were observers; at a minimum, two training /cperations personnel and I one human factors specialist participated. Some notes were recorded on the operator action forms, but excessive note-taking was avoided so that the observers were free to observe. Se tape record of the scenario permitted the observers to analyze occurrences later (see Section 1.2.3.8) . In addition to the videotape of the scenarios, ceguter printouts fran the simulator of switch, parameter, and annunciator status assisted in the analysis of the tapes if the observers were uncertain of an action because of camera placement. During the simulator runs, if the crew took an expected alternate path that was as correct as the expected path, they were allowed to continue 4 uninterrupted. If the operating crew momentarily took an unexpected alternate path that was an incorrect path, but were able to get back on the correct path using the procedure within a reasonable amount of time, the simulation continued undisturbed. If, howewer, the crew took an unexpected alternate path that was incorrect ard showed no sign of recovering, the simulation was j stopped. If an obvious, remediable error was involved, e.g. a page of the procedure was missing, the problem was 1ccerected and the run started again where it went astray. j 1.2.5.7 Debriefino of Operators ; L The operator debriefing session was conducted inmediately after each scenario run on the simulator. The connents of the operatcrs who participated in the
- exercise provided one of the most imortant sources of information for i evaluating the procedure set. Operater actions which did not lend themselves to direct observation, such as symptom diagnosis er conversion of displayed ;
j values were described by the operators during the debriefing. De operators' O 1-31 i J f _-__..---_-.,,,-..,._.,._-...,--,..__,_-__--m. - m.- _, _ ~ r_..,___-., . , . - - , . - . . - - _ _ - _ _ ~ , . . , , , , _ - , .
GULF STATES UTILITIES CCMPANY RIVER BEND SMTION O comments also contributed to greater accuracy in arnlyzing deviations from expected operator actions which occurred during the scenario. 1.2.5.8 Scenario Walkthroughs he purpose of the walkthrough was to evaluate the operational aspects of control room design in terms of control / display relationships, display grouping, control feedback, visual ard ccanunication links, manning levels ard traf fic patterns. Af ter the operator debriefing was ccznpleted, the operators were requested to perform a walkthrotsgh of the scenario in slower than real time. During the walkthroughs, the operators noted any errors, such as inproper step sequencing or branching, that occurred on the Task Analysis Forms. These errors were traced back to the EOPs for investigation to ascertain whether the error occurred because of a procedural problem. If a procedural problem was discwered, it was documented ard later written up on peccedure discrepancy forms. This documentation will be used in respordirg to Item 7 of Supplement 1 to NUREG-0737, which involves the Upgrade of Emergency Operating Procedures. This documentation will also be useful in any type of long-term training program which involves procedures upgrades. The peccedure discrepancy forms were submitted to GSU Operations which reviewed them ard took the appropriate action in accordance with their EOP Verification and Validation Program. The operators who performed the scenarios reviewed the Task Analysis Worksheets along with a human f actors specialist. The operators were asked to note any errors or problems that were encountered in the walkthroughs ard to expourd upon the source of the errors or problem. Any dynamic performance problems us. overed during this phase were documented as HEDs ard reviewed in the Assessment Phase. Once the events had been analyzed to extract the information noted above, Link Analyses (see Figures 1.2-11 through 1.2-18) , which trace the movement patterns of the operating crew in the main control room, were prepared to assess whether the control room layout hirdered operatcr movement while performing the events. The final step in the validation process was to have a reactor operator , who did not walk or talk throts)h the events, review the analysis in an attempt to uncover any cperator task difficulties from an irdependent objective viewpoin t. To document the validation process, a Systems by Scenarios matrix was completed to account for all systems functions ard associated operator tasks examined during emergency cperations. A matrix was ccrupleted for both safety-related and non-safety-related systems (see Figures 1.2-19 ard 1.2-20) l respectively. i i 1-32
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I l RIVER BEND STATION GUw PRATES UTILITIES Ct3tPANY s ! 1.3 AssEsssWPr AND INFLEMENMTION PMASE i The review team assessed identified discrepancies and recessmended actions for j their resolution in an iterative review process. Procedures used to assess and categorise NEDs and recomunending corrective actions are contained in this ; section. In addition, the implementation sche &le, the method of verification l r of design improvements ard an ongoing human factors maintenance plan are presented. l l 1.1.1 NED Cateeorisation ) 1.3.1.1 Determinine the I==Etance of NEDs f The MED assessment process is shown in Piqure 1.3-1. Se impot tance of an RED , was assessed on the basis of the potential for operating crew error ard its r potential ispect on safety. his was accoglished by analysing and evaluatin9 3 the problems that could arise from the identified NEDs. I i ' Muman factors specialists assisted OBU personnel in assessing the MEDs that l j were identified during the previous phases of the DCmR in a manner similar to guidance given in draft NUREG-0801, " Evaluation Criteria for Detailed Control I l Room Design Review (Reference E) ." he two primary criteria presented in I NUREG-0801 ares (1) whether or not the MED has resulted in a documented error or provides the potential for operator error, ard (2) what ispect the MED has on plant safety. Each of the criteria is discussed separately below. i 1.3.1.2 coerator Error r ) i Information from the operating experience review was used to help assess j whether an HED resulted in an operator error or provided the potential for j operator error. If an NED was the result of a documented error , for example in an LER m identified in an operator interview, then the MED was l f automatically assessed as having an effect on operator performance. MEDs not associated with documented errors were systematically assessed to determine their inpact on operating crew performance. Information gathered during the J survey of operating personnel was considered regarding problems that resulted ;
! in, or provided the potential for , operator error.
L HEDs that might affect operating crew performance were subjected to a series j of statements or questions, as shown in Table 1.3-1. Other performance shaping f actwa such as training, operator experience, proce&re adequacy and situational requirements were considered. We responses to this line of l questioning aided the reviewers in identifying those MEDs which degrade 1 operating crew performance enough to cause, or contribute to the potential i for , ope ra tor e rr or. This tedinique relied on the evaluators' judgment. i i :
- 1. 3 .1.3 Plant Safety Impact _
i NEDs considered to have resulted in documented errors or to have contributed to the potential for error were assessed according to impact on plant safety { based on the following criteria: !O l I 1-43 1 r,vw-,,,--,,-w -+----~~%.------w-------,y-----,m.-,m,,-~y---,.,-g-,,p_ ,my,._,,,,r,- -.w ,-,_ w ,-- ,
GULF 9:ATES UTILITIES COMPANY RIVER BDID S M TION O identified HEDs 1f Assessment Prioritization If lf Enhancements Modifications e lf Establish initial Ccerective Actions lf Integrate with Other improvement Progtoms 1I Finahze Corrective Actions O Pigure 1.3-1. HED Assessment Process
CULF SMTES IFFILITIES COMPANY RIVER BEND SMTION p kj (1) An unsafe condition may result. (2) Violation of a Technical Specification may result. EDs were assessed as to their impact on safety by subjecting each to a series of statements or questions, as shown in Table 1.3-2. The responses to this series of questions aided the reviewers in identifying those HEDs which impact plant safety. Also, task element tables from the plant-specific system review aM task analysis were consulted as an aid in establishing consequences of error for HEDs found during verification and validation phases. As before, the technique relied on the evaluators' judgment. l 1.3.1.4 Categorizing HEDS into Levels of Significance Categories in which HEDs were grouped are defined below. This categorization is an aid to the revleur in further assessing the importance of HEDs as well as providing a means of assigning priorities to HEDs for corrective action. The method allows for distinguishing between those discrepancies that are known to have contributed to operator error and those that have been evaluated to have potential for contributing to operator error (see Table 1.3-3). The categories ares Priority I - Safety Related
- Documented ard/or High Potential Error O Safety Related V Priority II -
- Iow Potential Error Priority III - Not Safety Related
- Documented aM/or High Potential Error Priority IV - Not Safety Related Iow Potential Error The HEDs were further examined for their cumulative or interactive ef fects.
If such ef fects wre found, they wre @ graded accordingly. In addition, when an HED was classified as not safety related, but was critical to safe plant operation, the DCIOR assessment team considered @ grading the HED to a higher priority. Table 1.3-3 provides a sununary of the HED categories to assist in
; the categorization process.
The primary purpose in categorizing the HEDs was to assist in assigning priorities to HEDs for resolution. HEDs having the most significant impact on I plant operations, i.e., Categories I ard II, would need resolution first. The review team assessed ard categorized HEDs in preparation for their resolution. i O 1-45
CILP STATES ITrILITIES CatPANY RIVER BEND STATION O TADLE 1.3-1 HED POrENTIAL FOR ERROR EVALUATION CRITERIA (Modified fem NUREG-0801) To what extent do you agree with the following?
- 1. Wis discrepancy will cause urdue operator fatigue.
- 2. This discrepancy will cause operator confusion.
- 3. This discrepancy will cause operator disemfort.
- 4. This discrepancy presents a risk of injury to control rom personnel.
- 5. mis discrepancy will increase the operator's mental workload (for example, by requiring interpolation of values, remembering inconsistent or unconventional control positions, etc.) .
- 6. This discrepancy will distract control com personnel fem their duties.
- 7. This discrepancy will affect the operator's ability to see or read accurately.
- 8. Bis discrepancy will af fect the operator 's ability to hear correctly.
- 9. Bis discrepancy will degrade the cperator's ability to communicate with others (either inside or outside the control room) .
- 10. This discrepancy will degrade the operator's ability to manipulate controls correctiv.
- 11. This discrepancy will cause a delay of necessary feedback to the ope ra tor .
- 12. Because of this discrepancy the operator will not be pecnidad with positive feedback about control task (s) .
- 13. 21s discrepancy violates control room conventions or practices.
- 14. This discrepancy violates nuclear industry conventions.
- 15. 21s discrepancy violates societal stereotypes.
- 16. Operators have attempted to correct this discrepancy themselves (by self-training, temporary labels, " cheaters," " helper" controlo, ccnpensatory bcdy movements, etc.) .
- 17. Tasks in which this discrepancy is involved will be highly stressful (i.e., highly time constrained, of serious consequerce, etc.)
9 1-46
. = _ - - _- . _ _ - _ _ _. . .- . __ . _ - - - = _ _ . . - _ _ _
GtIE SRTES (FFILITIES COMPANY RIVER BEND S M TION TABLE 1.3-1 (Continued)
- 18. This discrepancy will lead to inadvertent activation or deactivation of con trols.
- 19. If this discrepancy causes a specific error, it is probable that arother error of equal or more serious consequences will be committed.
, 20. This discrepancy is involved in a task which is usually performed concurrently with arother task (e.g., watching water level while manipulating a throttle valve control).
i I 1 i ! i
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! I I
i lO i l- 1-47 1 l t
GULP SIATES ITTILITIES COMPANY RIVER BEND STATION O TABLE 1.3-2 HED PLANT IMPACT EVALUATION GITERIA To what extent do you agree with the following:
- 1. This discrepancy involves controls or displays that are used by operators while executing amergency procedures.
- 2. It is likely that the error caused by this HED would result in
- a. A violation of a technical specification, safety limit, or a limiting condition for operation.
- b. The umvailability of a safety-related system neeSed to mitigate transients or system neeSa3 to safely shut down the plant.
- 3. %is discrepancy involves controls or displays that are part of an engineerst safety function or are associated with a reactor trip function.
- 4. %is discrepancy involves control or display problems that would not be readily identifled or corrected by alarm, interlocks or other instruments.
g
- 5. %is discreparcy could cause an event that readily develops into an ANS Condition II, III or IV event without other failures occurring.
O
OtXE SIRTES tFFILITIES Ct39ANY RIVER EEEED SMTION lO TABLE 1.3-3 NED PRIORITIIATION MhMIX Error Potential Documented and/or Low Potential High Potential Error Error ii ts a 3m I 11 O n d .g Ili iv
.ge O
1 - 49
GULF STATES UTILITIES CCMPANY RIVER BEND STATION O To reach a consensus concerning category assignment among DCBDR members, the following approach was used. All HEDs were categorized independently by DCRDR members. We first round of categorization results were summarized by the DCRDR Review Team Leader to determine the distribution of category assignments per IED. For all IEDs in which one or more DCIOR members categorized that HED as a "I," a meeting was held with all evaluators to determine the actual priority. For all remaining IEDs, the Review Team Leader ard Human Factwa Specialist determined the predminant conservative category (i.e., II through IV). We predominant conservative category was irdicated for each IED and results redistributed to the evaluators. Each evaluator had the opportunity, if desired, to defend his category choice if it deviated fran the predominant ca tegory. If no canents were received, the predominant category became the consensus. For HEDs for which comments were received, a meeting was held with all evaluators to determine which category would be assigned. h e evaluator that had provided comments earlier would be allowed to defend his choice. he final choice was made at that meeting by a vote of the attendees. 1.3.1.5 Cumulative Effects of Cateocry IV HEDs Category IV IEDs were reviewed by the DCRDR team with recomendations ard actions generated using the same process as fcr Category I-III IEDs. The potential cumulative or interactive effects of Category IV IEDs were further examined by sorting these IEDs on the basis of panel / system using the cmputerized database management system. We HEDs were then reviewed on a within-panel / system basis to determine (1) how many Categcry IV's existed and (2) the extent to which they cumulatively increase the potential for error on that panel / system. A sumary tabulation of Category IV HEDs is provided in Table 1.3-4. In those instances where there were more than three (3) Category IV HEDs per panel, the sinularity of those IEDs was assessed by the DCRDR team leader ard the lead hums. f actcrs specialist. If the HEDs were similar in either operation of the system, checklist area or in human performance modality (i.e., all visual or auditory moda lity) , the IEDs were considered to have a potential interactive effect. %e DCRDR team leader then upgraded the IIED(s) to at least one higher priority ratirn only if there was "no action" recomerded previously by the whole DCRDR team ard GSU management. If the IEDs were to be corrected, no upgradirn of prioritization was done. 1.3.2 RED Resolution 1.3.2.1 Recomenda tions for Resolution General Physics provided recomendations to resolve each HED documented during the review. Questions addressed by GP in determinirn recommerded actions are included in Table 1.3-5. In selecting recomendations for IED resolution, GP concerned itself with the issues of improvement effectiveness ard assurance that no new IIEDs resulted from the improvement. 9
~ . - . _ , _- .. -- ._ .
GULF STATES IFFILITIES COMPANY , RIVER CEND STATION TRBLE 1.3-4 St999LRY TABUIATION OF CATEGORY IV HEDs Panel / Workstation Total CRT IV NEDs P600 9 P601 7 P604 9 P614 9 P622 12 P623 12 P628 1 P631 1 P632 12 P642 14 P670 7 P672 7 P680 49 P908 44 P845 14 P861 1 P863 24 P869 8 O PM0 SPDS 3 3 COMPtFfER 1 GENERIC 15 O 1-51
GULF STATES UTILITIES CCMPANY RIVER BEND STATION O 1.3.2.2 Evaluation of Recommenditions
- 1. Engineering Feasibility ard Scope Review Upon receiving the list of HEDs ard associated recommendations for resolution, action by DCRDR Engineering Representatives, with Operations input, was necessary to decide how each HED would be r esolved . %e Engineering Representatives, supplemented by other members of the groups, performed feasibility ard scope reviews on all recomenda tions.
In evaluating the recomendations, a line of questioning similar to that in Table 1.3-5 was used. Additionally, other plant-specific questions were addressed, nese questions are listed in Table 1.3-
- 6. Team members had to be certain that implementing changes in the control room enhanced, rather than degraded, reactor safety and normal plant operations. We results of the engineerirs review were then forwarded to all DCRDR team members.
- 2. DCBDR Team Review To develop a final list of HEDs ard planned corrective actions required several iteratione of review. We first phase was the distribution of HEDs afd reccaner ded solutions to members of the DCIDR team. Team members obtained input from their respective departments. Subsequently, several meetings were scheduled to obtain consensus on selecting the optimal solution for each HED. Atterdee s had the opportunity to cuggest alternative solutions ard the basis for their choice.
From these meetings, a revised list of HEDs ard proposed corrective action was tabulated ard redistributed to the same DCIUR team members. If disagreements over particular items still existed, that disagreement was voiced to the DCIUR Review Team Leader ard arother meeting was scheduled. 1.3.2.3 Management Approval of HED Resolutions When consensus was reachei, the proposed corrective actions ard cost estimates we re tabula ted a rd f orwa . ded to GSU management for review ard approval. Mansgement authorization to proceed with inplementation of the corrective actions was necessary before the Sum:nsry Report could be submitted to the NRC. For those HEDs in Category I, II, III, or IV in which a decision not to cor rect, or only partially correct, was made, justification was required. Management personnel, as well as evaluator s, ensured that adequate justification existed fcr disallowing corrective action. O
GULF STATES 17FILITIES CCMPANY RIVER BEND STATION O V TABLE 1.3-5 HED RESOLUTION CRITERIA In evaluating how to resolve a given HED, the reviewer should ask the following questions:
- 1. Is the HED really a deficiency?
- 2. Due to its unique nature, does the HED require further study or assessment?
- 3. Can the HED be resolved with paint-tape-label enhancements?
- 4. Should the HED be resolved to maintain consintency with control room conventions or standards?
- 5. Is the HED part of a larger or generic HED?
- 6. Is the HED so minor that no physical change is needed and the only action required is to establish operator awareness in routine training?
TABLE 1.3-6 PLANT-SPECIFIC HED RESOLUTION CRITERIA In addition to the questions in Table 1.3-4, a reviewer should consider the following questions when evaluating recommendations for HED resolution?
- 1. Does the recommended fix really address the issue of concern?
- 2. Is the operator 's ability to respond to any plant transient or accident degraded by implementing the reconsnerded change?
- 3. Are there other, more cost-effective methois to resolve the HZD?
4 Is the HED in the process of resolution with an existing design change?
- 5. Could this RED result in significant plant downtime or personnel injuries?
- 6. Could resolution of this HED provide increased operator productivity and morale?
- 7. Is the reccsunendation consistent with present control room characteristics and practices?
- 8. Does the proposed change create any new REDe?
l-53 l i
GULF STATES UTILITIES CCMPANY RIVER BEND STATION O 1.3.3 Imolementation Sch edule ne development of a schedule for modifications to c& rect HEDs was dependent on HED categorization, complexity of the modifications resource requirements, ; and engineering and equipment lead time requirements (Section 2.0) . l l 1.3.3.1 Cor rective f etions Corrective actions were developed to bring the HEDs into agreement with l acceptable human factors guidelines or to counteract tneir effects. The l specific ccerective actions chosen were enhancements, design modifications, i I improved training, revised procedures, er any ccrnbination of the above. We review team developed the corrective actions. References used included NUREG-0700 (Reference G) , EPRI NP-2411 (Reference D) and other human engineering guidelines. The following factors were used in assigning the corrective actions: o Priority rating e Cost eff ectiveness e Extent of carection: Enharcement vs. modification e Ope ra tor per forma nce/re training e Potential for creating new errors e Integration with other control room improvement programs Sufficient detail regarding the corrective action was developed by the DCRDR team to provide adequate guidelines for its subsequent implementation action. 1.3.3.2 Sch edule for Implementation A schedule for implementation of HEDs was developed based on the category assigned, additional engineering study requirements, implementation complexity, and plant scheduling constraints. This schedule is discussed in detail in Section 2.1. Following the submittal of this report, any change in schedule of implementation and the reasons for the change will be submitted to the NRC as a supplement to the summary repor t. 1.3.4 Verification of Design Imorovements ne modified main control room instrumentation and controls design was evaluated to ascure that the selected design improvements, both individually and collectively, adequately correct their respective discrepancies and do not create other safety problems. The verification was accomplished by performing the following o Comparison of the modified main control room design with the control room human factors design conventions document. O
r. l GULF STATES ITfILITIES COtPANY RIVER BEND STATION O e Comparison of the modified main control room design with the instrumentation ard controls requirements identified during the control room survey ard task analysis, a Comparison of the modified main control room design with approved project design criteria (e.g., electrical separation criteria) . 1.3.5 Onaoina Human Factors Maintenance Plan I 1.3.5.1 Description of Design Chance Request Review Process Before ard during the operational lifetime of the River Bend Station, large numbers of engineering changes ard design modifications will occur to the plant's systems ard cmponents. Some of these changes ard modifications may directly impact the RBS control room design. Examples of danges the plant ' typically urdergoes include: o manges to meet FSAR/ License conmitments ard/or to continue constructions e Changes to igrove or enhance operation ard/or maintenance characteristics of a system or cmponents or e Modifications to satisfy an as-built or as-installed condition. Accomplishment ard occumentation of these changes ard modifications dictates the need for a process to maintain control of any change affecting the human facters design review of the control room. In order to maintain control of engineering changes ard design modifications affecting the r.ain control rom, a Design Gange Request (DCR) review process was developed ard i@lemented. Tne DCR review process er}sures that an accurate and cmplete review is performed to any plant design change having an impact on design, construction or operation of the RBS main control room ard remote shutdown panels. Included in the DCR review process are the following steps o Performing a detailed review ard analysis of a DCR package to determine the effect it has on the PGCC or remote shutdown panels. e Determining area (s) of the BWROG Checklist ard Design Conventions mecklist that are relevant to the DCR. e Applying Human Factors Engineering Checklist Conventions. e Identifying HEDs ard, where applicable, assessing their criticality. O l-55
GULF SIRTES UTILITIES COMPANY RIVER BEND S'IATION O e Analyzing all recomendations made to implement cor rections. e Completing DCR implementation with all HFE modifications incorporated. 1.3.5.2 Human Factors Open Items ard Verification Procedures The purpose of the Open Items ard Verification Procedures is to document the methods used to ensure that all changes affecting the human f actors design of the control panels are reviemd by the review team or utilizing the River Bend Station (RBS) Human Factors Maintenarce Plan. 1.3.5.3 Open Items Procedure The Open Items Procedure describes the methods used to track Field Disposition Instructions (FDIs) ard Field Deviation Disposition Reports (FDDRs) gene rated by GE that were eitherr (a) issued but not closed out prior to the DCRDR survey or (b) issued after the start of the DCBDR survey but prior to the implementation of the RBS Maintenance Plan. An open itens log book was developed to list open FDI/FIDRs which potentially affect human factors ard to indicate the status of those documents (see Figure 1.3-2). Initially, the FDI/FDDR numbers we re obtained by consulting the EDI/FDDR log book maintained by the S&W Preliminary Test Organization (PTO) . The PTO log book is updated daily and irdicates which FDI/FDDRs have been issued ard which cnes have been closed out. Af ter listing all open FDI/FDDRs, each document listed was reviewed by tha review team leader. Documents that met one or nere of the following criteria m ee listed as not affecting human f actors: e Work described muld not af fect the parels being reviewed during the DCFDR. e Work described would af fect those panels but muld not af fect the CRrs, instrumentation ard controls, engraving, erharcements or i annunciators. In otner words, it would not af fect the front of the panel. Any document that af fected the front of a parel to be reviewed by the DCRDR l vas listed as "affecting human f actors." Three letters were used to indicate the status of the document. A (c) indicated that the humsn f acters review of that document was cmplete. An (o) indicated that a tuman factors review of that document was not complete. An (f), in addition to indicating that a human f actors review was not emplete, indicated that this document involved a substantial amount of work ard that the review team leader had attached a form (see Figure 1.3-3) to it. By using this form, the engineer responsible for completing the work would notify the review team leader that the work was ccrapleted ard would irdicate how the work affected human factors. When the review team leader receives this form, the responsible engineer will be promptly contacted to define the specific human factors changes that were made.
! CTLF SmTES tFFILITIES COMPANY RIVER BEND S'5LTION l Open Items Log Page Detailed Control Roon Design Review FDDV Affects HP S tatus FDDIV Affects RF FDIf Yes No FDIS Yes No O Status Abbrev. J C-item completed C>-open, ready for review F-open w/ Form attached Figure 1.3-2. Open Items Log Book 1-57 l
GtLP SIATES 17PILITIES COMPANY RIVER BEND S1ATION O FDDR/FDI$ OPEN ITEMS m RM COMPLEfE THIS FORM WEN CLOSING CUT THE AT1 ACHED DOCIMENT During the first ten months of 1984, GSU will be performing a " Detailed Control Room Design Review." Sirce many FDI/FDDRs will be issued but rot completed when this review begins, this form was devised to alert the review team that an FDI/FDDR is completed. In addition, it indicates if the work performed affected the " human factors design" of the panel. If the work performed urder this FDI/FDDR affected the front of the panel in any way, please circle the type of charge that occurred below. If the front of the panel was rot affected, circle NO CHANGE. '1 hen detach this form, sign ard date it, ard send it to Don Chase (x-180) in the Brown Warehouse. Your assistarne in this effort is greatly appreciated. RWF/DC/ksa
- 1) Mimic
- 2) Annuncia tor s a) Moved b) Logic Change c) Window Change
- 3) Engraving Responsible Engineer Date
- 4) Panel Layout a) Add Device b) Move Device
- 5) Meter Scale Change
- 6) Other (explain)
- 7) NO CHANGS Figure 1.3-3. Open Items Form O
GtLF .91RTES UTILITIES COMPANY RIVER EEND SMTION m: The open items log book was developed just prior (1 day) to the start of the DCRDR survey by the review team leader. He is on distribution for all FDI/FDDR cover letters issued af ter the log book was developed. This ensures ' that all documents will be reviewed for human factors applicability. When a FDI/FDDR cover letter is received, the document number an5 rev. number (if rot
- 0) is recorded in the log book. Periodically, the review team leader (or designee) will review the documents and fill cut the "Affects HF" and " Status" columns of the log book for that document.
At an aopropriate time, the DCER review team will review all of the logged documents that affect human factors. Any HEDs resulting from this review will be included in the DCER assessment process. All documents issued after that time will be reviewed by the RBS Maintenance Plan. 1.3.5.4 Veri fication Procedure The purpose of this procedure (illustrated in Figure 1.3-4) is to pick tp where the open items procedure leaves off and perform an ongoing human f actors review of design changes af fecting the front of control panels required to stpper t emergency ope rations. When a modification is idetified for a control roan or remote shutdown panel, either a GE FDI or FDDR form is generate $ to initiate this modification. Printed on the site-attached cover sheet for an FDI, an5 on the FDDR form p itself (see Figure 1.3-5) is a " Pot Hum Eng Impact" item that is marked yes or d no. If the front of any of the following panels will be modified, the "yes" box will be marked by a GB engineer P600, P601, P604, P614, P622, P623, P628, P631, P632, P642, P670, P672, P680, P803, P845, P863, P8 69, P870, P877, C61*P001 If the front of these panels are not affected, the "no" box shall be marked. If the "no" box is marked, to further hu; nan f actors review is required ard the docuent continues on its approval cycle. If a "yes" is marked, a copy of the document ir sent to a 2 engineer familiar with human f actors principles. The GS engineer performs a preliminary review against the human factors design conventions to identify " gross" errces in human f acters design an! sends the results of his/her review to GSU Tech Staff. A GSU Tech Staff engineer will then perform a human factors review by completing the applicable design ccnventions checklist sections. A Human Factors Verification Form (Figure 1.3-6) shall be atta&ed to the front of the completed decklist sheets and the " Pre-Implementation" portion of the form shall be completed. If a discrepancy is roted, GSU Tech Staf f shall determine if the GB document requires modification ard initiate that modification if required. In addition, at the discretion of the Tech Staff engineer, mockups of major design changes will be performed to better evaluate the inpact of the change of th e panel. ) l Once the GE document has been issued ard the work has been performed, GE will l close out their documentation and rotify GSU Tech Staff. Tecn Staf f will then ccruplete the " Post Implementation" portion of the Human Factors Verification ! O V Form. l l l-59
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GULF SIRTES ITPILITIES COMPANY . RIVER BEND S'IATION Modification 8dentified k t t GE (site) Eng GE (San Jose) writes FDDR Eng. writes F DI l l GE (site) Eng. determines if HF are potentially NO impacted. VES Copy of document GE performs prehminary sent to GSU g ree,ew to determine if change is Tech. Staff consistent with desig" YES
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$ Document continues GSU spor es Human Enstneering NO '"'#'"*'"C
Principles and Compietes Pre fmsementation Section h of ver.f. cation Form N Document issued I y HED? to GSU!S&W k YES Work performed GSU No efecision to mudW Y' GE closes out packese YES
+
Document modified GE notifies GSU that pechage is closed Note Th.s process will be ediusted es requesd to be h cons stec - ith changes in site organgstion g GSU completes Post-Implementation
$seten of Verification Form k
GSU HF documents closed O Figure 1.3-4 Verification Procedure
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Figure 1.3-5 FDDR Form s 1-61
GILP ETIATES UTILITIES COMPANY RIVER BEND S'IATION River Bend Station Human Factors Verification Form PRE-IMPLEM!N'IRTION Documentf HEDI (if applicable) Design Conventions Reviewed Description of Change (s): Operator Input Discrepancies Noted: Action Taken Reviewer Dates POST-IMPLEMENTATIO_N BtfiOG Checklist Sections (if applicable) Discrepatries Noted: Operator Input: Action Taken: Reviewer Date O Figure 1.3-6 Human Factors verification Form
i i l GULF STATES UTILITIES COMPANY RIVER BEND STATION f3 N) If, at the discretion of the Tech Staff engineer, the design change is considered major (new insert, new panel, etc.) , the applicable BWROG decklists sections will be completed and HEDs will be prioritized (per RBS DCRDR program plan) by the Tech Staff engineer. Reconnendations for corrective actions will be developed and GSU management shall have final approval on the reconmendations. If the design dange was not major, the completed work will be compared against the previously completed HP conventions checklists to determine if the modification provided the needed ard anticipated correction. By performing a visual inspection of the mo11fied panel, modifications will be evaluated individually as well as collectively. We IEC requirements identified during the control roan survey ard task analysis will also be referenced, as required, to determine if the correction was appropriate. Regardless of the scope of the change, an appropriate GSU operator (s) will be asked for their input on the impact of the modification. his information is recorded on the HF Verification Form ard will be used in developing i recommendations for cor rective actions. When a "F Verification Form has been completed, it will be sent, along with all documentation generated from the HF review of this mo11fication, to the ' Permanent Plant File. l.4 DOCtPENTATION PHASE 1.4.1 Reference Documentation The following documents were identified as possible reference material. e RBS Final Safety Analysis Report e BWROG Control Room Survey Program e BNROG Emergency Procedure Guidelines e RBS Emergency Operating Procedures e NRC Regulatory Guides (e.g.,1.97 a d 1.47) e NRC guidance occuments (e.g., NUREG-0700, Reference G) e Main control room drawings e Systems descriptions i e Piping ard instrumentation diagrams e Annunciator arrangement drawings e BWROG RBS Control Room Survey Sungnary Report e Human Factors Design Information e BWROG Control Roan Design Review Prcgram Summary Report e Operator ard training documents , e RBS Administrative Procedures ! e Main Control Room Photographs O 1-63 i i j l
GULF STATES UTILITIES COMPANY RIVER BEND STATION 1.4.2 Review Documentation Throughout the review process, documents were processed to record data, analyses ard firdings. Whenever practical ard appropriate, standard forms were developed ard used. We bulk of the documentation generated by the review process was necessary to do the followirig e Document the criteria used for each review activity e Record the results of the survey, operating experience review ard system functions review ard task analysis e Cmpile HEDs ard associated data for review ard assessment In order to facilitate systematizing ard recording main control room design review activities, several standard forrrs were developed. R ese forms, which appear as samples in Appendix C, are s e Operator Interview Form o BWROG Control Room Survey Checklist e HED Record e Task Analysis Form o Information ard Control Requirement Sources e Equipment 01aracteristics e Equipment Suitability EDs e FDDR Form for Design Changes Requests All HEDs are tra:eable to a master set of color photos taken as a part of the control room inventory. 1.4.3 Database Management System A cceputerized dattbase management system (DBMS) was used for the RBS DCRDR. We system was used to input, store, retrieve ard analyze significant data from the DCRDR project. We majority of data was generated from the control rom survey, task analysis ard operating personnel interviews. We major sources of data input were the following e HED Records e Task Analysis Data e Operating Personnel Interview Data e System Nomenclature List Each of the data files allows smooth management ard tracking of the DCRDR review firdings ard results. We IED file provides a look-alike output form (see Appendix C) that was used in the final DCRDR report documentation. 1.4.3.1 IED Management One of the major benefits of the emputerized database management system is its HED sorting capability. 21s capability was used effectively to manage duplicate HEDs. i
GULF STATES UTILITIES COMPANY RIVER BEND SMTION l O After the HEDs were input into the database, they were recorded on diskettes and placed in the DCRDR file. His serves as an ar&ive of HEDs that were originally generated. A sort of all HEDs by decklist area was then printed. By reviewing this sort, duplicated HEDs were accurately i identi fied. His printout was then marked-@ to indicate either that a specific HED would be deleted (since it was an exact duplicate of another identified HED) or that specified HEDs should be combined to form a generic HED (panel or control room generic) . His printout was placed in the DCRDR file to prwide an aiditable trail of danges affecting duplicated HEDs. A form was then developed by the Review Team Leader to document any changes of this type occurring thereafter. His form indicated the HED(s) affected, described the change, and the reason for this change. Se ecsupleted forms were reviewed and agreed upon by GBU and GP prior to iriput in the database. All of these forms were then placed in the DCRDR files. This program for database management of HEDs ensured a clear auditable trail for the evaluation ard resolution of HEDs. l.S CONTROL 1EXN/ SIMULATOR DIFFEREIKES STUDY A detailed comparison was performed between the RBS Control Room Panels ard the RBS Simulator on February 8, 9,10 and 11,1984. The actual comparison took place in the simulator room located at the RBS Training Center and was conducted during a period when the simulater was not in use.
"he comparison consisted of inspecting each panel of the simu?rtor ard viewing a photograph of the correspording control room panel in order to determine any differences. All differences between the photographs and the simulator were documented in detail ard are included in Reference P. In addition to the control room photographs, several types of vender documents were also available.
Reference P is divided into the following sections:
- 1. Comparison Methed
- 2. Simulator / Control Room Differences
- 3. Significance of Simulator / Control Room Differences ,
- 4. Reconnended Actions
- I
- 5. Qualifications.
There are three appendices included that listed the main control room / simulator differences by their potential impact on the RBS DCIDR. 1.5.1 Comparison Methcd The first step taken 17 preparatim for the similator/ control room camparison was to separate ard categorize the many (wer 100) photographs taken of the actual control room panels. We photographs were separated by panel ard then each group of panel photographs was divided into sections: benchbeard, O 1-65
GtEF SFATES UPILITIES COMPANY RIVER BEND SMTION vertical and annunciator wiMow array. There was, eventually, a photograph categorized to each corresponding section of a control panel as defined by available veMor documentation. For examples lH13*P870, Long Response Benchboard was subdividal into 6 sections; 51, 52, 53, 54, 55 aM 56, each functionally associated with either a specific plant , system or group of related systems. Each of these sections was further divided; 51a (Annunciator wiMow array), 51b (vertical portion) and Sic (henchboaed por tion) . There were 18 subdivisions to panel P870 aM there were also 18 photographs of panel P870, one for each of the subdivision. Se photographs were next arranged in a book in the following ceder: left-to-right; first the benchbmed, then the vertical aM finally the annunciator array section. Table 1.5-1 describes how the completed book, containing all photographs, was organized, by panel. The order in which the panels are listed corresponds to the order 'n which they we re reviewed. The actual comparison consisted of a detailed examination of a simulator panel section ad then comparing this information with the. correspoMing control room photograph of the idmtical panel section. Areas that were emphasized during the comiurison include: Benchboard Portions e Component Engraving / Tag (actual physical presence) e Engraving Description (functionally cor rect) e control switch assemblies (positions, associated indicating lights aM switch type. i.e., 3 position, 2 position, key locked, etc.) e Mimics associated with system Vertical Pcrtions e All of the above areas e Meter range, scale, units e Con troller s e Recorders Annunciator Arrays e Window engraving e Window Alarm Function e Window Location O
GILF SDLTES IFFILITIES C(MPANY RIVER BEND SMTION O I V I MBLE 1.5-1 PIEFf0 GRAPH ORGANIZATION i Total Pictures ; Panel Benchboard Vertical Annun.* 1H13xP870 (Long Response Benchboard) 6 6 6 1H13xP863 (HVAC Benchboard) 6 6 5 IH13xP808 (Electrical Dist. Benchboard) 7 7 7 1H13xP680 (Principal Plant Control Console) 11 11 1H13xP877 (Standby D.G. Control & Dist. Panel) 2 2 2 1H13xP601 (Reactor Core Cooling Benchboard) 6 6 9 1H13xP845 (Off Gas Panel) 3 Tep/3 Bottom 1H13xP614 (NSSS Temp. Recorder Panel) 2 Top /2 Bottom 1H13xP8 69 (BOP Recorder Panel) 3
- There was one photo for each complete annunciator array except for P680 where they were included on the vertical photos.
/7 Af te r comparing each simulator pane 1 segment with a photograph, any difference V was documented on a pre-defined form. This became the basis for the following section.
1.5.2 Simulator / Control Room Difference Results There were approximately 5000 items compared, 2000 of which were individual annunciator wirdows. An estimated total of 700 differences were examined ard '
- documented. The differences were categorized into 18 separate types which are defined below.
- 1. Engraving Error (On Control Room Panel) i The engraving error appeared to exist on the control roan panel. This was determined af ter examining a nameplate engraving list provided by .
GSU.
- 2. Engraving Error (On Simulator)
The engraving error appeared to exist on the simulator panel. This was also determined af ter examining a nameplate engraving list provided by GS U. i
- 3. Engraving Error (Und etermined)
There was a difference between the simulator ard the control roan; however, there was insuf ficient vendor documentation to determine the i error location. O 1-67
GULF SMTES UrILITIES COMPANY RIVER BEND S'mTION O
- 4. Tape Covering an Engraving Error A piece of embossed tape ha$ been placed over an existing simulator engraving error (Type #2) with the cor rect wording.
- 5. Tape Creating an Engraving Error l A piece of embossed tape ha$ been placed on the simulator engraving. i This created a departure from the control panel and nameplate engraving list.
- 6. Hardware Missing / Removed from Control Room The actual hardware item hai either been removed from the control rom (
panel or had rot yet been installed. No comparison could be made. l
- 7. Control Room Hardware Not on Simulator The control rom panel contained a hardware item that did not exist on the simulator. This could have been adie3 to control room after the simulator design freeze.
- 8. Hardere Locations Reversed The actual hardware items exist on both the simulator panel ard the control room panel; however, there was a difference in the physical location. There was insufficient vender documentation to verify the error.
- 9. Posalble Hardware (New) Addition A review of vendor supplied documentation (assembly insert drawings anS nameplate engraving lists) inSicated a new hardware item would be added to ccritrol rom panel. There was no item on simulator.
- 10. Hardere Diffe rences There appeared to be a significant difference in the h:rdware item con figuration. The nost occurring difference appeared on panel P601, Reactor Core Cooling Benchboard where 31 centrol switches were of the keylocked type on the simulator but regular non-locking type on control room panel. Vendor assembly drawings appeared to suppor t co'itrol rocm d es ign.
- 11. Mater Error - Rarne/ Scale
- 12. Meter Error - Unita There were obvious differences in these two categories but there was insuf ficient venior documentation to determine where the error existed.
13 . Meter Error - Engraving These were similar to category type #3 but in nost cases the control rocn meter had a red background ban $, associats$ with an "out-of-specs" limit, on the meter face ard the simulator did not.
- 14. Annuncia tor : On Simulator / dot on Control Room Panel The reviewed annunciator window on simulator array ha3 an engraved alarm
- the control room counterpar t was either labelled "apare"or was blank.
GULF FFATES ITPILITIES CG4PANY RIVER BEND STATION j l Q l b f
- 15. Annuncia tor : On Control Room Panel /Not on Simulator The reviewed annunciator window on control room panel had an engraved alarm -- the simulator counterpart was either labelled " spare" oc was bla nk .
- 16. Annunciator Disagreement Both the simulator array and the control room array windows had an engraved alarm -- however, there was a difference in either the engraving or the alarm function or both.
(In camparing the above three category types, the provided annunciator window engraving drawings sometimes disagreed with the fir Sings.)
- 17. Inoperative Irv51 cation - Unit Error There appeared to be a difference between the entire Inoperative Indication Unit -- the unit was on the wrong panel or the unit was completely blank, etc.
- 18. Inoperative Indication - Window Error The reviewed window engravings of the simulator ard control room disagreed ard there was no documentation to determine where the error exists.
A canplete list of all differences discovered and documented is provided in O Refererce P. Each panel has its own list of differences and each list provides the following informations e Component Description e Section - Vender Assembly Drawing Designation e ID - Item Number fron Vendor Assembly Drawing Designation e Description of Difference e Location of Difference o Photograph Identifying Control Room Panel Section 1.5.3 Significance of Control Rocen/3imulator Differences As a result of the detailed review and evaluation of RBS main control room photcgraphs ard actual simulator panels, several reconumerded actions were ' presented in order to ensure that an accurate IX'RDR verification ard validation took place on the RBS simulator. Specific recomendations include: e Where a specific piece of hardware is missing from the simulator, ard is shown to be on control room panel, a piece of tape or photograph of the missing instrumentation) was place! in the appropriate location on simulator. e verification ard validation personnel were aware of ard had copies of l discrepancies documented by this report. These include O l-69
l GULF STATES UTILITIES CCMPANY RIVER BEND STATION l
- 2e location swap of inoperative irdication wirdow assemblies 414 ard 415 that should be on sections 55B ard 56B repectively of lH13*P870, vertical pertion.
- The 31 switches on lH13*P601 that are all Key-Lock types in control room, but regular switches on simulater.
- The numerous meter errors, including range / scale differences, unit differences ard actual engraving differences that exist on panels P870, P808, P68 0 ard P601.
- 2e annunciator section differences, including disagreement in engraving ard blank wirdows or; simulator for correspording alarm in control room.
1.5.4 Recomended Actions GP performed a cmprehensive review ard evaluation of over 5,000 items existirg on the RBS main control room by a detailed comparison between photographs of control room panels ard the actual simulator panels. h is task was accenplished in order to determine ard document all differences existing between the sit.ulator ard the control room. Key facts resultina from this ccuparison are as follows: g e here were an estimated total of 700 differences between the simulater ard control rocn. e Cf the 700 differences, approximately 450 or 65% appear to irtpact the simulator as either hardware or software modifications. o mere were sufficient differences to irdicate the original, or mcdifications to, the control room design may need to be reexamined for accuracy. e As a result of the differences, some procedures ard other documentation used in the trainirg of operatcrs may require changes or revisions. Following is a sampling of differences that could be considered significant. e On P870, Section 52B, vertical, meters for " Cold R& eat Steam to MSR's 1 & 2 Temp." simulator reads 0-500 F, control room reads 0-100 pe rc ent. , e on P863, Section 75C, benchboard, for control roca air operated dampers 107/108, simulator has irdicating lights only ard control room has two position switch in addition to irdicating lights. o On P863, same Section, control room has control switches for " Control Room Outside Air Pressure" damper controls, simulator is blank.
I l 1 GULF SFATES (7fILITIES CCMPANY RIVER BEND STATION O e On P680, meters fcr feedwater flow have " Gallons Per Minute" for units on einmalator ard "Pourds Per Hour" on control room. Based on these and other differences currently existing between simulator ard control room, the following recomunendations are made: e he most significant reconumendation should also be the most obvious: The development ard implementation of a configuration management program for the River Berd simulator. e ne second recesumendation is to incorporate all of the differences that impact the simulator, as a training device, at the earliest convenience. Included in this recesunendation would be the updating of all training material ard references presently used. e We third reconenendation is to begin investigating the problems that may exist in the control room design configuration. O I i O 1-71
GULF STATES UTILITIES CCEPANY RIVER BEND STATION O 2.0 IMPLEMENTATION SCHEDULE 2.1 HED Correetion Schedule GSU management has approved an aggressive schedule for prompt inplementation of corrective actions for signifcant HEDs. 'Ihis s&edule is consistent with guidance in NUREG-0801 and NUREG-0700 ard urderlines GSU's ccanittment to the DCRDR effor t. HEDs were assigned into one of two categories; enhancements or modifications (see Fiqure 1,3-1) . For each HED that was approved for corrective action, an implementation schedule was assigned to the HED based on its criticality rating ard category assigned. We implementation schedule is as follows: Enh ancemen ts All enhancements (Criticality Rating 1 through 4) shall be inplemented prior to exceeding 5% of full power rating. Mod i fications Criticality Rating Sch edu le 1 Prior to Fuel Load (Current Schedule - April 1985) 2 Prior to exceeding 5% of Full Power Rating (Current Schedule - June 1985) 3 Prior to exceeding 5% Full Power Rating 4 During 1st Refueling Outage It should be noted that practical constraints on the completion of some corrective actions dictated their implementation schedule rather than their castegory ard criticality rating. GSU has begun implementing the corrections as stated in this report but reserves the right to dange the implementation schedule on any HED if the need arises (i.e. material constraint) . Any significant slippage in the implementation schedule will be reported to the NRC. 2.2 Open RED Resolution The ecnpletion of the RBS DCRDR in a ten (10) month period required the cenplete cooperation ard committment of all involved organizations. he extent of this ccanittment is highlighted by the number of HEDs for which the technical evaluation was rot ccepleted in time to be included in this repor t. Of the more than 650 HEDs generated, only one (1) HED (#552) remained open due to ongoing technical evaluation. ne significance of this HED (power supplies fcr neutron monitoring) initiated an extensive design review by CSU, S&W, and GE which could not feasibly be completed by October 1984. %e results of this review will be included in Section 6 of this report, which will be submitted to the NRC prior to fuel lcad. I 2-1 l
GULF SmTES IFFILITIES COMPANY RIVER BEND SMTION en U 2.3 Open Items For Future Assessment Due to the construction completion status of RBS during the DCRDR, several sections of the BWROG checklists could rot be evaluated. Rese areas included HVAC, comunications, noise levels, fire prevention, emergency preparedness, safety, maintenance ard surveillance, and training ard staf fing. In addition, another lighting survey will be performed af ter completion of the lighting design ard installation of the control room flooring. Rese items will be evaluated ard the results submitted to the NRC (Section 6 of this report) prior to fuel load. O O 2-2 l l
GULF STATES tTPILITIES C04PANY RIVER BEND STATION O 3.0 OUALITY ASSURANCE PROGRAM AND AUDITS 3.1 OA Proiact Procedures The RBS DCRDR was performed in accordance with a formal Quality Assurance (QA) plan by GP with GSU internal review. GP maintains a ccrporate Quality Assurance program developed to emply with, where applicable, the most stringent standards of Title 10, Part 50, Apnerdix B of the Code of Federal Regulations. The QA Manual used prescribes controls for project organization, control of dcx:uments, inspection, corrective action, quality assurance records, review of project work, ard other applicable activitias. The Project Work Plan was prepared by the GP Project Director in accordance with the Quality Assurance manual ard this Program Plan. Project Procedures and Quality Assurance Procedures were prepared as necessary to control those tasks affecting project quality. We Project Work Plan was then submitted to the GSU Operations Quality Assurance Supervisor for review ard approval. After the plan and associated Project Procedures were reviewed, approved, ard implemented, the project was audited by the GP Quality Engineer for emplia nce. Project Personnel received orientation training on the content ard use of project peccedures during the initial phase of the project. Once approved, proiect procedures were treated as controlled documents. 03rrent ecpies are maintained at GP and GSU offices involved in the project. 3.2 OA Audit All DCRDR work was performed urder a Quality Assurance (QA) pr og ram. This involved developing and maintaining project procedures to ensure compliance with the QA progrant. During the ccurse of the project, an audit was performed by GSU QA personnel. We audit process ard subsequent results are described in the following paragraphs. A scheduled audit was co ducted at the GP, Columbia, Marylard office frm May 22 through May 24, 1984. We objective of the audit was to assess the adequacy ard implementation of the GP Project Quality Plan, including applicable sections of the QA Marmal ard implementing Project Procedures (PPs), ard to meet the objectives of the RSS DCRDR Program Plan. In addition, an assessment was performed to determine the adequacy of the DCIDR Program Plan in implementing the requirements of NUREG-0737, Supplement 1, " Requirements for Emergency Response Capability" (General Letter 82-33)", (Reference B) , using the guidelines of NUREG-0801, " Evaluation Criteria for Detailed Control Room Design Review" (Reference E) ard NUREG-0700, " Guidelines for Control Room Design Reviews" (Reference G) . The audit was conducted utilizing checklists ard/or criteria identified from the requirements ard/or guidelines of the dccuments listed in Appendix G of th is repor t. 3-1
_ = _ - _ - _ . - - - _ - . - - - _ _ . . -. - _ - - - . . . - - - _ . - - - - . i f GULF FmTES UTILITIES C(BtPANY RIVER BEND SMTION f O . Se audit covered all major aspects of the project, as delineated in the GP Project Quality Plan, the GP QA Manual an$ Project Procedures, and the DCRDR Program Plan. Se audit also covered a review of-the concerns expressed in NRC Letter, Staff Cosments on RBS DCRDR Program Plan, dated April 25, 1984. i l Specific areas of interest, which were examined, included the following:
- 1. Application of the GP QA Manual to the DCRDR, including:
! a. Periodic assessment of the QA Manual anS contract activities; i b. Indoctrination ard Training of project personnel to the QA Manual ard applicable documents /proce& ares;
- c. Design control measures;
- d. Use of approved instructions and procedures;
- e. Control of Measuring ard Test Equipment;
- f. Document Control ard QA Records; ard
- g. Audits
- 2. Operator interviews ard historical report review, including:
I I a. Identification of interviewers an$ interviewees; and i b. Collection, documentation ard analysis of interview ard historical j report data.
- 3. Main control room survey including:
- a. Physical survey performances ard documentation; ard
- b. Identification ard documentation of deviations from acceptable human engineering principals.
4 l 4. Syste:n functions review ard task analysis, including:
- a. Identification ard description of major plant operating systems ard j subsystems; 1 b. Identification ard documentation of representative event sequences of ;
i "sc ena rios";
- c. Identification ard documentation of the functions ard interfaces
- associated with the selected " scenarios"; ard
- d. Operator task identification ard analysis.
As a result of this audit, seven progransnatic deficiencies were noted. One of the deficiencies was corrected during the course of the audit. Se remaining six deficiencies were identified in Quality Assurance Firding Reports (QAFRs) . Rose deficiencies were responded to by the GP project staff ard . were subsequently resolved. 3.3 NRC In-Proaress Audit j An in-progress audit of the RBS DCRDR Program was conducted by the NRC during July 23-27,1984. Se audit focussed on nine areas including
- o .
3-2 l
GULF STATES UTILITIES COMPANY RIVER BEND STATION O (1) System Function and Task Analysis (2) Control Room Inventory (3) Control Rom Survey (4) HED Assessment (5) Modification Selection ard Improvements for HEDs (6) Integration with Other Supplement 1 to NUREG-0737 Areas (7) Structure ard Qualifications of DCRDR Team (8) Operating Experience Review (9) Data Marugement System ard Files '1he NRC a2dit team concludes that GSU was conducting a DCR)R which, if ccripleted in a manner consistent with that described to the audit team ard if adequately documented in this cummary report, should meet the requirements of NUREG-0737 Supplement 1. O
,J 9
3-3
l GtEF SMTES UTILITIES CGEPANY. RIVER BEND S'IRTION f 4.0 INTEGRATION OF DCER WI'HI OTHER SUPPLElelNT 1 TO NUREG-0737 ACTIVITIES GBU recognises the igortance of integrating the various emergency response capability activities and has developed the integrating plan outlined in this section. In order to develop and implement a site-specific integration program, GSU formed a dedicated organization as shown in Figure 4.0-1. This organization is headed by the task coordinator who reports directly to the Plant Manager. This ensures adequate management attention and provides the appropriate structure by making one person responsible for the program. Each of the five major activities has a lead person who receives input from various GSU organizations and works closely with the task coordinator. The resultant integration plan, which is discussed in detail in the following subsections, is shown on Figure 4.0-2. 4.1 EERGENCY OPERATING PNX2 TITRES (EOPs) The usability of the EOPs and their correlation to the control room hardware are important aspects of the EOP development program. GIU enhanced this development by integrating the EOP Validation program with the DCRDR Validation activity. This eliminated the duplication of work that would have otherwise occurred and ensured a coordinated effort between the two activities. In addition, as discussed in Section 1.2.3, the System Functions Deeceiption ard Task Analysis portion of the DCRDR used the RBS EOPs as its O basis. This examination of the EOPs irherently integrated their tygrading with the DCRDR. 4.2 ShFETY PARAMETER DISPLAY SYSTM (SPDS)
\
The development of parameters displayed on the SPDS, ard the format with which they are displayed, is depenient on input from several sources including the j DCRD R. From the DCRDR, operator requirements during conditions of emergency j operation were identified. These requirements defined some of the necessary plant inputs to the SPDS. Since the displays were not finalized at the time of the DCER, they will be reviewed under the GBU Human Factors Maintenance Plan. When the SPDS displays are finalized, the EOPs will be modified to refe rence them. The RBS SPDS Accidest Monitoring Study (Reference K), discussed in Section 4.4, compared the SPDS database against a composite list of variables to be monitored under transient or emergency conditions. Any variable not contained in the SPDS database was input into the DCER as an RED. l l l O 4-1 I
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GULF STATES (TTILITIES C(EPANY RIVER BEND STATION O 4.3 EMERGENCY RESPONSE FACILITIES (ERF) he ERP drills ard exercises perfmmed later this year and in early 1985 will assess the equipment, personnel & layout of the Emergency Response Facilities, including the control room. As part of the DCRDR, the Control Room Foreman's Desk was re-designed to accomodate the SPDS ard required communications equipment to support ERP activities. The interface between the Emergency Implementing Pror,edures (EIPs) ard the EOPs is being exacined by GSU to ensure that the EIPs are entered at the appropriate time ard that the implementation of the EOPs is not hirdered. During the drills, the SPDS will be evaluated fm its ability to suppmt ERF activities. 4.4 REGULATORY GUIDE 1.97 The SPDS Accident Monitoring Instrumentation Database Identification Study (Reference K) dated April 1984, was a partial response to the NRC for Regulatory Guide 1.97. As illustrated in Figure 4.4-1, a composite list of variables to moniter in transient cr emergency corditions was developed from three sources; Event Tree Analysis, EOPs, ard R.G.1.97. %is canposite list was compared against the control room hardware ard discrepancies noted were input into the DCRDR as HEDs. This provided a coordinated program for determining the adequacy ard availability of control room hardware. In addition, the Verification of Task Performance Capabilities portien of the DCRDR systematically verified the presence or absence of information required by the operator , and conversely, if any type of indication was required but miss ing . 4.5 TRAINING The RBS training department played a major role throughout the DCRDR process. Durity the Systems Review ard Task Analysis activities, training personnel develcped system deceriptions, formulated the scenarios, ard worked in conjunction with Human Factors, Operations, ard Engineering personnel to complete the information on the task aralysis worksheets. During the Validation phase, training personnel were scenario observers, noting discreparcies between expected ard actual operator actions. For the Verification activity, training personnel assisted Operations afd Engineering in determining the availability ard adequacy of control room hardware. A training instructor was one of the five persons who prioritized the DCRDR HEDs, giving insight to the potential for operator error noted during simulator training. Training personnel also assisted in developing recarnendations for corrective actions on HEDs. Much of the data gathered fecrn the DCIDR will be useful in future operator training courses. O 4-4
I GtKF frmTES (FFILITIES COMPANY RIVER EEND SMTION O EME" N REG. GUIDE 1.97 EVENT TREE ER AT N ANALYSIS REVISION 3 PROCEDURES 4 I I J VAR VAR VAR LIST LIST LIST e e e o e e o e
- 1r INPUT DATA CATEGORIZATION -/
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COMPOSITE VARIABLE -
- RANGE STUDY LIST e LOCATION e INSTRUMENT ID e SEQUENCE NO.
e PDS SIG. ID. O - REVIEW LICENSING AND TECHNICAL LfST FOR REQUIREMENTS ISCREPANCIES l DCRDR
- o RESOLUTION i OF
! DISCREPAN-CIES ; Figure 4.4-1. Accident Monitoring Instrumentation Study Implementation Methodology 4-5 ]
GtLF SIATES ITPILITIES CCMPANY RIVER BEND S'1% TION O
5.0 REFERENCES
A. BWR Owners' Group Letter BWROG 83-51 from W. J. Armstrong to V. A. Moore, dated Atgust 25, 1981. B. NRC Generic Letter 82-3 3, Supplement 1, to NUREG-0737,
" Requirements for Emergency Response Capability," December 17, 1982.
C. NRC Generic Letter 83-18, NRC Staff Review of the BWR Owners' Group Control Room Survey Program, dated April 19, 1983. D. " Human Engineering Guide for Enhancing Nuclear Control Rooms." EPRI Repcrt No. NP-2411, May 1982. E. " Evaluation Criteria for Detailed Control Room Design Review", NUREG-0801, Draf t Report, October 1981. F. "BWR Owners' Group Control Room Design Review Program, Summary Repcr t," Gene ral Electric Report No. IEDC-30285, October 1983. G. NUREG-07 00, " Guidelines for Control Room Design Reviews," September 1981 H. BWR Owners' Group Control Room Survey Workshop, October 1983. I. NU'IAC " Control Room Design Review Implementation Guideline," July 1983. J. NU'IA C, "DCRDR Task Analysis Guideline," September 1983. K. Safety Parameter Display System Accident Monitoring Instrumentation Idmtification Study for RBS, Docket No. 50-458, dated April 24, 1984. L. NUREG/CR-369 6, " Potential Human Factors Deficiencies in the Design of Local control Stations and Operator Interf aces in Nuclear Powr Plants," April 198 4. M. EPRI Graphics Display Guidelines (Draf t Report), January 1984. N. River Berd Station, Detailed Control Room Design Review Program Plan, Jarmary 1984. P. River Bend Station, Control Roont/ Simulator Differences Study, February 1984. Q. NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures," Atgust 1982. O 5-1
l GME SIRTES UTILITIES MANY - RIVER BWID SMTIOtt
= 6.0 SGGGutY REPORT ADDIDIDGt
-(To be provided by GBU later). :
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O APPENDIX A REStNES OF ORIGINAL BWROG CONTROL ROOM SURVEY TEAM WALLACE J. COLVIN, CLEVELAND ELECTRIC ILLtMINATING CCNPANY WILLIAM G. ALCUSKY, YANKEE ATQ4IC ELECTRIC CCHPAW BYRON K. V{IBODEAUX, GULF STATES UTILITIES DR. PAUL J. NICIDLSON, MASSACHUSEITS INSTITtTTE OF TECHNOLOGY (HtHAN FACTORS CONSULTANT) KENNETH C. ROSS, GENERAL ELECTRIC CCHPANY O O l
REStME Wallace J. Colvin EDUCATION AND TRAINING Attended Ohio State University, College of Engineering, 1964-1967 Atterded Kent State University, College of Education,1967 Twenty-Week Academic Program for Nuclear Power Plant Personnel (General Physics Corporation) ,1979 ! 'No 4feek Research Reactor Training Program, University of Wisconsin,
- (General Physics Corporation) ,1979 i Five-Week Dresden Nuclear Plant Technology Course (GE),1979 Ten-Week Operaters Training Course, Dresden Simulator (GE) ,1979 Four 4feek BWR Cheervation Training, Millstone Nuclear Power Plant (GE) , 1979 One-Week BWR Control Room Survey Workshop (GE) ,1980 Degree Cardidate, Clevelard State University, College of Engineering, 1980-1983 WORK EXPERIENCE
l 1973 - Present's Clevelard Electric Illuminating Company Joined CEI as Plant Operator A at Ashtabula Coal Power Plant. Promoted to Rovina Operator in 1977. Traneferred to Perry Plant in 1978 as Perry Plant Trainee. In 19'l9, qualified as l 1 Senior Reactor Operator at Dresden Simulator. Qualified as a member of the BWR Owners Group Survey team in 1980. Promoted [ O to Unit Suoervisor in 1981. Activities include systems operating instruction review ard evaluation of Control Room human factors. Reports directly to General Supervisor, Operations Section. 1969-1972: Union Carbide Corporation, Ferro Alloys Division Roving Operater at Ashtabula Coal Power Plant Steam Department. O
i REStEE O William G. Alcusky EDUCATION AND TRAINING BSEE,1971, Northeastern University, Boston, Massachusetts Graduate Courses in Management Sciences, Worcester Polytechnic Institute, Worcester, Massachusetts Course, " Human Factas in Process Control", University of Maine, Orono, Maine, May-June, 1912 Recent Training Courses ard Seminarn Stone & Webster Engineering Corp., "Furdamental Management Skills", Ja nua ry-Februa ry, 1982 American Management Association, " Improving Managerial Skills for the New or Prospective Manager", October,1981 EPRI Seminar, " Human Factors Enhancement Approaches for Nuclear Control Room", August,1981 NUS Corp. Seminar , " Emergency Response Pacilities", May 13, 1981 EPRI Seminar, " Computerized Opera tor Suppcet Systems", December, 1980 "Naclear Electronics Techrology Update", at General Atomic, January, 1980 WORK EXPERIENCE Yankee Atomic Electric Co. - October,1979 - Present Instrument ard Control Engineer: Work included environmental qualification of instrumentation ard electrical equipment, design of new instrumentation loops, ard procurement of instrumentation. Performed studies of Control Room Accident Monitoring Instrumentation for adequacy. Purchased isolation system for prototype SPDS. Responsible for human factors reviews of on-going design changes ard participated in Control Room Design Reviewa for 2 BWRs ard 1 PWR. Stone & Webster Engineering Corporation - June,1971 - October,1979 Work incleded layout ard equipment selection for control ard relav panels, ard arrangement ard procurement of plant annurciator systems. Develcped electrical control circuits for pumps, valves, etc. Worked at construction site supervising installation ard l checkout of electrical equipment ard installation. PROFESSIONAL AFFILIATION Member IEEE SC7, " Human Factors ard Control Facilities" t
i i RESIME p/ U Byron K. Thibedeaux l EDUCATION 5/73 LOUISIANA STATE UNIVERSITY, Baton Rouge, LA B.S. Electrical Engineering GPA: 3.4 of 4.0 Graduated with Honors LICENSES AE CERTIFICATIONS Registered Professional Engineer - State of Louisiana WORK EXPERIENCE 6/78 to GUIF STATES UTILITIES present Svtems Engineer, River Bend Nuclear Group - Plant Staff (1/81 to present) Major Responsibilities:
- 1. Direct the testing of the Power Generation Control Complex st the NSS verder's manuf acturing f acility.
- 2. Witness ard approve the fabrication of the Power Generation control Complex as a representative of the utility.
- 3. Provide technical suoport to the Plant Staff Operations Department.
- 4. Provide technical support to the Plant Staff Maintenance Department.
- 5. Participate in BWROG control room surveys 4 u persuant to satisf action of NRC requirements.
- 6. Coordinate A/E, NSS venace, ard utility activity so as to support Power Generation Control Complex fabrication, testing, ard installation.
Engineer, River Berd Nuclear Group - Project Engineering (10/79 ta 12/B0) Major Responsibilitles:
- 1. Review of work performed by the A/E on electrical, control, ard instrumentation aspects of the
' Nuclear Islard.
- 2. Review of work perfumed by the NSS vender on electrical, control, ard instrumentation aspects of the Nuclear Steam Supply System.
- 3. Review of work performed by the A/E on electrical, control, ard instrumentation aspects of the Balance of Plant.
- 4. Provide engineering support for River Bend site activities.
- 5. Coordinate ard expedite the activities of the A/E ard NSS verda in all aspects concerning the Power Generation Control Complex.
O
Engineer, Systems Engineering - Relay Design ard O Coordination (6B8 to 9/79) Major Responsibilities:
- 1. Direct ani supervise the activities of the Relay Stardards section. '1his section is responsible for optimization of relay designs ard through economics ard engineering, arriving at the best designs which are consistent with good engineering practices.
I. Supervise the preparation of relay construction data for use by operating personnel in the construction of substations for routine projects.
- 3. Perform the necessary engineering functions ard supervise the preparation of relay construction data for use by operating personnel in the construction of EIN and nenerating plant sub stations.
- 4. Ensure that all portions of projects urder my responsibility adhere to the actiedule for completion.
1/77 to ETHYL CORPORATION 6/78 Electrical Enqineer - Design Engineering (2/78 to 6/78) Major Responsibilitless g
- 1. Design motor control systems for new plants or W expansions.
- 2. Design lighting systems for new plants or expansions.
- 3. Design grourding systems for new plants or expansions
- 4. Design power distribution systems for new plants or expansions.
- 5. Furnish estimators with material take off for electrical materials used in each project.
- 6. Write electrical sc@e for contractors bid packages.
- 7. Write electrical sege for vendors bid packages.
Assistant Maintenance Supervisor - PVC Plant (1/77 to 2M8) Major Responsibilities:
- 1. Supervision of electrical ard instrument maintenance forces.
- 2. Supervision of painting ard sard1 blasting forces.
- 3. Supervision ard/or coordination of construction in a re a .
- 4. Supervise all maintenance forces in the absence of maintenance supervisor.
O l
- 5. Authorization c,e spare equipment ard parts to be s_ / stored on plant site for use in area.
- 6. Study breakdown frequencies ard establish preventive maintenance program to reduce downtime ard f requency.
- 7. Approval of replacement parts ard equipment to be purdased in area.
6/13 to ALABAMA POWER COMPANY 12/76 Enaineer - System Protection (6/73 to 12/76) Major Responsibilities:
- 1. Otecking ard correcting application of protection ard control s& emes by design personnel.
- 2. Supervision ard/or coordination of the construction of transmission ard generating plant -
substations; also generating plant facilities.
- 3. Testing ard evaluation of the followings a) instrument transformers b) protective relaying c) consnunication equipment associated with protective relaying ard control d) power transformers ard associated equipment e) circuit breaking devices OCB, ATB, PCB, MOD, Metal clad switchgear, Vacuum switches, etc.
f) regulating transformers (LTC afd integral unit)
\ g) complete system control functions ard coordination h) capacitcc banks i) customer distribution system ccupatibility j) meters ard instruments
- 4. Furnish operating procedures for all transmission ard generating plant substations.
2 PROFESSIONAL APFILIATIONS Senior member: Instrument Society of America Louisiana Engineering Society 3 Tau Beta Pi Phi Kappa Phi Eta Kappa Nu l O
O SIDRT REStNE Paul J. Nicholson P. J. Nicholson is currently an irdependent consultant serving the nuclear power industry in the areas of instrumentation ard control ard related topics. Wenty-three years of professional experience include 12 years in the aerospace electronic industry ard the remairder in nuclear research ard advanced reactor instrumentation ard dynamics. For the past four years, while principal sciercist at the C.S. Draper Lab, he has been guest lecturer in the MIT Nuclear Engineering Department, associate lead investigatcr for the MIT Advarced Reactcr Control Project, afd supervisor for a number of nuclear engineering graduate thesis projects. He has been nomimited for the position of Visiting Scientist at MIT for the 1980-81 academic year. From 1958-65 he held positions of increasing responsibility at Raytheon Company, managing advanced aerospace electric projects in air defense, radar an1 signal processing. Granted academic leave during 1965-69 he joined an experimental high energy physics research group at the Rutherford Laboratory at Harwell, U.K., accepting responsibility for all electric instrummtation for the 117 experiment, one of the first successful large scale ccrnputer controlled experiments. He was also responsible for control room design displays, data storage ard retrieval aspects. While in the U.K. he ccrnpleted studies fcr a Ph.D. degree at the Imoerial College in Lordon ard was appointed urdergraduate physics tutcr. Returning to Raythecn he was named marnger for Advanced Develcpment, O Aerospace Systents with responsibility for the USAF f ault tolerant computer program ard airborne multiplexing systems. He was a member of the SAE-2K multiolexing committee. Later at GTE Sylvania he was responsible for Air Force Satellite ccramunications, the joint services computer controlled small switch bcntd a rd DCA worldwide digital voice modem development. From 1974-1980 at C.S. Draper Lab he was senior project scientist ard principal investigatcr fcr advanced reactcr instrumentation ard control ani reactor modeling studies fcr the DOE fusion program ard the EPRI Fusion-Fission Hybrid Kinetics Study. He also collaborated with Combustion Engineering in the Disturbance Analysis System (DAS) Study ard interacted with the nuclear utilities, and industry ard the NRC in areas of LWR power plant I&C. Recently he was invited to lecture in the MIT Summer Course on Man-Machine Interf acing in Nuclear Power. He is a member of the AIAA Terrestrial Energy Technical Comittee, served on the IEEE/NRC Smart Instrumentation panel, ard is a consultant to the Stone ard Webster Engineering Corporation. He is authcr of several publications in the reactor IEC field. Prior to his post graduate studies in 'che U.K., Mr. Nicholson obtained a B.S. In Mechanical Engineering frcra MIT ard an M.A. in physics from Boston University. O e___ _ _ _ . _ _ _ _ _ _ ______________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
( RESIME Name: Kenneth C. Ross Position: Program Manager company: General Electric Experience includes nine years in the nuclear industry - four years as an instructa in the U.S. Navy nuclear power program, two years as an instructor for General Electric Company, ard three years as a program manager for General Electric Company. SIO License. Certified by NRC to teach all phases of BWR operation. General Electric program manager for BWROG Control Roaa Survey Program. Provided program management support for eighteen BWR control room design reviews. Principle authw of nine control room design review sununary reports, co-author of additional seven. Developed, organized, and presented BWROG Control Room Survey Program Worksh@. Attended MIT sununer seminar on human f actas engineering ard INPO workshop on control rocen evaluations. Co-author of training appendices to BWROG EPG's. 4 O I l I 'l .,O
1 1 O APPENDIX B RESINES OF REVIEW TEAM FOR REMAINING ACTIVITIES A. REVIEW TEAM D. A. CHASE, GSU REVIEW TEAM LEADER D. C. BURGY, GENERE PHYSICS LEAD HIMAN FACTORS SPECIALIST R. J. LIDDLE, GNERAL PHYSICS SENIOR HUMAN FACTORS SPECIEIST A. O. FREDIEU, GSU OPERATIONS SPECIEIST M. O. BISHOP, GSU OPERATIONS SPECIALIST E. P. SHANKLE, JR., GSU OPERATIONS SPECIALIST B. GUPPORTING INDIVIDUALS L. R. SCHROEDER, GENERAL PHYSICS SENIOR HUMAN FACTORS SPECIALIST R. E. PRICE, GENERE PHYSICS DIRECTOR OF BWR TRAINING SERVICES D. B. BARKS, ENERE PHYSICS !!UMAN FAcrORS SPECIALIST R. I. STAPN, GENERE PHYSICS OPERATIONS SPECIALIST L. R. BYRD, JR., ENERAL PIIYSICS TRAINING SPECIALIST D. C. BYRD, GDIERAL PHYSIG TRAINING SPECIALIST J. C. PRASKIEVICZ, GNERAL PHYSICS OPERATIONS SPECIALIST R. S. GROSECLOSE, GDIERE PHYSICS QUALITY ASSURANCE DIGINEER N. L. BORREGGINE, STONE AND WEBSTER ELECTRICAL DESIGN ENGINEER C. C. MATSO?i, EORGIA POWER COMPANY, I&C DIGINEER O
~ .
i 1 REStME
.Q D Donald A. Chase l
EDUCATION B.S. in Civil ard Environmental Engineering,1978 - Clarkson College of Te&nology I LICENSE Engineer-In-Training, Tennessee,1980 WORK EXPERIENCE System Engineer - Gulf States Utilities Company, River Bond Station: September,1983 to present.
- Participate in ard support startup modification ard acceptance testing of control room systems.
- Completed BWR-6 Technology course - General Physics Corporation, 1983
- Participated in BWROG control room survey workshcp - General Electric Co.,1983.
Area Coordinator - Control B *ilding - Gulf States Utilities Company, River Berd Station; November,1980 to September,1983. O - Chairman of control room construction management group. Held weekly meetings, expedited required material ard problem resolutions, ard assisted in scheduling to coordinate the installation of th PGCC ard Control Roca suppor t systems.
- Closely monitored ard coordinated with upper management ard contractors all civil, medanical, ard electrical activities for remairder of Control B *ilding.
- Identified problems associated with inef ficient construction methods, over-restrictive requirements, low productivity,.
safety, ard equipment maintenance. Then formulated timely corrective action. Reviewed ard made recommerdations on field material requisitions, bid packages, ard memorarda of cost changes. Prepared frequent reports ard gave oral presentations to advise upper management of job progress. Civil Engineer - Tennessee Valley Authority, Hartsville Nuclear Plant; June,1978 to November,1980.
- Approved all rebar ard civil embeds installation, ard the structural integrity of formwork prior to concrete placement.
Designed shcring systems over large oper.Ings ard equipment for Turbine Building slabs.
