ML20125C460
| ML20125C460 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/31/1985 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20125C454 | List: |
| References | |
| NUDOCS 8506120054 | |
| Download: ML20125C460 (239) | |
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DETAILED CONTROL ROOM DESIGN REVIEW
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SUMMARY
REPORT SUPPLEMENT-RIVER BEND STATION-UNIT-1"
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g-TABLE OF CONTENTS Page SECTION 6.0 'DCRDR
SUMMARY
REPORT SUPPLEMENT.............................. 1 6.1 Introduction......................................................... 1 6.2 Human Factors Specialist Continued Participation..................... I 6.2.1 .HED Resolution............................................... 1 6.2.2- HED Verification............................................. 2 6.3 Task Analysis Documentation.......................................... 2 .
6.4 . Control Room Survey.................................................. 5 6.5 Updated'Information For SER Listed HEDs.............................. 16 6.6 : Main Control Room M:dification Verification. . . . . . . . . . . . . . . . . . . . . . . . . . 16 L- Appendix A Task Analysis Worksheet - Scenario A.......................... A-1 Appendix B Cuidelines For Documentation Of Instrumentation & Controls.... B-1 Appendix C Instrumentation And Control Data Sheet Examples............... C-1 Appendix D . Equipment Characteristic Forms................................ D-1 Appendix E -Equipment Suitability Form And Associated HEDs................ .E-1
. Appendix F Safety Evaluation Report HEDs From T.E.R. Appendix A.......... F-1 Appendix G -Safety Evaluation Report REDS From T.E.R. Appendix B.......... G-1
-Appendix H DCRDR Summary Report HEDs With Schedule Changes............... H-1 t-
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1 6.0 DCRDR
SUMMARY
REPORT SUPPLEMENT 1
6.1 . INTRODUCTION This document is designed to be inserted in the RBS Detailed Control Room Design Review (DCRDR) Summary Report (Docket No. 50-458, dated 10/31/84) as section 6.0. Its purpose is to:
- 1) Close out open DCRDR items that were not previously completed due to the construction status of RBS at that time
- 2) Address all open and confirmatory items contained in the RBS Safety Evaluation Report for the DCRDR (sections 6.2 through 6.6)
- 3) Provide updated information for HEDs whose implementation schedule has changed from the DCRDR Summary Report 6.2 HUMAN FACTORS SPECIALIST CONTINUED PARTICIPATION As described in section 1.1 of the DCRDR Summary Report, GSU established a qualified multidisciplinary review team to perform the various tasks of the DCRDR. Procedures for performing these tasks were developed and included in the Summary Report and indicated the extent of participation of team members. To clarify the procedures used to resolve and implement HEDs, GSU submitted letter RBG-19,936 (Docket No. 50-458), dated January 23, 1985. This section will complement that letter by providing additional information to confirm the continued participation of human factors specialist in the remaining DCRDR activities.
6.2.1 HED Resolution The resolution of RBS HEDs required a substantial amount of plant design research to ensure accurate improvements were being developed. It was, therefore, not effective to keep 1
a human factors specialist at the site during this research period. Instead, after the design research was completed, Mr. Robert.J. Liddle (General Physics Corporation - see
. Appendix B of Summary Report for resume) reviewed the
-marked.up drawings, conventions,-and proposed changes. This' ensured that the HED corrective actions were sin compliance with human factors conventions prior to their implementation on the control boards.
Discrepancies -identified by Mr. Liddle were submitted to GSU for action. GSU worked 'with Mr. Lid'dle to resolve discrepancies- and took .necessary steps to implement acceptable human factors corrective actions.
6.2.2 HED Verification once the corrective actions are implemented on the control boards, Mr. Liddle will return to the site to participate with GSU in verifying design improvements. The objectives of this verification process are listed in section 1.3.4 of
.the Summary Report.
Throughout the HED Resolution and Verification phases, Mr.
Liddle was and is available for consultation on-any human factors problems or questions that arise.
6.3' . TASK ANALYSIS DOCUMENTATION The Verification of Task Performance Capabilities (i.e.,
availability and suitability' of displays and controls) followed the process described in Section 1.2.4 of the DCRDR Summary Report. The staff reviewed this process at a January 23, 1985 audit meeting with the GSU DCRDR team leader and GSU's human factors consultant (General Physics Corporation). The purpose of the audit was to~ determine if the ; function and task analysis and verification processes were adequately performed and documented. The audit found
-GSU had identified the discrete tasks, decisions and actions that operators need to undertake in order to carry out emergency actions. A review of GSU's documented information and control capabilities revealed that the information and control requirements iacluded more than the minimum requirements for task completion.
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The audit ~also found that the process employed in the verit'ication - - of availability and suitability of displays and controls was adequate and identified HEDs correctly.
.For. final confirmation,- .GSU was requested to provide
. written documentation in the DCRDR supplement report for at least one emergency. sequence which " unequivocally" demonstrates how it was determined that the. inventoried displays and controls provided the necessary information and control capability (i.e., verification of Availability and Suitability). .
Documentation for Sequence A, Inadequate Core Cooling, is provided with this response to demonstrate the steps followed and the . resultant data generated in the Verification process.
The Verification of Availability Land- Suitability of displays and controls was conducted in the following manner:
- 1. Task Analysis Worksheets completed through the "I&C Identification" column were accessed via the computerized database to generate an I&C alphabetical listing by scenario and task _(see Appendix A).
- 2. Guidelines for Documentation of Instrumentation and Contrcls (Appendix B) were developed to aid startup system engineers on-site to document key criteria to be used in the Verification of Suitability Process Flowchart (See Figure 1.2-9, p. 1-26 of DCRDR Summary Report) .
- 3. Data-regarding as-built instrumentation and controls was compiled on Tables 1 and 2 respectively in' the
. guidelines (See Appendix C for examples of completed data sheets).
- 4. A control room inventory list was compiled on an I&C Equipment Characteristics . Form (See Figure 1.2-8, p.
1-23) based upon a set of control board photographs of the RBS Instrumentation and Controls (See Section 1.2.3.7 of the DCRDR Summary Report) .
- 5. The Verification of Availability of displays and controls was done by comparing-the requirements in the "Information and Control Requirements" column with the "I&C Identified" column of~ the Task-3 i
Analysis Worksheet. For detailed comparison of the parameter, range, scale, etc. in the Verification of Suitability step below,.as-built display and control characteristics were provided in the control room inventory I&C Equipment Characteristics forms and in the Verification Tables 1 and 2 (See Appendix D).
- 6. If the displays and controls were available to meet the task requirements, a "Y" was entered on the Task Analysis Worksheet in the " Avail." column for that task. If there was no display or control available, then a "N" was placed in the " Avail." column and an HED was written on the discrepancy.
- 7. The Verification of Suitability of displays and controls was conducted using the Verification Flow Chart (See Figure 1,2-9, p. 1-26 in DCRDR Summary Report). If a control or display was available, then the relevant characteristics in the "Information and Control Requirements" column were compared with the as-built display and control characteristics. The as-built display and control characteristics were provided in the I&C Equipment Characteristics form and in the Verification Tables 1 and 2 (See Appendix D). General Physics subject matter experts and human factors personnel made the Verification decisions based on the data described above.
- 8. If the displays and controls did not satisfy all three decision points in the Verification Flowchart, then a "N" was entered on the Task Analysis Worksheet in the " Suit." column. The decision point (s) not satisfied were checked on the Equipment Suitability HED form and the discrepancy was subsequently written up as an*HED (See Appendix E).
If the displays and controls did satisfy all three decision points in the Verification flowchart, then a "Y" was entered on the Task Analysis Worksheet in the " Suit." column (See Appendix A).
- 9. All HEDs generated from the Verification of Availability and Suitability of displays and controls were reviewed by the DCRDR team using the HED Assessment process described in the DCRDR Summary Report in section 1.3.
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In summary, the Verification of Availability and Suitability of displays and controls followed a systematic process to compare the Information and Control requirements )
identified in the task analysis worksheets with the !
as-built RBS Instrumentation an Controls (I&C) present in the main control room. General Physics subject matter experts and human factors specialists conducted the Verification with the support of GSU startup engineering personnel and the GSU DCRDR team leader.
6.4 CONTROL ROOM SURVEY COMPLETION On May 2, 1985, R. Liddle, D. Chase, and D. Looney completed the remaining control room survey items. The BWROG checklist items that were completed included lighting, noise levels, communications, HVAC, availability of procedures, and adequate protective clothing. The team used the same methodology for completion of these checklist items as was used in the original survey (section 1.2.2 of Summary Report).
For the lighting survey, the average readings were approximately 80 ft. candles for normal lighting and 20 ft. candles for emergency lighting. All individual readings were greater than or equal to minimum levels listed in NUREG-0700. The average noise level reading was approximately 45dB.
As a result of this survey completion effort, three HEDs
(#875, 876, 877) were generated. These HEDs all relate to labeling on the remote shutdown panels and are included in the pages that follow.
In addition to the completion of the above stated items, the evaluation of several HEDs was completed. These HEDs were written during the original ~ survey (section 7.5 of Summary Report) but were left open pending panel completion. These HEDs are included in this report and are located after the three (3) new HEDs described above.
NOTE:
Updates to the text of original HEDs are indicated as follows:
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- HUMAN ENGINEERING DISCREPANCY RECORD 3R ,
. RIVER -BEND NUCL EAR. P L_ A N T .
cDATE:;05/02/85' HED NO = 875
-REVIEWER:. LIDDLE / CHASE / LOONEY TRACKING STATUS: SCHEDULE PHASE
. - - - - - - - - . =. --- -------------------------------------
~
- DATA SOURCE: .NONE
.. CHECKLIST-NO.: i i
LPANEL/ WORKSTATION NO. 1RSS-PNL102
(-1.)-
' - _ =- .= ---------------. ----------------------------------- .
LDESCRIPTION OF-DISCREPANCY:
"THE NOMENCLATURE ON LABELS IS NOT CONSISTENT WITH CONTROL ROOM LABELING.
-RECOMMENDATIONS:
REVIEW NOMENCLATURE OF ALL LABELS OR THIS-PANEL AGAINST,RBS NOMENCLATURE CONVENTIONS AND CHANGE LABELS THAT DIFFER.
IACTION:
- THE: REVIEW IS COMPLETE.-LABELS THAT-WERE NOT CONSISTENT WITH CONVENTIONS WILL BE CHANGED.
E&DCRM -ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 6
c.
HUMAN. ENGINEERING " DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT U DATE: 05/02/85 HED N O -= 876 REVIEWER: LIDDLE / CHASE / LOONEY 'TRACKINU di(,TUS: SCHEDULE PHASE
_- = - - - - - - - - _ _ _ _ _ _ _ _ _ - - - - - . - - - - _ - -- __________- :-- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
DATA SOURCE: NONE'-
CHECKLIST:NO.:-
- PANEL / WORKSTATION NO. 1RSS-PNL102
('1.) t
= DESCRIPTION OF DISCREPANCY:
.THE' TYPE SIZE IS_NOT CONSISTENT ON ALL LABELS RECOMMENDATIO'NS:
' REPLACE LABELS THAT ARE NOT CONSISTENT.
ACTION:
3NCONSISTENT LABELS WILL BE REPLACED.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
-CRITICALITY RATING: '4 .
IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
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. r-HUMAN ' ENGINEERING DISCREPANCY RECORD
.R I VER- BEND NUCLEAR PLANT.
DATE: 105/62/85 HED~NO_= 877
~
REVIEWER: LIDDLE / CHASE / LOONEY- TRACKING STATUS: SCHEDULE PHASE
--- ___. --. .-==-- -- _ -----------------------------------------------
- DATA SOURCE:'NONE CHECKLIST'NO.:
- PANEL / WORKSTATION NO. 1RSS-PNL102
-(~1.)
---==- ---------------- ._ -------------------------------------- __ -
DESCRIPTION OF DISCREPANCY-
-LABELS HAVE WHITE LETTERS ON BLUE / RED BACKGROUND RECOMMENDATIONS:
CHANGE' LABELS TO BE CONSISTENT WITH CONTROL ROOM BENCHBOARD LABELING.
ACTION:
LABELS WILL BE CHANGED TO BE CONSISTENT WITH BENCH 00ARD LABELING.
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 4 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
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HUMAN ENGINEERING' DISCREPANCY RECORD RIVER BEND - NUCL_ E A R Pt_.A N T
-DATES 02/28/84 HED NO = 199 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. OENERIC
( 1.)
' DESCRIPTION OF DISCREPANCY:
THE ILLUMINATION IS SO LOW AT-THE ENDS OF THE ECCS AND BOP PANELS THERE IS NO PROBLEM WITH GLARE. WHEN THIS PROBLEM IS CORRECTED THE QUESTION OF GLARE
! SHOULD BE EVALUATED RECOMMENDATIONS:
REEVALUATE WHEN NEW LIGHTING IS INSTALLED
<<<THE LIGHTING SURVEY WAS COMPLETED ON 5/2/85. THE INCREASED LIGHTING LEVELS IN THE CONTROL ROOM DO NOT CREATE A GLARE PROBLEM >>>
l ACTION:
NO FURTHER ACTION REQUIRED
'E&DCR# P-22305 ISSUE DATE 01/11/05
- FDDRM ISSUE DATE / /
, __= -- _________________________________________.______________________.______
CRITICALITY RATING: 5 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 9
v-
7.
- HUMAN ENGINEERING DISCREPANCY RECOR,D
' RIVER BEND NUCL EAR PL ANT
'DATE: 02/29/84 HED NO. :: 24
' REVIEWER:-BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- --------------------------------: ---------------------= .------=_ --
LDATA SOURCE: BWR OWNERS GROUP CHECKLIST'NO.: A1.3
~
' CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO.~1RSS-PNL102
( 1.)
- - - - - - - - - - - - - - = - = - - - - - - - - - - - - - - - - - - - - = - =___----------------_--------___-----
DESCRIPTION OF DISCREPANCY:
PANEL UNDER CONSTRUCTION NO LABELS RECOMMENDATIONS:
EVALUATE LABELING AFTER PANEL CONSTRUCTION IS COMPLETE
~<<<THE EVALUATION IS COMPLETE. HEDs 075,876,& 877 WERE GENERATED AS A RESULT >>>
ACTION:
SEE ABOVE REFERENCED HEDs FOR CORRECTIVE ACTIONS AND IMPLEMENTATION SCHEDULES.
E&DCR4 ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATINO: 5 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 10
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e HUMAN ENGINEERING. DISCREPANCY RECORD
^
RIVER BEND NUCLEAR PLANT DATE: 02/28/84 Fi EE I) P4 03 - = 1 C) E3 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA' SOURCE: BWR OWNERS GROUP.
CHECKLIST NO.: A1.4 .
- CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-74C
( 1.)
PANEL / WORKSTATION NO. P863-75C
( 1.)
DESCRIPTION OF DISCREPANCY:
THE PANEL HAS HOLES IN IT.BECAUSE IT IS BEING RE-DESIGNED RECOMMENDATIONS:
- REASSESS AFTER COMPLETION OF RE-DESIGN
~<<< PANEL WAS ASSESSED ON 5/2/85. ALL HOLES HAD BEEN COVERED. DESION CHANGE
-PROCESS CALLS FOR HOLES TO BE COVERED WHEN AN ITEM IS REMOVED.>>>
. ACTION:
NO FURTHER ACTION REQUIRED I
E8<DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
S CRITICALITY RATINO: 5
. IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 11
+
-HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
.DATE:
- 02/29/84 HED NO. = 31 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS:' SCHEDULE PHASE
_=. ----_--__----------- _ ---_______-____--______-__--____ --_______ _
DATA SOURCE: BWR OWNERS GROUP
.s CHECKLIST NO.: B2.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE
. PANEL / WORKSTATION NO. 1RSS-PNL102
( 1.)
_ _ _ .= _ = _ _ __-_-----____________________________-______-__________ __-_-___
DESCRIPTION OF DISCREPANCY:
NO PERMANENT LIGHTING INSTALLED RECOMMENDATIONS:
INSTALL PERMANENT LIGHTING AND TAKE LIGHTING READINGG
<<< PERMANENT LIGHTING IS INSTALLED AND LIGHT READINU'.3 WERE TAKEN ON 5/2/83 DY
'R.J. LIDDLE AND D.A'. CHASE. ALL LIGHT READINGS WERE ABOVE MINIMUM LIGHTING LEVELS LISTED IN NUREG- 0700.>>>
ACTION:
NO FURTHER ACTION REQUIRED
'I..
E8<DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
' CRITICALITY RATING: S IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD .
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m.
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT
<DATE: .02/29/84 l-l E D N O :: *2 O REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
- = - .
i DATA SOURCE: BWR OWNERS GROUP
' CHECKLIST NO.: B3.1 CHECILIST AREA: INSTRUMENTATION AND HARDWARE
. PANEL / WORKSTATION NO. 1RSS-PNL101
( 1.)
DESCRIPTION OF DISCREPANCY:
- TIGRAPH-100 RECORDER WAS NOT EVALUATED BECAUSE IT WAS NOT OPERATIONAL RECOMMENDATIONS:
EVALUATE WHEN OPERATIONAL
<<<THIS RECORDER WAS EVALUATED ON 5/2/85 BY R. LIDDL E , D. CHASE, AND D.
LOONEY. THE APPROPRIATE CHECKLIST SECTION WAS COMPLETED AND NO HEDs WERE GENERATED AS A RESULT >>>
ACTION:
NO FURTHER ACTION REQUIRED Et<DCR# ISSUE DATE / /
FDDR# ISSUE DATE /
CRITICALITY RATINO: 5 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 13 e.____________-.___-
.s HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
' DATE: 02/23/84 HED N O :: 481
. REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE:.DWR OWNERS GROUP CHECKLIST NO.: B3.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-1 DESCRIPTION OF DISCREPANCY:
- PRINTED VALUES FOR RECORDER CHARTS ARE NOT EASILY READ AND DISTINGUISHABLE.
(N/A-STILL DEING INSTALLED.)
RECOMMENDATIONS:
- EVALUATE RECORDER AFTER INSTALLATION IS COMPLETE.
< < THESE RECORDERS WERE EVALUATED ON 5/2/05 DY R. LIDDLE, D. CHASE, AND
' D. LOONEY. THE APPROPRIATE CHECKLIST SECTION WAS COMFLETED AND NO HEDS WERE
- OENERATED >>>
ACTION:
NO FURTHER ACTION REQUIRED ELDCR# ISSUE DATE / /
FDDR3 ISSUE DATE / /
__m____________________________________________________________________________
CRITICALITY RATING: 5
' IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 14
i ' HUMAN ENGINEERING DISCREPANCY RECORD-RIVER BEND' NUCLEAR PLANT HED
-DATE: 02/27/84 N O . :: *? 4 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.:-B3.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863-71D
( I.).
DESCRIPTION OF DISCREPANCY:
IN SIMULATOR THE ANNULUS TEMP. RECORDER HAS THREE PENS THE CHART PAPER HAS 2 SCALES RECOMMENDATIONS:
EVALUATE CONTROL ROOM RECORDER AFTER INSTALLATION.
<<< THIS RECORDER WAS EVALUATED ON 5/2/85 DY R. L.I D D L E , D. CHASE, AND D.
LOONEY. THE APPROPRIATE CHECKLIGT SECTION WAS COMPLETED. AS A RESULT,.THE RECORDER LABEL WILL.DE CHANGED (PRIOR TO EXCEEDINO 5% POWER) TO INDICATE A BPARE CHANNEL.>>>
ACTION: *
'NO FURTHER ACTION REQUIRED E&DCR4 ISSUE DATE / /
FDDR# ISSUE DATE / /
l.
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CRITICALITY RAT (NG: 5 l
IMPLEMENTATION SCHEDULE: PRIOR TO EXCECDING 5'/. POWEP l~
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u----------______------------
e 6.5 UPDATED INFORMATION FOR SER LISTED HEDS This section was developed in response to Appendices A and B of the Technical Evaluation Report (attached to the staff's DCRDR SER) to provide GSU's position on each of the listed HEDs.
GSU's program for implementation of enhancement corrective actions is based on a plan to uniformly install these changes on a panel-by-panel basis. An implementation schedule of " prior to exceeding 5% power" was used to allow sufficient time for the completion of the affected panels. GSU began work on the NSSS panels first since these panels control the vital systems required for fuel load. Once the NSSS work was completed, the BOP panels within the operator controls area began, followed by the remote shutdown panels and back panels. As a result, in general, the HED corrective actions for P680, P601, and P877 shall be completed prior to fuel load. The BOP and remote shutdown panels and generic corrective actions shall be completed prior to exceeding 5% power.
The HEDs in Appendix F & G have been updated to reflect their current status, implementation schedules, and any additional information requested in the DCRDR SER.
Justification or interim corrective actions are included on HEDs that have an implementation schedule that varies from the SER position. The HEDs are listed in the same order as they appear in the SER.
Appendix H contains HEDS whose implementation schedule has changed since their submittal in the DCRDR Summary Report.
6.6 MAIN CONTROL ROOM MODIFICATION VERIFICATION The on-going human factors maintenance plan, as discussed in section 1.3.5 of the Summary Report, is in place and being implemented under an approved site procedure (PEP-0006). Changes affecting the human factors design of the main control room, including those resulting from the DCRDR, have been or will be verified to assure that the desired correction has been obtained without introducing 16
new HEDs. Mr. R. Liddle shall be participating in the review of corrective actions resulting from the DCRDR. To date, this review team has reviewed completed drawing markups and conventions and made plans for mockups of certain changes to assure that the anticipated corrective actions are obtained. As discussed in section 6.2.2. of this report,. Mr. Liddle shall also assist ~ GSU in verification of completed corrective actions.
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APPENDIX A
- TASK ANALYSIS WORKSliEET SCENARIO A : INADEQUATE CORE COOLING A-1 t
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Pc me. 16 01101 0 RIER BC3 S'ATION TASA AdLYSIS WORKfwfET SEau RS EDP RAEPS TA6KISutTAEK CEEW LIEAT!W ACTION IWOAMTION EDS PAEL Conl0OT MIL SUIT SOURCE SubaE EeulEENTS 4 CONTA0L ID sueES LOCAlik RE0uiEENTS 1650 P061110N TO OPEN RPCCW E 55 IslLATION VIILVES DISCETE M70 stIH10V34 Y Y SIE PF ISOLATION CtVELL CONTR(L CAPASILITY CONTROLS, ,142,169,1 SUPPLV ISIL., CAD Ant STATUS Ine!CATOR 63,144,143
. SPPLY, DAVELL RETURN LilblTS INB. ISIL., BRfEl.L KiuRN OUT80. ISOL.
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APPENDIX B GUIDELINES FOR DOCUMENTATION OF INSTRUMENTATION AND CONTROLS B-1
.' General Physics Corporation i
\
MEMORANDUM DA TE: cruly 20. 1994 GP-M-212118 TO: Bob Price FROM: nnn n,,, mr
SUBJECT:
nas vn.er,,m.neneinn .na enneral ,
Characteristics (DCRDR Verification Phase)
Enclosed are " Guidelines for Documentation of Instrumentation and Controls." These guidelines have been developed as part of the Detailed Control Room Design Review (DCRDR) to assist those engineers who will have responsibility for providing information requisite to the DCRDR phase of verifying equipment suitability. l i
Please note that the attached guidelines contain three attachments and j two tables. Attachment 3 contains a listing of components for which Tables
-1 and 2 must be'completedc If the component identification is not sufficiently clear, the Task and Element description may provide clarifica-tion. Although there are nine columns on Table 1, please complete columns 1 through 5, and 8. Complete all columns of Table 2. The information you will be providing should be "as built" information. Therefore, please obtain all information from the control room, not the simulator. Finally, please use separate tables for each system.
All completed tables must be returned to Columbia by no later than August 6, 1984. If you have any questions, please call Rich Staan. The balance of the information will be completed by Startup Engineers onsite.
Don Chase will be coordinating the latter review onsite.
Enclosures .
cc: L. Baker D. Chase (GSU) ;
B. Byrd
-1. .A.
f!'C)Ch l
B-2
. VERIFICATION OF INSTRUNENthTIM AND C W TROL SUITABILITY ISSUES 1
GUIDELINES POR DOGDEENTATION OF INSTRUNENTETIM AND CWTROEA One objective of the Detailed Control Room Design Review being ,
performed for the River Bend Station is to determine the input and I output requirements of the control room crew for emergency operation and to ensure that required systems can be efficiently and reliably operated under emergency conditions by available personnel. Specific-ally, the DCRDR seeks to identify all information sources and control devices needed to 1) initiate, maintain or remove a system form service, or change a system configuration, 2) confirm that appropriate system response has or has not occured (i.e. feedback), or 3) make a decision regarding plant or system status. To this end, please provide the following information on copies of the attached Tables:
l Table 1: Instrumentation i Column 1: Control Room Output Parameter Provide the output parameter being displayed (e.g. flow, pressure, level, speed, position, amps, watts, etc.) Please be as specific as you can (e.g. CRD pusp amps, reactor feed pusy suction pressure, ,
wide. range react.or. water level, RCIC turbine speed, MSIV, position, etc.),
, , )
Column 2: Control Room Output Device Provide the means by which the output parameter in coluen 1 is presented to the operator (controller, mater, recorder, digital display, indicating light,~etc.)
i Column 3: I.D. #
, Provide the I.D. # for the output device described in column 2.
This number sky be provided by P&ID's, Instrument Data Sheets or any other traceable document.
Column 4: Control Room Output Device Range'and Units i Provide the range of the output device (e.g. 0 - 7000 gym) and the units in which the output is displayed (e.g. Is flow displayed in gym or Ibe/hr, is pressure displayed as peig or inches of water, etc.) If the output device is and indicating light displaying pump or valve status, etc., enter N/A.
Column 5: Location of Information or Control Device Use Attachment 1, Panel Insert Numbering, to provide the necessary information. For example, RCIC cosponents are provided on Panel
, 601, Insert 21. This may be written as P601/21. NOTE: You need not provide any information for information sources or control devices located on panels other than those shown on Attachment 1.
i I
r B-3
i Colusm 6: Output Device signal source Provide a description of the device measuring, directly or in-directly, the parameter being displayed (e.g. pressure transmitter, flow element, limit switch, conductivity element, etc.) This information may be provide by P&ID's, Instrument Data Sheets or any other traceable documents.
Column 7: I.D. #
1 Provide the I.D. # for the signal source described in column 6.
Column 8: Direct or Indirect
Indicate whether the information provided in the control room is direct (D) information or indirect (I) information (e.g. is indicated flow measured directly by a flow element or indirectly by a differential pressure transmitters does the SRV indicating light provide valve status or solenoid status; etc.) Attachsant 2, DCRDR Flow Chart, is provided for your review.
Colusm 9: SPDS (SEE BEIOf)
Table'2: Controls Column 1: Device, Paratreeter or Display Controlled Provide a specific description of every device, parameter and display associated with your assigned system (s) which can be controlled from the control room (e.g. RCIC pump flow, Reactor Mode, Core Map displays, reactor water level, recirc. flow control valve position,etc.) Once again, you need only adress those controls provided on the panels and inserts of Attachment 1.
Column 2: Control Room Control Device Provide a description cf the type cif device used to control the items listed in coluen 1 (e.g. switch, pushbutton, controller, etc.)
Column 3: I.D. #
Provide the I.D. # of the control room device described in column 2. This information may be provided by P&ID's, Instrument Data Shsets or any other traceable documents.
Column 9: Safety Parameter Display System (SPDS)
Indicate with a Yes or No whether the parameter is indicated on the SPDS.
B-4
._ _ = _ . ,.. _ _ _ . _ _.
Column 4: Control Device States J Provide all control device states for items in column 2 (e.g., 3-position rotating collar pushbutton - ARM / DISARM; switch - STOP/AUT0/ START comuously variable controller - AUTO / MANUAL)
Colusn 5: Location of Control Device Using Attachment 1, provide the Panel / Insert number as done for Table 1.
Column 6: Direct or Indirect Indicate whether the device, parameter or display is controlled directly (D) or indirectly (I) (E.G., Is recirculation system flow controlled by means of a flow demand signal or a flow control valve position demand
' signal, etc.)
The above listed information .should be provided for ALL instrumentation If and control devices located on those panels shown on attachment 1.
r.equired information is unavailable, please indicate this by entering N/A
-in the Dppropriate. column.- ,
The Information and Control column of Attachment 3 presents a listing of some of the data needed. Please note that the level of detail needed for Tables 1 and 2 is more extensive than that provided on Attachment 3.
Finally, please provide the system name and d!sijnationl (e.g.,
B21, C11, etc.) in the space provided at the top of each tab e.
1 i
- f s
I i
I B-5
1 System Name System designation TABLE 1 0 INSTRUDElNTATION (signals Originating Outside Control Room) Y
?
h O
Control Control Room Room Output y Control Room Location of Device y~
Output ,
Output Output Device Information or Signal u Parameter Device I.D. # -
Range & Units Control. Device 3
D m Source I.D. #
e
O D TABLE 2 System Designation COIFFROLS (Signals originating Inside control noem)
Device, Parameter or Display control Room Controlled Control Device Location Direct /
Control Device I.D. 8 States of Device Indirect
~
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e 9
9 9
9
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INSTRUCTOR CONSOLE .
oe>
PANEL INSERT NUMBERING (NoT 70 scALs)
B-8 i
~
RIVER SEND Flow Chart of Decision Proesse for Verifying Equipment Suitability ATTACHMENT 2 DCRDR For every task in the task snetysis,wr.