- Assisted craf t in interpretation of drawings, specifications, '
and pra:edures related to civil activities. l O
- Coordinated the resolution cf structural design problems as an O interf ace betwen the construction forces ard design org anization. - Solved field-related problems ard advised engineering managers of job progress. - Coordinated activities of a survey party to provide the work force with lines ard grades ard timely checkout of concrete f or mwork . O O l
I l l
.- EB8tPIE '
Doaald C. Burgy Director, Human Factus Engineering b EDUCATION Ph.D. Cardidate, Applied-Experimental Psychology, he Catholic University of America M. A., Applied-Experimental Psy& ology, he Catholic University of America 4 B.A., Psy& ology, Swarthmore College
, EXPERIENCE General Physics Corporation I 1979 - Present Mr. Burgy directs all human factors engineering and man-j machine systems design and evaluation work in the Company.
His human factors expertise includes system analysis, 1 information processing, man computer interactions, ' performance evaluation, training systems, an$ speech / . i nonspeech communications. Representative projects include: i
- e Control Room Desian Reviews l Directed or participated in nuclear power plant control l j room design reviews at ten nuclear power plants
- !
j Virginia Electric ard Power Company's North Anna and j Surry Stations, Commonwealth Edison Ccapany's Elon, ; I LaSalle, ard Dresden plants, Cincinnati Gas and Electric i i i Capany's Eisumer plant, Pennsylvania Power ard Light ! Company's Susquehanna Steam Electric Station, Illinois ! I Power Company's Clinton plant, Public Service Electric f and Gas Company's Salem Nuclear Generating Station, ard 'l i Portlard General Electric Company's Trojan Plant.
- ) .
- e Task Analysis of Nuclear Power Plant Control Room Crews i Managed a major 18-month 1stC research program on nuclear l power plant control room crew task analysis. A data collection approach ard methodology used to conduct a task analysis of nuclear power plant control roca crews was developed in this program. The task analysis methodology used in this project was discussed ard compared to traditional task analysis ard job analysis j methods in a Program Plan report. H e data collection t was conducted at eight power plant sites by teams f comprised of human f actus ard operations personnel.
I Plants were sampled according to NS88 vender, vintage, I simulata availability, arditect-engineer, and control 5 room configuration. He results of the data collection 1 effort were empiled in a computerised task data base. t f i i i s i I
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O e Comunications Problems in Nuclear Power Plants Electric Power Research Institute (EPRI) Managed project on Guidelines for Internal Plant Comunications for EPRI. 'Ihese guidelines were developed based on problsma previously occumented in EPRI research projects. Participated in an EPRI Technical Planning Study on Comunications Problems in Nuclear Power Plants prior to managing the guidelines study above. Developed methodology for collection ard analysis of real-time comunications data in operating power plants. o Prototype Large Breeder Reactor (PLBR) Operability Study Participated in an EPRI operability study of the two major PLBR designs -- pool ard loop types. Coauthored a PLBR Design Familiarization course text. Conducted task analysis fw initial design evaluations of PLBR control console layout, instrumentation ard control needs e Submarine Design Human Factus. U.S. Navy Developed task analysis famat ard collection methodology to promote team performarce improvement ard training enhancement in the Navy Submarine Advanced Combat Systems (SUBACS) program. 1976 - 1978 The Catholle University of American Human Performance Labora tory Mr. Burgy conducted applied ard basic research experiments on auditory signal classification of complex urder-water sourds in research sponsored by the Human Factors Engineering branch of the Office of Naval Research. PROFESSIONAL Member, Acoustical Society of America AFFILIATIONS Member, American Psychological Association Member, Human Factors Society SELECTED Applied Human Factors in Power Plant Design ard Operations, PUBLICATIONS General Physics Corporation,1980, Coauthor with P. A. Doyle, H. F. Barsam, R. J. Liddle
" Survey ard Analysis of Comunications Problems it' Nuclear Power Plants," EPRI Report NP-2035, September,1931, Conuthcr with D. A. Topmiller, D. R. Roth, P. A. Doyle, J. Espey.
" Task Analysis of Nuclear Power Plant Control Room Crews,"
Final Report, U.S. Nuclear Regulatory Commission, Washing ton , D.C. , May,198 3. Coauthor with C. Lempges, A. Miller , L. Schroeder, H. Van Cott, D. Paramore. O l l
RESGEE Robert J. Liddle Manager, Busan Pactas Power Services EDUCATION M.S., Industrial Engineering and Operations Research, Virginia Polytechnic Institute and State University B.S., Psy& ology, Virginia Polytechnic Institute and State University EXPERIENCE General Physics Corcoration 1980 - Present Mr. Liddle is a human factors engineer responsible for managing power plant control room design review metho$ ology, staffing, and training programs. He provides in-house staff instruction in technical and administrative aspects of control room reviews. Mr. Liddle serves as project manager for several human f actors projects and has had experience with utility / Nuclear Regulatory Commission negotiations involving human f actors issues. e Proaram Plan Development Developed program plans for various utilities which present detailed methodologies utilised in the performance of control room design reviews. 'the program plans encompass management, staffing and data collection and interpretation issues. e Control Room Desian Review Managed detailed control room design review projects at the Pennsylvania Power ard Light Company Susquehanna Steam Electric Station and Washington Public Power { Supply System No. 2; acted as lead human f actus engineer in control room design review for Georgia Power Company's Plant Vogle, Unit 1, ard managed human f actors review at Long Islard Lighting Company's Shoreham Nuclear Power Station. e Selection Testina Admittisters General Physics Basic Mathematics ard Science Test (BMST) for operator training and selection; assists in human reliability analysis with emphasis on nuclear plant applications ard the accompanying task analytic procedures, e Development of Human Enaineerina Stardards Compiled ard developed stardards, in control coding, legerd plate design, mimic ard demarcation lines, ard color coding practices. O l
e Human Factors Training O Instructs utility ard industrial personnel in topics of performance evaluation techniques, experimental methodology and control room review procedures. 1977 - 1978 Virginia Polytechnic Institute ard State University In his research project, Mr. Liddle investigated the use of videotape recording apparatus in an assessment center process. He assisted in scheduling ard debriefing participants, data collection ard interpretation, ard repor t writing. P ROFESSIONAL Member, Human Factors Society APFILIATIONS PUBLICATIONS Applied Humsn Factors in Power Plant Design ard Operation, General Physics Corporation,1980, Coauthor with D. C. Burgy, P. A. Doyle, H. F. Ha r sam. Susquehanna Steam Electric Station Detailed Control Room Desion Review Program Plan, General Physics Corporation, 1982. Shoreham Nuclear Power Station Detailed Control Room Denian Review Pecoram Plan, General Physics Corporation, 1983, Coauthor with D. C. Burgy. O
REStME (V} Anthony O. Fredieu OUALIFICATION SISSIARY Twelve (12) years experience in the power industry with over eight (8) years in consercial nuclear power. 21s experience includes: Shift Supervisor - Nuclear Assistant Operator - Nuclear Shift Foreman - Nuclear Assistant Operator - Fossil Plant Operator - Nuclear EDUCATION University of South Alabama, Mobile, Alabama Memphis State University, Memphis, Tennessee McGill Institute, Mobile, Alabama General Physics Corporation - Physics, hermo-Dynamics - 1972 Westinghouse On-Site Nuclear Training - 1974 - 1976 General Electric Medanical ard Nuclear Training Services, BWR-6 Technology Course - 1980 General Electric Mechanical ard Nuclear Training Services, BWR-6 SRO Certification - 1982 LICENSE / CERTIFICATION Senior Reactor Operator Licensos Nos. SOP-3138 ard SOP-3138-2 BWR/6 SRO Certification - G.E. Nuclear Certification Level III 0 ANSI 45.2.6 EXPERIENCE Present - Shift Supervisor - GULF STATES LTFILITIES, RIVER BEND NUCLEAR PLANT. Currently pursuing STA Qualifications via Memphis State University's Advanced Technical Principles Training. Previous duties ard responsibilities included
- 1. Obtaining a BWR/6 SRO certification at General Electric Training Center in Tulsa, Oklahoma.
- 2. Coordinating development of Operations Group, as well as, total plant administrative program while acting Administrative Supervisor .
- O
O
- 3. Serving as GSU representative in the Dynamic Screening for the Safety Parameters Display System.
- 4. Supervising activities of Shift Fornmen ard Operators during Start-tp ard Preoperational testing of River Berd Plant.
- 5. Developing the Plant Wide System ard Component Identification Program.
1980 - Shif t Forernan - ALABAMA POWER CCMPANY, JOSEPH M. FARLEY NUCLEAR PLANT Licensed Senior Reactor Operator on Unit I and II at this PWR site. Responsibilities included supervision of plant opertcre durino both normal ard of fnormal operations in conjunctic . with Start-up participation as a Cold Licensed 4RO on Unit II. 1975 - Plant Operator - NUCLEAR - ALABAMA POWER CMPANY, 1980 - JOSEPH H. FARLEY NUCLEAR PLANT Participated in procedure development, start-up testing ard initial criticality on through commercial operation on Unit I. Other duties included direction ard training of now licensed operator on shif t. 1974 - Assistant Plant Operster - NUCLEAR - ALABAMA POWER CmPANY, 1975 - JOSEPH H. FARLEY NUCLEAR PLANT Participated in system level testing during the Start-up phase. Duties included procedure verification ard actual performance in conjunction with surveillance over operating plant equipment. 1971 - Annistant Plant Operator - ALADAMA POWER CmPANY, DARRY STEAM PLANT O l
. RESIME Mer ton O. B ishop EDUCATION Memphis State University - 32 semester hours of Nuclear Reactor Furdamentals -
1981 StDe4ARY OF EXPERIENCE
- 1. Fourteen years experience in the operation, maintenance, personnel training, and equipment installation associated with a 62.5 *t (20 me) liquid metal cooled fast breeder reactor.
- 2. Five years experience in the operation ard maintenance of the propulsion equipment associated with a nuclear power submarine.
- 3. Eight months experience as forest fire fighter in northern Idaho.
- 4. One year experience as shipfitters helper. Included construction and repair of barges, tug boats, ferry boats, off shore drilling platforms ard river pushers.
- 5. Presently serving as shift supervisor on an operatino crew at River Bend Nuclear Station, a 940 We BWR urder construction at St. Francisville, Louis iana . In this position since August 1980.
PRQ7ECT TYPES
- 1. Naval Propulsion Plant
- 2. Pressurized Water Reactor
- 3. Liquid Metal Cooled Fast Breeder Reactor
- 4. Construction ard Shipbuilding
- 5. Forest Fire Protection
- 6. Bolling Water Reactor .
DETAILED WORK EXPERIENCE i 91f Staten Utilities - Auquet,1980 - present Engloyed in August,1980 as a shift supervisor at River Bend Station, a 940 We BWR urder construction. In this position I have been in charge of the procedure development effort for the Operation Department for four (4) months, in charge of operations personnel dile atterding the Nuclear Reactor Furdamentals Class, Research Reactor Training, ard BWR Training at Crard Gulf Nuclear Plant in Port Gibson, Mississippi for six months. I also represent Gulf States Utilities on the BWR Owner Group Emergency Procedures Subcommittee. During the six (6) month training period at Grard Gulf Station, I attended a six-Week BWR Technology course ard one (1) week Mitigating Core Damage course. 1he remainder of the six months, I was acting in the capacity of Ass 1stant Operations Supervisor. i i 1
O Argonne Na tional Laboratory - 1966 - Auqunt ,198 0 Employed in December of 1966 as operator trainee. Completed training program in December of 19 69. We training program consisted of qualifying in the following five a reas: Coolant, Reactor Operator , Fuel Hardling, Electrical, ard Power Plant. This training program is carried on in addition to performing work duties ard staMing watches on a rotating shift basis. Qualified operators are responsible for knowing ard implementing all a::tions necessary for operating ard maintaining the reactor ard associated systems. This includes 25,600 KVA generator which is operated in parallel with the power grid. Upon ocupletion of qualification I was transferred to the Procedures Group for fourteen months. In this capacity I was responsible for the generation of new operating procedures, review ard updating of existing operating procedures, and prcniding an interf a:e between the Operations aM Engineering Departments in regard to procedural matters. Transferred back to an operating crew at the end of the assignment. Promoted to Foreman of an operating crew in August,1974. In this position I was responsible to the Shift Supervisor for the direct supervision of the crew of fourteen men ard the proper operation of the plant. Promoted to Shif t Superviser in August,1976. In this position I was directly responsible to the Operations Manager for the safe ard proper operation ard maintenance of the plant on a rotating shif t basis. In addition I was responsible for the safety ani proper maintenance of the entire Argonne West Site during my assigned shif t. %is included the Power Plant, Puel Cycle Pacility, Plant Services Facility, ZPPR, ard other support facilities. Also responsible for trainirrj of all perosnnel assigned to my crew. United Staten Navy - 1959 - 1966 (Honorable Discharoe) Progressed from rank E-3 to E-6 while assigned to the USS Snook. During the last 2 years on bonrd was the Leading Petty Of ficer in charge of "M" division. In this capacity I was responsible for the operation ard maintenance of the engine room ard auxilliary machinery spa:e, maintenarce of all qualifications, maintenance of a divisional ard ships training program for division personnel, ard submitting required repcrts. U.S. Naval Prototype (SlW) Naval Reactor Training Station, Idaho (9 mo.) . Served as trainee on the S1w (Submarine) Propulsion plant for 5 months. Upon completion of the training program was assigned as an operator / instructor for 5 mon ths . During the four months as operatcr instructor, my duties included starding watches at various stations ard instructing personnel in the proper operation of the main prcpulsion equipment, turbine generators, air ccepressors, radiation detection equipment, water chmistry control equip.nent, steam genera tor level, control equipment, a rd emergency D/C. O t
1 U.S. Navy Basic Nuclear Power School, Vallego, California (6 months) . O Received instruction in reactor theory, reactor kinetics, algebra, trigonometry, calculus, water chemistry, ard general operating practices of power plants. Also received courses in thermodynsmics, electrical theory, turbine themy, nuclear instrumentation ard radiation safety. Graduated in the top fifty percent of the class. U.S. Navy Training Schools - Various Locations Boot Camp - San Diego, California M4"A" School - Great Lakes, Illinois Submarine School - New London, Connecticut Clearwater Timber Protective Assn., Orofino, Idaho (8 montjh Received instruction and practical experience in map ard compass utilization, fire fighting procedures, ard first aid. Participated in cambatting several large fires ard various small ones. Last 4 months was in darge of a fire crew of eight men. Also participated in aerial reconnaissance of several fires. Burton Construction and Shipbuildina, Port Arthur, Texas (1 year) Employed as shipfitters helper. Assisted in the repair afd the construction of barges, tug bmts, off-shore drilling rige, river pushers ard ferry boats. Also assisted in the installation of large diesel engines for pegulsion purposes as well as smaller equipment fw auxiliary purposes. 1h is included installation, fourviation mounting, aligning, ard checking out the O above listed equipment. On several occasioas wecked for the outside machine sh@ in the repair ard realignment of drive shaft ard seals. O
O RESUME Ellis P. Shankle, Jr. WORK EXPERIENCE Gulf States Utilities - October,1977 to Present Control Room Foreman - January,1981 to present , Presently working at a DWR-6 plant being built by GSU. Duties have included writing a nd reviewing plant operating procedures ard system descriptions. Since Julv of 1983, have been assigned to a shift as supervisor in charge to suppor t the ctart-up testing prog ram. Spent six months on temporary assignment at Grani Gulf Nuclear Station. Successfully comoleted an eight-week BWR-6 Technology program. For the remainder of the time was assigned to a shift as an assistant to the Shift Supe rv isor . Duties wre to provide administrative and operational assistarce during the plant start-up testing program which included flot-Ops testing. Attended G.E. 's BWR-6 Simulator Training program on the Perry Plant Simulator. Completed BWR-6. SRO ani RO certification. IIave completed Memphis State Reactor Fundamentals Program ard the Advarced Operator Training Program. Personnal Reprenentative - May,1980 to January,1981 O Primarily functionei as a recruiter for River Berd. Directly involved in the recruiting, screening, anl hiring of a maiority of the RO and SRO licensing ca n11da tes . Proiuction Tra ininq Representative - October,1977 to May,1980 Responsible for training fossil fuel power plant operations and maintenance personnel in the area of power principles. Have extensive experience in planning ani conducting formal classroom training using a video tape / lecture for ma t. Since January of 1978, hava conducted over twenty thcusard manhours of training for powr plant personnel. This has required the direct supervision of a number of personnel for several weeks at a time. !! ave also been involv,xi in the development of training projrams, training aids, reviewing training programs of other campanies and updating training noterial. Since October of 1977, have functionel without direct supervision. !! ave performed duties withir. quidelines established by the Training Coordirmtor. Unite 1 States Navy - September,1969 to September 1977 O I
Engineering Watch Supervisor Senior watch station for enlisted personnel aboard a nuclear powered submarine. Directly in charge of enlisted engineering watch personnel, responsible for supervising plant watchstanders during all phases of plant operations, ensuring that all evolutions were conducted in accordance with prescribed operational procedure. Have experience in supervising aM conducting an extensive systems testing program as a result of a core refueling @eration. Additional watch stations included Shutdown Reactor Operator, Shutdown Electrical Operator, Electric Plant Control Panel, Steam Plant Control Panel, Auxiliary Electrician arrt Auxiliary Mschinery Space Upper Level. Have a total of six years of plant operating experience on board a nuclear submarine. During that time, have acquired extensive experience operating, troubleshooting and testing equipment and piping systems. Utilizing schematic 3 and piping diagrams, technical manuals, and procedural marmaals. i l O I O i l
O REStNE I4thar R. Schroeder Senior Scientist EDUCATION Ph.D., Experimental / Applied Psychology, Lehigh University M.S., Engineering Psychology, Lehigh University B.S., General Engineering, University of Illinois B.A., Psychology, University of Illinois EXPERIENCE General Physics Corporation 1982 - Present Dr. Schroeder's areas of expertise include task and error analysis, equipment design studies, operations research, and organizational design an$ maragement. fie is currently managing the control room design review at the Trojan Nuclear Power Plant and has assisted in the Salem control room design review. Other representative projects includes supporting NRC research in the application of control room crew task analysis data for human engineering design ard staffing areas, evaluating SPDS placement, reviewing tagging procedures, and assessing the human factors aspects of Emergency Instruction Flowcharts. 1981 - 1982 _U.N. C. Nuclea r Indu strin Dr. Schroeder worked as a human factors specialist, interf acing with engineers at:1 other staff in identifying and solving problems relating to equipment design, the use of procedures, ard training efforts at Hanford's N-Reactor. lie also performed a human factors review of the 105-N control room in support of an ongoing control room upgrade pr og ram. 1974 -1980 Department of Psychology, Moravian College Dr. Schroeder's responsibilities as Assistant Professor Department Chairperson included planning ard coordinating a day ard evening program in psychology involving over 100 majors, servirn on several college committees, supervising irdividual field study, irdependent study, ard honor s projects, ard serving as a:ademic advisor to day ard evening session students having an interest in applied psychology. 1973 Wiqdahl Electric Cmpany Dr. Schroeder worked as a consultant, identifying potential organization problems ard conducting problem solving sessions. O
i 1972 Jewish Employment ard Vocational Services N As an irdustrial psychologist, Dr. Schroeder consulted with several irdJstries ard governmental agencies in order to , develop, validate ard administer " job-related" personnel I selection tests urder a Department of Labor contract PROFESSIONAL Member, Human Factors Society AFFILIATIONS Member, American Nuclear Society PUBLICATIONS " Human Factor s Review of N-Reactor Control Room," U.N.C. Nuclear Industries Report UN1-2097, June,1982.
"A Human Factors Guided Survey for Systems Development, American Nuclear Society Winter Meeting, December,1981, coauthor with D. R. Fowler.
" Control Room Human Factors in Context," American Nuclear Society Winter Heating, November,1982, coauthor with D. R. Fowler in D. E. Friar.
" Learning Style Data Applied to Nuclear Power Plant Training Programs." Paper accepted for presentation at the ANS Annual Meeting, June,1983.
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O REStME Robert E. Price Direc tor, St. Francisville BWR Training Services EDUCATION B.S. Cardidate - Electrical Engineering, The University of the State of New York l U.S. Navy Nuclear Power Training Program / Certified SRO Simulator Inetructor EXPERIENCE Genera 1 Phyaics Corporation l 1982 - Present Mr. Price is responsible for operation of General Physics' St. Francisville office ard directs activities at the River I Bend Nuclear Training Center. He directs all phases of departmental activities including technical performance, budgetary ard cost controls, personnel selection ard training, ard product development ard marketirry. Representative projects includet e Simulator Procurement Mr. Price managed the final procurement stages of the River Berd Simulatcr. Directed the River Berd Factory acceptance test as lead Test Director. e Training Center Precurement O Managed the ceroplete startup of the River Bend Training Center including staf f recruiting, training, material development, ard validation. Laboratory equipment selection, procurement ard acceptance for both I ard C and Chemistry Training Labs, e Research ard Develcoment Directed several advanced projects in the development of evaluation tools fer personnel training; assisted in an extensive study for the Electric Power Research Institute to develcp a computer-based performance measurement system adaptable to power plant simulators. e Conputer-based Education Develcoment Produced, frorn its inception, the General Physics computer-based interactive edtx:stional system, EASY, developed hardware ard software for the system ard wrote much of the educational courseware to support it. O
Q e On-site Trainino Coordinator b Acted as Training Coordinator for the Power Authority State of New York's James A. Fit: Patrick Nuclear Power Plant ard Cincinnati Gas ard Electric Company's William H. Zinumer Nuclear Powr Station; responsible for all site training programs; coordinated Nuclear Regulatory Commission licensing activities; was involved with Final Safety Analysis Report preparation. o On-Site Instruction conducts training programs for licensed ard non-licensed operators, te&nicians. ard station engineering ard management personnel. 1972 - 1975 Stone a rd Webster Enoineerinho Mr. Price was an Associate Engineer at Stone ard Webster. l He was protect Licensing Assistant on the Long Islard Lighting Company's Shoreham Project. Mr. Price was directly involved in the preparation, review ard submittal of the Shoreham FSAR. 1965 - 1972 United States Navy Mr. Price's Navy tuclear experience included positions as Lead Reactor Operator Instructor at a Navy prototype where his responsibilities were preparation ard administration of , an 18 '.mek formal Presentation on pressurized water reactor O' theory ard reactor control systems. Mr. Price qualified as Engineering Watch Supervisce, Reactor Operator, Reactor Techniclan, Reactor Shutoown Watch, Radlation Repair ard
, Calibration Specialist ard Navy Instructor.
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i O RESUME David B. Barks EDDCATION UNIVERSITY OF THINESSEE, Chattanooga, TN B.S. Psychology WORK EXPERIENCE 1980 to present GENERAL PHYSICS CORPOPATION Senior Scientist, Human Factors Group Major Responsibilities:
- l. Participate in human f actors control design reviews for nuclear power plants:
e Omaha Public Power District's Fort Calhoun Station e Gulf States Utilities' River Bend Station e Georgia Powers' Plant Vogtle
- 2. Participate in human factors design review of letter sorting machines for the United States Postal Workers Union.
- 3. Serve as project manager for the task analysis of '
nuclear power plant operator actions: e Develop a methodology to demonstrate what information could be derived from task analysis e Investigat 1 various data sources to demonstrate the applicability to the nuclear power plant environment e Develop performance criteria for Oak Ridge National Laboratory using errors of omission and commission and cunpliance with procedure step for various plants.
- 4. Develop a model of safety-related operator performance that was implemented on a computer to be used as a design evaluation tool. The results were used to provide an alternative to an American National Standards Institute standard.
- 5. Teach supervisory skills to shif t technical advisors at the E. I. Hatch Nuclear Power Plant.
- 6. Assist in the writing of systems training manual for a l
cogeneration power plant for Syncrude Canada Ltd. 1978 - 1980 HENRY J. KAISER COMPANY Principal Generation Construction Turnover Engineer Mrf or Responsibilities:
- 1. Perform and evaluate construction testing for the Cincinnati Gas ard Electric Canpany.
- 2. Ensure accuracy of client deliverables.
- 3. Ensure that appropriate documentation is on file.
PUBLICATIONS " Criteria for Safety-Related Operator Actions: Final s Report," USNRC Report NUREG/CR-3515, January 1984. C(author with E. J. Kozinsky, A. N. Beare, F. E. Gomer, L. H. Gray.
" Nuclear Power Plant Control Roca Task Analysis Pilot Study for Pressurized Water Reactors," USNRC Report NUREG/CR-2598, May 1982. Coauther with E. J. Kozinsky and S. Eckels.
" Criteria for Safety-Related Nuclear Power Plant Operator Actions: Initial Boiling Water Reacters (BWR) Simulator Exercises", USNRC Report NUREG/CR-2534, September 1981.
Coauthor with A. N. Beare, D. S. Crowe, E. J. Kozinsky, P. M. Haas.
" Nuclear Power Plant Control Room Task Analysis Pilot Study for Boiling Water Reactors," USNRC Report NUREG/CR-3415, Jur.s 1983. Comuther with F. E. Gomer, E. J.
Kozinsky, G. F. Moody. O l 1 l l iO 1 ! l l :
RESUME Richard I. Stamm EDUCATION OHIO STATE UNIVERSITY, Columbus, OH M.S. Nuclear Engineering STATE UNIVEISITY OF NEW YORK COLLEGE, Potsdam, NY B.S. Chemistry LICENSES AND CERTIFICATIONS Senior Reactor Operator, Boiling Water Reactor /6 W ,ORK EXPERIENCE 1983 - Present GENERAL PHYSICS CORPORATION Senior Engineer, Engineering Services Department Major Responsibilities:
- 1. Provide technical assistance to power utilities inn e operator ard plant systems precedure development ard preparation e surveillance procedure development e Systems descriptions preparation and review
- 2. Review and evaluate for impact on simulator hardware, software, and training all design changes and proposed facility charges to Southern California Edison's San Onofre Nuclear Generating Station, Unit 2.
1979 - 1982 GENERAL ELECTRIC COMPANY Nuclear Startuo Engineer, Startup Test Operations Unit, Grard Gulf Nuclear Station. Major Responsibilities:
- 1. Revise plant system descriptions.
- 2. Review operating procedures.
- 3. Develop ard teach reactor physics ard applied engineering courses.
- 4. Instruct operators in BWR systems and operations.
Associate Engineer, Radiological Testing ard Instrumentation Unit, Vallecitos Nuclear Center Major Responsibilities:
- 1. Design fuel red scanner detector housing ard shield.
- 2. Develop procedures for monitoring U-235 inventory in waste incinerator.
- 3. Analyze radioisotope transport in radwaste volume reduction process.
- 4. Perform fuel ard piping gamma scans ard dose rate measurements at reactor sites.
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1977 - 1979 ORIO STATE 1& 7ERSITY, Columbus, OR Graduate Research Associate [. Major Responsibilities:
- 1. Participate in the development of ganuna ray cameras for medical use.
- 2. Participate in the design, fabrication, ard evaluation of germanium strip detectors.
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O REStNE Lawrence R. Byrd, Jr. Manager-Boiling Water Reactor Training Programs E DUCATION Graduate Candidate, Law, Jackson School of Law B.S. Caniidate, Dublic Adminstration, U niversity of Miss issippi LICENSES AND Licensed Senior Reactor Operator: Gran$ Gulf Nuclear CERTI FICATIONS Station Senior Reactor Operator Certification: River Bend Simula tor EXPERIENCE General Physics Corporation 7/83 - Present Mr. Byrd is Manager of St. Francisville Boiling Water Reactor Training Programs for General Physics at the Gulf States Utilities River Bend Training Center. June, 1983 Participated in many phases of training activities including development and presentation of the Licensed and Non Licensed Operatcra Training, Simulator and Classrocn Training, and On-site Training. 1971 - 1983 Mississippi Power ani Light Company O As an Operations Instructor, Mr. Byrd developed requalification program, performed NRC walk through exams, and develope $ program for operator pipe line to staff plant with required number or licenses. As an Operations Shift Supervisor , Mr. Byrd supervised shift operations in support of plant operating, testing, and surveillance procedures. He was responsible for safe operation of all equipment and directed the activities of operating personnel on shift. As Nuclear Operator "A", Mr. Byrd supervised personnel on shift in support of plant startup and testing program. As Assistant ard Auxiliary Operator, Mr. Byrd operated auxiliary equipment in support of plant operation, l O
, RESIME s .s David C. Byrd Senior Engineer EDUCATION M.S., Electrical Engineering, Purdue University i
B.S., Electrical Engineering, Purdue University LICENSES AND Certifie$ Nuclear Power Plant Senior Reactor Operator CERTI FICATIONS Instructer, Boiling Water Reactor i EXPERIENCE General Physics Corporation I 1980 - Present Mr. Byrd is responsible for simulator management, training : center management and procurement of training equipment at i 4 the Gulf States Utilities Company River Bend Training Center. Representative projects includet l e Training Material Development Managed the production of training texts, lesson plans t ! and aids for use in systems training an! simulator training for the Gulf States Utilities Company River Bent simulator; participated in the development of the simulator training materials for the Geacgia Power Campany Plant Natdt simulator. e On-Site Training Programs, Tennessee Valley Authority v Conducted simulator trainir.g programs, basic nuclear training, and on-site observation training at Browns Ferry Nuclear Plant simulator. e Training Center and Simulator Procurennent, Gulf States Utilities Company 4 Assisted in the database riccument processing, uesign l review, an5 simulator acceptance testing for the River 1 Bend Simulator; consulted with the River Bend Emergency 4 Coordinator in presenting the Emergency Operating Facility proposal to the Nuclear Regulatory Connission. e Simulator Management Responsible for the operation, maintenance, and modifications of the River Bend Simulatcr. e Training Center Management Responsible for management of entire training facility l including classrooms, laboratories, building grounds, and building service plant. l n
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l I e Training Facility Precurement, Chemistry ard Health Physics Laboratory Manages the procurement ard installation of chemistry laboratory analysis equipment, including a spectroscopy system ard supporting digital analyzer. 1960 - 1980 United States Navy As a Tactics Instructor at the Naval Submarine School, Mr. Byrd taught formal classrocn subjects ard conducted team training in Submarine Combat Systems Trainers. As Director of Tactical Training Devices Division at Naval Submarine School, he managed all phases of training device operation, maintenarce ard modification. He nerved on three nuclear submarines as Main Propulsion Assistant, Supply Of ficer , Comunicator, Operations Officer ard Navigator. Mr. Byrd achieved <Tualifications as Engineering Officer of the Watch, Officer of the Deck, Engineering Officer, ard Executive Officer. He served as a Missile Technician or; a Polaris nuclear submarine. O 1 l l O
(~') RESIME (/ - Joseph C. Praskievicz Executive Director, Power Services Development EDUCATION U.S. Navy Nuclear Power Training Program LICENSES AND Licensed Senior Reactor Operator , Dresden' (BWR) CERTIFICATIOME Licensed Senior Reactor Operator, SEFOR (IMFBR) EXPERIENCE General Physics Corporation 1971 - Present As Executive Director, Power Services Development, Mr. Praskievicz performs special assignments related to program development, simulator procurement and training facility design. In his previous assignment as Executive Director of General Physics' Chattanooga Division, Mr. Praskievicz had overall responsibility for over one hurdred personnel involved in training, procedure writing, simulator based research, simulator procurement, training material development and emergency planning. His responsibilities included marketing ard sales, technical performance, budgetary and cost controls, ard personnel utilization. Representative projects includes e Simulator Procurement Project Director for the Procurement of the Vogtle, Hatch, Palisades, Midlard and River Berd Simulators. Consultant to the procurement of the San Onofre, Fermi, Shoreham ard Limerick Simulators. Corducted feasibility studies ard prepared detailed technical specifications for ten other simulators. e Trainino Center Desion Leads General Physics efforts in the area of training center design ard construction. Participated in the design ard/or construction of eight simulator training c enter s. e Trainino Center Operation Managed all activities associated with General Physics use of the Tennessee Valley Authority's Power Operations Training Center including program development, delivery ard certification. Participated in NRC certification of Browns Ferry afd Sequoyah Simula tors. 4 e Trainino System Development Project Director for development of Systems Appresch to 1 ' Training (SAT) program for sin.alator training. Responsible for conception ard overall direction of the development of EASY, a videotape / computer based
- educational learning system.
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e Plant Operations O Was Project Supervisor fcr the revision ard standardization of BWR plant operating and emergency procedures and revision ard recrganization of the Dresden Nuclear Power Station's administrative ard departmental procedures; researchei system design ard detailed ar+alyses of station operating techniques to develop a uniform approach to the operation of BWR stations. 1969 - 1974 Genera 1 Electric Cernoany Mr. Praskievicz developed ard delivered courses in all phases of BWR theory and operation, including classroom instruction ard sinulator training. He received Atomic
'cargy Commission Reactor Operator ard Senior Reactor
@erator licenses for Dresden Nuclear Power Station.
Previously, Mr. Praskievicz was licensed as Senior Operator on the liquid metal fast breeder reactor (SEFOR) . He gained experierce in sodium ard sodium-potassium (NaK) hardling, remote operation of fuel transfer equipment, fuel assembly ard disassembly equipment, fuel inspection, ard manipulator operation. He was a participant in all phases of the SEFOR project during construction, startup, coeration (including transient ard excursion tests) , ard d ecommiss ioning . He developed original precedures ard techniques for NaK equipment replacement ard plant d ecommissioning . He also worked within inert gas atmosphe res. 1960-1968 United States Navy Mr. Praskievicz served as Electronics Technician onboard Fleet subtrarines USS RAZORBACK ard USS CLAMAGORE. He served as Reactor Oparator ard Engineering Watch Supervisce onbcntd nuclear submarines USS THCM\S JEFFERSON ard USS WILL ROGERS. O
i I i. A RES!ME V Richard S. Groseclose Supervisce, Engineering Projects i EDUCATION B.S., Liberal Studies (Concentration in Industrial Engineering), The University of the State of New York EXPERIENCE General Physics Corporation 1977 - Present Mr. Groseclose provides technical assistance to power utilities and government clients in the areas of quality assurance, training, maintenance programs, inservice - inspection programs, and engineering services. l Representative projects includes i e Quality Assurance Manager, Inservice Inspection Prog rams Developed and implemented Quality Assurance Programs
- during the Inservice Inspection projects for Oyster 5
Creek Nuclear Power Plant, Jersey Central Power ard 2 Light Company, ard Midland Nuclear Power Plant, Units 1 l and 2, Consumers Power Campany. I Quality Assurance Records Validation, Mississippi Power e i ard Licht Company i Managed Quality Assurance Program for records validation at Grand Gulf Nuclear Station, Unit 1. O e Pressure Vessel and System Recertification, National Aeronautics and Space Administration Assisted in the conducting of an integrated recertifi-cation prngen of all pressure vessels and piping systems at thu Goddard Space Flight Center ard the Jet Propulsion Laboratory.
- e Nondestructive Examination, Inservice Inspection Seminar s Teaches inservice inspection-related nondestructive i examination methods at seminars conducted by General j Physics.
e Nondestructive Examination Oualification Procram Development and Revision, Tennessee Valley Authority Revised persor'nel qualification program and prepared general, specific, and practical examinations for ', inspection Levels I, II, ard III for all methods. I
- 1975 - 1977 Nuclear Installation Services Company Mr. Groseclose was a Field Quality Assurance / Quality control (QA/QC) Ma nager. Ne developed construction plans
! and quality assurance procedures for Clevelard Electric l Illumirating Company and managed the QA/QC programs at i Salem Nuclear Generating Station, Unit 1, lO i
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Public Service Electric and Gas Company, ard during steam O generator mcdification work at Donald C. Cook Plant, Irdiana ard Michigan Electric Comparrf. 1974 - 1975 Control Flow Systems, Incorporated Mr. Groseclose was the Manager of Manufacturing. He supervised fabrication, material plannirig ard control, purchasing, scheduling, ard quality assurance for this engineering /manuf acturing company. 1973 - 1974 Florida Power ard Light Comoariy. Mr. Groseclose was a Quality Supervisor in the Plant Construction Department. He implemented on-site quality control for fossil plant cons *ruction ard provided quality control liaison on all nuclear projects. 1970 - 1973 Burns ard Roe, Incorporated Mr. Groseclose was Lead Quality Assurance Engineer. He managed the Burns ard Roe Quality Assurance Program at the Three Mile Islard Nuclear Power Station, Unit 2, General Public Utilities, dJring construction. 1968 - ?970 United Nuclear Corporation Mr. Groneclose was a Senior Irdustrial Engineer. He developed methois, standards, ard precedures for nuclear fuel fabrication ard nordestructive testing. 1966 - 1968 Kirylard Shipbuilding ard Drydock Ccrupany Mr. Gtoseclose was the Quality Control Superintendent responsible for directing nordestructive testing, mechanical ard optical inspections, ard certification of welders, welding procedures, ard lifting equipment. 1962 - 1966 T.D. Associates, Incorpora ced Mr. Groseclose was responsible for product design ard engineering, ard management of quality assurarce, including the training ard supervision of inspection personnel ard performarce of nordestructive testing. 9
RESIME Nicholas L. Borreggine EDUCATION Widener College - Courses in Electrical Engineering Stone & Webster Engineering Corporation - Various Continuing Education Courses in Electrical Design ard Instrumentation Instrument Society of America - Courses l';. Pressure ard Level Measurement EXPERIENCE SIM4ARY Mr. Borreggine has 16 years of experience in the engineering, design, and construction industries. Currently, as Electrical Design Group Leader, he is responsible for coordinating the efforts of Gulf States Utilities Company, General Electric Company, ard various Stone & Webster Engineer ing Corporation disciplines with regard to the design ard installation of the power generation control complex for the River Berd Station. 1 Since joining Stone & Webster Engineering Corporation in 1974, he has been assigned to two boiling water reactor plant projects as a Senior Electrical Designer, Group Leader, ard Control Systems Engineer. Prior to joining Stone 8. Webster Engineering Corporation, Mr. Borreggine was a Lead Electrical Designer for E. I. du Pont de Nemours ard Company, Inc., DE, w where he was responsible for the conversion of textile process systems from existing hard-wired relay control of conveyer networks to the use of programmable controllers. WORK EXPERIENCE STONE & WEBSTER ENGINEERING CORPORATION, CHERRf HILL, NJ (July 1980 - Present) Appointments: Electrical Engineer - Sept.1981 ' Designer - July,1980 4 River Bend Station, Gulf States Utilities Company (July,1980 - Present) ! As EECTRICAL ENGINEER, directly responsible for coordinating the power l generation control cumplex (PGCE) activities of SWEC, the Client, ard General Electric Company. Responsibilities include providing technical direction and delegating work to assigned personnel. Reviews all electrical ard control i corresporderne ard engineering relating to PGCC. Develops a detailed network for PGCE inst allation interfacing among SWEC, Constructior', ard GE activities. { e l i O
O E. I. DUPONT DEMOURS AND COMPANY, INC. , WILMINGTON, DE (March 1980 - July, 1980) As LEAD ELECTRICAL DESIGNER ia che Control Mechanization Group, responsible for plant modifications necessary fcr implementing updated control systems using mcdular raceway design in conjunction with progrartmable controllers. Duties included maintenarce and development of drawing schedules, coordination of Design ard Construction activities with the site, ard interface with verdor's supplied raceways and programmable controllers. STONE r WEBSTER ENGINEERING CORPORATION, CHERRY HILL, NJ (March ,1974 - March , 1980) River Bend Station, Gulf States Utilities Company (Feb , 1978 - Ma rch , 198 0) As CONTROL SYSTEM 3 ENGINEER, responsible for the preparation of logics, loops, and elementary diagrams for balance-of-plant (BOP) systems. Additional duties included review of P& ids for PSAR updates, verdor drswings, ard engineering-ger.erated documents of other disciplines. Prepared anslog wiring diagrams for BOP instrumentation, including instrument panel arrangement t'rawings and billa of material. Nine Mlle Point Nuclear Station - Unit 2. Niagara Mohawk Power Corporation (March, 1974 - Feb., 1978) As ELECiRICAL DESIGNER, responsible for preparation of interconnection wiring diagrams of relay panels, motor control centers, switchgear, instrument racks, and locally mounted auxiliary panels. Also prepared wiring block diagrams from elementary, logic, ard flow diagrams. Responsible for supervising ard checking work performed by subordinate drafting personnel. GENERAL MOTORS CORPORATION, WILMINGTON, DE (April, 1971 - March, 1974) As ELEC7RICAL TECHNICIAN, assigned to the Manuf acturing Engineering Division of General Motor s' Wilmington assembly plant. Duties included installation of automated equipment; specifically, this included design, fabrication, ard installation of conveyor control systems for assembly line operation. Additional duties included diagnosis ard repair of equipment malfunctions af ter design ard installations were completed. NIXLEAR SERVICE AND CONSTRtCTION COMPANY, INCORPORATED, CAMDEN, NJ (April,1970 - April,1971) As ELECTRICAL DESIGNER, duties included the development of electrical wiring composite installation plans. Developed elementary, isometric, ard connection diagrams for interior ccraunications ard weapons control systems. Performed design work on electrical arrangements in the areas of lighting, power, ccsmunications, fire control, ard centralized control systems. i 1
SUN SHIPBUILDING AND DRY DOCK CCMPANY, CHESTER, PA (June,1966 - April,1970) As JOURNEYMAN ELECTRICIAN assigned to electrical Department, responsible for
- l layout ard design of cableways ard ships' wiring ard operation of electrical systems in accordance with maritime standards ard Coast Guard specifications.
Attained Certified Journeyman Electrician status in the State of Pennsylvania. i O I I O I
O RESUME Charles C. Matson s EDUCATION: Bachelor of Electrical Engineering (Co-op) 1965-1970 Gecrgia Institute of Technology Partial Work on MBA Georgia College at Milledgeville - 1970 - 1971 Georgia State University - 1972 TRAINING: Control Room Design Review Workshep; BWROG/GE 24 hcurs, October 1983. Power Plant Electrician Skills Strike Duty Training; GPC; 80 hours,1981. Noise Control Workshop for Power Plants; EEI/ Bolt, Beranek & Newman; 26 hours,1978. Nuclear Engineering Basics; GPC/NUS; 150 hours,1975. Microprocessor Basic Design & Maintenance Training, SCS/GE: 160 hours,1972. Middle Management Training, GPC; four diffe rent 40- hour c our ses , 1977 - 1982. Signal Corps Officers Training; Communications Equipment & Combat Leadership; U.S. Army; 11 Weeks,1971. EXPERIENCE: 7 Present Project Coordinating Engineer (GPC, Atlanta) for Emergency Response Capability Projects for Plant Hatch (BWR) . Responsible for the prcept ani complete integration of the following TMI projects:
- 1. New Emergency Operating Procedures
- 2. Control Room Design Review
- 3. Safety Parameter Display System
- 4. Emergency Response Facilities
- 5. Reg. Guide 1.97 items
- 6. Training for above 3 7-83 Assistant Project Manager (GPC site) - Cable Tray Restoration Project at Plant Hatch. $4 million crash program responding to NRC findings.
5 3-83 Proj ect Coordintting Engineer - (GPC - Atlanta) Simulator and Skills Training Facilities at Plant Hatch. Responsible for all activities, especially contract
administration, schalule ard budget for $25 million O addition and overhaul to site f acilities. 6 6-82 Project Engineer (GPC - Atlanta) - Hatch Control Room Remodeling Project. Assisted in s&eduling and budget work for architectural inprovements ard panel overlay additions to Control Room, $1.5 million project. 9 6-81 Project Coordinating Engineer - (GPC-Atlanta) Mitchell Balanced Dr: aft Conversion. Responsible for all activities of $7.2 million retrofit of 160 Nt coal-fired unit for balanced draft operation including the addition of solid state control system and control panel inadifications. 10 9-79 Various staf f engineering assignments (GPC - Atlanta) . Including hoists, cranes, elevator s, acoustics, precipitators, cooling towers, plant conceptual design, engineering economy and environmental reports. , 8 3-73 Various plant engineering assignments. Including Results Engineer at six-unit fossil station. Instrumentation ard controls maintenance engineer for approximately eighteen months. Start-up engineer for retrofitted digital load control fcr five fossil units. i 19 65 - 69 Co-op Experience IBM - Research Triangle Park; ' New system circuit testing. IBM - Cape Kennedy , Space Centeer Grourd electrical system laund team member. DuPont - Wilmington Experiment Station; Instrumentation & control system drafting afd fabrication PROFESSIONAL AFFILIATIONS: 1977 - Present, ASME Member - National 1981 - Present, ANS Member - Local t l O l
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O APPENDIX C DOCII4ENTATION FORMS: e OPERATOR INTERVIEW FORM e BWBOG CONTIOL PDOM SURVEY CHECKLIST e HED RECORD e TASK ANALYSIS MRM e INMRMATION AMD CONTROL REQUIREMENT SOURCES e EQUIPMENT CHARACTERISTICS e EQUIPMENT SUITABILITY HEDs e FDDR FORM FOR DESIGN CHANGES REQUESTS O O
- l. OPERATOR INTERVIEW v
INTRODUCTION TO QUESTIONMRE i Job Position l Years Experience Commercial Nuclear Fossil Navy Nuclear
- j R0 SRC
. Date of First License Education / Degree Age Sex Height Weight j
In response to a post-TM1 NRC requirement, your utility, along with j other BWR owners, is conducting an updated control roo- review to identify and correct design dificiencies in the operator-control room jy interface to minimize the potential for human error. This review is ' performed by a survey team, composed of utilit3 . m .:Antc.i.ca a:.d human factor specialists from General Physics Corporation, using checklists prepared by the Control Room Improverc. nts Sabgroup of the BWR Owners Group. You are asked to complete the attached questiona.re bcsing yn:r responses on your operational experience and kno.ieogi. ot your control room and interfacing systems. You may complete this questionaire in the control room if you desire, but please do so wiir. cut uiscums.4 yoar
' detailed responses with other operators completing this survey. If additional space is needed, the attached Comment Form is to be used.
i Following completion, a survey team representative will review your responses with you. Upon completion of all interviews, the survey team will consolidate the information obtained and apply it in their evaluation of your control room for compliance with human factor 4 engineering principles. The biographical 2nformation requested above will be used in compiling 4 3 statistics on operating personnel physical characteristics. Current
! recommendations for panel design are based largely on data obtained from l
! measurements of military personnel; there are few statistics presently i
available as, for example, the average height and weight of operators.
- i ,
This survey provides you with a valuable opportunity for applying your l knowledge and experience toward improving operating conditions in both l your control room and future control room designs. Your honest and forthright opinions are not only welcomed, but needed. l
- Because of the construction status of the River Bend Station, you may substituce your experience on the River Bend Simulator for the plant control room experiences.
O V C-2 l
1 1 OPERATOR INTER \'IEW I. ll QUESTIONAIRE A. Would you recommend any changes in the following areas: Al training A2 color coding A3 control room access As control panel layout or access A5 communciation systems A6 heating or ventilation A7 lighting or noise levels AS data recording and log entries A9 information flow A10 furniture, equipment or workspace All computers A12 other? s O C-3
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- 1. OPERATOR INTERVIEW
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QUESTIONAIRE
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B. Are any controls difficult to operate? C. Are any controls designed, positioned or labeled in a manner that I cause risk of inadvertent operation? I D. Are any recorders or indicators difficult or confusing to read? E. Are any important indicators located such that they are difficult to see during normal or emergency operations? T. Do you feel any control room displays are unnecessary, provide unimportant information or needlessly clutter the control panels? G. Based on your operations) experiences, does your controi room lack ('~J') N any controls or displays needed in your responses to normal or emergency situations? H. Do you consider the annunciator system to be effective in conveying important information to you? l i v l r C-4
! I i l f I
- 1. OPERATOR INTERVIEW I
QUESTIONAIRE ~ ) l
- l. Do you have any problems locating or using procedures or operational instructions?
J. Have you experienced any problems using or understanding your procedures? K. Is there a particular panel which you consider more difficult or confusing to operate than the others? L. General Comments: O i I l l O C-5 i-
I. OPERATOR INTERVIEW 7, COMMENT FORM This form is for use by the operator or interviewer for expanded
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responses to the Operator Interview questiv.>. ~.';.ex. u.,ed , e.d. 4.3 pons e will be identified by item number on this form and also so noted in the space following the applicable question to assure proper cross-referencing. Item Response
^
i . i 9 M ._eM @ N Ch J
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NEDC-30285 III CONTROL ROOM REVIEW Panel
% PANEL LAY 0t.Tr and DE:5IGN A1 For control panels:
A1.1 does the design generally meet measurement 4 3 2 1 0 x 2 = standards per the attached anthropometric diagra=s (cceplete and attach) A1.2 are they of the sa=e laycut and design on 4 3 2 1 0 x 2 = multi-unit plants (not mirror image) A1.3 when panel cceponents are percanently 4 3 2 1 0 x 2 = re=oved , are spaces covered to prevent debris or dust f rca entering panel internals and repainted to avoid visual distinctiveness O A1.4 have sha p corners and edges been 4 3 2 1 0 x 1 : eliminated? A2 Are lines of demarcation, m1=ics er other graphic displays: A2.1 used to distinguish between cocconly shared 4 3 2 1 0 x 2 a syste s or components in multiple mit centrol rooms A2.2 used to enclose related displays 4 3 2 1 0 x 3 = 1 0 A PANEL LAYOUT and DESIGN (Ccatinued) VERTICAL PANEL .EASUR_.N F,NT ( A1.1) Anthropometric Diagram PANEL Jk
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(min / max) a Control height i d (min / max) O I t _ ,,,n min. max. min. max. 60 l a h2 l b 'L8 68 I e -- 88 -- l -~ ~
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HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: HED NO = REVIEWER: TRACKING STATUS: DATA SOURLE: CHEC6; LIST NO. pat 1EL/WORisSTATION NO.
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DESCRIPTION OF DISCREPAf4CY: RECOMMENDATIONS: ACTION: Et,DCR # ISSUE DATE / / FDDR# ISSUE DATE / /
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CRITICALITY RATING: IMFLEMENTATION SCHEDULE: O
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SiO FIELD DEVIATION OF Q] Ol5 POSITION REQUEST SHEET F DDR ORIGIN ATOR DATE
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UNIT i PR OJE CT l EOUiPMENT (MPL OR DESCRIPTION OR BOTH) DOCUME NT NO. l SH NO.l REV l TITLE 1 1 1 DEVIATION DESCRIPTION Fif t D CONCuenE Nct DATE SITE OC CONcummENcf DATE O SuccESTED DISPOSITION O EXPEDITED DISPOSITION E zPEDITE D DISPOSITION APPR') vat 8V Daft DtSPO$sTsON NE ED D ATE GE SJ PATL REQ. DATE: q) FINAL DISPOSITION SITE PATL SUPPLY: SALV. PATL:0 TAG s 5 AVE O SCRAP DOC REV RE0: O YE5 O NO l POT HUM ENG IMPAC1 O YES C h0 10C INSP RE0: 80**t MTE WORK REQ O VES O N0 3G ' . G GSU GE E.oco O 8 PATL ONLY O G50 Ih ";L FWA D VE5 D NO COS; LL: i^ f ce t - s e,. e JUST!FICATION OF DISPOSITION DECislON (S AFETY, RELI ABIL!To DESIGN VERIFICATION STATEMENT l VEasF6ED sv DATE DRF NO If. APPLICABLE T HIS E QUIPMl ?. ' 115 Ar ETY RE LATED O ves ho i APPROV ALS DATE S AFETY F UNCT TON IS AF F E CTED Ovts No l CX)MPLE TION Rt CORO $UPPLIER ACitON APPROVALS DATE REouiRED eV R E. R EQUIR E D ggaggy y O ns O Ne O "s O No
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O O O-Figure 1 ) DOCUMENT RECEIPT / DISTRIBUTION IAG Project: GSU 2 Docueneet C *--ory: Techn21 Documents Supplied by GSU and Utd.ty Companies Distribution Par =H - Dates m w ie MF=/Reinarks To: Date Notice i Recewed Rd.; 1 Identification Revision Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-39 0 RPV Control EOP-1 File 4-10-84 4-10-84 GSU-250-40 0 Emergency Operating Procedures f primarv rnnainwne ennevnt mp-7 i gen y pera ng Procedures Mle 4-10-84 4-10-84 .GSU-250-41 0 Secondary Containment Control EOP-3 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-42 O Radioactivity Release Control EOP-4 l I Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-43 0 Level Restoration EOP-5 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-44 0 Emergency RPV Depressurization EOP-6 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-45 0 Steam Coeling EOP-7 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-46 0 Core Cooling Without Level EOP-8 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-750-47 0 Alternating Shutdown Cooling EOP-9 1 Emergency Operating Procedures File 4-10-84 4-10-84 GSU-250-48 0 RPV Flooding EOP-10 l ! l 4 1
l 0 d O 5 e v 2 s e i e c U t a e S D R G lII t - i c j e l l a e o c i c r e t P R o N 4 4 4 4 4 e 8 8 C 4 4 4 4 4 t 8 8 8 8 8 8 a - - - d - - - 0 0 0 - - - n D 1 1 1 1 1 1 1 1 1 1 o - - - - - - - 5 5 5 i t 4 4 4 5 5 5 5 u b i r t : s D To e i e e e e e e e e e l l l l l l l l l l i i i i i i i i i i F F F F F F F F F F G O L s t N s r e a O I i n h T a c p w U m o B o l I F 1 e R T S I C i t y k s r a s e r u s e r u
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- Received Identification Revision Description / Remarks To: Date Notice i Received File GSU-251-89 Video tape log for DCRDR & V&V task analys .s 5-7-84 5-7-84 I
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Task Analysis Worksheet - Remote Shutdown File 8-28-84 8-5-84 GSU-250-139 Task Analysis Workr,heet - Inability t File 8-28-84 8-5-84 GSU-251-140 Determine React or Water IcVel Task Analysis Worksheet - Primary Contmt File 8-28-84 8-5-84 GSU-251-141 Temp Task Analysis Worksheet - Alternate Cool- File 8-28-84 8-5-84 GSU-251-142 Ing Injection Memorandum - File Code G4.15 - Monthly File 8-28-84 Status Report - Detailed Control Room 8-13-84 GSU-250-14 3 Design Review - River Bend Unit 1 8-1-84 GSU-250-144 Gulf States Ltr. File Code G15.2.1 File 8-28-84 GSU Audit Of Vendors Closing Action Status For QAFR's Equipment suitability HEDs File 8-28-84 7-31-84 GSU-250-145 Equipment Suitability IIEDs File 8-28-84 8-4-84 GSU-250-146 File 8-28-84 6-27-84 GSU-250-147 EOPs ulf States Utility File Code M . G15.2.1 File 8-28-84 8-24-84 CSU-250-148 Ltr. GSU Audit of Vendors Extension of Revised Corrective Action Due Dates for OAFR's O O e
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- Distribution Recall - Dates Received Identification Revision Description / Remarks To: Date Notice i Received 9-10-84 GSU-250-159 S rt by IIED With Priority and BWR Owners Group Checklist 9-10-84 File 3-10-84 GSU-250-160 S rt by Checxlist With Priority / Panel /IIED 9-10-84 File 9-10-84 GSU-250-161 5 rt by Checklist / Panel /IIED # 9-10-84 File 6-27/84 GSU-250-162 RBS EOPs 9-10-84 File 9-19-84 GSU-250-163 Prioritization of IfEDs on SPDS/ Accident 9-19-04 Iil" Monitoring Instrumentation 9-19-84 GSU-250-164 Deletion of liEDs 9-21-84 File 9-28-84 GSU-250-165 Prioritized llEDs 9-28-84 File 10-3-84 GSU-250-166 Telecon Priorities 10-3-84 File 10-3-84 GSU-250-167 Dispositioned liEDs 10-3-84 File 10-3 -84 GSU-250-168 Link Analyses 10-3-84 File O O O
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10-3-84 G3U-250-179 Task Analysis Scenarios - I 10-3-84 File i 10-3-84 GSU-250-180 Task Analysis Scenarios -J 10-3-84 Filc h 10-3-84 GSU-250-181 Task Analysis Scenarios - K 10-3-84 File l(' 10-3-84 GSU-250-182 Task Analysis Scenarios - L 10-3-84 File 10-3-84 GSU-250-183 Task Analysis Scenarios - M 10-3-84 File 10-3-84 GSU-250-134 Task Analysis Scenarios - N 10-3-84 File 10-3-84 GSU-250-185 Task Analysis Scenarios - O 10-3-84 File 10-3-84 GSU-250-186 Task Analysis Scenarios - P 10-3-84 File l 10-3-84 GSU-250-187 HECs - Criticality #1 10-3-84 File 10-3-84 GSU-250-188 IIEDs - Criticality #2 10-3-84 File g 9 $ G G G
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O APPBNDIX E SYSTEN IESCRIPTIONS I O O i f
- - - - - - - - - - _ _ _ _ _ _ _ , _ _ _ _ mv w,,.,y. ._ , _ _
PL ANT SYSTEM I: UNCTION DESCRIPTION RIVER BEND NUCL EAR PL ANT F 'L(,t i l SYSTEtt IJAML: hLAC10R f'RUTECTION SYSTEM SY S I Lt1 aDDREVIATIOrl: RPS SYSTEtt t1Ut1LLR 1 SYSTLil DTATUS (SAFETY /NON-SAFETY): SAFETY SY ST Et1 F UNL1 10t4 ( S ) : ttONITOf(S CRITICAL PL. ANT PARAMETERS FOR CONDITIONS THAT COULD THREATEN THE FULL OR COOLfdlT SYSTEM DOUNDARIES, AND PROVIDES AUTOMATIC REACTOR TRIPS IF SCl F'OINTS ARL REACHED. Pht. VENTS FUEL DAMAbE, LIMITS NUCLEAR SYSTEM PRESSURE, AND RESTRICTS THE , RELEASE OF RADIOACTIVE MATERIAL. COND11IOtG iUR SYSTLM USC: AN/ TIME Af4/ RODS ARE f40T FULLY INSERTED. SYB1Er1 F RUCLDUhE REI ERENCES: 1--ARF -7'7, 1 --50f - 19 O REVIEUCit: DAVID DYRD DATE: 4-3-84 0 - - - - - - - - - - - - - - - - - - - - - - a
PLANT BYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT { PLA111-SYSTEM NAMCs Ef1CRGEllCY CORE COOLING SYSTEM S'yblEM ADDhEVlbl 1014; ELCL SYSTEM NUMDER: 2 SYS1EM STATUS (SAFETY /NON-SAFETY): SAFETY __________________________- - - _ = _ _ _ _ . - - .. SYG1EM FUNC1IOrl(S): , THE ECCS IS COMPRISED OF ADS, HPCS, LPCS AND THE LPCI FUNCTION OF RHR. IT PROTECTS THE CORE AGAINST FUEL CLAD DAMAGE DURING/FOLLOWING LOCA ACROSS THE i I SPECTRUM OF LINE DREAl: SIZES. CONDITIONS FOR SYSTEM USE: , SEE INDIVIDUAL SYSlEM DESCRIPTIONS.
! SYSTEM PROCEDURE
REFERENCES:
1 1 J i ____________________________________________________________________________,,_ f REVIEWCRs DAVID DYRD DATE: 4-3-84 i i 1 i l 1 1 I 4 I i I i i ? d 4 1
- , , - . . - _ - _ ~ - _ - . - - - - - _ - , _ . -_.-- -,-- - . - . ___,--,,n -
, ,.--,_,-_n.,- -. - - , - . -
PLANT SYSTEM frWNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT l F L AtJ1 LYSTEM NAME: AUT OhAT I C DEPRLSOURI Z AT 1014 SYSTEM i SYGl Ef1 ADDREVI ATION: ADS SYOlEt1 Nut 1 DER: 2 SYOTEM GTATUS (SAFETY /NON-SAFETV): SAFETY GYSlEM FUf JL i 1 Orl(L ) : 10 DLPRESSURIZE THE REACTOR Ot1 A SMALL DREAl' LOCA TO ALLOW THE LOW PREbSURL ECCG'S TO ItJJECT ItJTO THE REACTOR VESSEL. CONDITIOtJS FOR SYSTEM USE: Et1ALL DhEAl: LOCA IfJ WHICH THE HIGH PRESSURE ECCS CANNOT RESTORE PRESSURE VESGEL LEVEL. S(LTEM PROLEDURE
REFERENCES:
I - ARP --29, 1 -SOP -27 O REVIEWER: DAVID BYRD DATE: 4-3-84 l O
ALANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLAtJ1 SYSTEM 14AMCs HIGH PREbtURE CORE SPRAY SYSTEM OYSTEt1 ACBREVI ATIOtis HPCS SYS1EM taut 11tER: 2- SYCTEM CTATUS (SAFETY /NON-SAFETY): SAFETY i
----------------------------------------- -- - - = _ _ _ .---------------------
SYLTEM Fut4C110N(S): TO INJECT WATER A's HIGH PRESSURE INTO THE REACTOR VESSEL ON A LOCA THAT DOES NO1 Ih'1EDIATELY DEPRESSURIZE THE REACTOR. CONDITIONS FOR SYSTEM USE: ANY LOCA IN WHICH THE AUTOMATIC INITIATION CONDITIONS ARE REACHED: 2 PSIG It4 THE DRYWELL OR LEVEL 2 (-30 ItJCHES WITH RESPECT TO NARROW RANGE INSTRUMEtlT ZERO). SYSTEM PROCEDURE
REFERENCES:
1-ARP-30, 1-SOP-30, 1-AOP-26 O l ---------------------------------------==__ . _ _ - _ _ = _ .
- - = _ _ _ _ _ _ ___ __------_-----
REVIEWER: DAVID BYRD DATE: 4-3-84 N 4 i i l O
PL ANT SYSTEM frWNCTION DESCRIPTION RIVER BEND NUCL EAR PL ANT PLANT SYSTEM NAl1C: LOW l'RESSURE CORE SPRAY SYSTEM S't S1 Ett ADDREV1 A110f 4: LPLS SYSTEM NUMEER: 2 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEri FUtJCTION :SJ : AUTOMATICALLY SPRAYS LOW PRESSURE WATER ON TOP OF THE REACTOR CORE INSIDE THE REACTOR PRESSURE VESSEL SHROUD TO REMOVE HEAT AFTER A LOCA, DEPRESSURIZATIOfJ, AND LINCOVERING OF THE FUEL. cot 1DITIONS FOR SYSTEM USE: AUTOMATIC IfJITIATION CONDITIONS: DRYWELL PRESSURE AT OR ADOVE 2 PSIG OR REACTOR VESSEL LEVEL AT LEVEL 1 (-144" WITH RESPECT TO WIDE RANGE INSTRUMEfJT ZERO). INJECTION OCCURS WilLt1 REACTOR PRESSURE FALLS DELOW PUMP DISCHARGE PRESSURE. SYSTEM PROCEDURE
REFERENCES:
1-ARP-32, 1-SOP-32 0 REVIEWER: DAVID DYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLAT 11 SYSll:M tJAME: F<LSil>UAL HE AT REMOVAL SYSTEM (LPCI MODE) CYSTEM ADDREVI A TIOtis RHR1 SYSTEM flUMBLfis 2 SYSTEM S1ATUS (SAFETY /i!ON-SAFETY): SAFETY SYS;EM FUNCllON(S): THE LOW PRESSURE COOLAtJT INJECTION (LPCI) MODE OF RHR AUTOMATICALLY INJECTS COOLANT INTO THE REACTOR VESSEL FOLLOWING A LOCA WHEN REACTOR PRESSURE HAS DECREABED DELOW THE DISCHARGE PRESSURE OF LCPI. COf4DITIONS FOR SYSTEM USE: LCCA: HIGil DRY WELL F'RESEUT(L (2 PSIG) OR LOW VESSEL LEVEL -144". SYS TEM PROCEDURE
REFERENCES:
1-ARP-31, 1-SOf *- 31 O - - - - - - - - _ - - - - - - - - - - - - - _ _ - - - - - - - = _ _ _ _ . . . _ _ _ _ __ REVIEWER: DAVID DYRD DATE: 4-3-84 O
PL. ANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PL AtJT SYSTEM NAME: CONTAINNENT AND REACTOR VESSEL ISOLATION CONTROL SvSIEM ABBREVIATION: CRVICS SYSTEM NUMDER: ~. SYSTEt1 STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUNCTION (S): INITIATFS (RCPD) AUTOMATIC CLOSURE OF VARIOUS REACTOR COOLANT FRESSURE BOUNDARY SETPOINTS. CONTAINMENT ISOLATION VALVES IF MONITORED PARAMETERS EXCEED ND LIMITS LOSU OF COOLANT FROM THE RCPB AND RELEASE OF RADIOACTIVE MATERIALS FROM THE DRYWELL OR cot 4TAlt4 MENT. CONDIT IC;JS FOR SYST EM USE: WHEN MONITORED LEAKAGE PARAMETERS EXCEED SETPOINTS. SYSTEM PROCEDURE REFFRENCES: 1 -- APP - 4 , 1-SOP-4 O REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT C F LAt41 SYSTEM NAME: MAIN STEAM ISOLATION VALVE (MSIV) POSITIVE LEAKAGE CONTROL S YSTEM bYSTEM ADDREVIA110N: MSIV SYSTEM NUMDER: 4 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
- _ - - - - - _ _ - - - _ _ _ - - - _ - - - - _ - = - - - = - - - _ - _ _ _ _ = = - _ _ _ __-===-- _ =-- - _ - _______
SYSTEM FUNCTION (C): FRESSURIZES THE MAIN STEAM LINES FOLLOWING A LOCA TO SEAL THEM AGAINST At4Y LEAKAGE OUTSIDE CONTAINMENT. COMPRESSED AIR IS INJECTEL BETWEEN THE TWO CLOSED MSIV'S IN EACH MS LINE. PREVENTS RELEASE OF FISSION PRODUCTS TO THE ATMOSPHERE. CONDITIONS FOR SYSTEM USC: POST LOCA CONTAINMEtJT SEALING. SYSTEM PROCEDURE
REFERENCES:
1-ARP-34, 1-SOP-34 _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ - - _ _ _ - __ = _ _ _ _ - _ _ RCVIEWER: DAVID BYRD DATE: 4-3-S4 O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PL ANT PLANT 5/C1LM NAME: STAtJDDY GAS TREATMENT SYSTEM CY31EM ADDREVIATION: SBUT SYGTEM NUMUER: D CYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY CYSTLM F UNCT I ON ( C ) : FROCESSES POTENTIALLY RADIOACTIVE EXHAUST AIR FROM THE CONTAINMENT ANNULUS, AUXILIARY DUILDING, AND CONTAINMENT /DRYWELL PURGE SYSTEMS PRIOR TO RELEASE THROUGH THE PLANT EXHAUST DUCT. USES TWO IDENTICAL 100*/. CAPACITY REDUNDANT FILTER TRAINS. COf1DITIONG FOR SYSTEM USE: ON A LOCA SIGNAL (2 PSIG DRYWELL FRESSuRE OR RPV LEVEL 2) OR EXTREME HIGH ANNULUG RADIATION. GTS AUTOMATICALLY INITIATES AND MAINTAINS ANNULUS VACUUM. IT MAY DE DELIDERATELY UCED TO PROCESS AIR FROM ANY OF THE VENTILATION VOLUMES SERVED TO PREVENT POSSIBLE INADVERTENT RELEASE OF POTENTIALLY COtJTAMINATED ATMOCPHERE OR ALLOW RAPID VENTILATION IF NORMAL VENTILATION IS LOCl. SYSTEM PROCEDURE
REFERENCES:
1-ARP-43, 1-SOP-43 REVIEWER: DAVID BYRD DATE: 4-3-84 l 9
PLANT SYSTEM FUNCTION DESCRIPTION (3 RIVER BEND NUCLEAR PLANT O PLAN 1 SYSTEM NAME: CONI AINNLtJ1 COMDUSTIBLE GAS CONTROL SYSTEM SYSTEl1 ADDREVIATIO!Ja CCGC SYSTEM NUMDER: 6 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUtJCTION(S): CONSISTS OF THE HYDROGEN MIXING SYSTEM HYDROGEN RECOMBINERS, AND THE HYDRUGEt1 PURGE SYSTEM AS A BACKUP. MONITORING FOR HYDROGEN IN CONTAINMENT IS PROVIDED-DY THE CONTAltJMENT ATMOSPHERE MONITORING SYSTEM. CONDITIONS FOR SYSTEM USE: USED AFTER LOCAS FOR HYDROGEN MIXING SYSTEMS AND HYDROGEN RECOMBINERS. USED AFTER A LOCAC AtJD DURING NORMAL OPERATION HYDROGEN ANALYZER. SYSTEM PROCEDURE
REFERENCES:
CPM ARP-04, SOP-84; CMS te HYDROGEN RECOMBINES ARP-40, SOP-40 0
- _ - - - - - _ - - - _ - - _ - - - - - - - - - - - - _ _ _ _ __ _ __=__-_ _-_--_
REVIEWER: DAVID 1:YRD DATE: 4-3-84 ( l l 0 - 1
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT FLAN 1 SYSTEM NAML: PL ACT OR F'L AN T VENTILATION SYSTEM S's bl Lt1 AEDHLV1 AT ION: HVR1 SYSTEM NUMBER: 7 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSlEM F UNE T IUN (S) : HVR LONSISTS Or FOUR SUBSYSTEMS: 1. ANNULUS PRESSURE CONTROL SYSTEMS, 2. CONTAINMENT /DRYWELL PURGE SYSTEM, 3. CONTAINMENT COOLING SYSTEM, 4. ANNULUS MIXING SYSTEM. CONDITIONS FOR SYSTEM USE: SEE THE FOLLOWING SUDSYSlEM DESCRIr'TIONS. SYSTEM PROCEDURE
REFERENCES:
O REVIEWER: DAVID BYRD DATE: 4-3-84 i i l O
PLANT- SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PL6t il SYST EM 14AME: RESIDUAL l!LAl REMOVAL, SUPPRESSION POOL COOLING MODL SNC1EM ADDREVIA110tJ: RHR2 SYSTEM IJUMDER: C SYSTEM STATUS (SAFETY /NOtJ-SAFETY) : SAFETY
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SYSTEM FUNCTIOrl(S): MAINT AINS THE SUPPRESSION POOL TEMPERATURE BELOW REQUIRED LIMITS TO ENSURE THE POOL WILL DE #DLE TO RECEIVE ALL THE ENERGY RELEASED DURING A LOCA. AFTER A LOCA, THIS MODE CAN LE USED TO REMOVE DECAY HEAT DEPOSITED INTO SUPPRESSION POOL. RHR PUMPS A At1D D ONLY CAN DC USED FOR THIS MODE. CCflDIT10145 FOR SYSTEM USC: WHEN SUI'PRCUSION PUOL TEMPERATURE APPROACHES LIMITS. NORMALLY, IT IS MAINTAINED DELOW 95 DEGREEES F. SYSTEM PROCEDURL
REFERENCES:
I-ARP-31, 1 -SOP--31 O REVIEWER: DAVID DYRD DATE: 4-3-84 O-
- 1
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCL EAR PLANT F'ANI SYL1 Ln lu,ME: L1 AN!'Lv OERVICE WATER L.O1 L:n AbEitLVlsi1U:4: StJ;'l SYEl EM NUMI-:LR: 9 LYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYST EM F LitJt'T ION (S) : f'ROVIDES COOLING OF CERTAIN NORMAL SERVICE WATER (NSW) HEAT LOADS IF NORMAL SCRVICE WATER IS LOST. LOADS I MF' ORT AN1 10 EAFETY INCLUDE DIESEL GENERATOR COOLERS, RHR SYSTEM HEAT CXCHANGERS, CONTAINMENT UNIT COOLERS DURING LOCA, & RPCCW COOLERS IF NSW IS LOL1. CONDITIONS FOR SYDTEM USE: LULO DF NUf(MAL 0! NVICE WATEic l'RESSURE; LOSS OF RFCCW PRESSURE; MANUAL INITIATION. SYSTEM F ROCEDLIRE REI ERENEED: 1 - ARF' - 4 2 , 1 -SOP- 4.' O 3 REVIEWER: DAVID DYRD DATE: 4-3-84 i O
PLANT SYSTEM FUNCTION DESCRIPTION l RIVER BEND NUCLEAR PLANT (v] PLANl SYSIEM NAME: CONTROL BUILDING VENTILATION BY31LM ABDRLVIAIION: HVC l SYSTEM NUMDER: 10 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
- - - = _ . . __-- . -- ______
SYSTEM FUNL110f4(S): PROVIDEC VErlTILATION AND AIR CONDITIONING FOR THE CONTROL BUILDING, INCLUDING CONTROL ROOM t< ADJOINING SHIFT SUPERVISOR OFFICE, KITCHEN AND TOILET FACILITIES. IF LOCA OR HIGH RADIATION CONDITION IN THE LOCAL AIR INTAKE IS DETECTED, THE VENTILATION SYSTEM WILL AUTOMATICALLY REALIGN TO A SELF-CONTAINED SYSTEM WITH THE RECIRCULATED AIR BEING PROCESSED BY CHARCOAL FILTERS AND REPLACEMENT AIR DEItJO TAKEN FROM A REMOTE INTAKE. CONDITIONS FOR SYSTEM USE: SHIFTS TO EMERGENCY MODE AUTOMATICALLY WHEN SIGNALS (LOCA, HIGH RADIATION) ARE DETECTED. SYSTEM PROCEDURE
REFERENCES:
1-ARP-58, 1-SOP-58 O _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ = = = - - - - _ REVIEWER: DAVID BYRD DATE: 4-3-84 r I
P L_ A N T SYSTEM fr W N C T I O N DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT CYSTEM NAME: ST A!JDLY SLF<VICE WATER PUMP HOUSE VENTILATIOrl SYSTEM SYSTEM ABBREVIATION: SSW-HVAC SYSTEM NUMDER: 11 SYSTEM S1ATUS (SAFETY /NON-SAFETY): SAFETY CYLT EM FUNCT IOtJ tS) : MAINTAINS PROPER AMBIENT 1EMPERATURE t< HUMIDITY AROUND STANDBY SERVICE WATER PUMPS, ASSOCIATED ELECTRICAL SWITCHGEAR AND TRANSFORMER TO ENSURE RELIADILIT( ItJ CASE OF LOCA OR LOSS OF tJORMAL SERVICE WATER. CONDITION 3 FOR SYSTEM USE: CUNl1NUOUS SYSTEM FRUCEDLIRE
REFERENCES:
O REVIEWER: DAVID BYRD DATE: 4-3-84 l i O
J PLANT SYSTEM FUNCTION DESCRIPTION
- RIVER BEND NUCLEAR PLANT F'L AN1 SYSTEM NAME
- AUXILIARY DUILDING VENTILATION SYSTEM SiClEM AUBRLVIATION: .HVRS SYCTEM NUMDER: 12 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
. _ _ = - - . --
SYSTEM FUNCTION (C): MAINTAINS AREAS IN AUXILIARY BUILDING CONTAINING SAFETY SYSTEMS WITHIN DESIGN i TEMPERATURES. DIRECTS EXHAUST AIR THROUGH A FILTER SYSTEM AUTOMATICALLY ON LOCA OR HIGH IsADIATION CONDITION. CONDITIONS FOR SYSTEM USE: CONTINUOUS. SHIFTS 10 CMERGENCY MODE AUTOMATICALLY ON LOCA OR SIGNAL OF HIGH RADIATION IN EXHAUST. SYSTEM PROCEDURE
REFERENCES:
l J O REVIEWER: DAVID DYRD DATE: 4-3-84 4 1 l i i f O
PLANT S Y S T E P1 F UNCT I ON DESCRIPTION RIVER BEND NUCLEAFR PLANT PLANT SYSTEM IJAME: FUEL DUILDItJfs VENilLATION SYSTEM CYGTEM ADbHEVIATIOll: HVR6 SYElZM NUMEER: l '_. SYSTEM STATUS ( SAFET Y/rJON-S AFETY ) : SAFETY SYSTEM FUNCTION (S): VEtJTILATES AREAS IN FUEL BUILDING WHERE FUEL HANDLING OPERATIONS ARE DONE. PROCESSES POTENTIALLY RADIOACTIVE AIRDORNE MATERIAL FOLLOWING A DESIGN BAS LOCA. COfJDITIONS FOR SYSTEM USE: CorJT IrJUOUS. AUT OT1AT I C ALLY ALIGNS FOR EMERGENCY FILTRATION ON A LOCA OR HIG FUEL BUILDING RADIATION COtJD I T I ON. SYSTEM F'ROCEDUI.E rsEFTI<EfJLES: O REVIEWER: DAVID DYRD DATE: 4-3-84 1 t l { O
PLANT SYSTEM FUNCTION DESCRIPTION A RIVER BEND NUCLEAR PLANT U PLAr4T SYSTEM NA!1L: REAC10R CORE ISOLATION COOLING SYSTEM GYSTEM AUDREVIATIOt4: RCIC SYSTEM NUMBER: 14 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
--------------- _=----== ___ ==_ -
_ - - =_ = SYC1EM FUtJC1IUN(S): F'ROVIDES A MEANS 10 FEED THE REACTOR VESSEL TO MAINTAIN LEVEL CONTROL WHEN FEEDWATER SYSTEM IS NOT AVAILABLE & REACTOR IS HOT WITH STEAM AVAILABLE TO DRIVE RCIC TURBINE. TURBINE-DRIVEN RCIC PUMP DISCHARGES INTO VESSEL VIA FEEDWATER LINES. EXHAUST FROM THE TURDINE IS DIRECTED INTO THE SUPPRESSION POOL. CONDITIONS FOR SYSTEM USE: 1)REO.CTOR VE5SLL ILULATED & MAINTAINED IN HOT STANDBY.2) REACTOR VESSEL ICOLATED WITH LOSS OF FEEDWATER SYSTEM.3)ON PLANT SHUTDOWN WITHOUT NORMAL FEEDWATER TO DEPRESSURIZE VESSEL SO THAT RHR SHUTDOWN COOLING CAN BE
, INITIATED.
j 4)RCIC I!4 CONJUNCTION WITH HPCS MITIGATES THE SEVERITY IF A DESIGN BASIS ROD DROP ACCIDEt4T. SYSTEM PROCEDURE REFEREt4CES: 1-ARP-35, 1-SOP-35 0 . REVIEWER: DAVID BYRD DATE: 4-3-84 i l l i O
PLANT SYSTEM Ft_fN C T I O N DESCRIPTION RIVER BEND NLICLEAR P L_ A N T PLAril SYS1L11 NAT1E: RLSll>L%L !!E AT REMOVAL SYSTEM SYSTEt1 ADL :iLV I AT IOt4: RHR3 SYST Et1 IJUML:ER: 15 SYST Lt1 CifTUS (SAFETY /NON-SAFETY): SAFETY SYSTLM FUNLlIONtL);
- 1. LOW F'RESSURL COOLANT INJECT . (LPCI) MODE: AUTOMATICALLY INJECTS COOLANT INTO REACTOR VESSEL FOLLOWING LOCALDEPRESSURIZATION OF REACTOR TO WITHIN OPER(4TINO PRESCURE LIMITS OF RHR SYSTEM.2. SUPPRESSION POOL COOLING REMOVE DECAY HEAL FROM SUPPR.3.SHUTDOWt1 COOLING MODE: ret 10VL DECAY HEAT FORM THE REACTOR DURING SHUTDOWN COtJDI T IUNS. 4. CTEAt1 CONDENSING MODE: LIMITS AMOUNT OF DECAY HEAT REJECTED TO SUPPRESSION POOL WHEN REACTOR VESSEL IS ISOLATED FROM THE MAIN CONDENSEH AND FEEDWATER PUMPS ARC NOT AVAIL.
S. FUEL POOL COOLINS ASSIST :SLIPPLEMENTS THE FUEL POOL COOLING SYS.TO REMOVL HEAT FROM THE FUEL POOLS.6. cot 4TAINMENT FLOODING MODE A STANDBY METHOD OF INJr_C1 ING WALER INTO THE REAETOR VESSEL FROt1 THE SERVICE WATER INTO THE REACTOR VEGEL FROM SER.WAT.SYS CONDIlIONS FOR SYSTEt1 USE: ANY OF THE SIX CONDITIONS IMPLIED ADOVE. SYSTEM PROCEDURE
REFERENCES:
1 - AR P- !.1, 1-COP-31 REVIEWER: DAVID BYRD DATE: 4-3-84 l l 9
I l PLANT SYSTEM FUNCTION DESCRIPTION
/7 RIVER BEND NUCLEAR PLANT PL4t li SYSTEM NAML: STANDDY LIQUID CONTROL SYSTEM SYS1LM ADDREVIATION: SLC SYSTEM NUNDER: 16 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
------------------------= =. _
_===- --
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SYSlEM FUNCl ION (S): PROVIDES REDUNDANT, INDEPENDENT BACKUP FOR CONTROL RODS WHICH ENADLES OPERATOR TO MANUALLY SHUT DOWN REACTOR FROM RATED POWER TO COLD SHUTDOWN & MAINTAIN IT SHUTDOWN IF CONTROL RODS CANNOT BE INSERTED. NEDATIVE REACTIVITY IS INSERTED BY INJECTION OF A SODIUM PENTABORATE SOLUTION THAT POISONS THE REACTOR. CONDITIONS FOR SYSTEM USE: BASED ON HEA1 CAPACITY TEMPERATURE LIMIT (HCTL) OF SUPPRESSION POOL FOLLOWING FAILURE-TO-SCRAM WITH ISOLATION: GOAL OF EOP BASES IS TO COMPLETE INJECTION OF MINIMUM WEIGHT OF DORON TO ATTAIN SHUTDOWN PRIOR TO REACHING HCTL IN ORDER TO AVERT NECESSITY TO DEPRESSUNI2L WITH THE REACTOR CRITICAL. HCTL USED IS THAT FOR RPV PRESSURE AT THE LOWEST SRV SETPOINT. SYSTEM PROCEDURE
REFERENCES:
1-ARP-20, I-SOP-20, 1-AOP-30 O b
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REVIEWER: DAVID DYRD DATE: 4-3-84 i i
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT FLANT CYSTEN NAME: RLMU IE LHLITDOWil CYSTEM CYSTEM ADDREVI ATIOrd: RSS CYST EM tJLIMUEF:: 17 SYCTEM ST ATUS (SAFETY /NON-SAFETY): SAFETY SYST Ltl F UNCT ION (S) : THOVIDES LOCATIOf1 6 MEANC TO SAFELY SHUT DOWN REACTOR & MAINTAIN IT CHUT DOWt1 IF TitC COtJ1ROL ROOM BECOMES UrJUSEABLE FOR THIS PURPOSE. CONDITIONS FOR SYSTEM USE: cot 1 TROL ROOM UNAVAILABLE. SYSTEM PROCLDURE REF EREtJEES: 1 - AR P - 2 ', , 1-SOP-27, 1-AOP-31 0 REVIEWER: DAVID DYRD DATE: 4-3-84 O
l PLANT SYSTEM -FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYC1CM FJAME: SAFETY-REL'ATED DISPLAY INSTF(UMENTAT ION , I l l SVGTLM ADDREVIATION: SRD SYSTEM T1 UMBER: 1C SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
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SYST EM FUNCT 1014 (S) : PROVIDES INFORMATION TO OPERATOR ENABLING'HIM TO MONITOR TRANSIENT FsEACTOR PLANT DEHAVIOR At4D VERIFY PROPER SAFETY SYSTEM PERFORMANCE. CONDITIONS FOR SYSTEM 'SE: 3 ANY TRANSIENT REOdIRING USE OF SAFETY SYSTEMS, WHETHER AUTOMATICALLY OR MANUALLY-INITIATED. SYSlEM PROCEDURL
REFERENCES:
f O - - - - . - - - - - - - - - - - - - . - - . REVIEWER: DAVID DYRD DATE: 4-3-84 i 9 F l 1 O I i
PLANT SYSTEM Fr WN C T I O N DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM NAML: RELIICULATION PUMP TRIP SYSTEM ADEREVIATION: RP 1 SYST EM NUM'JETi: 19 SY S'. EM SlATUS (SAFETY /NON-SAFETY): SAFETY l SYSTEM FUNClION(S): TRIPS RECIRCLfLATION PLIMPS EARLY IN TRANSIEN' CAUSED BY A GENERATOR LOAD REJECT OR TURBINE TO IflCREASE t< TRIP. THIS RAPIDLY REDUCES CORE FLOW CAUSING VOID CONTENT ItlSERT NEGATIVE REACTIVITY WHICH AIDS REACTOR SCRAM IN OVERCOMING POSITIVE REACTIVITY THAT RESULTS FROM THE PRESSURE INCREASE ON THIS TRANSIENT. CONDITIONS FOR SYSTEM USE: TURUINE MAIN STOP VALVES UH CONTROL VALVES FAST CLOSURE, MAIN GENERATOR TRIP ON LOAD REJECT. SYSTEM PROCEDURE
REFERENCES:
O REVIEWER: DAVID DYRD DATE: 4-3-84 l O
PL. ANT SYB' REM F= UNCTION DESCRIPTION j RIVER BEND NUCLEAR PLANT F'L AIJ i CYSTEt1 NAME: LLAt: DEILC110tJ SYSTEM SYSTEM ADBREVIATIOl4: LDS1 CYG1EM NUMDER: 20 CYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - - = _ - - - - - - - - - - - - - - SYS1EM FUNCTION (S): ' MUNIlORS VARIOUS TEMPERATURES, PRESSURES, LEVELS, FLOWS, & RADIATION LEVELO TO ALARM LEAKAGE CONDITIONS L, IN SOME CASES, TO ISOLATE LEAKAGE PATHS IN ;
)
REACTOR SYSTEMS. l 1 CONDITIONS FOR SYSTEM USE: OF'ERATION OF- MUNITORED REACTOR PLANT SYSTEMS. l SYSTEM PROCEDURE
REFERENCES:
1 J O _______________,.____ - _ _ _ _ _ _ _ _ _ - - - - REVIEWER: DAVID BYRD DATE: 4-3-84 i 0 l i i i i
,O 1
1
, -m. , , . . - . - , - - - - . , , ,, , , - , , , , . - , , , - - , . ,.,-n----- - , , , , . - . - - - , - - , - - , ---
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLI,fil SYSTEM tJAME: NL U T ROlJ MONITORING SYSTEM S (STEM ADDi<EVIH i 1ON: IlMS SYSTEM NUMF:LR: 21 SYSTEM ST/,TUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUNCTION (SJ: PROVIDES NECESSARY NEUTRON FLUX t< POWER DISTRIBUTION INFORMATION OF REACTOR CORE DURING STARTUP, iEATUP, & POWER RANGE OPERATIONS. DETECTS CORE CONDITIONS THAT COULD THREATEN FUEL BARRIER INTEGRITY DUE TO EXCESS POWER GENERATOR ON TRANSIENTS, EXCESS POWER-TO-FLOW CONDIlIONS, OR ABNORMAL DISTRIBUTION OF FLUX AS CAUSLD DY IMPROPER ROD PATTERNS. AS CONDITIONS REACH LIMITS, NMS SIGNALS RCIS OR RPS TO IN1TIATL NOD WlTHDRAWAL LtLOCKS OR SCRAMS. CONDITIONS FOR SYSTEM USE: ALL I L Alfi CONDlllONL SYSTrM PROCEDUF:E
REFERENCES:
1-ARP-74, 1 --SOP- 7 4 0 REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSlCM NAME: RADIATION MONITORING SYSTEM BYSTEM ADDREVIATION: RMSI SYSTEM NUMBER: 22 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY __ - - - _ _ - - - . ------= SVCTEM FUNCTION (S): MEACURES, EVALUATES, & DISPLAYS RADIOACTIVITY IN PROCESS STREAMS, IN LIQUID L GASEOU3 EFFLUENTS, & IN PLANT AREAS WHERE RADIOACTIVITY COULD BE , RELEASED. LIMITS RELEASE OF RADIOACTIVE MATERIALS TO ENVIRONMENT BY GIVING ALARMS WHEN LIMITS ARE APPROACHED CONDITIONS FOR SYSTEM USE: CONTINUOUS SYSTEM PROCEDURE
REFERENCES:
I O ____-______-_______-.---__ _ _ - - = - - -- _ _ - - - - - __ ___-----_--- REVIEWER: DAVID DYRD DATE: 4-3-84 1 6 1 i !O 1
l PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PL A'J1 SiSTEM NAME: FULL POOL COOLING t< CLEANUP SYSTEM SYSTEl1 ADDREVIATIOrl: FPCCS SYST EM tJUME'ER: 27 SYCTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUNCTION (S): F ROVIDES COOLING OF POOLS ItJ F UEL BUILDING t< CONTAINMENT. MAINTAINS LEVEL, TEMPERATURE L PURITY OF WATER IN THESE POOLS. HEAT IS TRANSFERRED TO RPCCW SYSTEM. Mfd;EUP 15 FROM CONDENSATE STORAGE TANK. CONDITIONS FOR SYSTEM USE: CONTINUOUS. STANDDY SERVICE WATER cat 1 BE USED AS ALTERNATE MAKEUP SUPPLY. SYSTEM PROCEDURE
REFERENCES:
O e REVIEWER: DAVID BYRD DATE: 4-3-84 9
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLAN 1 SYSTEM NAME: F'ENElRATION VALVE LEAKAGE CONTROL SYSTEM SYSTEl1 ADDREVIATION: PVLCS - SYSTEM NUMBER: 24 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
- _ _ _ - - - = _ _ _ _ - - - - = - - - - _ _ - - - - - - -
= _ _ - ___- =- . - - _ _ _ _ _ _ _ _ _
SYCTEM FUNCTION (S): SEALS PROCESS LINES INTO/FROM CONTAINMENT DY INJECTION OF COMPRESSED AIR BETWEEN DISCS OF DOUBLE-DISC GATE VALVES AT CONTAINMENT BOUNDARY, THUS PREVENTS ANY RADIDACTIVE LEAKAGE FROM BYPASSING STANDBY GAS TREATMENT SYSTEM OR FUEL DUILDING CHARCOAL FILTERS. CONDITIONU FOR SYSTEM UOL: POST-LOCA SITUATION IN WHICH CONTAINMENT IS SEALED. , SYSTEM PROCEDURE
REFERENCES:
1-ARP-41, 1-SOP-41 i
- - - - -_ __-_==_ -_______
REVIEWER: DAVID DYRD DATE: 4-3-84 I f i l l l !O
T PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT F L A!J1 SYSTEM l l Al 'T. : ROD l'AITEf:fJ CONTROL SYSTEM SiSILt1 ADDRLVIAIIOlJ RPCS SYSTEM NUMUER: 25 SYSTEM CTATUS (SAFETY /NON-SAFETY): SAFETY S'iS1EM F Ut'CT I LiN ( S ) : LIMITS SEVERITY O F' 'IRANSIENT OtJ A ROD DROP. ACCIDENT DY RESTRICTING ROD MOVEMCt4 T TO ACCEPTADLE POD PATTERf43. CONDITIONU FDR SYSTLM USEt ClAf(TUP, HOT OPElli' T I ON AT LOW POWER, AND SHUTDOWrJ SYSTEM PROEELURE RLFERLtJCES:
, O REVIEWER: DAVID D(RD DATE: 4-3-84 1
s O
\
1
- . .. . - .- _ ._ _. - - - = - - _ - .. . . -. . -. . . . ~ .
t i e + . PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT s PL AtJ T SYSlEM t1AME: SAFELY RELIEF VALVES 4 !?,'t G I Li1 1BBRLV I.4 t luu SRV SVG1EM NUMliLR 26 SYSTEM STATUS (SAFETY /NOtJ-S AFETY) : SAFETY l
-- . ------------- -- -----------------==_- . _- _.
SVE,ILt1 FUNCl lutl(Ci l REDUCE 0VERPRESSURE CONDITIONS IN REACTOR VESSEL THAT COULD LEAD TO FAILURE 1 ! OF REACTOR COOLANT PRESSURE BOutJDARY.
= COtJDITIOt45 FOR SYSTEM USE:
l PRESSURE INCREASES TO THE SETPOINTS OF THE SRVS. SYD1EM PROCEDURE
REFERENCES:
1 i i i I l
-= - - , - -
---------__ ---------------- - - - _ - _ - - = _ _ _ _ = _ - - - - - - - -
l l - REVIEWER: DAVID BYRD DATE: 4-3-04 6' 1-t s' l ) l 1 i 4 i i . I ; 4 j s j .I 1 I f i d I , f 4
' N'
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR P L_ A N T PLANT SYSlEM IJAME: LONTROL I:UILDING CHILLED WATER SVGTLM AbbREVIATIOtJ: HVK SYSTEM NUMDER: 27 CYCTEM CTATUS (SAFETY /NON-SAFETY): SAFETY __------_----_--------~~------------_-__-------------__----__----- --_------- SYSTEM rUNCTION(S): ALSURE THE MAIN CONTROL ROOM AREA, THE STAND BY SWITCH GEAR ROOM, AND THE CHILLER EDUIPMENT ROOM HVAC UtJITS HAVE ADEQUATE CHILL WATER DURING NORMAL SHUTDOWi1 OR EMERGENCY CONDITIONS. CONDITIONS FOR SYSTEM UCE: NORMAL, SHUlDOWN Ok fiECIDENT CONDITIONS OYSTEt1 FROCLDURE
REFERENCES:
A R f '- 66 , SOi*-66 0 REVIEWER: LEE MILLER DATE: O
. _ . . .- ~. . ..
PLANT SYSTEM FUNCTION DESCRIPTION O RIVER BEND NUCLEAR PLANT V PLArn SYSTLM NAME: E.TANDDY I'OWER SUPPORT SYSTEMS f SYU1LM ADDREVIATIOt4: EG4,EGF SYSTEM NUMBER: 20 SYCTEM CTATUL (SAFETY /NON-SAFETY): SAFETY
- - - - --. -- --=--
SYLlEM FUNCTION (C): INSURE THE AVAILABILITY OF THE DIESEL GENERATOR AUXILI ARY SYSTEMS. MANUAL CONTROLS FOR DIESEL STARTUP AT DIESEL GENERATORS AND REMOTELY IN MAIN CR. CONDITIONS FOR SYSTEM USE: COtJDITION UNDER WHICH THE RESPECTIVE DIVISIONAL ECCS SYSTEMS ARE AUTOMATICALLY INITIATED OR FOLLOWING A LOSS OF RESPECTIVE BUS VOLTAGE. CYC1EM IROCLDURL
REFERENCES:
ARP-52, ARP-53, SOP-52, SOP-53 I O ------ ..------------------------ _ _ _ - - -- --_-_e==---__ -- REVIEWER: LEE MILLER DATE: IO 1 1
..-w,- -e -
-., y- r., -,-,--.-e.,,,.---e,---, --,------.---g,
1 I l PL ANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLAf4T LYSlEM NAME: DIECEL GENERATOR BUILDING VENTILATION SYSTEM CYSTEM ADDREV1ATION: HVP GYCTEM NUMDLR: 29 SYSTEM STATUS (CATETY/NON-SAFETY): SAFETY SYSlEM FUNCTION (L): MAINTAINS THE DG BUILDING WITHIN ITS DESIGN TEMP TO ENSURE PROPER OPERATIOrJ OF DG'S. CONDITIONS FOR SYSTEM USE: WHEN DG IS IN OPERATION AND OUTDOOR TEMP IS 96 DEGREES OR GREATER. SYSTEM PROCEDURE
REFERENCES:
ANP-61, SOP-61 0
~~--_---------------_ --_--_--__---_____-__ _ _ _ _ _ _
REVIEWER: LEE MILLER DATE: O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PL. ANT PLANT SYSTEM NAME: HYDROGEt1 MIXING SYSTEM SYSTEM ADDRCVIATION: CPM SYS1EM NUMBER: 30 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUNCTION (S): REDUCES HYDROGEN CONCENTRATION IN THE DRYWELL BY REMOVING AIR FROM THE DRYWELL. THE SYSTEM REPLACES THE AIR REMOVED FROM THE DRYWELL WITH AIR FROM CONTAINMENT OUTSIDE THE DRYWELL. CONDITIONS FOR SYSTEM USE: POST-LOCA SITUAT ION IN WHICH HYDROCEN CONCENTRATION HAS BUILT UP INSIDE THE DRYWELL. SYSTEM PROCEDURE
REFERENCES:
1-ARP-40, 1-SOP-40 REVIEWER: DAVID BYRD DATE: 4-3-84 I l O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR P L_ A N T F L AtJT SYSTEM TJAML: DIESLL GEt1ERATORS SYSTEM ABBREVIATION: DG A&9 SYSTEM NUMDER: 31 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY SYSTEM FUNCTIOTJ(S): PROVIDE STANDDY 4160 i:.V POWER TO STANDBY BUSES A & B AND HPCS BUS RESPECTIVELY (THESE BUSES POWER ECCS'S & OTHER SAFETY SYSTEMS).DG-A - DIVISION I,DG-D - DIVISION II, HPCS DG - DIVISION III (HPCS BUS) CONDITIONS FOR SYSTEM USE: EMERGENCY GlART SIbNAL (LOSS OF POWER TO STANDBY BUSES OR LOCA) SYSTEM FROCEDURE
REFERENCES:
1-ARP-52, 1-ARP-53, 1-SOP-52, 1-SOP-53 0 REVIEWER: DAVID DYRD DATE: 4-3-84 9
l PL ANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM NAME: HYDROGEN RECOMDINER SYSTEM SYSTEM ADDREVIAlION: HCS SYSTEM NUMBER: 32 SYSTEM STATUS (SAFETY /NON-SAFETY): SAFETY
- - - - - - - - - - - - - - - - - - - - - = - - - - _ _ _ _ _ - - - - --
SYSTEM FUNCTION (S):
' REMOVE HYDROGEN FROM CONT AINME*4T ATMOSPHERE. THE TWO RECOMBINERS ARE LOCATED INCIDE CONTAINMENT, OUTSIDE AN.) ABOVE THE DRYWELL.
CONDITIONS FOR SYSTEM USE: IN A POGT-LOCA SITUATION WITH THE HYDROGEN MIXING SYSTEM OPERATING TO REMOVE / DILUTE HYDROGEN FROM THE DRYWELL ATMOSPHERE. CYSTEM PROCEDURE
REFERENCES:
1-ARP-40, 1 --GOP-40
- O - - - - - - - - - - - - - - - - - - - _ _ - _ _ _ - - - - - - - - - - _ -_ _ ._
REVIEWER: DAVID BYRD DATE: 4-3-84 4 f I O l l l _. - _ _ . _ . . - = , _ _ . . . _ . _ _ . - . _ _ _ - _ _ - _ _ . - _ _ _ ___
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT FLArJ1 SYSTEM NAML: ANNULUS MIXING SUDSYSTEM SYS'ILM ADDREVI ATIOth iIVR4 SYSTEM NUMBER: 33 SYSTEM SlATUS (SAFETY /NON-SAFETY): SAFETY SYSTLM iUNC1IOt1(S): MIXES THE ANNULUS AIR AND DILUTES RADIOACTIVE CONTAMINANTS, IF PRESENT, DY EXHAUSTING AIR FROM A NUMBER OF EXHAUST DUCTS LOCATED HIGH IN THE ANNULUS AND DISCHARGING THE AIR TO SUPPLY DUCTS LOCATED LOW IN THE ANNULUS. THE MIXING FANS ARE LOCATED OUTSIDE THE ANNULUS IN THE AUXILIARY BUILDING AND DISCHARGE THE SAME AIR REMOVED FROM THE ANNULUS BACK INTO THE ANNULUS. CONDITIONS FOR SY!$ TEM USE: A LOCA SIGNAL PRELENT (2 PSIG DRYWELL PRESSURE OR LEVEL 2 RPV LEVEL ) OR EXTREME HIGH ANNULUS RADIATIOt4 SIGNAL IN THE APCS EXHAUST WILL STOP THE APCS FANS. SGT AND T HE ANNULUS MIXING FANS START AND ANNULUS PRESSURE IS MAINTAINED DY SGT. SYSILM PfiOLEDURE
REFERENCES:
O REVIEWER: DAVID DYRD DATE: 4-3-84 9
PLANT SYSTEM FUNCTION DESCRIPTION O V RIVER BEND NUCLEAR PLANT PLANT SYSTLM NAME: NUCL EAR STEAM SUPFLY SHUTOFF SYSTEM (CONTAINMENT ISOLATIOt1 5 YSTEM) SYS1LM ABbHLVIATION: NSSSS SYSTEM NUMBER: 34 S*/ STEM ST ATUS (SAFETY /NON-SAFETY): SAFETY ______________ =_ __ _____ SYSTEM FUNCTION (S): OPERATES AUTOMATICALLY 10 ISOLATE REACTOR AND/OR PRIMARY CONTAINMENT TO MAINTAIN THEIR INTEORITY, WHEN LEAKAGE CONDITIONS ARE DETECTED, TO PREVENT OR MITIGATE CONSEQUENCES OF LOCA & TO MINIMIZE RELEASE OF RADIOACTIVITY AS RESULT OF DESIGN BASIS ACC I DEtJT . MANUAL ISOLATIONS ARE PROVIDED IN THE CASE OF FAILURE OF THE AUTOMATIC FUNCTIONS. CONDITIONS FOR SYSTEM USE: ANY OF VARIOUS FORMS OF LEAKAGE THAT WILL CAUSE ALARMS AND/OR AUTOMATIC ISOLATION 3. MANUAL OPERATION IF AUTOMATIC OPERATION FAILS TO PROPERLY FUNCTION. SYSTEM PROCEDURE
REFERENCES:
1-ARP-4, 1-SOP-4 O ___=- - - _ _ - __ - - _ _ _ _ _ _ _ _ _ _ - - - - __ REVIEWER: DAVID BYRD DATE: 4-3-84 i l O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT FLANT SYSTEM NAME: ANNULUE F'RESSURE CONTROL SYSTEM S(STEM ABBREVIATION: APCS SYSTEM NUMPER: I SYCTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM F UNCT ION (L): MAINTAINS A CLIGHT VACUUM IN THE ANNULUS DURING NORMAL REACTOR OPERATION. ONE OF TWO 100% EXHAUST FANS DISCHARGE FPOM YHE ANNULUS INTO THE PLANT VENTILATION EXHAUST DUCT. DURING A LOCA OR HIGH ANNULUS RADIATION CONDITION THE APCS IS AUTOMATICALLY ISOLATED AND ANNULUS NEGATIVE FRESSURE IS MAINTAINED BY THE STANDBY GAS TREAlMENT SYSTEM. CONDITIONS FOR SYSTEM USE: NORMAL FLANT OPERATION WITHOUT A LOCA SIGNAL OR EXTREME HIGH ANNULUS EXHAULT RADIATION SIGNAL. SYSTEM PROCEDURE
REFERENCES:
1-ARP-59, 1-SOP-59 O REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION O PLANT 'g RIVER BEND NUCLEAR PLANT SYSTEM NAME: NUCLEAR DOILER INSTRUMENTATION SYSTEM ABBREVIATION: B21 SYSTEM NUMPER: 2 SYSTEM STATUS (SAFETY /NON-SAFET7): NON-SAFETY
------------ ___ -=_ _ _ _ - _ - _ _ - - ------
SYSTEM FUNCTIOrJ(S): MOtJITORS PARAMETERS OF LEVEL, PRESSURE, TEMPERATURE, CORE FLOW, JET PUMP FLOW, CORE DIFFERENTIAL PRESSURE, & VESSEL FLANGE SEAL LEAKAGE FLOW. PROVIDES REMOTE & LOCAL INDICATION OF PARAMETERS MEASURED & INPUTS TO REACTOR PROTECTION SYSTEM. EMERGENCY CORE COOLING SYSTEMS, AND NUCLEAR STEAM SUFPLY SHUTOFF SYSTEM FOR AUTOMATIC PROTECTIVE ACTIONS. CONDITIONS FOR SYSTEM USE: ALL PLANT CONDITIONS f SYSTEM PROCEDURE
REFERENCES:
1-ARP-1, 1-SOP-1 0 _ _ - . - - - - - - - - - - = _ - - - - - - - - REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCT10N DESCRIPTION RIVER BEND NUCLEAR PLANT F L AtlT SYSTEM tJAME: CONDENSATE DEMINERALIZER SYSTEM SYSTEtt ADDREVIATION: CND SYSTEM NUMDER: 3 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): FURIFIES CONDENSATE PRIOR TO BEING PUMPED BACK TO REACTOR AS FEED WATER. USED TO CLEAN UP REACTOR COOLANT DURING A STARTUP. CONDITIONS FOR SYSTEM USE: STARTUP; NORMAL OPERATION. SYSTEM PROCEDURE
REFERENCES:
1 - ARI '-93, 1-SOP-93 O REVIEWER: DAVID BYRD DATE: 4-3-84 1 O 1 l l
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PL ANT SYSTEM NAME: CONDENSA1E SYSTEM
- GYS1EM ADDREVIATION
- CNM SYSTEM NUMBER: 4 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
_______-_____________-___=- _ _ _ _ _ _ - _ _ _ _ . __ SYSTEM FUNCTION (S): REMOVES CONDENSATE FROM MAIN CONDENSER HOTWELLS DURING NORMAL OPERATION, PURIFIES IT PRIOR TO BEING PUMPED BACK TO REACTOR VESSEL BY FEEDWATER SYS1EM. DURING STARTUPS IS USED TO RECIRCULATE AND PURIFY THE PRIMARY COOLANT AND CONTROL THE INVENTORY OF COOLANT IN THE REACTOR. CONDIT IONC FOR SYSTEM USE: STARTUf' OR NORMAL OPERATIONS; ALSO DURING ADNORMAL/ EMERGENCY OPERATIONS THAT REQUIRE USE OF MAIN CONDENSER OR CONDENSATE PURIFICATION SYSTEM. CONDENSATE PUMPS ARE AN ALTERNATE WAY TO PLACE WATER IN REACTOR VESSEL IF PRESSURE IS SUFFICIENTLY LOW. SYSTEM PROCEDURE
REFERENCES:
1-ARP-7, 1-SOP-7, 1-AOP-5, 1-AOP-37 1 O 4
--_-_______________________=-- - _ _ __ ___ - __
REVIEWER: DAVID BYRD DATE: 4-3-84 I i -
, . . - _ . _ - . - . - ,- _ _ . . . . - - - _ _ < - . , , _ . . , _ . p .
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM t1AME: CONDENSA1E STORAGE, MAKEUP,L TRANSFER SYSTEM SYSTEM ADDREVIAlION: Ct4S SYSTEM NUMBER: 5 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): PROVILES FOR STORAGE & REPLENISHMENT OF REACTOR GRADE WATER FOR USE IN CONDENGATE SYSTEM L OTHER SYSTEMS REQUIRING PURE WATER. PROVIDES A SOURCE OF PURE WATER FOR INJECTING INTO REACTOR BY THE EMERGENCY CORE COOLING SYSTEMS. PROVIDES PIPING FOR THE TRANSFER OF WATER TO AND FROM CONNECTED SYSTEMS. CONDITIONU FOR SYSTEM USE: ALL PLANT CONDITIONS SYSTEM PROCEDURE
REFERENCES:
1-ARP-8, 1-SOP-8, 1-EOP-10, 1-EOP-8, 1-AOP-37 O REVIEWER: DAVID DYRD DATE: 4-3-84 0
PLANT SYSTEM FUNCTION DESCRIPTION ,Os ( ,/ RIVER BEND NUCLEAR PLANT PLANT SYSTEM NAME: HYDROGEN PURGE SYSTEM BYSTEM ABBREVIATION: CPP SYSTEM NUMDER: 6 SYSTEM GTATUS (SAFETY /NON-SAFETY): NON-SAFETY
- - - _ _ _ ==--
SYSTEM FUNCTION (S): REDUCE HYDROGEN CONCENTRAlION INSIDE CONTAINMENT BY REPLACING CONTAINMENT ATMOSPHERE WITH COMPRESSED AIR FROM THE SERVICE AIR SYSTEM AND BLEEDING AIR FROM CONTAINMENT INTO THE ANNULUS, HENCE OUT THROUGH THE STANDBY GAS TREATMENT SYSTEM. CONDITIONS FOR SYSTEM USE: POST-LOCA WITH A CONCENTRATION OF HYDROGEN INSIDE THE PRIMARY CONTAINMENT. SYSTEM PROCEDURE
REFERENCES:
1-ARP-40, 1-SOP-40
=- -----
REVIEWER: DAVID BYRD DATE: 4-3-84 l l 1 e 1 1
PL ANT BYSTEM FUNCTION DESCRIPTION RIVER BEND N U C L_ E A R Pt_.A N T PLArJT SYSTEM NAME: COtJTROL ROD DRIVE HYDRAULIC SYSTEM S 'ST'iM ADDREVI ATIOtJ: CRDH SYSTEM NUMl;ER: 7 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCT ION (S): F'ROVIDES CLEAN, PURE, FILTERED PRESSURIZED WATER TO CHARGE CONTROL ROD DRIVE MECHANISM (CRDM) ACCUMULATORS; OPERATION OF CRDM*S FOR REACTOR STARTUP, SHUTDOWN,t POWER ADJUSTMENTS DURING NORMAL OPERATION CODING OF CRDM'S; SCRAMMING OF COf4 TROL RODS Ot4 AUTOMATIC PROTECTIVE FUNCTIONS; AND SEAL WATER FOR THE RECIRCULATION PUMPS. CONDITIONS FOR SYSTEM USE: STARTUPS, SHU1DOWNG, NORMAL POWER ADJUSTMENTS, SCRAM TESTING OR ACTUAL SCRAM, OPERATIOrl OF RECIRCULATION PUMP. SYSTEM PROCEDURE
REFERENCES:
1-ARP C, 1-SOP-2, 1-AOP-1, 1-AOP-30, 1-AOP-30, 1-AOP-40 0 REVIEWER: DAVID BYRD DATE: 4-3-84 O
l i PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM NAME: CIRCULATING WATER SYSTEM l t' ! SYSTEM ADDREVIATION: CWS ; i SYSTEM NUMBER: O SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
---- _. =--=-_ - - _
SYSTEM FUNCTION (S): PROVIDES CIRCULATING WATER TO THE MAIN CONDENSERS. CONDITIONS FOR SYSTEM USE: WHENEVER MAIN CONDENSERS ARE REQUIRED. SYSTEM PROCEDURE
REFERENCES:
1-ARP-6, 1-COP-6, 1-ADP-5 i i
-------- ----------- . _ = _ _ _ ----.--------- _--__ -
REVIEWER: DAVID BYRD DATE: 4-3-84 s j l I i l I l t . 1 i I !.O i
. - . - -.,... - - -.- - - -. _-., -,- - . . - - . - - . - - - . - . . . . . . , , - . _ - , , . . - . . _ . - . . . ~ . , - - - , _ - _ , - . , , . . . - . , , . - _ . , . _
PLANT SYSTEM fr WN CT I ON DESCRIPTION RIVER BEND NUCLEAR Pt_ ANT PLANT SYSTEM NAME: ELEC1RICAL DISTRIBUTION SYSTEMS SYSTEM ABBREVIATION: ED SYSTEM NLIMDER: 9 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY S/ STEM FUNCTION (S): DISTRIBUTE ELECTRICAL POWER TO LOADS THROUGHOUT PLANT AT PROPER VOLTAGES. TRANSMIT GENERATED POWER FROM MAIN GENERATOR TO GRID. PROVIDE CONTINUITY OF POWER IO ESSENTIAL AND SAFETY SYSTEM LOADS. CONDITIONS FOR SYSTEM USE: ALL PLANI CONDITIONS. SYSlEM PROCEDURE
REFERENCES:
1- arf'-45 TilROUGH 1-ARP-50, 1-SOP-45 THROUGH 1-SOP-50 0 REVIEWER: DAVID DYRD DATE: 4-3-84 4
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT U 4 PLANT SYSTEM NAt1E: ELEClROHYDRAULIC CONTROL SYSTEM 1 SYSTEM AB!)REVIATIOt4: EHC SYSTEM NU.1BER: 10 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ - - - _ - - - ----_______ ___- -_=- - = - - SYSTEM FUNCTION (S): PROVIDC SPEED t< LOAD CONTROL FOR MAIN TURBINE; PROVIDES AUTOMATIC LOAD FOLLOWING FOR THE MAIN TURBINE; PROVIDES TURBINE PROTECTIVE AUTOMATIC TRIPS. t i CONDITIONS FOR SYSTEM USE:
- MAIN TURDINE OPERATING.
i SYSTEM PROCEDURE
REFERENCES:
1-ARP-14, 1-SOP-14, 1-AOP-2, 1-AOP-41, 1-AOP-17 i i 1 i REVIEWER: DAVID BYRD DATE: 4-3-84 l j e a i e I l i O .
--,-,-,-,.--r-- , , - . , - - - - - - - - , - . - - - - - - , - - , - , - - - - - - - . , - - -- w- - - - - -
---,---..--e----- -r--+w.w -ee. ww-*w-r-.. n --- - - - - --, --<.-ww+~+ --~ - - -
PLANT SYSTEM FUNCTION DESCRIPTION # RIVER BEND NUCL EAR PLANT PLANT SYSTEM NAME: FEEDWATER SYSTEM
- SYSTEM ABBREVIATION: FWS SYSTEM NUMDER: 11 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYS T Et1 FUNC1IUN(S):
PROVIDE PREHEATED mal'EUP WATER TO THE REACTOR VESSEL, AT SUFFICIENT PRESSURE AND FLOW, TO MAINTAIN REACTOR WATER LEVEL DURING NORMAL OPERATION AND CERTAIN ADNORMAL OPERATIONS; F'ROVIDES PREHEATING OF REACTOR COOLANT, USING FEEDWATER HEATERS, PRIOR TO PUMPING Il INTO THE REACTOR. THE FEEDWATER LINES PROVIDE A PATH FOR OTHER SYSTEMS tSUCH Af3 THE RHR SHUTDOWN COOLING MODE) TO PUMP INTO THE REAC10R VESSEL. CONDI110NS FOR SYSTEM USE: NORMAL OPERATION 5; DURING SHUTDOWN WHEN SHUTDOWN COOLING IS IN PROGRESS; DURING A0 NORMAL / EMERGENCY CONDITIONS AS A PATH VIA WHICH COOLANT CAN DE INJEC1ED ItGO REACTOR; FROVIDES PURIFICATION PATH FOR COOLAN'6 CLEANUP DURING STARTUP. SYSTEM PROCEDURE
REFERENCES:
1-ARP-9, 1-SOP-9, 1-ARP-10, 1-SOP-10, 1-AOP-6, 1-ADP-7, 1-AOP-23 REVIEWER: DAVID DYRD DATE: 4-3-84 O
l 1 PLANT SYSTEM FUNCTION DESCRIPTION - - . RIVER BEND NUCLEAR 5='L A N T PLATJT SYSTEM NAME: GEtJERATOR HYDROGEN SEAL OIL SYSTEM SYSTEM ADDREVI AllON: GMD
*SYGTEM NUMDER: 12 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
------------------------------ ___ -. _=-- - - - - - --
= - _ - _
CYGTEM FUNCTION (S): i PREVENTS LEAKAGE OF HYDROGEN COOLING MEDIUM INTO TURBINE BUILDING ATMOSPHERE THROUGH GENERATCR SEALS. 4 CONDITIONS FOR SYSTEM USE: SYSTEM PROCEDURE
REFERENCES:
1-AOP-2, 1-ARP-19, 1-SOP-19 i t REVIEWER: DAVID BYRD DATE: 4-3-84 l i i O 4 l _. , _.__.--.-.~_.,--._-_,-_._.__,-.m_..___,_.-_-._,.- , _ _ _ . _ . . , _ . . . . _ - - .
f PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT FLANT SYSTEM NAME: GLAND SEAL AND EXHAUST SYSTEM SYSTEM ABBREVIATION: GSS SYG1EM NUMBER: 13 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): SEALS Malt' TURDINE SHAFT GLANDS, REMOVES EXHAUSTED STEAM AND CONDENSES IT. PREVEt1TS LEAKAGE OF RADIOACTIVE STEAM FROM REACTOR ESCAPING THROUGH MAIN TURDINE SHAFT GLANDS. CONDITIONS FOR SYSTEM USE: WitEN MAIN TURDINE IS OPERATED. REQUIRES AUXILIARY STEAM AND AUXILIARY CONDENCATE SYSTEM OPERATION. SYSTEM FROCEDURE
REFERENCES:
1-AROP-15, 1-SOP-15 0 REVIEWER: DAVID BYRD DATE: 4-3-84 O
l l PLANT SYSTEM FUNCTION DESCRIPTION l p J RIVER BEND NUCLEAR PLANT PLAN 1 SVC1EM NAMCs CONTAINMEllT/DRYWELL PURGE SYSTEM faYSTEM ABBREVIATION: HVR2 SYSTEM NUMDER: 14 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = = _ _ = _ _ _ _ = - - - - _ - - - - __
- _ _ - - - - - - _=______
SYSTEM FUNCTION (S): THE HVR SYSTEM CONTINUOUSLY PURGES OUTSIDE AIR THROUGH THE CONTAINMENT AND DRYWELL ATMOSPHERE OR RECIRU'4TES THE CONTAINMENT /DRYWELL AIR THROUGH A CHARCOAL FILTER. THE SYSTEM HAS A PURGE AIR SUPPLY FAN, EXHAUST FAN, CHARCOAL FILTER, AND RECIRCULATION PATH WITH DAMPERL. A HIGHER CAPACITY MANUALLY ACTIVATED SYSTEM IS PROVIDED AS A DACI:UP AND FOR FAST PURGE FOR CONTAINMENT ENTRY. AIR IS EXHAUSTED TO THE STANDDY GAS TREATMENT SYSTEM DURING PURGE. CONDITIONS FOR SYSTEM UCE: NDHMAL OPERATIONS. THE CONTAINMENT AND DRYWELL ARE AUTOMATICALLY ISOLATED DURING LOCA CONDITIONS. SYSTEM PROCEDURE
REFERENCES:
O REVIEWER: DAVID DYRD DATE: 4-3-84 i i 4 e 0 0
PLANT SYSTEt1 FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM f1AME: LONTAINMLtiT COOLING SYSTEM SYSlEM ADDREVIATION: HVR3 SYSTEM NUMDER: 15 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
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SYSTLM FUNCTION (S): FOUR RECIRCULATION FANS RECIRCULATE AIR IN THE CONTAINMENT DOME. THREE UNIT COOLERS PROVIDE COOL AIR THROUGHOUT CONTAINMENT VIA A DISTRIBUTION DUCT. CONDITIONS FOR SYSTEM USE: IN LOCA CONDITIONS, TWO COOLERS (A & D) START AUTOMATICALLY (IF NOT RUNNING) AND CHILLED WATER TO THESE COOLERS ISOLATES. COOLING WATER IS AUTOMATICALLY SHIFTED TO T HE SERVICE WATER SYSTEM. CAPACITY OF EITHER COOLER IS SUFFICIENT TO PREVENT THE CONTAINMENT DESIGN TEMPERATURC LIMIT OF IOS DEC,REES F FROM BEING REACHED. SYSTEM PROCEDURE
REFERENCES:
O REVIEWER: DAVID BYRD DATE: 4-3-84 9
PLANT SYSTEM FUNCTION DESCRIPTION /N RIVER BEND NUCLEAR PLANT Q PLANT SYSTEM NAME: INSTRUNEf1T AIR SYSTEM SYSTEM ABBREVIATION: IAS SYSTEM NUMDER: 16 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYS1EM F UNC1IOt4(S): PROVIDES CLEAN, DRY, FILTERED AIR AT REQUIRED PRESSURES TO VARIOUS COMPRESSED AIR LOADS. PRESSURE IS MAINTAINED TO ESSENTIAL LOADS BY ACCUMULATORS IN SYSTEM WHENEVER COMPRESSORS ARE NOT AVAILABLE. THE ACCUMULATORS STORE SUFFICIENT AIR TO OPERATE ESSENTIAL LOADS SUCH THAT THE DDA CRITERIA ARE MET EVEN IF IT OCCURS DURING A LOSS OF INSTRUMENT AIR. CONDITIONS FOR SYSTEM USE: WHENEVER ESSLullAL SYSlEMS ARE OPERATED THAT REQUIRE INSTRUMENT AIR: MSIV'S; CRDH SYSTEM (INCLUDING AIR-OPERATED SCRAM VALVES); VARIOUS AIR-OPERATED HVAC DAMPERS; OlHER AIR LOADS AS THE SITUATION REQUIRES. SYSTEM PROCEDURE
REFERENCES:
1-ARO-22, 1-SOP-22, 1-AOP-O REVIEWER: DAVID BYRD DATE: 4-3-84 1 j l 1 (~ i \-)h 1 1
PLANT SYSTEM fr W N CT I O N DESCRIPTION RIVER BEND N U CI._ EE A R PLANT PLANT SYSTEM NAME: MAIN STEAM SYSTEM SYSTEM ABDREVIATION: MS SYSTEM NUMDER: 17 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): PROVIDES F'IPING AND ISOLATION VALVES FOR ROUTING STEAM FROM THE REACTOR TO THE MAIN TURBINE, TURDINE BYFASS VALVE SYSTEM, MAIN STEAM REHEATERS, STEAM JET AIR CJECTORS, AUXILIARY STEAM SYSTEM, AND OFFGAS SYSTEM PREHEATERS. CONDITIONS FOR SYSTEM USE: STEAM AVAILADLE FROM THE f(EACTOR. SYSTEM PROCEDURE
REFERENCES:
1-ARP 11, 1 -SOT'- 1 1, 1-ADP-36, 1-AOP-35 0 REVIEWER: DAVID BYRD DATE: 4-3-84 9
l l l PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLAN 1 SYSTEM tJAME: OFF6AG GYCTEM SYSTEtt ADDREVI ATION: OFG SYSTEM '"tMDER: 10 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
- - - - - - - _ _ _ - - = - - - - - - - -
-- -- . _ = -- --------_-- -_--- -
SYSTEM } UNCTION (S): CONTROLS RELEASE OF RADIOACTIVE GASES TO ATMORPHERE. HOLDS UP RADIOACTIVE NODEL GASES TO ALLOW THEM TO DECAY, FILTERS OUT RADIOACTIVE ISOTOPES, RECOMBINES THE HYDROGEN TO CONTROL COMBUSTIBILITY. DILUTES, AND CONDITIONS THE PROCESSED GAS PRIOR TO RELEASE. PROVIDE ELEVATED RELEASE POItJT. CONDITIONS FOR SYSTEM USE: ANYTIME MAIN CONDEtJSER IS OPERATED. AUTOMATIC ISOLATIONS ARE PROVIDED IF RADIOACTIVE RELEASE RATE LIMITS ARE EXCEEDED; ALARMS & INDICATIONS ALERT OPERATOR IF COMBUSTIDILITY IS NOT oROPERLY CONTROLLED. SYSTEM PROCEDURE
REFERENCES:
1-ARP-92, 1-SOP-92 , O
- - - - - - = _ . - - - - - - - - - - - - - - - _ - -- -_-------. . _ _ _ _ _ - - - - - - - - - - - - - - - - .
REVIEWER: DAVID BYRD DATE: 4-3-84 i O
, - . _ -- . . , . . _ . - , - . ,. , - , . . .- .. . . . . c., .,- - - .
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEM NAME: ROD CONTROL L INFORMATION SYSTEM SY31EM ADDREVIATION: RCIS
- SYSTEM NUMBER: 19 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S):
DISPLAYS STATUS L POSITION OF CONTROL RODS. PROVIDES CONTROL OF RODS FOR WITHDRAWAL L INSERTION. PREVENTS ROD WITHDRAWAL OUT OF SEQUENCE L ENFORCES ROD PATTERN DURING STARTUP AND SHUTDOWN. CONDITIONS FOR SYSTEM USE: ANY. SYSTEM PROCEDURE
REFERENCES:
1-ARP-71, 1-SOP-71 O
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - = = - - _____--__--_________
REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION ( RIVER BEND NUCLEAR PLANT PLANT SYSTEM N4ME: REACTOR RECIRCULATION SYSTEM SYSTEM ABBREVIATION: RCS SYSTEM NUMBER: 20 SYSTEM GTATUS (SAFETY /NON-SAFETY): NON-SAFETY
- _ _ _ _ _ _ - - - - ----=-- -___--- _____
SYSTEM FUNCTION (S): PROVIDES RECIRCULATION OF COOLANT THRCUGH REACTOR CORE VIA JET PUMPS.PROVIDES CONTROL OF REACTOR POWER & AUTOMATIC LOAD FOLLOWING DURING NORMAL OPERATION VIA FLOW CONTROL VALVES & RECIRCULATION FLOW CONTROL SYSTEM. JET PUMPS PROVIDE PROTECTIVE FUNCTIONS OF 2/3 CORE COVERAGE DURING LOCA CONDITIONS THAT WOULD EMPTY THE REACTOR VESSEL. CONDITIONS FOR SYSTEM USE: RECIRCULATION PUMP 3, FLOW CONTROL SYSTEM ARE IN USE DURING ALL PLANT OPERATIONS EXCEPT SOME SHUTDOWN CONDITIONS IN WHICH NATURAL CONVECTION PROVIDES SOME RECIRCULATION, OR LOCA CONDITIONS THAT DISABLE A RECIRCULATION LOOP. SYSTEM PROCEDURE
REFERENCES:
1-ARP-3, 1-SOP-3, 1-AOP-24, 1-AOP-33, 1-AOP-49 O REVIEWER: DAVID BYRD DATE: 4-3-84 1 O
i . PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PL ANT PLANT SYSTEM NAME: PRUCESS RADIATION MONITORING SYSTEM SYSTEM ABDREVIATION: RMS2 SYSTEM NUMEER: 21 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (C): MONITOR RADIATION LEVELS AT LOCATIONS THROUGHOUT PLANT WHERE RADIOACTIVE FLUIDS ARE PROCESSED OR COULD LEAK. DISPLAY STATUS OF RADIATION DETECTORS & RADIATION LEVELS. PROVIDES SIGNALS FOR SOME AUTOMATIC PROTECTIVE FUNCTIONS. CONDITIONS FOR SYSTEM USE: ALWAYS. SYSTEM PROCEDURE
REFERENCES:
1-ARP-82, 1-SOP-82 O REVIEWER: DAVID BYRD DATE: 4-3-84 O
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PLANT SYSTEM FUNCTION DEEBCRIPTION
- p. RIVER BEND NUCLEAR PLANT
\ ~
PL(.fl1 SYS1EM NAME: REAC10R PLANT COMPONENT COOLING WATER SYSTEM S(STEM ADDREVI A11014: RPCCW SYSTEM NUMBER: 22 SYSTEM STATUS (SAFETY /NON--EAFETY): NON-SAFETY
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SYSTEM FUNCTION (S): , PROVIDES CLOSED, PURE WATER SYSTEM TO REMOVE HEAT FROM PRIMARY SYSTEMS THAT CONTACT HOT COOLAf4T & TRANSFER HEAT TO SERVICE WATER SYSTEM. CONTAMINATION OF SERVICE WATER BY COOLANT IS PREVENTED, AND ENTRY OF IMPURL SERVICE WATER INTO PRIMARY COMPONENTS IS PRECLUDED. CONDITIONO FOR SYSTEM USC: OPERATION OF ANY OF RPCCW HEAT LOADS: REACTOR WATER CLEANUP SYSTEM PUMP & NONREGENERATIVC EXCHANGER, RECIRCULATION PUMP MOTORS & SEALS, FUEL POOL HEAT EXCHANGERS, RESIDUAL HEAT REMOVAL PUMPS, CONTROL ROD DRIVE HYRAULIC PUMPS & DRYWELL EQUIP. DRAIN SUMP COOLER. SYSTEM PROCEDURE
REFERENCES:
1-ARP-16, 1-SOP-16, 1-AOP-11 O REVIEWER: DAVID BYRD DATE: 4-3-84 4 l lO I i
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PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANI SYSTEN NAME: REACTOR WATER CLEANUP SYSTEM SYSTEM ABOREV I(4 T I ON : RWCU SYSTEM NUMBER: 23 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): MAINTAINS COOLANT PURITY. REJECTS COOLANT INVENTORY TO MAIN CONDENSER DURING PLAT 4T HEATUP. PROVIDES DRAIN PATH FROM VESSEL BOTTOM HEAD TO PREVEf4T TEMPERATURE STATIFICATION DURING LOW RECIRCULATION FLOW. COf4DITIONS FOR SYSTEM USE: ALL PLAT 4T CONDITIONS. ICOLATES IF A LEAK IS DETECTEL' OR IF SLC IS INJLC1ED. SYSTEM PROCEDURE
REFERENCES:
1-ARP-90, 1-SOP-90 0 REVIEWER: DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYSTEt1 NAMC NORMAL CERVICC WATER SYSTEM Sf3lEM ABBREVIATION: SWP2 SYSTEM NUMDER: 24 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY
------------- _ _ :=--_- . _ = - = _ - - - - _ _ _ _ - . --- . = = - - - - - - - - _ = = - - -
SYSTEM FUNC110N(S): HEAT REMOVAL FROM VARIOUS HEAT LOADS THROUGHOUT REACTOR PLANT SYSTEMS: RPCCW TPCCW, CHILLED WATER SYSTEMS, RHR SYSTEM HEAT EXCHANGERS, AND DIRECT GENERATOR COOLERS. ( CONDITIONS FOR SYSTEM USE: CONTINUOUS EXCEPT DURING SOME EMERGENCY CONDITIONS THAT ISOLATE NORMAL SERVICE WATCR & SHIFT TO STANDDY SERVICE WATER FOR SOME COOLINO LOADS. SYSTEM PROCEDURE
REFERENCES:
1-ARP-18, 1-SOP-18, 1-AOP-9 iO i REVIEWER: DAVID BYRD DATE: 4-3-84 i t i 4 I a 4 I i i i O 6 i i s
. - . .__.._.-_._._,,._._,_,,_..,,_,...~.___,.__._-,,.,,__,.,_._,~_,,,,,_,,m. __,.____--..,-c..,____,~~_ .%... y_.
PLANT SYSTEM FUNCTION DESCRIPTION RIVER BEND NUCLEAR PLANT PLANT SYLlEM (JAME: MAIN TURUINE LUDL OIL SYSlEM SYSTEM ABBREVI ATIOr4: TML SYSTEM Nut 1 DER: 25 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYCTEM FUNLTION(S): PROVIDES CLEAN, FILTERED DIL AT PROPER PRESSURE & TEMPERATURE TO BEARINGS OF MAIN TURBINE, DEARING LIFT PUMPS, MAIN GENERATOR BEARINGS, L TURNING GEAR. EONDITIONS F OR SYSTEM USE: ANY TIME THE EHAFT 15 ROTATING OR THE LIFT PUMPS ARE OPERATING. SYSTEM PROEEDURE
REFERENCES:
1-ARP-12, 1 - E Of '- 12, 1 - ADf "-2 0 REVIEWCRs DAVID BYRD DATE: 4-3-84 O
PLANT SYSTEM FUNCTION DESCRIPTION , l RIVER BEND NUCLEAR PLANT ' O s/ F'LAtl1 SYSTEM NAME: TURDINE PLANT COMPONENT COOLING WATER SYSTEMS SYSTEM ADDREVIATION: TPCCW SYSTEM NUMBER: 26 SYSTEM STATUS (SAFETY /NON-SAFETY): NON-SAFETY SYSTEM FUNCTION (S): PROVIDES CLOSED PURE WATER COOLING SYSTEM TO REMOVE HEAT FROM TURBINE PLANT COMPONENTS & TRANSFER IT TO SERVICE WATER SYSTEM. PREVENTS CONTAMINATION OF SERVICE WATER SYSTEM THROUGH CONTACT WITH POTENTIALLY RADIOACTIVE TURDINE PLANT COMPONENTS; PREVENTS CONTACT OF TURBINE PLANT COMPONENTS WITH IMPURE WATER. CONDITIONS FOR SYSTEM USE: WHENEVER ANY OF THE TURDINC PLANT HEAT LOADS ARE OPERATED: CONDENSATE PUMP MOTORS & THRUST DEARINGS; ISOLATED PHASE BUS DUCT COOLERS; MAIN GENERATOR STATION WATER COOLERS; TURBINE PLANT SAMPLE COOLERS 3 INSTRUMENT AIR COMPRESSOR COOLERS; FEEDWATER HEATER DRAIN PUMP MOTOR BEARINGS RADWASTE EVAPORATOR COOLER 5; FEEDWATER PUMPS MOTOR, LUBE OIL, AND SEAL WATER COOLERS 3 CONDENSER AIR REMOVAL PUMP 3 AUXILIARY EDILER COMPONENTS, OFF GAS SYSTEM VARIOUS COOLERS. SYSTEM PROCEDbRE
REFERENCES:
1-ARP-17, 1-COP-17, 1-AOP-12 O REVIEWER: DAVID DYRL DATE: 4-3-84 O
O APPENDIX F OPERATING SEQUENCE DESCRMIONS O I I \ O
A. Operating Sequences Inadequate Core Cooling V Initial conditions: Plant is at 1004 power in the middle of core life, normal system lineup. The following equipment have been tagged outs the "B" Control Rod Drive Hydraulic Pump, Residual Heat Removal Loops "B" and "C", Condensate Pump "A". The plant is generating under a 72 nour limiting condition for Cperation of the Technical Specifications. NOTE: Simulator IC-13 The tagged components have been tripped with simulator malfunctions. The Residual Heat Removal loops were taken out of service to prevent the alternate injection path f rom standby service water. Sequence Initiator: Condensate pumps "B" and "C" trip at the same time resulting in loss of the Reactor Feedwater pumps. The low pressure core spray pump and Residual Heat Removal pump fail to start on Reactor Vessel level one (-144"). The High Pressure Core Spray pump starts, but the injection valve f ails to open. The Reactor Core Isolat!on Cooling system starts, but the turbine trips and cannot be reset. The running Control Rod Hydraulic pump "A" trips. NOTE: Simulator Malfunctions: 15A, B - Control Rod Drive Hydraulic pump trips 51 - RCIC Turbine trips 55 - HPCS injection valve fails to open 6548, C
- RHR pump trips 84A, B C - Condensate pump trips 62 - Low Pressure Core Spray trip.
Progression of Action The crew acknowledges annunciators and attempts to verify the scram and restore reactor water level. The crew attempts to Os restart the condensate pumps. The crew attempts to restore level with High Pressure Core Spray and Reactor Core Isolation cooling. The Shif t Supervisor declares an Alert and plant personnel are notified when reactor water level drope to Level 2 (-30"). The Shif t Supervisor inventories sources of makeup to the vessel. The crew verifies the automatic actions of the containment and reactor vessel isolations which occur at reactor Level 2 (-30") and verify the High Pressure Core Spray diesel generators start. The crew verifies the main steamline isolation occurs at reactor Level 1 (-144"). Reactor pressure is now being controlled by the safety relief valves. The crew manually controls reactor pressure. When the reactor water level stabilizes at the low and of the wide range level indication (-140"), a safety-relief valve will open and stick open until water level reaches the top of active fuel then recloses. The Shift Supervisor upgrades the emergency to site amargency. The crew will attempt to reclose the safety-relief valve to minimize vessel inventory loss. The crew attempts to line up at least two alternate injection subsystemas none can be used. The crew initiates steam cooling. Af ter steam cooling has been initiated, the operator at the High Pressure Core Spray ir'ection valve finally gets it o pe n . High Pressure Core Spray injects to the reactor vessel. O
The crew rapidly depressurizes the core to maximize the injection rate. Five m i r. , 2 later the Residual Heat Removal pump "A" is restored. Reactor water level is being recovered. The Shift Supervisor directs crew to equalize the containment and drywell pressure when reactor water level is restored above Level 2 (-30"). This allows resetting the Reactor Protection System Power Distribution, ECCS Initiation Logics, and Containment and Reactor Vessel Isolation Logics. The crew restarts the drywell cooling system and maintains drywell pressure less than two pounds. The crew continues the reactor cooldown by placing Residual Heat Removal Icop "A" in the shutdown cooling mode. Final Conditions: The reactor is depressurized, being maintained cool by the shutdown cooAing mode of Residual Heat Removal. The containment and drywell isolations are reset. Major systems: Reactor Protection System, Emergency Core Cooling Systems, Coritainment and Reactor Vessel Isolation Control, Main Steam - Positive Leakage Control, Standby Gas Treatraent, Combustible Gas Control, Reactor Plant Ventilation, Control Building Ventilation, Auxiliary Building Ventilation, Fuel Building Ventilation, Reactor Core Isolation Cooling, Residual Heat Removal Shutdown Cooling Mode, Saf ety-related Instrumentaticn, Recirculation Pump Trip, Leak Detection System, Neutron Monitoring System, Radiation Monitoring System, Penetration Valve Imakage Control System, Rod Pattern Control System, Safety - Relief Valves (Relief Mode). O O
l B. Operating Sequences small Break Loss of Coolant Accident p Initial conditions: The plant is at full power with normal plant lineup. V sequence Initiator: Small steam leak in the drywell develops in a weld on safety relief valve F041A joint to the main steam line. NOTE: Simulator Malfunction 97- variable steam leak (50-6000 GPM 0-100% ). For a small steamleak nearly the same as Malfunction 43- coolant leak in drywell (1-30 GPM 0-100% ). Progression of Action: The crew acknowledges annunciators and attempts to identify severity and location of the leak. The crew utilises the drywell coolers to control the drywell pressure and temperature increase. After the leak propagates and the reactor scrams, the crew acknowledges annunciators and verifies the reactor scram and containment reactor isolations. The Shif t Supervisor declares an Alert Condition and plant personnel are notified. Reactor Vessel level is being maintained by the feedwater system. Suppression pool cooling is placed in service to maintain containment integrity. The reactor vessel is being cooled down and depressurised by manually operating the safety-rollef valves. NOTE: Residual Heat Removal-shutdown mode is not available when Reactor Protection system power diatribution is de-energized. Therefore alternate shutdown cooling is required - will be demonstrated with inadequate core cooling. Final Conditions: The reactor is shut down and is being depressurized to the point where alternate shutdown cooling will be used. The reactor feedwater system is maintaining the reactor level. Drywell and containment pressure are 10 psia and 5 psia respectively. nsjor systems: Reactor Protection System, Emergency Core Cooling System, Containment and Reactor Vessel Isolation Control, Standby Gas Treatment, Reactor Plant Ventilation, Residual Heat Removal - Suppression Pool Cooling Mode, Control Duilding Ventilation, Auxiliary Building Ventilation, Fuel Building Ventilation, Safety-related Instrumentation, Leak Detection System, Heutron Monitoring System, Radiation Monitoring, Saf ety-Relieve Valves (Relief Mode). .O l t l
C. Operating Sequence: Main Steamline Rupture in the Drywell Initial Conditions:, The plant has been operated at full power for two weeks with a normal full power lineup. NOTE: Simulator IC-13 1004 power-middle of life. Sequence Initiator: Complete sever of the "B" main steamline. NOTE: Simulator malfunction 98 - complete sever of main steamline "B": between the flow element and the inboard MSIV steamline flow will equal 170% of line flow after the isolation. Progression of Action: The crew acknowledges annunciators and attempts to verify the scram and containment reactor isolation. The sudden reactor vessel depressurization causes reactor vessel level to swell to reactor level 5, tripping the reactor feed pumps, Reactor Core Isolation Cooling turbine and the High Pressure Core Spray injection valve. The crew monitors the containment and drywell parameters and takes action to maintain their integrity. Suppression pool cooling is placed in service. The Shif t Supervisor declares a site emergency and plant personnel are notified. The operating crew restores feedwater system to operations, maintaining reactor vessel level. The reactor vessel is depressurized through the main steamline break. , For continued cooldown of the vessel the operating crew de-energizes equipment in the bottom of the drywell to allow flooding the drywell to establish an alternate shutdown cooling method. Final Conditions: The reactor is shut down, depressurized and being cooled by an alternate shutdowr. cooling method. Major Byatems: Reactor Protection Byetem, Emergency Core Cooling System, Containment and Reactor vessel Isolation control, Main Steam - Positive Leakage Control, Standby Gas Treatment, Combustible Gas Control, Reactor Plant Ventilation, Residual Heat Renoval Suppression Pool Cooling Modo, Standby Sorvice Water, Control Building Ventilation, Standby Service Water Pump House Ventilation, Auxiliary Building ventilation, Fuel Building Ventilation, safety-related Instrumentation, Recirculation Pump Trip, Leak Detection System, Neutron Monitoring System, Rod Pattern Control System, Safety-Relief Valves (Relie f Mode) . O
.m , D. Operating Sequence Anticipated Transient Without SCRAM i *' Initial conditions: The plant is at full oower with normal plant lineup.
Sequence Initiator: The Main Turbine trips and the Control Rod Drive Hydraulic System malfunctions to prevent the control rods f rom shutting down the reactor. Note: The instrument air module is taken out of service to prevent the reactor SCRAM from loss of instrument air. Progression of Action: The crew acknowledges annunciators and attempts to verify the reactor scram. When the reactor does not scram, the crew generates additional scram signals. When the reactor still has not scrammed, the crew attempts to insert the control rods manually. The reactor.is eventially shut down by the operation of standby liquid control system. When the SCRAM signal has cleared, the scram is reset and the CRD system restored to operability. The operating crew verifies the containment and reactor vessel isolation at reactor vessel level 2 and MSIV isolation on level 1. The crew verifies the starting of the emergency diesel generators. With the decrease in reactor level the crew verifies autanatic start of the reactor core isolation cooling system and verifles the starting of high pressure core sprays, low pressure core spray, and the low pressure coolant injection systems. The Shif t Supervisor declares a site emergency and plant personnel are notified when attempts to generate additional scram signals fail to shut down n the reactor. () ' Reactor pressure is being controlled through the operation of the safety relief valves operating in the relief mode. Water level decreases to below TAT requiring RPV emergency depressurization and subsequent RPV flooding. The crew monitors drywell and containment parameters. Suppression pool cooling is placed in service to maintain containment integrity. Final Conditions: Reactor power decreasing through the source range, control rod insortion not completed, the reactor vessel is depressurized and reflooded. Major Systees: Reactor Protection System, Emergency Core Cooling System, Containment and Reactor Vessel Isolation Control, Standby Gas Treatment, Combustible Gas Control, Suppression Pool Cooling Mode, Standby Service Water, Auxiliary Building Ventilation, ruel Duilding Ventilation, Reactor Core Isolation Cooling, Standby Liquid Control, Safety-related Instrumentation, Recirculation Pump Trip, Radiation Monitoring System, Safety - Relief Valves (Relief Mode). O
E. Operating Sequence: Shutdown from Outside thd Main Control Room Initial Conditions: The reactor is at full power with normal plant lineup. Sequence Initiator: Any condition requiring evacuation of the Main Control Room. Progression of Action: The Shift Supervidor makes the decision to evacuate the control room and designates which operators are to man the remote shutdown panel. Before leaving the control room, the operators scram the reactor and manually initiate the RCIC system. At the remote shutdown panel, the operators monitor and control reactor water level, reactor pressure and reactor power while proceeding to cold shutdown. They also monitor and control suppression pool water level and temperature. Final Conditions: The reactor is depressurized, being maintained cool by the shutdown cooling mode of RNR. Major Systems: Emergency Core Cooling Systems, Residual Heat Removal - Suppression Pool Cooling, Standby Service Water, Reactor Core Isolation Cooling, Residual Heat Removal - Shutdown Cooling, Remote Shutdown System, Safety Related Instrumentation, Safety Relief Valves. 9 O
Operating segmence: Inability to Determine Water Level ft d F. Initial Conditions: IDCA has occurreds reactor has been scramned and all rods are full int water level cannot be determined. Sequence Initiator: This is a residual task. Progression of Action After evaluating plant status, the Shift Supervisor determines the need to flood the reactor vessel to attempt to restore water level instrumentation to operability. The crew depressurises the reactor using safety relief valves and commences injection into the reactor to j increase water level. The crew monitors water level increase by observing the ntsaber of SRY's open and by observing reactor pressure. The crew controls l water level increase by throttling injection. The crew increases water level until the instrument reference lege are full and temperature in their vicinity is low enough to permit reliable operation. , Final Conditions: Reactor water level indication is available; water level is being controlled within acceptable limits. Major Systems: Reactor Protection System, Emergency Core Cooling System, Containment and Reactor Vessel Isolation Control, Standby Service Water, i Reactor Core Isolation Cooling System, Standby Liquid Control, Safety-related Instrumentation, Safety Relief Valves. 4
,I E
O , a I i i l l !O
~ - - - - - - - - _ , _ . _ _ _ _ _ _ _ _ _ _ _ _
G. Operating Seqyence Alternate Coolant Injection (Containment Flooding) and Steam Cooling Initial conditions: The plant is at full power with normal plant lineup. Sequence Initiator: Malfunctions 84A, B, C, condensate pumps A, B and C trip at the same time resulting in a loss of the reactor feedwater pumps. Other malfunctions: Malf. 63 - LPCS injection valve inop; Malf. 65A and C - RHR injection valve inops Malf. 66B - RHR 'B ' pump trip s Malf. 51 - RCIC turbine trip; Malf. 26A - CRDH system flow control valve A fails to minimum; Malf. 25A and B - CRDH pump A and B trips Malf. 62A and C - RHR pumps A and C tripp Malf. 71A, B and C - normal se rvice water pumps A, B and C trips Malf. 61A - SRV cycling. I/O Overrides: I/O 1579 - SLc pump to stops I/O 1609 - SLc pump to stop; I/O 1665 - ROIC turbine exhaust to suppression pool valve cloced; I/O B21R615/B21R610 - Fuel zone reactor water level indicates water level below top of active f uel. Note: The simulator operator will control the timing of malfunction entry to ensure the rate of water level decrease is not excessive. Progression of Action: The crew acknowledges the annunciators, verifies the reactor SCRAM and attempts to restore reactor water level. HPCS initates but fails to inject due to an inoperative injection valve. LPCS and LICI A and C initiate but also fail to inject due to inoperative injection valves. RCIC initiates but the RCIC turbine trips due to high exhaust pressure. CRDH pumps A and B trip. The crew succeeds in lining up LPCI injection but subsequent RHR pump trips prevent injection. The crew attempts to restart the condensate /feedwater system. The crew verifies automatic containment isolations. Containment flooding water is lined up for injection but fails to recover water level due to trips of the Normal Service Water pumps. When fuel zone range reactor water level instruments indicate a reactor water level below the top of the active f uel, the crew commences steam cooling of the reactor core per EOP-7. Normal Service Water pumps are restored to operability and the crew commences Emergency RPV depressurization. Containment flooding water subsequently recovers reactor water level. Final Conditions: The reactor is shut down, depressurized and isolated with containment flooding water maintaining reactor water level. Major Systems: Reactor Protection System, Emergency Core Cooling Systems, Containment and Reactor Vessel Isolation Control, Reactor Plant Ventilation, Residual Heat Removal Suppression Pool Cooling Mode, Standby Service Water, Auxiliary Building Ventilation, Fuel Duilding Ventilation, Reactor Core Isolation Cooling, Residual Heat Removal Shutdown Cooling Mode, Standby Liquid Control, Safety-related Instrumentation, Reactor Protection Trip, Leak Detection System, Neutron Monitoring System, Radiation Monitoring System, Safety - Relief Valves (Relief Mode). O
E. Operating Sequences Stuck Open Relief Valve Initial Conditions: The plant is at full power with normal plant lineup. (] V Sequence Initiator: Simulator malfunction 61A, stuck open relief valve used to cycle the SRV. Other malfunctions: Malf. 152 - suppression pool temperature annunciators: Malf. 145A and B - ItiCU pump A and B trip; Malf. 116A and B - stator water cooling pump trip. Progression of Actice: The crew acknowledges annunciators and monitors plant operating parameters. The crew determines which SRV is open and succeed in closing it before it has been open for two minutes. The crew places the suppression pool cooling mode of RHR into service. The SRV periodically cycles open and closed dumping heat to the suppression pool. Concurrently, Reactor Water Cleanup System pumps A and B and Stator Water Cooling pumps trip diverting operator attention from the cycling SRV. An I & C technician monitoring suppression pool temperature reports suppression pool temperature increasing, ultimately to above the heat capacity temperature limit. The crew SCRAM's the reactor and commences emergency RPV depressurization and subsequent water level recovery. End scenario. Final Conditions: The reactor has been scrammed and depressurized. Water level is being recovered. Itajor Systems: Reactor Protection System, Emergency Core Cooling Systems, Containment and Reactor Vessel Isolation Control, Standby Gas Treatment, Reactor Plant Ventilation, Residual Heat Removal Suppression Pool Cooling Mode, Standby Service Water, Auxiliary Building Ventilation, Fuel Building ventilation, Reactor Core Isolation Cooling, Safety-related Instrumentation, Leak Detection System, Neutron Monitoring System, Radiation Monitoring System, O Safety - Relief Valves (Relief Mode). i e I e O _ _ _ . _ _ _ , . _ . - . , , _ _ _ . . , , _ _ _ , , -,,m,, ,.-,.m,..c- ,,,,- _,-.,,._.y.,_ , - - _ _ - ,_ .---_,,y-___ -_- -
I. Operating Sequence: Radioactivity Release O Initial conditions: The plant is at full power with normal plant lineup. Sequence Initiator: A fuel element failure occurs and the offgas system fails to isolate. Following the reactor SCRAM, MSIV's leak. NOTE: Simulator operator will control timing and severity of malfunctions to direct progression of action. Progression of Action: The crew acknowledges annunciators and diagnoses the problem. Tney notice the offgas system has failed to isolate as required and determine that radioactivity has been released to atmosphere. Operators recognize the need for, and manually initiate a reactor SCRAM and containment isolation. The crew acknowledges annunciators and verifies the reactor scram and containment isolations. Leaking MSIV's result in offsite doses requiring emergency RPV depressurization. The crew recover and maintain reactor vessel water level per EOP-1 and initiate the MSIV Leakage Control System to control radioactive releases. Final Conditions: Reactor shutdown and depressurized; shutdown cooling in operation. Level is being maintained. Major Systems: Reactor Protection System, Emergency Core Cooling Systems, Containment and Reactor Vessel Isolation Control, Main Steam - Positive Leakage Control, Standby Liquid Control, Safety Related Instrumentation, Reactor Protection System, Leak Detection System, Neutron Monitoring System, Radiation lionitoring System, Penetration Valve Leakage Control System. O
l I l J. Operating P : Secondary Containment haperature Abnormal
' Initial conditions: The plant is at full power with normal plant lineup.