Ify that the equipment specified is suitable to meet the demands of emer.
gency contingencies.
I CRITERIA FOR DECislONS Does the equipment HFE/Opg povide appropiate M O information displayed to appropriate information/feedbacl.
- g .
modality (visual vs. euditory) for the l task?
O Appropriate parameter displayed i O Display of guentitative and/or quellte-tive information appropriate for task any g, . ,
YES o Discrete / continuous sontrol functions Spropriate mileWe dich provides O Displey of trend information avelleWe appropriate tuhen apprcpriate information/
- feedteck?.
i p_ YES Does
~ the equipment provide actual
- NO system status information?
lac *(direct) r O Actuel system / equipment status infor.
motion is provided rather than indirect Information (e.g., demand vs. valve position for controllers, direct vs. in-
[ leany other equipmefit YES direct measure of flow in system loop) available that provides appropriate information and reflects actual system NO status?
3r YES HFE/ ops /l&C '
O Equipment provides appropriate pre- g, eision and range of control the O Scale units are consistent with the de- equipment NO yes of precision needed useable?
O Seele tenge spens the expected range U I U i of operationet parameters O Wlues dispieved are in a form immedi. HED stely useable w/o conversion ygg IDMFIED U .
EOUlpMENT MEET $
SUITAtlLITY REQUIREMENTS FOR TASK PERFORMANCE oe44:30 B-9 m ..
8 ATTACHMENT 3 t
l PAK DC. 80001
, 87/88/84
! . I & C ALPNA LISTINS
- i i CEDW4 DENT SCEN MO PABEL LOCAT TASK & ELE 8EteT ;
! SCCD-fq0W158,159,192 A 3668 PS78 55 POSITION TO OPEN CONTAlpSENT IETURN Ioanaan Iggs,mIgB8,CONTAI8eqENT AETURN OUTBOARD ISOLATIEDt. CEBIT.9ERVICE AIR 19tE VALVES
] 1630 pe79 55 POSITION TO OPEN ApCCW ISOLATION DetVWELL SISPLY ISOL., CAD SppLY, 3CCP-eWV38,142,169,1 A
' 63,144,143 DAvtELL NETURN IND. ISOL., DAVtELL AETURN (RJTBD. ISEL. VALVE ,
I 1CMB-AA258 C GS Pees e3 MONITOR DAYWELL TEMPEftATUAE 3 CMS-AA258 C GSS POSS 43 MONITOR CONTAINMENT INDICATICBGB 3 CMS-Pet 2GA .
scus-TA443 l 3C86-PARA B 718 POSS/ S3 MONITOR DAVWELL/CONTAIDSENT PREamaer ;
}
G88 j ICMS-PAEA, A 1329 Pees 43 OBSERVE DAYWELL TEMPEltATUE Ape PRESSURE i SCest-TAV42A
' SCMS-PA28 D 480 peOS 83 OBSERVE CONTAINMENT /DAYWELL PRES 9UAE S CseS-PA29 D Sie POSS 83 IserOISq SHIFT SUPERVISOA OF St@pAESSION POOL HIEDI LEVEL ALAAM
, SCMS-PA23 D 529 POSS S3 OSSEftVE SUPPRESSION POOL LEVEL 1CseS-PA2B D 538 POSS 83 MONITfMI DetYtELL PRESSURE 3 CMS-PA28 C 748 PeOS S3 MONITOft CONTAINMENT TEppERATUIE AIG SISORESSION POEL TEppEftRTURE SCMS-TA488 '
IC86-TR244 D RSS POSS 84 OBSERVE StPPIESSION POOL TEppERATURE g
250 Peet 83 OBMAWE SuppfESSION POOL TEppEARTURE
) a 3 CMS-TA248 D INFOApe CONTROL fBOOM CAEW StPPIESSION POOL TEspEATUK GIEATER THAN 200 j 5 1 CSS-TA248 9 478 Pees S3
, 1CSES-Tit 249 A 2330 pese 43 OSSERVE SuppfESSION POtX. WATER LEVEL
- SCMi-LI235 3 CMS-TA414,3 3 1250 pass 83 MONITOft DAYWELL TEppEftATURE l
! IWOlent SHIFT FOREfeRN OF DetVtELL TEspEftRTUIE ftND PRESSURE
! 1 CMS-TA414 TA413,PA2 3 75 POSS S3 l A,PAES SCset-TA414 C 318 POSS S3 INFORM CONTROL ADON CAEW DetVtELL TEppEftATUAE STitATINE TO DECAEASE AND i 1Caes-TID 4em. SuppMSSION POOL TEppEATURE DECREASING i 3 CMS-TAN 422, C 958 PeOS S3
- INFOAM IF CNTNMT TEpp. IS 75 DEGREES F. D/W PfESS. IS 3.5 LBS., AND 1CDeS-PitaA,
- DetVtELL TEMP. IS SAEATER THAN Ese DESAEES F !
t 3CpW-78414 SCse-MOV125, A 3698 PS79 DAMS POSITION TO OPEN CONDESATE 9eAME-UP CONT.ISOL. CONT. SDftV6 DELL EST.DftAIN l 18ER-AGP127 OUTS.ISOL.,BACMWASH TANK DRAIN CONT. ISOL. VALVES 6 1HCS-seOV172 5
1CNS-seOV325 A 2000 Pe7e 55 AEGUEST FROM TM SHIFT FOREMAN IF HE UNISOLATED TM MISCELLANIOUS
]
1BER-Alp 127 DitYtELL AND CONTAINMENT VALVES j
j 3CCpUEOV158,159 1 1 andCS-#EDV172
! KE DELOh8 3Cpet-1FN S A B 1918 Pe63 71 POSITION TO STAftT HYDROSEN MININS FANS j 1 cpm-1FNSB 4
ICPO4-FM1 A C See Pe63 72 POSITION TO STAftT DetVWELL HYDAGGEN MINING FANS ,
f I 1 CPM-FNIS ICpes-FM1 A C 850 Pe63 72 POSITION TO STOP DetVWELL HYDAOSEN MINING FANS ;
1CPO4-FM13 3CPet-teSW2A C 878 pe63 71 POSITION TO CLOSE OftVWELL HYDAOGEN MINIpdB INBOARD AND OUTBOAftO
- SCpel-9EOV29 ISOLATION VALVES
! 1CPee-seOV4A I
y SCPM-seOV24,3 3 1995 pe63 71 POSITION TO CLOSE .INDOAftO AND OUTBOfut0 ISOLATION VALVES j
ICP=-MOV4A,o i
't a
PAGE ND. 8e002
C7/2e/e4
. I & C ALPHA LISTINS COMPOpENT SCEN SEO PApEL LOCAT TASM & ELEMENT 3CPee-MOV2A C &&G Pe63 71 POSITION TO OPEN DAYWELL HYDROSEN MIXINS INBOARD AND OUTBOARD ACPoe-seOV4A ISOLATION DAMPERS .
, 3CPee-MOV2A B 936 Pe63 71 POSITION TO OPEN Ipannan AND DUTBOARD H2 MIXINS ISOLATION VALVES ICPM-MOV25, l ICPee-se0V48, 1CPee-se0W4A 3 CPM-MOV2B C 700 Pe63 71 POSITION TO OPEN DRYWELL HYDROSEN MIXINS INBOARD AND OUTBOARD SCPee-seDV4B ISOLATION VALVES SCPee-seDV3A . C 750 Pe63 73 POSITION TO OPEN DRYWELL HYDROSEN MIXINS OUT Imaannan AND OUTBOAAD SCPee-seVIA IBGLATION VALVES SCPee-seDV3A B Me PK3 72 POSITION TO OPEN INBOARD AND OUTBOAAD H2 MIXINS ISOLATION VALVES 1CPW-seDVIA 1CPee-seV3B ICPee-MOV1B ICPee-MOV3A C e68 pe63 72 POSITION TO r1 ner DRYWELL HYDA00EN MININS OUT INSOMD AND OUTBOAAD l
l 1CPee-stoV3e ISILATION VALVES ACPee-seDV1A SCPee-MOV1B TICPee-MOV3B C Sie PS63 72 POSITION TO OPEN DRYWELL HYDROSEN MININS Imaannan AND DUTBOMD
~ ICPee-seDV1B ISOLATION DAgePERS .
" SCPee-MOV4A & 2A A 127e P K3 71 POSITION TO CLOSE INBOARD AND DUTBOMO ISOLATION VALVES FOR HYDROSEN MIXINS :
ICPee-seDV4A B 9ee Pe63 71 POSITION TO OPEN INBORAD AND OUTBOARD ISQLATION VALVES SCPM-MOV2B 1DRS-VC1E A 1488 PM3 71 POSITION TO OFF DRYWELL UNIT COOLER 1DRS-VCID A 1230 Pe63 71 POSITION TO QN DRYWELL UNIT COOLER FAN 1E12-Feces C 566 Pe79 56 POSITION TO CLOSE HEAT EXCHANSER 3 SERVICE WATER DISCHARCE VALVE 1E12-Fe6&A C 525 P474 55 POSITION TO CLOSE HEAT EXCHANGER A SERVICE WATER DISCHMSE VALVE 1E12-F06&A E 17e Peet ce POSITION TO OPEN HEAT EXCHANSER SERVICE WATER DISCHAASE VALVE SE12-Fe6eASB D 418 Pe78 2e POSITION TO OPEN HEAT EXCHANGER A AND 8 SERVICE WATER VALVES 1E12-F042A A 17e P641 28 OBSERVE RHR SYSTEM LINE-UP ,
1EJ3-ACBee9 8 1855 P477 31 OBSERVE AND FOLLOW TRIP INDICATION ON BAEAKERS
- 1EJ2-ACaes5 1EJS-ACBe49 A 2429 Pe77 32 POSITION TO TRIP ELECTRICAL BREAKERS SEJ3-ACBS58 ()
1EJ3-AcBe66 SEJ3-ACBS25 SFWP-F164A E 166 Peel Se VERIFY LOOP FLOW 1FWS-P1A B 348 P686 e3 POSITION REACTOR FEEDWATER PUMP SWITCH TO OFF 1FWS-P1A B 1518 P680 e3 INFORM SHIFT FOREseAN OF REACTOR LEVEL AND STARTING A REACTOR FEEDWATER PUMP 1FWS-PIA,B,SC D 318 P6&G e3 INFORM CONTROL ROOM CREW FEEDWA'TER PUMPS TRIPPED 1FWS-PAA,B,4C D 525 P680 S3 POSITION TO START FEEDWATER LUBE DIL SYSTEM AND PUMP 1FWS-P1A B 925 P6&G e3 POSITION TO START -seEACTOR FEEDWATER PUMP Ace POSITION TO OPEN REACTOR 1FWS-seOV264 FEEDWATER P1NEP DISCHAASE VALVE ,
IFWS-P19A 1FWS-P1B B 744 P68e e3 POSITION TO START RFP LUBE DIL fiVSTEM START SWITCH 1FWS-P1B B 1558 P684 e3 INFORM SHIFT FOREseAN STARTING SECOND FEEDWATER PUMP AND OPENIND 1FWS-seOV269 e DISCHARGE VALVE
!WS-9198 ,
1 1 PAGE NO. 808S3 .
C7/28/84 i I & C ALPHA LISTINS COMPONENT SCEN SEO PREL LOCAT TheK& ELEMENT 1FWS-PIB B 235 P648 e3 POSITION REACTOR FEEDWATER Pu p SWITCHES f 1FWS-P1C
- j 1HOL-PSA A 2298 P688 82 POSITION TO STOP THE HEATOR DRAIN PUMPS A&S
- 1HDL-919 l ,
1 SHve-UCIC C 948 PG63 71 POSITION TO START CONTAINMENT UNIT COOLER SHVR-UCIC C SOS P463 71 OSSERVE CONTAINMENT UNIT COOLER NOT STARTING 1HVR-UCIC C 968 PG63 71 POSITION TO STOP CONTAINMENT UNIT COOLER IIAS-MOV186 A 1368 PS79 55 POSITION TO OPEN CONTAINMENT INSTRUMENT AIR ISOLATION
- 1NHS-9CCle2B A 1518 PS77 32 POSITION TO RESET SUPPY BREAKER
'1NPS-ACSSS S BSS PGSS 87/88 VERIFY AUTOMATIC TRANSFER AND'* Fm a m BREAMER INDICATIONS 1MPS-ACS11
, INNS-AC986 i INNS-ACSS7 j 1NNS-ACD14 j 1RCS-MOV61A,618,6eA, A 1348 PGGS St POSITION TO OPEN RECIRC HYDRAULIC POWER ISOLATION VALVES 688,59A,598,SSA,4588 1RCS-MOV619,618,6eA, A 1620 P681 18 POSITION TO OPEN REACTOR WATEll CLEAN-UP ISOLATICBd VALVES ESS,59A,598, sea,588 tz 1SWP-MOVSSES,5838,48 A 1220 PS70 56 POSITION OPEN "B" CONTAINMENT UNIT COOLERS AND "S" DAYWELL UNIT
! j , 58, COOLERS I N 1TMS-J111e A 19e P68e 87 VERIFY TURSINE TRIP i ITMS-JIGS D 29 P688 09 OSSERVE TURSIDE TRIP I 1TMD-JI118 I ISMS-SI l 1TMS-JI194 E 4e P648 87 VERIFY TURSINE TRIPPED 1
1TME-MOV56 C 368 PS70 54 POSITION TO OPEN MAIN STEAM SYSTEM ST VALVE
. 1TME-MOVS2 C 418 P974 54 POSITION TO OPEN STEAM SEAL EVAPORATOR ST HEATER SYPASS VALVE l 1TMS-TSN A 1595 P688 et POSITION TO START TURNINS GEAR MOTOR l ITML-1,2,3,4 A 2648 P688 09 DOSITION TO RESET THE EMERSENCY SEARING AND SEAL OIL PUMPS ,
5 SRV'S D 155 P681 19 INFORM SHIFT FOREMAN FIVE SRV*S OPEN
! ADS INITIATE 9 1548 P681 19 POSITION TO ARM ADS MANUAL INITIATION PUSHSUTTON i ADS LOGIC MAN. INIT. S 1785 P681 19 POSITION TO NORMAL COLLARS OF' ADS "A" INSTANTAMEOUS LOGIC MANUAL
, INTIATION 1 ADS LOW WATER LEVEL A 2100 P681 28 OSSERVE LOW WATER LEVEL ADS WITH CONFIRMATION INDICATORS ALL RODS C 68 P680 e6 VERIFY ALL RODS ARE INSERTED
, ALL RODS, FULL CORE E 58 P688 85 VERIFY ALL RODS IN i DISPLAY
! ANN A 1248 P688 86 DETECT VENTILATION ALARM
{ ANN A 1280 PS45 SS OBSERVE ReseUNCIATORS FOR OFF SAS SYSTEM ANN 9 10 P681 22 OSSERVE DRYWELL SUMP HISH RATE ANNUNCIATOR ANN 0 45 P6SG St OSSERVE DAYWELL HIGH ANSIENT TEMPERATURE ANNUNCIATOR i ANN 8 16e P688 SS INFORM SHIFT FOREMAN OF HISH DRYWELL PRESSURE ALARM
) ANN 8 17e PSet 44 INFORM SHIFT FOREMAN OF DAYWELL ATMOSPHERE RADIATION ALARM ,
ANN S 948 PG63 71 INFORM SHIFT FOREMAN OF CONTAINMENT UNIT COOLER DRAIN FLOW ALARM ANN 8 1138 PS70 51 IneFORM CREW OF REACTOR SUILDING FLOOR SUMP T e k F ALARM
! ANN S-4 C 48 P681 22 INFORM CR CREW OF HIGH DAYWELL PRESSURE ANN-5C A 1785 P884 83 OBSERVE SUPPRESSION POOL TEMPCRATURE ANNUNCIATOR AND VALUES I 1 CMS-PR484 r I 1 CMS-PR400 l ANN-SC Ae 2119 P681 19 INFORM CR CREW THE ANNUNCIATON IS ADS LEVEL
t 1 PAGE NO. See84 l C7/ae/84
. I & C ALPHA LISTINS j COMPONENT SCEN SEO PANEL LOCAT TASK & ELEMENT
] ANN-A4, ANN-AS, A 18 P640 82 OSSERVE AfecuNCIATORS '
ANN-54, ANN-B5, RNN-C4 ANN-83 p les P681 16 OBRERVE ANNUNCIATOR DIESEL SENERATOR (DS) RUNNINS
ANN-E5 C 37e Pe78 54 INFORM CONTROL ROOM CREW OF STEast SEAL LOW PRESSURE ALARM ANN /ACK A 395 P601 at POSITION ANNUCIATOR ACMMOWLEDGE SWITCHES ANN /ACK A 428 Pe78 52 POSITION ANNuCIATOR ACKNnWIFDGE SWITCH
! ANN /ACK A 434 Pe63 73 POSITION ApesuCIATOR ACHNOWEDGE SWITCH ANN /ACK A 450 Pete 65 POSITION ANNUNCIATOR ACNNOWLEDGE SWITCH ANN /ACK A 53e P68e 86 POSITION ANNUNCIATOR ACHNOWLEDSE SWITCHES ANN /ACK B 15 P681 28 POSITION ANNUNCIATOR ACKNOWLEDGE SWITCHES ANN /ACK D 64 P681 17 POSITION TO ACNNOWLEDGE ANNUNCIATOR SWITCHES l ANN /ACK B 37e P681 16 VERIFY AUTOMATIC INITIATION SIGNALS FOR DIVISIONS 1,2,AND 3, VERIFY
- E22-Cest PUMPS Rupe6 INS, & INFOdes FOREMAN OF STATUS
! E21-Cest l E12-Cee2A,B,C i ANNC-6 C 344 P681 19 DESERVE " CONTAINMENT /DRYWELL DIFFERENTIAL PRESSURE HIGH" ANNUCIATOR
{ ANNUNCIATORS D 18 P648 85 OSSERVE AsseUNCIATORS l APAN MATRIX A 119e P648 SS OBSERVE APRM STATUS LIGHTS l B21-Fe41D A Ele P641 19 POSITION QPEN SRV i
to 321-FG41D A 648 P601 19 POSITION renw SRV 1 Bat-Fe4lD A 2250 P6et 19 POSITION TO AUTO MAIN STEAM LINE B RELIEF VALVE W B21-FG47A B tale P688 19 POSITION TO OPEN ONE SRV B21-FG47C B 1828 P681 19 POSITION TO OPEN TWO SRV*S, ONE IN LINE B, ONE IN LINE C ,
921-F0518 321-FS51C B 57e P681 19 ADJUST REACTOR PRESSURE WITH iiRV'S l 921-Fe51D A SAS P681 19 DIAGNOGE STATUS OF ADS AND SRV?8
) B21-F0518 9 590 P681 19 AbJUST REACTOR PRESSURE WITH SRV'S B21-F05tG C 1828 P681 19 POSITION TO OPEN TWO SRV'S B21-Fe51D 1 B21-Fe65A A 2144 P648 83 FOSITION TO CLOSE THE FW HDR SHUT-OFF VALVES 1 B21-Fe658 i B21-F041B A 964 P681 19 POSITION TO OPEN SRV +
B21-R644 D 788 P648 83 MONITOR REACTOR LEVEL
! B21-R645 A S4e P681 17 INFORM SHIFT FOREMAN RPV LEVEL
! B21-R685 B 1868 P641 17 MONITOR REACTOR LEVEL ON SHUT DOWN RANGE
) 921-R618 A 348 P681 17 INFOaN CREW LEVEL ON FUEL ZONE' INDICATOR j B21-R618 A 415 P681 17 OBSERVE REACTOR WATER LEVEL i B21-R618 A 658 P681 28 INFORM RO INDICATION SHOULD BE'ON WIDE RANGE LEVEL RECORDER B21-R615 D 67e P641 16 ADJUST REACTOR LEVEL WITH HPCSNINJECTION
! E22A-Fe@4 B21-R623A A 284 P681 28 OBSERVE REACTOR WATER LEVEL B21-R6234 B 3de P681 2e INFORM SHIFT FOREMAN THAT POST-ACCIDENT MONITOR PRESSURE INSTRUMENT FAILED LOW l B21-R6234 B 1867 P681 28 INFORM SHIFT FOREMAN REACTOR' LEVEL INCREASINS B21-R623A C 230 P681 28 MONITOR REACTOR WATER LEVEL . ,
! B21-R623A C ete P601 17 INFORM CONTROL ROOM CREW REACTDR WATER LEVEL IS 60 INCHES
. 921-R623A D 448 P681 2e INFORM SHIFT FOREMAN LEVEL IS '1e INCHES l B21-R623A D , 6ee P641 28 MONITOR REACTOR PRESSURE .
.. -- . _ . . .-. - -_ ._.-_ -- . - . -- .~. . . - ~ . .,
PAGE NO. 30005 .
C7/2e/84
. I & C ALPHA LISTING COIFONENT SCEN SED PANEL LOCAT TW 4 ELE 8ENT 821-R623A48 9 210 P6et 17 MONITOR WIDE-RANGE REACTOR WATER LEVEL
! S21-R6234,9 D 710 P6el 24 MONITOR REACTOR LEVEL
- 321-R6233 A 9ee P6et 17 MONITOR REACTOM PRESSURE l 321-R6233 p 1828 P641 17 INFORM SHIFT SUPERVISOR OF REACTOR WATER LEVEL AND PRESSURE STATUS i 321-R643 H 1458 P614 Se COMPARE TEMPERATURES ON RECIRC SYSTEM S33-C001A 43 D 249 P6ae 04 POSITION TO TRIP REACTOR KCIRC Ptsps -
C33-R615A 49 333-C801448 A 2588 P6ae 04 POSITION TO STOP THE ASS RECIRC Pu es i B33-CSSIA,mi m 1B C SG P688 84 DESERVE FEEDWATER PUMP INDICATOR LIGHTS B33-Fee 3A&e A 2498 P6ae 84 POSITION TO OPEN THE RECIRC S4CTION VALVE C33-Fe23A A 2010 P6ae 84
!. S33-Fe238 POSITION TO r1 nas' THE RECIRC PUMPS SUCTION VALVES A&B
- B33-M682 B 18e P6ae e4 POSITION TO LOWER SETTING RECICRC FLUX CONTROLLER B33-M6et.M6834.M6438 9 14e P6ae e4 POSITION TO LOWER SETTING RECIRC FLUX CONTROLLER
! B33-M683A C 365 P6ae 84 C33-M6838. POSITION TO DECREASE RECIRC LOOP A AND B FLOW CONTROLLERS l 033-M6034 A 2578 P688 84 POSITION TO CLOSE THE LOOP ASS FLOW CONTROLERS i C33-M6833
! to 533-R644 A 2688 P688 82
,! C33-R684 DISCUSS?THE DELTA TEMPERTURE IN RECIRC LOOPS WITH CR CREW j A 2620 P614 Se OBSERVE REACTOR VESSEL TE8pERATURE
! e 321-R643 I B33-R623A A 254e P681 17 OBSERVE REACTOR WATER LEVEL
! BREANER POSITION A 131e Pete 38 OBSERVE ELECTICAL SYSTEM CONDITION
! Cit-Pe1A A 270 P681 22 POSITION TO START CAD PUMPS
} C11-PS1B C33-R688 9 ale P688 83 POSITION TO MANUAL MASTER FEEDWATER CONTROL
, C33-R681A,B,C B 957 P684 83 POSITION FEEDWATER FLOW CONTROLLERS IN MANUAL MODE j C33-R642 9 955 P68e e3 ADJUST LEVEL WITH START-up LEVEL CONTROLLER IN MANUAL MODE C33-R642 3 2ae P688 e3 POSITION TO OPEN STARTup LEVEL , CONTROLLER AND ISOLATION VALVE
,l FWS-MOV185
- C33-R685 D 17e P68e 83 C33-R6e5 INFORM CONTROL ROOM CREW WATER LEVEL DECREASINS
! B 468 P681 19 ADJUST REACTOR PRESSURE WITH SRV'S j B21-Fe47F e -
C33-R685 D 16e P688 03 MONITOR REACTOR PRESSURE AND LEVEL 1 C33-R686A,S SC I C33-R649
! B21-R604 9
} C33-R688 C33-R646A,B.C B 318 P6ae 83 I C33-R688 INFORM SHIFT SUPERVISOR AND SHIFT FOREMAN OF HIGH REACTOR WATER LEVEL i C33-R606A,B,C B 35e P680 83 C33-R6ea INFORM SHIFT FOREMAN THAT REACTOR WATER LEVEL EXCEEDED HIGH WATER j LEVEL TRIP j C33-R646A,C33-R6868 A SSe P688 03 OBSERVE REACTOR WATER LEVEL
- l C33-R686C C33-R6ee A 330 P68e 83 OSBSERVES REACTOR WATER LEVEL 4
C33-R684 A 18e5 P6ae 83 INFORM SHIFT SUPERVISOR OF REACTOR LEVEL l C33-R648 A 1790 P688 6 DIASNOSE INCREASE IN REACTOR WATER LEVEL j C33-R648 A 1848 P688 e6 DIAGNOSE INCREASE IN REACTOR WATER LEVEL i C33-R648 A 1844 P68e 83 OBSERVE REACTOR WATER LEVEL l
C33-Mee A , 1858 P6ae 43 OBSERVE REACTOR WATER LEVEL
_- . . = - . . .. -~ - - - - - . - -.- -- . . - . . , - - - .. ~. . . - - . . . - -.-
i I
PAGE NO. See86
- C7/20/84 .
, I & C ALPHA LISTING I
l COMPONENT SCEN SEO PANEL LOCAT TASK & ELEM NT I
i C33-8644 A 2005 P684 83 REQUEST T M AO TO SHUT THE RECIRC SUCTION VALVES C33-26es A 2eae P648 43 OSSERVE REACTOR WATER LEVEL C33-R60s A 2318 P6ae 83 OSSERVE REACTOR WATER LEVEL DECREASE
, C33-A6es p 898 P6SS S3 INFORM CONTROL ADOM CAEW REACIDA WATER LEVEL IS 128 INCHES i C33-2688 C 1958 P688 83 OSSERVE REACTOR WATER LEVEL DECREASINS C33-A6es D 308 P6eS S3 INFORM CONTROL ROOM CREW WATER LEVEL DECREASING FAST l C33-A688 PMS A 978 P6ae 84 MONITOR REACTOR PRESSURE .
} C33-A6ee,PMS A 79 P6eG e5 MONITOR AND CONTROL AVP WATER LEVEL i C33-A6SS . B 580 P688 S4 INFOAM EHIFT FOREMAN REACTOR LEVEL IS 55 INCHES AND DECAEASINS I PMS C41-FestA D 330 P681 SS POSITION TO AUN THE SLC PUMPS C41-FeS4A C41-FOD1 B C41-FOD4B C51-A683A,B.C, 4D A 548 P688 e6 OBSERVE NUCLEAR POWER DECREASE l
- C51-A683A B.C.D D 698 P681 19 MONITOR MACTOR POWER 321-FS47A,B,C,D.F ,
to 321-Fe41A,B,C,D.F,8, C61-Rest E 260 Pest es ADJUST COOLDOWN RATE WITH RCIC FLOW CONTROLLER .