Sequence Initiator Secondary Containment Tuperature High Annunciator Progression of Action: The crew acknowledges the annunciator (s) and evaluates secondary containment temperatures and radiation levels. The crew operates available area coolers. They also operate secondary contairunent MVAC or the Standby Gas Treatment System (if needed and available) to control secondary containment atmosphere. Temperatures continue to increase causing the crew to isolate certain systems discharging to the secondary containment. After detemining that a primary system is discharging to the secondary contairunent, the crew scrans the reactor. Temperature ultimately increases to a level requiring the crew to emergency depressurize the reactor. Final Conditions: Reactor is depressurised; area coolers are slowly reducing secondary containment temperatures. i Major Systems: Containment and Reactor Vessel leolation Control, Standby Gas Treatment, Reactor Plant Ventillation, Auxiliary Building Ventillation, Fuel Building Ventillation, Safety Related Instrumentation, Leak Detection System,
! Radiation Monitoring System, Safety Relief Valves.
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A. Operating Sequence: Secondary Containment Radiation Abnormal O Initial Condations: The plant is at full power with normal plant lineup. Sequence Initiator: Secondary Containment Radiation High Annunciator. Progression of Action: The crew acknowledges the annunciator (s) and evaluates secondary containment radiation levels. When radiation levels exceed 5 mr/hr, they isolate secondary containment HVAC and initiate Standby Gas Treatment System. Radiation levels continue to increase causing the crew to isolate certain systems discharging to the secondary containment. After determining that a primary system is discharging into the secondary containment, the crew scrams the reactor. Radiation levels ultimately reach levels requiring the crew to emergency depressurize the reactor. Final Conditions: Reactor is depressurized; Secondary Containment radiation level high. Major Systems: Containment and Reactor Vessel 1 solation Control, Standby Gas Treatment, Reactor Plant Ventillation, Auxiliary Building Ventil]ation, Fuel Building Ventillation. Safety Related Instrumentation, Leak Detection SysteA Radiation Monitoring System, Safety Relief Valves. O O
L. Operating Segesnoe Secondary Containment Water Level Abnormal l'\ (/ Initial M itions: The plant is at full power with normal plant lineup. Sequence Initiator Secondary Containment Water Level High Annunciator Progression of Actions The crew acknowledges the annunciator (s) and evaluates secondary containment water levels and radiation levels. The crew operates secondary containment HVAC or the Standby Gas Treatment System (if needed and available) to control secondary containment atmosphere. The crew operates available sump pumps to control water levels. Water levels continue to increase, causing the crew to isolate certain systems discharging to secondary containment. Af ter determining that a primary system is discharging to secondary containment, the crew scrams the reactor. Water level ultimately increases to a level requiring the crew to emergency depressurize the reactor. Final Conditions: Reactor depressurizeds sump pumps decreasing secondary containment water level. Major Systems: Containment and Reactor Vessel Isolation Control, Standby Gas Treatment, Reactor Plant Ventilation, Auxiliary Building Ventilation, Fuel Building Ventilation, Safety Related Instrumentation, Leak Detection System, Radiation Monitoring System, Safety Relief Valves. O j 4 O
n M. Operating Sequence Core Cooling Without Level Restoration Initial Conditions: Reactor has been scrammed; water level cannot be - maintained above the top of the active fuels reactor pressure is low and decreasing. Sequence Initiator: This is a residual task. Progression of Action: The operator evaluates plant status and determines that ECCS, RCIC, CRDS and condensate /feedwater systems are not supplying adequate water inventory to prevent uncovering the reactor core. The operator starts the pumps in alternate injection subsystems which are lined up for injection. When water level decreases to the top of the active fuel, the operator opens all ADS valves. The operator terminates injection to the reactor from sources external to the primary containment when injecting core spray systems have suction from the suppression pool. . Final Conditions: Core spray systems are injecting with suction from the suppression pool. Injection sources external to the primary containment are isolated. Water level is below the top of the active fuel. Major Systents: Peactor Protection System, Emergency Core Cooling Systems, Standby Service Water, Reactor Core Isolation Cooling, Safety Related Instrumentation, Safety Relief Valves. O l
- E. Operating Segosace: ATWS Residuals (5)
Residual 1 p)
'% Initial Conditions: ATWS has occurred; Standby IJquid Control System is in operation Progression of Action: Twenty minutes after SLC initiation, the crew is successful in their attempts to insert control rods. After verifying all control rods are full in, the crew terminates boron injection, Final conditions: Reactor is shutdown; boron injection terminated.
Major Systems: Standby Liquid Control, Neutron Monitoring System Residual 2 Initial conditions: ATWS has occurred: reactor operator has taken the Mode switch to shutdowns the main turbine generator is still on-lines MSIV's are open. Progression of Action: After evaluating plant status, the operator initiates a recirculation flow runback to preclude a turbine trip. The operator determines reactor power to be above 5% and trips the recirculation pumps. The operator attempts to insert control rods and concurrently monitors suppression pool temperature to determine whether SLC injection is required. Final Conditions: The operator is attempting to insert control rods and evaluating the need for SLC. Major Systems: Safety-related Instrumentation Residual 3 Initial Conditions: ATWS has occurred; all attempts to generate scram signals have failed: SLC has been initiateds main condenser is still available. Progression of Action: Af ter evaluating plant status, the crew attempts to determine whether there has been any fuel failure or a steamline break. The crew determines there has not been either and opens MSIV's to reestablish the main condenser as a heat sink. Final Conditions: MSIV's open, SLC injecting. Major Dystems: Standby Liquid Control, Saf ety-related Instrumentation, Radiation Monitoring System O v 1 _______j
Residual 4 Initial Conditions: ATWS has occured all attempts to insert scram signal or drive control rods have been unsuccessful; reactor power is above 5%; all ECCS systems operating and ADS timer running; SLC has failed to inject. Progress of Action: Af ter evaluating plant status, the operator prevents the automatic initiation of ADS. The shift supervisor recognizes the need to injoct boron by alternate means and notifies auxiliary operator to inject boron by means of HPCS, CRD, RCIC or con?.ensate/feedwater systems Final Conditions: Automatic ADS is being inhibited. Reactor not shutdown; Auxiliary operators attempting to inject boron by alternate means. Major Systems: Emergency Core Cooling Systems, Reactor Core Isolation Cooling System, Safety-related Instrumentation. Residuol 5 Initial Conditions: ATWS has occurred: SLC is operating; water level cannot be determined; power level instrumentation is available. Progression of Action: After evaluating plant status, the crew attempts to ensure at least partial core coverage by controlling injection into the reactor to maintain power above 84 but as low as practicable. The <rew continues this technique until water level instrumentation is available. Final Conditions: Water level instrumentation is available. Power is decreasing due to SLC injection. Major Systems: Emergency Core Cooling systems, Reactor Core Isolation Cooling System, Standby Liquid Control, Safety-related Instrumentation. i e
O. Operating Segsence Primary Containmer.t Temperature and Pressure Abnormal (V Initial conditions: The plant is at full power with plant lineup normal except the hydrogen mixing valves are open although the position indication lights show them to be closed. segsence Initiator: Small steam leak in the drywell develops in a weld on a safety relief valve joint to the main steamline (Malfunction 97). Other malfunctions: Malf.' 58Q - SRV failure to open (all valves): Malf. 98 - Main stesmline rupture. I/O Overrides: Hydrogen mixing valves (8) open. Note: The simulator operator will vary the magnitude of the steam leak to control the rate of change of drywell and containment parameters. Progression of Action: The crew acknowledges annunciators and attempts to
- identify the location and severity of the leak. The crew notes that primary containment temperature, pressure and radiation are increasing and attempt to identify and isolate the leakage path between the drywell and containment.
Operators recognize the need for, and manually initiate a SCRAM. The crew acknowledges annunciators and verifies the reactor SCRAM. With reactor vessel
- water level being maintained by the feedwater system, the suppression pool cooling mode of RHR is lined up and drywell and containment coolers are placed into service. The reactor vessel is being cooled down and depressurized by manually operating the safety relief valves.
Unable to isolate the steam leak into the drywell, drywell temperature c () increases to a level requiring emergency RPV depressurization. The crew manually initates the Automatic Depressurization System, however all ADG - valves fail to open. All attempts by the operators to open SRV's are unsuccessful. The crew attempts to relieve reactor pressure by using the 4 steam condensing mode of RHR. During the attempt to reduce pressure, a main steamline ruptures, increasing l drywell and containment pressures to levels requiring reactor vessel flooding. The crew commences reactor vessel flooding using available I systems. End scenario. l } Final Conditions: Reactor shut down and flooded. Drywell and containment l pressure slowly decreasing. j Major systems: Reactor Protection System, Emergency Core Cooling Systems, - Containment and Reactor Vessel Isolation Control, Main Steam - Positive } Leakage Control, Standby ' Gas Treatment, Combustible Gas Control, Reactor Plant Ventilation, Residual Heat Removal Suppression Pool Cooling Mode, Standby l Service Water, Auxiliary Building Ventilation, ruel Building Ventilation, Reactor Core Isolation Cooling, Residual Heat Removal Shutdown Cooling Mode, I Remote Shutdown System, Safety-related Instrumentation, I.- ivs 7.vieetion-trtg7 Leak Detection System, Neutron Monitoring System, Radiation Monitoring I System, Rod Pattern Control pystem, Safety - Relief Valves (Relief Mode). i lO I
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P. Operating Sequence: Fuel Pool Cooling and Cleanup Initial Conditions: LOCA has occurred and recovery is in progress. Sequence Initiator: Fuel Pool Temperature High Annunciator Progression of Action: After successfully recovering water level following a LOCA, the crew is monitoring the general state of the plant when a fuel pool high temperature alarn is received. The crew evaluates the FPCC System and observes that following the LOCA load shedding and sequencing, the FPCC System has failed to restart. They attempt to restart the system. They also verify closure of FkCC containment isolatien valves. kinal Conditions: FPCC System is operating and all FPCC containment isolation valves are verified closed. Major Systems: Fuel Pool Cooling and Cleanup System, Containment and Reactor Vessel Isolation Control, Standby Service Water. O I i l l O
APPENDIX G QA PR171BCT PIOCEDURES O l l lO l f I i 1
O f3 General Physics Corporation f3 6# Quality Assurance Manual Applicability D# Project: River Bend Detailed Co7 trol Room Design Contract No. Gsu-250 Review Client: Gulf states utilities company Quality Assurance Manual Section: appuc. die. Appuc.di .. Appincabw
- 1. Organization O O
- 2. Quality Assurance Program [ O O
- 3. Design Control O O I
- 4. Procurement Document Control O O [F
- 5. Instructions, Procedures, & Drawings O O
- 6. Document Control [ O O
- 7. Control of Purchased Material, Equipment,
& Services O O F
- 8. Identification & Con .rol of Materials, Parts & Components O O Y
- 9. Control of Special Processes O O W
- 10. Inspection O O G7
- 11. Test Control O O M
- 12. Control of Measuring & Test Equipment V O O
- 13. Handling, Storage, & Shipping O O &
- 14. Inspection, Test, & Operating Status O O #
- 15. Nonconforming Materials, Parts, or Camponents V O O
- 16. Corrective Action [V O O
- 17. Quality Assurance Records 7 O O
- 18. Audits V O O Applicable, in accordance with 10CFR50, Appendix B
** Applicable, limited to specific project requirements Prepared by: &M Proli e t hia ish e t
- b. bYV Date: 8M[
Review by Chief Quality Engineer (Check appropriate block (s)): I Concur with indicated applicability , O Additional requirements are indicated / O Recommendations are attached chief Qu'afat E ng snce r 2-/4F# Detr Fmal Approva3. US, fwsk c , ,, , ,, ,,n ,,,,,,,, z,,14-g, E4 O
('N, V s3 General Physics Corporation s2 Project Quality Plan O# Sheet l_ of _.l_. Project: River Bend Deta}tled Control Room Design Contract No.: GSU-250 Review Client: Gulf States Utilities Company Applicable gppg ;,,g, Project Task Description Section, Procedure (s) QA Manual
- 1. Review Program Plan I, II None
- 2. Control Photographs None PP-GSU-250-1
- 3. Owner Approval of QA Program Manual I, II, V, XII, XVII, XVIII
- 4. Survey PP-GSU-250-1 PP-GSU-250 .
1
- 5. Inventory PP-GSU-250-1
- 6. Operating Experience Review
- 7. Review Generic Events
- 8. Develop System Functions / Task Analysis
- 9. Verification / Validation " "
- 10. 90% HEDs Assessed
/'] 11. Draft Summary Report V 12. Maintenance Procedure / Criteria "
- 13. HED Assessment Completed
- 14. HED Corrections Identified
- 15. Implementation Schedule Completed
- 16. Summary Report Completed
- 17. Documentation of Control Room / Simulator Differences QA Manual Exceptions r
Prepared by: N Woject Manager Date: F Approved by: Date: 2-/ M [
'[ Quef Quality Engineer i
l A k i
LIST OF EFFECTIVE PAGES Project Documents / Records Control Page Number Revision Page Number Revision 1 0 2 0 3 0 4 0 5 0 O e i
RECORD OF REVISIONS O e-)*o ta dc*> Revision Pages Number Description of Change (s) Dak Affected O i O u
l l l Copy No. GULF STATES UTILITIES COMPANY RIVER BEND STATION DETAILED CONTROL ROOM DESIGN REVIEW QUALITY ASSURANCE PROJECT PROCEDURES O Project GSU-250 Contract 84 5N-72860 1 Prepared by General Physics Corporation Columbia, Maryland G
l Copy ?!o, C.'.]S ' GENERAL PHYSICS CORPORATION HUMAN FACTORS ENGINEERING DEPARTMENT Project Procedure PP-GSU-250-1, Revision 0 January 1984 Project Documents / Records Control O RECORD OF APPROVAL
$ 05 Approved by: Project Director Date
-~I 1 Approved by: Division Direcd Date a
e Approved and t Authorized for Chief Quality Engineer Date L'ae by: I l
! l D -
5 , l
PP-GSU-250-1 Revision 0 PROJECT DOCIMENTS/RECOBDS CONTROL 1.0 PURPOSE The purpose of this Project Procedure (PP) is to establish measures to control project documents and records. 2.0 SCOPE This PP applies to project documents and records which are developed as contract items, which provide information for use by the project staff, or which furnish documentary evidence of project activities. 3.0 TYPES OF DOCIMENTS The following types of documents and records shall be controlled in accordance with this PP. 3.1 Technical documents supplied by Gulf States Utilities (GSU) for use by the project. 3.2 Technical documents prepared by the project for delivery to GSU, whicti include the following: 3.2.1 Detailed Control Room Design Review (DCRDR) Program Plan 3.2.2 Monthly letter reports 3.2.3 Control Room Survey Checklists 3.2.4 Task Analysis Worksheets 3.2.5 DCRDR Final Report 3.3 Documents and records for the control of project activities (project procedures) . 3.4 Project correspondence used to transmit information between member s of the project staff ard/or GSU. This includes the following types of documentation. 3.4.1 Internal project correspondence at General Physics Corporation headquarters in Columbia, Maryland, and General Physics Corporation offices in St. Francisville, Lou isiana. 3.4.2 External project correspondence transmitted or received. 3.4.3 Project contact reports. 3.4.4 Project progress reports. 1
I
! PP-GSU-250-1 Revision 0 ,~
4.0 RESPONSIBILITIES The Project Manager, has the overall responsibility for the management of Project Documents / Records Control and for authorizing access to project files. The project document coordinator will be responsible for implementation of this PP. Project Document / Records will be maintained at General Physics Corporation headquarters in Columbia, Maryland. All documents / records should be routed to the Columbia office for this purpose. 5.0 PROCEDURE 5.1 Filing System A filing system shall be established for the retention of the types of documents described in Section 3.0 of this PP. Two types of filing systems, central and remote, shall be maintained as follows. 5.1.1 Central Project File A central project file, located in the Human Factors Engineering Department, General Physics Corporation headquarters, shall be established for the filing of documents supplied by the client, technical documents prepared for the client, ard project correspondence. 3 A file index shall be developed concurrently with the development and expansion of the project file. The file index shall be retained in the project file, and shall be revised periodically to include additional file categories as they are added. All documents and records in the central file shall be uniquely numbered ard logged-in accocding to the procedures described in Sections 5.2, 5.3, and 5.4 of this PP. Sign-out cards shall be used for accountability whenever an item is removed from the central project file. Access to the central project file be limited to those persons as authorized by the project manager. 5.1.2 Remote Project Files l A t'e mote project file shall be established at any location outside of the General Physics Corporation headquarters, as approved by the Project Manager, where project task work is performed by assigned project personnel. The remote project file shall be used for filing only those documents received from or transmitted to the Project O Manager, such as project correspondence, contact reports, 2 l
- _ , . _ . ~ . . _ . - - - . _ , ~ _ _ _ - _ - _ - . . , _ . . _ . _ _ _ _ _ , - _ _ , _ . .
PP-GSU-250-1 Revision 0 project drawings, technical information and technical specifications. 5.2 Technical Documents Supplied by GSU The types of documents described in Section 3.1 of this PP will serve as the primary technical refererces for the project, and shall be received and controlled by the Human Factors Engineering Department as described below. 5.2.1 Receipt and Log-in of Documents All documents shall be marked with the date received, labelled with a unique rumber of the form CSU-250-9ii, and listed on the Project Document Receipt / Distribution Log (Figure 1). 5.2.2 Verification of Document Revision All attachments to transmittals shall be examined to verify that their identification and revision conform to the listing on the transmittal. 5.2.3 Distribution of Documents Following receipt ard logging-in actions, the Project Manager or designee shall review all documents received prior to distribution ard/or filing. When any of the documents are distributed, the person to whom distributed ard the date shall be listed in the Distribution column in line with the Document Identification. This includes assigning the document to a remote file. Either the original or a copy of all technical documents received will typically be provided to GP St. Francisville office. 5.2.4 Filing of Documents Those documents which are not distributed shall be filed in the central project file. Documents which have been distributed to project personnel at remte locations shall be filed in the applicable remte project file in accordance with paragraph 5.2.1 above. i l l 9 l 3
PP-GSU-250-1 Revision 0, r j 5.2.5 Document Recall and Reissue i Document recall / reissue actions shall also be recorded on the Document / Receipt / Distribution Log form (Figure 1) . 5.3 Technical Documents Prepared for Delivery to GBU The types of documentation described in Section 3.2 of this PP represent the product of the project to be delivered to the , client, and shall be controlled by the Human Factors Engineering I Department as described below. 5.3.1 Approval and Transmittal ? Documents which have been approved for submittal to GSU as 3 described in the applicable Project Procedure, shall be forwarded with a transmittal letter, which lists the I document identification and revision information, and is signed by the Project Manager or his designee. t 5.3.2 Log-In and Filing Each transmittal Jetter shall be identified with a unique
! project outgoing correspondence number obtained from the department outgoing correspondence log. Each letter shall be entered in the Project Outgoing Correspondence Log j (Figure 2), along with the addressee, the originator, the i subject and the date. One copy of each transmittal letter shall be filed in the central project file (Outgoing l Cor respo ndence) .
5.4 Project Correspondence The types of documentation described in Section 3.4 of this PP are used to transmit information between members of the project staff and/or GSU, and are controlled by the Department as described below, i 5.4.1 Internal Project Correspondence Any member of the Project Staff may document project information informally by generating a memorandum. Each i memorandum shall be ider.Lified with a unique number obtained from the Human Factc.rs Engineering Department Memorandum Log and entered in the Project Internal l Correspondence Log (Figure 3) . One copy of each meno , shall be filed in the central project file (Internal l Correspondence) . The Project Manager shall be included on the distribution for all internal correspondence. i lO 4 i i
- . . . - ., ,___ym _ _ - _ _ _ _ . . _ . _ _ . _ _ _. . _ . , _ _ _ _ , . . . _--.__y ,___,.-m,_-._,,__-__r _.,-_,__,,m_.,-.,..,.m_____.
PP-GSU-250-1 Revision 0 5.4.2 Outgoing Correspondence Project outgoing letters shall be identified with a unique identification number of the form described in paragraph 5.3.2 and entered in the Outgoing Correspondence Log (Figure 2), along with the addressee, the originator , the subject and the date. One copy of each letter shall be filed in the central project file (Outgoing Correspo ndence) . 5.4.3 Incoming Correspondence Project incoming correspondence (other than technical documents supplied by the NRC which are covered in Section 6.2) shall be identified with a unique identification number of the form IN-GSU-250-fil and entered in the Ircoming Correspondence Log (Figure 4) . Following receipt and logging-in actions, the Project Manager or his designee shall review the document prior to distribution and/or filing. Distribution actions shall be recorded on the Incoming Correspondence Log (Figure 4) . Items of correspondence which are not distributed shall be filed in the central project file (Incoming Correspondence) . 5.4.4 Contact Reports The significant results of meetings and telephone contacts shall be documented by General Physics Corporation Contact Report forms (Figure 5) . Each contact number shall be identified with a unique number of the form CR-GSU-250-if f and entered in the Internal Correspondence Log (Figure
- 3) . One copy of each contet' report shall be filed in the central project file (Contact Reports) . The Project Manager shall be included on the distribution for all conte t reports.
5.4.5 Progress Reports ( Project Progress Reports shall be prepared monthly and I submitted to GSU by a cover letter in accordance with the procedure of paragraph 5.4.2. A copy of this submittal shall be filed in the central project file (Progress Reports). 6.0 REFERDICES
- 1. Appendix B to 10CFR50
- 2. General Physics Corporation Quality Assurance Manual, Section 6.
- 3. PP-GSU-250-2 " Control of Measuring ard Test Equipment" 5
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O GENERAL PHYSICS CORPORATION EE , (wg CONTACT REPORT 6#
,,...e, Cont.et osie r
Meeting IAcetion f ) N;ture of Contact O C.u meceived O Can u.de O weettas Participants (Name. Title, Organisation) SummasF O Commitments Fouow Up Action Copy To GP-sF.34 (2,80) l
Figure 6 O GENERAL PHYSICS CORPORATION _ D l Gf PROJECT PROGRESS REPORT bf Cbent Date Submitted , Authorization Reference (Purchase Order, Contract Letter, etc.) Report Period Protect Descnption Contract Charge Number Project Manager Contract Administrator Cognizant Client Representative Summary of Progress During Period O Reports / Correspondence issued During Per'od Meetings Attended During Perlod Actions Planned for Nest Period l I l .- Authortred/ Established (Jms* Espended During Period Ex : nded to Date I Remaining at End of Period Status Project Director Project Manager
Sched:le mnned Espenditures ----- Year Month Actual F.spenditures (~j ) Nnned Muestenes b Aehleved Planned Muestones h Slipped Muestones D Achieved Supped Muestones k Explanations E i a f^r s v/ Y"' Milestone Schedule l Menth b ! GP-SF47 (2/80) i
Copy No. O GENERAL PHYSICS CORPORATION HUMAN FACTORS ENGINEERING DEPARTfEPTT Project Procedure PP-GSU-250-2, Revision 1 January, 1984 Control of Measuring and Test Equipment Record of Approval Approved by: l' Project Directdf Date Approved by: M / 7//i/// D isigrf Director 'Dat'e by 3 h Ch'ief Quality Engineer Date l l O
LIST OF EFFECTIVE PAGES Ues Project Docuenenta/ Records Control Page Number Revision Page Number Rension 1 0 2 0 3 0 1 4 0 4 1 O i
, , . , , , , , _ . - , ,_. -__y ,-_,,,,y, _, p,,, , ,,,,
9
i l RECORD OF REVISIONS 0 Project Documents / Records Control Revision Pages Number Description of Change (s) Date Affected 1 Deleted Luminance Meter and Velometer from 3/6/84 4 Attachment A (not required for BWROG Checklist Survey) O 9 11
GENERAL PHYSICS CORPORATION PP-GSU-250-2 Revision 0 y _\ Control of Measuring and Test Equipment 1.0 GENERAL General Physics requires that all inspection tools, test instruments and indicating devices used in the operation, maintenance and testing of plant components, systems and material be maintained in satisfactory working condition. Therefore, adequate control of the instruments is a prerequisite for assuring their accuracy. 2.0 PURPOSE The purpose of this PP is to establish a system for maintaining and controlling measuring and test equipment used at nuclear power plant sites or related facilities. 3.0 SCOPE This PP applies to all inspection, test, and measuring equipment, and standard devices used to verify conformity with specification and drawing requirements, or those used to determine the operability and/or performance of systems or operating machinery. ,a V 4.0 RESPONSIBILITIES The Project Manager is responsible for directing activities involving the control of measuring and test equipment used for a specific project. The Chief Quality Engineer is responsible for conducting a review of measuring and test equipment control activities daring the initial QA audit. 5.0 PROCEDURE 5.1 Human Factors Engineering The Human Facters Engineering group in Columbia, Maryland is considered to be responsible for maintaining control of measuring and test equipment used for Detailed Control Room Design Reviews. A complete and accurate master list of all precision measuring devices and equipment shall be maintsined by this group. 5.2 Status of Measuring and Test Equipment All gauges, meters, and measuring and inspection tools for a specific project shall be listed on a master list, along with the applicable calibration frequency and the date of last calibration of each item. m 1
GENERAL PHYSICS CORPORATION PP-GSU-250-2 Revision 0 5.3 Storage of Measuring and Test Equipment All devices identified on the master list shall be stored, when not checked out for use, in a secure, dry area with access limited to personnel authorized by the Project mnager. 5.4 Issue of Measuring and Test Equipment Devices may be checked out by personnel authorized by the Project mnager for use on project activities. Devices which do not have calibration stickers, or whose calibration has expired, shall not be issued. A log shall be maintained which lists: (1) identification of the device issued, (2) date issued, (3) individual to Whom issued, and (4) calibration due date. 5.5 Calibration of Measuring and Test Equipment
- 1. All devices shall be calibrated in accordance with the frequency specified in the master list.
- 2. All devices shall be calibrated by the applicsble manufacturer or a certified testing laboratory to standards traceable to the National Bureau of Standards.
- 3. Calibration stickers shall be affixed to calibrated devices indicating (1) date of calibration, (2) dae date of next calibration, and (3) initials of calibration.
- 4. A certificate of calibration shall be secured for each device calibrated which identified the standard used, traceability of the standard, accuracy of the device, date of calibration, and authorized signature, prior to the issue and use of the device.
Calibration certificates and associated documentation shall be filed and maintained with die official project records.
- 5. Calibration standards used shall have an error requirement of no more than 1/4 of the tolerance of the device being calibrated, unless limited by the " state of the art."
- 6. When performing calibrations where national standards do not exist, the procedure and basis for calibration shall be defined in the calibration certificiate or associated documentation.
5.6 Recall of Measuring and Test Equipment
- 1. All devices shall be removed from service that have not been properly maintained or calibrated in accordance with applicable schedules or proc edure s .
- 2. All devices shall be removed from service that show evidence of h damage or that are suspected of being out of calibration. They shall be repaired and/or recalibrated prior to reissue for use.
2
l GENERAL PHYSICS CORPORATION PP-GSU-250-2 Revision 0 O V
- 3. All devices shall be recalled and recalibrated on or before the calibration &te date.
- 4. Recall and recalibration actions shall be documented by appropriate notations in the issue /signout log.
6.0 REFERENCES
The following references were used: 1 Appendix B to 10 CFR 50
- 2. General Physics (brporation's Quality Assurance Manual, Section 12 7.0 ATTACHMENTS A list of applicable measuring and test equipment is provided in Attachment A to this Project Procedure.
O l 1 4 I t l l O i l 3
GENERAL PHYSICS CORPORATION PP-GSU-250-2 Revision 1 Attachment A DCRDR Measuring and Test Eqaipment Calibration Equipment Frequency
- 1. Bruel & Kjaer Precision Integrating Sound Level Meter Annual (Type 2218)
- 2. Bruel & Kjaer 1/3 Octave Filter Set (Type 1616) Annual
- 3. Weston Illumination Meter (Model 615) Annual O
l 9 , 4
O RIVER BEND STATION DETAILED CONTROL ROOM DESIGN REVIEW
SUMMARY
REPORT l i VOLUME 2 HUMAN ENGINEERING DISCREPANCY RESULTS i i O l ' October,1984 I l GULF STATES UTILITIES COMPANY O
RIVER BEND STATION GULF STATES UTILITIES CGEPANY ) O 7.0 IERV7BN FIlWINGS All NBS DCER Busan Engineering Discrepancy (EED) findings are provided in this section. The RED forms provide the coglete record of findings which were ccuplied throughout the RBS DCICR project. Se HEDs are uniquely identified with a number for reference purposes; however, they are logically organized in the following hierarchial sorted neder: 1 1. Priority Ranking (from HED Assessment Phase)
- 2. BWROG Otocklist Number (Area)
.i 3. Panel / Workstation Nusber (Location) Each level of priccity HEDs (i.e., ranking I's through IV's) is separated with dividers in Sections 7.1 through 7.4 of this volume. A locator / cross-reference index is also provided to help locate specific REDS by the BWROG checklist area. ! Several HEDs have "SPD8" listed for the panel / workstation nusber. H is means ' ' tat the discrepancy came from Reference K, SPDS Accident Monitcring Instrumentation Identification Study. Open IDEDs, that were not given a criticality rating due to their construction ' status, are presented in Section 7.5 of this volume. Se criticality ratirn of 5 is used strictly for database mensgement purposes. t l l 1 O 7-1 l
.k Page No. 1 10/30/84 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY HED CHECKLIST PANEL NUMDER IDENTIFICATION 1 837 C61-POO1 1 839 C61-POO1 1 840 C61-POO1 ' 1 842 C61-POO1 1 399 ERIS 1 196 GENERIC 1 200 GENERIC 1 381 GENERIC 1 637 LER-373-82042 1 576 LER-373-82072 h 1 778 LER-387-82070 1 780 LER-387-83070 1 777 LER-416-83067 1 638 LER-416-92047 1 838 LOCAL VLV 1 847 P601 1 310 P601-17B ' ~ 1 565 P680 1 194 P6BO-01,P6BO-02,P680-03,P680-04,P68 O-06,P680-05,P680-07,P680-08,P680-0 9 1 833 PDOB 1 197 P870-54,P870-55,P870-56,P877-31,P87 l 7-32 1 198 P870-54,P870-55,P870-56,P877-31,P87 7-32
Page No. 2 10/30/84 HED INDEX (VOLUME 2 -
SUMMARY
REPORT)
."q_/
('~) PRIORITY HED CHECKLIST PANEL NUMBER IDENTIFICATION 4
-------- ------ -- -- ==
, 1 193 P870-56,P870-55,P877-31,P877-32,P60 1-16,P601-21,P601-20,P601-17,P601-1 8,P601-19,P601-22 1 307 P877 1 775 SPDS 1 776 SPDS 1 5 A2.1 C61-POO1 1 316 A2.10 P863-76 1 6 A2.2 C61-POO1 1 7 A2.3 C61-POO1
+
1 8 A2.7 C61-POO1 1 466 A2.7 P680-1 4 1 25 A3.1 1RSS-PNL102 1 26 A3.1 1RSS-PNL102 1 77 A3.1 P863-71,P863-72,P863-73,P680-2,P680
-3 1 1 368 A3.2 P680-2,P680-3 1 417 A3.2 P600-4,P680-5,P680-6 1 10 A4.1 GENERIC )
1 421 A4.2 P680-4,P680-5,P680-6 4 1 830 A5 P680 I 1 804 A5 P863 l 1 283 A5.1 P601-19 1 747 AS.1 P680-7D 1 510 A5.1 P680-8B&C,P680-9 I
Page No. 3 10/30/84 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY I HED CHECKLIST PANEL NUMBER IDENTIFICATION 1 225 A5.1 P808-81B 1 236 A5.1 P808-83B,P808-84B 1 80 AS.1 P863-71 l 1 269 A5.1 P870-55C,P870-56C 1 29 A5.10 1RSS-PNL102 1 284 A5.10 P601-19 1 427 A5.10 P680-4 1 116 AS.10 P863-75C,P863-74B 1 274 A3.10 P870-55 1 428 A5.11 P680-4,P680-5,P680-6 1 422 A5.2 GENERIC i 1 O A5.2 P863-71,P863-72,P863-73 1 298 AS.3 P877-32,P601-16 1 13 A3.5 C61-POO1 1 322 A5.5 P863-76 1 812 B1 P601 ' 1 820 B1 P601 1 234 Bl.1 P808-838,P808-849 l 1 235 B1.1 P808-83B,P808-84B 1 23 Bl.3 GENERIC 1 795 E2 P863 1 30 B2.1 GENERIC 1 230 B2.11 P808-83,P808-84 0. 4
d Page No. 4 10/30/84 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) ja PRIORITY HED CHECKLIST PANEL NUMBER IDENTIFICATION 1 432 B2.17 GENERIC 1 16 B2.2 C61-POO1 1 479 B2.3 P680-1
; 1 431 D2.3 P680-4,P680-5,P680-6 1 215 B2.3 P808-87B 1 91 D2.3 P863-73D 1 245 B2.3 P870-51 1 300 D2.3 P877-31,P877-32 1 32 B4.7 GENERIC 1 285 B4.7 P601-18,P601-19,P601-22 1 133 D4.7 P628,P631 L-1 437 B5.1 P680-4,P680-5,P680-6 1 783 DS.1 P680-4B 1 231 B5.1 P808-83,P808-84 1 301 DS.1 P877-31,P877-32 1 22 B5.10 GENERIC 1 287 D6.1 P601-19 1 97 D7.5 P863-71,P863-72,P863-73 1 452 C6.3 GENERIC 1 291 C8.2 GENERIC 1 802 E GENERIC 1 355 E4.13 GENERIC 1 307 E4.17 GENERIC I
1 l
Page No. 5 10/30/04 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY HED CHECKLIST PANEL NUMUER IDENTIFICATION 1 359 E4.19 GENERIC 1 353 E4.0 GENERIC 1 360 E5.1 GENERIC 1 361 E5.3 GENERIC 1 362 E6.1 GENERIC 1 363 E6.3 GENERIC 1 540 SA1.3 P680-01, P6CO-02, P680--03 1 490 SA3 P600-01C 1 454 CA3 P680-06C 410 SA3 P680-2,P6DO-3 lh 1 1 541 LBl.1 P600-OD,P680-07,P680-10 1 412 GU1.1 P680-1,P680-2,P680-3,P690-4,P680-5, P6CO-6 1 292 GBl.3 P601-18,P601-19,P601-22 1 503 LDI.4 P6GO-1 1 457 5D1.4 P680-4,P680-5,P680-6 ( 1 504 S D'z . 1 P680-1 1 545 SPDS SPDS 1 546 SPDS SPDS 1 547 SPD3 SPDS 1 551 SPDL SF DS 1 554 SPDS SPDS 1 55b GPDU bi'D5 1 560 SPDS SPDS
Page No. 6 10/30/84 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) (_) PRIORITY HED CHECKLIST PANEL NUNDCR IDENTIFICATION 2 195 DESK 2 836 P601 2 309 P601-20D 2 564 P680-2 2 82 5.6 GENERIC 2 818 A P601 2 238 A1.1 P808-81B,P808-83B,P808-84D 2 237 A1.1 P808-83,P808-84 2 296 A1.1 P877-31,P877-32 9 2 311 A1.3 P863-76C 2 76 A2.10 P863-71,P863-72,P863-73 (~}
\_/
2 113 A2.10 P863-74C, ,P863-75C 2 128 A2.2 GENERIC 2 239 A2.2 P870-51C,P870-52C 2 265 A2.2 P870-55,P870-56 2 72 A2.3 P863-71C,72C,73C 2 109 A2.3 P863-74C, P863-75C 2 110 A2.4 P863-74C,P863-75C 2 203 A2.6 P808-87B 2 313 A2.6 P863-76C 2 129 A2.7 P628,P631 2 73 A2.7 P863-71,P863-72,P863-73 2 111 A2.7 P863-74C, P863-75C O L)
Page No. 7 10/30/U4 I!ED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORIIV HED CHECKLIST PANEL N JMULTe IDLNrIFICAT10N
--------- ------------~~---------------------
2 294 A2.8 P877-31,PU77-32,P601-16 2 279 A2.9 P601-19 2 74 A2.'/ P863-71,P863-72,P863-73 2 7G (2.9 P863-71,P963-72,P863-73 2 112 A2.9 FG63-74,P863-75 2 315 A2.9 P863-76 2 104 A3.1 P863-71,P863-72,P863-73 2 9 A 7. 2 1RSS-PNL101 2 221 A3.2 l'808-83C 2 114 A3.2 P863-74,P863-75 h 2 317 A!.2 P863-76 2 130 A3.3 P628,P631 2 .;u/ A J. , - P680-2,P680-3,P680-4,P680-5,P680-6, P863-74C,P863-75C 2 78 A3.3 Pb63-71,P863-72,P863-73 2 295 A3.3 P877-31,P877-32 2 27 43.4 1 RSS--PNL 102 2 224 A 3. 4 POO8-84C 2 28 A .:. 6 1RSS-PNL102 1 2 131 A3.6 P628,P631 2 260 A3.6 P870-55,P870-56 2 319 A3.7 P863-76 2 50', A4.2 GENERIC 2 11 A4.2 IRSS-PNL101
1 Page No. g i 10/30/g4 HED INDEX (VOLUME 2 -
SUMMARY
REPORI) m (' ) PRIORITY HED CHECKLIST PANEL , NUMBER IDENTIFICATION 2 297 A4.2 P601-16 2 574 A4.3 P808-85C-1 2 79 A4.3 P863-71,P863-72,P863-73 2 320 A4.3 P863-76 2 826 A5 P601-19 2 37 A5.1 1RSS-PNL102 2 160 A5.1 P622,P642,P632,P623 2 299 A5.10 P601-16 2 323 A5.10 P863-76 2 15 AS.11 C61-POO1 gg 2 227 A5.11 P808-81C V 2 86 A5.11 P863-71,P863-72,P863-73 2 270 AS.11 P870-55,PU70-56 2 665 A5.3 P680-1,P680-7C,P680-8C,P680-9C,P680
-160 2 423 A5.3 P680-4,P680-5,P680-6 2 46 A5.4 GENERIC 2 474 A5.5 P680-1 2 14 A5.7 C61-POO1 2 83 A5.7 GENERIC 2 132 A5.8 P631,P628 2 210 AS.8 P808 (PANEL GENERIC) 2 426 AS.9 P680-4,P680-5,P680-6 2 226 A5.9 P808-83B gs v)
_ . . _ . . . , _ _ _ _ _ - _ , _ . , _ _ . _ , _ _ . , . _ _ - . _ _ _ ._ ,o
Page No. " 10/30/34 FIED INDEX (VOLUME 2 -
SUMMARY
REPO!(I ) PRIORIIY lied CHECI' LIST PANEL nut 1 DER IDENIIFICATION l 2 84 Ab.9 F 863--71, P863-7 2, PD63-7 3 2 87 A7.2 P863 2 35 D1.1 1RSS-PNL102 2 228 D1.3 GENERIC 2 D27 U2 P601 i I 2 92 D2.11 F863-71B i l 2 '25 D2.11 PE63-76 l j 2 17 D2.12 C61-POO1 2 f.z0 U2.12 P863-76 l 2 18 D2.13 C61-POO1 2 1 '? D2.17 C61-POO1 2 324 D2.J P863-76 2 2r C U2. 3 PO70-54 1 2 22'7 U2.5 PGO8-818 i 2 7'/2 D3 POOD 2 /'7 3 D3 PG45 l 2 303 D3.1 P601-16 I 2 148 D3.15 GENERIC 2 145 D3.'. GENERIC 2 43S B4.2 P680-4,P680-5,P6GO-6 2 523 It4.5 PLOO-7,P680-8,P680-9 2 769 B5.1 P680-4D 2 770 05.1 P600-6D1 l
. - . . - - . - . _ _ - - - . . . . . - - , _ , . . . . . . . - - _ _ - - _ . - - - . . - - - _ - . . - - - . . - - , . .,- .-. , . ~ . _ . . . _ . , - - _ _ _ . . . - , . , - - - - _ - . - . . . - _ . . . . - - _
Page No. 10 10/30/04 HED INDEX (VOLUME 2 -GUMMARY REPORT) [h
\~J HED CHCCKLIST PANEL PRIORITY nut 1L;ER IDENTIFICATION d
2 121 D5.1 P863 2 439 B5.11 P6BO-4,P680-5,P680-6 2 206 DU.2 P601-19C 2 302 B5.2 P877-31,P877-32,P601-16 2 272 D5.3 P870-55,P870-56 2 33 B5.5 GENERIC 2 660 US.6 P601-20C,P601-17C 2 661 D5.8 P601-20C,P601-17C 2 440 D6.1 P680-4C 2 441 D7.1 P680-4,P680-5,P680-6 () 2 2 208 C1.1 59 C1.1 P601-18,P601-19,P601-22 P808-85A 2 304 C1.3 P877-31,P877-32,P601-16 2 444 C2.1 P680-4,P680-5,P680-6 2 98 C2.1 P863-72A, P863-71A i 2 328 C2.2 P863-76 2 289 C2.5 P601-19 2 329 C2.5 P863-76 2 290 C2.7 P601-19A 2 232 C2.7 P808-81A 2 305 C2.7 P877-31,P877-32,P601-16 2 282 C2.8 P601-19 2 451 CL.6 GENERIC l
Page flo. 11 10/30/04 IICD INDCX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY llED CHECI:. LIST PANEL NUMUCP IDENTIFICA~IION 2 354 E4.11 GENERIC 2 35L E4.16 GENERIC 2 J50 L4.10 GENERIC 2 3 4 2 S U.' .1 P869 2 505 UL:3 GENERIC 2 5 4 ~J GD 1.1 P680 2 548 EPDS SPDS 2 549 SPDS SPDS 2 550 LPDC SI'DS 2 552 SF D3 SPDS 2 bb? SPDL SPDS 2 557 SPDJ SPDS 2 LLD bi 'L)S SPDS 3 841 C61-POO1 3 044 DRMS 3 57L LER-373-83098 3 779 LER-387-83022 3 843 P680 3 569 P600-4 3 571 P600-5A i 3 570 P68O-6 1 3 572 P680-6C 3 L 7 Z. P600-6C
l Page No. 12 10/30/84 HED 1NDEX (VOLUME 2 -
SUMMARY
REPOf ft ) d PRIORITY HED CHECKLIST PANEL NUMDER IDENTIFICATION 3 70 P808-858 3 333 P863-76 3 819 A GENERIC 3 823 A GENERIC 3 366 A1.1 P680-2,P860-3 3 808 A2 P845 3 800 A2 P863 3 800 A2 P870 3 382 42.1 P600-2 3 606 A2.10 P870-56C,P870-55C N 3 200 A2.11 P800-86,P808-87,P808-88 t k'~_) 3 700 A2.11 P863-74,PB63-75C i 3 629 A2.11 P870-53C,P870-54C 3 262 A2.11 P870-54C
! 3 639 A2.12 P601-18C,P601-19C,P601-22C i
; 657 A2.12 P601-20C,P601-17C 3 607 A2.12 P870-56C,P870-55C 3 415 A2.2 P680-4C 3 694 A2.2 P863-71,P863-72,P863-73C 3 135 A2.3 GENERIC 3 240 A2.3 P870-52 3 251 A2.3 P870-54C,P680-4,P680-5,P680-6 3 266 A2.3 P870-55,P870-56 1
s
. , . . . _ . _ . _ - _ , . . . , _ __ . . . - _ _ _. _ . - _ _ - . , _ _ - _ . . . _ . _ _ - _ _ . _ . . ~ - _ _ _ _ _ _ . ~ ,
Pagte tJo . 13 10/30/04 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY llED CHECKLIST PANEL NUtil:LI: IDENfIFICA1 ION I 3 601 A2.5 P600-4 C , P600-5C ,I'600-6C , P600- 10C 3 465 A2.6 P680-1 3 .'70 A2.7 l-'601 - 10, P601 - 19 I 3 204 A2.7 P808-86,P800-87,P808-80 3 2i '5 ( 2. 7 POOD-OSC [ 3 70S A2./ PO45 3 J14 A2./ PO63-76 3 64/ A2.9 P601-21C 3 605 A'.Y F '070- 56C , PO70-55C 3 267 A'.2 P870-55C 3 466 m3.3 PLOv-10 3 4l'/ 43.4 P6DO-4,P600-5,P680-6 3 B*it A4 PU70 3 133 A4.2 f 845 3 105 A4. .. P670,P672 3 161 A5.1 P623 3 4/v AS.1 P600-1 ' ^* I 751 A5.1 P600-15C 3 321 AS.1 PU63-76 3 336 AS.1 P869 3 24 ~2 A5.1 P870-52,P870-51 l 3 2 A5.1 PO70-54D i
; 50 AS.10 P800-51C
I i l I Page No. 14 10/30/U4 i llED It'DEX (VOLUME 2 -
SUMMARY
REPORT) PRIORITY HED CHECKLIST PANEL NUMDER IDLNTIFICATION 3 211 Ab.10 P808-86C,P800-07C,P808-BOC 3 244 A5.10 P870-52 3 51b AS.11 P680-7,P680-0,P680-9 3 754 AG.3 P680-15C 3 753 Ab.3 P680-DD 3 752 AL.3 P680-8C P 5 3 756 Ab.3 P680-9D 3 640 AS.5 P601-19D 3 650 AL.5 P601-21C,P601-20C,P601-17C 3 400 A5.5 P600-2 3 603 AL.5 l '600-4 C , P680-5C , P600-6C , P680-10C 3 164 65.5 PO45 3 170 A5.0 P614,P604,P600 3 162 AD.9 P622,P632,P642,P627 1 3 49 AL.9 P800-05C1 3 212 A6.6 P800-87,P000-00 1 3 376 A7.3 P6DO 3 015 D1 GENERIC 3 025 D1 P600 l 3 014 DI PO70 3 102 D1.1 P614 O 463 D1.1 P680-4 3 600 151.2 P660-2C,P600-3C 1
i Pace f lu . 15 . 10/70/U4 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) l, FRIURITY HED CllCCl. LIST FAIJEL rit nif :Ll': IDENTIFICATION
? U l ~/ Li P600 1
I 1 3 010 D2 i U /O 7 ' '/ 2 U2.I1 i'600-2 i l 2 tRO D2.11 F600-7,P600 -0,P600 '? 3 107 !C.11 PU63-73D 1 '. 163 D2.13 P6.'2 , P623 i l . 66' U2.1. F '6UU- 7C , P600-UC , P600-9C , f '6GO- 15C i 3 14!. T2.13 PU45 l ? tA 1:2.1. PO/u L4D I i I : 14 2 b .' . 2 PU45 3 1.. I?.3 F 69's 1 3 1/1 IC . *. P614 i i 1 1. ' . 1;; . I 670,I'672 l
~~
i . 76? 0 3 PLOO 15C ! 3 'M 1 I r. . ' P600- 2 t i
! /61 1. . .
- F60* r-7A
; / t,t > ly.. I'600 9b 1
1 3 /in I'i . ' P600 *?D 3 .46 I C . .~. PO70 -52b
? 1 D .' . 2 PU/v-54 l
l I
? 144 D 3.1 I'U4b l l
l 3 3 7 Lf * .1 PO6'l I l
'40 I
.10 I 'Ju/
l
Page No. 16 10/30/04 HED INDCX (VOLUME 2 -
SUMMARY
REPORT) b(3 PRIORITY HED CHECKLIST PANEL NUNDEft IDENTIFICATION 3 247 D3.10 P070-51 3 338 D3.2 P869 3 95 D3.3 Pu63-71B 3 717 D3.5 P622,P642,P632,P623 3 54 D4.1 POOO-05C1 3 63 B4.1 POOO-05C1 0 150 D4.4 GENERIC 3 745 D4.5 P614 0 55 D4.6 POOD-USC 3 010 D5 P600 3 524 D5.1 P6DO-9C 's 3 149 D5.1 PO45 3 157 Db.1 PG45 3 150 DS.1 PU45
~
662 D5.11 P601-20C,P601-17C 3 525 B5.2 P600-15C 3 255 DU.5 PO70-54 3 520 D6.1 P600-7,P600-0,P600-9 3 256 D6.1 P870-53 3 022 C GENERIC 3 020 C P601 3 021 C P600 3 375 C1.1 CENERIC s
Page No. 17 10/30/04 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORIFY HED CHECL:' LIST PANEL NUtliff: IDENTIFICATIGN 3 651 C1.1 P601-21A 3 155 C1.1 P845 g 257 C1.1 PO70-54A 3 443 C1.3 P600-4A,P690-5A,P680-6A 3 b30 C1.3 P680 -7, P600-0, P600--9 3 60 C1.3 POOU--OSC 1 3 106 C2.1 GENERIC i 3 663 C2.1 P601-20A,P601-17A 3 L52 L2.1 P601 -- 214 3 406 C2.1 P600-1
; S31 C2.1 P600--7A 3 600 C2.1 POOO-01C,POOO-03C,POOO-04C 121 C2.1 PO63-74A 3 613 C2.1 P O 70-- 56C , PO 70-55C 3 4lf/ C2. 2 P600-1A 5 273 C2.3 GENERIC 3 409 C2.5 P600-1A 3 534 C2.5 P600-7,P600-0,P600-9 3 220 C2.5 POOO-07A 3 132 C2.5 PO45 3 100 C2.S PU63-71A 3 2'/3 C2.5 PO70-55A, PO70-564 3 4'/O L2. 6 GENCRIC
Page No. 18 10/30/04 HED INDCX (VOLUME 2 -
SUMMARY
REPORT) { N PRIORITY llED CHECKLIST PANEL NUNDER IDENTIFICATION 3 653 C2.6 P601-21A 3 644 C2.7 P601-18A,P601-19A,P601-22A 3 491 C2.7 P680-1 3 536 C2.7 P680-7,P680-8,P680-9 3 221 C2.7 P808-06 3 124 C2.7 PO63-74A 3 233 C2.0 P800-01,P808-82,P808-83, 3 62 C2.9 GENERIC 3 406 C3.2 P680-2,P680-3 3 450 C5.1 P680-4,P680-5,P680-6 [s 3 249 C5.2 P870-52A j 3 66 CG.1 GENERIC 3 346 D4.1 P680 3 009 E P863 3 700 L2 P6CO 3 351 E2.0 GENERIC 3 352 E2.3 GENERIC 9 811 H1 P680, P870 3 411 GA4.1 P600-- 1 C 3 709 SB P870 : i 3 502 SD1.3 GENERIC i 3 456 SD1.3 P680-06C l 3 17Y SD1.4 P600 i (1)
Page Mc . . 19 HED INDEX (VOLUME 2 -
SUMMARY
REPORT) PRIORIrY HED CHECKLIST PANEL NUMDER IDENTIFICATION 3 100 SD2.1 P614,P604,P600 3 459 S84.1 P680-10C 3 654 SD4.2 P601-21C 3 350 SE2.1 P6DO 3 559 Sf 'DL SPDS 4 300 P680 4 340 l'600 4 347 P6GO 4 ULO f600-5,P680-6 4 4 POO8 4 834 PBOB 4 71 P300-G5C-1 4 501 P808-86,PBOO-87,P808-88C 4 G16 A P800 4 832 A P861 4 15? A1.1 P622,P642,P632,P623 4 724 A1.1 P620,P631 4 742 A1.1 P670,P672 4 506 A1.1 P680 4 134 A1.1 P845 4 703 A1.1 P863-76C 4 277 A1.3 F601-22 4 692 61.3 PO63-71,P863-72,PU63-73L l
Page No. 20 10/30/04 HED iNDEX (VULUME 2 -
SUMMARY
REPORT) O PRIORITY hED CilCCl; LIST PAtlEL NUMUER IDErlTIFICATION 4 693 A1.4 P863 4 38 A2.1 P808-85C-1 4 200 A2.10 P601-19 4 467 A2.10 P680-1 4 207 A2.10 POOO-88C, P808-86C 4 241 A2.11 P870-51 4 281 A2.12 P601-19C 4 682 A2.12 P680-4C,P680-5C,P680-6C,P680-10C 4 275 A2.12 P870-55 4 40 A2.3 P808-85C1 4 312 A2.5 P863-76 4 589 A2.6 P808-85B,P800-85C-1 4 604 A2.6 PU70-56C,P870-55C l 4 206 A2.9 P808-86,P808-87,P800-88 4 67 A7.1 P800-85C-1 4 263 A3.1 P870--53C 4 42 A3.2 P808-85C j 4 43 A3.2 P800-85C 4 242 A3.2 P870-51C 4 169 A3.4 P614,P604,P600 4 507 A3.4 P680-8B 4 44 A3.4 P808-85C 4 334 A3.4 PC69
-)
Page No. 21 10/30/04 HED INDEX (VOLUMC 2 -
SUMMARY
F(EPOfi f) Pit I OR I I '.' HED CliECULIG1 PANEL NUMBLf: IDENT If ICA T IGN 4 45 A3.4 PU/O-S4D 4 104 A3. P670,P672 4 2/o AJ./ PO70-55 4 '.37 A4.2 P600--2 4 _.7 U A4.2 P600-2,P680-3 4 20'1 A4.3 P BOG --86C , POOO -DOC 4 _'. .'. 5 A 4 . c. PU6Y 4 G5 AG.10 P8 63 -71, P O6 3-72 , P O 63 --73 4 51 AL.11 F'Ov0-C5C-1 4 100 A5.13 P670,P672 4 i Ab.; GENLRIC 4 757 AU.3 Pc280 -?D 4 L'il Ab. 2 F 'UOO - 81 C , P800--83C , PHOB- 0 4 C 4 139 AL.3 PO45 4 7 2b AL . *. F84S 4 60f1 AG.4 PU/0-56C,PO70-55C 4 SI'_. A5.5 PLBU-7,P6GO-8,P600-Y 4 61? AG.5 PO70-51D,PO70-52B 4 649 AL.6 P601-21C 4 712 AS.6 P622,P642,P632,P623 4 671 AL.6 P6DO-1C 4 607 A5.6 P600--2C , P600- 3C 4 L'/ .~. A 5 . 6 l'OOO- 01 C , POOU- 03C ,l 'UOO- 04C
~
Pago No. 22 10/30/04 IIED I NDE)' (VOLUME 2 -
SUMMARY
REPORT) PRIORITY ltED CllCCKLICT PANEL NUlil<ER 1DENIIFICATION 4 695 AS.6 P863-71,PO63-72,P863-73C 4 705 A5.6' P863-76C 4 743 AS.7 P614,P604,P600 4 577 A5.7 POOB-86,,POO8-87,P808-88C 4 731 A5.7 P869 4 40 AS.O POOO-51C 4 47 AS.O l'UOD-05C-1 4 570 AS.O POOB-06,P800-07,P800-GOC 4 726 AS.O l'045 4 620 A5.8 PO70-51C,PO70-52C 4 106 Ab.9 l'670,l'672 4 140 A3.9 PG45 4 4 AG.9 PD70-53 4 579 A6.2 GENERIC 4 375 A7.2 P600 4 210 A7.2 POOO 4 141 A7.2 PO45 4 53 A7.3 PCOO 4 CD A7.3 P063 4 791 D P600 4 790 D1 P600 4 029 Di PO63 4 101 bl.1 l'614,P604,P600 0
Fuge No. 23 iw 50/04 llED INDEX (VULUME 2 -SUMMArn' fief'Of(I) PI< I ON I T Y llED CllECKLIST PANEL NU;10EI: IDENT111 CAT 10N I 4 160 D1.1 l'642 i 4 154 D1.1 PO45 I 4 15e D1.1 l'U4L i 4 5% D1. 3 F000-01C,POOO-03,POOO-84C 4 7'/ 7 L'2 l'600 i , L 4 l'76 D2 PG70 i 4 (,4 6 L:J.10 f 600 BC i j 4 1'/3 02.12 l'614 l 4 / 1 L L:2 . 1 2 P 622 , f '6 4 2 , P63 2, l62 3 ! 4 l'10 I<2.12 P670,P672 i 4 521 l' J .12 l'600+ - 7, P600- 0, PLOO '/ ) 1 4 5'/ / DJ' .12 l'OUU - 01 C , F 000 -O!C , Pl]vu - 04 C f l 4 216 1: 12 l'Ouu-U/U,IUUD-06D i j 4 *1 ;. D2.!? T '06 ? 71D ! 4 1 l 'r 1 : .' .1.' l'U U. '/ 5 D I 4 6*1 11.'. 1 2 f>0 /o - 53D , PO70-54 D l l 4 .lL ; D2.12 1 0/0-54 4 60"1 D2.12 PU70-56D,P070-55D 4 611 l'2.12 i'U /O -5614, PU 70-5511 4 /40 11.' .1 ; P6/0,P672 4 LU2 D2.12 POOO-06, F 000-- 0 7, POUU -UU 4 '.' 1 / D 2 .1 ". POUU -06D , f'000--0 7 Li ,l'Ou0 -00Lt 4 72/ i:. 1. l'U4b l l
Page No. 24 10/30/04 UCI' It4DL X (VOLUME 2 -SUrlt1ARY RLF'UR I )
/~N< >O PRIORI ~IV ilCD CHECKLIST PANEL tlUtlDCll 1 Dtit4T I F I CAT ION 4 191 B2.17 CENERIC 4 716 D2.10 P622,P642,P632,P623 4 741 D2.10 P6/0,P672 4 590 D2.10 P908-81B 4 L10 D2.2 P6DO-7,P600-0,P680-9 4 764 I'2.3 P6GO-15C 4 7bu D2.3 P600-0D 4 765 D2.3 P600-9C 4 90 D2.3 PD60-73D 4 604 D2.4 P600- 4 D ,P600-LD ,P600-6D , P600- 10D 4 713 D2.5 P622,P642,P632,P623 ! 4 396 D2.5 P000-POOO-01C,P008-O!C,P000-04C t
4 630 D2.5 PU70-54D 4 744 D2.0 P614,P604,P600 4 714 D2.0 1 %22, F'64 2, P632, P623 l 4 6/2 D2.0 P600-1D i 4 696 D2.0 P063-71 4 621 D2.0 P070-51C,P070-52C 4 202 D2.0 l'070-04 4 794 D3 P000 l 4 174 ti!.1 f'614 I 4 71'1 U .'. 10 P622,P642,P632,P623 4 16b it3.4 l'642 U
P.ayc IJo. 25 10/ .O 'U4 FRlut(ITY llCD CliCCI LIST PANEL , NUtli Ll? IDLf411fICAIlON 4 146 D.L Pb4L 4 7 J.4 D.5 PU69 l 4 147 !<! . 6 LCNERIC l
) 4 166 B 3. 6 F622,P623,P632,P642 i
4 LU3 0 2. 7 GENCfilC 4 120 D4.5 GENERIC l 4 175 1:4.L P614 P604,F'600 l 4 ~21 L4.5 P622, F'64 2, P632, P623 l 4 341 04.L l'069 S 4 36 D4.7 PUOH -05C 1 i j 4 L. I:4.O P000 U*JC-1 i 1 //? 10.1 PLOO -4 A 1 i 4 L U/ L '.i . 1 f 't,00 -41t ' l 4 //1 LL.1 F600-GA 4 7f11 IG.1 I'tA!U - 6C 4 16/ [G.', I622,P623,P602,P642 t 4 50 L:5.6 POOU-OSC 4 674 05.; P600-1C i 4 72. I',.(' I '6 22, P64 2, P6 32, F '623 i 4 67'i 16.3 P600 1C 4 7 '. / Is . O l'U69 4 600 lib. '? P601 -21C 4 t.6 0 lib . '/ 1 %Da i 70, P600- OL ,I 600--9C , P600- 1 LC i
Page No. 26 10/30/04 HED INDEX (VOLUME 2 -Sut1 MARY REPORT) k_s) PRIORITY HED CHECKLIST PANEL Nut 1 DER 1DENTIFICATION 4 706 05.9 PO63-76C 4 105 C1.1 GENERIC
! 4 676 C1.1 P600-1A I 4 669 C1.1 P600-7A,P600-04,P600-9A,P600-15A l 4 210 C1.1 P000-06,P000-07,P000-00 4 670 C1.1 PO63-71,P063-72,P063-73C 4 127 C1.1 P063-74,P063-75 4 701 C1.1 P063-74A,PU63-75A 4 126 C1.1 PO63-75,PO63-74 4 707 C1.1 P063-76A 4 622 C1.1 P070-51A,P070-52A 4 643 C1.2 P601-10A,P601-19A,P601-22A ; 4 6/7 C1.2 P600-1A j 4 6'70 C1.2 P600-2A,P600-3A t 4 442 C1.2 P600-4A,P600-5A,P600-64 i
4 U2? C1.2 P600-7A,P600-GA,P600-9A 4 090 C1.2 P000-05C,P000-05-C-1 l 4 504 C1.2 POOO-06,POOO-07,P000-00C 1 4 /20 C1.2 PU45 I 4 700 C1.2 PU63-76C I 4 623 C1.2 PU70-514,P070-52A ) 4 403 C1.3 P600-1 i l 4 3'/6 C 1 . 3 P6UO-2A il 4, e
I I 5 Page ita. '/ J 1 t > / f o/D4 IIED INDLX (VOLut1C '2 -LUtir1ARY RLPURI) i PRIORITY llED CHECICLIST PANEL f Util:LI: I DL N I I f: 1 U A I 10N l 4 b u b L1. .'. F 'UOU - 06, F 'UOlF 0 7. f'Uou-UUL l i 4 lui C1.2 PU1G l 4 624 Lt.3 l 'U /O-- b 1 A , f 'U /O-b2 A 4 ?<n C2.1 F'U b :-- 7 b A l 4 6Jb C...I l'U70-510,PU70-520 l i 4 7 7 C .. . J (2L! ILi< I C 4 664 L '. . ~./ I'U.i l 200, f '601 - 17 A 4 5 3.' C J . .' P600 7,P689-U,P600-9 i 4 99 CL. IUL /1, PU63- 72, F 'U6'l - 71 4 6:. L 2. .' l'U/v U36 l 4 611 l..c Itt:'u LLA,f'U/O--bbA 6 leel L .' . S I 'U 6 -~ - 7 2 D i } 4 1/ c , l. . . t l '61 1, I'60 4 , f '600 l 4 15 t z . <, l'U lu i i 4 1,' / C J . l '614 . l TO4 , f '600 I i 4 4 4 ,' C .' . / I '. 0 0-- 4 , P6U O -G , P600- 6 l 4 LU6 LL.7 f'UOU--0 6 ,P OO O- 07 ,P OU U -U UC i ! 4 JG3 C2.7 f' U 7 0-'5 44, P U 70-5 2 A 4 6; L '. . I'UOU-ULL1 i 4 7.?'l C L .', 6 'tJ 4 L 4 /U2 L6.4 LLNLi<!C 4 65 C.,.4 l'110t3 -USC 4 l t . '>l D Lt.NI le l L
Page tio . 20 10 / f.e s/tt4 hcl) INDCX (VOLUME 2 -SUMrtoltY REPORI) PittuRITY llED CllCCKLIST PANEL Ifulit:LR IDEt41 IFICAT IOr4 4 70~/ D2 COMPUTER 4 343 D.'. 2 P600 4 344 D3.4 P600 4 345 D3.5 P600 4 003 C1 GErJCRIC 4 364 E7.4 gel 1ERIC 4 4 5.5 S A l . 3 GLtJCRIC 1 22.2 C63.1 POUG -06,POOO-0 7,P908-08 4 ,!60 LA4.2 l'U/U-L3U 4 '/27 5A4.3 P622,P642,P632,P623 r 4 606 bA4.3 P6DO-4C,P600-LC,P600-6C,P6DO-10C 4 602 GA4.3 PUOG-G1C,POOO-03C,POOO-84C ; L 4 7 30 Lei 4. 3 T 069 4 626 GA4.3 P0 70-51 C , PO70--52C 4 170 51tl.1 P614 , f '604 , P600 l 4 697 U111. 2 l'863-71,P063-72,PC63-73C 4 710 001.2 P863-76C i 4 739 Gl31.2 PG6? 4 / ,'i l ! ;l r.' . I l'6U(o 211,l'6flo - 313 t j 4 627 GD2.1 PU/O-50D 4 746 GD3 l'614,604,600, 4 261 004.1 PO70-54D 4 347 LD1.b f'600 0
1 O Page tJo. 29 10/"i e . tui HED It1DE X PRIORITY (VOLUME 2 -
SUMMARY
REPORT) HED CllCC) LIST FWNEL IJUtil'LR IDLNIIFICA1 ION 4 365 eel.1 GENERIC 4 U31 GF GENCHIC 4 Ob6 SI 'DG Li'DU 4 561 SPDS SPDS 4 562 LPDS GPl>U 5 199 GEtaERIC S 2 41 A1.3 1 RSL - F'NL 102 O U 100 41.4 b PO63-74C,P863-75C 21 U2. 2 5 1 RUS -l tJL 102 20 D 3.1 L 1RSS-PNL101 4U1 D 3.1 P6Co -I 5 94 13 3 . 1 PG63-71D
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RIVER BP.ND STATION GUTE SmTES ITf!LITIES COMPANY 7.1 PluDRITY I mmR O O 7-2 l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NLJCI E AR P L. A N T DATE: 07/25/84 HED NO- = G37 REVIEUER: DISHOP/HOWELL TRACr'. ING STATUS: SCHEDULE PHASE _---------_-_-__--_----..---_---______-----_-----------------------------~~----- DATA SOURCE: T AGI . AtJAL Y S I L CHED. LIST TJO. : PANEL /WOf d:.ST AT ION tJO. C61-POO1 DESCRIPTIOrl OF DICCREPATJCY: (SCEf1ARIO E/SEDUEf1CE 220) THE TASK / SUBTASK SAYS " VERIFY PUMP AMPS" HOWEVER, THERE IS tJO PUMP AMP METER Of4 C61*POO1. RECOMMENDATIONS: CHANGE F ROCEDUliE. FUMP AMPS ARE NOT REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT ELDER # ISSUE DATE / / FDDR4 ISSUE DATE / / CRITICALITY RATIf4G: 1 IMPLEMENTATION SCHEDLtLE: PRIOR TO FUEL LOAD. 9
ENGINEERING DIBCREPANCY RECORD l HUMAN BEND NUCLEAR PLANT (N_)
'i RIVER F4 EEI) PJ C3 E3 C5 CP DATE: 07/25/84 REVIEWER: BISHOP /HOWELL TRACKING STATUS: SCHEDULE PHASE
- = - -
-----==.