CHABEL SELECTS D See P6SS 86 POSITION TO SELECT SAM CHANNELS A,B,C, AND D AND IAN CHANNELS A.B.C,D.E.F.S.AND H AND POSITIQN TO ON DRIVE IN AND POWEA DN PS j
i DMS A 498 P684 e6 OBSERVE PLANT STATUS I DRIVE IN C 180 P688 e6 POSITION TO "IN" THE DETECTOft DRIVE IN SWITCH l DAMS A 688 DAMS DAMS 096ERVE LEAKABE CONTROL
{ SAME A tile DRMS DAMS OBSERVE DAYWELL ACTIVITY ,
DRMS A 1829 DRMS DAMS INFORM SHIFT FOREMAN THAT DAYWELL ACTIVITY INCREASING DRMS A 1298 DAMS DAMS MONITOR CONTAINMENT RADIOACTIVITY DHMS A 138e DAMS DRMS INFORM SHIFT SUPERVISION STATUS,OF CONTAINMENT DAYWELL SUMPS DRMS A 1398 DAMS 95 DIAGNOSE WITH AO DAYWELL PRESSURE DRMS B 638 DAMS DRMS OBSERVE DAVWELL AADIATION MONITORING DRMS C 718 DAMS DAMS TYPES TO CALL up RADIATION MONITORINS DISPLAY ,
DAMS C 720 DAMS DRMS MONITOR CONTAINMENT RADIATION LEVELS l DRMS C 738 DAMS DAMS MONITOR CONTAINMENT RADIATION LEVELS p j DAMS C 778 DRMS DAMS INFORM SHIFT FOREMAN GASEOUS AND PARTICULATE RADIA1 ION INCREASING
- DAMS C 789 DAMS DRMS INFORM CONTROL ROOM CAEW CONTAINMENT SAGEOUS ALAAM INITIATED j DAMS C ese DAMS DAMS INFORM SHIFT FOREMAN OF ARDIATION READING y
DAS-uCSE,uC1F B 11e Pe63 71 POSITION TO ON DAYWELL UNIT COOLEAS i DAYWELL LOGIC RESETS S 1798 P681 14 TO POSITION TO RESET HIGH DAYWELL PRESSURE APV LOW REVEL LOGIC A AND S AND HIGH DAYWELL PRESSURE RESET'A AND 3 lj E12-Ces2 S 1429 P681 21 POSITION TO CLOSE ACIC TRIP AND THROTTLE VALVE 4
Eta-Casa B 1431 P6et 21 POSITION TO OPEN ACIC TRIP AND THROTTLE VALVE l E12-Ces2, STATUS B 1424 P681 21 INFORM SHIFT FDAEMAN ACIC Tunet.NE TRIPPED AND WILL RESET l
LIGHTS E12-Ces2A A 729 P6el 28 OBSERVE RHA A Pup @ RupedINS
! E12-Cee2A A 156e P641 28 POSITION TO STOP AHA A PUMP E12-COS2A A 2789 P681 28 POSITION TO ON THE RHA A PUMP.,
i' E12-Cee2A B 1457 P6el 28 POSITION TO STOP AHA A Pupp E12-Ces2A B ,
1492 P681 28 POSITION TO START RHA PUMP A i
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L i
1 l-PAGE No. eBSSs C7/28/94 l . I & C ALPHA LISTINS ,
i l rnmaranY SCEN SEO PAML LOCAT TAGL & ELE 8ENT i
l E12-FO48A C Sie P681 ES - POSITION TO n ruw AMR A MAT EXCHANGER SHELL SIDE AVPASS VALVE i E12-F04eA68 D 619 P681 29 ADJUST SERVICE WATER FLOW TO M AT EXCHANGER FOR AHA LO WS A AND B i E12-A612A&S 1 E12-86eaAsa f ;
! E12-ASS 5 E SSS POS1 SS NONITOR AHR FLOW
! E12-ASS 5 E 398 PSG1 SS DECIDE FLEB4 NEACHES 5808 591 -
! E12-A681 A 2358 P681 82 OBSERVE SMR TEspERATUAE I i E12-AESS A 3648 P691 2e rw na ATE MAT TRANNEA ARTE !
E12-AES3A .
E12-A6e2A C 648 P681 SS OSSERVE RHA SYSTEN E12-RES3R E12-A6829 E12-A6844 S 1461 P681 at POSITION TO AUTOMATIC AND ADJUST AHR A M AT EXCHANGE LEVEL CONTROL E12-A644A A 1474 P681 as POSITION TO NANuRL AND ADJuBT' AHA A MAT EXCHANSEA LEVEL CESITAOLLER E12-8605 3 1462 PESS 29 POSITION TO NANuRL Age ADJUST AHR TO ACIC PAESSUK CONTAOL i l Eta-RESEA A 1473 P681 88 POSITION TO NApaARL AMA PRESSuaE CONTROLLER !
- E12-A611A A 2525 P681 17 OBSERVE VALVE POSITION IpeICATOR ,
E12-A611A A 2698 P688 84 POSITION TO OPEN THE RECIAC A&S DISCHAASE VALVES
)W
! E12-A6118 l
i 1 E12-A612A C 529 P681 29 OBSERVE E12-FS44A VALVE POSITION ISSICATION l 4
- E12-A612A D 468 P681 29 OSSERVE VALVE POSITION AND AHR SERVICE WATER FLOW f E12-A6824 2 r
2 E12-26123 C 548 P681 17 OSSERVE E12-F0488 .
E21-CSS 1 A ESSS SANS DSIS INFOANS CISITAOL ADON CAEW THAT INDICATION STATES LPCS TRIP HAS SEEN ,
AESET
- j E21-CSS 1 C 468 P681 '21 POSITION TO STOP LPCS PUMP ,
1 E21-CeSt A 248 P681 21 OSSERVE LPCS Ptsp TRIP , !
! E21-86eS .
i SE21-COS1 l E21-Fee 5 9 1668 P641 21 POSITION TO CLOSE LPCS INJECTION SHUTOFF VALVE
- E21-FeS5 3 1868 P641 21 POSITION TO OPEN LPCS INJECTION VALVE E21-FeOS C 245 P681 21 POSITION TO CLOSE THE LPCS'S INJECTION SHUTOFF VALVE E21-FeS5 A 2320 P-641 29 POSITION TO CLOSE THE LPCS Is&3ECTION VALVE AND LPCE NIIf FLOW TO E2l-Fett SuPPRESION POOL * !
E21-Fe12 3 1835 P681 21 ADJUST LPCS TEST NETUAN TO SUPPRESSION POES. VALVE ,
E21-Fe42C S 1665 P681 17 POSITION TO CLOSE AMA C 306JECTION VALVE !
E21-A600 3 1A65 P681 21 OSSERVE LPCS Pupp FLOW E22-CSS 1 0 1885 P681 16 POSITION TO STOP HPCS pupp NOTOR FEEDER SfEAMER E22-CSS 1 C 488 P641 16 POSITION TO TRIP HPCS Pupp NOTOR SEEAMER E22-CSS 1 C 498 P6G1 16 OSSEAVE IteICATION OF HPCS TAI,P
- E22-RES3 i E22-ft641 l E22-A683 A 138 P681 16 -OSSERVE HPCS FLOW E22A-Fe84 A 129 P6et 16 POSITION OPEN TDE HPCS Pupp INJECT SHUT OFF VALVE E222-FSS4 A ISS P661 16 OSSERVE VALVE 388ICATIONS FDA HPCS E22A-Fe84 A 2170 P681 16 POSITION TO OPEN HPCS INJECT SNUT OFF VALVE E22A-Fee 4 A 2298 P681 16 POSITION TO OPEN HPCS INJECTION SHUT-OFF VALVE E22A-Fes4 A 2234 P641 16 POSITION TO OPEN HPCS INJECTION SHUT-OFF VALVE l E224-FeS4 C 250 P681 16 POSITION TO CLOSE Ted HPCS INJECTION SMuTOFF VALVE E22A-Fe84 De 658 P641 16 H3SITION TO M f M HPCS PUNP SHUTOFF INJECTION VALVII ;
l
! PAGE NO. Seele .
C7/28/64 ,
t -
i , I & C ALPHA LISTINS COMPONENT SCEN SEO PANEL LOCAT TeeK & ELESENT E22A-Fe11 D 64e P681 16 POSITION TO OPEN HPCS TEST RETUAN TO CST VALVE E220-FOO4 A 7ee P6et 16 POSITION TO CLOSED HPCS INJECTION VALVE E31-CSS 21, A683, B 1425 P681 21 MONITOR ACIC PAAAsETERS f' A684, A641, 2686 l TUneINE SPEED, TU.leINE EXHAUST PAESSURE, RCIC PUMP SUCTION PAEseUAE, i DISCHAASE PfESSUAE, ACIC FLOW '
l E51-COO 21, A683, B 1455 P641 21 INFORN SHIFT F N m ACIC TUASIME ALaedING AND FLOW INCAEASING
- A6 . A6 1, 26 6 i E51-Fee 22 9 1625 P681 21 POSITION TO n w ACIC TEST FLOW CONTROL VALVE TO emwnsmaTE STOAAGE l E31-Fe59 TApet VALVE
! E51-FeS2 3 1427 P681 21 ADJUST POSITION ON ACIC TEST FLOW CONTAOL VALVE'TO em " N TE STOAmeE l Tapet l E51-Fet2 B 1438 P681 21 ADJUST ACIC TEST FLOW CONTROL. VALVE TO emmassaTE STOAASE TANK
! E51-Fe45 3 1424 P641 21 POSITION TO OPEN ACIC TURSINE STEast SUPPLY
] E51-Fe59 3 1426 P681 21 POSITION TO OPEN ACIC TEST RETUAN T0 c m M*' mate STOAASE TANK VALVE
] E51-FG76 D 638 P641 21 POSITION TO n N ACIC STEAft LINE WAmpHP ISELATION VALVE AND ACIC AND j E51-Fe63 AMA ST SWPLY I- ISELATI(Be VALVE ADJuBT ACIC TEST FLOW CONTROL VALVE TO CONDENSATE STOAASE TANK E31-F022 3 1432 P681 21 E51-FO45 3 1615 P641 21 POSITION TO CLOSE ACIC TUASINE STEast SUPPLY SHUTOFF VALVE
, E51-26ee D 376 P681 21 POSITION TO ManuRL wrwW ACIC Puse FLOW CONTROLLEA
- en E51-A686 C 110 P641 21 OSSERVE ACIC SYSTEM j e E61-Fe46 3 1423 P681 21 POSITION TO OPEN ACIC TunSINE. LUBE OIL COOLINS WATER SWPLY VALVE l8 i
ELETAICAL BAEAMEAS FULL CORE DIWLAY D
D 2e8 P6ee 94 80 P688 85 VERIFY TRIP OF AECIACULATION PUMPS VERIFY 2003 DID NOT SO IN FULL CORE DISPLAY D lie P6es 85 VERIFY A003 DID 8eT SO IN FULL CORE DISPLAY D 3ee P688 e5 INFORM SHIFT FOREMAN CANNOT INSEAT ROOS seRNUALLY 833-CSS 1
- A 1588 PGAS et POSITION TO START AMCU AECIRC'PUpp A & B
! C33-CSS 13 j E33-Ces1A&B A 2528 P688 el POSITION TO OPEN THE AWCU AECIRC PUMP A AND S i' C33-Fest,4,20,34,39, A 245e P681 16 POSITION TO OPEN THE AWCu ISOLATION VALVES I 53,54,48 .
i l
E S33-Fest,Fes4,F053,F A 1834 P6 1 18 POSITION TO CLOSE THE REACTOR WATER CLEAN-UP ISOLATION VALVES 454 S33-Fles A 2215 P6ee et POSITION TO n N AMCU AECIAC-LOOP A AND 3 SUCTION VALVES 633-F196 i S33-FO39 A 1828 P681 18 POSITION TO CLOSE THE REACTOR WATER CLEAN-UP ISOLATION VALVES Fe34 F028 FG44 r i 633-A648 A 2240 P688 83 DESERVE REACTOR WATER LEVEL l SP1 C 3e P688 85 POSITION TO AAft AND DEPRESS THE peANUAL SCAAN PUSHOUTTON SP2 SP3 I Sp+
SAOup 1,2,3, AND 4 D 40 P688 e5 POSITION TO AAst AseD DEPRESS peANUAL SCARN PUSHOUTTONS ,
SAOUP 1,2,3,AND 4 D tee P68e e5 POSITION Tsf seANUAL SCAAft PUSGUTTONS HI WTA LVL RESET'S 3 738 P688 63 POSITION TO RESET HISH WATER LEVEL TRIPS A, B, AND C HIGH DW PAESS, AESET A 171e P681 19 POSITION TO RESET HIGH DAVWELL PAEseUAE RESET A AND B l HPCS seRN. INIT. E 68 P641 16 POSITION TO AAM Assp DEPAESS HPCS seANUAL INITIATION PUSHSUTTON E21-A683 E21-A641 .
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l l PAGE NO. 88012 j C7/as/84 l
. I & C ALPHA LISTINS COMPOM NT SCEN SED PANEL LOCAT TASM & ELEMENT l
ISOL E SETS A 24ee P6et 19 POSITION TO RESET TM ISOLATION BESET SWITCHES ;
ISh5>=ceOV5eam,5834,4A A 1210 P870 55 POSITION INIEN CONTAINE NT UNET COOLEAS AND DRYWELL UNIT COOLERS A
} 5A
, LO-LO ESET lA 1720 96e1 19 POSITION TO RESET ADS PAESSURE (LOW-LOW) RELIEF INHIBIT LOSIC A&B i RESET -
} LOOP TEMP A 1498 DMAS INeeS CALCLA. ATE RECIRC SYSTEM DELTA *T'S FOR AESTART OF RECI AC SYSTEM -
l LOW LEVEL ESET'S C 368 P68e 19 POSITION TO A/S VEsan LOW LEVEL RECIRC INTEALOCMS t LPCS INIT. WEACT A 1550 P681 21 POSITION TO RESET LPCS INITIATION LPCS seN. 18eIT. A 2e8 P6et 21 INITIATE LPCS estpasAL SCARN E 2e P688 SS POSITION TO AAM AND DEPRESS IqANUAL SCAAM PUSHBUTTONS PWhesuTTONS j nassaAL SACAM 3 ISS P648 SS POSITION *
- SCARM COLLAAS'TO AAM AND DEPRESS SWITCHES I SWITCHES seOE SWITCH B 192 688 e6 POSITION TO SHUTDOWN THE REACTOR seODE SWITCH
! 8eOSE SWITCH C 45 P6ae 86 POSITION REACTOR seODE SWITCH TO SMUTDOWN
! seOTION INHIBIT A 2568 P688 34 POSITION TO RESET THE RECIRC A43 seOTION IsetISIT RESET aESETS I seOVeeA E 12e POS1 SS VERIFY 1SWP peOV4eA (DISCHMSES VALVE OPENS IY
'N IeOVS10A E 14e Peet es POSITION TO OPEN peOV5 tee. AND MOV584A VALVES seOV584A '
seOV35A E 13e Pest SS POSITION TO OPEN 8tETUAN TO STANDSY COOLING TOWER OUTBD. ISOL, RESET, A 355 P6et 19 POSITIOpe INaOAfte Apee OuTSOMO -ISOLATION RESET INSO. ISEL ESET .
, P681 B 1888 16 INFOApe SHIFT FORENAN, STOPPINS HPCS PUBEP l Pee SELECTS D 579 P688 36 POSITION TO IRet RED ANS Pais PEN acenanca SELECTS 4 Pees A 16e P688 SS OSSERVE REACTOR WATER LEVEL Age PREmar
! Pets A 575 P688 SS INFORM SHIFT SUPERVISOR OF DAYWIt Aped APV PHEseumE i i Pees A 598 P688 85 IeFOAst CAEW OF RPV PRESEuAE INCREASINS j Pees A 698 P688 e6 DInmnsr DRYWELL TEMPERATURE j PoeS A SIS P680 85 Dgna nar apV STATUS 1 Poes A See P6ae 86 OBSERVE DRVWELL TEpePEMTURE INDICATOR j Poe6 A 1838 P6ae 86 DESERVE DAYWELL INDICATIONS -
l 1
Pees A 1e44 P68e 12e HEcuEST DRY wt1. TElePERATURE INFOAstATION FROM 500
! poeS A tese P6ae e6 INFORM SHIFT SUPERVISOR OF DRYWELL TEsePERATURE Pose A tese P688 e6 peONITOR DAY wt1. TEpePERATURE l Pees A te98 P688 e6 DECIDE TO STAftT HYDAOSEN MININS SYSTEpe Pees A 113e P688 e5 INFORM CAEW OF DRYWELL PRESSumE Aped TEs@ERATURE Pees A 12ee P6es 85 OBSERVE DAYWELL PAESeumE AND LEVEL l Pees A 1544 P688 46 INFORM CREW OF DAYWELL PMSSURE l Pees A 1780 P6es 94 ODSERVE REACTDA WATER LEVEL I PoeS B 3e P6ae 85 INFORM SHIFT FOREstAN THAT REACTDA LEVEL AND PRESSURE ARE HOLDING
{ PoeS B 44 P640 e6 IWOAM SHIFT FOREf4AN DAYWELL TEsePERATuaE AND PAESSURE INCAEASING Poes B 68 9688 e6 INFORee SHIFT FOREseAN OF DRYWELL TEMPERATURE AND PREEN Pees S Se P688 86 INFORM SHIFT FOAEMAN OF TEMPERTueE AND PRESSURE ,
Pees S 185 P688 e5 INFOAss SHIFT FOAEseAN OF DeVWELL PAESeuRE CONTINUING TO INCitEASE ;
pues 3 15e P6ae 95 seONITOR RECIRC FLOW .
Pues 3 237 P684 95 OSSERVE FEEDWATER FLOW Poes B 465 P6ae 85 sq0NITOR REACTOS PAESSURE . i i
Pees S 644 P680 85 INFOAse 6HIFT FOREpeAN REACTOR LEVEL IS 55 INCHES AND DECAEASING 1 Pees S . 678 P6ae e5 IteFOAM SHIFT SUPERVISOR REACTOR WATER LEVEL DECREASIleS SLOWLY
j i
PAGE NO. 88013 ,
C7/28/84
. I & C ALPHA LISTINS'
- CopePONENT SCEN SEO PANEL LOCAT TMK & ELEMENT
! pets B 700 P688 SE MONITOR DAYWELL/CONTAINSEENT PMatsumE pees S 86e P648 e6 MONITOR DRYWELL PRESSUAE - 1 pees S See P688, e6 IW OAM CAEW DRYWELL PAESSURE DECREASINS l
8 P888 l
. pees S 1838 P688 e5 INFOAM SHIFT SUPERVISOR DOES NOT HAVE COdTROL OF REACTOR LEVEL WITH I FEEDWATER SYSTEM PoeS S 1838 P648 e6 AEOUEST STATUS OF DEPRESSURIZINS PLANT AND MONITOAS DRYWELL
] TEsWEARTufE DECREASING I Poes 3 127e P681 e6 INFOAM CREW DRYWELL TEMPERATU M HOLDINS i Pees S 1344 P6ee 85 IW ORM C M W REACTOR LEVEL IS'45 INCDES Pees C 15 P6ae 86 seONITOR DAYWELL PAESSURE. TEsePERATumE , AND SUPPAESSION POOL LEVEL, CONTAIfeMENT TEMPEAATumE, AND; PRESSURE
- Pees C 79 P648 86 INFOAM CR CREW VALUES OF DRYWELL PAEESUAE, REACTOR PAESSUAE, REACTOR ;
LEVEL Pass C 129 P6SS 86 INFOfte CR CAEW OF REACTOR PRESSUAE Pees C 16e P688 e5 IWOAM CR CIEW EF REACTOft LEVEL INCMASINS Pees C 248 P688 85 IW OAM CA CAEW OF REACTOR PREass w AND LEVEL Pees C 320 P68e 86 IIFORM SHIFT FOREpeAs4 OF MACTOR PRESSURE AND LEVEL l Pees C 450 P681 22 INFDAM SHIFT FORE 8 east DAYWELL PRESeumE TOO HIGH l to Poes C S15 P68e/ e6 MONITOR CONTAINMENT PRESeuRE.
!O ese i
N PoES, FLA L COAE C % P644 85 VERIFY ftEACTOR SCAAst i CISPLAY, C51-R643A, '
C51-R6838, C51-96e3C,
- Pees, REAC. SYS. 5400E A 5e P688 SS VERIFY REACTOR SCRAf4
! SW., COAE peAP, ADDS IN j Poes. C33- A6ee C 65 P684 e5 MONITOR REACTOR PRESSURE AND LEVEL Pets, CORE peAP S 2ee P688 e5 VEAIFY SCARet l
j Poe6. FULL COAE C 29 P688 SS INFORM CONTROL ROOM CREW THE, REACTOR HAS SCAAftED ,
I DISPLAY j pass B 1318 P6SG e4 INFORM SHIFT FOAEMAN REACTOR PREnss M DECREASINS ,
j C33-2685
! Pees S 117e P68e 84 INFORM SHIFT FOREpeAN STARTINS SECOND REACTOR FEEDWF.TER PupaP AND l C33-A6ee REACTOR LEVEL DECREASING Poes S 1688 P684 84 peONITOR APV TE8@ERATUAE, PREams w , AND LEVEL C33-#648 P C33-A685 i PMSS A 948 P6ee 96 OBSEAVE DRYWELL TEMPERATumE TREND
> POWER ON C 19e P6ee 86 POSITION TO ON THE DETECTOA POWEA AANGE SELECTS D 688 P6es e6 POSITION TO DOWN IAN AANGE SWITCHES
, ACIC MAN. IMIT. A 75 P6et 21 POSITION AC1C feANUAL INITIATE.TO AAM POSITION 4 ACIC pean. INIT. E 78 P641 21 POSITION TO AAM AND DEPHESS ACIC annad e INITIATION PUSHSUTTON E5t-A6e6 E51-#6et AEPC. SYS. MODt. E 38 P688 86 POSITION TO SHUTDOWN REACTOR SYSTEM MODE SWITCH SWITCH IIEACTOR SYS MODE D 54 P648 86 POSITION TO St4JTDOWN REACTOR; SYSTEM MODE SWITCH SWITCH ,
l 9
4 i PAEiE NO. SSS14 l C1/28/84
- . 1 & C ALPHA LISTINS .
COMPOBENT SCEN SEO PANEL LOCAT TASK & ELEMENT AHA SYSTEN 3 498 P681 16 VERIFY CTS SYSTEMS LINE-UP INDICATINS LISHTS men VALVE AND N A 1418 P681 22 INFORM SOP TO TAME AHR A OUT OF SUPPAESSION POOL COOLINS AND INTO INDICATOR LIGHTS i SHUTDONN COOLING ;
~
1 AMA VALVES AND D 498 P681 17 OBSERVE VALVE LIE -t2' FOR RHR S l LIGHTS M)DS IN A 300 P6SS 95 VERIFY ALL RODS IN APS DIV 1 APS DIV A 64 P6SS 95 POSITION MABGJAL SAAM BUTTONS
! 2 APS DIV 3 APS j EIV 4 l SCRAM PUSNSUTTONS B 191 688 05 POSITION TO SCAAM THE MANUAL SCARM PUSHOUTTONS
! SMALL 5 OUTPUT METEA B 195 ESS S4 VEAIFY RECIRC PUMP AL3GACK SAM PS A,S.C,D C 130 P6SS GE POSITION TO SELECT TE SAM'S SAV A 210 P6SS 19 INFOAMS C m OF SAV INITATION' SRV D ISS DESK DESK AEOUEST N1sWER OF SAV'S OPSNINS FROM BDP OPERATOR SAVS S A 956 P681 19 INFOAM SOP TO OPEN ONE SRV ,
i SAV'S B 538 P681 19 ADJUST REACTOR PAEmm w WITH SAV'B SAV'S D 54 P681 19 VEAIFY SAV'S HAVE LIFTED l SAV' S D 55 P681 19 INFOAM CONTROL AGOM CREW SAFETY RELIEF VALVES LIFTINS
]Y j"
N SAV'S WJPPLY BAEAMEAS D
A 668 P681 19 OSSEAVE SAV'S 1428 POSS 87 88 POSITION TO TRIP SUPPLY BREAKERS l SUPPLY BREAMERS D 558 PS77 32 POSITION TO CLOSE ALTERNATE SUPPLY BREAMEAS i VARIOUS A 2478 P681 28 OSSERVE AHR SYGTEM INDICATORS l VAAIOUS C 100 PS63 73 OSSEAVE INDICATIONe FOR SSST l VARIOUS C 425 P681 28 OBSERVE STATUS OF HPCS AND AHA SYSTEMS 1 VAAIERJS C 928 PS63 71 OBSEAVE CONTAIMMENT/DRYWELL/HYDAOSEN MININS EYSTEMS
, WARIOUS C 999 P681 19 INFOAM CONTAOL ADOM CREW ADS VALVE OPENINS j ,
i i
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= .
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e D'
APPENDIX C INSTRUMENTATION AND CONTROL DATA SHEET EXAMPLES C-1
System Nams I (( 8 Systmo designation &Z.1 TABLE 1 Suter INSTRIBENT& TION
! - (Signale Originating Outside Control Room) i i
E Output f Control Control Device Room Boom control Room Location of '
h i
Output Output Output Device Information or Signal e
-' Range & Units ControliDevice Source I.D. O Parameter Device I.D. 9 gg gtt-coeg A TAM P601 -S I FfNc07. T A
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C t- te e INSTMIBENTATION
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Control control output E-E88" Boom Control Room Location of Device
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' 8' l
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syetas doel p tion GSS Taas.s 1 !!
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. N Control Control Getyst 8
Room moce control Room . Location of Device i .
Oetyst Output "
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System Designation B33 N
(signals originating Inside control noom)
Device, -
Parameter or Display Control Room Control Device Imcation Direct /
Controlled Control Device I.D. 8 States of Device Indirect valve pushbdh nl-Fo13A cloSE/ y Ppo-04 valve pushktJHow, ass-FoZ38 cless/open P680-d pump pushbuh an- cooin yo, _an gy P61o +
pump pushbuh sys-coal B 33ee -me P6m-o4 -
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System Name
' 2 System Designation C. l 1 COtrFROLS (Signals Originating Inside Control h )
Device, -
~
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, pump s e rrc.4 cil-coo 8 A sw/new[sTARr ht -"
pump Sw TC. H ol(. cool & sW[A@M.fstnRT P6@R
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System Name -
System Designation C34 mu2 COtfrROLS (Signals Originating Inside Control Room)
Device, Parameter or Display control Room Control Device Iacation Direct /
Controlled Control Device I.D. 8 States of Device Indirect FEED VAlvgE b yggugg c,33.g4 oo AWTo-tnAnusl (.80-o3 engwa C33 Rh8 i
c n-RWc .
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e 6
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System Ilmme
- System Designation Tm 2 E 12.
COtrFROLS (Signals originating Inside Control Room)
Device, Parameter or Display Control Room Control Device Location Direct /
Controlled control Device I.D. 8 States of Device Indirect rwov sw rc o g ais- ro6s a o/c
- P890-56 1E11. Fo&V A C/c.
- P190-55
' f IEll- Fo41 A Class /Augdpf4 ? 601 s2O v g Sw Jcb m2- Foo% O/C " PGo 1 - 2.0 ,
Pu mp suTca Elz- cootA syep/nu p pgon-2o n Ei2- tooth P6ei-17 5 y e E12- eoo1c e PGot - L'7
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" ~
E 12- Fco9 ct/,ois Mt -2o Eti- Folt A t/o # P6ol-20 Ei2- Fo14 A c/o * ,P 6al-2 o E12.- Fo2.4 8 c/0) P6el-O El2 - F027R C/0 t t Got-20 ER- Fon 8 C/O* Pkt -n
,, Y Ell - F073C C/O P601 - t T s
System Name System Designation Ei2 cowrhoLs (Signals Originating Inside Control Room)
Device, Parameter or Display Control Room Control Device Location Direct /
Controlled control Device I.D. O States of Device Indirect MoV " waTcd E rz -Fo40 c./o F@ t -To i PboI-2o E12- FoW c-/ o en-rowe e/.ss 4 A ea re r-n t s:- fc42c. ClosE[A6M*[ofervpoog-17 ,
Es2 FonA C/O % i-to
[ E t2- Fo4TI. ClosE[4tJ%n/opf4 P6oI 20
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l E 12 F o 6'l 4 h P6oI-2o Eta Fury A C/o P6of '10 T 9 E12 Fo73 A P6 ol-2.0 C[O s
. B
f:
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! APPENDIX D 1
1 e
i 1
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t APPENDIX E EQUIPMENT SUITABILITY FORM AND ASSOCIATED HEDs E-1
RIVER BEND DCRDR PROJECT EQUIPMENT SUITABILITY HEDs Comp \eted by: Jasm/Ju Jin'64.
Date: 2-10 -8 $
l&C Direct Sys.
TAW REF, Not Equipment Info. net Statu. pg, ,,
Ident. Appropriate Ni Useable Scen. Task 1.D. p,o ded j9 *470 % psA. f ptsta S '
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E-2
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct_.E A R PL ANT DATE: 07/25/84 Fi EE E) P4 C3 - = E321 5 REVIEWER: HOWELL/ BISHOP /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 CONDENSER VACUUM IS AT.24 INCHES OF HG.'HOWEVER, METER'S 1CNM-P145(A & B) ARE LABELED " INCHES HG. ABS".
. RECOMMENDATIONS:
CHANGE TO INCHES HG.
ACTION:
- APPROVED BY GSU MANAGEMENT.
E&DCR# C52,620 ISSUE DATE / /
FDDRM LD1-2401 RO ISSUE DATE 10/24/04 CRITICALITY RATING: 3 IMPLEMENTATION-SCHEDULE: PRIOR TO EXCEEDING 5% POWER E-3
an
' HUMAN ENGINEERING' DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 08/10/04 F4 EE E) P4 C3 . = E3etzt REVIEWER: BISHOP /HOWELL/MCGHEE TRACKING ST ATUS: SCHEDULE PHASE
_ _ _ _ _ _ _ _ _ _ _ = - ____==- ____________ - - - = - ___________________
' DATA SOURCE: TASK ANALYSIS CHECKLIST NO.:
- PANEL / WORKSTATION NO. DRMS
( 1.) DRMS 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 SYSTEM IN THE SIMULATOR WHICH WAS DEVELOPED PRIOR TO THE PURCHASE OF THE PLANT SYSTEM. THE PLANT DRMS WILL MONITOR THE PARAMETERS AS STATE 3 IN THE FSAR WHICH INCLUDES DW & CONTAINMENT RAD LEVELS.
NO FURTHER ACTION ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 3 IMPLEMENTATION SCHEDULE:
E-4
! ')
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 HED NO = ~2 3 0 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
?
--=_ - _ _ . . = _ _ _ --- -------------------------------=- -. -----------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST-NO.: B2.11 .
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808-83 PANEL / WORKSTATION NO. P808-84
. - _ . _=_ _ - - . - - - - - - _ - - - - _ - _ _ - - - _ - - = _ _
- - - - - - - - - - = _ _ _ - - = _
DESCRIPTION OF DISCREPANCY: .
DRYWELL TEMP METERS AND RECORDER RANGES TO ONLY 200 AND NEEDS TO GO TO AT
.LEAST 330 (SCENARIO A/ SEQUENCE 690)
RECOMMENDATIONS:
EVALUATE OPERATIONAL LIMITS OF DRYWELL TEMP RECORDERS.
<<<C60,586 WAS GENERATED TO CORRECT THIS HED BUT /AS CANCELLED SINCE P40,941 HAD ALREADY BEEN ISSUED TO ADDRESS THIS PROBLEM >>>
<<<IN ADDITION TO E&DCR P40,941, SEE C68,866 >>>
ACTION:
EVALUATION HAS DETERMINED THAT PRESENT RANGE OF* RECORDERS IS INADEQUATE.
- RECURDER WILL BE RECALIBRATED FOR A RANGE OF 40 DEGREES TO 440 DEGREES FARH.
TO AGREE WITH REG. GUIDE 1.97 POSITION IN FSAR ELDCRM P40,941 ISSUE DATE / /
FDDR# LD1-2387 RO ISSUE DATE 01/18/85
.--------------= --
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
T~
b HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 07/25/84 HED NO = 836 REVIEWER: HOWELL/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- ___________________________________==__= - =___=== _______________
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.: ,
l
- PANEL / WORKSTATION NO. P601
'( 1. ) - INDD. ISO.RST INBOARD ISOLATION RESET
( 2.) OUTBD. ISO.RST OUTBOARD ISOLATION. RESET
==_
________= . = _ = _ _ _ _ _ - .. ----== _________
DESCRIPTION OF DISCREPANCY:
(SCENARIO A/ SEQUENCE 1150 & SCENERIO D/ SEQUENCE 560) THE TASK / SUBTASK.SAYS "POS.ITION 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 DY GSU MANAGEMENT E&DCRM C51,074 ISSUE DATE O2/29/84 FDDR# LD1-1134 R1 ISSUE DATE 11/21/83
___________________== - ==_____________________________________________________
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
L.
[ LJ HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUC L_E AR P L_ A N T DATE: 08/10/84 F4 EE E) b4 C3 . = E3dL37 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.
<<< THESE HAVE BEEN RE-LABELED AS FOLLOWS: SAFETY RELIEF VALVE LOW LOW SET LOGIC'A RESET >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD E-7
APPENDIX F SAFETY EVALUATION REPORT HUMAN ENGINEERING DISCREPANCIES FROM T.E.R. APPENDIX A F-1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
!. DATE: 02/23/84 HED ' N O :: 41~7 REVIEWER:.BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.2 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6
- - - - - - - - - - - - - - - _-___ - - - - - - _ - = _ ---_-----_-----
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.
<<< THE DISCREPANCY IS THAT OPERATORS CONFUSE THE CRD SCRAM DISCHARGE HI WATER LVL' BYPASS KEYLOCK SWITCHES WITH THE SCRAM RESET KEYLOCK SWITCHES. TO iRESOLVE THIS, THE SCRAM RESET SWITCHES WILL BE CHANGED TO A DIFFERENT TYPE OF SWITCH. MATERIAL -
CONSTRAINTS FOR THESE SWITCHES WILL PREVENT INSTALLATION FROM OCCURING PRIOR TO FUEL ~ LOAD. MISOPERATION OF ANY OF THESE KEYLOCK SWITCHES WOULD NOT ADVERSELY AFFECT THE CONDITION OF THE PLANT IN MODE 4, 5. CHANGE IS NOT REQUIRED PRIOR TO FUEL LOAD >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM C53,566 ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER u i
HUMAN ENGINEERING ~ DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 FiEEI) b4 C3 . = /L 5 37 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
-__--- _ - = _ - _ . - - _ _ _ _=_ - - - - - - - _ _ _ - - - - - - - ----------_------_____-__
DATA SOURCE: -BWR OWNERS GROUP CHECKLIST NO.: B5.1 CHECKLIST' AREA: INSTRUMENTATION AND HARDWAR'E PANEL / WORKSTATION NO..P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION 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 SWAPPED.)
RECOMMENDATIONS:
OUT OF SERVICE INDICATION-MANUAL SWITCHES ONLY, TRAINING INFORMS OPERATORS OF FUNCTION. NO ACTION.
<<<THESE CONTROLS WERE REVIEWED ON 3/27/85 . THEY ARE NOW CONFIGURED LEFT/RIGHT NORMAL /INOP WHICH IS CONSISTENT WITH ALL OTHER INOPERABILITY CONTROLS'IN THE MAIN CONTROL ROOM . NO FURTHER ACTION REQUIRED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
--- ____ - __=--------_ =------------------------- -_-- = - - - - - - - .
CRITICALITY RATING: 1
' IMPLEMENTATION SCHEDULE:
g HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NU C L_ E AR P L._ A N T DATE: 02/28/84 FiEEI) P4 C3 - = 1 97da REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
==-- _ ___________-_--_____-_____ =__________-______-__
DATA SOURCE: CONTROL ROOM SURVEY - NUREG 0700 CHECKLIST NO.: .
GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUB-CATEGORY: EMERGENCY LIGHTING PANEL / WORKSTATION NO. GENERIC
( 1.)
DESCRIPTION OF DISCREPANCY:
DC BATTERY PACK EMERGENCY LIGHTING IS INADEQUATE BEING A MAX. OF 6 FOOTCANDLES AT ITS-BRIGHTEST SPOT AND NEAR O FOOTCANDLES AT MANY SPOTS.
LIGHTING CAUSES. SHADOWS AND DARK AREAS ON THE BOARD RECOMMENDATIONS:
. EVALUATE LIGHTING TO MEET HUMAN FACTORS MAINTENANCE PLAN STANDARDS
<<< SWEC HAS COMPLETED ITS' EVALUATION OF THE OVERALL LIGHTING DESIGN FOR THE CONTROL ROOM. IT WAS DETERMINED THAT, DUE TO THE REDUNDANT POWER SUPPLIES OF THE EMERGENCY LIGHTING FIXTURES, AT LEAST 20% OF THE LIGHTING FIXTURES WILL BE AVAILABLE.
THE. BATTERY PACK LIGHTING PROVIDES ADEQUATE LIGHTING FOR EGRESS FROM THE CONTROL ROOM . NO FURTHER DESIGN MODIFICATION IS REQUIRED >>>
ACTION:
- STONE & 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.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
==___________--_-____---__-_--_________________________
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD. ,
1 b_m. .
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER BEND- NUCLEAR PLANT DATE:-02/28'/84 HED NO. :: 194 REVIEWER: BARKS / CHASE /SHANKLE 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. P680-01
( 1.)
PANEL / WORKSTATION NO. P680-02
( 1.)
PANEL / WORKSTATION NO. P680-03
( 1.) ~ '
FANEL/ WORKSTATION NO; -P68'OlO4' *
~
- - *- ~
- - ( 1.) ,
PANEL / WORKSTATION NO. P680-06
- o. ( 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 PANEL <<< INSERTS >>> HAVE BELOW THE RECOMMENDED 50.FOOTCANDLES FOR SEATED OPERATOR STATION RECOMMENDATIONS:
EVALUATE LIGHTING OVER THIS PANEL. '
<<< A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS SUCH THAT ALL READINGS WERE IN COMPLIANCE WITH NUREG 0700 GUIDANCE. NO FURTHER ACTION REQUIRED >>>
ACTION:
STONE & 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#-P-22305 ISSUE DATE 01/11/85 i FDDRM ISSUE DATE / /
______- = = - ==____________________ _
- = - - - - =-- --==__________________
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD u
r HUMAN ' ENGINEERING DISCREPANCY RECORD RIVER BEND NU CL_E AR PL ANT
. DATE: 02/28/84 F4 EE I) P4 C3 . = 1 cP E3 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:
SHADOWING OCCURS WHERE LIGHT LEVELS ARE LOW ON THE LISTED PANEL INSERTS RECOMMENDATIONS:
EVALUATE LIGHTING LUMINANCE DISTRIBUTION ACROSS CONTROL BOARDS
<<<A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS SUCH THAT THE SHADOWING WAS ELIMINATED AND THAT READINGS WERE.IN COMPLIANCE WITH NUREG 0700 GUIDANCE. NO FURTHER ACTION REQUIRED >>>
ACTION:
SAME AS HED #193 E&DCR# P-22305 ISSUE DATE 01/11/85 FDDR# ISSUE DATE / /
CRITICALITY RATING: 1 l . IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
$ DATE: 02/20/84 FiEE E) b4 C3 . a 1 9737 i REVIEWER: BARKS / CHASE TRACKING STATUS: SCHEDULE PHASE-
= _ _ _ _ _ _ _ _ = - _ - ---
= _____________________________.
DATA SOURCE: CONTROL ROOM SURVEY - NUREG 0700 CHECKLIST NO.
9 GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT PROBLEM SUB-CATEGORY: ILLUMINATION PANEL / WORKSTATION NO. P870-54
( 1.)
t PANEL / WORKSTATION NO. P870-55
- , ( 1.)
's PANEL / WORKSTATION NO. P870-56 ~
( 1.)
PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION'NO. PG77%32 ~ *
( 1.)
______-- ____________- _== __=-
DESCRIPTION OF DISCREPANCY:
AT THE ENDS OF THE TWO BENCH BOARD LISTED THE TASK AREA LUMINANCE RATIOS ARE LOWER THAN MINIMUM LEVELS ALLOWED SINCE THEFE ARE NO LIGHTING FIXTURES EXTENDING OVER THESE PORTIONS OF THE CONTROL BOARDS
, RECOMMENDATIONS:.
INVESTIGATE DESIGN STANDARD FOR PGCC CONTROL ROOM LIGHTING AND CORRECT TO MEET HUMAN FACTORS MAINTENANCE PLAN STANDARDS
<<< A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS SUCH THAT ALL READING 3 WERE IN COMPLIANCE WITH NUREG 0700 GUIDANCE. NO FURTHER ACTION REQUIRED >>>
- ACTION:
STONE & 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.
ESDCR# P-22?OS ISSUE DATE 01/11/85 FDDR# ISSUE DATE / /
____-- -- ________=- - - - _ _ _ _ - - _ = = - - = -
, . CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT r
DATE: 02/28/84 FiEE E) DJ C3 . z 1 CP 3
.I REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ . _ _ _ . . . _ - - - -= =___. _ ==-_-- _.._______.__-- ---_.-_-___-___--_-__-___
. DATA SOURCE: CONTPOL ROOM SURVEY - NUREG 0700 CHECKLIST NO.
' GUIDELINE AREA: CONTROL ROOM WORKSPACE PROBLEM CATEGORY: ENVIRONMENT +
PROBLEM SUB-CATEGORY: ILLUMINATION PANEL / WORKSTATION NO. P870-56
,, ( 1.)
PANEL / WORKSTATION NO. P870-55
( 1.)
PANEL / WORKSTATION NO. PG77-31 .
, ( 1.)
FANEL/ WORKSTATION NO. P877-32
. . ( .1. V , .
'. ~
... " P A"NEC/ WORkST'At IDM' Nd. 'P601'- 16'
( 1.)
PANEL / WORKSTATION NO. P601-21 l'
( 1.)
PANEL / WORKSTATION NO. P601-20
- i ( 1.)
PANEL / WORKSTATION NO. P601-17 i ( 1.)
. PANEL / WORKSTATION NO. P601-18
( 1.)
PANEL / WORKSTATION NO. P601-19
.- ( 1.)
PANEL / WORKSTATION NO. P601-22
( 1.)
DESCRIPTION OF DISCREPANCY:
THE LISTED PANELS INSERTS ARE ILLUMINATED BELOW THE 20 FCOTCANDLES MINIMUM RECOMMENDATIONS: ,
LIGHTING SHOULD BE EVALUATED OVER ABOVE PANELS. REASSESS LIGHTING MEASUREMENTS AFTER INSTALLATION.
<<< A LIGHTING SURVCY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS SUCH THAT ALL READINOS WERE IN COMPLIANCE WITH NUREG 0700 GUIDANCE. NO FURTHER ACTION REQUIRED.>>>
! ACTION:
j STONE & WEDSTER IS EVALUATING CONTROL ROOM LIGHTING AS A RESULT OF DCRDR.
[. FINAL LIGHT READINOS WILL DE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE l IMPLEMENTED.AND FLOORING IS INSTALLED.
ELDCR# P-22005 ISSUE DATE 01/11/85 FDDR4 ISSUE DATE / /
l CRITICALITY RATING 1
{ IMPLEMENTATION GCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 HED - N O :: 432 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. D2.17 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. GENERIC
( 1.)
1 DESCRIPTION OF DISCREPANCY:
INDICATING DEVICES ARE NOT DESIGNED SO THi- T A FAILURE MODE IS EVID'ENT. ' (NOT
,KNOWN)
RECOMMENDATIONS:
ESTADLISH CONVENTL.,NS BY INVESTIGATING FAILURE MODES IN CONTROL ROOM GWEC HAS COMPLETED THE EVALUATION. THE RESULTS ARE-DOCUMENTED ON l ib.3-9782, DATED-10/23/S4 ,~AND ARE INCLUDED IN SECTION 3 OF THE MAINTENANCE PLAN . THE MAINTENANCE PLAN HAS DEEN SUBMITTED TO TRAINING FOR USE AS A REFERENCE IN THEIR TRAINING PROGRAM >>>
ACTION:.
' APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
'H U M A N- ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T*
DATE: 02/29/84 F 1EEI) P4 C3 . -
1 d>
REVIEWER ~ BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-POO1
( 1.)
DESCRIPTION OF DISCREPANCY:
NO PERMANENT LIGHTING IN REMOTE SHUTDOWN ROOM RECOMMENDATIONS:
INSTALL LIGHTING AND TAKE LIGHT READINGS <<<THE RESULTS OF THIS LIGHTING SURVEY WILL BE INCLUDED IN THE ADDENDUM TO THE DCRDR
SUMMARY
REPORT >>>
<<< A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85 FOR THE REMOTE SHUTDOWN PANELS. ALL LIGHT READINGS WERE IN COMPLIANCE WITH NUREG 0700 GUIDANCE.NO FURTHER ACTION REQUIRED >>>
ACTION '
APPROVED BY GSU MANAGEMENT. .
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DIBCREPANCY RECORD RIVER ' BEND -NUCLEAR PLANT DATE: 02/29/84 FiEE E) P4 03 . = C5:2 REVIEWER:-BARKS / CHASE /SHANKLE. TRACKING STATUS:. SCHEDULE PHASE
.=- ------------------------------------- _----
DATA SOURCE: 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 '.E., SRV SONIC INDICATIONS RECOMMENDATIONS:
INVESTIGATE DIRECT / INDIRECT STATUS INDICATIONS IN VERIFICATION PHASE. THIS INFORMATION WILL BE INPUT INTO TRAINING / PROCEDURES AS APPROPRIATE.
<<<IT WAS DETERMINED THAT THE SRVs HAVE INDIRECT INDICATION BUT THAT OTHER VALVE INDICATOR LIGHTS REFLECT DIRECT INDICATION OF VALVE POSITION. THIS INFORMATION WAS ALREADY INCLUDED IN RBS TRAINING . A DESIGN CHANGE WILL BE IMPLEMENTED PRIOR TO FUEL LOAD TO COMPLIMENT THE PRESENT SRV INDICATION BY,GIVING DIRECT INDICATION OF VALVE STATUS >>>
ACTION:
- APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 l
IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD J__
HUMAN ENGINEERING DISCREPANCY RECORD
' RIVER BEND NUCL EAR PL ANT DATE: 02/22/84- HED .NO = 285 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - _ - = _ _ _ - = _ _ __=___-------------=- - __=--------__- -----------------
DATA SOURCE: BWR OWNERS-GROUP CHECKLIST NO.: B4.7 i .
l CHECKLIST AREA: INSTRUMENTATION'AND HARDWARE s
PANEL / WORKSTATION NO. P601-18' PANEL / WORKSTATION NO. P601-19 PANEL / WORKSTATION NO. P,601-22
,---- --- =_-. . - _ - - - - - - - - _ - - - _ _ - - - ------ --- -- -----_--_---
DESCRIPTION OF DISCREPANCY:
SRV POSITION INDICATION IS ACTUALLY SOLENOID POWER INDICATION RECOMMENDATIONS:
DESIGN CHANGE IN PROGRESS TO GIVE DIRECT INDICATION IN CONTROL ROOM. NO i FURTHER ACTION REQUIRED. <<<THIS SONIC MONITORING SYSTEM WILL COMPLIMENT THE '
PRESENT SOLENOID POSITION INDICATIONS AND WILL BE IMPLEMENTED PRIOR TO FUEL
. LOAD >>>
-ACTION:
APPROVED BY GSU MANAGEMENT.
- E&DCR# ISSUE DATE / /-
FDDRM ISSUE DATE / /
_ - - - - _ - - _ _ = _ _ _ = - - - - _---_----- Z_------_-----_-----__- - - _ - - - - _ _ - - - - - - - - - -
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD e
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct_.E A R PL ANT DATE:=O2/23/84 HED NO.= 541
, REVIEWER: 'BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SB1.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-08
( 1.)
PANEL / WORKSTATION NO. P680-07
( 1.)
PANEL / WORKSTATION NO. P680-10
( 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.
L RECOMMENDATIONS:
CHANGE TO LARGER METERS.
<<< IN ADDITION TO TRAINING ADDRESSED BELOW, BACKUP LIGHT INDICATION IS
,AVAILABLE (FULL OPEN,OPEN, CLOSED). ALSO~PMS COMPUTER MONITORS VALVE POSITION.
THIS IS NOT A SAFETY-RELATED SYSTEM. NO FURTHER. ACTION REQUIRED.
ACTION:
-NO ACTION. THESE METERS ARE FOR TURBINE BYPASS. OPERATORS ARE TRAINED USING THESE. METERS ON PLANT-SPECIFIC SIMULATOR.<<< IN ADDITION TO TRAINING, BACKUP LIGHT INDICATION-IS AVAILABLE (FULL OPEN,OPEN, CLOSED). ALSO,PMS COMPUTER MONITORS VLV POSITION.>>
r E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 1
' IMPLEMENTATION SCHEDULE:
V HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT-DATE: 02/22/84 FiEEI) P4 C3 . = 229P 2 REVIEWERi LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
__- .=- .. ------- - - - - - - - - - - _ - - --
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SB1.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-18 PANEL / WORKSTATION NO. P601-19 PANEL / WORKSTATION NO. P601-22
-_=_--------------------------== __------------. . -------
DESCRIPTION OF DISCREPANCY:
SRV OPEN IS ONLY A DEMAND SIGNAL BUT IS NOT LABELED AS SUCH RECOMMENDATIONS:
DESIGN CHANGE IN PROGRESS TO GIVE DIRECT SRV INDICATION. NO FURTHER ACTION REQUIRED. <<< THIS SYSTEM WILL COMPLIMENT THE PRESENT DEMAND SIGNAL INDICATION AND WILL BE IMPLEMENTED PRIOR TO FUEL LOAD >>>
ACTION:
--APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE'DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1
. IMPLEMENTATION SCHEDULE: PRIOR TO FUEL' LOAD l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Cl-.E A R P L_ ANT DATE: 08/10/84 FiEEI) b4 C3 = E3 2477 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 F : PRESENTLY' LABELED INCORRECTLY. THEY SHOULD BE LABELED "SRV LOW-LOW SET / RESET" FOR A & B TRAIN.
N ' RECOMMENDATIONS:
EVALUATE FUNCTION OF SWITCHES AND CHANGE LABELS IF APPROPRIATE.
O <<< THESE HAVE-BEEN RE-LABELED AS FOLLOWS: SAFETY RELIEF VALVE LOW LOW SET LOGIC A RESET >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
-l HUMAN ENGINEERING DISCREPANCY RECORD ,;
RIVER BEND NU CL_ E A R P L_ A N T DATE: 07/25/84 Fi EEI) P403 . = E3:5:5 !
REVIEWER: HOWELL/ BISHOP TRACKING STATUS: SCHEDULE PHASE l l
_ _ - = __ _ - = _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - - - - - --
DATA SOURCE: TASK ANALYSIS CHECKLIST NO.:
PANEL / WORKSTATION NO. P808
( 1.)
^
_ _ = = - - - =__== -- _______ ____________ _ ___
DESCRIPTION OF DISCREPANCY:
(SCENARIO 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.
<<< PERMANENT LABELS HAVE BEEN ORDERED. TEMPORARY LABELS WILL BE ADDED PRIOR TO FUEL LOAD. PERMANENT LABELS WILL BE INSTALLED PRIOR TO EXCEEDING 5*/. POWER ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
- ______________- _____ _=____________________ _ _ _ - - - ________
CRITICALITY' RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
cD HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 F4 EE I) P4 C3 . = 55 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
= ==_ _ _ .-------------------------_-----_---------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.1 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN i
PANEL / WORKSTATION NO. C61-POO1
( 1.)
DESCRIPTION OF DISCREPANCY: -
NO MIMIC OR DEMARCATION USED TO DISTINGUISH SYSTEMS OR COMPONENTS i
RECOMMENDATIONS: l USE COLOR CODING, LINES OF DEMARCATION, MIMICS, AND HIERARCHICAL LABELING TO l SIMPLIFY OPERATION OF PANEL.
<<< THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE THE MAIN CONTROL ROOM.
THE REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM REQUIRED FOR LOADING FUEL. THE OPER,ATORS WILL NOT BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL REACTOR STARTUP OPERATIONS BECAUSE THIS PANEL IS NOT IN USE >>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
n.
-HUMAN ENGINEERING- DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO- :: ~5 l '6 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - = = - - _-_-------------=_ ----=- _ -
= - - - - - - - - - - - - - - _ _ - - - - - - = - - _ - - _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.10 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76
( 1.) 1HVF*AOD37A COMPONENT DESCRIPTION NOT FOUND
( 2.) 1HVF*AOD37B COMPONENT DESCRIPTION NOT FOUND t
-- - =--_=---____------_--__=--- - - _ - = - - - - _ - _ - - _ _ - _ _ - - - - _ - - - _ - _ _ --_ - - _ _ - _
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.
<<< MIMIC HAS BEEN ADDED SINCE THE SURVEY TO PROPERLY DISPLAY AIR INLET THROUGH DAMPERS.1HVF*AOD37 A&B >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
_=--------------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
o l,
B-tW M A N ENGINEERING DISCREPANCY RECORD I i
RIVER BEND NUCLEAR PLANT l DATE: 02/29/84 F4 EEI) b4 03 . = 77 ll l
REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
_ = - - - _ = = - - __------ __=---------
DATA SOURCE: 'BWR OWNERS GROUP CHECKLIST NO.: A2.3
- CHECKLIST AREA: PANEL-LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1
( 1.)
- _ = = _ _ _ _ _ - _ __ _
DESCRIPTION OF DISCREPANCY:
SUBGROUPS OF COMPONENTS ARE NOT GROUPED 9
RECOMMENDATIONS:
USE COLOR CODING AND HIERARCHICAL LABELING IF APPROPRIATE TO SUPPLEMENT DEMARCATION
<<<THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE THE CONTROL ROOM. THE REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM-REQUIRED FOR LOADING FUEL.
THE OPERATORS WILL NOT-BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL REACTOR
- STARTUP OPERATIONS BECAUSE THIS PANEL IS NOT IN USE.>>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
f HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U CI-.E A R P L A N'T DATE: 02/29/84 F4 EE I) D4 03 . = E3 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
(
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION 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
<<< THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE THE CONTROL ROOM.
REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM REQUIRED TO LOAD FUEL. THE OPERATORS WILL NOT BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL REACTOR STARTUP OPERATIONS BECAUSE THIS PANEL IS NOT IN USE >>>
ACTION:
- r.
APPROVED BY OSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
-m HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND ~ NUCL EAR PI_ ANT DATE: 02/23/84 F4 EEI) P4 C3 . = ZF da d>
REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ _ - - - - - - . - - - - -- -- z --=------- - = - - - - - - - = - - - - - - .
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:
REWORK MIMIC
<<< MIMIC.IS BEING CHANGED TO REFLECT PROPER SYSTEM CONFIGURATION >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
- _=------------------------------ -----------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
CJ
' ~
T:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER' BEND NUCLEAR PLAN'T DATE: 02/29/84 FiEEI) b4 C3 . = 22 55 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
________________-- _ _ - - - - - =- _ _ _ - -
- _ _ - - = _ _ - _ - _ - - - _ _ _ _ _ _ _ _ _ _ _ _ -_ __
' DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.1 .
CHECKLIST AREA: PANEL. LAYOUT AND DESIGN PANEL / WORKSTATION NO. tRSS-PNL102 l
( 1.)
_ _ _ _ _ _ _ - - - = - _=-- =_________--- -- _=- ___________ __________________
DESCRIPTION OF DISCREPANCY:
THERE ARE NO LINES OF DEMARCATION FOR RHR LOOPS B & C FOR SYSTEM ENHANCEMENT RECOMMENDATIONS:
ADD LINES OF DEMARCATION BETWEEN SYSTEM TRAINS B & C.
<<<THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE OF TAE CONTROL ROOM.
REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM FOR LOADING FUEL. THE OPERATORS WILL NOT BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL Rx STARTUP OPERATIONS BECAUSE THIS PANEL IS NOT IN USE >>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 F4 EE I) b4 C3 . = 77 37 REVIEWER: BARKS / CHASE /SHANKLE 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.)
PANEL / WORKSTATION NO. P680-2 )
i
( 1.)
PANEL / WORKSTATION NO. P680-3 '
( 1.)
DESCRIPTION OF DISCREPANCY:
CONTROLS AND DISPLAYS ARE NOT GROUPED ACCORDING TO SYSTEM RECOMMENDATIONS:
ADD LINES OF DEMARCATION AND COLOR CODING AS APPROPRIATE <<< THE SWITCHES ON P863 THAT ARE NOT GROUPED ACCORDING TO SYSTEM ARE GROUPED ACCORDING TO FLOWPATH. THE DISPLAYS ARE GROUPED APPROPRIATELY, BEING IN THE MIDST OF THE CONTAINMENT VENTILATION SYSTEM. THE CONTROLS ON P680 ARE GROUPED PROPERLY SINCE THE DISPLAYS HAVE NOW BEEN CHANGED ( SEE HED 412 ). NO FURTHER ENHANCEMENT OR DESIGN MODIFICATION IS REQUIRED >>>
ACTION:
APPROVED BY GSU MANAGEMENT. <<<NO FURTHER ACTION REQUIRED >>>
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 1 l l
IMPLEMENTATION SCHEDULE:
(,- . - . .-
.g HUMAN. ENGINEERING. DISCREPANCY RECORD RIVER . BEND NU C L.E AR PL ANT DATE: 02/23/84 HED NO. = 421 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
= - - - - - . -. -== - - - - - - - - - - . ------------
DATA-SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.2 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO..P680-6
=------------------_ - ------------------------------------------
DESCRIPTION OF DISCREPANCY:
SELECTED USE OF COLORS IS NOT CONSISTENTLY APPLIED FOR ALARM PRIORITIZATION (NO DIFFERENTIATION ON ANNUNCIATOR 4C).
RECOMMENDATIONS:
DEVELOP ANNUNCI TOR COLOR SCHEME AND IMPLEMENT THROUGHOUT CR
<<<'THE COLOR CODING OF ANNUNCIATORS WILL BE COMPLETED ON A GENERIC BASIS THROUGHOUT THE CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED'BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT DATE:~09/19/84 HED NO = 830 REVIEWEM: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING PERSONNEL INTERVIEW
- CHECKLIST NO. : A5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680 DESCRIPTION OF DISCREPANCY:
LABEL FOR MANUAL " INITIATION" OF CONTAINMENT SHOULD READ " ISOLATION" ON P680.
RECOMMENDATIONS:
CHANGE LABELS ON INSERT 7D TO READ ISOLATION INSTEAD OF INITIATION.
<<< LABELING IS BEING CHANGED TO REFLECT CORRECT FUNCTION >>>
. ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE ./ /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
-DATE: '09/28/84 HED NO = 804 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: A5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863
( 1.)
DESCRIPTION OF DISCREPANCY:
LABEL FOR I HVR*AOD 263 AND 264 MISWORDED (SHOULD BE TEST TO SGT") ON P863.
RECOMMENDATIONS:
CHANGE LABEL TO INDICATE CORRECT FUNCTION.