DATA SOURCE: TASK ANALYSIS CHECKLIST NO. PANEL / WORKSTATION NO. C61-POO1 _ _ _ - - -=------ -----
- - - - _ . =. -- - -_ __
DESCRIPTION OF DISCREPANCY: (SCENARIO E/ SEQUENCE 410) THE TASK / SUBTASK SAYS " OBSERVE RHR TEMPERATURE". HOWEVER, THERE IS NO RHR TEMPERATURE INDICATOR PROVIDED. RECOMMENDATIONS: CHANGE THE PROCEDURE AS FOLLOWS: COOLDOWN RATE SHALL BE MONITORED BY USING THE CORRELATION BETWEEN RPV PRESSURE AND TEMPERATURE. THE OPERATOR WILL MONITOR THE RPV PRESSURE IN CONJUNCTION WITH A SATURATED STEAM CURVE IN THE PROCEDURE TO LIMIT COOLDOWN RATE TO 100 DEGREES FARH./ HOUR (^T DOWN TO 212 DEGREES FARH. (,) SINCE RBS HAS BEEN ANALYZED FOR COOLDOWN RATES IN EXCESS OF 200 DEGREES FARH./ HOUR, THIS PROCEDURE PROVIDES SAFE SHUTDOWN OF THE PLANT. ACTION: APPROVED BY GSU MANAGEMENT ELDCRW ISSUE DATE / / FDDRM ISSUE DATE / /
---=
--__ _ ==------------ ____. __
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD i (a~'T l i
HUMAN ENGINEERING DISCREP(4NCY RECORD RIVER BEND NUCL EAR P L_ A N T DATE: 07/25/04 HED NO- :: 84O REVIEWER: BISHOP /HOWELL TRACKING STATUS: SCHEDULE PHASE DA1A SOURCE: TASI. ANALYSIS CHECKLIST NO.: PANEL / WORKSTATION NO. C61-POO1 ( 1.) E12-F010 DESCRIPTION OF DISCREPANCY: (SCENARIO E/ SEQUENCE 490) THE TASK / SUBTASK SAYS REQUEST AUX OPERATOR TO VERIFY OPEN E120-F010 VALVE. HOWEVER, THERE IS NO INDICATION FOR THIS VALVE ON C61*POO1 AND IT REQUIRES A DRYWELL ENTRY TO VISUALLY VERIFY VALVE POSITION. RECOMMENDATIONS: THIS VALVE WILL BE LOCl'.ED OPEN DURING MODE 1,2, AND 3. ACCESS TO THIS AREA IS ADMINISTRATIVELY CONTROLLED TO PREVENT ACCESS DURING OPERATION IN 1,2, AND 3. PROCEDURE CHALL DE CHANGED. ACTION: APPROVED BY GSU MANAGEMANT E!DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O l l l l
RECORD HUMAN ENGINEERING DISCREPANCY RIVER BEND NUCLEAR PLANT [")T
'% HED N O . :: 842 DATE: 07/25/04 REVIEWER: BISHOP /HOWELL TRACKING STATUS: SCHEDULE PHASE
- - = = ._ -__
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.* PANLL/WORKST AT IOt4 NU. C61-POO1
--- =_
i DESCRIPTION OF DISCREPANCY: (SCENARIO E/ SEQUENCE 610) THE TASK / SUBTASK SAYS MONITOR COOLDOWN RATE. HOWEVER, THERE IS NO WAY TO READ RHR TEMPS ON C61*POO1. RECOMMENDATIONS: CHANGE THE PROCEDURE AS FOLLOWS COOLDOWN RATE SHALL BE MONITORED BY USING THE CORRELATION BETWEEN RPV PRESSURE AND TEMPERATURE. THE OPERATOR WILL MONITOR THE RPV PRESSURE IN CONJUNCTION WITH A SATURATED STEAM CURVE IN THE PROCEDURE TO LIMIT COOLDOWN RATE TO 100 DEGREES FARH. f- SINCE RBS HAS DEEN ANALYZED FOR COOLDOWN RATES IN EXCESS OF 200 DEGREES 4 l j FARH./ HOUR, THIS PROCEDURE PROVIDES SAFE SHUTDOWN OF THE PLANT. ACTION: APPROVED BY GSU MANAGEMENT 4 ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- _=_ _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 1
\_/
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T DATE: 05/01/84 HED NO = 399 REVIEWER: CHASE TRACKING STATUS: SCHEDULE PHASE __-----------------_----__---_-----------_----- =_-_-----_--_---_------------- DATA SOURCE: OTHER CHECKLIST NO.: PANEL / WORKSTATION NO. ERIS
= - - --- =___---_--
DESCRIPTION OF DISCREPANCY: THE FROPOSED ERIS CONSOLE LOCATION REQUIRES CAREFUL REVIEW TO DETERMINE IF THE LOCATION IS OPTIMUM TO SUPPORT THE OPERATORS RECOMMENDATIONS: DESIGN A CONTROL ROOM FOREMAN'S DESK THAT WILL ACCOMMODATE THE TWO ERIS DISPLAYS ON EITHER END. THIS IS OPTIMUM DESIGN TO SUPPORT OPERATORS. ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR # ISSUE DATE / / FDDR# ISSUE DATE / /
=_ -_-_-_------_-___---_--____
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD
-( RIVER BEND NUCLEAR PLANT D6lE: 02/20/04 HED NO- = 194.,
4 REVIEWER: BARKS /CidASE/SHANKLE TRACKING STATUS: SCHEDULE PHASC
--------_---- =- - - = - - - - - _ _ - - - - - _-___=_ = - - - - - - _ - _ - - -
DATA SOURCE: CONTROL ROOM SURVEY - NUREG 0700 CHECKLIST NO.: 4 GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT F'ROBLEM SUD-CATEGORY: EMERGENCY LIGHTING PANEL / WORKSTATION NO. GENERIC ( 1.)
- - = _ . _ __
DESCRIPTION OF DISCREPANCY: DC BATTERY PACK EMERGENCY LIGHTING IS INADEGUATE BEING A MAX. OF 6 FOOTCANDLES AT ITS BRIGHTEST SPOT AND NEAR O FOOTCANDLES AT MANY SPOTS. 0- LIGHTING CAUSES SHADOWS AND DARK AREAS ON THE BOARD RECOMMENDATIONS: EVALUATE LIGHTING TO MEET HUMAN FACTORS MAINTENANCE PLAN STANDARDS ACTION: STONE L WEDSTER IS EVALUATING CONTROL ROOM LIGHTING AS A RESULT OF DCRDR. FINAL LIGHT READINGS WILL DE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED AND FLOORING IS INSTALLED. i E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / __--------------------- - ==- - - - _ _ _ - - - - - - . - - - - _ - - __ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD ! O l l l t l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/28/84 HED N O . :: 200 REVIEWER: BARMS/ CHASE TRACKING STATUS: SCHEDULE PHASE
------------------------------------_ =__ ---- _-------------------------------
DATA SOURCC: CONTROL ROOM SURVEY - NUREG 0700 , CHECKLIST NO.: GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PRODLEM SUB-CATEGORY: EMERGENCY LIGHTING PANEL / WORKSTATION NO. GENERIC ( 1.) l -------------------------------_------------------- . DESCRIPTION OF DISCREPANCY: THE DIESEL POWERED CONTROL ROOM LIGHTING IS NOT AUTOMATICALLY ACTUATED RECOMMENDATIONS: THE EMERGENCY LIGHTING IS AUTOMATICALLY ACTIVATED. THE POWER SOURCE IS A SAFETY-RELATED BUS, BACKED UP BY THE PRIMARY DIESEL GENERATOR (SEE FSAR SECTION 9.5.3.2) NO FURTHER ACTION REQUIRED. l l ACTION: l APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDRs ISSUE DATE / / CRITICALITY RATING: 1 . IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIBCREPANCY RECORD BEND NUCLEAR PLANT [J'a DATE: 03/22/84 RIVER FiEEI) hJ C3 . - 25 E31 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE _----- _=_. =-- ------------------- DATA SOURCE: BWR OWNERS GROUP CHECHLIST NO.: PANEL / WORKSTATION NO. GENERIC
----------= - .___==- - - - - - = - - - _ -
DESCRIPTION OF DISCREPANCY: THERE IS NO CONTAINMENT ISOLATION MIMIC SHOWING THE STATUS OF THE PENETRATIONS RECOMMENDATIONS: ADD CONTAINMENT ISOLATION STATUS DISPLAY ON SPDS ACTION: APPROVED BY GSU MANAGEMENT. O ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / _=_ - = - _-- -------- CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULC: F RIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCt_ EAR PL ANT O DATE: 04/18/84 F4EEE) b4 C3 - = d2 25 7F REVIEWER: LED / LIDDLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATIONAL EXPERIENCE REVIEW CHECKLIST NO.: FANCL/ WORKSTATION NO. LER-373-82042 DESCRIPTION OF DISCRIPANCY: LASALLE LER WHERE AN OPERATOR FAILED TO RECOGNIZE POTENTIAL DRAIN PATH IN THE LINE-UP AND THE REQUIRED VESSEL LEVEL FOR RHR S/D COOLING RECOMMENDATIONS: THIS SPECIFIC PROBLEM IS ADDRESSED IN TRAINING. THE RBS PANEL MIMIC ACCURATELY DEPICTS PROPER SYSTEM LINE-UP. ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: I IMPLEMENTATION SCHEDULE: O
ENGINEERING DIBCREPANCY RECORD HUMAN RIVER BEND NUCLEAR PLANT h$ F4 EEI) P4 C3 . = "5 7P db DATE: 07/06/84 REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
. - - =-. _----
_==_ DATA SOURCE: OPERATIONAL EXPERIENCE REVIEW CHECKLIST NO.: PANEL / WORKSTATION NO. LER-373-82072 DESCRIPTION OF DISCREPANCY: LER (LASALLE) WHILE UNDERGOING A STARTUP THE 100 DEGREE /HR HEATUP RATE WAS EXCEEDED. THE CAUSE WAS AN OVER DEPENDENCE ON THE CRT BY THE OPERATORS RECOMMENDATIONS: A GSU OPERATORS ARE NOT NORMALLY GOING TO USE THE CRT TO PLOT HEAT-UP RATE. RECORDER ON P-845 WILL BE USED. ACTION: APPROVED BY GSU MANAGEMENT (s) ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING 1 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR Pt_.A N T DATE: 03/14/81 HED NO. :: 770 REVIEUER: LCR/ LIDDLE TRACKING STATUS: SCHEDULE PHACE DATA COur:CE: OFERATIONAL EXPERIENCE REVIEW CHECVLIST NO.: PAfJCL/WORI:GT ATION NO. LER-387-OC070 DESCRIPTION OF DISCREPANCY: LER (SUSOUEHANNA) SURVEILLANCES MISSED DUE TO A LACK OF A TRIGGER MECHAfJISM TO PERFORM THEM PRIOR TO ENTRY INTO O.C. #2. CHANGE MADE TO GENERAL OPERATING PROCEDURE REDUIRING COMPLETION OF SURVEILLANCES PRIOR TO ENTRY OF O.C. #2. FECOMMENDATIONS: THIS IS ADDRESSED IN RBS GOP PROCEDURE. NO FURTHER ACTION REQUIRED. ACTION: O APPROVED DY GEU MANAGEMENT E t< DCR # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD i O l
DISCREPANCY RECORD HUMAN ENGINEERING fm RIVER BEND NUCLEAR PLAN'T t i HED NO.x 780 J DATE: 08/I4/84 REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
- - - - -_.- _ - - - - = _ - -_- - ---------------------------
DATA SOURCE: OPERATIONAL EXPERIENCE REVIEW CHECKLIST NO.: PANEL / WORKSTATION NO. LER-387-83070
- - - - - - - - _ - - - - - - - - -=_
- - - - - - = - -
- - _ - = - - - - - - - - - _ _ --_- - - - - _ _
DESCRIPTION OF DISCREPANCY: SYSTEM REQUIRED TO MAINTAIN 1/8 IN. POSITIVE PRESSURE WITH FLOW OF 5820 SCFM. FLOW LIMIT OMITTED FROM PROCEDURE. SURVEILLANCE RECORDED FLOWS OF 6000 AND 6200 SCFM ON SUBSYSTEM. PROCEDURE WAS SUCCESSFULLY CORRECTED. RECOMMENDATIONS: THIS WILL BE ADDRESSED IN RBS PROCEDURE AND VERIFIED DURING PRELIMINARY TESTING. p d ACTION: APPROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
------=
= - - _ - -
-------- ----------=. - - - - - - - - - - - _ - - - - = _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD I
H U l*I A N ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PL ANT DATE: 04/24/84 HED NO. :: 777 REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OFERATIONAL EXPERIENCE REVIEW CHECELIST NO.: PANEL /WORLSTATION NO. LER-416-83067 ( 1.) DESCRIPTION OF DISCREPANCY: DIVISION I ECCS WAS INOPERABLE DUE TO ANNUNCIATORS WHICH WERE THOUGHT TO BE OFERABLE DURING MODE CHANGE BUT WERE LATER SHOWN TO HAVE BEEN INOPERABLE AT THAT TIME. RECOMMENDATIONS: GSU STP WILL VERIFY REQUIRED SYSTEM OPERATIONS. RBS TRAINING ADDRESSES THIS MODE CHANGE SITUATION. ACTION: APPROVED BY GSU MANAGEMENT Et<DCR # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEt1ENTATION SCHEDULE: PRIOR TO FUEL LOAD i l
- . . . - . . . - . - - - . __ . . _ ~ ._ __. ____ _- - -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 04/10/84 HED NO.a 638 i REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
.---=_ = - = - - __ _=----
DA'IA SOURCE: OPERAIlONAL EXPERIENCE REVIEW
^
CHECKLIST NO.: PANEL /WORl'.ST AT ION NO. LER-416-92047
---------------------------------------------------------_- _ _ - = - _ - - - - - - - = - - - - - - - - -
j DESCRIPTION OF DISCREPANCY: i GRAND GULF LER WHEN TENSIONING THE RPV HEAD A PROCEDURAL.AND OPERATOR ERROR j WAS MADE DY NOT VERIFYING THE 70 DEGREE T.S.(TECH. SPEC. 4.4.6.1.4.D) e RECOMMENDATIONS: THIS PROBLEM IS ADDRESSED IN TRAINING AND THE APPLICABLE GSU PROCEDURE WILL 2 CONTAIN THE TEMPERATURE VERIFICATION REQUIREMENT. 1 ) i ACTION: APPROVED BY GSU MANAGEMENI E t<DCR # ISSUE DATE / / FDDR# ISSUE DATE / /
- - - - - - - - = - - - - - - - - = = _ _ _ ------
--------. = = = - - - - - - - = - = - - - - - - - - - - - - - - - - - - - - -
l CRITICALITY RATING: 1 i IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD I
}
i
- O 4
i 5 h
H LJ M A N ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L.E A R P L. A N T DATE: 0//CS/O1 HED NO- : 8 3 Cl REVIEWER: DICHOP/HOWELL TRACKING STATUS: SCHEDULE PHASE DATA SOURCL: l AS) . ANALYSIS CHEClLIST NO.: F ANEL/ WORI.Sl AT ION NO. LOCAL VLV ( 1.) E12-F049 REMOTE SHUTDOWN PANEL DESCRIPTION OF DISCREPANCY: (5CENARIO E/bEQUENCE 390) THE 1 ASl;/SUDTASK SAYS " REQUEST AUX OPERATOH TO POSITION TO OPEN RHR RADWASTE INBOARD ISOLATION VALVE". HOWEVER, THERE IS NO CONTROL OR POSITION INDICATION PROVIDED FOR E12-F049 ON C61*POO1. RECOMMENDATIONS: CHANGE PROCEDURL. LOCAL OPERATION IS A VIABLE OPTION WITH THIS EVOLUTION ACTION: APPROVED DY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDRh ISSUE DATE / / CRITICALITY RATINLi: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD
~T RIVER BEND NUCLEAR PLANT (U DATE: 08/10/84 HED NO a 847 REVIEWER: BISHOP /HOWELL/MCGHEE TRACKING STATUS: SCHEDULE PHASE
==----- -- - ------------- __________
________________________=- DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: PANEL / WORKSTATION NO. P601 ( 1.) LO-LO RESET ADS PRESS. RLF INHIBIT LOGIC (AB)RST _- __ = - -
---________. ._==__ _
DESCRIPTION OF DISCREPANCY: (SCENARIO A/ SEQUENCE 1720) THE TASK / SUBTASK SAYS POSITION TO RESET ADS PRESSURE (LOW-LOW) RELIEF INHIBIT LOGIC A&B RESET. HOWEVER,THE SWITCHES ARE PRESENTLY LABELED INCORRECTLY. THEY SHOULD BE LABELED "SRV LOW-LOW SET / RESET" FOR A & B TRAIN. RECOMMENDATIONS: EVALUATE FUNCTION OF SWITCHES AND CHANGE LABELS IF APPROPRIATE. O ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 04/OC/84 F4 EE E) b4 C3 . = C51 C) REVIEWER: CHASE TRACMING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL / WORKSTATION NO. P601-17B ( 1.) 1EGS-E1C SERVICE WATER OUT TEMP. DESCRIPTION OF DISCREPANCY: SUBJECT DISPLAY IS NOT ON SAME INSERT AS HPCS DIESEL RECOMMENDATIONS: CHANGE LOCATION OF METER TO SAME INSERT AS HPCS. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 9
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT (% HED NO s 565 DATE: 2/23/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/CHASC
-- -__ -=_ - - ~ _ _
DATA SOURCE: BWR OWNERS GROUP CHECI: LIST NO. : PANEL / WORKSTATION NO. P680 ( 1.) DESCRIPTION OF DISCREPANCY: (DEVIATION VS O-1007) CONTROLLERS 3D L 2D HAVE DIFFERENT VERTICAL SCALES
; RECOMMENDATIONS:
UTILITY STATIONS C33-R601A, R601B L R613 HAVE DIFFERENT VERTICAL SCALES DUE TO THEIR FUNCTION. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGMENT. 1 I E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / ___-______________________=--- CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: i { I lO i l l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/28/84 F4 EE I) b4C3. = 1974 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCL: CONiROL ROOM SURVEY - NUREG 0700 CHEO, LIST NO.: GUIDELINE ARCA: CONTROL ROOM WORKSFACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUB-CATEGORY: ILLUMINATION PANEL / WORKSTATION NO. F680-01 ( 1.) PANEL /WORLSTATION NO. P680-02 ( 1.) PANEL / WORKSTATION NO. P680-03 ( 1.) PANEL / WORKSTATION NO. P680-04 ( 1.) PANEL / WORKSTATION NO. P680-06 ( 1.) PANEL / WORKSTATION NO. P680-05 ( 1.) PANEL / WORKSTATION NO. P680-07 ( 1.) PANEL / WORKSTATION NO. P680-08 ( 1.) PANEL / WORKSTATION NO. P680-09 ( 1.) DESCRIPTION OF DISCREPANCY: THE LISTED PANELS HAVE BELOW THE RECOMMENDED 50 FOOTCANDLES FOR SEATED OPERATOR STATION RECOMMENDATIONS: EVALUATE LIGHTING OVER THIS PANEL. ACTION: STONE t< WEBSTER IS EVALUATING CONTROL ROOM LIGHTING AS A RESULT OF DCRDR. FINAL LIGHT READINGS WILL BE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED AND FLOORING IS INSTALLED ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT g} \ V HED NO. s 198 DATE: 02/28/84 REVIEWER: BARKS / CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - _ _ - - = - - - - - - _ . _ __
- == ---------------------------------------
DATA SOURCE: CONTROL ROOM SURVEY - NUREG 0700 CHECKLIST NO.: GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUB-CATEGORY: ILLUMINATION PANEL / WORKSTATION NO. P870-54 PANEL / WORKSTATION NO. P870-55 PANEL / WORKSTATION NO. P870-56 PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32
- =------------------------------_ --------------------------
=_ __--------=_
DESCRIPTION OF DISCREPANCY: x_/ SHADOWING OCCURS WHERE LIGHT LEVELS ARE LOW ON THE LISTED PANEL INSERTS RECOMMENDATIONS: EVALUATE LIGHTING LUMINANCE DISTRIBUTION ACROSS CONTROL BOARDS ACTION: SAME AS HED #193 ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/04 F1 EE I) P4 C3 . = 1 EP ~' REVIEWER: BARl:S/ CHASE TRACKING STATUS: SCHEDULE PHASL DATA SOURCE: CONTROL ROCM buRVEY - NUREG 0700 CHECKLIST NO.: GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUD-CATEGORY: ILLUMINATION PANEL / WORKSTATION NO. P870-54 ( 1.1 PANEL /WORl' STATION NO. P870-55 ( 1.) PANEL /WORLSTATION NO. PG70-56 ( 1.) PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-02 ( 1.) DESCRIPTION OF DISCREPANCY: AT THE ENDS OF THE TWO BENCH LOARD LISTED THE TASK AREA LUMINANCE RATIOS ARE LOWER THAN MINIMUM LEVELS ALLOWED SINCE THERE ARE NO LIGHTING FIXTURES EXTENDING OVER THESE PORTIONS OF THE CONTROL DOARDS RECOMMENDATIONS: INVESTIGATE DESIGN STANDARD FOR PGCC CONTROL ROOM LIGHTING AND CORRECT TO MEET HUMAN FACTORS MAINTENANCE PLAN STANDARDS ACTION: STONE t< WEDSTER IS EVALUATING CONTROL ROOM LIGHTING AS A RESULT OF j DCRDR. FINAL LIGHT READINGS WILL DE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED AND FLOORING IS INSTALLED. 1 i EtDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: FRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
,-s
( ) 'V DATE: 07/25/04 HED NO a 833 REVIEWER: HOWELL/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - _ - - - _ =- - - - -=_--=---------------------------------------- - - _ _ _==-----
DATA SOURCE: TASK ANALYSIS CHECKLIST NO. PANEL / WORKSTATION NO. PBOB ( 1.)
--------------------------- =_=__ -----------------------------------_-
DESCRIPTION OF DISCREPANCY: (SCCNARIO D/ SEQUENCE 480) THE TASK / SUBTASK STATES " OBSERVE CONTAINMENT /DRYWELL PRESSURE" AND THERE IS NO INSTRUMENT LABELED " CONTAINMENT PRESSURE" IN THE CONTROL ROOM RECOMMENDATIONS: ADD LABELS TO RECORDERS 1 CMS-PR2A & 2B TO INDICATE CONTAINMENT PRESSURE. ACTION: O APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATZ / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O s f
HUMAN ENGINEERING DISCREPANCY RECORD - RIVER BEND NUCL EAR PI. ANT DATE: 02/28/04 HED NO a 19:3 REVIEWCRs DArd S/ CHAM /SHANKLE TRACKING STATUS: SCHEDULE PHASE - - - - - - - - - - . . . - . . . . . . . - - - - - - - - - - = - _ - __=----- ------------------------------- DATA SOURCC: CONTROL ROOM SURVEY - NUREG 0700 CHEClL13T NO. GUIDELINC (4:CA: COtlTh0L ROOM WORUSPACE PRODLEM CATEGDF.n ENV I rot 4f1Et4T PROLLEM SUD-CATEGOR): ILLUMINATION PANEL /WORESTATIOf4 NO. P870-56 ( 1.) . PANEL / WORKSTATION NO. PO70-55 ( 1.) PANEL /WGPI: STATION NO. FB77-31 ( 1.) PANEL / WORKSTATION NO. F1377-22 ( 1., PANEL / WORKSTATION NO. P601-16 ( 1.) PANEL / WORKSTATION NO. P601-21 ( 1.) PANEL / WORKSTATION NO. P601-20 ( 1.I PANEL /WOIESTATION NO. P601-17 ( 1.1 PANEL /WORKSTATIOt4 NO. P601-1B ( 1.1 PANEL / WORKSTATION NO. P601-19 . ( 1.) PANEL /WCRESTATION NO. PbO1-22 ( 1.)
- - - - - - - - - - - - - - - - - - - - - - - . - - - - - . = = = _ _ _ - - - - - - - - _ = _ _ = _ ------------------
DESCRIP TION OF DISCRCPANCY: THC LISTED PANELS INSERTS ARE ILLUMINATED BELOW THE 20 FOOTCANDLES MINIMUM RECOMMENDATIONS: LIGHTIt4G SHOULD PE EVALUATED OVER ABOVE PANELS. REASSESS LIGHTING MEASUREMENTS AFTER INSTALLATION. ACTIOf4: STONE t WEBSTER IS EVALUATING CONTROL ROOM LIGHTING AS A RESULT OF DCRDR. FINAL LIGHT READINGS WILL DE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMCtfTED AND FLDORING IS INSTALLED. EtDCOs ISSUE DATE / / FDDkt ISSUE DATE / / CRITICALITY RATING: 1 1MPLEMENTATION SCHEDULE: PRIOR TU FW1. LOAD
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUC L.E AR PL ANT HED NO. s 307
'd DATES 04/02/04 REVIEWER: CHASE TRACKING STATUS: SCHEDULE PHASE
________________________________ ---=___________=_---_-_-=____________________ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL / WORKSTATION NO. P877 ( 1.) ANNUNCIATOR COMPONENT DESCRIPTION NOT FOUND
--- =_===____ =_ _ -- ___________-
DESCRIPTION OF DISCREPANCY: SEVEN CONDITIONS WILL RENDER HPCS INCAPABLE OF RESPONDING TO AN AUTOMATIC EMERGENCY START SIGNAL. HOWEVER, ALL OF THE CONDITIONS DO NOT ACTUATE SUBJECT WINDOW RECOMMENDATIONS: DESIGN CHANGE IN PROGRESS (FDDR 1417) TO CORRECT CONDITION. ACTION:
'q IMPLEMENT DESIGN CHANGE.
g Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / ______________=- =__________ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
~
I l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND N U Ct-.E A R PI_ ANT DATE: 04/C4/84 HED N O . :: 775 REVIEWER: SPDS TRACKING STATUS: SCHEDULE F'HASE
.=== ===-----------------------
DATA SOURCE: OTHER CHECKLIST NO.: PANEL / WORKSTATION NO. SPDS ( 1.) DESCRIPTION OF DISCREPANCY: THERE IS NO DIRECT READOUT OF CST WATER LEVEL EXCEPT THROUGH USE OF THE SPDS AND CRT DISPLAYS RECOMMENDATIONS: THIS REG. GUIDE 1.97 CATEGORY 3 PARAMETER MAY BE PROCESSED ON DEMAND FOR DISPLAY AND IS NOT REQUIRED TO BE SEISMICALLY OUALIFIED. THEREFORE, THE PRESENT DESIGN OF DISPLAYING THIS PARAMETER THROUGH THE PROCESS COMPUTER AND SPDS DATABASE IS ADEOUATE. h NO FURTHER ACTION REQUIRED. ALIION: APPROVED BY GSU MANAGEMENT. Et<DCR 4 ISSUE DATE / / FDDR# ISSUE DATE / / _==------------------------------ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
, ~x
) DATE: 04/24/84 HED NO.a 776 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
_ ---------------------- - -- -_ _---------------=== - ===_ ---- DATA SOURCE: OTHER CHECKLIST NO.: PANEL / WORKSTATION NO. SPDS ( 1.)
=---------==- _-_---_--- == -_ - _ = - - - - - - - -
-- ==-
-------=__ ._
DESCRIPTION OF DISCREPANCY: THE SPDS DATA BASE DOES NOT CONTAIN THE STATUS INFORMATION FOR THE MAIN STEAM
- LINE RADIATION RECOMMENDATIONS:
INFORMATION CONCERNING THIS VARIABLE IS AVAILABLE ON PANELS 1H13*P669,P670,P671,AND P672. HIGH MAIN STEAM LINE RADIATION WILL AUTOMATICALLY INITIATE A SCRAM OF T!--! REACTOR PROTECTION SYSTEM AND WILL BE ANNUNCIATED ON PANEL 1H13*P601. _ THEREFORE, NO DESIGN CHANGE IS CONSIDERED NECESSARY. V ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------------- = - - - - - -- == _ - ---------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/29/B4 F4 EEI) PJ C3 = 55 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE _ - - = _ - - = - - - - - - - - - = = = - - --------
==
DATA SOURCC: BWR OWNERS GROUP l CHECKLIST NO. A2.1 l CHECKLIST AREA: PANEL LAYOUT AND DESIGN 1 l PANEL / WORKSTATION NO. C61-POO1 ( 1.) DESCRIPTION OF DISCREPANCY: NO MIMIC OR DEMARCATION USED TO DISTINGUISH SYSTEMS OR COMPONENTS RECOMMENDATIONS: USE COLOR CODING, LINES OF DEMARCATION, MIMICS, AND HIERARCHICAL LABELING TO SIMPLIFY OPERATION OF PANEL. ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
---=. = =_- -=- -----
=_
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED N O . :: 3 1 4:2 (/w w) REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNF.RS GROUP CHECKLIST NO.: A2.10 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PU63=76 ( 1.) 1HVFaAOD37A COMPONENT DESCRIPTION NOT FOUND ( 2.) 1HVF*AOD37B COMPONENT DESCRIPTION NOT FOUND
-------------------------- --------=_- - - - . _
DESCRIPTION OF DISCREPANCY: THESE TWO AIR INLET DAMPERS HAVE NOT BEEN MIMICED TO SUPPLY AIR IN. RECOMMENDATIONS: ADD MIMIC TO SHOW SUPPLY AIR INTO DAMPERS. O (..)- ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
. = ----
==. ------- _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER (~ ! V) I 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 F4 EE I) b4 C3 . = db REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR CWNERS GROUP CHECKLIST NO.: A2.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1 ( 1.) DESCRIPTION OF DISCREPANCY: DEMARCATION NOT USED TO ENCLOSE METERS RECOMMENDATIONS: NO ACTION - ONLY 5 METERS PRESENT AND ARE ADEQUATELY SPACED FROM ADJACENT ILC ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: 1 1 I t O
l HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR P L AN'T 3 7y F4 EE E) 7F (_) DATE: 02/29/84 bJ C3 . - REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE _ _ _ ______=- - _== -- _ - - _ _ _ _ _ - - - DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.3 CHECHLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1 ( 1.) DESCRIPTION OF DISCREPANCY: SUBGROUPS OF COMPONENTS ARE NOT GROUPED RECOMMENDATIONS: USE COLOR CODING AND HIERARCHICAL LABELING IF APPROPRIATE TO SUPPLEMENT DEMARCATION ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / ______________________= CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U CI_.E A R PL ANT DATE: 02/29/84 F4 EEI) b4 C3 . = E3 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKSTATIGt NO. C61-POO1 ( 1.)
= - _ _ __----_------_--
DESCRIPTION OF DISCREPANCY: THE VALVES FOR THE RHR SYSTEM ARE NOT ARRANGED TO BE EASILY RECOGNIZABLE RECOMMENDATIONS: PROVIDE MIMIC FLOW DIAGRAM ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
--_-____----_------__---__-----____= ==_ ___________-_--___--__-_-_-_--_-_-_
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER r l l
)
1 l ENGINEERING DISCREPANCY RECORD ( HUMAN l RIVER BEND NUCLEAR PL ANT l n HED NO a 466 DATE: 02/23/84 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
=
- == - - = = = = - - - - - -
- = - - - -_ _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-1 _ =_. DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS, OR OTHER GRAPHICS ARE NOT LAID OUT SO THAT FLOW PATHS AND ARRANGEMENTS ARE ORDERLY AND EASILY RECOGNIZED. (ADD ISOLATION VALVE INDICATORS TO MIMIC) (REDO MIMIC) RECOMMENDATIONS: i REWORK MIMIC
\ \_)
ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / 4 FDDR# ISSUE DATE / /
--= . _ -- ----------__
--- _ =------------ _== _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT O DATE: 02/C9/84 HED NO- m 25 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
--------------------------- -------- ==-----== ------ .-- ----------
DATA SOURCE: BWR OWNERS GrDUP CHECKLIST NO.: A3.1 CHECKLIST AREA: PANEL LAYOUT (4ND DESIGN PANEL / WORKSTATION NO. IRSS-PNL102 ( 1.)
==--------------
DESCRIPTION OF DISCREPANCY: THERE ARE NO LINES OF DEMARCATION FOR RHR LOOPS B & C FOR SYSTEM ENHANCEMENT PECOMMENDATIONS: ADD LINES OF DEMARCATION BETWEEN SYSTEM TRAINS B L C. ACTION: APPROVED DY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i O
l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT HED NO. s 26 DATE: 02/29/84 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _ _ - = _ ---------
--------- __. -----=. _ -__ - - - - - = = _ - _ - - _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A'3.1 CHECKLIST AREA: FANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. 1RSS-PNL102 ( 1.) DESCRIPTION OF DISCREPANCY: THE B TEST RETURN VALVE IS AFTER THE B INJECTION VALVE. RECOMMENDATIONS: NO ACTION. TRAINING WILL IDENTIFY PROPER SEQUENCE OF SYSTEM INITIATION. O ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: l l l
ENGINEERING DISCREPANCY RECORD HUMAN RIVER BEND N U Ct._ E A R P L. ANT HED NO. :: 77 DATE: OC/27/84 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.1 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 ( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO. P863-73 ( 1.) PANEL / WORKSTATION NO. P680-2 ( 1.) PANEL / WORKSTATION NO. P680-3 ( 1.) 9 DESCRIPTION CF DISCREPANCY: CONTROLS AND DISPLAYS ARE NOT GROUPED ACCORDING TO SYSTEM RECOMMENDATIONS: ADD LINES OF DEMARCATION AND COLOR CODING AS APPROPRIATE ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
= _ - - - - - - - - - _ - - - - - - - - - = - - - - -
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER O
-(
HUMAN ENGINEERING DISCREPANCY RECORD X RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO. :: 3428 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE ,
-DA1A SOURCE: BWR OWNERS GROUP CllECKLIST NO.: AO.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORl: STATION NO. P680-2 PANEL /WOki;S'I ATION NU. P680-3
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = _ - - - _ - - -
DESCRIPTION OF DISCREPANCY: ORDERING FOR COMPONENTS IS NOT CONSISTENT LEFT/RIGHT OR TOP / BOTTOM RECOMMENDATIONS: INSERT 3C, CHANGE LEVEL A OR D BUTTONS FROM B/A TO A/B. MASTER CONTROLLER TO j BE MOVED TO BE AT RIGHT OF GROUP. ACTION: APPROVED BY GSU MANAGEMENT s ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / /
- = - - _ _ _ - - - - - - - . . - - - - - - - - - - - - - = _ _ _ --- -
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i 1 1 O
. - . , - , , - - - - , - + emr--. ~ - - - - --- ,- -- . ---.-,r---na--.. . ,,--, ,- - .,e .., --- , , r-
biUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T DATE: 02/23/84 F4 EE I) b4 C3 . = 4t 1 77 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.C CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P690-6
----------------------------------------=__ -----------------------------
DESCRIPTION OF DISCREPANCY: THE ORDERING OF COMPONENTS OF SIMILAR FUNCTION IS NOT CONSISTENTLY FROM LEFT-TO-RIGHT OR FROM TOP-TO-BOTTOM (KEY LOCK SWITCHES SHOULD BE GROUPED WITH SCRAM DISCHARGE VOLUME AND SCRAM RESET BUTTONS TOGETHER). RECOMMENDATIONS: NO ACTION. THE LOCATIONS AND SEQUENCE TO OPERATE THESE SWITCHES IS THOROUGHLY ADDRESSED IN TRAINING. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------ ---------------- _== -------------------------------
t i CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: l l O
HUMAN ENGINEERING DISCREPANCY RECORD m RIVER BEND NU C L.E AR PL ANT DATE: 02/29/84 F4 EE E) PJ C3 . a 1 C) REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
= -------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.1 CHECVLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. GENERIC ( 1.) B21F051D MANUAL BLOWDOWN VALVE DESCRIPTION OF DISCREPANCY: THERE IS NO PLANT STANDARD LIST FOR COLOR USAGE RECOMMENDATIONS: MAKE PLANT STANDARD LIST AND INCLUDE IN MAINTENANCE PLAN ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: FRIOR TO FUEL LOAD 4 O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C I_. E A R PL_ A N T O DATE: 02/23/8-4 HED N O :: 421 hEVIEWLR OURGY/LH45L TRACKINO STATUGs SCHEDULE F'HAbL DATA SOURCE: E:UR OWNERC GROUf' CHECLLIST NO.: A4.2 CHLClLIST Ahl4: FANLL LAYOUT AND DESIGN PANCL/WORLSTATIOf4 NO. P6DO-4 PANLL/WDRES1ATIOfi NO. P600--L FANEL/WORFGTATION NO. P680-6 DESCRIPTION OF DISCREPANCY: SELECTED USE OF COLORS IS NOT CONSISTENTLY APPLIED FOR ALARM PRIORITIZATION (NO DIFFERENTIATIOf4 ON ANf4UNCIATOR 4C). RECOMMENDATIONS: DEVELOP ANNUNLIATOR COLOR SCHEME AND IMPLEMENT THROUGHOUT CR ACTION: AF F ROVED DY GSU MANAGEMENT. E t,DC R # ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATINO: I IMPLEME;4TATION SCHEDULE: FRIOR TO EXCEEDING 5% POWER I l l [
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT HED NO.a 830 DATE: 09/19/04 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: OPERATING PERSONNEL INTERVIEW CHECVLIST NO. A5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680 DESCRIPTION OF DISCREPANCY LABEL FOR MANUAL " INITIATION" OF CONTAINMENT SHOULD READ "! SOLATION" ON P600. RECOMMENDATIONS: CHANGE LABELS ON INSERT 7D TO READ ISOLATION INSTEAD OF INITIATION. ACTION: i APPROVED BY GSU MANAGEMENT. l L I ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i i
ENGINEERING DISCREPANCY RECORD HUMAN RIVER BEND N U C L.E AR Pt._ A N T HED NO. :: 804 DATE: tY/ / 28 / 04 REVIEWCR: LINI. TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: Of ERATING f EF<bONNEL INTERVIEW CilCCI.: LIST NO. A5 l CHLLILIST hhlha IwNLL LAYOUT AND DESIGN l l F AtlLL /WORI .S T AT 10tJ NO. PO63 ( 1.) DECCRIPTION OF D I SCREP AtJCY : LAl;CL FOR 1 HVReAOD 263 AND 264 MISWORDED (SHOULD DE : TEST TO SGT") ON PO63. fiECOMMENDAT IOtJ3 : CH.4NGC LAl'LL TO ItiDICATE CORRECT FUNCTION. ACTION: AfPh0VED DY GCU MAtJ4,GEME NT . E R. D C R M ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATIOt1 SCHEDULE: PRIOR TO EXCEEDING 5"/. POWER O
_. . . ~_ . . _ _ = , __. _- .-. . _ _ . l 1 i l HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCL EAR PL. ANT t b- DATE: 02/22/04 HED No.a 28"3 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: BWR OWNERS GROUP
; CHECKLIST NO.: A3.1
, CHECELIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19 i 1 DESCRIPTION OF DISCREPANCY: THERE ARE NO LABELS ON INDICATING LIGHTS BELOW SLC PUMP A RECOMMENDATIONS: LABELS HAVE BEEN ADDED SINCE SURVEY. NO FURTHER ACTION REQUIRED. ~ ACTION: APPROVED BY GSU MANAGEMENT. j 3 r i i o l ELDCR# ISSUE DATE / / } FDDR# ISSUE DATE / / 1
@mmerm6666MMWe#M66m6MMMMW.WWWWWSMmmeMWWWWMmmemmehmmmmmmemememememmmmmmem-mememe CRITICALITY RATING: I ; IMPLEMENTATION SCHEDULE:
i i 4 I t I i i h
',.__,_ _ _ , . - . . . _ . . . . _ , , , , . . _ _ _ . _ . _ . - _ , _ _ , _ _ _ _ _ _ . . _ , _ _ , _ _ . , _ _ _ , _ - _ _ . , , , , . , , , . , _ _ , _ . _ . , _ . . . . , . , , , , ,o,.-.~
1 1 HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T DATE: 02/04/04 HED NO. m 747 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: bWR OWNEFS GROUP CHECt .L I 5 T NO. A5.I CHEClLIST AREA: PANEL LAYOUT AND DESIGN FANEL/WORI. STATION NO. P680-7D DESCRIPTION OF DISCREPANCY: MISSING ESCUTCHEONS FOR MN STM ISLN MANUAL. INITIATION - B21H-525 AbD. (MISSING DECAUSE STANDARD SIZE ESC. CON B&C) WON'T FIT FOR A&D.) RCCOMMENDATIONS: ADD ESCUTCHEONS TO MN STM ISLN MANUAL INITIATION PUSHBUTTONS ACTION: AF F ROVED DY OSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: I IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD i O L
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT p (_) DATE: 02/23/84 F4 EE E) bJ C3 . a "5 JL <> REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE _ - - - - - - - _ - - _ = - - _ _=------------
---== =_ _ - - - - - - - - - - - - - - - - - - - = = _ _ _ - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECULIST NO.: A5.1 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-8BLC PANEL / WORKSTATION NO. P680-9
--------------------------------------------------------------------==-__ ___==-
DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES, OR ESCUTCHEONS ARE NOT USED TO IDENTIFY COMPONENT FUNCTION. (NO LABELS ON TURBINE INSERT BLC) THREE TRIP BUTTONS,MULTISCALE METERS,TWO POTENTIOMETERS, UNITS ON METER FACE. UPGRADE DUE TO IMPORTANCE OF FUNCTION AVAILABILITY. RECOMMENDATIONS: P680-8B L C INSERTS REQUIRE LABELING. AN RCF IS BEING GENERATED TO HAVE THESE LABELS MADE AND INSTALLED. ACTION: i AFFROVED BY GSU MANAGEMENT. 4 i ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / _-----_-_---_--==--=-- =----_---------_ -- --_-____------_---_-_-_-_--_---__-__ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: FRIOR TO FUEL LOAD i i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 9 DATE: 02/24/84 HED NO- :: 225 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - _ - - - - - - - - - - - - - - _ _ _ - - - - - = - - - - _ _==--- _----_--------_------_--
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.1 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. POO8-81B
. ( 1.) --_-_------_---------------__---_-_-__-_-- __----- _----=. --. =--------
DESCRIPTION OF DISCREPANCY: TWO BAILEY CONTROLLERS HAVE LABELS THAT SAY ONLY ' DIVISION l' & ' DIVISION 2*: EEVERAL UNLABELED COMPONENTS RECOMMENDATIONS: ADD LABELS TO INDICATE NAME, FUNCTION AND DIVISION TO COMPONENTS ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l 9
DISCREPANCY RECORD HUPsAN ENGINEERING ' RIVER BEND NUCLEAR PLANT HED NO. a 236
'- DATE: 02/C4/04 REVIEWER: LIDDLL/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
--__-_____-_-_ - - - _ = =
_ _ - _ - - _ _ = - = - DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.1 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORV. STATION NO. POOO-83B PANEL / WORKSTATION NO. P808-84B
._-_--___-__-_...._-_________-.-_-__.=---
DESCRIPTION OF DISCREPANCY: LABELS SHOULD DIFFERENTIATE BETWEEN THE DIFFERENT PENS RECOMMENDATIONS: CHANGE LABELS TO DIFFERENTIATE BETWEEN PENS USING A COLOR DOT CODE AND FUNCTION / PARAMETER NAME (~ U ACTION: APPROVED BY GSU MANAGEMENT. i ELDCRM ISSUE DATE / / l FDDRM ISSUE DATE / / CRITICALITY RATING: 1 . IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER a 1 [
1 HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct._E A R Pt_ ANT DATE: 02/27/84 HED N O :: 80 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECt: LIST NO. A5.1 CHECl' LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. F'865-71 ( 1.) 1HVR-AOD241 DECAY HEAT REMOVAL INLET ( 2.) 1GTS FLT1B DECAY HEAT REMOVAL OUTLET DESCRIPTION OF DISCREPANCY: DECAY HEAT REMOVAL OUTLET IS LABELED INLET /AGTS-FLT1B IS NOT LADELED RECOMMENDATIONS: RELAEEL TO SAY OUTLET. AGTS-FLT1D LABEL HAS BEEN ADDED SINCE CR SURVEY. ACTION: APFROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER O
.e DIBCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT O NO_s 2 687 O DATE: 02/21/04 HED TRACNING STATUS: SCHEDULE PHASE RCVIEWCRs LIDDLE /MATSON/DISHOP ! DATA SOURCE: BWR OWrJERS GROUP CHECLLIST NO.: A5.1 ' CHEClLIST AREA: PANEL LAYOUT AND DESIGN i
I
! FANCL/WORKSTATIOt1 f 40. P870-55C PANEL /WORKST AT Iota NO. P070-56C I
i ________________________ .________. ___ . .___________....___.____.________..__ l DESCRIPTION OF DISCREPAtJCY: i 1 THREE POSITION SWITCHES HAVC NO AUTO FUNCTION NOTED ON LABEL OR ESCUTCHEO RECOMMENDATIONS: PERFORM ENGINEERING EVALUATION TO DETERMINE IF 3RD POSITION HAS A FUNCTIO IS IN tJEUTRAL POSITIOr4 AND RELABEL IF REQUIRED. l 1 ACTION: } ALL 3 POSITION SWITCHES ON P-070(WITH ONLY 2 FOSITIONS LABELED)WERE l EVALUATED.!T WA3 DETERMINED THAT 1DSR-MOV109 AND 1DSR-MOV107 ' SPRING RETURN HAVE TOAUTO ,
; FutJCT IONS AtJD THESC LAL'ELS WILL E4C CHANGED. ALL OTHERS ARE i NEUTRAL', REQUIRING 90 LADEL CHANGE.
h ISSUE DATE / /
- Et<DCR N
. FDDRM ISSUE DATE / / i i i F
- CRITICALITY RATING
- 1
\ IMPLEMENTATION SCHEDULE: FRIOR TO EXCEEDING 57. POWER i i 1 i io ; 1 j ' < l
HUMAN ENGINEERING DIOCREPANCY RECORD RIVER DEND NUCLEAR PLANT DATE: 02/29/04 HCD NO. a '2 9 FEVIEWLR: l<AFI S/CHASL/SHANt LE TRACVING STATUS: SCHEDULE PHASC DM A SOL'f <CL I Wii OWNERL GROUI' CHCCILIST NO. AS.10 CHLCFLIST 4REA: PANEL LAYOUT AND DESIGN FANCIdWORIGTATION NO. 1RSS-FNL102 ( 1.) 1E 1 2*MOVf % ?L' SHUTDOWN COOLING INJECTION VALVL ( 2.) 1E12eMOVF037D SHUTDOWN COOLING UFFER POOL VALVE DESCRIPTION Of' DISCFEPANCY: THELE VALVCG ALL NOI ACCURATELY LADELED. SHOULD DE SHUTDOWN COOLING VALVC. RECOMMCt JDA T I ON3 : ELLAl<EL AL NELLECAhY TO LE CONSISTENT WITH cot 1Th0L ROOM. ACTION: Af'Th0VED EY GSU MANAGLMENT EfDCFn ISSUC DATE / / FDDRn ISSUC DATE / / CR1TICAL!TY FiATING: 1 IMPLEMENTATION GCHEDULE: Fh!UR TO EXCEEDING L*/. POWER \ l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/22/84 HED NO.s 284 REVILWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE I DATA SOURCC: DWR OWNERS GROUP l CHCCLLIST NO. A3.10 CHECKLIST AREA: PANEL LAYOUT AND DESIGN , I k i t PANEL /WORLSTATION NO. P601-19 f i ._... .... ..... _ .....__....____.... __ ._..___ ....__........____........... DESCRIPTION OF DISCREPANCY: MAIN STEAM LINC C SAFETY RELIEF VALVE SWITCH S26A IS ACTUALLY AN ADS SAFETY i RCLIEF VALVE t i RECOMMENDATIONS:
- RELABEL TO READ ADS SAFETY RELIEF VALVE i
O ACTION: ! AFPROVED DY GSU MANAGEMENT. j i. Et<DCR # ISSUE DATE / / 1 FDDR# ISSUE DATE / / \ ,
- CRITICALITY RATINGS !
IMFLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I 1 ) f l l t 1 t 1 I
HUMAN ENGINEERINO DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO- a 427 REVIEWER: buRGY/ CHASE TRACT!NG STATUS: SCHEDULE PHASE DATA EOURCE: OWR OWNERS GROUP CHEC6 LIST NO. : AS lO CHEClLIST AREA: FANEL LAYOUT AND DESIGN PANEL / WORT: STATION rJO. F600-4 DESCRIPTION OF DISCREPANCY: LAFELS ARE NOT SUCCINCTLY WOFDED AND ACCURATE WITH RESPECT TO FUNCTION OR INPUT SIGNAL. GECIRC. FCV A/D MOTION INHIBIT RESET, USE RST TO ADDREVIATE RESET.) RECOMMENDATIONS: CHANGE LA0EL ACTION: AF F ROVCD DY GSU MANAGEMENT. E!.DCR# ISSUE DATE / / FDDRn ISSUC DATE / / CRITICALITY RATINO: 1 IMF LEMENT AT ION SCHEDULE: PRich TO EXCEEDING 5'/. POWER O
RECORD HUMAN ENGINEERING DIBCREPANCY O RIVER BEND NUCLEAR PLANT F4EE E) PJ C3 . s 1 i dh k- DATE: 02/CD/94 REVIEWER: BARUS/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHEChLIST NO.: A5.10 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PG63-75C ( 1.) 1HVC*FN3B BATTERY ROOM 18 EXH OFF ( 2.) 1HVCoACU1A CONTROL ROOM AIR HLDO. UNIT j ( 3.) 1HVC*ACU1B CONTROL ROOM AIR HLDG. UNIT 4 PANEL /WORVSTATION NO. PG63-74B ( 1.) 1HVKeL11A CPRSN TANK LEVEL METER c i i DESCRIPTION OF DISCREPANCY: 1 THESE LADELS ARE NOT ACCURATE IN RESPECT TO THEIR FUNCTION
; RECOMMENDATIONS:
4 CHANGE LALELS TO INDICATE TRUC FUNCTION ACTION: APPROVED BY GSU MANAGEMENT. T' l ELDCR# ISSUE DATE / / l ISSUE DATE / / i FDDR# 1 i CRITICALITY RATING: 1 'l IMPLEMENTAT10H SCHEDULE: PRIOR TO EXCEEDINO 5'/. POWER l 9 4 t I
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/84 HED N O - :: 274 REVIEWER: LIDDLE /MATSON/DISHOP TRACI'ING STATUS: SCHEDULE PHASE DATA COURCE: DWR OWNERS GROUF' CHECl-.L I G T NO.: AS.10 CHECl. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-55 ( 1.) 1E12-PCOO2A COMPONENT DESCRIPTION NOT FOUND ( 2.) 1E12-PCOO2B COMPONENT DESCRIPTION NOT FOUND DESCRIPTION OF DISCREPANCY: PUMP LADELS DO NOT REFLECT COMPONENT FUNCTION RECOMMENDATIONS: NO CHANGE REQUIRED.FURTHER EXAMINATION BY THE DCRDR TEAM CONCLUDED THAT LADELS ARE CORRECT ACTION: APPROVED DY GSU MANAGEMENT. E t<DCR M ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT e f C DATE: 02/23/84 HED NO- 428 REVIEWER: DURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P600-6 DESCRIPTION OF DISCREPANCY: COMPUTER TREND RECORDER A&B MISSING LABELS INDICATING WHAT INK COLORS REFER TO. p) y RECOMMENDATIONS: ADD LABELS TO INDICATE WHAT THE COLORS REFER TO AND/OR USE COLOR DOTS NEXT TO PEN NAMES ACTION: APPROVED BY GSO MANAGEMENT. ! E&DCR# ISSUE DATE / / l FDDRM ISSUE DATE / / i CRITICALITY RATING: 1 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l l lO
HUMAN ENGINEERING DIGCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO. :: 422 REVIEWER: EURGY/CStASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHECI LIST f40. : AL.O CHECFLICT AREA: PANEL LAYOUT AND DESIGN FANEL/WORKSTATICN NO. GENERIC DESCRIPTION OF DISCREPANCY: LAPCLS, LEGEND PLATES, AND ESCUTCHEONS ARE NOT USED TO IDENTIFY OPERATIONAL LIMITS OR WARNINGS, SOME METERS HAVE LIMITS SOME DO NOT. RECOMMENDATIONS: NORMAL / ABNORMAL RANGES WILL BE ADDED TO VISUAL DISPLAYS. ACTION: APPROVED BY GSU MANAGEMENT. E t,DC R # ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT FiEEI) P4 C3 . E3 1
'- DATE: 02/27/84 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
___________________________________-_____ ____= DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.' 2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P863-71 ( 1.) 1HVR-AOD125 COMPONENT DESCRIPTION NOT FOUND ( 2.) 1HVR-AOD126 ( 3.) 1HVR-AOD147 ( 4.) 1HVR-AOD148 PANEL / WORKSTATION NO. P863-72 ( 1.) 1HVR-AOD148 FANEL/ WORKSTATION NO. P863-73 ( 1.) 1HVR-AOD148
- = -
_--=_ _=-_---=- -=_ DESCRIPTION OF DISCREPANCY: THE LISTED VALVES NEED WARNING LABELS DUE TO THE POSSIGILITY OF INADVERTENT OPERATION VIOLATING CONTAINMENT INTEGRITY RECOMMENDATIONS: ADD WARNING LABELS. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER /3
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCL EAR P L. A N T DATE: 02/20/04 HED N O . :: 298 i REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: PWR OWNERS GROUP CHECULIST NO.: A5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P877-32 PANEL / WORKSTATION NO. P601-16 - - - - - _ _ - - - - - - - - _ - - - - - - _ - _ - - - - _ - _ - _ = - - - - _ _ - - - - - - . . - - - - - . - - . . _-------_----__- DESCRIPTION OF DISCREPANCY: DIVISION 2 AND 3 IS NOT LABELED RECOMMENDATIONS: DIVISION 2 LABEL HAS BEEN ADDED SINCE SURVEY. ADD DIV. 3 LABEL. h ACTION: APPROVED BY GSU MANAGEMENT. EODCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
1 HUMAN ENGINEERING DIBCREPANCY REC E.J R D RIVER BEND NUCLEAR PLANT
\'M F4EEE) P4[3 a 1 25 DATE: 02/29/84 REVIEWER: BARKS /DISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP I
CHECKLIST NO.: A5.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1 ( 1.) NUCL BLR REACTOR VESSEL LEVEL L PRESS INST. ( 2.) E51-F064 RHR CNDS HX STM LINE ISO ( 3.) E12-F024A RHR TEST LINE ( 4.) RCIC SO ROOT RCIC SQ ROOT EXTRACTOR ( 5.) E12-F037A SHUTDOWN UPPER POOL COOLING ( 6.) HRV-UC12 UNIT COOLER DESCRIPTION OF DISCREPANCY: (~} 4,,_/ THE NOMENCLATURE AND ABBREVIATIONS ARE INCONSISTENT WITH THE LABELS IN THE MAIN CONTROL ROOM RECOMMENDATIONS: RELABEL TO BE CONSISTENT WITH CONTROL ROOM LABEL STANDARDS n' ACTION: APPROVED BY GSU MANAGEMENT E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NU C L_E AR PL ANT DATE: 02/27/04 HED NO_ :: 322 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76 DESCRIPTION OF DISCREPANCY: LABELS HAVE BEEN NOTED THAT USE INCONSISTENT ABBREVIATIONS (CONTMT VS CONT AND FB VS FUEL BLDG ). RECOMMENDATIONS: ' CORRECT LABELS TO MEET STANDARD ABBREVIATION LIST ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l O
HUMAN ENGINEERING DISCREPANCY RECORD g RIVER BEND NUCLEAR PLANT DATE: 07/98/4 HED NO- a 812 f(EVI LWLit s LINK TRACKING STATUS: SCHEDULE PHASE
------------------------------=
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECVLIST NO.: Di CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601 ( 1.) DESCRIPTION OF DISCREPANCY: MAIN STEAM VALVE (MSIVs) IS DIFFICULT TO LOCATE OR ACCESS l RECOMMENDATIONS: COLOR CODE MSIV'S (INDOARD AND OUTBOARD). O ACTION: APF' ROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
--n------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR P L_ A N T O DATE: 09/28/4 HED NO. :: 82O REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
=-_ =- -----------
-=-__--__--
DATA EDURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B1 CHCCKLIST AREA: INGTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601 DESCRIPTION OF DISCREPANCY: DNE OPERATOR SUGGESTS THAT THE LPCS CONTROLS ON P601 ARE DIFFICULT TO LOCATE AND DISTINGUISH RECOMMENDATIONS: ADD ENHANCEMENTS AS REQUIRED TO PROVIDE VISUAL DISTINCTIVENESS FOR THIS SYSTEM. ACTION: APPROVED BY OSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- _ - - - - - - - - - - _ - - _ _ - _ _ - - - - - - - _ _ _ - - _ _ - - = = _
-_ ===__=-----_-___----_--
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/04 HED NO. s 2'34 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASC
- =-------- --
DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO. B1.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE FANEL/ WORKSTATION NO. P808-83B ( 1.) PANCL/ WORKSTATION NO. POO9-84B ( 1.)
=-
-_ - - = _ - _ - . - - - - _ . - ----.
DESCRIPTION OF DISCREPANCY: ONLY TWO SUPPRESSION FOOL LEVEL METERS IN CONTROL ROOM AND THEY ARE BEHIND THE 680 PANEL. ALSO THEIR RANGE IS INSUFFICIENT Q Q RECOMMENDATIONS: IN ADDITION TO THE DIV 1 & 2 METERS ON P808, THIS PARAMETER IS MONITORED BY SPDS WHICH IS IN FRONT OF P680. SINCE THE SURVEY E&DCR# 40848 WAS ISSUED WHICH ADDS NARROW RANGE LEVEL SWITCHES. THESE SWITCHES PROVIDE SIGNALS TO THE HIGH AND LOW LEVEL SUPPRESSION POOL ANNUNCIATORS. THIS SYSTEM PROVIDES THE ACCURACY REQUIRED BY TECH. SPECS. NO FURTHER ACTION REQUIRED. ACTION: APPROVCD BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O
l l l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/24/84 HED NO- = 25-5 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECKLIST NO.: Bl.1 CHCCF. LIST AREA: INSTRUMENTATION AND HARDWARE F'ANEL/ WORKSTATION NO. P808-83B PANEL / WORKSTATION NO. P808-84D
---------------------------------------------------- - =-------------
DESCRIPTION OF DISCREPANCY: USE PSIG ON RECORDERS NOT PSIA RECOMMENDATIONS: CHANGE RECORDCRS TO INDICATE PSIG ACTION: APPROVED BY GSU MAf1AGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
---------------------------------------------- - ==------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T* (,\ U DATE: 02/29/94 HED N O . :: 23 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
----------_--------------- . = = _ _ - - - -====_ ==__ ==_ . --------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B1.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) __-- = _ _ -= __ -- DESCRIPTION OF DISCREPANCY: (1) THE DEMAND SIGNAL ON THE CONTROLLERS IS NOT LABELED AS A DEMAND SIGNAL. (2) LABELS ARE NOT POSITIONED CONSISTENTLY ABOVE OR BELOW DEVICE. (3)NEED VALVE NUMBERS ON LABEL NOT INSTRUMENT NUMBERS. (4) LABELS ARE NOT ACCURATE WITH RESPECT TO FUNCTION. O k,) RECOMMENDATIONS: (1) ADD SYMBOL ON LABELS TO CONTROLLERS TO INDICATE DEMAND OR ACTUAL SIGNAL. (2) POSITION LABELS ABOVE DEVICE (3) PLACE VALVE NUMBERS ON LABELS, (4) REVIEW CONTROLLER FUNCTION AND CHANGE WORDING TO BE ACCURATE. ACTION: APPROVED BY GSU MANArEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / o
-- =-_---_-
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1 I ()
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR P L_ A N DATE: 09/19/04 HED NO_ :: 795 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING FERSONNEL INTERVIEW CHECULIST NO.: B2 CHCCKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORESTATION NO. F863 ( 1.) DESCRIPTION OF DISCREPANCY: THERE IS NO INDICATION OF CONTAINMENT ANNULUS PRESSURE RECOMMENDATIONS: RECORDER 1LMS-TR127 ON P-863 INDICATES CONTAINMENT ANNULUS PRESSURE. LABEL REQUIRES CHANGING. ACTION: CHANGE LABEL TO READ ILMS-lR127 ANNULUS TEMPERATURE / PRESSURE. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: I IMPLEMENTATION SCHEDULE: F'RIOR TO EXCEEDING 5% POWER O
l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT ( ,) DATE: 02/29/84 HED NO :: :50 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---- ------- =------------------- -
=== ==. _ -- ---
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B2.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT BANDED TO SHOW NORMAL / ABNORMAL STATE RECOMMENDATIONS: BAND OR MARK THE INDICATING DEVICES TO SHOW NORMAL / ABNORMAL STATE
~
ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / /
-. -----------------------=. - _ _ _ _-__ _--
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER w
/
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 HED N O . :: 230 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B2.11 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808-83 PANEL /WORMSTATION NO. P808-84 DESCRIPTION OF DISCREPANCY: DRYWELL TEMP METERS AND RECORDER CANGES TO ONLY 200 AND NEEDS TO GO TO AT LEAST 330 RECOMMENDATIONS: EVALUATE OPERATIONAL LIMITS OF DRYWELL TEMP RECORDERS. ACTION: EVALUATION HAS DETERMINED THAT PRESENT RANGE OF RECORDERS IS INADEDUATE. RECORDER WILL BE RECALIBRATED FOR A RANGE OF 40 DEGREES TO 440 DEGREES FARH. TO AGREE WITH REG. GUIDE 1.97 POSITION IN FSAR ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
= _ = = - - ----------------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 9
i HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT U DATE: 02/23/84 HED NO. 432 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
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-------------------------------====-- ---=
i DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B2.17 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT DESIGNED SO THAT A FAILURE MODE IS EVIDENT. (NOT KNOWN) RECOMMENDATIONS: 1
/~N ESTABLISH CONVENTIONS BY INVESTIGATING FAILURE MODES IN CONTROL ROOM km ACTION:
APPROVED BY GSU MANAGEMENT. Et<DCRM ISSUE DATE / / FDDR# ISSUE DATE / /
--==--- _.-- ---------- _ _ _ - . _ _ _ _ - -
I CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD l l l t
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct._ E A R PI-.A N T DATE: 02/29/84 HED NO- :: 1 da REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO. B2.2 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-POO1 ( 1.) DESCRIPTION OF DISCREPANCY: NO FERMANENT LIGHTING IN REMOTE SHUTDOWN ROOM RECOMMENDATIONS: INSTALL LIGHTING AND TAKE LIGHT READINGS ACTION: APPROVED BY GSU MANAGEMENT. E t.DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/C3/84 HED N O :: 479 REVIEWCR: BURGY/ CHASE TRACKING STATdSt~ ~ SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECFLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-1 _-- = ---- - _-------
------------ =. -_ =----- . -
DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT SCALED IN PROCESS UNITS THAT RELATE TO SYSTEM OPERATION. LABELLED PSIA VS PSIG. UPGRADED DUE TO ERROR POTENTIAL. RECOMMENDATIONS: CHANGE TO PSIG. O ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _z_ - _ - -
=---. --_
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 F1 EE I) P4 C3 . = 4L C51 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
-------------------------------- ------------------ =-_ --- -_ --------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680 -5 PANEL /WORLSTATION NO. P680-6 DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT SCALED IN PROCESS UNITS THAT RELATE TO SYSTEM OPERATION. (LOOP A/B FLOW RECORDER READS GPM INSTEAD OF % FLOW) (TOTAL FLOW /A PRESSURE RECORDER RED SHOULD BE % FLOW) RECOMMENDATIONS: ADD LADEL TO INDICATE PROPER SCALE UNITS FOR RECORDER. CHANGE GPM TO % FLOW ACTION: APFROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
--------------------------------=-- _ _ _ _ _ = _ _ - - _ _ - - - - - - - - - - - - - - - -
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD i e
HUMAN ENG I NE EE R I NG DISCREPANCY RECORD RIVER BEND NUCL_ EAR PL ANT q b DATE: 02/C4/84 F4EEI) P4 03 . = 52 1 :5 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808-87B ( 1.) _ - - _ = = . - DESCRIPTION OF DISCREPANCY: BATTERIES HAVE SEVEN AMP METERS THAT SHOULD BE 'DC AMPS CHARGE * & *DC AMPS DRAIN
- INSTEAD OF AC AMPS RECOMMENDATIONS:
(~T METERS HAVE BEEN CHANGED SINCE SURVEY TO INDICATE DC AMPS. NO FURTHER ACTION d REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - = - - -
------- _---- = ---------== _-
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
r DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT HED NO. :: 91 DATE: 02/27/84 REVIEWER: BARK 5/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCL: DWH OWNERS GROUF CHECULIST 140. : B2.~ CHECKLIST ARLA: Il4M RLIMLirl AT ION AND HARDWARE pal 4EL/WORUCTATIOt1 NO. P867,-73B ( 1.1 DESCRIPTION OF DISCREPAtJCY: THE UNITS FOR " MAIN PLANT EXHAUST" IS IN "% CFM" AND THIS IS CONFUSING RECOMMENDATIONS: CHANGE UNITS TO READ IN CFM ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / l CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT /..,\ M DATE: 02/24/04 F4 EE I) P4 [3 - - 02 et "5 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----------- -- . - - - - - - - _ _ - - - ==- .-----------------------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. PB70-51
=_. - - . -
- - - - - - - - - - - - - - - - - - - - - - - - ==----=-
DESCRIPTION OF DISCREPANCY: REACTOR PLANT FLOOR DRAIN AND DRYWELL EQUIPMENT DRAIN SUMP LEVEL INDICATORS ARE IN PERCENT AND NEED TO BE CONSISTENT WITH PROCEDURES WHETHER GALLONS OR PERCENT RECOMMENDATIONS: T CHANGE DRYWCLL FLOOR DRAIN SUMP LEVEL & DRYWELL EQUIPMENT DRAIN SUMP LEVEL (~/ (_ METERS TO GALLONS. , ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - - - - - - - - - - = = - - - - - - - - __
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD n m
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PL A N'T DATE: 02/20/84 HED N O :: 300 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECV. LIST AREA: INSTRUMENTATION AND HARDWARE F*ANEL/ WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32 DESCRIPTION OF DISCREPANCY: METERS ARE DC AMPS AND SHOULD BE AC AMPS RECOMMENDATIONS: NO ACTION. ITEMS CORRECTED SINCE SURVEY. ACTION: APFROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: I IMPLEMENTATION SCHEDULE: l l l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT t'3 b DATE: OC/29/84 HED NO. 32 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO.: B4.7 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.)
- - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - ---------- --== ----=-= _=_-------
DESCRIPTION OF DISCREPANCY: FOR VALVE INDICATIONS (LIGHTS) IT IS UNKNOWN IF DIRECT OR IMPLIED INDICATION USED I.E., SRV SONIC INDICATIONS RECOMMENDATIONS: INVESTIGATE DIRECT / INDIRECT STATUS INDICATIONS IN VERIFICAT!DN PHASE. THIS O INFORMATION WILL BE INPUT INTO TRAINING / PROCEDURES AS APPROPRIATE. ACTION: APPROVED BY GSU MANAGEMENT. i 6 ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / 4
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = ._----- -==-------= ------------------
i CRITICALITY RATING: 1 1 IMPL" MENTATION SCHEDULE: PRIOR TO FUEL LOAD O
.--,y -,r -- - -m-- , - - , - .,,,y . -%- - - -.,---.--.9_.. - -- -m*7-y.-- - s,.~ .-
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l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/C2/04 HED NO. :: 285 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHACE DATA EDURCE: BWR OWNERS GROUP CHEC). LIST NO.I B4,7 CHECI: LIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORI' STATION NO. P601-19 PANEL /WORl:CTATION NO. P601-19 PANEL /WORl: STATION NO. P601-22 DESCRIPTION OF DISCREPANCY: SRV POSITION INDICATION IS ACTUALLY SOLENOID POSITION RECOMMENDATIONS: DESIGN CHANGE IN PROGRESS TO GIVE DIRECT INDICATION IN CONTROL ROOM. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O i
HUMAN ENGINEERXNG DIBCREPANCY RECORD 7"T RIVER BEND NUCLEAR PLANT U DATE: 02/CD/84 HED NO_z 133 REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE ______________________________________________=__-=-==__=____ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B4.7 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE f PANEL / WORKSTATION NO. P628 ( 1.) g , PANEL / WORKSTATION NO. P631 ( 1.)
=_
___________________________________________=-==---=___________________=. DESCRIPTION OF DISCREPANCY: THE VALVE POSITION INDICATION IS SOLONOID POSITION. 4 RECOMMENDATIONS:
< DESIGN CHANGE IS IN PROGRESS TO GIVE DIRECT INDICATION OF SRVS IN CONTROL ROOM ON P-601. NO FURTHER ACTION REQUIRED.
ACTION: APPROVED BY GSU MANAGEMENT. 1 Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / i I CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: 4
, _ _ _ _. _. - . , _ . _ . , _ . _ . _ , . . . , , m. . _ , . , - . , . , , . , _ _ _ . , . , , , , , , . . ,
._r...,....m. _. ~ _ _ . .,_ _.__
H Ub1 A N ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct-.E A R PL_ A N T DATE: 02/C3/84 HED N O . :: 437 REVIEWER: BURGY/ CHASE TRACl:ING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHEClLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 PANEL /WORI: STATION NO. P680-5 F'ANEL/WORLSTATION NO. P680-6 DESCRIPTION OF DISCREPANCY: HANDLES FOR SWITCHES DO NOT MOVE CONSISTENTLY IN THE SAME DIRECTION IN ACCORDANCE WITH EXPECTATIONS. (RPS TRIP OUT-OF-SERVICE SWITCHES-NORM, IN OP POSITION SWAPF'ED.) RECOMMENDATIONS: OUT OF SERVICE INDICATION MANUAL SWITCHES ONLY, TRAINING INFORMS OPERATORS OF FUNCTION. NO ACTION. ACTION: AF FROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 1MPLEMENTATION SCHEDULE: l l t i O
. . . . . - . - . . -. .=. . - . . . . _ _ - . - .
l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT J DATE: 02/24/04 HED NO m 783 REVIEWCR: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE ____________________-_________ .________ . - - - - - - - - _ _ _ = _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DalA SOURLC: DWR OWNERS GROUP CHCCl:LIOT NO. : D3.1 l . CHECI:LICT AREA: INSTRUMENTATION AND HARDWARE l 1 i i i PANCL/WORUGTATION NO. P680-4B i i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - - - - - - - - _...-_________ ___________________________ y } DESCRIPTION OF DISCREPANCY: i MISSING DRYWELL PRESSURE METER TO INSERT 4B 1 ) RECOMMENDATIONS: l THIS INDICATION IS AVAILABLE ON P808(DIV 1L2) AND PMS. NO ACTION REQUIRED P I ACTION: j APPROVED DY GSU MANAGEMENT i l 1 l ELDCR# ISSUE DATE / / } FDDRH ISSUE DATE / / j _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . .- =-----_______________________ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: i l
'l \
i
- i t
i i i ) !O 4 1 4 t _ - - - - - . . , -_y. ,-y---pm- ---m.-- - -*-.-.. - me -..---.-w-- e-- - -----_,.%.,- ,-,,,,-m.m-.m, - , - - , , , - . -
----m--,.--,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L_ A N T DATE: 02/ % /84 HED NO. - 231 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECI'. LIST NO. : B5.1 CHEC6 : LIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808-83 PANEL / WORKSTATION NO. F808-84 DESCRIPTION OF DISCREPANCY: FUSH BUTTONS ARE OPEN ON LEFT AND BYPASS ON RIGHT WHICH IS REVERSED RECOMMENDATIONS: REVERSE FUNCTION F'OSITIONS ON SWITCHES SO THAT OPEN IS ON THE RIGHT AND BYPASS ON THE LEFT ACTION: AFFROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD I O l l \
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT
,f3 V DATE: 02/20/04 HED NO.= 3. O 1 R5 VIEWER: LIDDLE /MATSON/ BISHOP TRACING STATUS: SCHEDULE PHASE
-------_-------_---- ---------_-==
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32
=___----- _
DESCRIPTION OF DISCREPANCY: GOVERNER AND VOLTAGE REGULATOR CONTROLLERS ARE LABELED RAISE / LOWER LEFT/RIGHT RECOMMENDATIONS: FUNCTION AND LABELS TO BE CHANGED TO LOWER / RAISE LEFT/RIGHT. 4
- ACTION
APPROVED BY GSU MANAGEMENT. 2 ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / i CRITICALITY RATING: 1 IMPLEMCHTATION SCHEDULE: PRIOR TO FUEL LOAD 1 1
- O t
l I
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 HED NO.= 22 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECHLIST NO.: DD.10 CHECMLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: PHYSICAL DISTINCTION BETWEEN PUMPS AND VALVES IS NOT USED. INSERT 4C-SAME SWITCH TYPE IS USED FOR VALVES AND BREAKERS. C33-COO 1A RWCU PUMP A&B. USE SAME SWITCH FOR BREAKERS AND PUMPS. RECOMMENDATIONS: COLOR CODING ON BENCHBOARD FOR PUMPS AND FANS TO DISTINGUISH FROM VALVES & DAMPERS ACTION: AFPROVED BY GSU MANAGEMCNT ELDCR# ISSUE DATE / / FDDR# ISSUC UATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TC EXCEEDIND 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL_ AN'T
/,'T DATE: 02/22/84 HED NO- :: 287 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DAlA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B6.1 CHECl: LIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-19
_-= - - - - - - - - - - - - - _=-----------
--------------== ==---=_
DESCRIPTION OF DISCREPANCY: RESET BUTTONS ARE NOT ACCURATELY MARKED RECOMMENDATIONS: RELABEL TO INDICATE PROPER FUNCTION. ACTION: APPROVED BY GSU MANAGEMENT. E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / _ - - _ - = __ _=-------.------ - - _ ._ _ CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIGR TO EXCEEDIN3 5*/. POWER 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR Pt_ ANT DATE: 02/27/84 F4 EE E) bJ C3 - = 97 7 REVIEWER: BARI:S/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECULIST NO.: B7.5 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-71 ( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO. P863-73 ( 1.) DESCRIPTION OF DISCREPANCY: PROCEDURES ARE NOT WRITTEN YET FOR KEY-LOCK SWITCHES RECOMMENDATIONS: OPCRATION OF THESE SWITCHES WILL BE INCLUDED IN THE SYSTEM OPERATING PROCEDURES (SOPS) ACTION: APPROVED BY GSU MANAGEMENT. EI<DCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NU C L_E AR PL ANT - ( ) 452
DATE: 02/23/04 HED NO. ::
REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
=--_----__ --
DATA SOURCE: UWR OWNERS GROUP CHECKLIST I40.: C6.3 CHECKLIST AREA: At4NUNCI ATORS PANEL / WORKSTATION NO. GENERIC ( 1.)