<<< TECH. SPEC. 3.6.5.4 ONLY REQUIRES THIS SYSTEM (STANDBY GAS TREATMENT) IN CONDITIONS 1, 2i 3. THIS SYSTEM IS NOT REQUIRED TO LOAD FUEL.>>>
ACTION:
APPROVED BY'GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER
r HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 FiEEI) P4 03 . 77 44 57 REVIEWER: DURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.1 . .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-7D DESCRIPTION OF DISCREPANCY:
' MISSING ESCUTCHEONS FOR MN STM ISLN MANUAL INITIATION - B21H-S25 A&D.
(MISSING BECAUSE STANDARD SIZE ESC. CON BLC3 WON'T FIT FOR ALD.)
RECOMMENDATIONS:
ADD ESCUTCHEONS TO MN STM ISLN MANUAL INITI ATION FUSHDUTTONS
<<< LABELS TO BE ADDED PRIOR TO FUEL LOAD >>>
ACTION:
APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
r 5' HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct._ E A R P L_ A N T DATE: 92/24/84 HED NO = 225 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP ,
CHECKLIST NO.: AS.1 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-81B
( 1.)
DESCRIPTION OF DISCREPANCY:
TWO DAILEY CONTROLLERS HAVE LABELS THAT SAY ONLY ' DIVISION l' & ' DIVISION 2's SEVERAL UNLABELED COMPONENTS RECOMMENDATIONS:
ADD LABELS TO INDICATE NAME, FUNCTION AND DIVISION TO COMPONENTS
<<< LABELS HAVE DEEN ADDED SINCE SURVEY AS A RESULF OF STARTUP & TEST WORK >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATINO: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
y HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 F4E I) P4 C3 . = 5225 db REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A5.1 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL /WORKGTATION NO.'P808-83B PANEL / WORKSTATION NO. P808-04B
___________________________________________________________________ = _ = = - -
DESCRIPTION OF DISCREPANCY:
LABELS SHOULD DIFFERENTIATE BETWEEN THE DIFFERENT PENS RECOMMENDATIONS:
CHANGE LABELS TO DIFFERENTIATE BETWEEN PENS USING <<< COLOR CODING >>> AND FUNCTION / PARAMETER NAME
<<< PERMANENT LABELS HAVE BEEN ORDERED. TEMPORARY LABELS WILL DE INSTALLED PRIOR TO FUEL LOAD. PERMANENT LABELS WILL BE INSTALLED PRIOR TO EXCEEDING 5%
POWER >>>
ACTION:
- APPROVED DY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD l
I i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO = 80 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
- - _ _ _----. - - - - - - - - - - - - = - - - = .------. ._-_ - - - = - - - - - - - - - - - - - - - - - - - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.1 CHECKLIST-Ar?A: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71
( 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 LABELED RECOMMENDATIONS:
RELADEL TO SAY OUTLET. AGTS-FLT1B LABEL HAS BEEN ADDED SINCE CR SURVEY.
<<< PERMANENT LABEL HAS BEEN ORDERED. TEMPORARY LABEL WILL BE ADDED PRIOR TO FUEL LOAD. PERMANENT LABEL WILL BE INSTALLED PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD e
RIVER BEND NUCLEAR PLANT DATE: 02/21/84 FiEEI) P4 03 . = C2 42 97 I
REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
_______-= ----_---_-__ _ - - - - - - - - - . - _ - - - - - - - - .--- -------------
' DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.1 CHECKLIST AREA: PANEL. LAYOUT AND CESIGN PANEL / WORKSTATION NO. P870-55C PANEL / WORKSTATION NO. P870-56C
=- --------------------------=- __--------------------------
DESCRIPTION OF DISCREPANCY:
THREE POSITION SWITCHES HAVE NO AUTO FUNCTION NOTED ON LABEL OR ESCUTCHEON RECOMMENDATIONS:
PERFORM ENGINEERING EVALUATION TO DETERMINE IF 3RD POSITION HAS A' FUNCTION OR IS IN NEUTRAL POSITION AND RELABEL IF REQUIRED.
<<<THESE VALVES ARE PART OF THE MAIN STEAM SYSTEM WHICH WILL NOT BE IN USE FOR SOME TIME AFTER FUEL LOAD. THIS IS NOT REQUIRED FOR FUEL LOAD >>>
ACTION:
ALL 3 POSITION SWITCHES ON P-870(WITH ONLY 2 POSITIONS LABELED)WERE EVALUATED.IT WAS DETERMINED THAT 1DSR-MOV109 AND 1DSR-MOV107 HAVE AUTO FUNCTIONS AND THESE LABELS WILL BE CHANGED.ALL OTHERS ARE ' SPRING RETURN TO NEUTRAL', REQUIRING NO LABEL CHANGE.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER w_
q HUMAN ENGINEERING DISCREPANCY RECORD j i
RIVER BEND N U Ct-.E A R Pt. ANT I
-DATE: 02/29/84 F4 EEI) P4 C3 . = 22 97 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
-= ------------=_ - - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.10 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. 1RSS-PNL102
( 1.) 1E12*MOVF053B SHUTDOWN COOLING INJECTION VALVE
( 2.) 1E12*MOVF037B SHUTDOWN COOLING UPPER POOL VALVE DESCRIPTION OF DISCREPANCY:
THESE VALVES ARE NOT ACCURATELY LABELED. SHOULD BE: SHUTDOWN COOLING VALVE.
RECOMMENDATIONS:
RELABEL TO BE CONSISTENT WITH CONTROL ROOM.
<<< THIS IS THE REMOTE SHUTDOWN PANEL WHICH-IS OUTSIDE OF THE CONTROL ROOM.
REMOTE' SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM REQUIRED FOR FUEL LOADING.
THE OPERATORS WILL NOT BE SUBJECTED TO' CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL REACTOR STARTUP OPERATIONS BECAUSE THIS PANEL WILL NOT BE IN USE >>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
a
' HUMAN ENGINEERING DISCREPANCY RECORD RIVER- BEND NUCLEAR PLANT
'DATE: 02/22/84 HED NO- : 284
' REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - -- =------_------------ ----_----- -_=---_
- - - - _ = - - - - -
~ DATA SOURCE: BWR OWNERS GROUP-CHECKLIST NO.: A5.10 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19
==------------------------------====- _==------
___-- ====
DESCRIPTION OF DISCREPANCY:
MAIN STEAM LINE C SAFETY RELIEF VALVE SWITCH S26A IS ACTUALLY AN ADS SAFETY
. RELIEF VALVE RECOMMENDATIONS:
RELABEL TO READ ADS SAFETY RELIEF VALVE ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
__===
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER ' BEND N U Ct._ E A R P L._ A N T DATE: 02/23/84 F4 EEI) P4 C3 - = 44 237 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.10 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4
_ _ _ _ _ - - - _______________________________- -=___------_____________________
DESCRIPTION OF DISCREPANCY:
LABELS ARE NOT SUCCINCTLY WORDED AND ACCURATE WITH RESPECT TO FUNCTION Oh INPUT SIGNAL. (RECIRC. FCV A/B MOTION INHIBIT RESET, USE RST TO ABBREVIATE RESET.)
RECOMMENDATIONS:
CHANGE LABEL
<<< LABEL IS BEING CORRECTED TO REFLECT CORRECT FUt1CTION >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
~
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N"T' DATE: 02/28/84 F4 EE E) b103 . = 1 1 d2
. REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.10 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-75C
( 1.) 1HVC*FN3B BATTERY ROOM 18 EXH OFF
( 2.) 1HVC*ACU1A CONTROL ROOM AIR HLDG. UNIT
( 3.) 1HVC*ACU1B CONTROL ROOM AIR HLDG. UNIT PANEL / WORKSTATION NO. P863-74B
( 1.) 1HVK*LI1A CPRSN TANK LEVEL METER i
DESCRIPTION'OF DISCREPANCY:
THESE LABELS ARE NOT ACCURATE IN RESPECT TO THEIR FUNCTION RECOMMENDATIONS:
CHANGE LADELS TO INDICATE TRUE FUNCTION
<<< CHANGING THESE LABELS AFTER FUEL LOAD WILL NOT CAUSE OPERATOR CONFUSION SINCE THIS EQUIPMENT IS IN USE AT THE PRESENT TIME. THE MINOR AMBIGUITIES THAT EXIST HAVE BEEN WELL NOTED BY THE OPERATORS >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER
m.- __
a HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE:'02/23/84 HED NO a 428 REVIEWER: BURGY/ 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 ALD MISSING LABELS INDICATING WHAT INK COLORS REFER TO.
RECOMMENDATIONS:.
ADD LABELS TO INDICATE WHAT THE COLORS REFER TO AND/OR USE COLOR DOTS NEXT TO PEN NAMES ACTION:
APPROVED DY GSU MANAGEMENT. ,
ELDCRW ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 i
IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L_ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 F4 EEI) b4 03 . a E3 1 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71
( 1.) 1HVR-AOD125 COMPONENT DESCRIPTION NOT FOUND
( 2.) 1HVR-AOD126
( 3.) 1HVR-AOD147
( 4.) 1HVR-AOD148 PANEL / WORKSTATION NO. P063-72
( 1.) 1HVR-AOD140 PANEL / WORKSTATION NO. PO63-73
( 1.) 1HVR-AOD148 DESCRIPTION OF DISCREPANCY:
THE LISTED VALVES NEED WARNING LADELS DUE TO THE POSSIBILITY OF INADVERTENT OPERATION VIOLATING CONTAINMENT INTEORITY RECOMMENDATIONS:
ADD WARNING LABELS. *
<<< THE 4 VALVES LISTED ABOVE NOW HAVE AN ALARM / ANNUNCIATOR ASSOCIATED WITH THEM. THE ANNUNCIATOR WILL SOUND IF ANY ONE OF THE 4 VALVES IS OPENED. THIS WILL PREVENT INADVERTENT VIOLATION OF CONTAINMENT /DRYWELL INTEGRITY. NO l FURTHER ACTION REQUIRED >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
ELDCRW ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING 1 IMPLEMENTATION SCHEDULE: ;
l
l I
HUMAN ENGINEERING DISCREPANCY RECORD I 1
RIVER BEND NUCLEAR PLANT l l
DATE: 02/20/84 F4EEE) b4 C3 . s 029P E3 i REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE 1
l DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.3 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P877-32 PANEL / WORKSTATION NO. P601-16 DESCRIPTION OF DISCREPANCY: l DIVISION 2 AND 3 IS NOT LADELED RECOMMENDATIONS:
DIVISION 2 LADEL HAS DEEN ADDED SINCE SURVEY. ADD DIV. 3 LADEL.
<<< DIVISION LADELS ARE DEING CHANDED TO DE CONSISTENT WITH THE hEIRARCHICAL LADELING FORMAT >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
ELDCRW ISSUE.DATE / /
FDDR# ISSUE DATE / /
-CRITICALITY RATING: I IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 4
~
7 HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/29/84 F4 EE E) b4 C3 . 1 05 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE l
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.5 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-P001
( 1.) NUCL BLR REACTOR VESSEL LEVEL & PRESS INST.
( 2.) E51-F064 RHR CNDS HX STM LINE ISO
( 3.) E12-F024A RHR TEST LINE
( 4.) RCIC SO ROOT RCIC SO ROOT EXTRACTOR
( 5.) E12-F037A SHUTDOWN UPPER POOL COOLING
( 6.) HRV-UC12 UNIT COOLER DESCRIPTION OF DISCREPANCY:
THE NOMENCLATURE AND ADDREVIATIONS ARE INCONSISTENT WITH THE LABELS IN THE MAIN CONTROL ROOM RECOMMENDATIONS:
RELADEL TO DE CONSISTENT WITH CONTROL ROOM LABEL STANDARDS
<<<THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE OF THE CONTROL ROOM.
THE REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM REQUIRED FOR LOADING FUEL. THE OPERATORS WILL NOT DE SUDJECTED TO CHANGES IN ENHANCEMENTS DURING THE PERIOD OF INITIAL REACTOR STARTUP OPERATIONS DECAUSE THIS PANEL IS NOT IN USE >>>
ACTION:
APPROVED DY OSU MANAGEMENT ELDCRM IOSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATINO: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5'/. POWER
c_J
, n-HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
- DATE: 02/27/84 HED NO :: 322 REVIEW'ER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE I
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - =__-______________________- . _ _ _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.5 . ,
ICHECKLIST AREA: PANEL LAYOUT AND DESIGN
- f
. 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:
- ~j CORRECT LABELS TO MEET STANDARD ABBREVIATION LIST
<<< PERMANENT LABELS HAVE BEEN ORDERED. PRESENT LABELING HAS NOT CAUSED
. OPERATOR CONFUSION. LABELS WILL BE CHANGED PRIOR TO EXCEEDING 5% POWER >>>
b ,
ACTION:
APPROVED'BY GCU MANAGEMENT.
r- ,
i r f '; ISSUE DATE
.J&DCR# -
/ /
' ISSUE DATE
,- .F,DDR# / /
J'.}
CRITICALITY RATING: 1
~
IMPLEMENTATION _ SCHEDULE: PRIOR TO EXCEEDING 5% POWER
. ^
d-
+ w-
. ?
, .- .i v.
4 I
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUC L_E A R P L_ A N T
-DATE: 09/98/4 F4 EEI) P4 03 . = E31 2
-REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ - _ _ _ _ _ _ _ _ _ = = _ - - - _____ _- -
l DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B1
. CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL /WORXSTATION NO. P601
( 1.)
_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ = - - - - _ _ --_=- _ _ _ - - _ = ===__________________.
' DESCRIPTION OF DISCREPANCY:
. MAIN STEAM VALVE (MSIVs) IS DIFFICULT TO LOCATE OR ACCESS RECOMMENDATIONS:
COLOR PAD MSIV'S '(INBOARD AND OUTBOARD) .
.<<<.THE~ INBOARD AND OUTBOARD MSIVs ARE BEING COLOR-PADDED AND LABELED >>>
ACTION:
APPROVED BY-GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
________________________-- ==______________ - _____- _________________ ==_ _
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
'DATE: 09/28/4 HED NO = 8 '2 O REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
_ = _ - - ___________ -______________________-_____-____________________ .
' DATA SOURCE: OPERATING PERSONNEL INTERVIEW LCHECKLIST NO.: B1 ,
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601
__- :-- . - - -_-_ _ .== _ _ _ _ _ _ _
DESCRIPTION OF DISCREPANCY:
ONE 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.
..<<< TAN COLOR PADS WILL BE USED FOR THIS BENCHBOARD >>>
ACTION:
-APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR Pt_.A N T DATE: 02/29/84 F4 EE I) P4 03 = 22 5 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCES 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.
RECOMMENDATIONS:
(1) ADD SYMBOL ON LABELS TO CONTROLLERS TO INDICATC 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.<<< (5) INDICATE UNITS ON LABELS AS REQUIRED >>
<<<-DEMAND SIGNALS HAVE BEEN DETERMINED BY SULT ENGINEERS. ALL' HORIZONTAL METERS ON BOTTOM OF CONTROLLERS ARE DEMAND SIGNALS. A GENERIC CONVENTION FOR LABEL LOCATION HAS DEEN ESTABLISHED. VALVE NUMBERS SHALL BE PLACED ON LABELS.
- CONTROLLER FUNCTIONS
'ARE BEING REVIEWED TO ENSURE LABEL ACCURACY >>>
ACTION:
. APPROVED BY GSU MANAGEMENT <<< LABELS HAVE BEEN ORDERED AND WILL BE IMPLEMENTED ON A GENERIC BASIS THROUGHOUT THE CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
E&DCR# ISSUE.DATE / /
FDDR# ISSUE DATE / /
' CRITICALITY. RATING: 1
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING S% POWER m
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
.DATE: 09/19/84 FiEEI) b4 C3 = 77 97 55 REVIEWER:-LINK TRACKING STATUS: SCHEDULE PHASE
== - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ - =-------------------------------
DATA SOURCE: OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: B2 .
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P863
( 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.
<<< SECONDARY CONTAINMENT INTEGRITY IS NOT REQUIRED FOR FUEL LOAD PER TECH.
SPEC.~3/4.~6.5, THEREFORE THIS CHANGE IS.NOT REQUIRED PRIOR TO FUEL LOAD >>>
ACTION:
CHANGE LABEL TO READ 1LMS-TR127 ANNULUS TEMPERATURE / PRESSURE.
E&DCR# ISSUE DATE / /
FDDRM : ISSUE DATE / /
==_- - - _ = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - -
CRITICALITY RATING: 1
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5*/. POWER i
l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L-.E A R P L_ ANT DATE: 02/29/84 F4 EE I) P4 C3 . = ~ 52 :2
-REVIEWER:: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST;NO.: B5.10 CHECKLIST AREA: ' INSTRUMENTATION AND HARDWARE *
' PANEL / WORKSTATION NO. GENERIC
( 1.)
.---_-------------- - - - - - _ _ _ - - - _ _ _ - - - _-- - - - - - - = = - - - - - -
DESCRIPTION OF DISCREPANCY:
PHYSICAL DISTINCTION'DETWEEN PUMPS AND VALVES IS NOT USED. INSERT 4C-SAME
. SWITCH TYPE IS USED FOR VALVES AND BREAKERS. C33-C001A RWCU PUMP &B. USE
'SAME SWITCH'FOR BREAKERS AND PUMPS.
RECOMMENDATIONS:
COLOR' CODING ON BENCHBOARD FOR PUMPS AND FANS TO DISTINGUISH FROM VALVES &
<<< COLOR-CODING CONVENTIONS HAVE BEEN DEVELOPED AND WILL BE APPLIED
-THROUGHOUT THE MAIN CONTROL ROOM ON A GENERIC BASIS PRIOR TO EXCEEDING 5%
POWER'>>>
ACTION: .
~ APPROVED BY GSU MANAGEMENT E&DCR#- ISSUE DATE / /
FDDR# ISSUE DATE / /
_ = = - - - - - - - - - - - - - - - - - - - - - - - - - - - -----
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER-
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/22/84 HED NO- :: 287 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B6.1 .
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-19
' DESCRIPTION OF DISCREPANCY:
RESET BUTTONS ARE NOT ACCURATELY MARKED RECOMMENDATIONS:
RELABEL TO INDICATE PROPER FUNCTION.
<<< THE FUNCTION OF RESET BUTTONS HAS BEEN REVIEWED AND LABEL CORRECTIONS ARE BEING MADE >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
.e
HUMAN ENGINEERING DISCREPANCY RECORD
. RIVER BEND NUCLEAR PLAN'T
-DATE: 02/C3/84 HED N O :: 540 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA-SOURCE: -BWR OWNERS GROUP CHECKLIST NO.: SA1.3 CHECKLIST AREA: PANEL ~ LAYOUT.AND DESIGN PANEL / WORKSTATION NO. P680-01
( 1.)
PANEL / WORKSTATION NO. P680-02
( 1.)
PANEL / WORKSTATION NO. P680-03
(' 1.)
DESCRIPTION OF DISCREPANCY:
THE ASSOCIATION OF FEEDBACK INDICATION TO RELATED CONTROLS IS NOT MADE READILY_ APPARENT THROUGH LABELING, MIMICS, DEMARCATION LINES OR POSITION.
RECOMMENDATIONS:
ADD MIMIC, LABELING, DEMARCATIONS AS REQUIRED.
- <<< LABELING,. MIMIC AND LINES OF DEMARCATION ARE BEING CHANGED / CORRECTED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE /- /
FDDR# ISSUE DATE / /
=-- -----
JCRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
(. '[
HUMAN- ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L. A N T DATE: 02/23/84 FiEE E) P4 03 . = ZU 9P E3
' REVIEWER: 'BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - =- - ------ =--------------------------------------
DATA SOURCE: BWR OWNERS GROUP
. CHECKLIST NO.: SA3 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-01C
( 1.)
- - - - - - - - .= - - -_ . - - - - - - - - - - - - - - = = - - = - - -- ---------- _
DESCRIPTION OF DISCREPANCY:
THE ASSOCIATION.0F FEEDBACK IDENTIFICATION TO RELATED CONTROLS IS NOT MADE -
READILY APPARENT'THROUGH LABELING, MIMICS, DEMARCATION LINES OR POSITION.
RECOMMENDATIONS:
ADD DEMARCATION AND ENHANCEMENTS AS REQUIRED TO MAKE ASSOCIATION READILY
~ APPARENT
' ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
.FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
'DATE: 02/23/84 Fi EE I) b4 C3 . = Z4 "5 21 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
_ = - - - _ - - - - --__
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SA3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-06C
( 1.)
- - - - - - - - - - - - - _= -----------==_=_ -------------------------- _
DESCRIPTION OF DISCREPANCY:
_- --- 'l; THE ASSOCIATION OF FEEDBACK. INDICATION TO RELATED CONTROLS IS NOT READILY i APPARENT ~THROUGH LADELING, MIMICS, DEMARCATION LINES OR POSITION.(IRM BYPASS) i
-RECOMMENDATIONS:
IMPLEMENT COLOR CODING OF SWITCHES AND RECORDERS
<<<IT WAS DETERMINED THAT COLOR CODING WOULD NOT BE APPROPRIATE. HEIRARCHICAL-LABELING WILL BE ADDED TO THE SYSTEM / SUBSYSTEM >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
_ _ = - - - - - - - - - - - - - - - - - - = _ - = _ ------------------= -_-----------
- CRITICALITY RATING: 1-IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
'DATE: 02/23/84 F4 EEI) b4 C3 . = ZF 1 C)
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 MADE.
READILY APPARENT THROUGH LABELING, MIMICS, DEMARCATION LINES, OR POSITION ON CONTROL / DISPLAY GROUPING.
RECOMMENDATIONS:
ADD-MIMICS, LINES OF DEMARCATION
.<<< MIMIC IS BEING ADDED TO REFLECT PROPER SYSTEM CONFIGURATION >>>
ACTION:
APPROVED BY GSU MANAGEMENT. .
EE<DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
= ----------------------___. - - - - - - - - - - - - - - - - - - - - - - ---------
CRITICALITY RATING: 1
' IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCE-EAR PL ANT DATE: 02/23/84 HED NO :: 503 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
--- ---- --------- - =------------------------------ - - - - -
DATA SOURCE: 'BWR OWNERS GROUP CHECKLIST'NO.: SBl.4 .
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-1
= _ - - _ - -
=__= _
' DESCRIPTION OF DISCREPANCY:
PROCESS UNITS AND MULTIPLIERS ARE NOT SPECIFIED. (NOT ON RECORDER)
RECOMMENDATIONS:
CHANGE-LABELS FOR RECORDERS ON P680 TO INDICATE UNITS ACTION:
. APPROVED BY.GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
-----=- __ __---------------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
. HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L A N'T DATE: '02/23/84 HED- NO- = 457 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
=-----------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SBl.4 CHECKLIST-AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5
- PANEL / WORKSTATION NO. P680-6
- - - - - - - - - _ - - - - _ - - - - - - . ---= .------------ - _- ------
- DESCRIPTION OF DISCREPANCY:
PROCESS UNITS AND MULTIPLIERS ARE NOT SPECIFIED. (SRM LUG COUNT RATE RECORDERS , RECIRC LOOP A/B FLOW RECORDER, AND TOTAL FLOW / DELTA PRESSURE RECORDER HAVE NO UNITS). UPGRADED DUE TO IMPORTANCE OF INDICATION.
RECOMMENDATIONS:
CHANGE-LABELS TO INDICATE UNITS.
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
'FDDR# ISSUE DATE / /
--- _ . = - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
' CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD m
r HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL AN'T DATE: 02/23/84 HED NO = 422
' REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- = = _ - _ _ .-----------------------------
DATA ~ SOURCE: BWR OWNERS GROUP -
CHECKLIST NO.: A5.2
-CHECKLIST AREA: PANEL LAYOUT-AND DESIGN
- PANEL / WORKSTATION NO. GENERIC
_ = _ - - - - - - - - - - - - - - - - - - - - - -------
DESCRIPTION OF DISCREPANCY:
LABELS, 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.
<<< THE BANDING OF VISUAL DISPLAYS IS NOT REQUIRED FOR FUEL LOAD. OPERATOR CONFUSION'WILL NOT RESULT FROM ADDING THE BANDING AFTER FUEL LOAD. ALTHOUGH
~THE BANDING IS CONSIDERED AN' ENHANCEMENT, A GREAT DEAL OF ENGINEERING IS
-INVOLVED =IN. DETERMINING THE BANDING LIMITS FOR THE METERS . THIS CHANGE WILL BE COMPLETED THROUGHOUT.
THE CONTROL-ROOM ON A GENERIC BASIS PRIOR TO EXCEEDING 5% POWER >>>
ACTION: .
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
' CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
. HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PI_ ANT DATE: 02/29/84 F4 EE E) P4 03 - = T C)
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
<<<THE BANDING OF VISUAL DISPLAYS IS NOT REQUIRED FOR FUEL LOAD. OPERATOR CONFUSION WILL NOT RESULT FROM ADDING THE BANDING AFTER FUEL LOAD. ALTHOUGH THE BANDING IS CONSIDERED AN ENHANCEMENT, A OREAT DEAL OF ENGINEERING IS INVOLVED IN DETERMINING THE BANDING LIMITS FOR THE METERS . THIS CHANGE WILL BE IMPLEMENTED ON GENERIC BASIS THROUOHOUT THE CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
ACTION: ,
APPROVED BY GSU MANAGEMENT E&DCRM ISSUE DATE- / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: -1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l-
s-y HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L-.E A R Pt._ A N T DATES.02/29/84 FiEEI) P4 03 . = C5 5 55 REVIEWER: SCHROEDER TRACKING STATUS: SCHEDULE' PHASE
-_ _ _ - = - - - - - - - - - - - - - - - = - - - - - - - - - -- -.___ - - _ - - _
_---- ----_--===
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: E4.13 CHECKLIST AREA: PROCEDURES PANEL / WORKSTATION NO. GENERIC
(-1.)
= = - - - =-- - - - - - - . - - - - - _ _ _ = = = - =--------------
DESCRIPTION OF DISCREPANCY:
PROCEDURES DO NOT GIVE NORMALLY EXPECTED RESULTS (SUCH AS VALVE POSITIONS, FLOW RATES, ETC.)WHERE APPROPRIATE RECOMMENDATIONS:
CONTROL-ROOM METERS / INDICATORS WILL BE MARKED TO INDICATE NORMAL OPERATING BAND.
<<<THE BANDING OF VISUAL DISPLAYS IS NOT REDUIRED FOR FUEL LOAD. OPERATOR CONFUSION WILL NOT RESULT FROM ADDING THE BANDING AFTER FUEL LOAD. ALTHOUGH THE BANDING 1IS CONSIDERED AN ENHANCEMENT, A GREAT DEAL OF ENGINEERING IS INVOLVED IN DETERMINING THE BANDING LIMITS FOR THE METERS.THIS CHANGE WILL BE COMPLETED ON A GENERIC BASIS THROUGHOUT THE CONTROL ROOM PRIOR TO EXCE5 DING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
= . _ - - - - - - - - _ - . --===_ _---------------------------------
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
c
' HUM AN ENGINEERING DISCREPANCY RECORD, RIVER BEND NUCL. EAR PR-.A N'T" DATE: '04/24/84 HED NO = 775
-REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
__ - - - = - ----------- ===-------- ----------------------
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 DEMA'ND FOR DISPLAY AND IS NOT REQUIRED TO DE SEISMICALLY-QUALIFIED. THEREFORE, THE PRESENT DESIGN OF DISPLAYING THIS PARAMETER THROUbH THE PROCESS COMPUTER AND SPDS DATABASE IS ADEQUATE.
NO FURTHER ACTION REQUIRED.
<<<CRT DISPLAY-IS ADEQUATE. IN ADDITION , CONTROL ROOM HAS A LOW AND.HIGH ALARM FOR CST. AUX CONTROL ROOM HAS DIRECT INDICATION AND THERE ARE TWO DIRECT LINES, A RADIO, AND THE GAITRONICS FOR COMMUNICATIid BETWEEN-THE TWO CONTROL ROOMS >>>
ACTION:
- APPROVED BY GSU MANAGEMENT. <<.:SPDb WILL BE FULLY FUNCTIONAL BY FEDRUARY 1986->>>
ELDCR# ISSUE DATE / /
'FDDRM- ISSUE DATE / /
ICRITICALITY RATING: 1 LIMPLEMENTATION SCHEDULE:
m
v 7
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PR-.A N T D TE:'02/23/84 F4 EE I) b4 C3 . = 55 /1 45 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
.. :-_=------------------------ __----------------
DATA SOURCE: OTHER CHECKLIST NO.': SPDC .
' CHECKLIST AREA: CHECKLIST AREA NOT FOUND
-PANEL / WORKSTATION NO. SPDS
- - - - - - - - - - - - - - - -_-----. =------- -- ----------------
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 PRESENT DESIGN OF THE NORMAL SUPPRESSION POOL TEMPERATURE MONITORING
~ SYSTEM SATISFIES THE RECOMMENDATIONS'OF GE DOCUMENT NO. 22A4379, REVISION 1 ,-
' SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM. AVERAGE POOL TEMPERATURE CAN
.BE:OBTAINED BY MANUALLY AVERAGING'THE OUTPUTS FROM THE-TEMPERATURE SENSORS THAT ARE DISTRIBUTED 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 TAKE CORRECTIVE ACTION.
THEREFORE.:A BULK SUPPRESSION POOL TEMPERATURE AVERAGING SYSTEM IS NOT-REQUIRED.
ACTION:
' APPROVED'BY GSU MANAGEMENT. <<<THIS HED DOES NOT REQUIRE THE USE OF THE SPDS.
SPDS WILL BE FULLY FUNCTIONAL BY FEBRUARY 1986 >>>
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING 1 IMPLEMENTATION SCHEDULE:
u
o i
~ HUMAN. ENGINEERING , DISCREPANCY RECORD RIVER BEND NUCLEAR. PLANT DATE: 02/23/84 HED N O :: 547 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
. DATA SOURCE: OTHER
- CHECKLIST NO.: SPDS .
CHECKLIST AREA: CHECKLIST AREA NOT FOUND
-PANEL / WORKSTATION NO. SPDS DESCRIPTION OF DISCREPANCY:
SLCS TANK LEVEL DOES NOT MEET THE EQUIPMENT GUALIFICATION GUIDELINES SET FORTH BY R. G .' 1.97, REVISION-3.
RECOMMENDATIONS:
'THE SLCS IS NOT REQUIRED TO PROVIDE A SAFETY FUNCTION DURING ANY POSTULATED
' PIPE BREAK EVENTS. THE SLCS TANK LEVEL INSTRUMENTATION IS CONTAINED IN
- ENVIRONMENTAL ZONE CT-4, WHICH HAS A MILD ENVIRONMENT DURING NONACCIDENT CONDITIONS.
WHILE THIS SYSTEM-IS SAFETY-RELATED,IT IS CONSIDERED LESS IMPORTANT TO SAFETY THAN,THE REACTOR PROTECTION SYSTEM. THEREFORE, THE REGULATORY. GUIDE CATEGORY 2 REQUIRE. IS NOT CONSIDERED _ APPROPRIATE, AND CATEGORY 3 INSTRUMENTATION IS USED.
'NO FURTHER ACTION REQUIRED. <<< THIS HED DOES NOT REFERENCE THE USE OF THE SPDS. SPDS WILL.BE. FULLY FUNCTIONAL.BY FEBRUARY 1986 >>>
' ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUF DATE / /
FDDR# ISSUE DATE / /
r - - - - = - = -----
_== -_---------------------------------------
. CRITICALITY RATING: 1-IMPLEMENTATION SCHEDULE:
e --
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT.
DATE: 02/23/84 FiEEI) P4 03 . = 5555 1 REVIEWER: 'SPDS TRACKING STATUS: SCHEDULE PHASE
- ==------- = . - - - .=-- =
- = = _ .-- --= - - - - - - - - - - - - - - - -
DATA SOURCE: OTHER CH'ECKLIST NO.: SPDS ,
' CHECKLIST AREA: CHECKLIST AREA NOT FOUND PANEL / WORKSTATION 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;
<<<THIS HED DOES.NOT REFERENCE THE USE OF THE SPDS. SPDS WILL BE FULLY FUNCTIONAL BY FEBRUARY 1986 >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
-FDDR# ISSUE DATE / /
- - - - - = _ - . . _ _ - - - - - - - . =- - ------- .- - - - - - - -
=----
LCRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
5
~ HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L. E A R P L_ A N T
- DATE: -02/23/S4 HED NO- = 554 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
- - = _ - - - _ = - - - _ _ _ _ _ = _ - - - - - - - - _ - - - - - - - - - - - - - - - - -
- DATA SOURCE: 'OTHER CHECKLIST NO.: SPDS .
CHECKLIST AREA: CHECKLIST AREA NOT FOUND
~ PANEL / WORKSTATION NO. SPDS
_-- ---------------------_-------------- .= --------------- _ - - - -
- DESCRIPTION OF DISCREPANCY:
- THE DESIGN OF RBS DOES NOT PROVIDE FOR MAIN CONTROL ROOM INSTRUMENTATION WHICH COVERS THE RANGE REQUIRED FOR THE CONTAINMENT WATER LEVEL.
-RECOMMENDATIONS: ~
INVESTIGATE THE EXPANSION OF RANGE ON CONTAINMENT WATER LEVEL INDICATIONS IN CONTROL ROOM
<<< THIS HED DOES NOT REFERENCE THE USE OF SPDS. SPDS WILL BE FULLY FUNCTIONAL BY FEBRUARY 1986 >>>
ACTION:
NO~ ACTION. TECHNICAL JUSTIFICATION ON P. 40 OF REFERENCE "K" IN
SUMMARY
- REPORT. -
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
_-----------=- - - - - - ----------------------- =. ---_------------
CRITICALITY. RATING: 1 IMPLEMENTATION SCHEDULE:
4
.m- ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND - NU C L_E A R Pt_.A N T DATE: 02/23/84 FiE~I) P4 C3 . = S55555 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE DATA 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.
<<< ANNULUS PRESSURE IS AVAILABLE ON P863 AND CONTAINMENT PRESSURE IS AVAILABLE ON P808. RATE OF DEPRESSURIZATION CAN BE CONTROLLED WITH THESE PARAMETERS.- SPDS WILL BE FULLY FUNCTIONAL BY FEBRUARY 1986 >>>
^ ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
L
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L_ E A R P L_ A N T DATE: 05/01/84 F4 EE I) P4 C3 . = ~5 97 97 REVIEWER: CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: OTHER CHECKLIST NO.: ,
PANEL / WORKSTATION NO. ERIS DESCRIPTION OF DISCREPANCY:
THE PROPOSED 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 DESION TO SUPPORT OPERATORS.'
<<<THE DESIGN IS COMPLETE AND HAS BEEN IMPLEMENTED. TABLE HAS BEEN FABRICATED AND INSTALLED PER THE ELDCR LISTED BELOW >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# C52,757 ISSUE DATE 01/,31/85 FDDRM ISSUE DATE / /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
r u HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND- NUCLEAR PLANT DATE: 07/06/84 HED NO = 576
- REVIEWER: LER/ LIDDLE TRACKING STATUS: SCHEDULE PHASE
____ - _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = - - __ -. -____ ----_____ __________
DATA SOURCE: 1 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.JTHE CAUSE WAS AN OVER DEPENDENCE ON THE CRT BY THE OPERATORS
' RECOMMENDATIONS:
GSU OPERATORS ARE NOT NORMALLY GOING TO USE THE CRT TO PLOT-HEAT-UP RATE. A RECORDER ON P-845 WILL BE USED.
<<< PROCEDURE GOP-OOO1 REQUIRES THE RECORDING OF HEATUP RATE INFORMATION.>>>
ACTION:
APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE ./ /
CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
i 3
APPENDIX G
+
SAFETY EVALUATION REPORT HUMAN ENGINEERING DISCREPANCIES FROM T.E.R. APPENDIX B
(
I l
i G-1 l
L
1;
-F4W M A N ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct._E A R P L_. A N T DATE: 02/28/84 F4 EE I) b4 C3 = 1 l et REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
______________ ___________________= _____________________________________
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.2.
CHECKLIST AREA: PANEL LAYOUT AND DESION
' PANEL / WORKSTATION NO. P863-74
( I.)
PANEL / WORKSTATION NO. PB63-75
( 1.)
~ DESCRIPTION OF DISCREPANCY:
COMPONENTS ORDERED LEFT/RIGHT RECOMMENDATIONS:
' DIVISIONAL SEPARATION CRITERIA DICTATES THE PRESENT COMPONENT ORDERING. NO
-ACTION.
.<<< C60,972 HAS BEEN GENERATED SINCE THIS HED WAS WRITTEN. IT-IMPROVES THE
.GROUPIING OF CONTROLS INTO AN OPTIMUM ARRANGEMENT FOR THE DIVISIONAL
' SEPARATION CONSIDERATIONS THAT EXIST. WORK WILL BE COMPLETE PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
L k.
y t-
' HUMAN ENGINEERING DISCREPANCY RECORD-RIVER BEND NUCLEAR PLANT DATE: 02/21/04 FiEEI) bJ C3 . - z 03 ds E3 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.6 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P870-55 ,
PANEL / WORKSTATION NO. P870-56 I DESCRIPTION OF DISCREPANCY: .
TOP ROW OF METERS IS 72 INCHES OFF THE GROUND <<< (BOTTOM / TOP 66.5 IN/72 IN) > > > AND FOUR ROTARY CONTROLS.ARE 65 INCHES RECOMMENDATIONS:
NO ACTION. THIS IS STANDARD HEIGHT FOR METERS IN THE CONTROL ROOM. <<<THE FOUR CONTROLS ARE OFF/ON SWITCHES FOR INOPERABILITY INDICATION LIGHTS. THEY DO NOT CONTROL ANY SYSTEM FUNCTIONS. THEY ARE LOCATED THERE TO BE IN CLOSE PROXIMITY TO THEIR RELATED INOP. LIGHTS. SWITCHES THAT PERFORM A FUNCTION ARE 60" OR LESS FROM THE FLOOR. METERS FACES ARE BOTTOM / TOP 66.5"/72" & ARE CLEARLY VISIBLE BY ALL OPERATORS.>>> .
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
L
F4UMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATEi'02/20/84 F4 EE I) b4C3 . = 22 97 97 LREVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR' OWNERS GROUP CHECKLISTLNO.: AS.10 .
CHECKLIST AREA:-PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-16
( 1.)
-DESCRIPTION OF DISCREPANCY:
THERE IN AN UNLABELED METER ON P601-16 RECOMMENDATIONS:
THE METER IS BLANK.140 ACTION REQUIRED.
<<< SINCE THIS HED WAS WRITTEN,THE SERVICE WATER PUMP C AMPS METER HAS BEEN
-LOCATED IN THIS POSITION . NO FURTHER ACTION REQUIRED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E8<DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
.* a HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL EAR PL ANT
- DATE: '02/24/84 _
FiEE E) P4 03 . = 22 53 E3
/
REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
_ . = = - -
_ = -----------------------------------------------
DATA. SOURCE: BWR OWNERS GROUP CHECKLIST NO.: Bl.3 ,
l CHECKLIST AREA: INSTRUMENTATION AND HARDWARE e
'l
- PANEL / WORKSTATION'NO. GENERIC 3
Y
_ _ _ _ _=---------------------=
2 DESCRIPTION OF DISCREPANCY:
'<<<DUE TO THE CONSTRUCTION PHASE OF RBS, BAILEY CONTROLLERS ARE COLLECTING DIRT IN.THE BUTTONS. THIS WILL,,00ER A PERIOD OF TIME, OBSCURETHE WORDS
'CLOSE' AND 'OPENON THE BUTTONS >>>
1 p RECOMMENDATIONS:
' ALL RBS BAILEY C,0NTROLLERS ARE LAYED OUT THE SAME WITH CLOSE BUTTON ON LEFT
--CORRESPONDING TO 0% & OPEN ON RIGHT CORRESPONDING TO 100%. NO ACTION.
'<<<THE MAIN CONTROL ROOM WAS IN THE' CONSTRUCTION PHASE WHEN THIS HED WAS I GENERATED.-ONCE.THIS PHASE IS COMPLETED, GSU OPERATIONS CAN MONITOR CONTROL b BOARD. CLEANLINESS AND INITIATE CLEANING AS REQUIRED >>>
ACTION:
- APPROVED BY GSU MANAGEMENT ,
t L
L- E&DCR# ISSUE DATE / /
h FDDRM j ISSUE DATE / /
==
Y - - - =__--__-_-_-_-____-_---_-_ ---
CRITICALITY l RATING: 2 1 IMPLEMENTATION SCHEDULE:
/
~
. HUMAN , ENGINEERING DISCREPANCY RECORD f
RIVER' BEND NUCLEAR' Pt. ANT DATE:.09/19/84 HED NO- = 8'27 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ _ _ _ _ _ - - _ _ - - - - - - - - - - - - - .___= = =--
. DATA SOURCE: -OPERATING PERSONNEL INTERVIEW CHECKLIST NO.:.B2 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601
-( 1.)
____ =_ - _ _ _ _ _ - - - - - _ - - - - - - - - = = = - - = - . _ _ _ - - _ _ _ - - - - - = _ _ _ ___
DESCRIPTION.0F DISCREPANCY:
.<<< SYSTEM' PARAMETERS DISPLAYED ON ECCS (LPCS) PANELS ARE AMPS AND' FLOW _
INDICATORS ONLY. ALSO NEED PRESSURE INDICATION >>>
RECOMMENDATIONS:
"<<<LPCS IS DESIGNED PRIMARILY FOR RE-FLOOD AFTER A DESIGN BASED LOCA WHERE Rx PRESSURE IS " LOW". DURING TRAINING ON THE SIMULATOR, OPERATORS ARE. TAUGHT IN' PART,-TO MONITOR LPCS SYSTEM STATUS AS A FUNCTION OF RPV PRESSURE (IE.
ALTHOUGH THE LPCS-SYSTEM
.WILL INITIATE UPON RECEIPT OF A HIGH DRYWELL PRESSURE OR LOW Rx WATER LEVEL
. SIGNAL, IT WILL NOT INJECT INTO THE RPV UNTIL RPV PRESSURE DECREASES TO BELOW THE LPCS INJECTION VALVE INTERLOCK PRESSURE ). IN ADDITION, OPERATORS ARE TRAINED TO KEY IN ON
- FLOW RATES, AND THE RELATIONSHIP BETWEEN PUMP HEAD AND FLOW RATES. POSITIVE
! INDICATION.0F4 FLOW IS GIVEN FROM THE FLOW METER AND DIRECTLY THROUGH THE TESTABLE. CHECK VALVE WHICH HAS DIRECT INDICATION OF POSITION.LPCS SYSTEM PRESSURE IS NOT REQUIRED >>>
. ACTION:
'APPROVEDLBY.GSU MANAGEMENT <<< INFO. REQUIRED IS DOCUMENTED IN TASK SEQUENCE
< TASK SEQUENCE 1590 & 1610'(RPV PRESSURE / INJECTION VALVE INTERLOCK). NO FURTHER-ACTION' REQUIRED >> ,
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
-_______--- =--_________-________-_____ -
' CRITICALITY RATING: :2 '
IMPLEMENTATION SCHEDULE:
HUMAN ENGINEERING DISCREPANCY RECORD RIVER- BEND NUCL EAR P L_ ANT DATE: 02/29/84 Fi EE I) P4 03 . = 1 E3 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
_- - - _ - - - - _ ==----------- . - - = - - -
DATA ~ SOURCE: BWR' OWNERS GROUP CHECKLIST NO.: B2.13 CHECKLIST AREA:- INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. C61-POO1
-(- 1. ) .
DESCRIPTION OF' DISCREPANCY:
RPV. PRESSURE HAS SUBDIVISIONS IN MULTIPLES OF 3 RECOMMENDATIONS:
NO ACTION. OPERATIONS PERSONNEL FIND THE SCALE ON THIS METER TO BE.
APPROPRIATE. <<< THE SCALE HAS MINOR INCREMENTS OF 20, INTERMEDIATE
- INCREMENTS OF 100, AND MAJOR INCREMENTS OF 300 . THE ORIGINAL DESCRIPTION OF DISCREPANCY WAS MISLEADING >>>
ACTION:
APPROVED BY GSU-MANAGEMENT ~
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
-= _ -- -__ - - _ = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
' CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
M l
u.
HUMAN ENGINEERING -DISCREPANCY RECORD
-RIVER BEND- NUCLEAR PLANT
, JDATE: 02/23/84- HED N O :: 435
_ REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - - _ - - - - - -- = . --_____-------------_ ---
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: 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 QUT WHEN SCRAM' SIGNAL IS IN.)
RECOMMENDATIONS:
- <<< SIMULATOR >>> TRAINING PROPERLY ADDRESSES THIS. THE SCRAM STATUS IS ALSO ANNUNCIATED.
<<< THE SCRAM SOLENOID LIGHT INDICATES THAT THE SCRAM. SOLENOID IS ENERGIZED.
WHEN YOU LOSE INDICATION, YOU HAVE LOST POWER TO THESE SOLENOIDS. THESE ARE WHITE,_ POWER AVAILABLE LIGHTS.. THIS IS CONSISTENT WITH RBS CONVENTIONS. NO L- FURTHER ACTION '
REQUIRED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E84DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
_ _ _ _ _ _ - _ - _ - - _ _ _ _ _ _ - _ - _ _ - - - _ = _ _ - - - - - ---_-_-_------ _=--__-------_--_-_______
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
7,.~.
i HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
~DATE: 02/21/84 F4 EE E) P4 C3 . = dad 2C)
~
. REVIEWER: BURGY/ CHASE / BISHOP TRACKING STATUS: SCHEDULE PHASE
=-_ -------__--___-_-- --_ - =--___-----------___-----_-____
' DATA SOURCE:.BWR OWNERS GROUP CHECKLIST NO.: B5.6 .
CHECKLIST AREA: INSTRUMENTATION AND HARDWARE
- PANEL / WORKSTATION NO. P601-20C PANEL / WORKSTATION NO. P601-17C
___-----_-___------ . - _ - . _-----------_ =_---__ _ _ _ _ _ _ _ _ - - - _ - -
DESCRIPTION OF. DISCREPANCY:
FOR SWITCHES,' HANDLES.ARE NOT DURABLE AND OF ADEQUATE' SIZE.
RECOMMENDATIONS:
INVESTIGATE CHANGING SWITCH' HANDLES
'<<<THESE." PISTOL GRIP" SWITCHES ARE MADE BY ELECTROSWITCH AND ARE A STANDARDL
- DESIGN USED:IN THE NUCLEAR INDUSTRY. THE OPERATOR ON THE SURVEY REVIEW-TEAM HAD A' PREFERENCE.FOR THE LARGER HANDLED SWITCHES FOUND ON OLDER CONTROL BOARDS. THIS PREFERENCE IS NOT SHARED BY THE GSU OPERATIONS DEPT. THAT TYPE OF SWITCH IS NOT APPROPRIATE FOR THE RBS CONTROL BOARDS AND IS NOT NECESSARY. THE
'ELECTROSWITCH. SWITCH IS DURABLE AND APPROPRIATELY SIZED FOR RBS.>>>
, ' ACTION:
NO' ACTION. THESE SWITCHES ARE APPROPRIATE AND ARE USED TO DISTINGUISH PUMPS FROM VALVES.
[l E&DCR# ISSUE DATE / /
.FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
L
~%p-D .x
DISCREPANCY RECORD HUMAN ENGINEERING BEND NUCLEAR PLANT RIVER F4EEE)- bJ C3 . = db 461 DATE: 02/21/84-TRACKING STATUS: SCHEDULE PHASE REVIEWER: BURGY/ CHASE
.-------------------=------.
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B5.8 CHECKLISTLAREA: 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 FR IS OPERATED.
FROM VISUAL OBSTRUCTION BY HAND OR ARM WHEN SWITCH RECOMMENDATIONS: ISPLAYS IS EVALUATION BY. OPERATIONS DETERMINED THAT LAYOUT OF CONTROLS & D CORRECT AND THAT NO. CHANGE IS REQUIRED.
-<<<THIS INSERT WAS REVIEWED AGAIN TO DETERMINE WHAT THE EX OR IS. NO VISUAL OBSTRUCTION BY HAND OR ARM WAS FOUND WHEN OPERATING SWITCHES. MODIFICATIONS HAVE OCCURRED ON THIS INSERT SINCE THE SURVEY WAS COMPLETED. IN.THAT
.THE REVIEW. TEAM BELIEVES THAT THE DISCREPANCY HAS ELIMINATED MANNER.>>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
.FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
c.
fHUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/22/84 HED N O :: 2 CP O REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
_ _ = - - - - - _-----------_------= - _ - - _ - - - - _-
! DATA SOURCE: .BWR OWNERS GROUP CHECKLIST NO.: 'C2.7 .
CHECKLIST AREA: ANNUNCIATORS PANEL / 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 <<< APPROPRIATELY LOCATED >>> ON 19B INSERT. OPERATOR ~
ACTION WILL BE THE SAME WHETHER TEMP. IS HIGH OR LOW <<< (DISPATCH AN OPERATOR IN A TIMELY MANNER TO THE' TANK >>>
<<<11) STANDBY LIQUID HEAT TRACE TEMP. HI/ LOW / POWER LOSS; OFFGAS COMB.-
PRETREAT SAMPLE HI/ LOW FLOW; OFFGAS POST-TREAT SAMPLE HI/ LOW FLOW;AND OFFGAS VENT 1 PIPE SAMPLE HI/ LOW FLOW ANNUNCIATORS ARE ON THIS INSERT. THE OPERATOR ACTION WILL BE THE SAME
-FOR THESE ANNUNCIATORS ALSO.2) NEEDED INSTRUMENTATION IS ON 19B INSERT WHICH IS DIRECTLY BELOW ANNUNCIATORS.3)AN NEO WILL BE DISPATCHED FROM THE CONTROL ROOMETO' EVALUATE THE ANNUNCIATED CONDITION.THIS IS CONSISTENT WITH GOOD-HUMAN FACTORS PRINCIPLES)
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
L
HUMAN ENGINEERING . DISCREPANCY RECORD RIVER BEND NUCL EAR P L_ A N'T DATE: 02/23/84 HED NO_ :: 543 REVIEWER: BURGY/ CHASE -TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: SB4.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680
=-
DESCRIPTION OF DISCREPANCY:
KEY-OPERATED SWITCHES ARE NOT USED ONLY WHERE APPROPRIATE (i . e. TO' PREVENT UNAUTHORIZED CONTROL ACTUATION.) <<< SCRAM RESET SWITCHES SHOULD NOT BE KEYLOCK >>>
RECOMMENDATIONS: ,
NO ACTION. OPERATORS ARE WELL TRAINED ON THE USE'OF THESE SWITCHES .<<<SINCE THIS HED WAS SUBMITTED, THE' DECISION WAS MADE TO CHANGE THE SCRAM RESET
.-SWITCHESJSO THAT THEY ARE NOT KEY-LOCK TYPE (SEE HED 417)>>>
' ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
_ - - - - - - - - - - - - - - - - - _ - = - ------------------------------
CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE:
7 --
HUMAN ENGINEERING DISCREPANCY RECORD
. RIVER BEND NU C L_E AR PI_ ANT
.DATE: 02/22/84- HED NO = 288 REVIEWER: -LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
-DATA SOURCE: BWR OWNERS GROUP
' CHECKLIST-NO.: C1.1' CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P601-18 PANEL / WORKSTATION NO. P601-19 PANEL / WORKSTATION NO.-P601-22
_ _ _ _ . _ ______________- _________ - _ = = -
DESCRIPTION OF DISCREPANCY:
ANNUNCIATORS ARE NOT OROUPED BY SPECIFIC SYSTEM RECOMMENDATIONS:
' OPERATIONS EVALUATED THE ANNUNCIATOR ARRANGEMENTS AND FOUND THEM TO BE
-APPROPRIATE. NO FURTHER ACTION REQUIRED. <<< SINCE SURVEY, SEVERAL ALARM
. WINDOWS HAVE BEEN CHANGED. THE ANNUNCIATORS ARE NOW APPROPRIATELY GROUPED.
ANNUNCIATORS ARE LOCATED ABOVE
-THE SYSTEMS THEY ARE ASSOCIATED WITH, WITH THE EXCEPTION OF CERTAIN OFFGAS ANNUNCIATORS. THE MONITORS ARE LOCATED ON P604 WHICH HAS NO ANNUNCIATOR INSERT, THEREFORE,'THESE ALARM ARE GROUPED ON THIS INSERT.
' ACTION:
-APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
f HUMAN ~ ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: ~02/27/84 F4 EE E) P4 [3 . = 55 97
^
REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
. _ _ = - _ _ - - - _ = - - - - - __--------------
DATA SOURCE: 'BWR OWNERS GROUP CHECKLIST NO.: C 1.1.
CHECKLIST AREA: ANNUNCIATORS .
-PANEL / WORKSTATION NO. P808-85A
( 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.
<<< SINCE THIS HED WAS WRITTEN, THESE ANNUNCIATORS HAVE BEEN. DELETED. NO FURTHER-ACTION REQUIRED.>>>
- ACTION:
' APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
L
P '(
HUMAN ENGINEERING DISCREPANCY RECORD -
RIVER BEND N U Ct_.E A R P L_ ANT DATE: 02/23/84 Fi EEI) bJ C) . = 4F 551 REVIEWER: BURGY/ CHASE TRACKING STATUS:-SCHEDULE PHASE
_______ - - - - - - - . - =_ -- -
--- = - - _ _
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C5.6 .
= CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO.-GENERIC
( 1.)
, ________________________ ________________________________==- =______
' DESCRIPTION OF DISCREPANCY: ~
JALARM RESPONSE IS NOT PROVIDED A "FIRST-OUT" FEATURE OR DUAL RESET FOR
'INFORMATION RETRIEVAL HIGH PRIORITY ALARMS.
RECOMMENDATIONS:
BOTH-SPDS'AND PMS HAVE SEQUENCE OF EVENTS FEATURE FOR PRE-SELECTED HIGH
~PR10RITY ALARMS."NO FURTHER ACTION REQUIRED.<<< ANNUNCIATORS THAT CAUSE Rx SCRAM OR LARGE EQUIPMENT MALFUNCTIONS WILL BE' CODED RED SO THAT-INCIDENT
- CAUSING ALARMS ARE EASILY IDENTIFIABLE. ALERT STATUS ALARMS WILL BE CODED AMBER TO INDICATE A POTENTIAL CONDITION THAT COULD CAUSE A Rx-SCRAM OR LARGE EQUIPMENT MALFUNCTION . ALARM ARE- ON ALARM PRINTER. SPDS WILL BE FULLY FUNCTIONAL BY FEBRUARY 1986.N3>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
' CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
p_.
HUMAN ENGINEERING DISCREPANCY RECORD
- RIVER BEND NUC L.E AR PL ANT DATE: 02/28/84 HED NO- :: 195
' REVIEWER: BARKS / CHASE /SHANKLE 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. ERIS DESCRIPTION OF DISCREPANCY: -
ILLUMINATION IS BELOW THE RECOMMENDED 50 FOOTCANDLES RECOMMENDATIONS:
INVESTIGATE. METHODS'OF INCREASING ILLUMINATION
<<<'A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS SUCH THAT ALL READINGS WERE IN COMPLIANCE WITH NUREG 0700 GUIDANCE. NO FURTHER ACTION REQUIRED >>>
ACTION:
' STONE & WEBSTER IS EVALUATING CONTROL' ROOM ILLUMINATION AS A RESULT OF.DCRDR.
FINAL LIGHT READINGS WILL BE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE
, IMPLEMENTED & FLOORING IS INSTALLED.
E&DCR# P-22305 ISSUE DATE 01/11/85 FDDRM ISSUE DATE / /
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = = - - - - - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD P
1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
-DATE: 02/23/84 HED NO. = 2O2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
= = - - - _ --------------- ------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: B2.3 CHECKLIST AREA: INSTRUMENTATION AND HARDWAR'E 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 RECOMMENDATIONS:
INVESTIGATE' WAYS-IMPROVING THE CONTROL ROOM LIGHTING A LIGHTING SURVEY WAS CONDUCTED BY R. LIDDLE AND D. CHASE ON 5/2/85. THE IMPROVED LIGHTING DESIGN INCREASED THE LIGHTING LEVELS. THIS EVENED OUT THE CONTROL ROOM LIGHTING BECAUSE THE LIGHTING SURROUNDING THE MAIN CONTROLS AREA HAD PREVIOUSLY BEEN BRIGHTER. NO FURTHER ACTION REQUIRED >>>
ACTION: .
STONE & WEBSTER IS EVALUATING THE CONTROL ROOM ILLUMINATION AS A. RESULT OF DCRDR. FINAL LIGHT READINGS WILL BE TAKEN AFTER DESIGN CHANGES (IF ANY) ARE IMPLEMENTED AND FLOORING IS INSTALLED.
E&DCR# P-22305 ISSUE DATE 01/11/85 FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
m v
HUMAN ENGINEERING DISCREPANCY RECORD RIVER' BEND NUCLEAR PLANT
'DATE: 02/23/84 HED NO = 552 REVIEWER: SPDS TRACKING STATUS: SCHEDULE PHASE
== _ _ _-- - - --
== ------------------------
DATA SOURCE: 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.
<<< THE TECHNICAL EVALUATION HAS BEEN COMPLETED. IT WAS DETERMINED THAT NO MODIFICATIONS ARE REQUIRED FOR THE EXISTING SYSTEM . THIS EVALUATION SHALL BE PUBLISHED IN THE RBS REG. GUIDE 1.97-REV. 3 COMPLIANCE REPORT, SCHEDULED FOR NRC-SUBMITTAL BY FUEL LOAD >>>
ACTION:
SUBMIT RESOLUTION PLAN PRIOR TO FUEL LOAD. <<< SUBMIT RG 1.97 COMPLIANCE
-REPORT BY FUEL LOAD >>>.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE ' PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT iDATE: 02/27/84 FiEEL)- bJ C3 . = E3 C2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
/ DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: 5.6 CHECKLIST AREA: CHECKLIST AREA NOT FOUND ,
PANEL / WORKSTATION NO. GENERIC
( 1.)