= - - - - - - - - - - - - - - - _ - _ . - - --
DESCRIPT10t1 OF DISCREPANCY: EACH WINDOW DOES NOT REFLASH FOR SECOND ALARM INPUT. RECOMMENDATIONS: ANNUNCIATOH REFLASH EVALUAT10t4 WAS COMPLETED AS FOLLOWS: OPERATIONS DEVELOPED (~} A LIST OF Atat4UNCIATORS FOR REFLASH. THIS LIST WAS THEN REVIEWED BY THE PGCC
\_/ SUPERVISOR WHO ELIMINATED ANNUNCIATORS FOR WHICH: 1)THE OBVIOUS CONSEQUENCE WAS THE SAME FOR ANY ACTIONS (RX sci <AM TURDINE TRIP) 2)IF MULTIPLE ACTION COULD NOT EXIST AT SAME TIMC 3) ALARM HAD ONLY ONE INPUT. THIS LIST WAS THEN REVIEWED BY THE SYSTEMC ENGINEER FOR SPECIFIC SYSTEMS RELIABILITY AND PLANT SAFETY. AS A RESULT, REFLASH WILL DE ADDED TO THE FOLLOWING ANNUNCIATORS: "RECIRC PUMP MTR A/B TEMP HIGH" , " INST AIR COMPRESSER TROUDLE", "DRYWELL AL CONTMT REAC DR SEAL FAIL".
ACT ION: APPROVED BY GSU MANAGEMENT 4 ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - - - - - - - - _ - _ - =
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O CATE: 02/22/64 Fi EE E) P4 C3 = 22 CP 1 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C8.2 CHECl: LIST AREA: ANNUNCIATORS PANEL /WORLSTATION NO. GENERIC DESCRIPTION OF DISCREPANCY: THERE IS NO ADMINISTRATIVE PROCEDURE TO ALLOW PROMPT RECOGNITION UF OUT OF SERVICE ANNUNCIATORS RECOMMENDATIONS: PROCEDURE HAS DEEN WRITTEN SINCE SURVEY. LAMP CHECK PERFORMED ONCE A SHIFT. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O l l
l i i HUMAN ENGINEERING DISCREPANCY RECORD I
. ,-( RIVER BEND NUCLEAR PLANT
( I DATE: OW90/4 HED NO :: ' 802 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
= - - _=_-__ - - - -- --------
DATA SOURCC: OPERATING PERSONNEL INTERVIEW CHECl: LIST NO. E CHECKLISl AREA: PROCEDURES PftNEL/ WOR):GTATION NO. GENERIC ( 1.)
- DESCRIPTION OF DISCREPANCY
IT IG DIFFICULT TO TELL WHICH EOP YOU SHOULD GO TO OR BE IN RECOMMENDATIONS: IN CONJUNCTION WITH THE DCRDR, RBS HAS DEVELOPED AND IS PERFORMING A EOP
- O U
VERIFICATION AND VALIDATION PROGRAM. THIS PROGRAM WILL PROVIDE A HIGH LEVEL ASSURANCE THAT THE PROCEDURES ARE USABLE AND WILL WORK. ACTION: l APPROVED BY GSU MANAGEMENT. Et<DCRit ISSUE DATE / / FDDRH ISSUE DATE / /
----------- __- - - - - - - - - - - = = - - - _ ___. --------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD I O
--- v y . ,3- - , -- . ._
.__,.,.-.-----,--.---.-----e - ~ - , - - , , , - - - - -- ., ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/2WU4 HED NO. :: 3.55 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHA5E
----__--- -------__---- _--___--_-____----- = _-- _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.1~ CHECl'L I S T AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( I.) DESCRIPTIOt1 OF DISCREPANCY: PROCEDURES DO NOT GIVE NORMALLY EXPECTED RESULTS (SUCH AS VALVE POSITIONS, FLOW RATES, ETC.)WHERE APPROPRIATE RECOMMENDATIONL: CONTROL BAND. ROOM METERS / INDICATORS WILL BE MARKED TO INDICATE NORMAL OPERATI ACTION: APPROVED BY GEU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- CRITICALITY RATING
- 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 9
i 1
r' HUMAN ENGINEERING DISCREPANCY RECORD
- RIVER BEND NUCLEAR PLANT
'd DATE: 02/29/84 HED N O . :: 357 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE
.-------=== -- ----------
-----------=- _ _ .
DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO.: E4.17 CHCCKLIST AREA: PROCEDURES PANEL /WORKSTATIOf4 NO. GENERIC ( 1.) _ - - _ - - - . = - - - ----- ____----- DESCRIPTION OF DISCREPANCY: NOT ALL EOPs EMPHASIZE THE USE OF MULTIPLE OR INDEPENDENT INDICATIONS TO PROVIDE FEEDBACK THAT AN ACTION HAS OCCURRED IN RESPONSE TO A CONTROL COMMAND. RECOMMENDATIONS:
/~T NO ACTION - THE NEED TO REFERENCE INDEPENDENT INDICATIONS IS EMPHASIZED IN V TRAINING AND IN GENERAL CAUTIONS.
ACTION: APPROVED BY GSU MANAGEMENT. Et<DCRM ISSUE DATE / / FDDRM ISSUE DATE / /
------= =-- _- - - - - = . --===--- _- -
- -- = __ _=== -__--_
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
1 1 1 HUMAN ENGINEERING DISCREPANCY RECORD ! l RIVER BEND NUCLEAR PLANT l DATE: 02/29/84 HED NO = 359 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE __---------------------------------__-------------------------== ---------_- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.19 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: PROCEDURES MAY REQUIRE USE OF REFERENCE MATERIALS FOR SOME CRITICAL STEPS. RECOMMENDATIONS: SOP'S WILL NOT REQUIRE USE OF REFERENCE MATERIALS IN ANY STEPS. NO ACTION REQUIRED. ACTION: AFPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
_-___----_____--------------_-___-=- -- -
== - __-_____-_-________
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: I l
)
HUMAN ENGINEERING DISCREPANCY RECORD m RIVER BEND NUCLEAR PLANT i 3 DATE: 02/29/84 HED NO- 353 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE
- - - - - - ---------- =----
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.8 CHECKLIST AREA: PROCEDURES 1 PANEL / WORKSTATION NO. GENERIC ( 1.) _ _ - _--=== ------------ DESCRIPTION OF DISCREPANCY: EOPs DO NOT ALWAYS PROVIDE SYMPTOMATIC OR DIAGNOSTIC ANALYSIS OR ENTRY EVENT GUIDANCE TO ASSURE CORRECT PROCEDURE IS IN USE. (e.g. EOP-8 CAN'T BE ENTERED FROM EOP-1) {dh i RECOMMENDATIONS: NO CHANGE TO PROCEDURE. EPG'S HAVE YOU ENTER CONTINGENCY 4 (EOP-OOOB) FROM CONTIGENCY 2 (EOP-OOO6) ACTION: APPROVED BY GSU MANAGEMENT. Et<DCRM ISSUE DATE / / FDDRM ISSUE DATE / /
--- - - - _ = - - - - - - - - - - - - - - - - - - - - - _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: 4 !O l
-- _, , - - - - ~ , - - - . - - -- . , . . . . - - -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCtEAR PL ANT DATE: 02/29/84 HED N O . :: 3 d2 O REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE
-------------------------------_ __ -_ - - - = _ _
.=-=----------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E5.1 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: REFERENCE MATERIAL IDENTIFIED IN A PROCEDURE IS NOT ALWAYS READILY AVAILABLE. FOR EXAMPLE, SOME REFERENCES REQUIRE VENDORS MANUALS WHICH MAY NOT BE AVAILABLE. kECOMMENDATIONS: THESE REFERENCES ARE NOT REQUIRED FOR SYSTEM OPERATIONS. THEY ARE AVAILABLE, HOWEVER, IN DOCUMENT CONTROL. ACTION: APPROVED BY G5U MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 l l IMPLEMENTATION SCHEDULE: i i O
HUMAN ENGINEERING DISCREPANCY RECORD (] RIVER BEND NUCLEAR PLANT V DATE: 02/29/84- HED NO :: 361 REVIEWER: SCHROEDER TRACMING STATUS: SCHEDULE PHASE
---== == =--------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E5.3 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( 1.)
- - =-----------.---
. ---.....----------- ----------- = ---
DESCRIPTION OF DISCREPANCY: INTERFACES BETWEEN SYSTEM OPERATING PROCEDURES MAY NOT BE COMPATIBLE. 1 RECOMMENDATIONS: REVIEW WILL DE PERFORMED TO ENSURE COMPATABILITY. ACTION: APPROVED BY GSU MANAGEMENT. l ELDCRM ISSUE DATE / / I FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
- O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PI_.A N T DATE: 02/C9/84 FiEEE) P4 E3 _ = C5 db :2 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECLLIST NO.: E6.1 CHCCVLIST AREA: FROCEDURES PANEL / WORKSTATION NO. GENERIC ( I.) DESCRIPTION OF DISCREPANCY: THERE IS NO CONTROLLED METHOD FOR REVISION TO PROCEDURES THAT ASSURES OPERATOR REVIEW AND WALKTHRU TO VERIFY CORRECTNESS, UNDERSTANDING, AND ABILITY TO USE. RECOMMENDATIONS: SECTION PROCEDURE TO BE WRITTEN TO INCLUDE SHIFT PERSONNEL IN THE REVIEW OF PROCEDURE REVISION 3. THE EOP VSV PROGRAM WILL ADDRESS CHANGES TO EOP'S. ACTION: AFFROVED BY G5U MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 0 l l t t
HUMAN ENGINEERING DISCREPANCY RECORD f'S, RIVER BEND NUCLEAR PLANT t
} DATE: 02/29/84 HED NO 363 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E6.3 CHECKLIST AREA: PROCEDURES i
PANEL / WORKSTATION NO. GENERIC ( 1.) _ _____---__-----_____--_____ ------__-- ---_- ----__--__- __ - - = - - - - - - = i DESCRIPTIOt1 OF DISCREPANCY: I THERE IS NO CONTROLLED METHOD FOR PROVIDING FEEDBACK TO THE OPERATOR AS TO THE RESOLUTION OF RECOMMENDED CHANGES TO PROCEDURES. i RECOMMENDATIONS: OPERATIONS SECTION PROCEDURE WILL BE WRITTEN TO INCLUDE THIS. ACTION: APPROVED BY GSU MANAGEMENT. 1 ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 4 1 i i I O ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL. EAR P L_ A N T O DATE: 02/27/84 HED NO. :: 540 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECLLIST NO.: SA1.3 CHECLLIST AREA: PANEL LAYOUT AND DESIGN F'ANEL/ WORKSTATION NO. P680-01 ( 1.) PANEL / WORKSTATION NO. P680-02 ( I.) PANEL /WORI: STATION NO. P680-03 ( 1.) DESCRIPTION OF DISCREPANCY: THE ASSOCIATION OF FEEDDACK INDICATION TO RELATED CONTROLS IE NOT MADE READILY APPARENT THROUGH LABELING, MIMICS, DEMARCATION LINES OR POSITION. RECOMMENDATIONS: ADD MIMIC, LADELING, DEMARCATIONS AS REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT (-]
, V F4 EEI) P4 C3 . s d4 9P E3 DATE: OC/23/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE
-- - = ---------- --
- - - - = _ - - = - - - = - .
------------------- ----------------=
DATA SOURCE BWR OWNERS GROUP CHECULIST NO. SA3 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-01C ( 1.)
- =------ ; DESCRIPTION OF DISCREPANCY:
THE ASSOCIATION OF FEEDBACK IDENTIFICATION TO RELATED CONTROLS IS NOT READILY APPARENT THROUGH LABELING, MIMICS, DEMARCATION LINES OR POSITION. RECOMMENDATIONS (qj ADD DEMARCATION AND ENHANCEMENTS AS REQUIRED TO MAKE ASSOCIATION READILY APPARENT 1 ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 s IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 4 I I r
. _ __ , _ _ , . _ . . , _ .-. , . _ _ -. _ ___-._.___,.-__,_7 , . , . _ , _ . _ .
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 HED NO :: 454 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SA3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKGTATION NO. P600-06C ( 1.) DESCRIPTION OF DISCREPANCY: THE ASSOCIATION OF FEEDBACK INDICATION TO RELATED CONTROLS IS NOT READILY APPARENT THROUGH LADELING, MIMICS, DEMARCATION LINES OR POSITION.(IRM BYPASS) RECOMMENDATIONS: IMPLEMENT COLOR CODING OF SWITCHES AND RECORDERS ACTION: APPROVED BY GSU MANACF_ MENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O V DATE: 02/23/84 HED NO.: 41O REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - _ _ -- __ _ _ _ _ _ _ = - _ _
_ - - _ _ _ - - _ _ - - _ _ _ _ _ __ =_ _- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SA3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-2 PANEL / WORKSTATION NO. P680-3
-------------==- __---------- _ ---------------------------------
DESCRIPTION OF DISCREPANCY: THE ASSOCIATION OF FEEDBACK INDICATION TO RELATED CONTROLS IS NOT MAD 2 READILY APPARENT THROUGH LADELING, MIMICS, DEMARCATION LINES, OR POSITION ON CONTROL / DISPLAY GROUPING. RECOMMENDATIONS: O ADD MIMICS, LINES OF DEMARCATION ACTION: APPROVED BY GSU MANAGEMENT. . ELDCRM ISSUE DATE / / i FDDR# ISSUE DATE / /
- - - - - - - - - - - - - - - = - - - - _ _ _ - - - - - - - - - - - _ = = _ -------------------- _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER CE) 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/C3/84 FiEEE) P4 C3 . = 5541 1 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SBl.1 CHCCELIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-08 ( 1.) PANEL / WORKSTATION NO. P680-07 ( 1.) PANEL / WORKSTATION NO. P6SO-10 ( 1.) DESCRIPTION OF DISCREPANCY: INDICATOR SCALES ARE NOT EASILY READ WHEN STATIONED AT THE PANEL (INSERT 7D METERS TOO SMALL). UPGRADED DUE TO SYSTEM RELIABILITY INCREASE. RECOMMENDATIONS: CHANGE TO LARGER METERS. ACTION: NO ACTION. THESE METERS ARE FOR TURBINE BYPASS. OPERATORS ARE TRAINED USING THESE METERS ON PLANT-SPECIFIC SIMULATOR. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIBCREPANCY RECORD
,e g RIVER BEND NUCLEAR PLANT C DATE: 02/23/84 F4 EE E) bJ C3 . a et 1 :2 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
____=-z = _ - - -_=__________- - _ = - - - == __________________= DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. SB1.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-1 PANEL / WORKSTATION NO. P680-2 PANEL / WORKSTATION NO. P680-3 PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6
=- _ = - - - = = = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ = - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
DESCRIPTION OF DISCREPANCY: INDICATOR SCALES STATIONED AT THE PANEL ARE NOT EASILY READ.(SMALL METERS FOR O FEEDWATER FLOW / RECORDER SCALES (RED / BLUE) TOO SMALL) RECOMMENDATIONS CHANGE 9 METERS (4) MAIN STEAM HEADER FLOW, (3) FEEDWATER FLOW, REACTOR LEVEL AND REACTOR PRESSURE TO LARGER METERS. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / j CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
c HUMAN ENGINEERING DISCREPANCY RECORD RIVER DEND NUCLEAR PLANT DATC: 02/22/04 1-lE D N O :: 2 c/ 2 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE DATA EDURCE: DWI? OWi4ERS GRUUP CHED LIET NO.: SBl.3 LHEClLILT AFLA: INLIRUMENTATION AND HARDWARE PANEL /WORISTATIOf1 NO. P601-18 fHNLL/Wohl:L1AT10N NO. P601-19 PANEL / WOW.STATIOfl NO. P601-22 DCSCRIPTIOf1 Or DISCREPANCY CRV GrEN IS ONLY A DEMAND SIGNAL DUT IS NOT LABELED AS SUCH RECOMMCf1DAT I ONS: DESIGN CHANGE IN f-ROGRESC TO GIVE DIRECT SRV INDICATION. NO FURTHER ACTION REQUIRED. ACTION: AF PROVED DY OSU MANAGEMENT. E t> DEh # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATIt1G 1 IMFLEMENTATION SCHEDULE: O
l 1 1 HUMAN ENGINEERING DIBCREPANCY RECORD f -- RIVER BEND NUCLEAR PLANT DATE: 02 /"l3/ 04 HED NO.a 503 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECt: LIST NO. : SBl.4 CHECFLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORVSTATION NO. P6BO-1 DESCRIPTION OF DISCREPANCY PROCESS UNITS AND MULTIPLIERS ARE NOT SPECIFIED. (NOT ON RECORDER) RECOMMENDATIONS: CHANGE LADELS FOR RECORDERS ON F600 TO INDICATE UNITS ACTION: APPROVED DY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / /
\
CRITICALITY RATING: 1 i IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER ) i I 1 1 I
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/03/84 HED N O . :: 457 REVIEWER: DURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: 581.4 CHECLLIST AhEA: INSTRUMENTATION AND HAF.DWARE PANEL / WOR) STATION NO. P6DO-4 PANEL / WORKSTATION NO. P690-5 PANEL /WORUSTATIOf1 NO. P600-6 DESCRIFTION OF DISCREPANCY: FROCESS UNITS AND MULTIPLIERS ARE NOT SPECIFIED. (SRM LOG COUNT RATE RECORDERS , RECIRC LOOP A/D FLOW RECORDER, AND TOTAL FLOW / DELTA PRESSURE RECORDER HAVE NO lif4ITS) . UFORADED DUE TO IMPORTANCE OF INDICATION. RECOMMENDAT IOtJS: CHANCE LAEELS TO INDICATE UNITS. AC T IOf J: APFh0VED BY GEU MANACEMENT. EtDCRW ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: I IMFLEMENTATION SCHEDULE: FRIOR TO EXCEEDING 5*/. POWER O
l
- HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT HED NO. 504 DATE: 02/23/84 REVIEWER: BUROY/ CHASE TRACKING STATUS: SCHEDULE PHASE l
DATA SOURCE: BWR OWNERS GROUP l CHECVLIST NO. SB2.1 CHECULIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P6SO-1 l DESCRIPTION OF DISCREPANCY: ALL RECORDER INFORMATION IS NOT VISIBLE THROUGH RECORDER WINDOWS SO THAT OPEN-DOOR OPERATION IS REQUIRED. RECOMMENDATIONS: NO ACTION - CLEAR PLASTIC COVER IS NOT DIFFICULT TO SEE THROUGH AND, IF REQUIRED, THE DOORS ARE EASY TO OPEN. O ACTION: APPROVED DY G5U MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 1 l i IMPLEMENTATION SCHEDULE: ! l l lO l i 1 I l ! l _. _ . _ . - _ _ - - _ . _ . - _ . . _ - . . _ . . _ . ~ _ - . ~ _ _.,.. _ _ _ _ _ _ _ _ - . _ ._, -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L_ E A R Pt ANT DATE: 02/03/84 HED NO. 545 REVIEWER: SPDS TRACHING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHECULIST NO.: SPDS CHEClLIST AREA: CHECELIST AREA NOT FOUND PANEL /WORKSTATIOf4 NO. SPDS DESCRIPTION OF DISCREPANCY: REACTOR VESSEL WATER LEVEL IS NOT CATEGORY 1 INSTRUMENTATION OVER THE FUEL ZONE RANGE. REFERENCE LEG INSTRUMENT LINES INSIDE THE DRYWELL ARE SUDJECT TO FLASHING AND DOILING. RECOMMENDATIONS: CONDUCT ENGINEER!?JG REVIEW TO DETERMINE ADEOUATE DESIGN DASIS ACTION: DESIGN REVISIONS LISTED ON P.26 !< 27 OF REFERENCE "K" IN
SUMMARY
REPORT WILL DE IMPLEMENTED. E t< DCR M ISSUE De s E / / FDDR# ISSUE DATE / / CRIT 1",ALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGZNEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT s ! V DATE: 02/23/84 HED NO. a 546 REVIEWER: SPDS TRACHING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHCCKLIST NO. SPDS CHECMLIST AREA: CHECI: LIST AREA NOT FOUND i PANEL / WORKSTATION NO. SPDS i DESCRIPTION OF DISCREPANCY: SUPPRESSION POOL TEMPERATURE METER DOES NOT PROVIDE A CATEGORY 1 DISPLAY OF THE BULK AVERAGE POOL TEMPERATURE ON EITHER 1H13*P808 OR 1H13*P601 RECOMMENDATIONS: THE FRESENT DESIGN OF THE NORMAL SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM SATISFIES THE RECOMMENDATIONS OF GE DOCUMENT NO. 22A4379, REVISION 1, (A) SUPPRESSION POOL TEMFERATURE MONITORING SYSTEM. AVERAGE POOL TEMPERATURE CAN BE ODTAINED BY MANUALLY AVERAGING THE OUTPUTS FROM THE TEMPERATURE SENSORS THAT ARE DISTRIDUTED EVENLY AROUND THE POOL. OPERATOR ACTIONS, DUE TO HIGH POOL TEMPERATURE DESCRIBED IN TECHNICAL SPECIFICATION NO.3/4.6.3.1,WILL BE BASED UPON THE HIGHEST READING TEMPERATURE SENSOR WHICH WILL ACTIVATE AN ALARM ON 1H13*P808. THE OPERATOR THEN WOULD HAVE SUFFICIENT TIME (LESS THAN 24 HOURS) TO TAME CORRECTIVE ACTION. THEREFORE, A BULE SUPPRESSION POOL TEMPERATURE AVERAGING SYSTEM IS NOT 2 REOUIRED. ACTION: APPROVED DY GSU MANAGEMENT. 4 ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 1 1 1MPLEMENTAT10N GCHEDULE 1 O/
, , _ _ - . , - _ . . . - _ _ - . . _ - . , - _ . _ _ _ _ , , _ , - , _ , _ . . _ . .. - - - _ _ - - - , , . _ , , - _ _ - _ , _ _ _ _ . . _ , _ - _ ~ - . - - . _ . _ .
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct._ E A R P L. A N T DATE: 02/C3/84 HED NO :: 547 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHECtLIST NO.: SPDS CHECELIST AREA: CHECFLIST AREA NOT FOUND PANCL/WORtSTATION NO. SPDS DESCRIPTION OF DISCREPANCY: SLCS TANE LEVEL DOES NOT MEET THE EQUIPMENT QUALIFICATION GUIDELINES SET FORTH DY R. G. I.97, REVISION 3. RECOMMENDATIONS: THE SLCS IS NOT REOUIRED TO PROVIDE A SAFETY FUNCTION DURING ANY POSTULATED PIPE DREAt? EVENTS. THE SLCS TANK LEVEL INSTRUMENTATION IS CONTAINED IN ENVIRONMENTAL ZONE CT-4, WHICH HAS A MILD ENVIRONMENT DURING NONACCIDENT CONDITIONS. WHILE THIS SYSTCM IS SAFETY-RELATED,IT IS CONSIDERED LESS IMPORTANT TO SAFETY THAN THE REACTOR PROTECTION SYSTEM. THEREFORE, THE REGULATORY GUIDE CATEGORY C REDUIRE. IS NOT CONSIDERED APPROPRIATE, AND CATEGORY 3 INSTRUMENTATION IS USED. NO FURTHER ACTION REOUIRED. ACTION: AFfROVED DY GSU MANAGEMENT. ELDCRN ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: I IMFLEMENTATION GCHEDULE: O t
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUC L_E AR PL. ANT m DATE: 02/23/84 HED NO : 551 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE , , DATA SOURCE: OTHER CHECl: LIST NO. : SPDS CHECt: LIST AREA: CHECKLIST AREA NOT FOUND PANEL /WORI. STATION NO. SPDS DESCRIPTION OF DISCREPANCY DRYWELL DRAIN SUMP WATER LEVEL IS NOT CATEGORY 1 PER RG 1.97. RECOMMENDATIONS: NO ACTION. TECHNICAL JUSTIFICATION ON P.35 & 36 OF REFERENCE "K" IN
SUMMARY
REPORT. O ACTION: APr' ROVED DY GSU MANAGEMENT. 1 ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / l
----_------------------------------------------------_------------------------- t CRITICALITY RATINO: 1 IMPLEMENTATION SCHEDULE:
s 4 1 O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO.= 554 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHECKLIST NO.: SPDC CHECl: LIST AREA: CHECFLIST AREA NOT FOUND PAfJEL/WORKSTATIOt1 NO. SPDS DESCRIPTION OF DISCREPANCY: 1HE DESIGN OF RBS DOES NOT PROVIDE FOR MAIN CONTROL ROOM INSTRUMENTATION WHICH COVERS THE RANGE REQUIRED FOR THE CONTAINMENT WATER LEVEL. RECOMMENDATIONS: INVESTIGATE THE EXPANSIOtJ OF RANGE ON CONTAINMENT WATER LEVEL INDICATIONS IN CONTROL ROOM ACTIOfJ: NO ACTION. TECHNICAL JUSTIFICATION ON P. 40 OF REFERENCE "K" IN
SUMMARY
REPORT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ - - - = _
CRITICALITY RATING 1 l IMPLEMENTATION SCHEDULE: O
l l HUMAN ENGINEERING DISCREPANCY RECORD es RIVER BEND NUCLEAR PLANT DATE: 02/23/84 HED NO_z 555 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
---_________ --=-- -_________
DA1A SOURCE: OTHER CHECKLIST NO.: SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION NO. SPDS
= = _ _ _ _ _ _ _ - - =_- ______
_________________________-===- DESCRIPTION OF DISCREPANCY: DIRECT READOUT OF PRIMARY CONTAINMENT ANNULUS DIFFERENTIAL PRESSURE IS NOT AVAILABLE IN THE MAIN CONTROL ROOM OR THE SPDS DATABASE. RECOMMENDATIONS: THIS VARIABLE IS AVAILABLE IN THE SPDS DATA BASE (HVRPY222,HVRPY223). WITH () THIS INFORMATION, THE OPERATORS CAN CONTROL THE RATE OF DEPRESSURIZATION OF THE CONTAINMENT INTO THE ANNULUS OF THE CONTAINMENT. THEREFORE, NO DESIGN CHANGE IS NECESSARY. ACTION: APPROVED BY GSU MANAGCMENT. Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / / _________--_______________- __=____________________ -- CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: O 1 1
-, - . _ ~ __ _ _
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 HED NO- = 560 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHECELIST NO.: SPDS CHCCKLIST AREA: CHECLLIST AREA NOT FOUND l l l PANEL / WORKSTATION NO. SPDS 1 l
-------------------------------- ===_-- __ - _ _ - _- ____------------------
DESCRIPTION OF DISCREPANCY: RBS DOES NOT DISPLAY METEOROLOGICAL DATA IN THE MAIN CONTROL ROOM OR FURNISH SAME TO THE SPDS DATABASE. RECOMMENDATIONS: INVESTIGATE THE ADDITION OF MET DATA IN CONTROL ROOM. ACTION: METEOROLOGICAL DATA WILL BE MADE AVAILABLE IN THE MAIN CONTROL ROOM. ELDCR4 ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD t
GULF SmTES ITrILITIES COMPANY RMR BM SMIM O l l 7.2 PRIORITY II BEDS O O 7-3
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L.E A R PL ANT DATE: 02/28/84 F4 0E I) bJ C3 . - 1 cP 5 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: COf1 TROL ROOM SURVEY - NUREG 0700 CHECKLIST NO.: GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUD-CATEGORY: ILLUMINATION PANEL /WORESTATION NO. DESK DESCRIPTION OF DISCREPANCY: ILLUMINATION IS BELOW THE RECOMMENDED 50 FOOTCANDLES REC'JMMEND AT IONS : INVESTIGATE METHODC OF INCREASING ILLUMINATION ACTION: STONE L WEBSTER IS EVALUATING CONTROL ROOM ILLUMINATION AS A RESULT OF DCRDR, FINAL LIGHT READINGS WILL BE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED L FLOORING IS INSTALLED. EODCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD
/~^ RIVER BEND NU C L_ E AR P L_ AN T HED NO- G36 DAIE: 07/25/04 REVIEWER: HOWELL/ BISHOP TRACXING STATUS: SCHEDULE PHASE
--=- -- -------
-----------..---- _=_ ---------__ ._.
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: PANEL / WORKSTATION NO. P601 ( 1.) INDD. ISO.RST INBOARD ISOLATION RESET ( 2.) OUTBD. ISO.RST OUTBOARD ISOLATION RESET _ = _ - -_------- =-_ ------------------------- DESCRIPTION Or DISCREPANCY (SCENERIO D/ SEQUENCE 560) THE TASK / SUBTASK SAYS " POSITION TO RESET INBOARD AND OUTBOARD ISOLATION SEAL IN RESETS". HOWEVER, THERE IS NO DIRECT INDICATION OF RESET EXCEPT FOR VALVES REPOSITIONING.
- RECOMMENDATIONS:
WHEN ISOLATION SIGNAL CLEARS, THE OPERATOR MUST TAKE DELIBERATE ACTION TO RESET THE ISOLATION VALVES. NO ISOLATION VALVE MOVEMENT WILL OCCUR FROM THIS ACTION. A SECOND ACTION IS REQUIRED TO OPEN A PARTICULAR ISOLATION VALVE ((- AFTER RESET. THE RESET IS VERIFIED WHEN THE OPERATOR MANUALLY REPOSITIONS AN ISOLATION VALVE. ADDITIONAL INDICATION IS NOT REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / .
- = - - . - - - - - - - - - _ -
----------------------=__
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCL_ EAR P L_ A N T DATE: 04/02/84 HED NO= ~5 0 9 REVIEWER: CHASE TRACKING STATUS: SCHEDULE PHASE
-------------------------------------------------- ==.
DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: PANEL / WORKSTATION NO. P601-20B
- - - - - - - - - - - . , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - _=- - . - - - - - - - - - - - - - - - - -
DESCRIPTION OF DISCREPANCY: INSERT 20B IS MISSING SERVICE WATER OUTLET TEMPERATURE DISPLAY RECOMMENDATIONS: SERVICE WATER DISPLAY IS LOCATED ON ADJACENT INSERT (RECORDER E12-R601). THIS LOCATION IS ADEOUATE. NO ACTION. ACTION: APFROVED BY GSU MANAGEMENT. E!< DCRtt ISSUE DATE / / CDLRd ISSUE DATE / / i CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
I HUMAN ENGINEERING DISCREPANCY RECORD l A RIVER BEND NUCLEAR PLANT U DATE: 02/23/04 HED NO.: 564 REVI EWL R: ItuRGY/ CHASE TRACKING STATUS: SCHEDULE PHASE _ - - = - - - - - - - - - - - - - DATA SOURCE: DWR OWNEHC GROUP CHECl; LIST NO.: PANEL /WORl: STATION NO. P6BO-O ( 1.)
=-----_____
. DESCRIPTION OF DISCREPANCY:
. NEED NARROW RANGE REAClOR WATER LEVEL METER.
RECOMMENDATIONS: NARROW RANGE METERS FOR REACTOR WATER LEVEL ARE AVAILABLE ON P-680. NO FURTHER ACTION REQUIRED. ACTION:
. APPROVED BY GSU MANAGMENT.
EtDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- - - - - - _ = - - - - _ _
- _ - - - . . - - - - . .=-= _ _ _ _ - __ _ _ _ _ _ _ _
CRITICALITY R4 TING: 2 IMPLEMENTATION SCHEDULE: i O l l I
- l. _
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO. s 82 REVIEWER: BAPKS/ CHASE /SHANVLE TRACKING STATUS: SCHEDULE PHASE
------------ ----- _-------__--_-__--------____==_ _ - = = = - - - - - - - - - - .---------
DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: 5.6 CHEClLIST AREA: CHEtt. LIST AREA NOT FOUND PANEL /WORESTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: G.S.U. ENGRAVED LAPELS ARE HARD TO READ RECOMMENDATIONS: CHANGE ILLEGIBLE GSU LABELS TO USE A MORE DISTINCTIVE LABEL ACTION: ADPROVED D( GEU MANAGEMENT. E t<DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER O l
HUMAN ENGINEERING DISCREPANCY RECORD g RIVER BEND NUCLEAR PLANT DATE: 09/90/4 HED N O . :: 81O REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
---- .--------------------- - - - - - -. = - - - - - - - - - - - - - - - - - _ - _ _ - - - - - - - - - - - - - - - - - - -
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CilECI:LICT NO.: A CHECl'.L i s t AREA: PANEL LAYOU1 AND DESIGN
- i PANEL / WORKSTATION NO. P601
( 1.)
- - - - - - - - - - - - - - - - - .=------------- . -_=_ _-
DCSCRIPTION OF DISCREPANCY: SEVERAL OPERATORS SUGGEST THAT THE "B" SOLENOID SWITCHES FOR SRV'S NEED TO DE
- , ON A FRONT PANEL.
RECOMMENDATIONS: 3 SINCE SURVEY, INDICATOR LIGHTS FOR D SOLENOID SWITCH POSITIONS ARE BEING 4 ADDED ON P-601. NO FURTHER ACTION REQUIRED.
- ACTION
AFPROVED D( GSU MANAGEMENT. E t<DCR4 ISSUE DATE / / FDDRM ISSUE DATE / /
-----------------------------= -- ___--- . . _ _ _ _ - - - - .--__--__-
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Cl-.E A R P L A N 'T DATE: <C/C4/04
. HED NO. = 2 5G REVIEWER: L I DDLE /t1A TCDfl / B I Si !OP TRACKING STATUS: SCHEDULE PHASE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = - - - - -------
DATA SOURLL: l'U R OWNL RS bkOUF-CHCClLIST tJO.: Al.1 CHECLLIST AREA: F%NLL LAYOU1 AND DESIGN F ANEL/ WOR): STATION tiO. P808-BIB PANEL / WORKSTATION NO. P8vD-ECD PANEL /WORI'.S T AT ION t10. POO8-84D DESCRIPTION OF DISCREPANCY: STATUS MAThlCES HAVE HANDWRITTEN LEGENDS AND ARE HARD TO READ. MAKE PERMINENT LABEL. RECOMMCtJDA T 10tJb : CHANGL 514TUS MAIRIEES LEbCNDS TO ALLOW EASE OF READING ACTION: APFROVED DY Gell MAf J ACEMLtJ T . ELDCun ISSUE DATE / / FCDRn ISSUE DATE / /
---_----__--- __-----------------------------------------------------------~---
CRITICALITY RATING: 2 IMPLEl1ENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER O
1 F4UMAN ENGINEERING DISCREPANCY RECORD
)
RIVER BEND NUCLEAR PLANT i
\_/ F4 EE E) b4 C3 . -
2225 7 i DATE: 02/24/04 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE i -_______________________________________ DATA SOURCE: DWR OWNERS GROUP CHECILIST NO.: A1.1 CHLCI,LIGT AREA: PANEL LAYOUT AND DESIGN PAtJCL/WORESTATICt1 NO. P800-83 PAtJCL/WORI'ST ATION NO. P800-84 DESCRIPTION OF DISCREPANCY i
. SEOt 4CE PROGRAMMER MANUAL CONTROLS ON 83 HAS 2 WHITE LIGHTS THE SAME CONTROL ON 84 HAS A GREEN AND A RED LIGHT . RECOMMEtJDAT IONS:
CHANGE LIGHTS Ot4 CONTROL TO BE WHITE & BLUE ACTION: APPROVED BY GSU MAtJAGEMENT. E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMEtJT ATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l l l
. . _ . , , , - , , -n - - . - - - ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER DEND N U C L.E A R PL ANT DATC: 02/20/04 HED N O . :: 294.2 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A1.1 CHECFLIST AREA: FANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P877-31 PANEL /WORFSTATION NO. P877 ~.2 DCSCRIPTION OF DISCREPANCY: GENERATOR AMPS / WATTS /VARS ARE NOT FUNCTIONALLY GROUPED RECOMMENDATIONS: CHANGE AMPS MElERS(2) LOCATION TO BE ADJACENT TO VARS. ACTION: APPPOVED DY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT ( \ 311 D# DATE: OL'/C7/04 HED NO = REVIEWER: SEHROEDER/MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE DAT A SOURCE: DWR OWNERS GROUl* i CitECMLIST NO. : A1.3 CHLCI' LIST AREA: PANEL LAYOUT AND DESIGN 4 PhilEL/ WORKSTATION NO. PG63-76C DESCRIPTION OF DISCREPANCY: SIX SWITCHES HAVE BEEN REMOVED AND IF THEY ARE NOT REPLACED THEN THE SPACES
. SHOULD DE COVERED TO PREVENT DEBRIS FROM ENTERING.
RECOMMENDATIONS: SPAREG HAVE BEEN COVERED SINCE SURVEY. NO FURTHER ACTION REQUIRED s i
) '
ACTION: j APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE:
1 O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCtEAR PL ANT D AT E. : 02/27/84 HED NO- : 76.2 REVIEWER: DARKS /CHf*SE/SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWtJERS GROUP CHEClLIST NO.: A2.10 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 ( 1.) 1HVR*A02 264 ( 2.) 1HRV*AOD18B PANEL /WORKSTATIOt1 NO. P863-72 ( 1.) 1HRV*AOD18B PANEL /WORMSTATION NO. P863-73 ( 1.) 1HRV*AOD18B DESCRIPTION OF DISCRCPANCY: NO STARTING OR ENDING POINTS ARE IDENTIFIED RECOMMENDATIONS: ADD STARTING AND ENDING POINTS ACTION: APPROVED F4Y GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/84 HED NO. :: 113 REVIEWER: BARKS / CHASE /SHAN!'LE TRACKING STATUS: SCHEDULE PHASE
--_= _ ------------
DATA SOURCE: DWR OWNERS GROUP CHECVLIST NO.: A2.10 CHECl, LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-74C ( 1.) PANEL / WORKSTATION NO. ( 1.) PANEL / WORKSTATION NO. P863-75C ( 1.) DESCRIPTION OF DISCREPANCY: STARTING AND ENDING POINTS ARE NOT IDENTIFIED ON MIMIC RECOMMENDATIONS: IDENTIFY STARTING AND ENDING POINTS ACTION: APFROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- _ _ = = . _ - -
--------------------------------- _ _ = - - - - = _---
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i 1 O i I
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT t DATE: 02/23/04 HED NO- = 128 REVIEWER: DARUS/ CHASE /CHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECLLIST NO.: A2.2 CHEClLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORVSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION ARE NOT USED TO ENCLOSE RELATED DISPLAYS RECOMMENDATIONS: USE LINES OF DEMARCATION TO ENCLOSE RELATED DISPLAYS ACTION: APPROVED BY GSU MANAGEMENT. EtDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i l l O l
HUMAN ENGINEERING DISCREPANCY RECORD
/" RIVER BEND NUCLEAR PLANT Q] - 5205 cP DATE: 02/23/84 FiEEE)- P4 C3 .
, REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
-------------------------------== _ _-----------------== ----------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN f PANEL /WORKGTATION NO. P870-SIC PANEL / WORKSTATION NO. P870-52C DESCRIPTION OF DISCREPANCY:
. COLOR DEMARCATION NEEDED TO CONNECT SWITCHES IN SYSTEM RECOMMENDATIONS:
ADD DEMARCATIONS TO CONNECT SWITCHES IN SYSTEM 1
,t a ACTION:
APPROVED BY GSU MANAGEMENT. J EI,DCR# ISSUE DATE / / l FDDR# ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - = . - _ _ _ _ _ _ -- _ __ _
CRITICALITY RATING: 2 l- IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I i ! C:) - i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/84 HED NO. = 265 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: A2.2 CHECE. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WOR WTATION NO. P870-55 PANEL /WORVSTATION NO. P870-56 DESCRIPTION OF DISCREPANCY: CONTROLS ARE NOT ASSOCIATED WITH THEIR RESPECTIVE DISPLAYS RECOMMENDATIONS: FURTHER EVALUATION DETERMINED THAT THE ARRANGEMENT AND ASSOCIATION ARE APPROPRIATE. NO ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT ESDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U CE._ E A R P t_ AN'T ( .s)
# DATE: 02/27/84 HED NO. :: 72 REVIEWER: BARKS /CHASC/SHANKLE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - = - - - - - -- ------- - ------- --
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.3 CHECV. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PO63-71C ( 1.) PANEL / WORKSTATION NO. 72C ( 1.) PANEL / WORKSTATION NO. 73C ( 1.)
-------------------- --_ _ - - . - = - _ - -
DESCRIPTION OF DISCREPANCY:
." LINES OF DEMARCATION ARE NOT USED TO SEPARATE SYSTEMS OR SUBGROUPS RECOMMENDATIONS:
USE LINES OF DEMARCATION TO SEPARATE SYSTEMS
, ACTION:
APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 57. POWER (
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T-DATE: 02/28/84 HED N O . :: 109
, REVIEWER: DARVS/ CHASE /SHANRLE TRACIING STATUS: SCHEDULE PHASE DATA SOUPCE: BWR OWNERS GROUP CHECFLIST NO.: A2.0 CHEClLIGT AREA: PANEL LAYOUT At4D DESIGN PANEL /WORMSTATIOf4 NO. PG60-74C
( 1.) PANEL / WORKSTATION NO. P863-75C ( 1.)
---------------------------------------- - - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION ARE NOT USED TO PROVIDE SEPARATION RECOMMENDATIOtJS: USE LINES OF DEMARCATION TO SEPARATE SYSTEMS ACTION: APPRGVED BY GSU MANAGEMENT. E t< DCR # ISSUE DATE / / FDDRM ISSUE DATE / /
----___----_----_-_------- - -----------=__ _ _ _ _ - - - _ - - - - - - _ - _ - _ - - _ - - - - _ _ _ _ _ _ _ _
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT (~} v DATE: 02/28/04 FiEE E) P4 C3 . : 1 1 C) REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---------------------------------------------------- ==. - - - - - - -- -----
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.4 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P863-74C ( 1.) PANCL/ WORKSTATION NO. PO63-75C ( 1.)
------------------------------------------ _ - - _ _ _ _ _ ----= _ = = _ - - _ _ __=------
. DESCRIPTION OF DISCREPANCY:
MIMICS ARE NOT USED TO DISTINGUISH BETWEEN PRIMARY AND SECONDARY FLOWPATHS . RECOMMENDATIONS: USE DIFFERENT WIDTH MIMICS TO DISTINGUISH BETWEEN FLOWPATHS ACTION: APPROVED BY GSU MANAGEMENT. I E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ - - - - - = _ - - - - - - _ _=_- __- -----
j CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER J
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/04 HED N O :: 203 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
------------------ ---------------------------------=_ = - - - - - - - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.6 CHCCFLIST AREA: PANEL LAYOUT AND DESIGN FAr1EL/ WORKSTATION NO. P808-87D DESCRIPTIOr4 OF DISCREPANCY: RED MIMIC LINES FALLING OFF OR MISSING ON BATTERY SYSTEM: BROWN SECTIONS ARE LIFTIt4G RECOMMENDATIONS: REPLACE / PERMANENTLY ATTACH MIMIC LINES AS REQUIRED ACTIOrt: APPROVED BY GSU MANAGEMEtiT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY GATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD q RIVER BEND NUCLEAR PLANT U DATE: 02/27/84 HED NO a 313 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----------------- - ------- . . - - - - - - - - - - - - _ = - - - - - - = = = - - - - - - = - - - - ---------
DATA SOURCE: BUR OWNERS GROUP CHECKLIST NO.: A2.6 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P860-76C
. -_-__--- --------- -- - - - - - - - - - - - - - - - _ - - - - - ---. -- -_-_- = --_
DESCRIPTION OF DISCREPANCY: THERE IS NO FLOW PATH DISPLAYED INTO OR OUT OF 1HVF* ADD 101. RECOMMENDATIONS: } DISPLAY A FLOW PATH ACTION: APPROVED DY GSU MANAGEMENT. I 1
, E&DCRW ISSUE DATE / /
4 FDDR# ISSUE DATE / / 4
--- -------------------------------= _
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 4 O
,- , -, .---,,..a--., . - , - - - - - ,-w
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/28/04 HED N O :: 129 REVIEWER: BARKS / CHASE /SHANI:LE TRACKING STATUS: SCHEDULE PHALE DATA SOURCE: BWR OWNERS GROUF 1 CHEC) LIST NO.: A2.7 l l CHECI. LIST AREA: PANEL LAYOUT AND DESIGN l 1 P(4NEL/ WORKSTATION NO. P628 ( 1.) PANEL / WORKSTATION NO. P631 ( 1.) DESCRIPTION OF DISCREPANCY: FLOW PATH OR LOGICAL ARRANGEMENT IS NOT USED ie. THE ORDER IS CONFUSING RECOMMENDATIONS: RELABEL TO INDICATE IN WHICH STEAMLINE THE VALVE IS LOCATED. ACTION: APFROVED BY GSU MANAGEMENT. E t<DCR# ISSUE DATE / / FDDRh ISSUE DATE / /
--------------------------------------- _ - - - = = - - - - - - = - = - - - - - _ _ - - - - - - - - - - - - - - - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT F4 EEI) b4 C3 a 7' C5 DATE: 02/27/04 REVIE WER: DARKS /CHASC/SHANKLE TRACKING STATUS: SCHEDULE PHASE
--- _-- - _- -=_=_--
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PO63-71
! ( 1.)
i PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL /WORMSTATION NO. P863-73 ( 1.)
-=_ =- --
-----------------------------------_=------ _ -__ _
(- DESCRIPTION OF DISCREPANCY: 4 ( VALVES AND FANS ARE NOT ARRANGED IN AN ORDERLY AND EASILY RECOGNIZED MANNER RECOMMENDATIONS: ADD COLOR CODING WILL DC ADDED FOR SWITCHES TO DISTINGUISH PUMPS AND VALVES. FLOW DIRECTION ARROWS FOR MIMIC. i ACTION: ! APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
= --- _-- --_ -------
-------------------------------------- -__=- __
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
r I HUMAN ENGINEERING DISCREPANCY RECORD RIVER BENO NUCLEAR P L A N'T DATE: 02/28/84 Fi EE I) bJ C3 - = 111 REVIEWER: BARES / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECFLIST NO.: A2.7 CHECl. LIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORESTATION NO. P863-74C ( 1.) PANEL /WORKST ATIOtJ NO. P863-75C ( 1.) DESCRIPTION OF DISCREPANCY: PORTIONS Or THE MIMIC ARE MISSIr4G/ SPARSE USE OF ARROWS MAKE THE FLOW PATH h AMBIGUOUS RECOMMENDATIONS: REPAIR MIMICS TO MATCH CONTROL ROOM DESIGN CONVENTION ACTION: AFFROVED BY GSU MANAGEMENT. ELDCR4 ISSUE DATE / / FDDR# ISSUE DATE / /
.r -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1 0
HUMAN ENGINEERING DIBCREPANCY- RECORD RIVER BE ND NUCLEAR PLANT
. (~T G' HED NO.s 2cP 4 DATE: 02/20/84 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE
- - -- = ---------------
, ---- --- ----- --------- ---------=- - - - - - - - _ DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO. A2.8' CllECisLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. F877-32 . PANEL / WORKSTATION NO. P601-16 .;_ . .
. - _ = - = = - - _ _ - - - - - - ---------
.-------- ----------==_
DESCRIPTION OF DISCREPANCY:
. MIMIC LINE MISSING BETWEEN 1EJS*SWG 1 B 24 1EJS*ACB050//AND//1EJS*SWG 2B t<
1EJS*ACB066 RECOMMENDATIONS: INSERT MIMIC LINE BETWEEN SWITCHES l ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 i IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i 1 e O _ _ . .-. ~ _ _ _ -- - .- . _ _ . - .
j FtWMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATC 02/22/04 FIC D NO. = 2'79 REVIEWER: LIDDLE /MATSON/ BISHOP TRAC):ING STATUS: SCHEDULE FHASC DATA SOURCE: B'.JR OWNERS GROUP CHECFLIST NO.: AC.9 CHECI. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19 T. DESCRIPTION OF DISCREPANCY: SRV SWITCHES DO NOT SHOW ACTUAL PARALLEL FLOW RECOMMENDATIONS: FURTHER INVESTIGATION CONCLUDED THAT MIMIC IS A TOPVIEW ARRANGEMENT SUCH THAT PARALLEL FLOW PATHS WOULD NOT BC APPROPRIATE. NO ACTION. ACTION: APPROVED DY GSU MANAGEMENT. El. DERM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: C IMPLEMENTATION SCHEDULE: 1 9
HUMAN ENGINEERING D I S C :it E P A N C Y RECORD q . RIVER BEND NUC L_ E AR PL ANT U DATE: 02/27/04 HED NO 74 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _--- - ----------= . = - - - . _ _- _---- -_ ---------- DATA SOURCE: BWR OWNERS GROUP CHCCVLIST NO. A2.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN i - 1 PANEL / WORKSTATION NO. PO63-71 ( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO. P863-73 ( 1.) DESCRIPTION OF DISCREPANCY: THERE ARE TOO FEW ARROWS INDICATING THE MIMIC'S FLOW PATH RECOMMENDATIONS: ADD ARROWS TO INDICATE FLOW PATH i .i l , ACTION: j APPROVED BY GSU MANAGEMENT. 1 ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
-=. - - - - - - - - - - - - - - - - - - - - - - - - - = _ --
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 2
,3 - - , - - - -
w ..-2 - - - , , . , . - , , , , - -- -- w,rw-w-
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NU CL_E A R PL ANT DATE: 02/27/04 FiEEI) P4 C3 . - ~7 55 REVIEWER: BARES / CHASE /EHANELE TRACKING STATUS: SCHEDULE PHASE DATA LOURCE: BWR OWNERS CROUP CHECFLIST NO.: AC.9 CHEClLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 ( 1.) 1HVR*UC1D CNTMT UNIT CHILLER 1B PANEL /WORESTATION NO. P963-72 ( 1.) 1HVR*UC1B CNTNT UNIT CHILLER 1B PANEL / WORKSTATION NO. P863-73 ( 1.) 1HVR*UC1B CNTMT UNIT CHILLER 1B DESCRIPTIOtt OF DISCREPANCY: ARROWS SHOWING SERVICE WATER SHOULD BE CHILLED WATER RECOMMENDATIONS: NO ACTION. FURTHER EVALUATION DETERMINED THAT MIMIC WAS CORRECT. ACTION: APPROVED DY CSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-------------------------------=_ - - - - - ---
-=_--- ------------------
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: e
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT C' , HED NO. 112 DATE: 02/28/84 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DA1A 50URCC: DWR OWNERS GROUP CHECKLIST NO.: A2.9 CHECI'. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PO63-74 ( I.) PANEL / WORKSTATION NO. P863-75 ( I.) 1 , DESCRIPTION OF DISCREPANCY: ARROWS DO NOT COMPLETELY SHOW FLOW RECOMMENDATIONS:
~~
USC ARROWS TO SHOW FLOW ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1 1
)
i
\
__ , __ _ . ~ _ . - - , , . , - < v --,m---%- . . - -. . . . , .-- -r -
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCL EAR PL ANT DATE: 02/C7/04 HED NO. :: 2.15 REVIEWER: SCHROCDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHEClLIGT NO.: A2.9 CHECLLIST AREA: PANEL LAYOUT AND DESIGN FANEL/WORKGTATION NO. P863-7e DESCRIPTION OF DISCREPANCY: MIMICS ON THIS PANEL ARE NOT CLEARLY MARKED WITH ARROWS TO SHOW DIRECTION OF FLOW. RECOMMENDATIONS: CLEARLY MARL MIMICS WITH REGARD TO DIRECTION OF FLOW ACTION: APPROVED BY GSU MANAGEMENT. E t<DCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD ! RIVER BEND NUCLEAR PLANT 7 DATE: 02/27/84 HED NO x 104 REVIEWER: BARKS / CHASE /SHANFLE -TRACKING STATUS: SCHEDULE PHASE
-==--- - ________________
_____________________________________ - - = - - - - DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A3.1
- CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71
( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO. P863-73 ( 1.)
. ____. _______ . - _ _ _ _ _ _ _ _ _ _ _ _ = = _ = = = - __ . DESCRIPTION OF DISCREPANCY:
THE CONTROLS AND FEEDBACK INDICATION RELATIONSHIP IS NOT READILY APPARENT RECOMMENDATIONS: USE HIERARCHICAL LADELING OR DEMARCATION TO MAKE THE RELATIONSHIP APPARENT ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 FI E~ I) P4 C3 . = CP REVIEWCR: BARLS/DISHOP TRACKING STATUS: SCHEDULE PHASE
~~------------------_----_-__-------_-_-__-----------_-___-----_--_-----_-_-_--
DAlA SOURCE: E4WR OWNERS GROUP CHEClLIST NO.: A~.2 CHEClLIST ARLA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. 1RSS-PNL101 ( 1.) ISWP*P2C SERVICE WATER PUMP 2C ( 2.) 1SWP*P2A SERVICE WATER PUMP 2A DESCRIPTION OF DISCREPANCY: SERVICE WATER PUMPS ARE ORDERED FROM RIGHT TO LEFT RECOMMENDATIONS: REORDER SWITCHES LEFT TO RIGHT ACTION: APPROVED BY GSU MANAGEMENT ESDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCt. EAR P t_. A N T
^
DATE: 02/24/04 HED NO = 223 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
-------------------n - .--- - - - __---_. --- .---
DATA SOURCE: BWR OWNERS GROUP CHECI: LIST NO. : A3.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKSIATION NO. P808-83C ( 1.) _ _ _ - _ _ - - - - - _ - - - =- DESCRIPTION OF DISCREPANCY: i
.. CONTAINMENT SAMPLE, DRYWELL SAMPLE, H2 MOISTURE ANALYZER CONTROLS ARE NOT IN f
. ALPHADETICAL TOP TO BOTTOM ORDER RECOMMENDATIONS:
REARRANGEMENT OF SWITCHES WILL NOT IMPROVE OPERABILITY. SIMULATOR TRAINING
\ - WILL FAMILIARIZE OPERATORS WITH CONTROLS.
ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
-----------------------== = = - _ - - --_ = - - - - - - - _ . _ _ - __-_
- CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT I;AT L : O'.* / 29 / D4 HED NO. :: 124 REV I E WEl< s BARFG/CHASC/SHANPLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.2 CHECFLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORFSTATION NO. PB63-74 ( 1.) P ANEL / WORl'ST AT I ON NO. P863-75 ( I.) DESCRIPTION OF DISCREPANCY: COMPONENTS ORDERED LEFT/RIGHT RECOMMENDATIONS: DIVISIONAL SEPARATION CRITERIA DICTATES THE PRESENT COMPONENT ORDERING. NO ACTION. ACTION:
. APPROVED BY GSU MANAGEMENT.
Et,DCR M ISSUE DATE / / FDDRM ISSUE PATE / / _____-___________________= _ _ _ - - - - - ____________________-______ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HLIMAN ENGINEERING DXBCREPANCY RECORD RIVER BEND Nt 8CL_E AR PL. ANT (-) dales 02/27/04 HED NO a 317
\
REVIEWER: 'SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
--___-_-_-------__---_-----_----==-- -_=-_-----____ --- =__---__ ----_----
DATA SOURCE: BWR OWNERS GROUP CHECl'. LIST NO. : A3.2 CHECifLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76
--- =- ====-- _----
DESCRIPTION OF DISCREPANCY: CONT. CHILLED WATER CONT. A APPEARS ON THE RIGHT INSTEAD OF THE LEFT. THE
.. ORDERINO OF THE A AND D INDICATORS IS REVERSED FOR THE CHARCOAL BED OUT
. TEMPERATURE DISPLAY.
RECOMMENDATIONS:
' '$g CHANGE "TO RADWASTE' TO 'FROM RADWASTE* LABEL ON MIMIC. CHANGE 'HRHX' LABEL ' s_/ TO '1HVR-UC1B CONT. UNIT COOLER. REARRANGE SWITCHES L/R A/B.
ACTION: APPROVED DY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-----_-_-___-_-__---_-_______-____--_-___--- --._ _- = - = . _ _ - - - __ __
l CRITICALITY RATING: 2 IMPLEMFNTATION SCHEDULE: PRIOR TO EXCEEDING 5%' POWER D d
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/84 HED NO. :: 130 REVIEWER: B ARI .S / CHASC / SHANI'LE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECFLIST NO.: A3.3 CHEC) LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P628 ( 1.) PANEL /WORKSfATION NO. P631 ( 1.) DESCRIPTION OF DISCREPANCY: CONTROLS ARE NOT ARRANGED FUNCTIONALLY THEY ARE ALPHA ARRANGED RECOMMENDATIONS: FURTHER EVALUATION OF THE ARRANGEMENT DETERMINED THAT ARRANGEMENT IS APPROPRIATE. NO FURTHER ACTION REQUIRED. ACTION: APFROVED BY GSU MANAGEMENT. Et<DCR # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 s IMPLEMENTATION SCHEDULE: I O
HUMAN ENGINEERING DIBCREPANCY RECORD
, RIVER BEND NUCLEAR PLANT
-(
'"" DATE: 02/23/04 F4EEI) PJ C3 . z C5 db CP REVIEWER: DURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
______________________________________________________=_ = - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A3.3 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-2 PANEL / WORKSTATION NO. P680-3 PANEL / WORKSTATION NO. P600-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6 PANEL / WORKSTATION NO. P863-74C PANEL / WORKSTATION NO. P863-75C _________________________________________ -- ____ - =-_________ - ---_______
/
DESCRIPTION OF DISCREPANCY:
\]- CONTROLS AND DISPLAYS ARE NOT ARRANGED IN A FUNCTIONAL OR SEQUENTIAL RELATIONSHIP RECOMMENDATIONS:
INVESTIGATE REARRANGEMENT ACTION: SWAP LOCATIONS OF METERS 1CNM-PI133 & 1CNM-TI107. E&DCRM ISSUE DATE / / FDDRM ISSUE DATE / / _______________________________- - - - - - - - - = = _ _ _ _ _ _ _ _ _ _ _ _ - - - _______- =-=______ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l C:)
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02 / 2~/ / 04 HED NO. = 78 REVIEWER: DARKS / CHASE /SHANFLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUF CHECFLIST NO.: A3.3 CHECFLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORESTATION NO. P863-71 ( 1.) 1HVR*AGD67B EXHAUST DAMPER PANEL / WORKSTATION NO. P863-72 ( 1.) 1HVR*AGD67B EXHAUST DAMPER PANEL /WORFSTATION NO. PO63-73 ( 1.) 1HVR*AGD67B EXHAUST DAMPER _____--____--------__---_-__--_--__-__-______-__---___ =-__--__-________- DESCRIPTION OF DISCREPANCY: THE EXHAUST DAMPER IS BEFORE ITS ASSOCIATED FAN RECOMMENDATIONS: THIS HED IS DEING CORRECTED PER FDDR1399RO. NO FURTHER ACTION REQUIRED. ACTION: APPROVED DY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: i I I O L.
HUMAN ENGINEERING DIBCREPANCY RECORD
/7 RIVER BEND NUCLEAR PLANT V
DATE: 02/20/04 HED NO_z 295 REVIEWER: LIDDLE /MATSOf4/DISHOP TRACKING STATUS: FCHEDULE PHASE _____ __________ __________________------ ______________- =- =---____________ DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: A3.3 CHECVLIST AREA: PANEL LAYOUT AND DESIGN PAtJEL/ WORKSTATION NO. PO77-31 PANEL / WORKSTATION NO. PB77-32 DESCRIPTION OF DISCREPANCY: DIESEL ENGINE STOP BUTTONS ARE NOT FUNCTIONALY GROUPED 9 RECOMMENDATIONS: NO ACTION. THE (2) SWITCHES ARE PURPOSELY GROUPED THIS WAY TO ENSURE A CONSCIOUS ACT TO STOP DIESELS. ACTION: APFROVED DY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / ________________________________________________________ _ _ _ _ _ _ _ - - ---- =______ CRITICALITY RATING: 2 ) IMPLEMENTATION SCHEDULE: 'O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/04 HED NO- :: 27 REVIEWER: D ARl:S/CHASC / SHAN)'.LE TRACI:ING STATUS: SCHEDULE PHASE 8 DATA SOURCE: DWR OWNERS GROUP CHECl. LIST NO.: A3.4 CHEClLIST AREA: PANEL LAYOUT AND DESIGN F'ANCL/WORl:GTATION NO. 1RSS-PNL102 ( 1.) DESCRIPTION OF DISCREPANCY: SIX OR MORE METERS ARC GROUPED TOGETHER WITHOUT DEMARCATION RECOMMENDATIONS: NO ACTION. THESE METERS ARE APPROPRIATELY LOCATED ADOVE CONTROLS. ACTION: APPROVED DY GSU MANAGEMENT ELDCRH ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 2 IhPLEMENTATION SCHEDULE: O
HUMAN ENGINEERINO DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT G' DATE: 02/24/04 HED NO- a 224 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----------------------------------------------==- =---------------------------
DATA SOURCE: BWR OWNERS GROUP CHCCKLIST NO.: A3.4 CHECELIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P800-84C DESCRIPTION OF DISCREPANCY: DEMARCATION WOULD ENHANCE THE COMPONENT GROUPING FOR THE SEQUENCE PROGRAMMER
.. CONTROL RECOMMENDATIONS:
ADD DEMARCATION TO ENHANCE COMPONENT GROUPING. \w ACTION: APPROVED DY GSU MANAGEMENT. l Et<DCR # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER t O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 HED NO. = 28 REVIEWER: BARFG/ CHASE /EHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: LWR OWNERS GROUP CHECELIST NO.: A3.6 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PAllEL/ WORKSTATION NO. 1RSS-PNL102 ( I.) DESCRIPTION OF DISCREPANCY: SIX METERS ARE ABOVE THE 60 INCH MAX RECOMMENDATIONS: NO ACTION. METERS ARE READABLE AT PRESENT LOCATION. ACTIO.: APPROVED BY GSU MANAGEMENT. 4 ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: S' l 4 l l l l
HUMAN ENGINEERING DISCREPANCY RECORD p RIVER BEND NUCLEAR PLANT
\
DATE: 02/28/04 HED NO- a 12.1 REVIEWER: BARKS / CHASE /5HANVLE TRACKING STATUS: SCHEDULE PHASE DA1A SOURCE: BWR OWNERS GROUP CHCCFLIST NO. A3.6 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P628 ( 1.) PANEL / WORKSTATION NO. P631 1 ( 1.)
--------------------------------- - _ - _ - -=____--. _ _ _ _ - - - - _ _ - - - _ = - - - - - -
, DESCRIPTION OF DISCREPANCY:
CONTROLS ARE LOCATED ABOVE THE 60 INCH GUIDELINES (UP TO 79 INCHES) RECOMMENf%TIONS: b NO ACTION. THESE BArKPANEL CONTROLS ARE IN ACCEPTABLE LOCATION. ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR M ISSUE DATE / / FDDR# ISSUE DATE / /
. CRITICALITY RATING: 2
, IMPLEMENTATION SCHEDULE: i t i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/84 HED NO. :: 268 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
---------- __---------_-__------------- _ _ = - - - _ _ - - - - - = = - - ==-------------
DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: A3.6 CHECI:L I ST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PO70-55 PANEL / WORKSTATION NO. P870-56 DESCRIPTION OF DISCREPANCY: TOP ROW OF METERS IS 72 INCHES OFF THE GROUND AND FOUR ROTARY CONTROLS ARE 65 INCHES RECOMMENDATIONS: NO ACTION. THIS IS STANDARD HEIGHT FOR METERS IN THE CONTROL ROOM. ACTION: APPROVED DY GSU MANAGEMENT. Et,DCRM ISSUE DATE / / FDDR# ISSUE DATE / /
-===__-------------------------------------
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
u HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT , [
'd DATE: 02/27/04 HED NO.s 319 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE' PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A3.7 CHECKLIS1 AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76 DESCRIPTION OF DISCREPANCY:
THE CHILLED WATER CONTROLS SHOULD BE LOCATED CLOSER TO THEIR RELATED HtN
. CONTROLS AT PG63-71C.
RECOMMENDATIONS: CHILLED WATER CONTROLS ARE APPROPRIATELY OROUPED. OPERATOR TRAINING WILL l FAMILIARIZE THEM WITH LOCATION OF CONTROLS.
.s ACTION:
APPROVED BY GSU MANAGEMENT. E&DCRM ISSUE DATE / / FDDRtt ISSUE DATE / / CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE: O 1 l l l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L. E A R PI-.A N T DATE: 02/27./D4 HED NO.= 509 RCVIEWER: DURGY/CitASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CliCCILLIST NO. : A4.2 CHEC) LIST AREA: PAtJEL LAYOUT AND DESIGN pat 4EL/ WORKSTATION NO. GENERIC ( I.) DESCRIPTIOr4 OF DISCREPANCY: SELECTED USE OF COLORS IS NOT CONSISTENTLY APPLIED FOR ALARM PRIORITIZATION (ALARM COLORS LACK RECOGNIZADLE STANDARD). RECOMMENDATIONS: A COLOR PRIORITIZATION CONVENTION WILL DE DEVELOPED AND CONSISTENTLY APPLIED TO THE RDS CONTROL ROOM PANELS. ACTION: APPROVED DY GSU MANAGEMENT l l l t ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTtTION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT i [V DATE: 02/29/84 HED NO.s 11 REVIEWER: DARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHECI. LIST NO.: A4.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. IRSS-PNL101 ( 1.) 1SWPnP2A SERVICE WATER PUMP 2A DESCRIPTION OF DISCREPANCY: THE START /STOP SWITCH LABELS FOR THE SWP*S ARE RED AND BLACK i RECOMMENDATIONS CHANGE LADELS TO HAVE BLACK BACKGROUND O ACTION: APPROVED DY GSU MANAGEMENT i Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / k CRITICALITY RATING: 2 IMPLEMENTAT!DN SCHEDULE: PRIOR TO EXCEEDING 5% POWER i i P a
- O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT DATE: 02/20/04 HED N O . :: 297 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE
---------------------------------------------------------=- -----------------
DATA SOURCE: BWR OWNERS GROUP CHECILLIST NO.: A4.2 CHECDLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-16
------------_---------------- -------_-- == . =--------------------
DESCRIPTION OF DISCREPANCY: SUPP. POOL MIMIC AND MIMIC THROUGH CST IS OF THE WRONG COLOR RECOMMENDATIONS: CHANGE MIMICS TO CONFORM TO CONTROL ROOM CONVENTIONS ACTION: APFROVED BY GSU MANAGEMENT.
, ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O l l l l l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 1n\ U DATE: 02/27/04 HED NO a 574 REVIEWER: BARMS/ CHASE TRACKING STATUS: SCHEDULE PHASE
---------------------------------_ -------------- _===-- - __---------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P908-85C-1 ( 1.)
----------------------------------------------------=-- _ -===-- .--=- . -_.
DESCRIPTION OF DISCREPANCY:
.. YELLOW INDICATOR LIGHTS UNDER 4160V BUS CW AREA SHOULD BE WHITE AND SHOW
. FUNCTION
. RECOMMENDATIONS:
EVALUATE FUNCTION OF LIGHTS L CHANGE COLOR IF VARIES FROM STANDARD k'_5) CONVENTIONS. EVALUATE LABELING & CHANGE IF APPROPRIATE. f ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
---------------------------------.. ------------- --------- __= == ------__-
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCFEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD . RIVER BEND NUCLEAR PLANT DATE: 02/27/04 FiEEI) P4 E3 . = 7F 9P REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PB63-71 ( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO, PG63-73 ( 1.) DESCRIPTION OF DISCREPANCY: SERVICE WATER AND CHILLED WATER USES THE SAME COLOR MIMIC RECOMMENDATIONS: CHANGE SERVICE WATER MIMIC TO DARK DLUE. ACTION: APPROVED DY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER , 1 9 t L
DZSCREPANCY RECORD HUMAN ENGINEERING
/N RIVER BEND NUCLEAR PLAN'T
\
ss } HED NO.s 320 DATE: 02/27/84 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECMLIST NO. A4.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN 1-1 PANEL / WORKSTATION NO. P863-76 4 DESCRIPTION OF DISCREPANCY:
" THE MIMIC LINES FOR THE SERVICE WATER AND CHILLED WATER SYSTEMS ARE NOT
.. DISTINGUISHED BY COLOR.
RECOMMENDATIONS: DISTINGUISH MIMIC LINES BY COLOR TO DIFFERENTIATE THE TWO WATER SYSTEt1S
'f-v.
- ACTION:
SERVICE WATER TO BE DARK BLUE. CHILLED WATER TO BE LIGHT BLUE. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / j CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
( l I I .1 i i L I
. , . _ , - _ _ _ _ _ _ - . . - .. . ,_.. - ._ . .. .-~ _.. - . - . . - _ - - _ . . - -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L_ E A R PLANT DATE: 07/19/84 HED NO. u G26 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECULIST NO.: A5 CHECFLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19 DESCRIPTION OF DISCREPANCY: LADELS ON ADS MANUAL INITIATION (P601 SECTION 19) READ EITHER " TIME DELAY LOGIC" OR " INSTANTANEOUS LOGIC" RECOMMENDATIONS:
. EVALUATE FUNCTION OF SWITCHES AND CHANGE LADELING IF APPROPRIATE.
ACTION: EVALUATION HAS DETERMINED THAT LADELS WILL DE CHANGED TO READ " MANUAL INITIATION". E t> DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER O
HUMAN ENGINEERING D I BCREP' ANCY RECORD RIVER BEND NUCLEAR P'L AN T (~] x / . DATE: 02/29/04 FiEE E) PJ C) _ s ;5 57 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.1 CHECisLIST AREA: PANCL LAYOUT AND DESIGN PANEL / WORKSTATION NO. 1RSS-PNL102 ( 1.) 1E12*MOVF024B VALVE F024B ( 2.) 1E12*MOVF011B VALVE F011B ( 3.) 1E12*MOVF037B SHUTDOWN COOLING UPPER POOL VALVE
. DESCRIPTION OF DISCREPANCY VALVES SHOULD BE LABELED AUTO FOR CONSISTENCY
) RECOMMENDATIONS:
LABELS HAVE BEEN CORRECTED SINCE SURVEY. NO FURTHER ACTION REOUIRED.
ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE:
O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER DEND NUCLEAR PLANT DATE: 02/28/84 F4 EE E) P4 C3 . a i d> C) REVIEWER: BARKS /MATSON TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: A5.1 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P622 ( 1.) PANEL / WORKSTATION NO. P642 ( 1.) PANEL / WORKSTATION NO. P632 - ( 1.) PANEL / WORKSTATION NO. P623 l . ( 1.) DESCRIPTION OF DISCREPANCY: THE PED LADELS FOR TRAIN 1 ARE DIFFICULT TO READ AND CAN ALLOW DIRT TO ODSCURE THE LETTERING RECOMMENDATIONS: THIS PANEL IS LABELED CONSISTENTLY WITH DACKPANELS AND USES RED STOCK TO MAKE THE DIVISION READILY APPARENT, NO ACTION. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD 7s RIVER BEND NUCLEAR PLANT
)
DATE: 02/20/04 HED NO.s 299 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: A5.10 CHECKLIST AREA: PANEL LAYOUT AND DESION l l PANEL / WORKSTATION NO. P601-16 ( 1.)
= = = _ - __-------
DESCRIPTION P~ DISCREPANCY: j
.. THERE IN AN L'ALABELED METER ON P601-16 i RECOMMENDATIONS:
. THE METER IS DLANM. NO ACTION REQUIRED.
C> ACTION: e APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / /
----------------------- _==___= - - - - . -= __----_=- -----
CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE:
I
1 l HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED N O . :: 323 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
------------------------ ----------------------------=_ ___------------
DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO.: A5.10 CHECMLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76 _. . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - . --- --------- - --__-_-------- DESCRIPTION OF DISCREPANCY: INOPERABILITY SWITCHES READ "NCTtMAL AND INOP" INSTEAD OF "OFF AND ON" FOR DIVISION 1 AND DIVISION 2. RECOMMENDATIONS: LABELS HAVE BEEN CHANGED SINCE SURVEV TO SAY OFF AND ON. NO FURTHER ACTION REQUIRED. ACTION: APPROVEL BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-------------- - - - - - - = - _ _ _ - _ - - - - _ _ _ - - __-
CRITICALITY RATING: 2 { IMPLEMENTATION SCHEDULE: 1 l l 0
HUMAN ENGINEERING DISCREPANCY RECORD ( RIVER BEND NU C L.E AR PL. ANT DATE: 02/29/84 F4 EE I) bJ C) . 1 55 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE _=_=----------
--------------.-------=_-- - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECHLIST NO.: A5.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1 ( 1.)