DESCRIPTION OF-DISCREPANCY:
. G.S.U. ENGRAVED LABELS ARE HARD TO READ RECOMMENDATIONS:
CHANGE ILLEGIBLE GSU LABELS TO USE A MORE DISTINCTIVE LABEL
<<.<THIS GENERIC CHANGE WILL BE COMPLETED THROUGHOUT THE CONTROL ROOM PRIOR TO EXCEEDING'5% POWER >>>
ACTION: -
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2
. IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER u.
p --
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/24/84 Fi EE I) D4 C3 - = 02 :5 03 REVIEWER: LIDDLE /MATsON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A1.1 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-81B PANEL / WORKSTATION NO. P808-83B PANEL / WORKSTATION NO. P808-84D DESCRIPTION OF DISCREPANCY:
<<<INOPERABILITY INDICATOR LIGHTS HAVE HANDWRITTEN LEGENDS AND ARE HARD TO READ. MAKE PERMANENT LADEL.>>>
RECOMMENDATIONS:
CHANGE STATUS MATRICES LEGENDS TO ALLOW EASE OF READING
<<< LEGENDS WILL BE CHANOED PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E'uDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER s
HUMAN ENGINEERING DISCREPANCY ' RECORD RIVER BEND NUCLEAR PLANT
'DATE: 02/27/84 F4 EE I) P4 C3 . = 77 db REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE:.BWR OWNERS GROUP CHECKLIST NO.: oA2.10
' CHECKLIST ARCA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71
( 1.)- 1HVR*A02 264
( 2.) 1HRV*AOD18D PANEL / WORKSTATION NO. P863-72
( 1.) 1HRV*AOD18B PANEL / WORKSTATION NO. P063-73
( 1.). 1HRV*AOD18B DESCRIPTION OF DISCREPANCY:
NO STARTING OR ENDING POINTS ARE IDENTIFIED RECOMMENDATIONS: -
ADD STARTING AND ENDING POINTS
.<<<THE MINIC'WILL BE CHANGED TO SHOW PROPER SYSTEM CONFIGURATION WHICH INCLUDES STARTING AND END POINTS . TECH SPEC 3.6.5.4 ONLY REQUIRES THIS SYSTEM IN CONDITIONS 1,2,& 3. THIS SYSTEM IS NOT REQUIRED FOR FUEL LOAD >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
. CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
-v HUMAN ENGINEERING DISCREPANCY RECORD
' RIVER BEND. NUC L_ E AR PL_ A NT DATE: 02/28/84 FiEII) D4 03 . = . 1125 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
.__________ - _ _ _ _ _ _ -_ = _ - _ . _ _ _ _ _ _ - - - - - -
=______------_______-____--_____
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.* A2.10 *
. CHECKLIST 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
<<<SINCE THE SURVEY, STARTING AND END POINTS HAVE BEEN ADDED TO THE MIMIC .
NO FURTHER ACTION REOUIRED >>>
ACTION:
' APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L.
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND- NUCL EAR PL ANT DATE: 02/28/84 FiEEI) b4 C3 . = 1 53E3 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.2 .
CHECKLIST AREA: ~ PANEL LAYOUT AND DESIGN PANEL / WORKSTATION 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
<<< LABELS, LINES OF DEMARCATION AND COLOR PADS WILL BE USED TO ENCLOSE
.RELATED DISPLAYS . THIS GENERIC CHANGE WILL BE IMPLEMENTED-THROUGHOUT THE
' CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
' CRITICALITY RATING: 2
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER t
n~ ,
HUMAN ENGINEERING DISCREPANCY RECORD RIVER -BEND NUCLEAR PLANT DATE: .02/23/84 HED NO :: 23 c7 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
_-_ _ _ _ _:_ _ - - - - _ _ _ - - - - - - - - = = - - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.2 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN -
PANEL / WORKSTATION NO. P870-51C PANEL / WORKSTATION NO. PB70-52C
__________________________ ===_===- - _ _ _ _ _ _ _ _ _ _ = - - -- =______________
DESCRIPTION OF DISCREPANCY:
COLOR DEMARCATION NEEDED TO CONNECT SWITCHES IN SYSTEM RECOMMENDATIONS:
ADD DEMARCATIONS TO CONNECT SWITCHES IN SYSTEM
<<< DEMARCATION WILL BE ADDED TO RELATE CONTROLS WITH THE SYSTEM >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
r== , ,
)i HUMAN ENGINEERING DISCREPANCY RECORD RIVER. BEND NUCL EAR Pl._ A N T DATE: 02/27/84 FiEEI) h4 03 - = 77 2 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
= = = - -------------- - ---- _-------- _=--------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.3 .
CHECKLIST. AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-71C
( 1.)
PANEL / WORKSTATION NO. 72C
( 1.)
PANEL / WORKSTATION NO. 73C
( l.)
~ DESCRIPTION OF DISCREPANCY:
LINES OF DEMARCATION ARE NOT USED TO SEPARATE SYSTEMS OR SUBGROUPS
-RECOMMENDATIONS:
.USE LINES OF DEMARCATION TO SEPARATE SYSTEMS
<<<. LINES OF DEMARCATION WILL BE ADDED . THE ADDITION OF THESE LINES DURING
-THE PERIOD OF INITIAL REACTOR STARTUP OPERATIONS WILL NOT CAUSE OPERATOR CONFUSION >>>
ACTION:
APPROVED BY GSU MANAGEMENT ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
w DISCREPANCY RECORD HUMAN ENGINEERING BEND NUCtEAR PL ANT RIVER F4 EEI) D4 C3 . = 1 C)97 DATE: 02/28/04 TRACKING STATUS: SCHEDULE PHASE l REVIEWER: BARKS / CHASE /SHANKLE
=
DATA SOURCE:'BWR OWNERS GROUP CHECKLIST NO.: A2.3 .
' CHECKLIST _ AREA: PANEL LAYOUT AND DESIGN 1
PANEL / WORKSTATION NO. P863-74C
( 1.)
PANEL / WORKSTATION NO. P863-75C
( 1.)
DESCRIPTION OF DISCREPANCY:
LINES OF DEMARCATION ARE NOT USED TO PROVIDE SEPAL <ATION RECOMMENDATIONS:
USE LINES OF DEMARCATION TO SEPARATE SYSTEMSTHE ADDITION OF TH
<<< LINES OF DEMARCATION WILL DE USED.
INITIAL REACTOR STARTUP OPERATIONS WILL NOT CAUSE OPERATO ACTION: .
APPROVED BY GSU. MANAGEMENT.
ELDCRM ISSUE DATE / /
ISSUE DATE ./ /
FDDR#
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER b_
HUMAN . ENGINEERING DISCREPANCY RECORD i
RIVER BEND N U Ct._E A R Pt_.A N T DATE: 02/28/84 HED N O :: 11O REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ____________._____ =- ___________________________________
DATA SOURCES-BWR-OWNERS GROUP CHECKLIST NO.: A2.4 CH'ECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-74C
( 1.)
PANEL / WORKSTATION NO. P863-75C
( 1.)
DESCRIPTION OF DISCREPANCY:
MIMICS ARE NOT USED TO DISTINGUISH BETWEEN PRIMARY AND SECONDARY.FLOWPATHS RECOMMENDATIONS:
-USE DIFFERENT WIDTH MIMICS TO DISTINGUISH DETWEEN FLOWPATHS <<< TO USE DIFFERENT WIDTH MIMIC HERE IS NOT POSSIBLE OR PRACTICAL SINCE THE SECONDARY FLOW PATHS USE SOME OF THE PRIMARY PATHS AND THERE IS MORE THAN ONE SECONDARY PATH. THIS WOULD CAUSE THE USE'OF SEVERAL DIFFERENT SIZES OF MIMIC. MIMIC WILL DE ADDED TO SHOW PROPER SYSTEM CONFIGURATION >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE PRIOR TO EXCEEDING 5'/. POWER
HUMAN . ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
.DATE:,02/24/84 HED NO.= 203 REVIEWER: LIDDLE /MATSON/ BISHOP' TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.6 CHECKLIST. AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-878 DESCRIPTION OF DISCREPANCY:
RED MIMIC LINES FALLING OFF OR MISSING ON BATTERY SYSTEM: BROWN SECTIONS ARE LIFTING RECOMMENDATIONS:
REPLACE / PERMANENTLY ATTACH MIMIC LINES AS REQUIRED
<<< PERMANENT MIMIC HAS DEEN ORDERED AND WILL DE INSTALLED PRIOR TO EXCEEDING 5% POWER. TEMPORARY MIMIC WILL DE INSTALLED PRIOR TO FUEL LOAD AS AN INTERIM CORRECTIVE ACTION >>>
ACTION:
APPROVED DY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITIC 4LITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD l
r i
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO a 313 REVIEWER:: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP
. CHECKLIST NO.: A2.6 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. PG63-76C DESCRIPTION OF DISCREPANCY:
- THERE IS NO FLOW PATH DISPLAYED INTO OR OUT OF 1HVF*AOD101.
RECOMMENDATIONS:
DISPLAY A FLOW PATH
<<< MIMIC HAS DEEN ORDERED AND WILL BE INSTALLED PRIOR TO EXCEEDING 5%' POWER.
. ACTION: ,
' APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
__r -__.____ . _ _ _ . _ . _ _ _ _ . . _ _ . - . . . _ _ _ . _ _ _ _ _ _- _ _ . _ _ _ -
' HUMAN- ENGINEERING . DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/28/84- HED NO a 129 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST-NO. A2.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / 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:
RELADEL TO INDICATE IN WHICH STEAMLINE THE VALVE 1G LOCATED.
<<< THESE LADELS ARE LOCATED ON DACK PANELS THAT ARE NOT REQUIRED FOR FUEL LOAD. LABELS WILL DE ADDED PRIOR TO EXCEEDINO 5% POWER >>>
ACTION:
APPROVED DY GSU MANAGEMENT. ,
E&DCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDINO 5'/. POWER l
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND. NUCLEAR PLANT DATE: 02/27/84 HED NO- = 73
' REVIEWER . BARKS / CHASE /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.)
PANEL / WORKSTATION NO. P863-72
( 1.)
' PANEL / WORKSTATION NO.-PG63-73
( 1.) .
DESCRIPTION OF DISCREPANCY:
VALVES AND FANS ARE NOT ARRANGED IN AN ORDERLY AND EASILY RECOONI2ED MANNER RECOMMENDATIONS:
COLOR CODINO WILL BC ADDED FOR SWITCHES TO DISTINGUISH PUMPS AND VALVES. ADD FLOW DIRECTION ARROWS FOR MIMIC.
<<<SEVERAL' ARROWS HAVE DEEN'ADDED SINCE THE SURVEY TO CLARIFY FLOWFATH. COLOR
- CODINO OF SWITCHES IS A DENERIC CORRECTIVE ACTION THAT WILL DE COMPLETED PRIOR TO EXCEEDING 5% POWER >>> a ACTION:
APPROVED BY GSU MANAGEMENT.
I C&DCR4 IGSUC DATE / ,
FDDR# ISSUE DATE /
T' CRIT (CALITY RATING: 2 IMPLEMENTATION f1CHC LE: PRIOR TO EXCEEDING 5% POWER i
_m___ _ _ _ _.
HUMAN. ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
.DATE: '02/28/84 F4 EEI) b4 C3 . = 111 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST'NO.: A2.7 .
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-74C'
( 1.)
PANEL / WORKSTATION NO. :PO63-75C-( 1.)
DESCRIPTION OF DISCREPANCY:
. PORTIONS OF THE MIMIC ARE MISSING / SPARSE USE OF ARROWS MAKE THE FLOW PATH AMBIGUOUS RECOMMENDATIONS:
REPAIR MIMICS TO MATCH CONTROL ROOM DESIGN CONVENTION
<<<SINCE THE SURVEY, MIMIC HAS DEEN ADDED IN APPROPRIATE. PLACES AND ARROWS HAVE BEEN-ADJUSTED TO REFLECT PROPER FLOW >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
p T '
t.,
HUMAN ENGINEERING DISCREPANCY , RECORD RIVER. BEND NU C L_ E AR PL. ANT p .DATE: 02/20/84 HED NO = 294
^ ~ REVIEWER:' LIDDLE /MATSON/ BIS' HOP TRACKING STATUS: SCHEDULE PHASE
_ _ _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - -- - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ - - _ - _ _
DATA' SOURCE: - BWR OWNERS GROUP CHECKLIST NO.: A2.8
- CHECKLIST AREA
- PANEL LAYOUT AND DESIGN'
, , p.
X - 8 9' PANEL / WORKSTATION NO. P877-31
' PANEL / WORKSTATION NO. P877-32 PANEL / WORKSTATION NO. P601-16 yff . -
I
!' # DESCRIPTION OF DISCREPANCY:
l MIMIC LINE MISSING BETWEEN 1EJS*SWG.1B'& 1EJS*ACB050//AND//1EJS*SWG 2B &
i 1EJS*ACB066.
t i
j RECOMMENDATIONS:
r INSERT-MIMIC LINE BETWEEN SWITCHES
<<< THERE SHOULD NOT BE A MIMIC LINE FROM 1EJS*SWG1B & 1EJS*ACB050. .THE OTHER MIMIC WILL BE ADDED >>>
-ACTION:
APPROVED BY GSU MANAGEMENT. -
/
Y
. s/
E&DCR# '~ ISSUE DATE
~
/ /
FDDR# ISSUE-DATE / /-
CRITICALITY RATING: 2 IMPLEMENTATION' SCHEDULE: PRIOR TO FUEL LOAD
~.]
i.
v- #
y/
r W.-.-..,T. ..... . . . .
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT 1
DATE: -02/27/84- Fi EE I) P4 03 . = 77 z4 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---_- - .-______--- --- - - - - - ___--_ -_=- -- - ===---_----___---_____---
l
- DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A2.9 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863 '
( 1.)
PANEL / WORKSTATION NO. P863-72
( 1.)
PANEL / WORKSTATION NO. P863-73
( 1.)
= . ------------------------------ _ = ---------_-------_--------------
t L
DESCRIPTION OF DISCREPANCY:
I THERE ARE TOO FEW ARROWS INDICATING THE MIMIC'S FLOW PATH RECOMMENDATIONS:
ADD ARROWS TO INDICATE FLOW PATH L<<<'THE ADDITION OF ARROWS DURING INITIAL STARTUP OPERATIONS WILL NOT CAUSE OPERATOR CONFUSION. ARROWS WILL BE ADDED PRIOR TO EXCEEDING 5% POWER >>> 3 6'
1 ACTION:
-APPROVED BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
-CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: FRIOR TO EXCEEDING 5% POWER
.n
r-HUMAN ENGINEERING DISCREPANCY RECORD RIVER- BEND NUC L.E A R Pt. ANT
'DATE: 02/28/84 FiEEI) b4 03 . = 11:2 l-
. REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
---____--_______- =-- - -_-_--_--_____--__---______-_---___--___________--_-___-
! . DATA SOURCE: BWR OWNERS GROUP'
' CHECKLIST NO.: A2.9 CHECKLIST AREA: PANEL' LAYOUT AND DESIGN PAN $L/ WORKSTATION NO. P863-74
'( 1.)
-PANEL / WORKSTATION NO. P863-75
( 1.)
- _ _ = - _ _ -
- - - - - - - - - _ _ _ - - - - - _ - - = ---______---____-----_-----_-----_---__
DESCRIPTION OF DISCREPANCY:
JARROWS.DO NOT COMPLETELY SHOW FLOW RECOMMENDATIONS:
'USE ARROWS'TO SHOW FLOW
<<<THE-NEW MIMIC TO LE USED HAS ARROWS INCORPORATED INTO THE TAPE. THE ADDITION OF ARROWS DURING INITIAL STARTUP OPERATIONS WILL NOT CAUSE OPERATOR
-CONFUSION . ARROWS WILL BE ADDED PRIOR TO EXCEEDING 5% POWER.
ACTION: ,
, APPROVED.BY-GSU MANAGEMENT.
E&DCR#- ISSUE DATE / /
FDDRM ISSUE DATE / /
- _= _____-----------_________----_--_-------------____----------_-_-_-___---
~CRATICALITY RATING:-2
[ IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND, NUCLEAR PLANT DATE: 02/27/84 FiEE E) b4 C3 = 5155
~
REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - = - - - - - - - - _-----------------------------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. A2.9 .
CHECKLIST AREA: PANEL L AYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76
- - - - - - - - - - - = - - - - - - - - - - - - - - = - - = - - - -- -------------
. DESCRIPTION OF DISCREPANCY:
MIMICS ON THIS PANEL ARE NOT CLEARLY MARKED WITH ARROWS TO SHOW DI.RECTION OF FLOW.
- RECOMMENDATION' S:
CLEARLY MARK MIMICS WITH REGARD TO DIRECTION OF FLOW
<<< THE MIMIC TO BE USED HAS ARROWS INCORPORATED INTO IT . SOME ARROWS HAVE
-BEEN ADDED SINCE THE SURVEY. THE ADDITION OF ARROWS DURING INITIAL STARTUP OPERATIONS WILL NOT CAUSE OPERATOR CONFUSION >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
Et<DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
-CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I '
HUMAN ENGINEERING DISCREPANCY RECORD
- RIVER BEND NUCLEAR PLANT DATE: 02/27/84 FiEEI) P4 03 . = 1 <> d4 REVIEWER: BARKS / CHASE /SHANKLE 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:
JUSE HIERARCHICAL LABELING OR DEMARCATION TO MAKE THE RELATIONSHIP APPARENT
<<< HEIRARCHICAL LABELING WILL BE ADDED ON A GENERIC BASIS THROUGHOUT-THE
-CONTROL. ROOM PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
0 _ _ _ _ _ _ _ _ _ _ _ _ _ . . . - _ _ - - - ____ _ - _ _ _ _ _ _ - _ _ - _ _ - - _ _ - _ _ _ - - _________
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER t
g, "
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
.DATE: 02/27/84 F4 EE I) b4 C3 . = 251 7 L REVIEWER :SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
________ =-_==_________________________==- =____________________
____=
, DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A3.2 .
CHECKLIST- REA: 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 ORDERING'OF THE A AND B INDICATORS IS REVERSED FOR THE CHARCOAL BED OUT TEMPERATURE' DISPLAY.
RECOMMENDATIONS:
. CHANGE ~"TO RADWASTE' TO 'FROM RADWASTE' LABEL ON MIMIC. CHANGE 'HRHX' LABEL TO *1HVR-UC1B-CONT. UNIT COOLER. REARRANGE SWITCHES L/R A/B.
'<<< LABELS AND SWITCH ARRANGEMENTS WILL BE COMPLETED PRIOR TO EXCEEDING 5%
POWER.>>>
ACTION:
APPROVED BY GSU MANAGEMENT. .
E&DCRM C60,5S9 ISSUE DATE / /
FDDR# LD1-2625 RO' ISSUE DATE 12/11/84 LCRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER I
- m .
HUMAN- ENGINEERING DISCREPANCY RECORD ~
RIVER BEND NUCLEAR PLANT DATE: 02/24/84' HED NO = 224
' REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR. OWNERS GROUP CHECKLIST NO.: A3.4 CHECKLIST AREA: PANEL' LAYOUT AND DESIGN
~ PANEL / WORKSTATION NO. P808-84C
-=------------------------------------------=- -___--------------------
. DESCRIPTION OF DISCREPANCY:
. DEMARCATION WOULD ENHANCE THE COMPONENT GROUPING FOR THE SEQUENCE" PROGRAMMER. '
' CONTROL RECOMMENDATIONS:
ADD' DEMARCATION ~TO ENHANCE COMPONENT GROUPING.
<<< THE ADDITION OF THESE LINES DURING INITIAL STARTUP OPERATIONS WILL NOT
.CAUSE OPERATOR-GONFUSION.' LINES WILL BE ADDED PRIOR TO EXCEEDING 5% POWER.
ACTION:
APPROVED BY GSU MANAGEMENT.
.E&DCRh 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: 02/23/84 FiEEI) P4 C3 . = 55 C) 97 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- _ _ _ _ _ ---------- -_ .=------ - __ . -----------
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.2 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN
~
PANEL / WORKSTATION NO. GENERIC
-( 1.)
DESCRIPTION OF DISCREPANCY:
SELECTED USE OF COLORS IS NOT CONSISTENTLY APPLIED FOR ALARM PRIORITIZATION (ALARM COLORS LACK RECOGNIZABLE STANDARD).
RECOMMENDATIONS:
- A COLOR PRIORITIZATION CONVENTION WILL BE DEVELOPED AND CONSISTENTLY APPLIED
- TO THE RBS CONTROL ROOM PANELS.
'<<<THIS GENERIC CHANGE WILL BE COMPLETED'THROUGHOUT THE CONTROL' ROOM PRIOR TO
- EXCEEDING 5% POWER.>>>
- ACTION: '
APPROVED EY GSU' MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
s
- 2-_------- ------------..------------------ ---------- -- -----------------
CRITICALITY. RATING: 2
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
7: -
HUMAN ENGINEERING DISCREPANCY -RECORD RIVER BEND NUCt. EAR P L_ A N T DATE: 02/29/84 F4 EE E) b4C3 = 11 REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE
= - - - - = - - - - -
.:--------- - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ -
DATA SOURCE: BWR OWNERS GROUP.
CHECKLIST NO.: A4.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. IRSS-PNL101
(.1.) 1SWP*P2A SERVICE WATER PUMP 2A ,
_ - = - _ _ _ - --=- --------_---------
DESCRIPTION OF DISCREPANCY:
THE START /STOP-SWITCH LABELS FOR THE SWP'S ARE' RED AND BLACK RECOMMENDATIONS:
CHANGE LABELS TO HAVE BLACK BACKGROUND-
<<< THE LABELS ON THIS PANEL WILL BE CHANGED TO BE CONSISTENT WITH.THE MAIN CONTROL ROOM PRIOR TO EXCEEDING 5% POWER. THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE-OF THE CONTROL ROOM. REMOTE SHUTDOWN PANEL IS NOT A TECH.
SPEC. -ITEM REQUIRED FOR FUEL LOAD..THE OPERATORS WILL NOT BE SUBJECTED TO CHANGES'IN ENHANCEMENTS ~
DURING INITIAL STARTUP OPERATIONS BECAUSE THIS PANEL WILL NOT BE IN USE >>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
' CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
. HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR- PLANT DATE: ..02/20/84 HED~ NO- = 297 REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
--- ----__--_-__ -= ____ ----=== _----____ ----
DATA SOURCE: BWR OWNERS-GROUP CHECKLIST NO.: A4.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN-PANEL / WORKSTATION NO. P601-16
_ _ ==_====---------------- ___
, . DESCRIPTION.0F DISCREPANCY:
SUPP. POOL MIMIC AND MIMIC'THROUGH CST'IS OF THE WRONG COLOR RECOMMENDATIONS:
CHANGE; MIMICS TO CONFORM TO CONTROL ROOM CONVENTIONS
<<< MIMIC IS BEING VERIFIED AND CHANGES WILL BE INCORPORATED >>>
ACTION:
- APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE ,/ /
FDDRM ISSUE DATE / /-
- CRITICALITYfRATING
- 2
'1MPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L
HUMAN ENGINEERING -DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 HED NO- = 574
- REVIEWER: BARKS / CHASE TRACKING STATUS: SCHEDULE PHASE
________ __== -= ____________ - _____________________________=
DATA SOURCE:'BWR OWNERS GROUP
-CHECKLIST NO.: A4.3 CHECKLIST AREAS PANEL' LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-85C-1
( 1.)
______________- _=_____- _______
DESCRIPTION OF DISCREPANCY:
YELLOW INDICATOR LIGHTS UNDER 4160V BUS CW AREA SHOULD BE WHITE AND SHOW FUNCTION ~
RECOMMENDATIONS:
' EVALUATE FUNCTION OF LIGHTS & CHANGE COLOR IF VARIES FROM STANDARD CONVENTIONS. EVALUATE LABELING & CHANGE IF APPROPRIATE.
<<< LABELING HAS BEEN EVALUATED AND IS APPROPRIATE. THE INDICATOR LIGHTS HAVE BEEN CHANGED TO WHITE. NO FURTHER ACTION REQUIRED >>>
L.
-ACTION:
APPROVED BY.GSU MANAGEMENT. ,
E'tDCR# C60.594- ISSUE DATE / /
-FDDRM ISSUE DATE / /
9
' CRIT ICALITY RATING: 2 ,
IMPLEMENTATION SCHEDULE:
HUMAN- ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT I
DATE: 02/27/84 F4 EE I) P4 C3 _ = 77 97 l
REVIEWER:fBARKS/ CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
_=__ ___ _--_ __ _ = _ _ - __________------_--_____________
DATA SOURCE: BWR, OWNERS GROUP CHECKLIST-NO.: A4.3 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:
SERVICE WATER AND CHILLED WATER USES THE SAME, COLOR MIMIC RECOMMENDATIONS:
' CHANGE SERVICE WATER MIMIC TO DARK BLUE.
.<<< A. COLOR CONVENTION HAS BEEN ESTABLISHED FOR MIMIC AND SERVICE WATER WILL BELCHANGED TO-BE CONSISTENT WITH THIS PRIOR TO EXCEEDING 5% POWER >>>
' ACTION:
APPROVED BYEGSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
l
_= ________ ______- _ ______ -_= __---__-_______________ ____-__
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L_ E A R P L_ A N T DATE: 02/27/84 HED NO :: 32O REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
- - _ _ -=_____________________ --_______________________________
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A4.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76 DESCRIPTION OF DISCREP4NCY:
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 SYSTEMS
<<< A COLOR CODE CONVENTION HAS BEEN ESTABLISHED FOR RBS MIMIC AND WILL BE APPLIED TO THESE MIMICS PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
SERVICE WATER TO BE DARK ELUE. CHILLED WATER TO BE LIGHT BLUE.
E&DCR4 ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
j
7 DISCREPANCY RECORD HUMAN ENGINEERING BEND NUCL EAR PL. AN T RIVER F4 EEI) P4 C3 . = E3 C2 42
-DATE: 09/19/84 TRACKING STATUS: SCHEDULE PHASE REVIEWER: LINK
- =. -=----- ----- _=- ---------- -------------- --.
=_:
DATA SOURCE: OPERATING PERSONNEL INTERVIEW
~ CHECKLIST NO.: A5
- CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P601-19
- - - - - =
~
DESCRIPTION OF DISCREPANCY:
LABELS ON ADS MANUAL INITIATION (P601 SECTION 19) READ EIT LOGIC" OR " INSTANTANEOUS LOGIC" RECOMMENDATIONS: IF APPROPRIATE.
EVALUATE FUNCTION OF SWITCHES AND CHANGE LABELING ACTION: UAL
-EVALUATION HAS DETERMINED THAT LABELS WILL BE CHANGED TO
_ INITIATION".
ISSUE DATE / /
ELDCR# C52,629 /
ISSUE DATE /
FDDRE LD1-2455 RO r --------------- -__
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR'TO FUEL LOAD l..
HUMAN -ENG'I NEER I NG DISCREPANCY RECORD RIVER BEND NUCt_ EAR PtANT DATE:: 02/29/84 ~ FIEEI) b4 C3 - = 1 55 MEVIEWER:' BARKS / BISHOP ' TRACKING STATUS: SCHEDULE PHASE
_ __ = = - - . _ =_. __
_ __ - _ - = = = --------------------------------------
DATA SOURCE: BWR OWNERS GROUP ,
CHECKLIST:NO.: A5.11 CHECKLIST' AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-POO1
( 1.)
-_ .- ==-- _--------------- _ ----- u DESCRIPTION OF DISCREPANCY:
LABELS ABOVE THE EMERGENCY TRANSFER SWITCHES ARE DUPLICATES-
- RECOMMENDATIONS:
. DELETE ONE SET OF LABELS
- THISLIS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE THE~ MAIN CONTROL ROOM. THE REMOTE SHUTDOWN PANEL IS NOT A TECH SPEC ITEM REOUIRED FOR FUEL LOAD. THE OPERATORS WILL NOT BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING INITIAL REACTOR STARTUP OPERATIONS BECAUSE THE PANEL WILL NOT BE IN USE >>>
ACTION: .
~APPROVCD BY GSU MANAGEMENT E&DCR# ISSUE.DATE / /
FDDR# ISSUE DATE / /
J CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
.Q HUMAN . ENGINEERING DISCREPANCY ' RECORD RIVER BEND. N U CR-.E A R PR-.A N T ,
DATE: 02/24/84 HED NO :: 227 REVIEWER: LIDDLE /MATSON/ BISHOP. TRACKING STATUS: SCHEDULE PHASE
= = _ _ - - _ - - - - - - =-- - = = - - - =_ - ---__--___________
- - - - - -- - =- ,
t
. DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO. -A5.11 .
CHECKLIST AREA:-PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-81C '
( 1.) l
_ -_ . ---- = = - - - - - -------
=_=
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 CONTROLS.