-_---__-=-
DESCRIPTION OF DISCREPANCY: LABELS ABOVE THE EMERGENCY TRANSFER SWITCHES ARE DUPLICATES RECOMMENDATIONS:
- DELETE ONE SET OF LABELS ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/24/84 HED NO-a 227 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----------------------------------------------------= = _-------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-81C ( 1.)
----------------------- _ _ - = _ - _ _ _ _ __ _ _ _ __ _ _ ____ _ _ _ _ =
DESCRIPTION OF DISCREPANCY: LABELS ARE POSITIONED UNDER H2 RECOMBINER POWER ADJUST, H2 RECOMBINER TEMP CHANNEL SELECT, AND H2 RECOMBINER POWER OUT RECOMMENDATIONS: REPOSITION LABELS ABOVE THE LISTED CCNTROLS. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
-------------------------------- __ _ - - - = - _ - ------------ -
_ _ _ _ _ = = _ = - _ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DIBCREPANCY RECORD /7 RIVER BEND NUCL EAR PR-.A N T DATE: 02/27/84 F4 EE I) PJ E3 . s E3 d2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---------------------------------== ==_ _-------------------------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 ( 1.) PANEL / WORKSTATION NO. P863-72 ( 1.) PANEL / WORKSTATION NO. P863-73 ( 1.) .. DESCRIPTION OF DISCREPANCY: THE AUX BUILDING UNIT COOLERS SHOULD BE LABELED ABOVE THE SYSTEM ( RECOMMENDATIONS: USE HIERARCHICAL LABELING t< ENCLOSE SYSTEM WITH LINES OF DEMARCATION ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/84 HED NO- a 270 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
---------------__..---_-__--_--------=- =- -- ---__-------- - = - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-55 PANEL / WORKSTATION NO. PB70-56
---------------------------- _ _ _ = - - - - - - - - - _=- _ = - . _ _ = -__----------
DESCRIPTION OF DISCREPANCY: STANDBY SERVICE WTR MULTIPEN RECORDERS OBSCURE THE LABELS RECOMMENDATIONS: MOVE LABELS ABOVE RECORDERS e ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
---------------------------------- _===---- - - - _ _ _ _ __ _ - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
RECORD HUMAN ENGINEERING DISCREPANCY RIVER BEND NUCLEAR PLANT (~'T %-) F4EEI) BJ C3 . s da d2:5 DATE: 02/21/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: DURGY/ CHASE
- -- _== -- -__________
--______-_____-------____-=---=---__-___--________--==
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-1 PANEL / WORKSTATION NO. P680-7C PANEL / WORKSTATION NO. P680-8C PANEL /WORKST ATION NO. P6BO-9C PANEL / WORKSTATION NO. P680-15C _ - - - - - ---__-=_=___
. __--_________=_--==--=---
DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES AND ESCUTCHEONS ARE NOT USED TO IDENTIFY SYSTEM s l ) DESIGNATION h4 RECOM.1ENDATIONS: IDENTIFY SYSTEM DESIGNATION WITH HIERARCHICAL LABELS ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- _.----_-____-_______-_____-_== -----______----______ -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l l 1 v
HUMAN ENGINEERINO DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/23/S4 Fi EE I) bJ C3 . = 4F 2 5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
-----------= ---------------------------------- - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. F6BO-5 PANEL / WORKSTATION NO. P680-6
--- ------------------------------ -- ___ ---- _ - - . --=- =
DESCRIPTION OF DISCREPANCY:
, LABELS, LEGEND PLATES, AND ESCUTCHEONS ARE NOT USED TO IDENTIFY SYSTEM DESIGNATION (SOME GROUPINGS ARE IDENTIFIED ON INSERT SC).
RECOMMENDATIONS: USE HIERARCHICAL LABELING TO IDENTIFY SYSTEM DESIGNATION ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRH ISSUE DATE / /
=------
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD l I RIVER BEND NUCLEAR PLANT DATE: 02/27/04 HED NO. s 46 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE l
- - - - - - - - - - =--_= -----------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.4 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. GENERIC ( 1.)
------_-__--=- - - - -
DESCRIPTION OF DISCREPANCY:
... PANELS ARE NOT LABELED BY FUNCTION AND NUMBER RECOMMENDATIONS:
THESE PANELS ARE LABELED, DUT LABELING IS ON THE BACK OF THE PANELS. LABEL FRONT 0?r PANEL IF APPROPRIATE 7~' N. ACTION: APPROVED DY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER r
HUMAN ENGINEERING DIBCREPANCY RECORD g RIVER BEND NUCLEAR PLANT DATE: 02/23/84 F1EEI) P4 C3 . s ek 7F dt REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE ______________________________________- ____- - = = = - - - - - - - ==-- __ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-1 ______=- ___________- =- - _______________________--
, __ ----- =______
DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES, AND ESCUTCHEONS ARE NOT CONSISTENT IN NOMENCLATURE, USE OF ACRONYMS, ABBREVIATIONS, ETC. RECOMMENDATIONS: CHANGE LABELS AS REQUIRED TO MATCH CONTROL ROOM DESIGN CONVENTION ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUF. DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l I l O
I HUMAN ENGINEERING DISCREPANCY RECORD
.- RIVER BEND NUCLEAR PLANT f DATE: 02/29/84 HED NO. = 14 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN
. PANEL / WORKSTATION NO. C61-POO1
( 1.)
~ __ __ --
DESCRIPTION OF DISCREPANCY:
,,, USE OF HIERARCHICAL LABELING FOR THE RHR & RCIC COMPONENTS WOULD BE HELPFUL RECOMMENDATIONS:
USE HIERARCHICAL LABELING WHERE POSSIBLE ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2
, IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
1 l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED N O . :: 83 REVIEWER: PARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: THERE IS NO HIERARCHICAL LABELING. LABELS ARE NOT SIZE CODED. RECOMMENDATIONS: USE HIERARCHICAL LABELING ACTION: APF' ROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULL: PRIOR TO EXCEEDING 5% POWER O
i HUMAN ENGINEERING DISCREPANCY RECORD 1 RIVER BEND NUCL EAR PLANT 7s k ,} DATE4 02/28/84 F4EEE) bJ C3 a 1 05 :2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
==--------
-----_ ------ _ - - - =-----------=- _ - _ _ _ _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.8 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P631 ( 1.) PANEL / WORKSTATION NO. P628
- . ( 1.)
= = _ - -
DESCRIPTION OF DISCREPANCY: THE WHITE ON BLUE LETTERING IS DIFFICULT TO READ AND CAN COLLECT DIRT IN THE ENGRAVED LETTERS RECOMMENDATIDNS: THESE LABELS ARE ON BACKPANELS. BLUE INDICATES DIVISION. THIS IS CONSISTENT WITH RBS CONVENTION FOR BACKPANELS. NO ACTION. ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: 1 m
\_
l
}
l HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/04 HED N O :: 21O REVIEWER: LIDDLE /MATSON/BIF!:OP TRACKING STATUS: SCHEDULE PHASE DATA EDURCE: PWR OWNERS GROUP CHECKLIST NO. AS.O CllECl: LIST A!'CA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. POO8 (PANEL GENERIC) ( 1.) DESCRIPTION OF DISCREPANCY:
.. ENGRAVED METALLIC LAE:ELS LACK DISTINCTION AND CONTRAST RECOMMENDATIONS:
CHAri: ANY ENCRAVED LADELS THAT LACK DISTINCTION AND CONTRAST. ACTION: APPROVED DY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PL_ ANT V DATE: 02/23/04 HED NO. 426 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- -----=- _=--
-------------------====_
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN
. PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6
-------=__ -- =------ _=--= = - ---- - - -___-
,,, DESCRIPTION OF DISCREPANCY:
LABELS ARE NOT EASILY READ WHILE SITTING AT PANEL (INSERT B METERS NOT EASILY READ). hx RECOMMENDATIONS: NO ACTION. THIS IS NOT A SIT DOWN ONLY PANEL. LABELS ARE FULLY VISIBLE WHILE (_) - STANDING. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR4 ISSUE DATE / /
--- - -- _ _ - - - = _
---------=
=_ - - - - -
~
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: 1 J O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/04 F4 EEI) b4 E3 . s 02:2 db REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----------------------------------------- _ _ - = _ .
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-83B ( 1.)
------------------------------ -= ._- __-- . . _ _ _ = - -.
DESCRIPTION OF DISCREPANCY: LABELS UNDER CHART RECORDERS ARE OBSCURED RECOMMENDATIONS: PUT LABELS ON CHART RECORDER OR ABOVE ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / /
---------------- =__ ------------- .. _
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT f~') (/ DATE: 02/27/84 HED N O - :: 84 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECMLIST NO.: A5.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 ( 1.) 1HVR*AOD265 DAMPER PANEL / WORKSTATION NO. P863-72 ( 1.) 1HVR*AOD265 DAMPER PANEL / WORKSTATION NO. P863-73 ( 1.) 1HVR*AOD265 DAMPER DESCRIPTION OF DISCREPANCY: THE OPEN AND CLOSED LABELS ARE OBSCURED BY THE SWITCH LOCKING NUT RECOMMENDATIONS: NEW LADELS HAVE CORRECTED PROBLEM SINCE SURVEY. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / _- _ . = - - - __ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: A U
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCt. EAR P t. A N'T DATE: 02/27/84 F4 EEI) hJ C3 . = EB 7 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- - - . . - - - - - - - - - - - - - - - - - - - - - - -------------- - _ = - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A7.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN l PANEL / WORKSTATION NO. P863 ( 1.) l
-_=--- - - - --
DESCRIPTION OF DISCREPANCY. CONTROL SURFACES ARE NOT VISIBLE FROM THE MAIN CONTROL AREA ' RECOMMENDATIONS: THIS PANEL IS MONITORED BY A UNIT (ROVING) OPERATOR. THIS IS APPROPRIATELY COVERED IN TRAINING. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 ( IMPLEMENTA7 ION SCHEDULE: l l O
HUMAN ENGINEERING DISCREPANCY RECORD
- RIVER BEND NUCLEAR PLANT (y)
DATE: 02/29/04 F4 EC E) b4C3 . s 05 "5 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
.===-_------ =_ ---
- _ = _ = _ _ - - - - - - - - - - --- -- --- _--_-------__
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. Bl.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. 1RSS-PNL102 ( 1.) DESCRIPTION OF DISCREPANCY:
. INDICATOR SCALES ARE NOT EASILY READ RECOMMENDATIONS:
THESE SCALES ARE CONSISTENT WITH SCALES IN THE CONTROL ROOM. NO ACTION. O. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: i I \ 1 l l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 HED NO- 228 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO.: BI.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC
---------------------------------___ ==. __-__= =- - - - - - - - - -
_==---- DESCRIPTION OF DISCREPANCY: BAILEY CONTROLLERS ARE COLLECTING DIRT IN THE BUTTONS RECOMMENDATIONS: ALL RBS BAILEY CONTROLLERS ARE LAYED OUT THE SAME WITH CLOSE BUTTON ON LEFT CORRESPONDING TO 0% & OPEN ON RIGHT CORRESPONDING TO 100%. NO ACTION. ACTION: AFPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------------------_ =- _ _ - - - - - - - - - - - - - - - - - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
}
llI l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT ( 1 L/ DATE: 09/19/04 HED N O ., a 827 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE ________- --- _____= - =--- -- = - - - - -- =_--- - - - - - = = = - - - ---_____ DATA EDURCC: OPERATING PERSONNEL INTERVIEW CHECKLIST NO. B2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601 ( 1.) ______:- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ = . . - _- DESCRIPTION OF DISCREPANCY:
.. . SYSTEM PRESSURE ON ECCS PANELS ONLY HAVE AMPS AND FLOW INDICATORS, BUT ALSO NEED PRESSURE INDICATION RECOMMENDATIONS: /-~x DURING TRAINING ON THE SIMULATOR, OPERATORS ARE TAUGHT TO MONITOR REACTOR t s_,) PRESSURE. WHEN REACTOR PRESSURE REACHES THE ECCS SYSTEM PRESSURE INITIATION, WILL OCCUR. THIS IS THE SAME INFORMATION THAT A PRESSURE INDICATOR WOULD GIVE YOU.
IN ADDITION, OPERATORS ARE TRAINED TO KEY IN ON FLOW RATES, AND THE RELATIONSHIP BETWEEN PUMP HEAD AND FLOW RATES. NO FURTHER ACTION REQUIRED ACTION: APPROVED DY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / ______=- - ------. _________- --- ________ ___--- ___ CRITICALITY RATING: 2 IMPLEMENTATION 3CHEDULE: l l l
1 1 l l HUMAN ENGINEERING DIBCREPANCY RECORD 1 RIVER BEND NUCLEAR PLANT DATE: 02/27/04 Fi EE I) bJ C3 . a 9P C2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
-------..------------------------- _ _ _ - _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - _=-------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B2.11 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORKSTATIOtt NO. PO63-71B ( 1.) 1RMS*RIW16B RX BLDG CNTNT HATCH RAD INDICATOR
-----_-----_-------. _ = = - - - - _ - = _ - - - - - -
DESCRIPTION OF DISCREPANCY THIS METER HAS NO INTERMEDIATE VALUES SPECIFIED ON THE SCALE RECOMMENDATIONS: THIS METER IS LEING REMOVED PER FDDR-1464RO. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDUR# ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - ==-- _ _____- - _ - - - - _===
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT r] 325 DATE: 02/27/84 HED NO.s REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
=------ --
=------- __. -- = - _ - . -
- - - - - - - - - - = - - .
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.11 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-76
-. -- --- =- --
DESCRIPTION OF DISCREPANCY: RADIATION METERS DO NOT HAVE INTERMEDIATE VALUES INDICATED ON THE SCALE. RECOMMENDATIONS: THESE INDICATORS ARE BEING REMOVED PER FDDR-1464RO. NO FURTHER ACTION . REQUIRED. O ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - - - - = - - -
__-------- . _ _-=- _ -
- - - - - - - - - - - - - - - - = _ = - - .
CRITICALITY RATING: 2
- IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L.E A R PI_.A N T DATE: 02/29/04 HED NO.s 17 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - __ - - - - - - = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.12 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-POO1 ( 1.) RPV PRESS REACTOR PRESSURE DESCRIPTION OF DISCREPANCY: THERE ARE 14 GRADUATIONS BETWEEN NUMEERED MARKINGS RECOMMENDATIONS: g NO ACTION. OPERATIONS PERSONNEL FIND THE SCALE ON THIS METER TO BE W APPROPRIATE. ACTION: APFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / _______________________ _ _ _ _ _ _ _ _ - - = _ - _ __ _ _ _ _ - - ._ _ - - - - - _ _ _ _ ____________ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: l 9l1 l l l
HUMAN ENGINEERING DISCREPANCY RECORD
. RIVER BEND NUCLEAR PLANT
\ / U DATE: 02/27/84 HED NO- a 326 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
----- __ --------- - === _- - --------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.12 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-76
- - - _ _ _ -. - - _ _ _ _ _ _ _ ___-_- =
DESCRIPTION OF DISCREPANCY: THE CHARCOAL BED TEMPERATURE INDICATORS HAVE 14 INTERMEDIATE GRADUATIONS
*- BETWEEN NUMBERED MARKINGS.
RECOMMENDATIONS: NO ACTION. OPERATIONS FINDS THIS SCALE APPROPRIATE. t ACTION: APPROVED BY GSU MANAGEMENT. E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: l I ($) l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 F1 EE E) bJ C3 . s 1 E3 REVIEWER: BARKS /DISHOP TRACKING STATUS: SCHEDULE PHASE ______________________________________-- ===_______- ____ ---_____________ DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: B2.13 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-P001 ( 1.) ______________________________ ___---- _ = - - - ______. -=- --- _=_____ DESCRIPTION OF DISCREPANCY: RPV PRESSURE HAS SUBDIVISIONS IN NULTIPLES OF 3 RECOMMENDATIONS: NO ACTION. OPERATIONS PERSONNEL FIND THE SCALE ON THIS METER TO BE APPROPRIATE. ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / ___ _ = = = _________= ____ __________- _- = _ _ _ _ _ _ _ _ _ _ _ _ . . CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD
- f. RIVER BEND NUCLEAR PLANT k' DATE: 02/29/04 F1EE E) bJ C3 z 19P REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
=------ =- _---=-- .== -=-------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. D2.17 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-POO1 ( 1.) _----------- - - - - - - - . = = - - ----- _---
---------====- __
DESCRIPTION OF DISCREPANCY:
.. RCIC TURB. SPEED FAILS TO ZERO RECOMMENDATIONS:
INVESTIGATE METHOD OF DETERMINING A FAILED METER O. ACTION: ADJACENT FLOW INDICATION IS BACKUP TO DETERMINE / VERIFY THAT METER IS FUNCTIONAL. NO ACTION. Et<DCRM ISSUE DATE / / FDDR# ISSUE DATE / /
=-_---- ==_ - - - = _ ---== ----------- -------- .-
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
H LJ M A N ENGINEERING DISCREPANCY RECORD RIVER . BEND N LJ C L E A R PLANT DATE: 02/27/84 HED NO t 324 REVIEWER: SCHROEDER/MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE
-------- -_- -----__-----_------------__- _= _- - __---_-_------------ _
DATA SOURCE: DWR OWNERS GROUP CHECI: LIST NO. B2.3 CitECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-76
-_______- _______ __-______-___--_ _ _ _ - _ - - . = _ _ _ --_=____-____-_-_______
DESCRIPTION OF DISCREPANCY: RADIATION LEVEL INDICATORS SHOULD HAVE THE TIMES MULTIPLIER ON THE SCALES. RECOMMENDATIONS: THESE INDICATORS ARE DEING REMOVED PER FDDR-1464 RO. NO FURTHER ACTION REQUIRED. ACTION: APPROVED DY GEU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRn ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O e l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT I') U DATE: 02/23/84 HED N O - :: 2O2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
=---____
DATA SOURCE: PWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE l PANEL / WORKSTATION NO. P870-54 ( 1.) 1GMC-PIEPR-15 STATOR COOLING WATER PRESS DESCRIPTION OF DISCREPANCY: THE LIGHTING IN THE CONTROL ROOM IS NOT EVEN , RECOllMENDATIONS: ( INVESTIGATE WAYS IMPROVING THE CONTROL ROOM LIGHTING Ih ACTION: STONE DCRDR. & WEBSTER IS EVALUATING THE CONTROL ROOM ILLUMINATION AS A RESULT OF FINAL LIGHT READINGS WILL BE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED AND FLOORING IS INSTALLED. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 HED NO. c 229 REVIEWER: LIDDLE /MATEON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
-------------------------------- ____ _. = - _ _ _ - ------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: D2.5 CHECl! LIST AREA: INSTRift1Et4TATION AND HARDWARE PANEL / WORKSTATION NO. P808-81B
--------------------------------- ..----- __-_ - _ - - - - - = = - - - - - - - - _ _ = = - - - - - - - - - - - -
DESCRIPTION OF DISCREPANCY: HONEYWELL INDICATORS ON VERTICAL BOARD HAS POINTERS WHICH OBSCURE NUMBERS RECOMMENDATIONS: INVESTIGATE COLORING THE METER FACE SUCH THAT POINTER WILL NOT OBSCURE NUMBERS. ACTION: NO ACTION. EVALUATION OF THCSE INDICATORS HAS DETERMINED THAT NUMBERS ARE NOT OBSCURED AG PREVIOUSLY THOUGHT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- - = _ _ _ - - _ _ __ .--- -- ______ - - - - - - - - - --
----- _ _ _ - - = - _ _ - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
l HUMAN ENGINEERING DIBCREPANCY RECORD g RIVER BEND NUCLEAR PLANT \ l DATE: 09/19/84 F4 EE I) bJC3. a 779P:2 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE _=---- DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808
--- ===___ -
__====-_ -- - DESCRIPTION OF DISCREPANCY: MULTI-PEN RECORDERS ON P809 NEED ALL SCALES INDICATED AND THOSE WHICH ARE
.., SPARES ( I . E. DRYWELL PRESS, SUPPRESSION POOL TEMPERATURE)
RECOMMENDATIONS:
. LABEL ALL SCALES TO INDICATE FUNCTION.
O ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- - - - - - - - - - - - - = = - - - - - - - - - - - - - - - _- __ __ _
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
r HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND N U Ct._E A R Pl_ ANT DATE: 09/19/84 FiEEI) b4 03 . -
~F 9P 5 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
-_____________-_________-_________ - _ _ = - - - - ---
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P845 DESCRIPTION OF DISCREPANCY: RPV TEMP. RECORDERS ON P845 READ IN DEGREES CELCIUS BUT SHOULD BE READ IN DEGREES-FARH. RECOMMENDATIONS: THIS HAS BEEN CORRECTED SINCE SURVEY. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: 9
HUMAN ENGINEERING DIBCREPANCY RECORD
- RIVER cdEND NUCLEAR PLANT DATE: 02/20/84 HED NO- = 303 REVIEWER: LIDDLE /MATSON/BISH3P TRACKING STATUS: SCHEDULE PHASE
=____ - _ - - ==______- _ _ _ _ - - - _ =_
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B3.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-16
-__- _ _= - _ = - - - -- - = - _ -
DESCRIPTION OF DISCREPANCY: DIESEL ENGINE STOPS ARE NOT CLEARLY MARKED
, RECOMMENDATIONS:
ENHANCE STOP BUTTONS ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / ______________=_ - - - . - - - = = -
- = = - - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 03/01/84 F4 EEI) b4 C3 - = 1 4bE3 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
-_--- __------- ._=---
DATA SOURCE: BWR OWNERS GROUP CHECV. LIST NO.: B3.15 CHECELIST AREAS INSTRUMENTATION AND HARDWARE PANEL /WORKSTsTION NO. GENERIC ( 1.) _----___------- ----- - = = - - - - DESCRIPTION OF DISCREPANCY: RECORDERS ARE NOT MARKED TO SHOW NORMAL / ABNORMAL RANGE RECOMMENDATIO!!S: MARK RECORDERS TO INDICATE NORMAL / ABNORMAL RANGE ACTION: RECORDERS SPECIFIED BY GSU OPERATIONS WILL BE MARKED FOR NORMAL / ABNORMAL I ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / i l CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER S
HUMAN ENGINEERING DISCREPANCY RECORD
,m RIVER BEND NUCLEAR PLANT i )
DATE: 03/02/84 HED NO-z 145 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
-------=- . == ----------------------=. -_ . - - - .
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B3.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.)
--------- --------= _ _ _ = _ _ _ _ _ __ - =--------
DESCRIPTION OF DISCREPANCY:
... ALARM POINTS ARE NOT IDENTIFIED ON THE RECORDER RECOMMENDATIONS:
NORMAL / ABNORMAL RANGES WILL BE IDENTIFIED ON SCALE (G-) ACTION: APPROVED BY GSU MANAGEMENT Et4DCRM ISSUE DATE / / FDDRM IS3UE DATE / /
---------------------- ==--- - --- - - - - - _ -
- = . ___
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l 1
I s. HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 FiEEI) bJ C3 . a e& C5:5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
---------------------------------__ -- ====_ __
DATA SOURCE: BWR OWNERS GROUP CHECKLIST i40. B4.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6
----------------------=-. -
DESCRIPTION OF DISCREPANCY: UNLIGHTED INDICATING LIGHTS DO NOT CONSISTENTLY REFLECT A NEGATIVE STATE OF
" POWER OFF". (SCRAM SD. VALVE INDICATING LIGHTS GO OUT WHEN SCRAM EIUNAL IS IN.)
h RECOMMENDATIONS: TRAINING PROPERLY ADDRESSES THIS. THE SCRAM STATUS IS ALSO ANNUNCIATED. ACTION:
, APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: l t I L
HUMAN ENGINEERING DIBCREPANCY RECORD / RIVER BEND NUCLEAR PLANT (]_- F1EE E) PJ E3 : 55 :2 :5 DATE: 02/23/84 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - =_ -- = _ - -
------_-==
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B4.5 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-7 ( 1.) PANEL / WORKSTATION NO. P680-8 ( 1.) PANEL / WORKSTATION NO. P680-9 ( 1.)
. --== __- ==------_=- . _ - - _ _ -
= = _ _ _ . - - - - - -
DESCRIPTION OF DISCREPANCY: (, BULB REPLACEMENT ON INDICATING LIGHTS IS NOT EASILY AND SAFELY PERFORMED. (7C N'I BUTTONS EASILY REPLACED) RECOMMENDATIONS: FURTHER EVALUATION OF PUSH BUTTON DESIGN INDICATED THAT THESE BUTTONS CAN DE REPLACED (PRESSED INTO POSITION) WITHOUT INADVERTENT SYSTEM INITIATION. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT
. E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
- - - - _ _ _ _ - _ ==---- ----------------
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: l O
HUMAN ENGINEERING DISCREPAhJCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 F4 EE I) bJ C3 - a 7F d2c7 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
-----_ _----------___ ==------------ _------- -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4D
- - - - - - - - - - - - - = - _ _ = - - _ - - - - - - - - - _ - = _ - - - - -
DESCRIPTION OF DISCREPANCY: RESET BUTION LIGHTS - NEED LABEL TO INDICATE FUNCTION. RECOMMENDATIONS: ADD LABEL TO INDICATE FUNCTION ACTION: APPROVED BY GSU MANAGEMENT.
, ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
-------------------------- __ ==---------- _ _=-__----- _ --
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEELING 5% POWER l l O
1 I l l HUMAN ENGINEERING DIBCREPANCY RECORD ,o RIVER BEND NUCLEAR PLANT DATC 02/24/84 HED NO a 770 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
==_ -_________
________..___..____________- - - _ _ - - _ _ _ _ _ _ _ - - .=-- __ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-6D1
= _____________ -
DESCRIPTION OF DISCREPANCY: SRM METERS TOO SMALL - SHOULD BE LOCATED NEAR SRM CONTROLS.
. RECOMMENDATIONS:
NO ACTION. SCALES ARE SMALL DUE TO SPACE CONSTRAINTS IN P-680.IF
. RE-LOCATED,THEY WOULD NOT BE ADJACENT TO CORRESPONDING RECORDER. SYSTEM f'} OPERATION IS ADDRESSED IN SIMULATOR TRAINING.
%s" ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / ____ -- - _ - _===- - - - - CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: V
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND N U C L_ E A R PR-.A N T DATE: 02/28/84 F4EEI) b4 C3 . 1021 REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DAT A SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHCCVLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863 ( 1.)
----------------------------------=- -_ ---=-
_ = - - - - - - - - - - - - __ - _ - - - - - - - - - - - - - - DESCRIPTION OF DISCREPANCY: MANY HVAC SWITCHES VIOLATE ESTABLISHED NORMS BY TURNING LEFT/RIGHT RUN/ AUTO RECOMMENDATIONS: CHANGE TO MATCH CONTROL ROOM DESIGN CONVENTION ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DIBCREPANCY RECORD 73 RIVER BEND NUCLEAR PLANT I
DATE: 02/23/04 FiEE E) bJ C3 . a eI C59P REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - =------_ -_ _ = - - . - -
-_=----
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B5.11 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANE'./ WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - -__------
.. DEF",RIPTION OF DISCREPANCY:
. HANDLES OR KNOBS ARE NOT SHAPED SO AS TO CLEARLY INDICATE POSITION WITHOUT OBSTRUCTION OF LEGENDS OR CONFUSION OF DIRECTION. (MANUAL SCRAM BUTTONS NEED
. BETTER INDICATION OF POSITION.)
O
) RECOMMENDATIONS:
NOTCH SWITCH COLLAR TO INDICATE FUNCTION. ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/22/84 HED NO.a 286 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ - - -_ - __==-------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-19C
--------------------------------------- -------- _ _ _ = = - - ==- - - = - - - - - -
DESCRIPTION OF DISCREPANCY: THERE IS NO OPEN CLOSED POSITION ON S25 MAIN STEAM LINE DRAIN VALVE RECOMMENDATIONS: LADEL HAS BEEN CORRECTED SINCE SURVEY. NO FURTHER ACTION REQUIRED. h ACTION: APPROVED BY GSU MANAGEMENT.
, ELDCP# ISSUE DATE / /
FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: 1 l l l l , l
HUMAN ENGINEERING DISCREPANCY RECORD p RIVER BEND NUCLEAR PLANT DATE: 02/20/84 HED NO. 302 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
------ _=_ _- =-=_ -- _ _ _ _ -=- -== --------------
DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: B5.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32 PANEL / WORKSTATION NO. P601-16
---------------------------------------------------------- = ---------------- '- DESCRIPTION OF DISCREPANCY: - STANDBY GENERATOR OND DISTRIBUTION INOPERABILITY INDICATION SWITCH DOES NOT HAVE THE BYPASS POSITION LISTED
/' RECOMMENDATIONS: 'v] CHANGE LABEL. ACTION: APPROVED BY GSU MANAGEMENT Et4DCR# ISSUE DATE / / FDDRu ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PL A N'T DATE: 02/21/84 F4EEI) P4 C3 . 02 77 :2 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE _= ==- =---___---_--_-__-_----__ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P870-55 PANEL / WORKSTATION NO. P870-56
--_--___-_-____--___--_-___----_-______- __ __-__-. - =___-----______
DESCRIPTION OF DISCREPANCY: FOUR ROTARY CONTROLS ARE 65 INCHES HIGH RECOMMENDATIONS: NO ACTION. CONTROLS ARE FOR MANUAL BYPASS INOPERADILITY INDICATION. ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDRn ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT u) DATE: 02/29/04 F4EEE) BJ C3 . 25 25 REVIEWER: BARKS / CHASE /SHANKEL TRACKING STATUS: SCHEDULE PHASE
------------- _ - _ _ - - - - - - - - - __=--= _=
- =---- =------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.s B5.5 1 I CHECKLIST AREA: INSTRUMENTATION AND HARDWARE l PANEL / WORKSTATION NO. GENERIC ( 1.)
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = _ _ - - - = = - - - - - - - - - - - - - - - - - - - - - . --------
DESCRIPTICN OF DISCREPANCY:
*.- THROTTLE VALVES NEED LARGER HANDLES BECAUSE THEY TAKE MORE THAN NORMAL HAND - PRESSURE TO OPERATE - RECOMMENDATIONS:
ADD HANDLES EXTENDERS TO THROTTLE VALVE SWITCHES ACTION: APPROVED BY GSU MANAGEMENT EtrCRM ISSUE DATE / / I FDDRM ISSUE DATE / / { J
---------------------=- - -------------------------- ----------------
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
F4UMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/04 Fi EE E) bJ C3 - = dad 2<) REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - = - - - = - = - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECMLIST NO. B5.6 CHCCI: LIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-20C PANCL/ WORKSTATION NO. P601-17C __---------- - - - _ _ = = - - - = - - -- ---- - - - - - - - - _ =--_---___-_---_-- DESCRIPTION OF DISCREPANCY: , FOR SWITCHES, HANDLES ARE NOT DURABLE AND OF ADEQUATE SIZE. RECOMMENDATIONS: INVESTIGATC CHANGING SWITCH HANDLES ACTION: NO ACTION. THESE SWITCHES ARE APPROPRIATE AND ARE USED TO DISTINGUISH PUMPS FROM VALVES. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------ _ = = - = = - - - -= ---------------- =- _= __--------- _
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: i l l l llh
HUMAN ENGINEERING DIBCREPANCY RECORD gm., RIVER BEND NUCLEAR PLANT (_) F4 EE E) d2 d> 1 DATE: 02/21/84 bJ C) . a REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
----------_-----_-- ==--==_ - - - - - - - - - - - - - - - - - - - - ---_____
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.8 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-20C PANEL / WORKSTATION NO. P601-17C
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = - - - - - - - - - - - - - - - - - - - - - - = = - - - - - - _ ----
DESCRIPTION OF DISCREPANCY:
*- FOR SWITCHES, ASSOCIATED DISPLAYS, INDICATING LIGHTS, AND LABELS ARE NOT FREE FROM VISUAL OBSTRUCTION BY HAND OR ARM WHEN SWITCH IS OPERATED.
RECOMMENDATIONS: i EVALUATION Bf OPERATIONS DETERMINED THAT LAYOUT OF CONTROLS & DISPLAYS IS CORRECT AND THAT NO CHANGE IS REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO. a 44O REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHEC): LIST NO. : D6.1 CPECF: LIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4C ( 1.) P _____--___--_________-_________------ _ _ - - _=_____________. --- ______________ DESCRIPTION OF DISCREPANCY: SWITCHES FOR EMERGENCY ARE NOT CLEARLY MARKED. (INSERT 4C TRIP BUTTON B33-SOO1 ALB SHOULD BE RED.) (I:4 SERT 4C-RECIRC. PUMP STOP BUTTONS B33-COOL ALB SHOULD LE RED.) RECOMMENDATIONS: CLEARLY DEMARCATE EMERGENCY SWITCHES ACTION: APPROVED DY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
l 1 HUMAN ENGINEERING D I EBCREP ANC Y RECORD l p RIVER BEND NUCt. EAR Pt. ANT DATE: 02/23/84 HED NO.a 441 REVIEWER: BURGY/ CHASE TRACKIN3 STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B7.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P600-6
- .- DESCRIPTION OF DISCREPANCY:
. KEY-LOCK SWITCHES DO REQUIRE IMMEDIATE ACTUATION DURING PLANT OPERATION. (CRD SCRAM DISCHARGE BYPASS & RESET KEYLOCKS-KEYS ARE ALWAYS IN LOCK.)
Q N/ RECOMMENDATIONS: GSU OPERATIONS POLICY WILL ADDRESS THIS ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/22/04 HED N O . :: 288 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
--------_--------_---------=-- --- _
- - - - - - - - - - - - - - - . - _ _ - - - - - - - - - = - - - - - - - - -
DATA COURCE: DWR OWNERS GROUP CHECKLIST NO.: C1.1 CHECULIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P601-18 PANEL / WORKSTATION NO. P601-19 PANEL / WORKSTATION NO. P601-22
------------------------=
DESCRIPTION OF DISCREPANCY: ANNUNCIATORS ARE NOT GROUPED BY SPECIFIC SYSTEM RECOMMENDATIONS:
- OPERATIONS EVALUATED THE ANNUNCIATOR ARRANGEMENTS AND FOUND THEM TO BE APPROPRIATE. NO FURTHER ACTION REQUIRED.
ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE ATE / / FDDR# ISSUE DATE / /
---------------------------------------------------------------_ __ -=---------- i CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT i) N' DATE: 02/27/04 FiEEI) b4 C3 . s 25 c7 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _-_-----_-_-__- . . - - - _ = _ - . . -_=- - - = = - ___-- - ====-- -_-______ DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: C1.1 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P800-85A ( 1.) _ _ _ - _ _ _ - = - - - - - =---__--- _ ======_----== - ------____== _---_____-- DESCRIPTION OF DISCREPANCY:
. CONTAINMENT PENETRATION ANNUNCIATORS SHOULD BE LOCATED IN INSERT 83A OR 84A RECOMMENDATIONS:
FURTHER EVALUATION HAS DETERMINED THAT PRESENT LOCATION IS PROPER. NO ACTION. [h s_s ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 . IMPLEMENTATION SCHEDULE: O m
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/D4 HED N O . :: 304 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C1.3 CHCCFLIST AREA: ANNUNCIATORS PANCL/ WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32 PANEL / WORKSTATION NO. P601-16 DESCRIPTION OF DISCREPANCY: ANNUNCIATORS SEGREGATED ARC NOT GROUPED SUCH THAT WARNING AND DIAGNOSTIC ALARMS ARE RECOMMENDATIONS: ALARMS WILL DE COLOR CODED FOR PRIORITIZATION. GROUPING IS ADEQUATE. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDINO 5% POWER O 1 l l
HUMAN ENGINEERING DIBCREPANCY RECORD .a RIVER BEND NUCLEAR PLANT DATE: 02/23/04 F1EE E) bJ C3 . s d& dF eb REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE ' __________________________==_ . = = - - - - -- ___-... =-- _____ -- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C2.1 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P600-5 PANEL / WORKSTATION NO. P600-6 _________________________________________-- =====___ ___--- === ____________
.., DESCRIPTION OF DISCREPANCY: , ALARM WINDOW IS NOT CONSISTENT IN NOMENCLATURE, USE OF ACRONYMS, ABBREVIATIONS, ETC. (INSERT 6A SRM DETECTOR RETRACTED NOT PERMITTED, SHOULD READ RETRACT.) (INSERT 4A-USE RECIRC INSTEAD OF RCIRC.)
O b RECOMMENDATIONS: COMPARE TO STANDARD ABBREVIATIONS LIST AND CHANGE AS APPROPRIATE. ACTION: APPROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER iO %/
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BE.ND NUCLEAR P L AN'T DATE: 02/27/84 HED NO.a 98 REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C2.1 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P863-72A ( 1.) ANN #0579 ( 2.) ANN #I179 PANEL / WORKSTATION NO. PB63-71A ( 1.) ANN #1179 DESCRIPTION OF DISCREPANCY: THE ABBREVIATIONS "U" AND "IFTS" ARE AMBIGUOUS RECOMMENDATIONS: VERIFY CONFORMANCE WITH DESIGN CONVENTIONS AND CHANGE AS REQUIRED. ACTION:
, APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _ _ _ _ _ _ _ _ . _ _ _ _ _ - = = = _ _ _ - = = = = _ _ . ___ . _______________________ ______ _ CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER O
1 1 i HUMAN ENGINEERING DISCREPANCY RECORD
,m RIVER BEND NUCLEAR PLANT I !
DATE: 02/27/04 HED NO.a 328 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE _______________________________==- == == =____________=- --___________ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. C2.2 CHECKLIST AREA: ANNUNCIATORS PANCL/ WORKSTATION NO. PO63-76
,' ________________________=-- _____________________________________ _==_____
DESCRIPTION OF DISCREPANCY: LEGENDS ON ALARM WINDOWS ARE NOT CONSISTENT IN TYPE STYLE AND THE APPLICATION
... OF TYPE SIZE.
RECOMMENDATIONS:
. MAKE ALARM WINDOWS CONSISTENT IN TYPE STYLE AND SIZE O ACTION:
TEMPORARY LEGENDS WILL BE REPLACED TO BE CONSISTENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
J
HUMAN ENGINEERING DIBCREPANCY RECORL RIVER BEND NUCLEAR PLANT DATE: 02/22/84 F4 EII) P4 03 - a 2 E3 c7 REVIEWER: LIDDLE /MATCON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ___=----------- . --------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C2.5 CHCCULIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P601-19
-------------------------- _ _ _ _ _ -. - _ = - _ _ __===-------- - - - - - - - - _ - ===
DESCRIPTION OF DISCREPANCY: ANNUNCIATOR FOR STANDBY LIQUID TANK / TEMP HI/ LOW IS NOT SUCCINCTLY WORDED RECOMMENDATIONS: REMOVE "/" PETWEEN TANK AND TEMP ON ANNUNCIATOR h ACTION: APPROVED BY GSU MANAGEMENT.
. ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
---------------------- --- -=
_ - - = - - - - - ==------- 1 ! CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD n RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO.a 329 REVIEWER: SCHROEDER/MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECHLIST NO. C2.5 CHECKLIST Ar<EA: ANNUNCIATORS l PANEL / WORKSTATION NO. P863-76 DESCRIPTION OF DISCREPANCY: NO LABELS ARE PROVIDED ON THE INOPERABILITY MATRIX. ALSO, WINDOW LABEL FOR "STBY SERVICE WTR PUMP HOUSE X-H TEMP SWGR RM A" IS UNCLEAR. ret:OMMENDATIONS: LABEL HAS BEEN ADDED SINCE SURVEY. CHANGE WINDOW TO BE CONSISTENT WITH f v) STANDARD CONVENTIONS (X-H TO EXT HIGH). ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / i CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATC 02/22/04 HED NO. 2 cP O REVIEWER: LIDDLE /MATSON/b! SHOP TRACKING STATUS: SCHEDULE PHASE DAYA SOURCE: BWR OWNERS GROUF-CHECKLIST NO.: C2.7 CHCCI: LIST AREA: ANNUNCIATORS PANCL/ WORKSTATION NO. P601-19A DESCRIPTION OF DISCREPANCY: MULTIPLE CHOICE ANNUNCIATORS ON THIS PANEL SUCH AS SLC TANK LEVEL AND TEMP RECOMMENDATIONS: NO ACTION. LEVEL METER IS ON 19B INSERT. OPEPATOR ACTION WILL LE THE SAME h WHETHER TEMP. IS HIGH OR LOW. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATC / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD (^ RIVER DEND NUCLEAR PLANT DATE: OC/24/04 HED N O :: 232 REVIEUER: LIDDLE /MATSON/BISHCP TRACKING STATUS: SCHEDULE PHASE
------------------------------------------- _---------------------=_ =------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. C2.7 CHCCKLIST AREA: ANNUNCIATORS PANCL/ WORKSTATION NO. P808-81A
---------- -====--- --__ - - _ -- --- ==- ------- __---= .-
DESCRIPTION OF DISCREPANCY: ANNUNCIATOR ON ROW 'B' AND COLUMN '12' IS A COMMON ALARM FOR TWO DIFFERENT
. COMPRESSORS RECOMMENDATIONS:
CHANGE TO TWO SEPARATE ANNUNCIATCRS. O ACTION: NO ACTION. REGARDLESS OF WHICH COMPRESSOR IS ANNUNCIATING, OPERATOR ACTION (SEND NEO TO EQUIPMENT) WILL BE THE SAME. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
-=-- = -====-
_ _== = _ - ---- ------ ----- _ _ - CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR P L_ A N'T DATE: 02/20/84 HED N O . := 305 REVIEWER: LIDDLE /MATSON/DISHOP TRACKING STATUS: SCHEDULE PHASE DATA COURCE: DWR OWNERG GROUP CHECt: LIST NO.: C2.7 CHECI: LIST AREA: Af 4NUNCI ATORS PANEL /WORI- STATION NO. P877-31 PANEL /WORl; STATION NO. PO77-32 PANEL /WORF: STAT ION NO. P601-16 __---____________ _-___--_--__-__--_- _=- - _ - - _ _ - - - = - - - - - _ - _ - - -__=____-- DESCRIPTION OF DISCREPANCY: DIESEL FUEL OIL STORAG" TANI: IS A MULTIPLE CHCICE ALARM HI/LO ' RECOMMENDATIONS: OPERATOR ACTION WILL DE THE SAME (SEND SOMEONE TO DIESEL) FOR EITHER ALARM. NO ACTION. ACTION: APPROVED LiY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O l l l
I HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT 7~
'% DATE: 02/22/84 HED NO. :: 282 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
--------------------------. _-- ------ ----- _ __=--- _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. C2.8 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P601-19 _=---- --- - _ - - - - = - - - - _ - _ . = DESCRIPTION OF DISCREPANCY: ANNUNCIATOR A-11 " MAIN STEAM LINE HIGH RADIATION" IS NOT CODED RED IN KEEPING WITH CONTROL ROOM CONVENTIONS RECOMMENDATIONS: CODE ANNUNCIATOR A-11 RED O ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DHTE / / FDDR# ISSUE DATE / /
-----------------=- =_-- -- -- ._
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I O
I J HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/C3/04 F4 EE E) P4 C3 . = d4551 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDfjLE PHASE
-------------------_----_--------- -- -------==---- - -_------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C5.6 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. GENERIC ( 1.)
- - - - - - . . - - - - - - - - - - - - - - = - - . _------------- - _ - -
DESCRIPTION CF DISCREPANCY: ALARM RESPONSE IS NOT PROVIDED A "FIRST-OUT" FEATURE OR DUAL RESET FOR INFORMATION RETRIEVAL HIGH PRIORITY ALARMS. RECOMMENDATIONS:
- DOTH SPDS AND PMS HAVE SEQUENCE OF EVENTS FEATURE FOR PRE-SELECTED HIGH PRIORITY ALARMS. NO FURTHER ACTION REQUIRED.
ACTION: APPROVED BY GSU MANAGEMENT Et4DCR # ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------- . = . _ - - - . _.
1 CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLAN"T 7 ' 1 DATE: 02/29/84 HED N O := 354 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE PHASE
-----------------== - - - = - - - - - - = . -
_ = = = - = _ _ _ - - - _ _ = _ _ = _ - - DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO. E4.11 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC i ( 1.) 1
- - - - - - - - - = = - - - _ - _ - _ _ - - - _ - - . -= -___ -
DESCRIPTION OF DISCREPANCY:
.. SOPS AND GOPs DO NOT INTEGRATE CHARTS, DIAGRAMS, AND GRAPHS INTO BODY OF PROCEDURE AS NEEDED TO DIRECTLY SUPPLEMENT STEPS.
RECOMMENDATIONS: l GDP*S DO UTILIZE CHARTS / GRAPHS TO SUPPLEMENT STEP
S. PROCEDURE
S WILL BE REVIEWED TO ENSURE THAT THE CHARTS ARE PROPERLY REFERENCED. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
--------------. __--=- = - - - - - = _ - - -- - .==_. .__ __---_-_ . CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN ENGINEERING DTSCREPANCY RECORD RIVER EEND NUCLEAR PLANT DATE: 02/29/84 F4 EE I) PJ C3 . = 25:5 db REVIEWER: SCHROEDER TRACKING STA1US: SCHEDULE PHASE
--_-------------------_---__-====-- -_-- - - - - - - _ -
- - - - - - - =-----------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.16 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( 1.)
---------- --..--- _==------- --
DESCRIPTION OF DISCREPANCY: CONTINGENCY ACTIONS OR CONDITIONAL INSTRUCTIONS ARE NOT GENERALLY PROVIDED IN SOPS. RECOMMENDATIONS:
- THESE INSTRUCTIONS ARE ADDRESSED IN ARP*S AND AOP*S . NO FURTHER ACTION REQUIRED.
ACTION: APPROVED BY GEU MANAGEMENT. E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
14UMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT (]
\_/
DATE: 02/C9/84 HED NO.s 358 i REVIEWER: SCHROEDER , TRACKING STATUS: SCHEDULE PHASE
=
-- = _ .
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.18 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC ( 1.) _ - - _ _ _ - - - - . = _ -_ --
---=---==--------- --
DESCRIPTION OF DISCREPANCY:
. NOT ALL PROCEDURAL STEPS LIMIT OPERATOR ACTIONS TO THOSE THAT ARE ESSENTIAL
, AND EFFECTIVE.
.- RECOMMENDATIONS:
NO CHANbd TO PROCEDURES. STEPS PROVIDE ACTIONS AS SPECIFIED IN EPG*S WITH FEW [} N- EXCEPTIONS (AS NOTED ON EXCEPTION FORMS). ACTION: APPROVED BY GSU MANAGEMENT. EI4DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
l () l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/84 HED NO. = 254 2 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = _ = _ = - - _ _ - - - - - - _ _ _ - - - - - - - - - - - _ - - _ - - - - - - - -
DATA SOURCE: E4WR OWNERS GROUP CHECKLIST NO.: 592.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORKSTATIOl1 NO. PO69 ( 1.)
--------------------------------------- _ _ _ _ - - - - . . _ - - = _ _ _ - - - - - - - - - - - - - - - - - - -
DESCRIPTION OF DISCREPANCY: THE LABEL COVERS PART OF THE RECORDER WINDOW AND OBSTRUCTS THE VISIBILITY OF THE SCALE ON THE PLANT CONDUCTIVITY RECORDER. RECOMMENDATIONS: MOUNT LADEL WHERE VISIBILITY IS NOT OBSTRUCTED. ACTION: APPROVED BY GSU MANAGEMENT. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
----_-- ----_-_-- - - - - _ - = _ - - - . . _ _ _ _ _ _z_-
CRITICALITY RATING: 2 i IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
l HUMAN ENGINEERING DISCREPANCY RECORD r"% RIVER BEND NUCLEAR PLANT DATE: 02/C3/84 HED NO m 505 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHACE
--------------------a-------:_-- .__-_== - - - - -
DA1A SOURCE: BWR OWNERS GROUP CHECKLICT NO.: SB3 CHECKLIST ARCA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) _= =-- _ - - - _- N' DESCRIPTION OF DISCREPANCY: PROCEDURAL OR DESIGN PROVISIONS NOT IMPLEMENTED TO PREVENT INTERCHANGING INDICATING LIGHT LENSES. LIGHT POSITIONS'AND PROXIMITY PRECLUDES INTERCHANGING PROBADILITY OF INTERCHANGE LO!4 DUE TO CONFIG OF LIGHT PLACEMENT. CONSISTENT POSIT PRECLUDES INTRCH RECOMMENDATIONS: AS STATED IN THE ABOVE DESCRIPTION, INDICATING LIGHTS ARE CONSISTENTLY POSITIONED (ie. L/R GREEN / RED) THROUGHOUT THE RBS CONTROL ROOM. INDICATOR LIGHTS ARE PLACED IMMEDIATELY ABOVE THEIR, ASSOCIATED CONTROLS SUCH THAT THE CONTROL POSITION SELECTED IS EASILY CORRELATED WITH THE PROPERLY COLORED INDICATING LIGHT. DURING TRAINING ON THE RBS SIMULATOR, LIGHT LENSES ARE PURPOSELY INTERCHANGED BY THE INSTRUCTORS (WITHOUT OPERATORS KNGWLEDGE).THIS EMPHASIZES THE IMPORTANCE OF VISUALLY COMPARING CONTROL POSITION WITH INDICA 10R LIGH1 COLOR AND THE NEED TO USE SECONDARY INDICATIONS. THE COMBINATION OF THESE FACTORS PROVIDES ASSURANCE THAT THE INTERCHANGING OF INDICATOR LIGHT LENSES, IF IT WAS TO OCCUR, WOULD NOT
, ADVERSELY EFFECT PLANT OPERATIONS.
ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
---------------------- ==-___= _
_ _ = - CRITICALITY RATING: 2 ( IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPAt4CY RECORD RIVER BEND NUCL EAR PR-.A N T O DATE: 02/23/84 F4 EE E) DJ C3 . = 55 el C5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
---------------------------------------=- ------------- -------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SD4.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P6SO
---------------------- -- =----- --- -
___ ====------ DESCRIPTION OF DISCREPANCY: KEY-OPERATED SWITCHES ARE NOT USED ONLY WHERE APPROPRIATE (i . e. TO PREVENT UNAUTHORIZED CONTROL ACTUATION.) RECOMMENDATIONS: NO ACTION. OPERATORS ARE WELL TRAINED ON THE USE OF THESE SWITCHES. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _____===- == -- CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: I O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct-.E A R C, DATE: 02/23/84 PL. A N T HED N O _ :: 548 REVIEWER: SPDS TRACKING ETATUS: SCHEDULE PHASE
- - - - - - - - - _ - - - _ - _ =-_-- --- - - - - _---- - - _
DATA SOURCC: OTHER CHECKLIST NO.: SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION NO. SPDS DESCRIPTION OF DISCREPANCY: PRIMARY CONTAINMENT RADIATION IS NOT PRESENTLY AVAILABLE FOR USE BY THE SPDS DATABASE. RECOMMENDATIONS: NO ACTION. INFORMATION AVAILABLE ON DRMS. SEE P.31 OF REFERENCE "K" IN
SUMMARY
REPORT FOR FURTHER DISCUSSION. ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIECRE PANCY RECORD RIVER BEND NUCLEAR PLANT DATC: 02/23/84 HED N O - :: 549 REVIEWER: SPDC TRACKING STATUS: SCHEDULE PHASE l l DATA SOURCC: OTHER CHECKLIST NO. SPDS CHECLLIC1 AREA: CHECl;L I 5'l AREA NOT FOUND pat 4EL/WORKSTATIOt1 NO. SPDS
= - _ - - - - - - - - - - -
DESCRIPTION OF DISCREPANCY:
. RDS HAS COOLANT. NO REAL-TIME MCASURE OF RADIATION LEVEL IN CIRCULATING PRIMARY RECOMMENDATIONS:
NO ACTION. TECHNICAL JUSTIFICATION ON P. 32, 33 OF REFERENCE "K" IN
SUMMARY
REPORT. ACT IOt4: APFROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR4 ISSUE DATE / / _ _ - - - - - - - - = - - CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: l l O
HUMAN ENGINEERING DISCREPANCY RECORD i l RIVER BEND NUCLEAR PLANT ' DATE: 02/23/84 HED NO a 550 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
------------=-= - _ - - - - - = _ - - - . __ -- .---------
DATA SOURCE: OTHER CHECKLIST NO. SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUNT PANEL / WORKSTATION NO. SPDS DESCRIPTION OF DISCREPANCY: THERE IS NO INSTRUMENTATION TO CONTINUOUSLY MONITOR THE CONTAINMENT AND
.,, DRYWELL FOR OXYGEN CONCENTRATION.
RECOMMENDATIONS:
, NO ACTION. TECHNICAL JUSTIFICATION ON P.34 OF REFERENCE "K" IN
SUMMARY
REPORT. ACTION: APPROVED BY GSU MANAGEMENT. E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / /
- - _ = = = - - --
CRITICALITY RATING: 2
, IMPLEMENTATION SCHEDULE:
l l l t l l l l l
i HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N"T" DATE: 02/23/04 F4 EE I) b4 03 - z 25 "5 :2 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
--..---------------------------------- --= -
DATA COURCE: OTHER CHECKLIST NO.: SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION NO. SPDS DESCRIPTION OF DISCREPANCY: RBS DOES NOT FURNISH THE SOURCE RANGE (SRM) AND INTERMEDIATE RANGE (IRM) NEUTRON DETECTOR DRIVE POSITIONING MODULES WITH CLASS 1E POWER. RECOMMENDATIONS: SEVERAL SOLUTIONS ARE PRESENTLY BEING EVALUATED BY GSU TO ADDRESS THIS
' CONCERN. DUE TO THE SUBMITTAL DEADLINE FOR THIS REPORT, THE FINAL DETAILED TECHNICAL EVALUATION BY GSU, S & W AND GE COULD NOT BE COMPLETED TO BE INCLUDED IN THIS REPORT.
ACTION:
, SUBMIT RESOLUTION PLAN PRIOR TO FUEL inen, t
ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _ _ --- ==--
- ----------_- -_- _. ______=
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 9
IIUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT l b) DATE: 02/23/84 HED NO. 553 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
-- =------------
DATA SOURCE: OTHER CHECKLIST NO.: SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUND 1 PANEL / WORKSTATION NO. SPDS
-- -------= __- _
. . = = _= - ___= .----
DESCRIPTION OF DISCREPANCY: STATUC OF HPCS DG-THE VARIABLE WHILE DISPLAYED IN THE CONTROL ROOM IS NOT
. CONTAINED WITHIN THE SPDS DATABASE.
RECOMMENDATIOP.S NO ACTION. TECHNICAL JUSTIFICATION ON P.39 OF REFERENCE "K" IN
SUMMARY
REPORT. (sx ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
1 l 1 1 HUMAN ENGINEERING DISCREPANCY R E C ol:CD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 F4 EE E) DJ C3 . m 55 55 77 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ = _ - - ---
- == -- -_ -=
DATA SOURCE: OTHER CHECKLIST NO.: SPDS CHECl: LIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION NO. SPDS
= = _ - =--- - - - = - - - - - ---
- - - - -- -- --- = - - -
DESCRIPTION OF DISCREPANCY: MSIV LEAKAGE CONTROL SYSTEM PRESSURE DOES NOT APPEAR IN THE SPDS DATABASE. RECOMMENDATIONS: NO ACTION. TECHNICAL EVALUATION ON P.43 OF REFERENCE "K" IN
SUMMARY
REPORT. ACTION: APPROVED BY GSU MANAGEMENT. . ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - = = - _==- __= _ -. - =- -
_ _ . __ ==---__-- CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BECN D NUCt. EAR Pt. ANT rN U DATE: 02/23/84 HED NO = 558 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE DATA 80URCE: OTHER CHECKLIST NO.: SPDS CHECKLIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION NO. SPDS DESCRIPTION OF DISCREPANCY: MAIN STEAM LINE FLOW IS NOT MONITORED BY THE SPDS DATABASE. RECOMMENDATIONS: THIS VARIABLE IS HVAILABLE IN THE SPDS DATA BASE (C33EA013 THROUGH s C33EA017).THIS INFORMATION CAN BE USED FOR DIAGNOSTIC PURPOSES TO IDENTIFY THE INITIATING EVENT AND ALSO TO INDICATE THE AVAILABILITY OF A RESTORED POWER CONVERSION SYSTEM. THEREFORE, NO DESIGN CHANGE IS NECESSARY. ACTION: APPROVED BY GSU MANAGEMENT. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
i GUTE SIRTES ITTILITIES COMPANY RIVER DEND S'IRTION 7.3 PIGDRITY III MEES O I l l 7-4
l HUMAN ENGINEERING DIBCREPANCY RECORD EtIVER BEND NUCLEAR PLANT HED NO 841
) DATE: 07/25/84 l
REVIEWER: BISHOP /HOWELL TRACKING STATUS: SCHEDULE PHASE
----------------- -== _--- - _- --
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: PANEL / WORKSTATION NO. C61-POO1 DESCRIPTION OF DISCREPANCY: (SCENARIO E/ SEQUENCE 550) THE TASK / SUBTASK SAYS REQUEST AUX OPERATOR TO VERIFY REACTOR RECIRC PUMPS RUNNING ON SLOW SPEED. HOWEVER,THERE IS NO DIRECT INDICATION OF RECIRC PUMPS RUNNING IN SLOW SPEED. RECOMMENDATIONS: NO ACTION. THERE ARE SEVERAL AVAILABLE MEANS BY WHICH THIS CAN BE DETERMINED BY THE OPERATOR ACTION: APPROVED BY GSU MANAGEMENT
)
ELDCRM ISSUE DATE / / FDDRM ISSUE DATE / / _ - - - _ - - = - - = = - - - - - - -- - -- CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l t ( O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCt. EAR PI_ A N T" O DATE: 08/10/04 HED N O ., s 844 REVIEWER: BISHOP /HOWELL/MCGHEE TRACKING STATUS: SCHEDULE PHASE
-------------------------------=---- __--- -------===
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: PANEL /WORKSTATN NO. DRMS ( 1.) uRMS DIGITAL RADIATION MONITORING SYSTEM
--------------------------- -=
DESCRIPTION OF DISCREPANCY: (SCENARIO A/ SEQUENCE 680) THE TASK / SUBTASK SAYS OBSERVE LEAKAGE CONTROL (DRYWELL AND CONTAINMENT RADIATION LEVEL). HOWEVER, THE PRESENT INFORMATION IN CR DOES NOT PROVIDE SUFFICIENT INFORMATION FOR THIS TASK. RECOMMENDATIONS: THIS HED IS BASED ON THE DRMS C.T TEM IN THE SIMULATOR WHICH WAS DEVELOPED PRIOR TO THE PURCHASE OF THE plt.e4T SYSTEM. THE PLANT DRMS WILL MONITOR THE PARAMETERS AS STATED IN THE FSAR WHICH INCLUDES DW L CONTAINMENT RAD LEVELS. NO FURTHER ACTION ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-----------.------------------------ -- _.. = = - - - - - ------ =- _ ----
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD PLANT f') Q RIVER BEND NUCLEAR DA'I E : OC/06/04 HED N O ., a 575 REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
--_-_-_______________-_-__--- _=-
DATA SOURCE: OPERATIONAL EXPERIENCE REVIEW CHECKLIST NO.: PANEL / WORKSTATION NO. LER-373-83098 ( 1.) ___---_---------------___--------= -_= ___-_ DESCRIPTION OF DISCREPANCY: LER(LASALLE COUNTY-1)AN OPERATOR INADVERTENTLY REMOVED FROM SERVICE A SERVICE WATER PUMP AND DID NOT TAKE SAMPLES PER T.S. 3.3.7.10. THE EVENT WAS CAUSED DY AN OPERATOR HANGING A TAG ON THE WRONG PIECE OF EQUIPMENT (VALVES WERE NOT LADELED PROPERLY) RECOMMENDATIONS: GSU OPERATIONS HAS DEVELOPED AND IS IMPLEMENTING A PROGRAM TO ACCURATELY TAG EVERY VALVE (UP TO ROOT VALVES) AT RBS. THIS PROGRAM WAS DEVELOPED IN ( RESPONSE TO THE ABOVE ST ATED TYPE OF ERROR. ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / __ - =
-------_==-. -
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 4 1 xsl
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 08/14/84 F4EEE) PJ C3 . p 7P 7F CP REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
---__ ___=- _-- =-= -_ .------------
DATA SOURCE: NONE CHECKLIST NO.: PANEL / WORKSTATION NO. LER-387-83022 ( 1.) _ -----=____=. _ -------------- DESCRIPTION OF DISCREPANCY: TECH SPEC 3.3.7.5 ENTERED LCO DUE TO POOR STOREROOM MIN INVENTORY AND LOW PRESSURE CONDITION OF GAS BOTTLE, ALLOWED BY LACK OF PERIODIC CHECKING RECOMMENDATIONS: ALL BOTTLES WILL BE COVERED BY OPERATIONS ROUTINE ROUND SHEETS. THE INVENTORY SYSTEM DEVELOPED USES MIN / MAX VALUES FOR STOCKING. ACTION: APPROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / __-- = _ - - _ = - ._-------
---------------------------------------- _ = _
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O
HUMAN E N G I N E E R I NtiB DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N*T* 7 HED NO.a 843 DATE: 07/25/84 REVIEWER: HOWELL/DISHOP/MCGHEE TRACKING STATUS: SCHEDULE PHASE
- = __ _ _ - _ ___
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: PANEL / WORKSTATION NO. P680 ( 1.) 1CNM-P145A CONDENSER VACUUM METER ( 2.) 1CNM-P145B COMPONENT DESCRIPTION NOT FOUND
-__--_---_------_--_-----_____=___-__ -___-___--______-_____.
DESCRIPTION OF DISCREPANCY (SCENARIO A, SEQUENCE 670) THE TASK / SUBTASK SAYS INFORM CREW CONDF.NSER VACUUM IS AT 24 INCHES OF HG. HOWEVER, METER'S 1CNM-P145(A & B) ARE LABELED " INCHES HG. ABS". RECOMMENDATIONS: CHANGE TO INCHES HG. r (m)h ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct-.E A R PL ANT DATE: OC/23/84 HED NO = 569 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL / WORKSTATION NO. P680-4 DESCRIPTION OF DISCREPANCY: RESET DUTTON LIGHTS NEED LADEL TO INDICATE FUNCTION. RECOMMENDATIONS: LADEL RESET BUTTON LIGHTS TO INDICATE FUNCTION ACTION: APPROVED BY GSU MANAGEMENT S ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER e
i HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT [ml DATE: 02/23/04 H Ef D NO.= 571 REVIEWER: BURGY/ CHASE TRACKING STATUS's SCHEDULE PHASE _________________________________________________________=--- - - - - ____________ DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: PANCL/ WORKSTATION NO. P680-5A e _____-- - - - -- ___ ._= _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - _ _ -- DESCRIPTION OF DISCREPANCY: ANN. RECIRC. PUMP TRIP SYS. s 1ANUAL BYPASS (&B) SHOULD BE LOCATED ON INSERT 4A(SHOULD ALSO BE RED) RECOMMENDATIONS: ANNUNCIATOR CAN NOT BE MOVED TO 4A SINCE THIS INSERT IS FULL. COMPARE COLOR + CODING CONVENTION TO THIS WINDOW & CHANGE COLOR AS APPROPRIATE ACTIOi4: w (~} kJ APPROVED BY GSU MANAGEMENT 1 E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I 1 l i
'i
1 RECORD HUMAN ENGINEERING DISCREPANCY RIVER BEND NUCLEAR PLANT HED NO 570 DATC 02/23/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL / WORKSTATION NO. P680-6 DESCRIPTION OF DISCREPANCY: SRM METERS TOO SMALL SHOULD BE LOCATED NEAR SRM CONTROLS. RECOMMENDATIONS: METERS ARE IN PRESENT LOCATION AND SIZE DUE TO SPACING CONSTRAINTS NO ON P-6SO. ADDITIONALLV, THEY ARE LOCATED NEXT TO THEIR CORRESPONDING RECORDER. FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIBCREPANCY RECORD g RIVER BEND N U Ct-.E A R PL ANT U HED NO.s 572 DATE: 02/23/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL /WORKSTATIOf4 NO. P680-6C
---=_. ---- ---
---=_. _----- __.
- - - - - - = - - = - - _ - _
DESCRIPTION OF DISCREPANCY: i IRM/APRM RECORDERS RED / BLUE PENS DO NOT CORRESPOND LEFT TO RIGHT WITH I ! CONTROLS A-H. RECOMMENDATIONS: COLOR CODE CONTROLS TO CORRESPOND TO DISPLAYS ACTION: APPROVED BY GSU MANAGEMENT O ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _- - - - - - - - - - - - - _ - - - - ._ -=. CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 HED N O . :: 573 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
------------------------------------------ __ _ _ - - - - - - - _ = - - - - - - - - _ - - - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECt: LIST NO. : PANEL /WORKCTATION NO. P680-6C DESCRIPTION OF DISCREPANCY: LABEL MISSING ON IRM CH-D PUSHDUTTON (DNSC/ BYPASS LABEL) RECOMMENDATIONS: , ADD LABEL ON IRM CH-B PUSHBUTTON ACTION: APPROVED BY GSU MANAGEMENT O ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATICN SCHEDULE: PRIOR TO EXCEEDING 5% PCWER O
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT ! e I i b4 C3 . 7F C) F4 EE E)
'~
DATEt 02/27/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BARKS / CHASE /SHANKLE __--_--_=_ ___________ __=--_-___----__ ___
--_--------_---_-- _=
DAT A SOURCE: BWR OWNERS GROUP CHCCKLIST NO. PANEL / WORKSTATION NO. P808-85B ( 1.) _=
---=_ --------_ -_---_-_--__
DESCRIPTION OF DISCREPANCY: THE MIMIC OF THE ELCCTRICAL SYSTEM IS INCORRECT AND CONTAINS REFFERENC
" UNIT 2" RECOMMENDATIONS:
CORRECT MIMIC TO SHOW CORRECT ELECTRICAL SYSTEM i 1 . ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
------ --_ -_ -_-- =
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l I l O
DISCREPANCY RECORD HUMAN ENGINEERING i RIVER BEND NUCL EAR PI_.A N T l F4 EEI) bJ C3 . = 2525 C5 DATE: 02/27/D4 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
---------__- - ---------=__
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: PANEL / WORKSTATION NO. PB63-76
----==.
- -------------------- - ---------=--_
DESCRIPTION OF DISCREPANCY: THIS PANEL MAY NEED A DIVISION 3 DSL GEN CONTROL ROOM VENT MANUAL BYPASS INDICATION SWITCH. RECOMMENDATIONS: INVESTIGATE THE NEED FOR A DIVISION 3 GEN CONTROL ROOM VENT MANUAL BYPASS SWITCH ACTION: NO ACTION. EVALUATION COMPLETE. SWITCH NOT REQUIRED ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-_-_--_--_--____---_...---------__-_-------___-__--_--_-_-_-__----=_.- _______--
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
%j F4 EEI) BJ C3 . z E3197 DATE: 09/90/4 i
TRACKING STATUS: SCHEDULE PHASE REVIEWER: LINK _= _ - _
-------------------------------------=----
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: A CHECMLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: DNE OPERATOR SUGGESTS THAT THE POWER TRANSFER SWITCH FOR RPS (ALT SHOULD BE ON A FRONT PANEL. RECOMMENDATIONS: NO ACTION. PRESENT LOCATION IS ACCEPTABLE.
%./
ACTION: APPROVED BY GSU MANAGEMENT. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: t 9 O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT DATE: 09/19/84 F4 EEI) D4 C3 . = E3:225 REVIEWCRs LINK TRACKING STATUS: SCHEDULE PHASE
._--=--- _ ------ ----------
=-
DATA SOUrsCC: OPERATING PERSONNEL INTERVIEW CHECKLIST NO. A CHLCl. LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. GENERIC ( 1.)
--==_ -
DESCRIPTION OF DISCREPANCY: ONE OPERATOR SUGGESTS THAT MORE S.P. PHONES ARE NEEDED (AT PANELS) AND THC HAND HELD RADIOS WILL CAUSE INTERFERENCE (ACTIVATE CONTROLS) RECOMMENDAT IONS: THIS IS A SIMULATOR PROBLEM, NOT A CONTROL ROOM PROBLEM. S.P. PHONES ARE AVAILABLE ON ALL PANCLS IN THE CONTROL ROOM. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT. E t< DCR # ISSUE DATE / / FDDRM ISSUE DATE / /
=- -_ --- _- . - - _
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD ,- p RIVER BEND NUCLEAR PLANT
'._) ~
DATE: 02/23/04 HED NO- 366 REVIEWER: BURGY/CHTSE TRACKING STATUS: SCHEDULE PHASE DATA SOURbEn BWR JWNERS GROUP CHECKLIST NO. A1.1 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-2 PANCL/ WORKSTATION NO. P860-3 _=_ - - _ _ --==- - == _- __ DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION ARE NOT USED TO DISTINGUISH BETWEEN COMMONLY SHARED SYSTEMG RECOMMENDATIONS: INVESTIGATE DEMARCATION OF THE MENTIONED SYSTEMS ( ACTION: ADD DEMARCATION AS APPROPRIATE ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- = = - _ _ _ - - - - _ _ _ _ _ _ - -
_ = = = . - -------- _
---------------------=_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i l 1 l i
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 09/90/4 F4 EE I) P4 C3 . = E3 <> E3 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECVLIST NO.: A2 CHECALIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P845
==------------------------
DESCRIPTION OF DISCREPANCY: ONE OPERATOR SUGGESTED A MIMIC OF THE OFFGAS SYSTEM FLOW PATH WOULD BE USEFUL ON PB45. OTHER PANELS NEEDING MIMICS MENTIONED:- FW, AND RWCU. RECOMMENDATIONS: THE NEED FOR ENHANCEMENT OF THIS PANEL IS DOCUMENTED ON HED #785. APPROPRIATE ENHANCEMENTS WILL BE ADDED TO THIS PANEL. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / l
- - - - - = = - -
=-----------------
i CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
. . v. "
HUMAN' ENGINEERING DIBCREPfeNCY RECORD RIVER BEND NUCLEAR PLANT
- HED N O . :: 805 DATE: 09/98/4 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
- - - = = - - --------------------- =_-_
DATA SOURCE: OPERATING FERSONNEL INTERVIEW CHECKLIST NO.: A2 CHECELISl AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863
- -------==- - ----------- ------===-_ =_ __
DESCRIPTION OF DISCREPANCY: MIMIC TO 1 HVR-FLT2 SHOULD APPEAR AFTER MIMIC 1HVR*AOD143 ON P863 RECOMMENDATIONS: REVIEW MIMIC AND CHANGE IF REQUIRED. sj ACTION: APPROVED BY GSU MANAGEMENT. ESDCR# ISSUE DATE / / FDDRM ISSUE DATE / / _ - - - = - - - - - - - -
- _ - - - - - _ = - - _
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 9 DATE: 07/90/4 HED N O . :: GOO REVIEWER: LINF TRACKING STATUS: SCHEDULE PHASE
=--__ -
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECULIST NO.: A2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870 DESCRIPTION OF DISCREPANCY: PB70 IS CONFUSING (NO MIMICS) RECOMMENDATIONS: AS A RESULT OF THE DCRDR SURVEY, SPECIFIC AREAS ON THIS PANEL THAT REQUIRE MIMICS HAVE BEEN IDENTIFIED AND ARE ADDRESSED IN THIS
SUMMARY
REPORT. ACTION: APPROVED By GEU MANAGEMENT. Et<DCR # ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER O
l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT Iq) HCD NO- a ~5 8 2 DATC 02/03/04 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
= - - - - - - _ _ = - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.1 CHECKLIST AREA: PANCL LAYOUT AND DESIGN a PANEL / WORKSTATION NO. P680-2
--------------- - = .=-------- - _
DESCRIPTION OF DISCREPANCY: LINE OF DEMARCATION ARE NOT USED BETWEEN COMMONLY SHARED SYSTEMS RECOMMENDATIONS: DEMARCATE BETWEEN CONDENSATE AND HEATER DRAIN PUMPS.
\ ACTION:
APPROVED BY GGU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / l _------------ ---_--_== _ . _ _ - - I CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO CXCEEDING 5% POWER l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCtEAR PL AN'T HED NO. :: 606 DATE: 02/23/04 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO.: A2.10 CHECFLIST AREA: PANEL LAYOUT AND DESIGN PAtlEL/ WORKSTATION NO. PG70-56C PANEL / WORKSTATION NO. PO70-55C
---------_ __-=----------------- -- ------
DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ACE NOT IDENTIFIED WITH STARTING AND END POINTS. WATER SYSTEMS DIU 1 MISSING MINIC SEGMENTS, LOOSE SEGMENTS. RECOMMENDATIONS: ADD STARTING AND END POINTS AND REPLACE AND MISSING SEGMENTS ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDRH ISSUE DATE / /
------------------------- -- -------- _-- _. __-------._= =-- ---------------
CRITICALITY RATING 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
- - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - ~ - - -
r HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT ! V DATE: 02/24/04 HED N O . :: 208 REVIEWER: LIDDLE /NATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
= --------
! DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.11 l CHECVLIST AREA: PANEL LAYOUT AND DESIGN l PAf4EL/ WORKSTATION NO. P808-86 ( 1.) PANEL / WORKSTATION NO. P808-87 ( 1.) PANEL / WORKSTATION NO. P808-89 ( 1.)
- - - - - - - - - - - - - - - - - - - = -
---------- --------=_. _ _ - - -
DESCRIPTION OF DISCREPANCY: NORMAL AND PREFERRED 4160 VOLT BREAKERS HAVE GROUP OF SWITCHE3 THAT SHOULD BE O DEMARKED RECOMMENDATIONS: THESE SWITCHES ARE APPROPRIATELY LABELED, GROUPED & MINICED. NO ACTION ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _- ---- -------== --_ _= CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O 1
k HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND N U CI-.E A R P L_ A N T DATE: 02/28/84 HED N O :: 700 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
---------------------------------------------- ---------=__
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.11 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. PO63-74 PANEL / WORKSTATION NO. P863-7SC
- _ - - - - - - _ _ - - . _ - - - - - - - - - - - _ - - - - - - _ - - - - - - - - ___---_--_-==____=-----_-----__----
DESCRIPTION OF DISCREPANCY: THE LINES OF DEMARCATION ARE NOT USED TO INTEGRATE SWITCHES, PUMPS, MANUAL AND REMOTELY-OPERATED VALVES, ISOLATION PATHS, ETC.
- RECOMMENDATIONS
USC LINES OF DEMARCATION TO INTEGRATE SWITCHES, PUMPS, MANUAL AND REMOTELY-OPERATED VALVES, ETC. ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- ==----------.---- __ _=--- ____ =--------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
I l 1 RECORD HUMAN ENGINEERING DISCREPANCY [] RIVER BEND NUCLEAR PLANT
\_J F4 EEI) P4 C3 a ds 2 cP DATE: 02/23/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE
----_ -- --------_-_--------_- _=--
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO,3 A2.11 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. PG70-53C PANEL / WORKSTATION NO. PS70-54C DCSCRIPTION OF DISCREPANCY: MIMICS OR OTHER GRAPHIC LINES OF DEMARCATION, DISPLAYS ARE NOT ISOLATION INTEGRATE SWITCHES, PUMPS, MANUAL & REMOTELY OPERATED VALVES, PATHS, ETC. RECOMMENDATIONS: ADD LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS AS APPROPRI ATC ACTION: APPROVED BY GSU MANAGEMENT Et<DCRM ISSUE DATE / / FDDRM ISSUE DATE / /
- - = - - - -
---- -------------- _---- ==
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I m
DISCREPANCY RECORD F1UMAN ENGINEERING G RIVER BEND NUCLEAR PLANT FIE D NO.= 262 DATE: 02/23/84 TRACKING STATUS: SCHEDULE PHAGE REVIEWER: LIDDLE /MATSON/ BISHOP
-------------------------------------------------------------___=_-------------
DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO.: A2.11 CHECKLIST AREA: Pf4NCL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-54C
- _ - _ = _ . --------_---_----_-----
DESCRIPTION OF DISCREPANCY: TUhD GEN EH FL FMP A t< B ARE NOT ASSOCIATED WITH THEIR RESPECTIVE RESET / LOCKOUT CONTROLS RECOMMENDATIONS: ASSOCIATE RESPECTIVE CONTROLS WITH THEIR LOCKOUTS BY DEMARCATION ACTION: APPROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD p RIVER BEND NUCLEAR PLANT V DATE: 02/21/04 FiEE I) P4 C3 . = d2 C5 CP REVIEWER: BURGY/ CHASE TRACKINS STATUS: SCHEDULE PHASE
- - - . . - - - - - - - - - - - - - - - - - - - - - - - _ = = - - _ _ - -
DhTA SOURCE: BWR OWNERS GROUP ' CHECMLIST NO.: A2.12 CHECMLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P601-18C PANEL / WORKSTATION NO. P601-19C PANEL / WORKSTATION NO. P601-22C
------------------------------------------- _ . = _ - - - _ _ _ = _ ---- =_ - __--
DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT CONSISTENT IN APPLICATION OF SYMBOLS FOR PUMPS, VALVES AND OTHER PROCESS ELEMENTS. RPV SYMBOL DIFFERENT DUT LABELED ON 19C. RECOMMENDATIONS: SYMBOL IS ADEDUATELY LABELED. NO ACTION ACTION: APPROVED BY GSU MANAGEMENT E t,DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
-----------------------------------_ _==---------- ----- ==----------_--
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: W v l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/21/04 F4 EE I) b4 E3 . = d2 "5 77 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: NONE CHECELIST NO.: A2.12 CHEClLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORl: STATION NO. P601-20C PANEL / WORKSTATION NO. P601-17C DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT CONSISTENT IN APPLICATION OF SYMBOLS FOR PUMPS, VALVES L OTHER PROCESS ELEMENTS. RECOMMENDATIONS: REVIEW SYMDOLS & CHANGE IF REQUIRED ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / /
' 'DRM ISSUE DATE / /
CRITICALITY RATING: 3 } ! IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l i l 9
ENGINEERING DISCREPANCY RECORD HUMAN RIVER BEND NUCLEAR PLANT N'l .) FiEEI) b4 E3 . = d2 C) ~P DATE: 02/23/04 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- _ _ _ =--_____
_=----_-=_ _=_..
---_ -=----------------- __
DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO.: A2.12 CHECf: LIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-56C PANEL / WORKSTATION NO. P870-55C
------------------------------=___
DESCRIPTION OF DISCREPANCY: OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT CONSISTENT IN APPLICATION OF SYMBOLS FOR PUMPS, VALVES & OTHER PROCESS ELEMENTS.56C LABEL USED FOR CONDENSATE STORAGC TANK VS. SYMBOL.55C REACTOR PLANT WTR CLG PUMP LAPELS INSTEAD OF PUMP O RECOMMENDATIONS: NO ACTION. LABELS ARE APPROPRIATE ACTION: APPROVED BY CSU MANAGEMENT EI<DCRM ISSUE DATE / / FDDR# ISSUE DATE / /
--------------------- _= ---__-_--_--_-____---_________________-__________
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PI_.A N T DATE: 02/C3/84 HED NO. = 415 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
-------------------; -====---.---------------.-------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AC.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4C DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS, OR OTHER GRAPHIC DISPLAYS ARE NOT USED TO ENCLOSE RELATED DISPLAYS, RECOMMENDATIONS: ADD ENHANCEMENTS AS REDUIRED TO ENCLOSE RELATED DISPLAYS ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRF ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD
,Q RIVER BEND NUCLEAR PLANT N) HED NO.m 694 DATE: 02/27/84 REVIEWER: IsuRGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: DWR OWNERS GROUP 4
CHECFLIST NO.: A2.2 CHECKLIGT AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71 PANEL /WORKGTATION NO. P863-72 PANEL / WORKSTATION NO. P863-73C ' -- ------=. ----
-- . ------ -------------------------------------=__ - = - - = .
DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT USED TO ENCLOSE RELATED DISPLAYS. O RECOMMENDATIONS: ENCLOSE RELATED DISPLAYS USING LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS d i ACTION: APPROVED BY GSU MANAGEMENT f E&DCR# ISSUE DATE / / FDDR# 1ESUE DATE / / CRITICALITY RATING: 3 , IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i l i fO 1
ENGINEERING DISCREPANCY RECORD HUMAN RIVER DEND NUCLEAR PLANT HED NO. : 1 55 DATE: 03/0!/04 a REVIEWER: BARKS / CHASE /SHANLLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWT4ERS GROUP CHECKLIST NO.: A2.3 CHECLLIST ARE A: PANEL LAYOUT AND DESIGN pat 4EL/WORLGTATIOt1 NO. GENERIC ( 1.)
-_------_--_----------------------_-_-----------=_----=-------------------------
DESCRIPTION OF DISCRCPAt4CY: LINES OF DEMARCATION ARE NOT USED TO SEPARATE SIMILAR SUBGROUPS OR SYSTEMS RECOMMENJATIONS ADD LINES OF DEMAF: CATION AS APPROPRIATE. ACTIOt4: APPROVED BY GSU MANAGEMENT E t<DCR M ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O l
. _ . . . ~ . _ . - - . - - - . . _ _ - .
DISCREPANCY RECORD
. HUMAN ENGINEERING h RIVER BEND NUCLEAR PLANT
[G HED NO.z 240 DATE: 02/2*/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: LIDDLE /MATSON/ BISHOP DATA SOURCE: BWR OWNERS GROUP 1 CHECKLIST NO.: A2.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN j pat 4CL/ WORKSTATION NO. P870-52 DESCRIPTION OF DISCREPANCY: 1)MSTR 2)RW-OFFGAS 3) AIR EJECTORS NEED DEMARCATION TO ASSOCIATE STM SUPPLY TO RECOMMENDATIONS: I CHECK INTO WAYS OF ADDING DEMARCATION 1 !O ACTION: J ADD DEMARCATION AS APPROPRIATE a a I E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / ________________________--------------------------~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ 4 CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER f e ? i I
. , , - . . -- - _ - - .- - - _ . . . . . = . . - . _ _ - - - . - - . - - - - - . - , - - . . , - - - - - - . . - - - , . - - _ . , - - - - , . - - - - . -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT HED NO. :: 251 DATE: OC/C3/04 REVIEWER: LIDDLE /MATSON/BISHOF- TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECELIST NO. AC.3 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-54C PANEL / WORKSTATION NO. P600-4 PANEL / WORKSTATION NO. P600-5 PANLL/WORtCTATION NO. P680-6 DESCRIPTION OF DISCREPANCY: SIMILAR SUDGROUPS OF COMPONENTS ARE NOT SEPARATED TO ASSOCIATE THEM WITH THEIR SYSTEM RECOMMENDATIONS CHECl! INTO SEPARATING SIMILAR SUBGROUPS TO BE ASSOCIATED WITH THEIR SYSTEM ACTION: CODE TURDINE GENERATOR SEAL t< EXHAUST TO ASSOCI ATE THEM WITH THEIR DISPLAYS AND LINM PAIRS OF CONTROLS TOGETHER Et< DCR# ISSUE DATE / / FDDRM ISSUE DATE / / LRITICALITY RATING 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
'" HED NO.s 266 DATE: 02/21/84 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - . -- - - _ =--------___-___
DATA SOURCE: Bb'9 OWNERS GROUP CHECKLIST NO.. .2. 3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-55 PANEL / WORKSTATION NO. PB70-56
.---=_-- = == _ __. - _ _ _ _ _ _ _ - - _ - = = - - = = _ _
______-___-__--_____-_-= - - _ - _ - - _ _ _ _ DESCRIPTION OF DISCREPANCY: DISPLAYS ARE NOT SEPARATED BY SUBGROUP OR SYSTEM RECOMMENDATIONS:
. DISPLAYS ARE GROUPED DY SYSTEM AS CLOSELY AS DIVISIONAL SEPARATION ALLOWS. NO ACTION.
i ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
1 HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PL ANT DATE: 02/C3/04 FiEEE) D4 C3 . = db E31 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4C PANEL /WORVSTATION NO. P6SO-5C PANEL / WORKSTATION NO. P680-6C PANEL / WORE:.ST AT I ON NO. P 6 BO-- I OC DF3CRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT VISUALLY DISTINCTIVE BETWEEN EACH CTHER L PANEL / BACKGROUND EXCEPT FOR ANNUNCIATOR BUTTONS. RECOMMENDATIONS: NO ACTION. COLOR COORDINATION IS APPROPRIATE ACTION: APFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
=__=_
CRITICALITY RATING: 3 l IMPLEMENTATION SCHEDULE: I O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT l /~N w-] FiEEI) P4 03 . = e& db"5 DATE: 02/23/04 1 TRACKING STATUS , SCHEDULE PHASE REVIEWER: BURGY/ CHASE
- --------- l DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A2.6 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-1 DESCRIPTION OF DISCREPANCY:
LINES OF DEMARCATION, MIMICS, OR OTHER GRAPHIC DISPLAYS ARE NOT PERMANENT AND MAINTAINED. (ONE PIECE IS DETACHED AND PIECES ARE MISSING) RECOMMENDATIONS: MIMIC HAS BEEN CORRECTED SINCE SURVEY. NO FURTHER ACTION REQUIRED v ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _. _. =_ CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O .
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N"T~ O DATE: 02/22/84 HED NO. s 278 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-18 PANEL /WORFSTATION NO. F601-19 DESCRIPTION OF DISCREPANCY: INBOARD AND OUTBOARD SAMPLE DRAINS ARE NOT LAID-OUT TO SHOW FLOWPATH RECOMMENDATIONS: ADD MIMIC AS APPROPRIATE. ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
--------------------------------------------------_ -- =-----------------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
- ,')
FiEEI) PJ C3 a C2C)di '# DATE: 02/24/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: LIDDLE /MATSON/ BISHOP
. - - = - _ - - _ -
_ _ _ =-- _______= DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-86 ( 1.) PANEL / WORKSTATION NO. P808-87 ( 1.) PANEL / WORKSTATION NO. P908-88 ( 1.) _________________ -=-_________==------ - - - _ - - - - DESCRIPTION OF DISCREPANCY: /~N THE 4160 AND DC FEED IS NOT CLEAR UNNECESSARY EXTENSION OF BROWN BUS ON BBC (, TO RESET / LOCKOUT ACB27: MIMIC LINE CUT SHORT ON HIGH SIDE OF 1NJS-X1F 1380-480 XFMR: MIMIC BETWEEN INJS-SWG15 L SWG1T SHOULD BE ELIMINATED (NO TIE) RECOMMENDATIONS: MAKE THE NECESSARY CORRECTIONS ON THE MIMICS ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O l l l 1
, , . ,--,m
ENGINEERING DISCREPANCY RECORD HUMAN RIVER BEND NUCLEAR PLANT 9 DATE: 02/24/84 HED NO_ :: 2O5 REVIEWER: LIDDLE /MATSON/PISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: FANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-88C ( 1.) DESCRIPTION OF DISCREPANCY: MIMIC FOR FEED TO XFMR INJS-X1V SHOULD BE TIED TO 1NPS-ACB21 RECOMMENDATIONS: TIE THE MIMIC FOR FEED TO XFMR INJS-X1V TO 1NPS-ACD21 ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
RECORD HUMAN ENGINEERING DIBCREPANCY RIVER BEND NUCLEAR PLANT p} l 7 E35 HED N O . :: DATE: 09/19/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: CHASE / BISHOP / BARKS 4 _ - - - - - - - _ __=_ ------------------ ------- DAT A S0URCE: BWR OWNERS GROUP CHECKLIST NO. A2.7 CHECKLIST AREA: PANCL LAYOUT AND DESIGN PANCL/ WORKSTATION NO, P845 , DESCRIPTION OF DISCREPANCY: PANEL REQUIRES SYSTEM FLOW PATHS AND ARRANGEMENTS ARE NOT EASILY RECOGNIZED. LINES OF DEMARCATION, MIMIC & COLOR CODING TO IMPROVE OPERABILITY. RECOMMENDATIONS: ADD LINES OF DEMARCATION, MIMIC 84/OR OTHER GRAPHIC DISPLAYS TO MAKE SYSTEM FLOW PATHS EASILY RECOGNIZABLE. ACTION: AFPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
------- -----------------------==_--
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR Pt._ A N T DATE: 02/C7/84 F4 EE I) P4 E3 . = C5 1 4-REVIEWER: SCHROCDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: AC.7 CHECLLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PO63-76 DESCRIPTION OF DISCREPANCY: THE CHILLED WATER CONTROL MIMIC IS NOT LAID OUT SO THAT PATHS AND ARRANGEMENTS ARE ORDERLY AND EASILY RECOGNIZED. RECOMMENDATIONS: EVALUATE MIMIC AND CHANGE AS REQUIRED. ACTION: APFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER O
ENGINEERING DISCREPANCY RECORD HUMAN RIVER BEND NUCLEAR PLANT
~
(b DATE: 02/21/84 HED NO.m 647 REVIEWER: BLRGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - _ . - = = = - - - - - - - - - - - = = - _ - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. AC.9 CHECKLIST AREA: PANEL LAYOdT AND DESIGN PANEL / WORKSTATION NO. P601-21C
----------------------------------------------------- __ ==_=------------------ -
DESCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT CLEARLY MARKED WITH ARROWS TO SHOW DIRECTION OF " FLOW" RECOMMENDATIONS: . CLEARLY MARK TO SHOW DIRECTION OF FLOW O t \j ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / CDDR# ISSUE DATE / /
---------------------------- _=== ==---------------------==---==---------------
CRITICALITY RATING: 3 O IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PLANT DATE: 02/23/84 HED NO. :: 42 O 5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECKLIST NO.: A2.9 CHECELIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-56C PANEL / WORT. STATION NO. PO70-55C DCSCRIPTION OF DISCREPANCY: LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS ARE NOT CLEARLY MAREED WITH ARROWS TO SHOW DIRECTION OF " FLOW". WATER SYSTEMS DIU I MISSING MIMIC SEGMENTS, LOOSE SEGMENTS. RECOMMENDATIONS: O UPGRADE LINES OF DEMARCATION, MIMICS OR OTHER GRAPHIC DISPLAYS TO INCLUDE THE DIRECTION OF FLOW AND ADD ANY MISSING SEGMENTS ACTION: AFFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 57. POWER l
l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 7s I \ 267 U HED NO a DATE: 02/21/84 l REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE I DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-55C
-- -_= --_----_-_-----_-_-----_----_-----------------------------------------
DESCRIPTION OF DISCREPANCY REACTOR PLT CMPNT CLG PUMP CONTROLS ARE FROM TOP / BOTTOM C/B/A RECOMMENDATIONS: REORDER FROM TOP TO BOTTOM A/B/C s ACTION: AFPROVCD BY GSU MANAGEMENT i I I ELDCRM ISSUE DATE / /
'- - FDDRs ISSUE DATE / /
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER I i 1 I
HUMAN ENGINEERING DIGCREPANCY RECORD
, IVER BEND NUCLEAR PLAN'T HED NO. :: 4 42 O DATE: 02/23/04 REVIEWER: DURGY/CHACE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECVLIST NO.: A7.3 CHiiCl L IST AREA: PANEL LAYOUT AND DESIGN PANEL /WORIGTATION NO. P6SO-1D DESCRIPTION OF DISCREPANCY GROUPINGS OF LINES OF DEMARCATION, MIMICS, OR OTHER GRAPHIC DISPLAYS ARE NOT ARRANGED IN FUNCTIONAL OR SEQUENTIAL RELATIONSHIPS. (CORRESPONDENCE DETWEEN RWCU TEMP SEL SW NOT UNDER RWCU TEMP G33R607 INDICATOR.)
RECOMMENDATIONS: ADD MIMICS TO SHOW RELATIONSHIP DETWEEN SELECT SWITCH AND METER ACTION: AFFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 0 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I l O
HUMAN ENGINEERING DISCREPANCY RECORD
!,_h RIVER BEND NUCL EAR PL AN'T s
F4 EEI) b4 C3 . a d4 1 9P DATE: 02/23/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE
-----------------------------------==_ _----------------------------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.4 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-S PANEL / WORKSTATION NO. P680-6 i DESCRIPTION OF DISCREPANCY: WHEN STRINGS (6 OR MORE) OR MATRICES (GREATER THAN 4x4)OF COMPONENTS OF SIMILAR OR COMMON FUNCTION ARE INSTALLED, THEY ARE NOT MADE VISUALLY DISTINGUISHAELE BY LINES OF DEMARCATION, HIERARCHICAL LABELING, COLOR CONTRAST, ETC. (RECIRC. A AND B). l RECOMMENDATIONS: NO ACTION. THESE METERS ARE WELL GROUPED AND SEPARATE FROM ADJACENT SYSTEMS ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: 4 1 l l l l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND N U C L_ E A R Pt_.A N T O DATE: 09/98/4 HED NO.s 806 REVIEWER: LINF. TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: OPERATING PERSONNEL INTERVIEW CHECFLIST NO. A4 CHECFLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870 DESCRIPTIOta OF DISCREPAf 4CY : PO70 NEEDS COLOR CODING OR ENHANCEMENT TO ASSIST IN DISTINGUISHING SYSTEMS RECOMMENDATIOt45: AS A RESULT OF THE DCRDR SURVEY, SPECIFIC AREAS OF CONCERN FOR THIS PANEL HAVE BEEN DOCUMENTED Of3 SURVEY HED'S AND ENHANCEMENT WILL DE ADDED TO THESE AREAS AS AFFROFRIATE. ACT I OtJ APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATINO: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDINO 5*/. POWER 1 l O
HUMAN ENGINEERING DISCREPANCY RECORD 1
/
l RIVER BEND NUC L.E AR PL ANT HED NO.s 138 l DATE: 03/01/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BARKS / CHASE /SHANKLE i DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A4.2 CHECHLIST AREA: PANEL LAYOUT AND EESIGN PANCL/ WORKSTATION NO. P845 ( 1.)
! DESCRIPTION OF DISCREFANCY: . FOR THE " BED A C AND BD SELECT PROCESS MODE PERMISSIVE" THE TWO RED LI ARE AMBIGUOUS RECOMMENDATIONS: ,
O ADD LADELS TO INDICATE FUNCTION ACTION: AFF ROVED BY GSU MANAGEMENT i E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / l
.I f CRITICALITY RATING: 3 4
1 IMFLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
! I l I i
4 l 1 I i ,! O I k i I
, _ _ , _ _ _ , _ . . _ _ _ _ . . . _ , _ _ _ _ . - . _ . . _ _ _ _ . . . _ , _ _ . _ _ _ . _ . - _ . . , , , _ . _ _ . _ _ _ _ c___,,___,_.,._,.. ,,_._,_m,.m.
H u t*1 A N ENGINEERING DISCREPANCY RECORD RIVER BEND N U CI-.E A R PLANT DATE: 03/01/84 HED N O :: 185 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA EOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.3 CHECt. LIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORtSTATIOrd NO. F670 PANEL / WORKSTATION NO. F'67 2 DESCRIPTION OF DISCREPANCY: APRM PANEL HAS GROUFS OF TWO WHITE LIGHTS THEN A YELLOW LIGHT WITH NO EXPLANATION RECOMMENDATIONS: INCLUDE SOME TYF E OF LABELING TO EXPLAIN THE LIGHT GROUPS ACTION: APF ROVED DY GEU MANAGEMENT EDDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMEf4T ATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER 1 1
- O l
l t
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT HED NO.s 161 DATE: 02/28/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: DISHOP/MATSON
- == ____
DATA SOURCC: BWR OWNERS GROUP CHECKLIST NO.: A5.1 CHCCKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P623 ( 1.) DESCRIPTION OF DISCREPANCY: LIGHTS OVER INDICATORS ON P623 DO NOT IDENTIFY COMPONENT FUNCTION RECOMMENDATIONS: IDENTIFY COMPONENT FUNCTION O. ACTION: ADD LABELS TO INDICATE FUNCTION i E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER d h 1 i 4 l 1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct_.E A R P L_ A N T DATE: 02/23/84 F4EEE) b4 E3 . = d4 3F C) REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHEC) LIST NO.: AG.1 CHEClLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WOR) STATION NO. P600-1 DESCRIPTION OF DISCREPANCY: LADELS, LEGEND PLATES, OR ESCUTCHEONS ARE NOT USED TO IDENTIFY COMPONENT FUNCTIOrl. (WRONG LADELS Or4 CONTROLLERS) (RWCU CONDUCTIIVITY G33-R604 R601;R603) (LADEL FORMAT ODD,EX. G33-FIO7 RWCU REGEN HX BYPASS) RECOMMENDATIONS: IDENTIFY ALL COMFONENT FUNCTIONS AND CHANGE LABELING AS REQUIRED ACTION: APPROVED DY OSU MANAGEMENT ELDLR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMEtJTATION SCHEDULE: FRIOR TO EXCEEDING 5*/. POWER O
l l 1 l l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
. U F4EE E) b4 E3 . m 7P 51 DATE: OC/24/84 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. AS.1 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-15C DESCRIPTION OF DISCREPANCY:
j NO LABEL FOR INDICATOR LIGHTS ABOVE 1TMG-TGM TURNING GEAR MOTOR SWITCH. RECOMMENDATIONS: ADD LABEL TO INDICATE FUNCTION. )- () ACTION: EVALUATION OF SYSTEM DETERMINED THAT FOUR (4) ADJACENT LABELS WILL BE CHANGED. ELDCR, ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER a i e O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/07/04 F4 EE E) P4 C3 . = C5:21 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OW.JERS GROUP CHECKLIST NO. A5.1 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKSTATIOt1 NO. P863-76 ( 1.) 1HVF*ACU1H FB AIR HDLG. Ui41T DESCRIPTION OF DISCREPANCY: THE COMFONENT FUNCTION FOR THIS CONTROL IS NOT IDENTIFIED ON ITS LADEL. RECOMMENDATIONS: COMPOtJENT FUNCTION HAS DEEN ADDED SINCE SURVEY. ADD MIMIC TO CONNECT cot 4 TROL WITH HVAC SYGTEM AS APPROPRIATE. ACT IOrJ: AFFROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATIOtJ SCHEDULE: PRIOR TO EXCEEDING 5% POWER 9
l I HUMAN ENGINEERING DISCREPANCY RECORD RIVER , BEND NUCLEAR PLANT
~
F4 EE E) b4C3 s 25 25 d2 DATE: 02/20/84 REVICWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE FHASE
---_----_-- --=_------_---.------------- -
DATA SOURCC: BWR OWNERS GROUP 1 CHECKLIST NO.: A5.1 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P869 ( 1.) DESCRIPTION OF DISCREPANCY: THE PUMP VIBRATION TRANSDUCER CONDITIONER OUTPUT JACKS (48) HAVE NO IDENTIFYING COf1PONENT FUNCTION LABELS. RECOMMENDATIONS: NO ACTION i THESE BOP OUTPUT JACKS ARE FOR TECHNICIAN'S USE ONLY.
, ACTION: *
) APPROVED BY GSU MANAGEMENT \* ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 i IMPLEMENTATION SCHEDULE: i l 1 .
HUMAN ENGINEERING DISCREPANCY RECORD
- RIVER BEND NUCLEAR PLANT HED NO. :: 243 DATE: 02/23/04 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECFLIST NO. A5.1 CHECt: LIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORF. STATION NO. PG70-52
( 1.) PANEL /WORESTATION NO. FG70-51 ( I.) DESCRIPTION OF DISCREPANCY: LADEL INFORMATION FOR 6 CONTAINMENT SUMP INDICATOR LIGHTS, AND THE FLOOR DRAIN LEVEL IflDICATORS IS INCOMPLETE lh RECCMMENDATIONS: LADELING HAS DEEN CORRECTED SINCE SURVEY. NO FURTHER ACTION REQUIRED ACTION: AF F ROVED E'Y GSU MANAGEMENT E t,DCR # ISSUE DATE / / FDDRu ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l 9 L
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 7
\ 2 DATE: OC/23/04 FiEE E) bJC3. m REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.1 l CHECKLIST AREA: PANEL LAYOUT AND DESIGN i
PANCL/ WORKSTATION NO. P870-54B ( 1.) DESCRIPTION OF DISCREPANCY: j THERE ARE INDIVIDUAL LIGHTS WITHOUT ASSOCIATED CONTROLS THAT HAVE LABELS THAT DO NOT INDICATE THE FUNCTION OF THE LIGHTS. ALSD. THERE ARE METERS AND TEST BUTTONS THAT ARE UNLABELED O RECOMMENDATIONS: ADD LABELS TO INSERT 54B AS APPROPRIATE . l
- ACTION:
j APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 I. IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l - i l i
.t i
f .i !CE) j
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED N O . :: 50 REVIEWER: DARUS/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.10 CHEClLIST AREA: FANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. F808-51C ( 1.> DESCRIPTION OF DISCREFANC/ BUTTONS AFE LADELED POORLY EX:" PUMP 1A UP DOWN" IS THE VACUUM PRIMING PUMP RECOMMENDATIONS: INVESTIGATE AND UPGRADE LAEELS ON DUTTONS TO REFLECT THE COMPONENT FUNCTION ACTION: ADD LADELS AS APFROFRIATE Et< DCR # ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1 0 l l
RECORD HUMAN ENGINEERING DISCREPAbCY
' RIVER BEND NUCLEAR PLANT FiEE E) P4 C3 . a 521 1 DATE: 02/24/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: LIDDLE /MATSON/ BISHOP
--__________--__-___-___-_-___-__---_-__-_===---_____-_-__--_-
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.10 CHEChLIST AREA: PANEL LAYOUT AND DESIGN i PANEL / WORKSTATION NO. P808-86C ( 1.) 1RTX-XSR1C 4.16 KV STBY BUS SWG(*A'NOT INCL.) ( 2.) 1NJS-ACB183 480 V BUS SWG 2O('C' NOT INCLUDED) PANEL / WORKSTATION NO. PB08-07C ( 1.) (1)NJS-SWG1R ( 2.) (1)NJS-SWG1T ( 3.) (1)NJS-X1B COMPONENT DESCRIPTION NOT FOUND PANEL / WORKSTATION NO. PB00-88C ( 1.) 1NPS-ACB21 LC XFMR X2F,2H,3B(1V) ( 2.) 1NJS-ACB419 480 V BUS SWG 30(D) i DESCRIPTION OF DISCREPANCY: THE LISTED LABELS ARE INCORRECT. CORRECTIONS ARE INDICATED IN PARENTHESES RECOMMENDATIONS: CORRECT THE LISTED LABELS ACTION: AFFROVED BY GSU MANAGEMENT Et.DCR# ISSUE DATE / / FDDR# ISSUE DATE / / I CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I !() 1 :
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: OC/C4/84 HED N O . :: 244 REVIEWER: LIDDLE /MATSON/PISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: EWR OWNERS GROUP CHECKLIST NO.: A3.10 CHECLLIST AREA: PANEL LAYOUT AND DESIGN PAtJCL/WORKSTATIOr4 t40. PO70-52 DESCRIPTION OF DISCREPANCY: LABEL READING 'COND AIR REMOVAL VAC PUMP
- NEEDS IMPROVING RECOMMENDATIONS:
LADEL CORRECTED SINCE SURVEY. NO FURTHER ACTION REQUIRED ACTIOti: APFROVED BY GSU MANAGEMEt4T ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: C IMPLEMENTATION SCHEDULE: O i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT /, ,h DATE: 02/23/84 F4E~I) PJ C3 . s 251 5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PH'ASE DATA SOURCE: BWR OWNERS GROUP CHECULIST NO.: A5.11 CHECKLIST AREA: PANEL LAYCUT AND DESIGN PANEL / WORKSTATION NO. P600-7 PANEL / WORKSTATION NO. P680-0 PANEL / WORKSTATION NO. P680-9 DESCRIPTION OF DISCREPANCY: LADELS ETC. ARE NOT CONSISTENTLY POSITIONED ABOVE OR BELOW DEVICES AND READILY ASSOCIATED WITH CORRESPONDING CONTROLS AND DISPLAYS. (INSERT ISD RECORDERS LABELED ON BOTTOM INSTEAD OF TOP.) RECOMMENDATIONS: POSITION LABELS ABOVE THEIR CORRESPONDING CONTROLS AND DISPLAYS ACTION: APPROVED BY GSU MANAGEMENT ESDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 0 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER (a
HUMAN ENGINEERING DISCREPANCY RECORD 1 RIVER BEND N U C L_ E A R Pt._ A N T DATE: 02/24/04 F4EEI) b4 C3 . 7F"541 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASC DATA SOURCE: BWR OWNERS GROUP CHECKLISY NO.: A5.3 i CHECKLIST AREA: W,'EL LAYOUT AND DESIGN PANEL /WORUSTATION NO. P600-15C DESCRIPTION OF DISCREPANCY: TURNING GEAR LIGHT (3 SETS) NOT LABELED TO INDICATE FUNCTION. RECOMMENDATIONS: LABEL TURNING GEAR LIGHTS TO INDICATE FUNCTION ACTION: APPROVED BY GSU MANAGEMENT EtDCRN ISSUC DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: ; IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/04 HED NO.a 753 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE _---_-----------_-_-____-----__=---===--------- _---------- --=--------- ..------ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-8B
- - - - - - - - - - - - - - - - - - - - - - - - - - - --=- - -
= - - - - - - _ -. - =-------------
DESCRIPTION OF DISCREPANCY: MISSING TURBINE CONTROL VALVES DESIGNATION LABEL RECOMMENDATIONS: ADD LABEL. ! ACTION: APPROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR Pt. ANT DATE: OC/C4/04 F4 EE I) b4 C3 . = P:5:2 RCVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - = _ . -_--- ------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.3 CHECLLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-8C
----------------------------------------- --- _ . _ _ - - - __=-------------
DESCRIPTION OF DISCREPANCY: ADD TURBINE CONTROL SYSTEM DESIGNATION LABEL. RECOMMENDATIONS: ADD TURBINE CONTROL SYSTEM DESIGNATION LABEL ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
.---- _ . = - = = - - - _------- ------------------------------------------ -- -===-
CRITICALITY RATING: 0 l l IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCt. EAR Pt. ANT HED NO.s 756 (Gj DATE: 02/24/84 REVIEWER: BUPGY/ CHASE TRACKING STATUS: SCHEDULE PHASC
..------ - - - = - - - - _ . -------------
- - - - - - - = - _ _ _ - _ _ _ - - - _ - - - - - - - = _ _-_=-
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-9B
- _ - _:=-----=. --
-_ _ = _ - - --------- ___
DESCRIPTION OF DISCREPANCY: LINE SYNC. INDICATES LABELS SHOULD SAY LINE SYNC. INTERLOCK OK. RECCMMENDATIONS: RELABEL WITH APPROPRIATE NAME AND FUNCTION O ACTION: U APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
- _ _ _ - _ _ _ -- - - -. _===-_-_---
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER A l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: OC/C1/04 HED N O . :: 640 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.5 i CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19B DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES AND ESCUTCHEONS ARE NOT CONSISTENT IN NOMENCLATURE, USE OF ACRONYMS, ABBREVIATIONS, ETC. (ON 19B, B21C-S37 A AND B SHOULD USE "INOP" VERSUS "ON" RECOMMENDATIONS: O CHANGE LABEL TO SAY "INOP" ACTION: APPROVED BY GSU MANAGEMENT E t<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / __--_ _ _ __ - - -= - . . . _ _ CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 9
)
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT p Q DATE: OC/21/84 F4 EE E) bl C3 . a eb 5 E3 REVILWER: DURGY/CHACE TRACKING STATUS: SCHEDULE PHASE
=- = = - - --- = = - - - - - _ - - -- ==-_=--------
- - - - - - _ - - - _ - - - - - = = _ _ _
=__
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-21C PANEL / WORKSTATION NO. P601-20C PANEL / WORKSTATION NO. P601-17C _ = - - - - - - - - - -=----------------
- - - - - - - - = = _ -
DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES AND ESCUTCHEONS ARE NOT CONSISTENT IN NOMENCLATURE, USE OF ACRONYMS, ABBREVIATIONS, ETC. VALVE VS V. RECOMMENDATIONS: s.,/ COMPARE AGAINST STANDARD ABBREVIATION LIST AND CHANGE IF REQUIRED ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
= = = = - . _. ... -_ _- ==------
--------- ---==_ -- _.
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
/
sm l l l - -- .-.
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/23/84 Fi EE E) b4 C3 . s dL C) <> REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- =------------ - -----------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.5 CHECLLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-2 ( 1.) PUSH BUTTON FW LUBE DIL PUMP ( 2.) 1FWP-P1A FW PUMP ( 3.) 1FWP-P1B FW PUMP 1B ( 4.) 1FWP-P1C FW PUMP 1C
- _----- - - - = = _ _
DESCRIPTION OF DISCREPANCY: FOR THE FW LUBE OIL PUMP THE GREEN LIGHTS SHOULD BE RED (REAC FWPMN LUBO PUMP PRESSURE NORM) RECOMMENDATIONS: CHANGE GREEN LIGHTS TO RED ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
------------- ----------------===
CRITICALITY RATING: 3 IMPLEMENTATION GCHEDULE: PRIOR TO EXCEEDING 5% POWER O l 1
HUMAN ENGINEERING DIBCREPANCY RECORD s RIVER BEND NUCLEAR PLANT ('") i DATE: OC/23/04 HED NO. a 685 l REVIEWER: BURGY/CHACE TRACKING STATUS: SCHEDULE PHASE l l _ = = = _ _ _ - _ - - - - - - - - - - _ -- - - - - - l _ - _ _ = = - - - - - - - - - - - - - - - - - - _ _ . I DATA SOURCC: BWR OWNERS GRC:? CHECKLIST NO.: A5.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4C PANEL / WORKSTATION NO. P680-5C PANEL / WORKSTATION NO. P680-6C PANEL / WORKSTATION NO. P680-10C I
=-__
-------------------------=_
DESCRIPTION OF DISCREPANCY: LABELS, LEGEND PLATES AND ESCUTCHEONS ARE NOT CONSISTENT IN NOMENCLATURE, USE OF ACRONYMS, ABBREVIATIONS, ETC. RECOMMENDATIONS: REVIEW LABELS ON THESE INSERTS AGAINST STANDARD ABBREVIATIONS LIST & CHANGE IF REQUIRED ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
.= _ _ _ _
=. --__ --
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l I l __ __ _ J
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O HED NO.= 164 DATE: 03/01/04 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - = - - -------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKSTATIOf4 NO. P845 ( 1.) N64-FO44 VLV COOLER DRAIN LOOP SEAL DIS _ _ = _ --------------- DESCRIPTION OF DISCREF ANCY: TWO VALVES HAVE THE SAME NAME. ALSO THE ABBREVIATION USED (" DIS") IS NOT THE PROPER ONE FOR DISCHARGE RECOMMENDATIONS: EVALUATE LABELING AND CHANGE IF REQUIRED ACTION: APPROVED BY GSU MANAGEMEt4T ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I l i Ol
RECORD HUMAN ENGINEERING DISCREPANCY RIVER BEND NUCLEAR PLANT n C) DATC 03/01/04 HED NO.s 170 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BARKS / CHASE /SHANKLE t _-__--_________--_-__---____-_----------__----------___---- i DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.8 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P614 ( 1.) PANEL / WORKSTATION NO. P604 ( I.) PANEL / WORKSTATION NO. P600 ( 1.)
=.---= = ----_
__==. - _ -_ - - _ _ -_ --=--...----_-_--__-------_.-_.-----__
. DESCRIPTION OF DISCREPANCY: ' RED AND GREEN INDICATOR LIGHTS CANNOT BE EASILY READ RECOMMENDATIONS:
CHECK INTO WAYS OF CHANGING INDICATOR LIGHT COLORS FOR EASE OF READING 1 ACTION: I CHANGE TO LIGHTER SHADES OF RED L GREEN f ELDCR# ISSUE DATE / / J FDDR# ISSUE DATE / / _ _ _ _ _ _ _ _ . - - . . . . . - _ _ = _
--_----------_= _ - - _ _ -_----_-------__-----_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULES PRIOR TO EXCEEDING 5% POWER i O I i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR Pt._ A N T O DATE: 02/20/84 F4EEE) P4 C3 . m 1 da:2 REVIEWER: BISHOP /MATSON TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P622 ( 1.) PANCL/WORKGTATION NO. P632 ( 1.) PANEL / WORKSTATION NO. P642 ( 1.) PANEL / WORKSTATION NO. P623 ( 1.) DESCRIPTION OF DISCREFANCY: MULTI-POINT RECORDERS ARE DIFFICULT TO READ RECOMMENDATIONS: NO ACTION. THESE ARE STANDARD TRACOR RECORDERS THAT OPERATORS BECOME FAMILIAR WITH DURING TRAINING ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 l IMPLEMENTATION SCHEDULE: l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT /)
/ DATE: 02/27/84 F4 EE E) P4 C3 . E dT CP REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
------------ =-------
---------===__--__-=----------------=_-
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PB08-85C1 ( 1.) _ _ = _ _ . --- -- .- - _ - . -
- _ _ - =--_ . - - - = _
DESCRIPTION OF DISCREPANCY: RAISED BUTTON LABELING NOT EASILY READ RECOMMENDATIONS: NO ACTION. THE LABELING FOR THIS SERVICE WATER INSERT IS APPROPRIATE FOR THE a
-) DESIGN (BACKLIT BUTTONS).
ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- _ = - = - - _ - - = _
= -_. _ - - = - = _ --_____-_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 F4 EEI) bJ E3 . c 02 1 52 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A6.6 CHECULIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORESTATION NO. P808-87 ( 1.) PANEL /WORESTATION NO. P808-88 ( 1.) ___--_--_-_--_----------------_------- - ---__=----- - - - - - - - - - - - - - - - - - - DESCRIPTION OF DISCREPANCY: EQUIPMENT UNDER GSU JURISDICTION GREEN LABELS ARE TOO BIG AND COVER MIMIC RECOMMENDATIONS: O THESE TEMPORARY LABELS INDICATE THAT A SYSTEM HAS BEEN TURNED OVER TO GSU STARTUP. THEY WILL DE REMOVED PRIOR TO FUEL LOAD. NO FURTHER ACTION REQUIRED ACTION: APPROVED BY GSU MANAGEMENT Et,DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-------------------------------=. -. __------- __---------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NU C L_ E AR PL. ANT
)
(%
~# DATE: OC/C3/04 Fi E~ I) bJ C3 . s C57Fdb REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- _ - - - - - - - _ - _ - - - _ - - - - _ _ - - - _ - - - _ _ _ _ - - = - _ _ - - _ - _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A7.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANCL/ WORKSTATION NO. P680
---_=_----- --
- = -===_ _=___
DESCRIPTION OF DISCREPANCY: THE SMALL ANNUNCIATOR WINDOWS ARE NOT IDENTIFIABLE FROM THE SEATED POSITION RECOMMENDATIONS: NO ACTION. THIS IS NOT A " SEATED ONLY' PANEL. ANNUNCIATORS THAT ARE NOT IDENTIFIABLE WHILE SEATED ARE IDENTIFIABLE WHEN STANDING. () ACTION: APPROVED BY GSU MANAGEMENT. j E&DCRM ISSUE DATE / / FDDR# ISSUE DATE / / ______-___-_--______-__------_---__------ ____ - - - _ _ - _ _ _ _ _-=__. _______- CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O i 1 I
. . . _ _ _ _ . - _ _ . - __ . _ _ _ .__ _ . _ . . _ _ _ _ _ _ _ _ - - _ . . _ , - - _ . . _ _ . _ _ . _ _ _ . _ ~ . _ . . _ _ _ _
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 09/98/4 F4 EE I) DJ C3 . s E3 1 "5 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE ___________________________________________________= --= _____________________ DA1A SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: BI CHEELLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORLSTATION NO. GENERIC ( 1.) ___________________________________________ ___=. --__________________________ DESCRIPTION OF DISCREPANCY: ALL PUMP CONTROLS ARE SET UP AS A, B, C, FROM BOTTOM TO TOP OF PANEL. RECOMMENDATIONS: AS A RESULT OF T HE DCF:DR SURVEY, SPECIFIC PROBLEM AREAS HAVE BEEN DOCUMENTED ON SURVEY HED'S AND THE APPROPRIATE ACTION WILL BE TAKEN. ACTION: AFFROVED BY GSU MANAGEMENT'. Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
.- - ~.
HUMAN ENGINEERING D I S C R E P Ai%8C Y RECORD l RIVER BEND NUCLEAR PLANT 4 (n'-) DATE: 09/19/94 F4EZI) bJC3 . E3 C2:5 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
= _ _ - _ - = = - - - - - = - _ _ _ _ _ _
______----__----__--=- --= _---___-_--___-_-- - - - - - - - - - = DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: B1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680
; ( 1.)
-=_ =. - - - - _ _ _
' - - = - - _ - _ _ _ -- =.-_-_ -_-= _
____--__-----_____=-- DESCRIPTION OF DISCREPANCY: BAILEY CONTROLLERS ON P6BO (02) DO NOT INDICATE UNITS RECOMMENDATIONS: THIS CONCERN IS DOCUMENTED GENERICALLY ON HED #23 AND THE APPROPRIATE l LABELING WILL BE ADDED. . ACTION: AFPROVED BY GSU MANAGEMENT. i ELDCR# ISSUE DATE / / r FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER }
- - . - _ . .- --____ ..., - -.--- . , _ . , - - - - , , , , _ , - , - , . _ _ _ _ , _ _ , . ._,,-n..,,,,-.,. . . . _ - , - .
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 09/98/4 HED NO- :: 814 REVIEWER: LINT TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECt. LIST NO.: D1 CHEElLIST AREA: INSTRUMENTATION AND HARDWARE PANLL/WORISTATION NO. P870 ( 1.) DESCRIPTIOtJ OF DISCREPANCY: HEATER DRAIN PUMI' VALVES ARE DIFFICULT TO LOCATE OR ACCESS RECOMMENDATIONS: TRAINING ON THE SIMULATOF: WILL FAMILIARIZE OPERATORS WITH SYSTEM DESIGN. ACTION: APPROVED DY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: ~ IMFLEMENTATION SCHEDULE: l l l l l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT U DATE: 03/01/84 HED NO = 182 REVIEWER: BARV.S/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE-
---------- _----------===_- -
.----------==--
__ = ------- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B1.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P614
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ - - - _ ------====__ ===---- =-------
DESCRIPTION OF DISCREPANCY: YELLOW INDICATORS UNDER
- COMMON LABELS ARE NOT COMPLETE SHOULD READ TANK EMPTY / TANK LOW AND OIL HOT / OIL WARM RECOMMENDATIONS:
ADD LABELS TO SHOW FUNCTIONS O ACTION: APPROVED BY GSU MANAGEMENT
~
ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _-_-_-_---_-_-- - ---____-__-==. _ _- - ----_---- ----- =____ --- ._ CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT F4 EE I) D4 E3 . = ZF d2 C5 DATE: 02/23/84 REVIEWER: DURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: Bl.1 CHECELIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 ( 1.) B03-COOIA/B RCIRC PUMP A/B --_--_-__-_--__-_-_--_------------- ---=--- DESCRIPTION OF DISCREPANCY: RCIRC PUMP A/B VIBRATION RESET-NO INDICATING LIGHTS RECOMMENDATIONS: CHECL INTO PROVIDING INDICATING LIGHTS FOR RCIRC PUMP A/B VIBRATION RESET ACTION: EVALUATION DETERMINED THAT LIGHTS ARE NOT REQUIRED. ANNUNCIATORS PROVIDE NEEDED INFORMATION ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / _=- --------------------------- CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
DISCREPANCY RECORD HUMAN ENGINEERING RIVER BEND NUCLEAR PLANT p/
'- F4 EE E) bJ C3 . s db E3 03 DATE: 02/23/04 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
__________ _ - - - _ - - __:-=_=_ _. DA'AT SOURCC: BWR. OWNERS GROUP CHECKLIST NO. B1.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-CC ( 1.) PANEL / WORKSTATION NO. P680-3C ( 1.) 1 _______ DESCRIPTION OF DISCREPANCY: CONTROLLERS THAT REQUIRE MANUAL OPERATION ARE NOT DESIGNED FIVE CONTROLLERS TO FACILITATE HAVE PRECISE CONTROL WHERE FINE ADJUSTMENTS ARE REQUIRED. PUSHBUTTONS TO SELECT A vs M INSTEAD OF LEVER. RECOMMENDATIONS: TRAINING ON THE PLANT-SFECIFIC SIMULATOR FAMILIARIZES OPERATORS WITH THESE CONTROLLERS. NO ACTION.
~
ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / __-_-=-- ____________ ____ CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATC: 09/90/4 F1EEI) b4 C3 . s E3 1 57 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: OPERATING PERSONNEL INTERVIEW . CHECKLIST NO.: BC CHECVLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORESTATION NO. P600 ( 1.)
------------------------------- - - - - _ - = - .-=------------------------------
DESCRIPTION OF DISCREPANCY: ONE OPERATOR INDICATED A NEED FOR VALVE POSITION AND ANNUNCIATOR INDICATORS FOR COND HTR FULL BYPASS RECOMMENDATIONS: AN ALARM HAS E'EEN ADDCD SINCE THE SURVEY TO INDICATE THAT THE VALVE IS NOT FULLY CLOSED. NO FURTHER ACTION REQUIRED. ACTION: AFPROVED BY G5U MANAGEMENT. ELDER # ISSUE DATE / / FDDR# ISSUE DATE / / l
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - __ _ - - - - - - = = - - - - - = __-----------------
l CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD f'"; RIVER BEND NU CL_E AR PtANT U DATE: 09/98/4 F4 EE E} P4 E3 . = E31 :3 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCC: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B2 CHLCKLIST AREA: INSTRUMENTATION AND HARDWARE pat 4EL/WORKSTATIOt1 NO. PB70 ( I.)
--- ___ _ ==---- ----- - - _ - = - = .
= ------------------------------
DESCRIPTION OF DISCREPANCY: CONDENSATE PUMP vet 4T IS DIFFICULT TO LOCATE OR ACCESS RECOMMENDATIONS: _ TRAINING ON THE SIMULATOR WILL FAMILIARIZE OPERATORS WITH SYSTEM DESIGN. O ACTION: APPROVED BY GSU MANAGEMEt4T. ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
- ---- _ _ -=
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
l l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 Fi EE I) bJ C3 = 25 97 :2 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
------- --------- -~~~---------
DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: B2.II CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P600-2 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = _ _ _ - - - - - - = = _ _ - --------- =------------ DESCRIPTION OF DISCREPANCY SUBDIVISIONS ARE NOT CONSISTENT WITH ACCURACY NEEDED FOR OPERATOR RECOMMENDATIONS: FURTHER EVALUATION DETERMINED THAT SUBDIVISIONS ARE APPROPRIATE. NO FURTHER ACTION REQUIRED ACTION: APPROVED DY GSU MANAGEMENT E t<DCRM ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD , 1 7 RIVER BEND NUCLEAR PLANT i s D' DATE: 02/C3/84 HED NO. 520 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.11 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P6SO-7 PANEL / WORKSTATION NO. P6SO-8 PANEL / WORKSTATION NO. P680-9 DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT MARKED WITH SUBDIVISIONS THAT ARE CONSISTENT WITH THE ACCURACY NEEDED BY THE OPERATOR. (15B TURNINO GEAR MOTOR AMPS CHANGE SCALE.)
/~'g Q RECOMMENDATIONS:
EVALUATE THE NEED FOR A SCALE CHANGE. ACTION:
, EVALUATION OF SYSTEM DETERMINED TH4T SCALE IS APPROPRIATE (MOTOR RUNS AT APPROX. 60A). NO FURTHER ACTION REQUIRED.
Et<DCR M ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------------- .---___==--------------=- ---------___-_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/04 HED NO. s 107 REVIEWER: DARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---_-------_---__-----_--_--_----_-------_=----_----__------ - - = = - - - - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHCCKLIST NO. B2.11 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANCL/ WORKSTATION NO. P860-73B ( I.) DESCRIPTION OF DI5:REPANCY: RADIATION INTAKE INDICATORS NEED INTERMEDIATE VALUES ON THE SCALE RECOMMENDATIONS: THESE INDICATORS ARE EEING REMOVED PER FDDR-1464. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT ELDER et ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
l HUMAN ENGINEERING DISCREPANCY RECORD l l RIVER BEND NUCLEAR PLANT l
]
(~h F4EEI) P4 C3 . s 1 d> C5 () DATE: 02/20/84 REVIEWER: BISHOP /MATSON TRACKING STATUS: SCHEDULE PHASE
-_ --- --------------------------- _===__ ----------------------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.13 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P622 PANEL / WORKSTATION NO. P625
- - - - - - - - - - - - - - - - - - _ - _ = - -_------- _--------------- -------------__ --
DESCRIPTION OF DISCREPANCY: THE METER " PLT SOL A MN STM LN" IS SCALED IN MULTIPLES OF 30 RECOMMENDATIONS: NO ACTION. METERS LOCATED ON BACK PANELS AND SCALE IS APPROPRIATE FOR SYSTEM OPERATION. ACTION: APPROVED BY GSU MANAGEMENT EI4DCR# ISSUE DATE / / FDDRM ISSUE DATE / /
--------------------------------------------------==__ _ ----------------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct_.E A R PLANT DATE: 02/21/04 HED NO.a 667 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECULIST NO. B2.13 CHECtLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORKSTATIOt4 NO. P680-7C PANEL /WORMSTATION NO. P680-OC PANEL / WORKSTATION NO. P600-9C PANEL /WORKCTATION NO. P6SO-15C DESCRIPTION OF DISCREPANCY: INDICATING DEVICES ARE NOT SCALED WITH SUBDIVISIONS IN DECIMAL MULTIPLES OF-1, 2 OR 5. INSERT 15B TURNING GEAR MOTOR AMPS METER--CHANGE SCALE. INSERT 9D-GEN. VOLTS METER-CHANGE SCALE. INSERT 7D-IST 4 MZTERS STARTING AT LEFT SCALED IN INCREMENTS OF 25 RECOMMENDATIONS: CHANGE SCALE ON 9D INSERT - GEN VOLTS V-1SPGN05. OTHER METERS HAVE APPROFRIATE SCALES ACTION: AFFROVED BY GSU MANAGEMENT Ef:DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l 9
HUMAN ENGINEERING D I BCREEP ANCY RECORD l RIVER BEND NUCLEAR P L A N'T (N/ ) DATE: 03/01/04 F4 EEI) P4E3 a l e& C5 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _== _
-------------- __ ===== = _-
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.13 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P845 ( 1.)
..==_ =-
_= _- - ----------------------
-----=_. =
DESCRIPTION OF DISCREPANCY: SCALES ON TRAIN A & B ABSORBER OUTLET FLOW METERS AND RECORDERS REQUIRE REVIEW (3 TO CO BY 1*S, 20 TO 30 BY 2*S) RECOMMENDATIONS: EVALUATE SCALES v ACTION: NO ACTION. SCALES ARE APPROPRIATE TO SUPPORT SYSTEM OPERATIONS ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
------------------- _-__=_--_-_
CRITICALITY RATING 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 Fi EE I) DJ C3 . c C2 "5 d1 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.13 CHCCKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P870-54B ( 1.) 1TME-PIEPR-35 ST. SEAL EVAP. TUBE SIDE PRESSURE ( 2.) 1TME-PIEPR-36 ST. SEAL EVAP. SHL. SIDE PRESSURE DESCRIPTION OF DISCREPANCY METERS HAVE DECIMAL MULTIPLES OF 3 RECOMMENDATIONS: NO ACTION. OPERATIONS DO NOT WANT TO CHANGE PRESENT SCALES ACTION: APFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
== ===------------------------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
DISCREPANCY RECORD HUMAN ENGINEERING g- RIVER BEND NUCLEAR PLANT
' HED N O . :: 142 DATE: 03/01/04 TRACKING STATUS: SCHEDULE PHASE REVIEWER: BARKS / CHASE /SHT.NKLE
---____=_---_--_=
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.2 FHCCKLIST AREA: INSTRUMENTATION AND HARDWARE PANCL/ WORKSTATION NO. P845 ( 1.) DESCRIPTION OF DISCREPANCY: INCHES ABOVE THE THERE IS SLIGHT PARALLAX PROBLEM WITH ALL SMALL METERS 53 FLOOR RECOMMENDATIONS: fG OPERATOR TRAINING ON PLANT-SPECIFIC SIMULATOR WILL FAMILIARIZE OPERATORS W L/ THESE OFFGAS PANEL METERS ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / ' _ _ _ _ _ - - - - _ _ _ = - . - - - CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: ()s L
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 03/01/84 FiEEI) DJ C3 . = 17P C2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE _---__--------_----__-_---_-----____----_-_ - - - = - = = - - - -= -=--- =---------- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHCCKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P600 ( 1.)
------------------------------------------------- = = _ _ . ----------------
DESCRIPTION OF DISCREPANCY: THERE ARE NO UNITS INDICATED FOR SCALES ON THE METERS RECOMMENDATIONS: ADD LABELS TO INDICATE UNITS ACTION: APPROVED BY GSU MANAGEMENT E8.DCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULC: PRIOR TO EXCEEDING 5% POWER 1 l I O
l l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 5 4 \ DATE: 03/01/94 FiEEE) P4 C3 = 1'71 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- - ==---- -----=_
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANCL/ WORKSTATION NO. P614 ( 1.) B21-R643 REACTOR VESSEL TEMP MONITORING
. = _ -- - - -
--. __ __----------- ____ _ _ _ _ = = . ___
DESCRIPTION OF DISCREPANCY: SCALE SHOULD BE IN DEGREES F NOT CENTIGRADE RECOMMENDATIONS: SCALE CHANGED TO DEGREES F SINCE SURVEY. NO FURTHER ACTION REQUIRED. fm \ ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
-------------------------------- = _ _ - = _ .
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
F4UMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 03/01/84 Fi EE I) DJ C3 . = 1 E3 97 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---------------------------------- _ _. = = - - - - _ ___-----------------
DATA SOURCE: EWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P670 ( 1.) PANEL / WORKSTATION NO. P672 ( 1.) DESCRIPTION OF DISCREPANCY: THE UNITS ON THE IRM CHANNEL B t< F ARE " UNITS" WHICH ARE INCORRECT RECOMMENDATIONS: RE-EXAMINATION OF UNITS DETERMINED THAT THEY ARE CORRECT. NO FURTHER ACTION REQUIRED. ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / /
------- ------------------------------ _ -_ _=__- _ _--------------
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l l O
HUMAN ENGINEERING DISCREPA'NCY RECORD RIVER BEND NUCLEAR P L AN'T iy) V DATE: 02/24/04 HED N O . :: 763 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
= - - =_ - - - - - - -__------
---- =-------------- __- --
DATA SOURCC: BWR OWNERS GROUP CHECV. LIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORl: STATION NO. P680-15C
=- - - _ --------------
DESCRIPTION OF DISCREPANCY: 3 BUTTON SWITCHES LABELED RUN/ AUTO /OFF - CHECK FUNCTION WITH SIMULATOR OR ENG. RECOMMENDATIONS: NO ACTION. BUTTON ARRANGEMENT IS CONSISTENT FOR BUTTON CONFIGURATION ACTION: APFROVED BY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Cl-.E A R PR-.A N T O DATE: 02/23/84 F4 EE I) DJ C3 . s 25 *P 1 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
----------------------------------=-
- - - - - - ----- - =--------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECFLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-2 DESCRIPTION OF DISCREPANCY: INDICATION DEVICES ARE NOT SCALED IN PROCESS UNITS THAT RELATE TO SYSTEM OPERATION (% VS ____) ON RECIRC PECOMMENDATIONS: NO ACTION. UNITS ARE % ERROR WHICH IS APPROPRIATE. ACTION: APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: l 1 l I l
I 1 l
\
HUMAN ENGINEERING DISCREPANCY RECORD I RIVER BEND NUCLEAR PLANT (3 C) DATE: 02/24/04 HED NO.s 761 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASC
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ = _ - - - _ ----- - = - - - - - - - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B2.3 CHECKLIST AREA: INSTRUMENTATIOP.' AND HARDWARE PANEL / WORKSTATION NO. P680-7A
------------------------------==== = ------=_ _ _-- - -----------
DESCRIPTION OF DISCREPANCY: ADD ANNUNCIATOR WINDOW FOR STEAM BYPASS REGULATOR A/B FAILURE. RECOMMENDATIONS: A RED INDICATOR LIGHT LABELED " REG. ERROR" ON P680-7C MONITORS REGULATOR A/B FAILURE. NO FURTHER ACTION REQUIRED. O ACTION: AFFROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / /
------------------------------------------------------ _==_ ------------_---_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT HED NO.s ~7 6 0 DATE: 02/C4/84 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE FHASE
-_--_-___-----_-----_--_----____--___-___ --=-_----__----_-_----------_-____---
DATA SOURCE: OWR OWNERS GROUP CHECKLIST NO.: BC.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-9B DESCRIPTION OF DISCREPANCY: AC VOLTS METER - SCALE SHOULD BE O-500 KV RECOMMENDATIONS: SCALES O'J THE INCOMING AND RUNNING METERS ARE APPROPRIATE. OPERATORS ARE INTERESTED IN WHETHER THE METERS READ THE SAME. ACTUAL VOLTAGE READINGS CAN BE READ AT OTHER METERS. NO FURTHER ACTION. ACTION: APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: i i l l l
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT O) ( DATE: 02/24/84 HED NO.s ~759 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE _ - - - - - - - _ - _ - - - - - - - - _ - - - - _ - - - - _ - - _ _ - - - = = = - _ = _ _ _ - - - - _ = = = - -- =---__-----__--- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECMLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-9D _ - _ - - - - - - - - - _ - - _ - - - - - - - - - - - - _ - - - - - - - _ _ - - - - - - _ _ - - - - - - - - = _ - - - _ - - - = - - - - - - - - _ - - - - DESCRIPTION OF DISCREPANCY: GEN. VOLT METER SHOULD BE MILOVOLTS NOT ;*1LOWATTS. RECOMMENDATIONS: RELADEL USING KILOVOLTS () ACTION: SCALE HAS DEEN CHANGED SINCE SURVEY. NO FURTHER ACTION. E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / /
- - - _ _ _ - - _ _ - - _ - _ _ _ _ - - - _ _ _ - - - - =__------__--- -- ---__-_________---____---
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 F4 EE E) bJ E3 . s 02 41 42 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - - - = _ - _ . - - ___________________--____________ DATA SOURCE: DWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECULIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P870-528 ( 1.) 1CRS-TI1D COLD REHEAT ST. TO MSR2 TEMP DESCRIPTION OF DISCREPANCYs SCALE SHOULD BE IN DEGREES NOT PERCENT RECOMMENDATIONS: SCALE HAS DEEN CHANGED TO DEGREES SINCE SURVEY. NO FURTHER ACTION REQUIRED ACTION: APPROVED BY GSU MANAGEMENT Et4DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/04 HED NO = 1 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
------_----- =_ - - - - - - - - - - - - - _ - _ - - - - - - _ - - - - _ .
DATA SOURCC: BWR OWNERS GROUP CHECKLIGT NO.* BC.3 CHCCKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P870-54 ? ( 1.) 1GMC-PIEPR-15 STATOR COOLING WATER PRESS
' - - - - . .=-------- __ ------ - = = - - - - - - - - - -
DESCRIPTION OF DISCREPANCY: SCALE IS IN PERCENT AND SHOULD BE IN PSI RECOMMENDATIONS: INVESTIGATE CHANGING SCALE TO READ IN PSI ACTION: CHANGE SCALE TO PSI EbDCRM ISSUE DATE / / ISSUE DATE FDDR# / /
=---------- --- ---------------------------------------- _==___ ---_==_-_
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 57. POWER I l I lO l l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 03/01/84 F4 EEI) P4 C3 . = 1 di di REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: E(WR OWNERS GROUP CHECLLIST NO.: B5.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P845 ( 1.) DESCRIPTION OF DISCREPANCY: IN THE SIMULATOR THE " GLARE FREE" GLASS BLURS THE VISION RECOMMENDATIONS: INVESTIGATE WAYS TO ELIMINATE GLARE WITHOUT ADDING BLUR TO THE GLASS ACTION: NO ACTION. IF REQUIRED, DOOh5 ARE EASILY OPENED ESDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T* DATE: 02/28/84 HED NO. 337 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. B;.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE i PANCL/ WORKSTATION NO. PO69 , ( 1.) 1CWS-CRY 7 PLnNT CONDUCTIVITY ( 2.) 1SST-CRYO 6 PLANT CONDUCTIVITY DESCRIPTION OF DISCREPANCY: RECORDER PRINTED VALUES ARE NOT EASILY READ OR DISTINGUISHABLE RECOMMENDATIONS: NO ACTION. RECORDER IS APPROPRIATE FOR PLANT CONDUCTIVITY ACTION: APPROVED DY GSU MANAGEMENT 4 E&DCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 , IMPLEMENTATION SCHEDULE: i l O f
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/CO/84 HED NO.s 34O REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECELIST NO.: B3.10 CHEClLIST AREA: INSTRUMENTATION AND HARDWARE PANL, WORES T AT IOf J NO. P869 ( 1.) ISST-CRYO 6 PLANT CONDUCTIVITY DESCRIPTION CF DISCREPANCY: NO COLOR LAEELING FOR ASSOCIATED RECORDER PEN RECOMMENDATIONS: ADD LABELING TO INDICATE FEN FUNCTIONS ACTION: AFFROVED DY GSU MANAGEMENT ElDCR# ISSUE DATE / / FDDRM ISSUE DATC / / CRITICALITY RATING: ! IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER O
HUMAN ENSINEERINS DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT 1 DATE: 02/24/04 FiEEE) b4 C3 . s 52 44 7F REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA COURCE: OWR OWNERS GROUP CHECKLIST NO.: D3.10 CHCCULIST AREA: INSTRUMENTATION AND HARDWARE I I i 1 PANCL/ WORKSTATION NO. P870-51 ( 1.) 1 MSS-FR31 MN ST FLOW TO 1 MSP -1/2 4 1 l DESCRIPTION OF DISCREPANCY: NEED COLOR AND SCALE DETAIL ON LABEL J RECOMMENDATIONS: ADD LABEL TO INDICATE FUNCTION OF EACH PEN & ADD SCALE UNITS
!C) ; ACTION:
1 APPROVED BY GSU MANAGEMENT 1 ELDCR# ISSUE DATE / / j FDDR# ISSUE DATE / / CRITICALITY RATINO: 0 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i I i C:) l s 4
HUMAN ENGINEERING DISCREPANCY REICORD RIVER BEND NUCLEAR PLANT DATE: 02/08/84 F4 EE E) P4 E3 . s 2505 E3 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: DWR OWNERS GROUP CHECI' LIST NO. : D!.2 CHECLLIST ARCA: INSTRUMENTATION AND HARDWARE PANEL /WORESTATION NO. PO67 ( 1.) ISGT-CRYD6 PLANT CONDUCTIVITY DECEFIPTION Of DISCREPANCY: THE RECORDER PAPER IS LINEAR AND THE SCALE IS LOG RECOMMENDATIONS: g THE SCALE ON THE RECORDER IS DOTH LINEAR AND LOG. THE PAPER USED AT THE W PRESENT TIME IS LINEAR DUE TO AVAILADILITY. THE PROPER PAPER WILL DE ORDERED AND INSTALLED. ACTICN: AFFROVED DY GSU MANAGEMENT ELDCRW ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD O l
HUMAN ENGINEERING DISCREPANCY RECORD l RIVER BEND NUCLEAR PLANT f~^ DATE: 02/07/84 HED NO x 95 REVIEWER: BARKS / CHASE /SPANKLE TRACKING STATUS: SCHEDULE PHASE DAT A EDURCE: BWR OWNERS GROUP CHECKLICT NO. B3.3 CHECl: LIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-71B ( 1.) i DESCRIPTION OF DISCREPANCY: I THERE ARE NO ALARM POINTS ON THE ANNULUS TEMP RECORDER RECOMMENDATIONS:
; SCALES WILL EE MARLED TO INDICATE NORMAL / ABNORMAL RANGES.
ACTION: APFROVED BY GSU MANAGEMENT Et,DCR M ISSUE DATE / / FDDR# ISSUE DATE / / 1 1
! CRITICALITY RATING 3 i
IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 57. POWER I 4 l
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HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/20/04 F4 EE I) b4 E3 - = ~P 1 7F REVIEWER: BARKS /MATSON TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: D3.5 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANCL/ WORKSTATION NO. P622 PANEL /WORKSTATIOt1 NO. P642 PANEL / WORKSTATION NO. P632 PANEL /WOFU ST ATION NO. P623
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DESCRIPTION OF DISCREPANCY: FOR RECORDER CHARTS, WHERE FAST TRACKING RATES OR TRENDS ARE PERIODICALLY REQUIRED, THERE IS NO HI/LO SPEED CAPABILITY. RECOMMENDATIONS: IN CONJt'NCTION WITH OTHER CONTROL ROOM INDICATORS, THE DESIGN IS APPROPRIATE. NO ACTION ACTION: AFFROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / /
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CRITICALITY RATING: 3 l IMPLEMENTATION SCHEDULE: 1 i l O
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: OC/C7/04 HED NO 54 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
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DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B4.1 CHECMLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808-85C1 ( 1.) l
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DESCRIPTION OF DISCREPANCY: THE BLUE AND WHITE INDICATORS ON THE HARRIS PANEL ARE AMBIGUOUS RECOMMENDATIONS: LADEL THESC INDICATORS ACTION: APPROVED DY GSU MANAGEMENT Et<DCR# ISSUE DATE / / FDDRM ISSUE DATE / / [ CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
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F4UM AN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT O DATE: 02/27/84 F4 EE E) b4 E3 . s d2 E3 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B4.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORESTATION F40. P808-85C1 ( 1.) DESCRIPTION OF DISCREPANCY: THERE ARE NO BARRIERS FOR THE PUSH BUTTONS LABELED 4160 BUS CW AREA AND CIRC. WATER AREA RECOMMENDATIONS: SERVICE WATER PANEL INSERT DOES NOT REQUIRE BARRIER. NO ACTION. ACTION: APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND NUCLEAR PLANT g t ) V DATE: 03/01/84 - HED NO.s 15O REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B4.4 CHECKLIST AREA: INSTRUMENTATIOb (. 1 HARDWARE PANEL / WORKSTATION NO. GENERIC ( 1.) DESCRIPTION OF DISCREPANCY: THERE IS NO POSITIVE MEANS OF DIAGNOSING FAILED INDICATOR LIGHTS,1)COULD NOT OPERATE, BUT APPEARS OK ON SEISMIC ANNUC. 2) MAY BE A PROBLEM ON PLANT V6 TRANSDUCER CONDITIONER CHAN FAULT LIGHTS RECOMMENDATIONS: s_/ AN OVERWHELMING MAJORITY OF INDICATOR LIGHTS (THAT DO NOT HAVE A LAMP TEST FEATURE) HAVE A RATED AVERAGE LIFE OF 25,000 HRS (APPROX. 2.0 YRS). PERIODIC SURVEILLANCE TESTING AND NORMAL OPERATION OF SYSTEMS WILL VERIFY THE LIGHT STATUS FOR MOST SAFETY-RELATED COMPONENTS. IN ADDITION, GSU OPERATIONS WILL PERFORM A VISUAL WALKDOWN OF THE CONTROL BOARDS AT EACH SHIFT CHANGE. LIGHTS THAT SHOULD DE LIT BUT ARC NOT WILL BE NOTED AND PROMPTLY CHANGED. IT IS RDS OPERATIONS POLICY TO PROMPTLY REPLACE BURNED OUT LIGHTS NOTED DURING SYSTEM OPERATIONS. THIS COMBINATION OF LAMP STATUS SURVEILLANCES AND LONG-LIFE BULBS PROVIDES SUFFICIENT ASSURANCE THAT BURNED OUT LAMPS WILL NOT ADVERSELY EFFECT PLANT OPERATIONS. ACTION: APPROVED BY GSU MANAGEMENT. ELDCR# ISSUE DATE / / FDDRM ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
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HUMAN ENGINEERING DISCREPANCY RECORD R I V8E R BEND NUCLEAR PLANT DATE: 02/28/84 Fi EE E) bJ C3 a 7P 41 *5 REVIEWER: BARKS /MATSON TRACKING STATLS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECLLIST NO.: B4.5 CHECLLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WOREST AT IOt1 f 40. P614 DESCRIPTION OF DISCREPANCY: FOR INDICATING LIGHTS, THE BULB REPLACEMENT IS NOT EASILY AND SAFELY PERFORMCD. CANT 40T FIGURE BULB REPLACEMENT FOR RAD MONITORS. RECOMMENDATIOt45: BULBS ARE CHANGED BY PUSHING ON ONE SIDE OF " INDICATOR ONLY" BUTTON. THIS RELEASES BUTTOr4 TO MAKE BULDS ACCESSIBLE. NO FURTHER ACTION ACTION: APPROVED BY GSU MANAGEMEt4T ELDCR# ISSUE DATE / / FDDR# ISSUE DATE / / CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE: O
1 l HUMAN ENGINEERING DIBCREPANCY}}