<<< LABELS ARE BEING PROPERLY LOCATED SO THEY WILL NOT BE OBSCURED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
t E&DCR#- ISSUE DATE / /
FDDRM ISSJE DATE / /
- - - - - - - - - - - -------------------------------- =---------------------------
, CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 4
g-HUMAN .ENG I NEER I NG - DISCREPANCY RECORD RIVER BEND NU C L_E A R Pt_.A N T DATE: 02/27/84 F4 EEI) b4 C3 - = E3 db 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 & ENCLOSE SYSTEM WITH LINES OF DEMARCATION
<<< LINES OF DEMARCATION AND HEIRARCHICAL LABELING WILL BE ADDED PRIOR TO EXCEEDING 5% POWER.
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCRG ISSUE DATE / /
FDDR# ISSUE DATE / /
= ---------- - ___
.----__-- = = - - - - - _ - _ _ - - - . _ _ - _ - - - - - - - - - _ - - - - - - - - - - - = = = =
i CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: FRIOR TO EXCEEDING 5% POWER E- .
p
' H U M'A N ENGINEERING DISCREPANCY RECORD
- R I VER : BEND NUCLEAR PLANT
-DATE: '02/21/84- HED NO- = 2 ~7 0
- 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. P870-56
= ==------------------- _ ----- -- ----------------- __=___-----
cDESCRIPTION OF DISCREPANCY:
STANDBY SERVICE WTR MULTIPEN RECORDER 3 OBSCURE THE LABELS
. RECOMMENDATIONS:
MOVE LABELS ABOVE RECORDERS . .
.<<< PERMANENT LABELS HAVE DEEN ORDERED AND WILL BE INSTALLED PRIOR TO EXCEEDING 5% POWER. TEMPORARY LABELS WILL BE ADDED PRIOR TO FUEL LOAD AS AN INTERIM-CORRECTIVE ACTION.
ACTION:
TAPPROVED DY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
- - - . . - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - = = ---------
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER c
LJ .:
P HUMAN ENGINEERING DISCREPANCY RECORD (RIVER BEND NUCLEAR PLANT DATE: 02/21/84 F4 EE I) P4 03 . = d2 d2 55 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-1 PANEL / WORKSTATION NO. P680-7C PANEL / WORKSTATION NO. P680-8C PANEL / WORKSTATION NO. P680-9C PANEL / WORKSTATION NO. P680-15C DESCRIPTION OF DISCREPANCY:
LABELS, LEGEND PLATES AND ESCUTCHEONS ARE NOT USED TO IDENTIFY SYSTEM DESIGNATION RECOMMENDATIONS:
IDENTIFY SYSTEM DESIGNATION WITH HIERARCHICAL LABELS
<<< HEIRARCHICAL LABELING WILL BE ADDED >>>
ACTION: ,
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: FRIOR TO FUEL LOAD l
p-HUMAN ENGINEERING. DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/23/84 F4 EEI) P4 C3 - = ZL 2 5 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
' DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: oA5.3 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P680-4 PANEL / WORKSTATION NO. P680-5 [
PANEL / WORKSTATION NO. P600-6 1 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.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION' SCHEDULE: PRIOR TO FUEL LOAD l
. HUMAN -ENGINEERING DISCREPANCY RECORD RIVER BEND' NUCLEAR PLANT DATE:-02/27/84 F4 EEI) b4 C3 - = 4& ds REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE
-DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.4 CHEC'KLIST~ 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, BUT LABELING IS ON THE BACK OF THE PANELS. LABEL FRONT OF PANEL IF APPROPRIATE
~<<< LABELS HAVE BEEN ORDERED AND WILL BE ADDED TO THE FRONT OF THE PANELS
-PRIOR TO EXCEEDING'5% POWER. THE ADDITION OF THESE LABELS DURING INITIAL STARTUP OPERATIONS-WILL NOT CAUSE OPERATOR CONFUSION->>>
ACTION:
. APPROVED BY GSU MANAGEMENT ,
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
\_
fN -
/
l
/
! HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCL E AR Pt__A N T DATE: 02/23/84 F4 EE E) b4 03 . = ZF 77 2F 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
<<< LABELING IS B.EING CORRECTED TO BE CONSISTENT WITH ALL LABELING IN THE CONTROL ROOM >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCR# ISSUE DATE / /
FDDR4 ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOP TO FUEL LOAD
[-
fs 1 l
/
/ HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT l
DATE: 02/29/G4 IH EE D b4 C3 = i d4 l l
REVIEWER: BARKS / BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: AS.7 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. C61-P001
( 1.) l 1
DESCRIPTION OF DISCREPANCY:
USE OF HIERARCHICAL LABELING FOR THE RHR & RCIC COMPONENTS WOULD BE HELPFUL RECOMMENDATIONS:
USE HIERARCHICAL LABELING WHERE POSSIBLE
<<<THIS IS THE REMOTE SHUTDOWN PANEL WHICH IS OUTSIDE THE CONTROL ROOM. THE REMOTE SHUTDOWN PANEL IS NOT A TECH. SPEC. ITEM FOR LOADING FUEL.THE OPERATORS WILL NOT BE SUBJECTED TO CHANGES IN ENHANCEMENTS DURING INITIAL STARTUP OPERATIONS BECAUSE THIS PANEL WILL NOT DE IN USE >>>
ACTION:
- APPROVED BY GSU MANAGEMENT ELDCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 l IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
1
/
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT DATE: 02/27/84 IH EE I) b4 C3 . = E3 05 REVIEWER: BARKS / CHASE /SHANKLE TRACKING STATUS: SCHEDULE PHASE W
DATA SOURCE: BWR OWNERS GROUP .
CHECKLIST NO.: A5.7 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
<<< THIS GENERIC CHANGE WILL BE COMPLETED THROUGHOUT THE CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRd ISSUE DATE / /
3 FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1
p _
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U Ct_.E A R PL ANT DATE: 02/24/84 HED NO- :: 21O REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: A5.8 ,
CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808 (PANEL GENERIC)
( 1.)
DESCRIPTION OF DISCREPANCY:
ENGRAVED METALLIC LABELS LACK DISTINCTION AND CONTRAST RECOMMENDATIONS:
CHANGE ANY ENGRAVED LABELS THAT LACK DISTINCTION nND CONTRAST.
<<< PERMANENT LABELS HAVE BEEN ORDERED FOR THIS PANEL AND WILL DE INSTALLED PRIOR TO EXCEEDING 5% POWER. TEMPORARY LABELS WILL BE INSTALLED PRIOR TO FUEL LOAD AS AN INTERIM CORRECTIVE ACTION FOR LABELS LACKING DISTINCTION AND CONTRAST >>>
ACTION:
- APPROVED BY GSU MANAGEMENT.
E&DCPM SEE HED#82 ISSUE DATE / /
FDDR4 ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER b
f HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR P L_ A N T DATE: 02/24/04 F4 EE I) D4 C3 - = 22:2 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. P808-83D
( 1.)
DESCRIPTION OF DISCREPANCY:
LABELS UNDER CHART RECORDERS ARE OBSCURED RECOMMENDATIONS:
PUT LABELS ON CHART RECORDER OR ABOVE
<<< PERMANENT LABELS HAVE BEEN ORDERED AND WILL BE INSTALLED PRIOR TO EXCEEDING 5% POWER. TEMPORARY LABELS WILL BE ADDED PRIOR TO FUEL LOAD AS AN INTERIM CORRECTIVE ACTION >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
Et<DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
CRITICALITY RATING: 2 l IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
1
HUMAN ENGINEERING DISCREPANCY RECORD RIVER ' BEND NUCL EAR PL ANT DATE: 09/19/84 Fi EE I) P4 03 . = 77 97 2 REVIEWER: LINK TRACKING STATUS: SCHEDULE PHASE
=_ -------------------------------------------------------------- .
DATA SOURCES. OPERATING PERSONNEL INTERVIEW CHECKLIST NO.: 83 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P808
- DESCRIPTION OF DISCREPANCY:
MULTI-PEN RECORDERS ON P808 NEED ALL SCALES INDICATED AND THOSE WHICH ARE SPARES (I.E. DRYWELL PRESS, SUPPRESSION POOL TEMPERATURE) -
-RECOMMENDATIONS:
LABEL ALL SCALES TO INDICATE FUNCTION.
<<< PERMANENT LABELS HAVE BEEN ORDERED AND WILL BE INSTALLED PRIOR TO EXCEEDING 5% POWER. TEMPORARY LADELS WILL BE INSTALLED PRIOR TO FUEL LOAD ~AS AN INTERIM CORRECTIVE ACTION >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / /
FDDR# ISSUE DATE -/ /
CRITICALITY RATING: 2 XMPLEMENTATION SCHEDULE: PRIOR T O EXCEEDING 5% POWER
DISCREPANCY RECORD HUMAN ENGINEERING BEND NUCt. EAR Pt_.A N T RIVER HED NO = 303
- DATE: 02/20/84 TRACKING STATUS: SCHEDULE PHASE
' REVIEWER:. LIDDLE /MATSON/ BISHOP DATA SOURCE:'BWR OWNERS GROUP.
CHECKLIST'NO.: 83.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P601-16
-DESCRIPTION OF DISCREPANCY:
DIESEL ENGINE STOPS ARE NOT CLEARLY MARKED RECOMMENDATIONS:
ENHANCE STOP BUTTONS
<<< LABELING IS BEING CHANGED >>>
ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 fMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD 1'
f ;;-
')
f i-HUMAN . ENGINEERING DISCREPANCY RECORD l
! RIVER BEND NUCLEAR PLANT DATE: 02/24/84 HED NO = '7 6 9
- TRACKING STATUS: SCHEDULE PHASE
' REVIEWER: BURGY/ CHASE ,
t.
. _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - = = - - . -----------
DATA SOURCE: BWR OWNERS GRbuP CHECKLIST-NO.: B5.1 t
l' -_ CHF.CKLIST, AREA: INSTRUMENTATION AND HARDWARE
) .,
PANEL / WORKSTATION NO. P680-4D
- - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - _ - - - - - -- - - - - - = - - - -
DESCRIPTION OF DISCREPANCY:?
l _fRESET B0TTON LIGHTS,- N@hD LABEL'TO INDICATE FUNCTION.
,- 4 I ? RECOMMENDATIONS:
[ ADD LABEL TO' INDICATE FUNCTION N<< LABEL ~IS BEING ADDED TO REFLECT CORRECT FUNCTION >>>
~$
, e 5.
i 'a
ACTION: v '
APPROVED BY GSU MANAGEMENT.
- ' L .~
r 7 y; ,
~
%< l ,
- w. ,
E&DCR#' -- - ISSUE DATE *
/ /
FDDR# ' ISSUE DATE / /
/-
-* I -
_ - -- _f _- -----./' ----------------------------------------------------
CRITICALITY RATING:42 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD e
w'y V % -
lsy" e ,
.y
- $e W'
'fgr.
p .
f- ,
HUMAN ~ ENGINEERING. DISCREPANCY RECORD RIVER' BEND NUCLEAR PLANT
'DATE: 02/20/84 HED NO :: 302
. REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
~ DATA SOURCES.BWR. OWNERS GROUP k
CHECKLIST NO.: _B5.2 CHECKLIST AREA: -INSTRUMENTATION AND-HARDWARE PANEL / WORKSTATION NO.JP877-31 PANEL / WORKSTATION NO.-P877-32 PANEL / WORKSTATION NO..P601-16
=- = =-----------------------------------------------------------
DESCRIPTION OF DISCREPANCY:
E STANDBY GENERATOR AND DISTRIBUTION INOPERABILITY INDICATION SWITCH DOES NOT L HAVE THE BYPASS POSITION LISTED
)~
h RECOMMENDATIONS:
~ CHANGE LABEL.
I $4<<=ALL INOP. INDICATION TAGS ARE BEING CHANGED TO BE CONSISTENT >>>
\
I ACTION:
I APPROVED BY'GSU MANAGEMENT
-E3<DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
> ------------------------------------------- = ===------------------------- -
-CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
HUMAN ENGINEERING DISCREPANCY RECORD RIVER ' BEND NUCLEAR PLANT DATE: 02/23/84 F4 EE I) b4 C3 - = ZF et C)
REV'IEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
- - - ---- =_ - = - =_ __ -____----_-___
- = = _ _ _ = -
DATA SOURCE: BWR OWNERS GROUP
. CHECKLIST NO.: B6.1 CHECKLIST AREA: INSTRUMENTATION AND HARDWARE PANEL / WORKSTATION NO. P680-4C-( 1.) P
=- ----------------_ - - - - - - - =---------- _-_ =_
DESCRIPTIONEOF DISCREPANCY:
SWITCHES FOR EMERGENCY ARE NOT CLEARLY MARKED. (INSERT 4C TRIP' BUTTON DB33-SOO1 A&B:SHOULD BE RED.) (INSERT 4C-RECIRC. PUMP.STOP BUTTONS B33-COOL
-A&B SHOULD BE RED.)
RECOMMENDATIONS:
CLEi.?LY DEMARCATE EMERGENCY SWITCHES
<<< BUTTONS ARE BEING ORDERED AND WILL BE INSTALLED PRIOR TO EXCEEDING 5%
POWER >>>'
ACTION:
APPROVED BY GSU MANAGEMENT. ,
E&DCRM ISSUE DATE / /
FDDR# ISSUE DATE / /
=-------------------- ------------------------------------------
CRITICALITY RATING: 2
_ IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER kl _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . .
HUMAN ENGINEERING DISCREPANCY RECORD I_:
!- NUC L_E AR PL. ANT RIVER. BEND DATE: 02/20/84 HED NO = 304 L -REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
________________ - - _ _ _ _ _ - __- _________________________________________ l DATA SOURCE: BWR OWNERS GROUP-i I 'CHECKL'IST NO.: C1.3 ,
, CHECKLIST AREA: ANNUNCIATORS l -.
PANEL / WORKSTATION NO. P877-31 PANEL / WORKSTATION NO. P877-32
. PANEL / WORKSTATION NO. P601-16
____ ____________________________- .__ __=---
--=_ - __L= _ __ _ _ _ _
' DESCRIPTION OF DISCREPANCY:
ANNUNCIATORS ARE NOT-GROUPED SUCH THAT~ WARNING AND DIAGNOSTIC ALARMS ARE SEGREGATED RECOMMENDATIONS:
. ALARMS-WILL BE C0 LOR CODED FOR PRIORITIZATION. GROUPING IS ADEQUATE.
<<<-COLOR CODING OF ANNUNCIATORS WILL BE COMPLETED ON A GENERIC BASIS THROUGHOUT THE CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
l ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDR# ISSUE DATE- / /
t-CRITICALITY RATING: 2 JIMPL'EMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER l
E
h HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U CE_.E A R P L_ ANT DATE: 02/23/84 FiEEI) b4 03 = ZF eL 24 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
==____ - - _ _ _ _ _ _ _ _ - - - - . __- -------_=-_-_-
-DATA LSOURCE: BWR OWNERS GROUP.
-CHECKLIST NO.: C2.1 CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. P680-4
- PANEL / WORKSTATION NO.-P680-5 PANEL / WORKSTATION NO. P680-6
__ = = = - - _ _ _ _ - _ _ _ _ _ _ _ _ _ . _________ ___________ =
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 RC1RC.)
RECOMMENDATIONS:
COMPARE TO STANDARD ABBREVIATIONS LIST AND CHANGE AS APPROPRIATE.
ACTION:
l
- APPROVED BY.GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L.
fl l HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCt_ EAR P L_ A N T
'DATE: 02/27/84 HED NO- = 98 REVIEWER: BARKS / CHASE /SHANKLE - TRACKING STATUS: SCHEDULE PHASE'
._- -. ---------__=- == = - - - _- ------_- ==_ =_ -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C2.1 CHECKLIST AREA: ANNUNCIATORS i
PANEL / WORKSTATION NO. P863-72A
( 1.) ANN #0579
( 2.) ANN #1179 PANEL / WORKSTATION NO. P863-71A
( 1.) ANN #1179
- - - _ _ __-_-___ =_--__---- - _ _ _ - - - _ - - - _ - - _ - - - - - - - - - - _ - - - - - - _ - - - - - - - - - _ - - - -
DESCRIPTION OF DISCREPANCY:
-THE ~ABBREVI ATIONS "U" AND "IFTS" ARE AMBIGUOUS
' RECOMMENDATIONS:
. VERIFY CONFORMANCE WITH DESIGN CONVENTIONS AND. CHANGE AS REQUIRED.
<<< ABBREVIATIONS WILL BE REVIEWED ON A PANEL GENERIC BASIS. THIS PANEL WILL DE COMPLETED PRIOR TO EXCEEDING 5% POWER >>>
ACTION: ,
APPROVED ~BY GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDDR# ISSUE.DATE / /
__-----__--_-----=- _-_-__--_______---__-----_____--__-__---_--- _--_---_-_-
CRITICALITY RATING: 2
' IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER i
u.. _ _ _
- HUMAN-ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT-
.DATE:f02/27/84 HED NO = ~3 2 8 REVIEWER: _SCHROEDER/MATSON/ BISHOP ' TRACKING STATUS: SCHEDULE PHASE
_________-. ________-___ ====--- ---_ - _ _ - - ._==________________
DATA SOURCE: BWR OWNERS GROUP CHECKLIST NO.: C2.2 .
CHECKLIST AREA: ANNUNCIATORS PANEL / WORKSTATION NO. PG63-76
_____ =----____ --. --_____--_____ ________ --===_ _
DESCRIPTION OF DISCREPANCY:
LEGENDS ON ALARM WINDOWS ARE NOT CONSISTENT IN TYPE STYLE AND THE APPLICATION
. 0F TYPE SIZE.
RECOMMENDATIONS:
MAKE ALARM WINDOWS CONSISTENT IN TYPE STYLE AND SIZE
<<< TYPE STYLE IS BEING HANDLED ON A PANEL GENERIC BASI!;. THIS PANEL WILL BE COMPLETED PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
~ TEMPORARY LEGENDS WILL BE REPLACED TO BE CONSISTENT.
E&DCR# SEE HED#397 ISSUE DATE / /
FDDR# ISSUE DATE / /
-__________________--- - ____________- =___________---_____________
CRITICALITY ~ RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 2
L'
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND . NUCLEAR PLANT
- DATE: 02/22/84 HED NO = 289
- REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING. STATUS: SCHEDULE PHASE.
. _ - - - - - - - = _ - - - - - - - - - - - - - - - - - - = - - - - _.--
- ----------- - = . _ _ = - - - - - - - - - - - - - -
DATA SOURCE: .BWR OWNERS GROUP CHECKLIST NO.: C2.5 CHECKLIST AREA:-ANNUNCIATORS PANEL / WORKSTATION NO. P601-19
= ------=___ - - - - - _ _ _ _
DESCRIPTION OF DISCREPANCY:
ANNUNCIATOR FOR STANDBY LIQUID TANK / TEMP HI/ LOW IS NOT SUCCINCTLY' WORDED RECOMMENDATIONS:
REMOVE "/" BETWEEN TANK AND TEMP ON ANNUNCIATOR
-ACTION:
, - APPROVED BY GSU MANAGEMENT.
-E8<DCR# C52,616 ISSUE DATE
~
/ /
FDDR# LD1-2424 RO ISSUE DATE 1Q/25/84
_-_=-----------------------------------------------------------------_---
CRITICALITY RATING: 2 j IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD L_.
8
-HUMAN ENGINEERING' DISCREPANCY RECORD RIVER BEND' NUCL_E AR PL ANT DATE: 02/27/84 HED NO- = 329-REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
-- - _ = - =_ . _ - - - - - - - - - = - - - __-------. --
'ATA SOURCE:'BWR' OWNERS GROUP D
CHECKLIST NO.: C2.5
-CHECKLIST AREA: ANNUNCIATORS .
p PANEL / WORKSTATION NO. P863-76
- - - - - - - - - - - - _ _ = = = _ _ __ _
- DESCRIPTION 0F DISCREPANCY:
NO LABELS ARE PROVIDED ON THE INOPERABILITY MATRIX. ALSO, WINDOW LABEL FOR "STBY SERV. ICE NTR PUMP HOUSE X-H TEMP SWGR RM A" IS UNCLEAR.
. RECOMMENDATIONS:
-LABEL HAS BEEN.ADDED SINCE SURVEY. CHANGE WINDOW TO BE CONSISTENT WITH STANDARD CONVENTIONS ~(X-H TO EXT HIGH).
<<<-THE ABBREVIATIONS FOR THESE INOPERABILITY INDICATION LIGHTS WILL BE COMPLETED FOR.THIS PANEL PRIOR TO EXCEEDING 5% POWER >>>
ACTION:
APPROVED BY GSU MANAGEMENT E84DCR# ISSUE DATE / /
FDDR# ISSUE DATE / /
.------------------=_ ------- -------------------------------------- . - -
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER
b f.
DISCREPANCY RECORD i HUMAN' ENGINEERING BEND NUCLEAR PLANT i RIVER
! F4 EE I) P4 03 . = 22 E3:2
-DATE: 02/22/84 TRACKING STATUS: SCHEDULE PHAGE-
. REVIEWER: LIDDLE /MATSON/ BISHOP
--==- _ - - -
- 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 CODE WITH CONTROL ROOM CONVENTIONS RECOMMENDATIONS:
. CODE ANNUNCIATOR A-11 RED z<<< COLOR CODING OF ANNUNCIATORS WILL BE COMPLETED ON A GENERIC THROUGHOUT THE. CONTROL ROOM PRIOR TO EXCEEDING 5% POWER >>>
. ACTION:
APPROVED BY GSU MANAGEMENT.
E&DCR#
ISSUE DATE / /
ISSUE DATE / /
FDDR#
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 5% POWER 1
l i
l l
l l
l
- a. >
f.:
L
' HUMAN ENGINEERING -DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT I
DATE: 02/24/84 HED NO- = 237 i
REVIEWER: LIDDLE /MATSON/ BISHOP- TRACKING STATUS: SCHEDULE PHASE
- - - - - - - - - . . __ - - - - - - . _ - . = - - - - - _---------------------=__ -
DATA SOURCE: BWR OWNERS GROUP
( CHECKLIST'NO.: A1.1-r .
' CHECKLIST AREA: PANEL LAYOUT AND DESIGN
. PANEL / WORKSTATION NO. P808-83 PANEL / WORKSTATION NO. P808-84 DESCRIPTION OF DISCREPANCY:
SEQUENCE PROGRAMMER MANUAL CONTROLS ON 83 HAS 2 WHITE LIGHTS THE SAME CONTROL ON 84 HAS A GREEN AND A RED LIGHT RECOMMENDATIONS:
CHANGE' LIGHTS ON CONTROL TO BE WHITE & BLUE
<<<C60,566.WAS ISSUED TO ADDRESS THIS HED BUT WAS CANCELLED. THE ABOVE LISTED LIGHTS AND CONTROLLERS HAVE DEEN DELETED PER CF-318(FDDR-1707 RO). NO FURTHER ACTION REQUIRED >>>
ACTION:
APPROVED BY GSU MANAGEMENT. . >
ELDCRM ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
'.6
F HUMAN ENGINEERING DISCREPANCY RECORD RIVER . BEND NUCLEAR PLAN'T
-DATE: 02/24/84 HED NO = 223
-REVIEWER: LIDDLE /MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE
. ----------- _ -------- = - - - - ----. -= --_ =-----------------
DATA SOURCES BWR OWNERS GROUP
' CHECKLIST NO.: 'A3.2 CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P808-83C
(~1.)
DESCRIPTION OF DISCREPANCY:
'CONTAINMENTz SAMPLE, DRYWELL SAMPLE, H2 MOISTURE ANALYZER CONTROLS ARE NOT IN ALPHABETICAL TOP TO BOTTOM. ORDER
. RECOMMENDATIONS:
REARRANGEMENT OF SWITCHES WILL NOT IMPROVE OPERABILITY. SIMULATOR TRAINING WILL FAMILIARIZE OPERATORS WITH CONTROLS.
<<<THE CONTROLS ARE ARRANGED TOP TO BOTTOM IN THE SAME ORDER THAT THEY ARE ARRANGED IN THE CONTAINMENT. THIS IS THE DESIRED ARRANGEMENT. THERE ARE TWO CONTROLS THAT ARE NOT ARRANGED LIKE THE PLANT AND THEY ARE BEING MOVED PER
~
E&DCR 60,893 >>>
ACTION:
. APPROVED BY.GSU MANAGEMENT.
E&DCRM ISSUE DATE / /
FDLRN ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE:
Eb J
y == -
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND NUCLEAR PLANT
- DATE: 02/27/84 F4 EE I) P4 03 . = C5 :L 97 REVIEWER: SCHROEDER/MATSON/ BISHOP TRACKING STATUS: SCHEDULE PHASE DATA SOURCE: BWR OWNERS GROUP
-CHECKLIST.NO.: A3.7 ,
- CHECKLIST AREA: PANEL LAYOUT AND DESIGN PANEL / WORKSTATION NO. P863-76 DESCRIPTION OF DISCREPANCY: -
THE <<< TURBINE BUILDING >>> CHILLED WATER CONTROLS SHOULD BE LOCATED CLOSER TO
'THEIR RELATED H&V CONTROLS AT P863-71C.
- RECOMMENDATIONS:
CHILLED WATER CONTROLS ARE APPROPRIATELY GROUPED. OPERATOR TRAINING WILL FAMILIARIZE ~THEM WITH LOCATION OF CONTROLS.
<<<DUE TO SPACE' CONSTRAINTS, THESE CONTROLS CAN NOT BE MOVED TO ANOTHER INSERT IN THIS PANEL. THEY ARE LOCATED ON A VERTICAL INSERT'WHICH IS CONSISTENT WITH.OTHER CHILLED WATER CONTROLS. THE MIMIC AND SYMBOLS WILL DE UPGRADED TO SHOW THE RELATIONSHIP WITH THE CONTAINMENT COOLERS PRIOR TO EXCEEDING 5% POWER
.THE DISTANCE BETWEEN THE CHILLED WATER CONTROLS AND TURDINE BLOG COOLERS IS 18 FEET.
ACTION:
APPROVED DY GSU MANAGEMENT.
E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATING: 2 IMPLEMENTATION SCHEDULE: PRIOR TO EXCEEDING 3% POWER I
o . - _ _ _ _ _ _ _ . . _ - - _ - _ _ _ _ _ _ _ _ - - _ _ _ .
-- t HUMAN ~ ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L._ E A R PL ANT DATE: 02/23/84 Fi EE E) P4 C3 = 44 T. 97 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE
_. -- _-- _ ___ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - =_ _ _ _ _ = - -
DATA SOURCE: BWR OWNERS GROUP CHECKLIST.NO.: B5.11 .
CHECKLIST AREA: INSTRUMENTATION.AND HARDWARE PANEL / WORKSTATION NO. P600-4 PANEL / WORKSTATION NO. P680-5 PANEL / WORKSTATION NO. P680-6 DESCRIPTION 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.)
' RECOMMENDATIONS'
<<< MARK >>> SWITCH COLLAR TO INDICATE FUNCTION.
<<<C52,617 WAS GENERATED TO CORRECT THIS HED BUT WAS CANCELLED. GSU SHALL HANDLE THIS CHANGE WITH AN RCF. IN ADDITION, THERE IS AN ANNUNCIATOR ASSOCIATED WITH THE SWITCH COLLAR POSITION (MANUAL SCRAM PUSHBUTTON ARMED >>>
ACTION:
APPROVED BY GSU MANAGEMENT E&DCR# ISSUE DATE / /
FDDRM ISSUE DATE / /
CRITICALITY RATINO: 2 IMPLEMENTATION SCHEDULE: PRIOR TO FUEL LOAD
/
7_ .:
i
)
i APPENDIX H L
DCRDR
SUMMARY
REPORT HEDs WITH IMPLEMENTATION SCHEDULE CHANGES H-1
r :-
HUMAN ENGINEERING DISCREPANCY RECORD RIVER BEND N U C L_E A R P L_ A NT fDATE: 03/22/84- HED NO := 381 REVIEWER: BURGY/ CHASE TRACKING STATUS: SCHEDULE PHASE L
= ==-------------------------------------------------------
. DATA SOURCE: BWR~ OWNERS GROUP CHECKLIST NO.
-PANEL / WORKSTATION NO. GENERIC.
' DESCRIPTION OF DISCREPANCY:
THERE IS NO CONTAINMENT ISOLATION MIMIC SHOWING THE STATUS OF THE PENETRATIONS 1
RECOMMENDATIONS:
ADD CONTAINMENT ISOLATION STATUS DISPLAY ON SPDS
- <<< PARAMETERS HAVE BEEN ESTABLISHED. GSU TECH STAFF IS DEVELOPING SOFTWARE: (
REFERENCE SCRB-6131 DATED 02/11/85 ). THE REQUIRED CONTAINMENT-ISOLATION STATUS INDICATIONS.ARE PRESENT IN THE CONTROL ROOM-ON THE DENCHBOARDS.-THE i - SPDS WILL ONLY . . ,
COMPLEMENT-THESE INDICATIONS. THE SPDS WILL BE FULLY FUNCTIONAL BY FEDRUARY 1986.>>>
. ACTION:
APPROVED BY GSU MANAGEMENT.
ELDCRM ISSUE DATE / / .
FDDR# ISSUE DATE / /
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- CRITICALITY RATING: 1 IMPLEMENTATION SCHEDULE:
L_ .. .