ML18151A145
| ML18151A145 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/15/1992 |
| From: | Aube D, Pinion M, Washington E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18150A453 | List: |
| References | |
| NUDOCS 9208060233 | |
| Download: ML18151A145 (562) | |
Text
{{#Wiki_filter:--------- Cp~~p~)!{OO~ DESIGN RE~W
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I. EXECUTIVE
SUMMARY
- Virginia Power completed a detailed Control Room Design Review (CRDR) of the Surry Power Station Units 1 and 2 control room in accordance with NUREG-0737 Supplement 1. The CRDR consisted of an extensive human factors engineering review and assessment performed in accordance with the guidelines of NUREG-0700 and a CRDR Program Plan submitted to the NRG in Letter No. 87 dated March 1, 1984.
The results of the CRDR were presented in a Final Summary Report, Volumes 1 & 2, submitted to the NRG in Letter Serial No. 86-171 dated March 31, 1986. The Final Summary Report documented the approach, assessment process, results and identified the Human Engineering Discrepancies (HED). In conjunction with the Final Summary Report the proposed corrective actions (CAs) and implementation schedule were submitted. The proposed corrective actions were the result of a complex selection process that considered tp.e inter-relationship 'with and between other Virginia Power programs, such as the installation of a Safety Parameter Display System, operator/simulator training, instrumentation upgrades per Regulatory Guide 1. 97 and Emergency Operating Procedures upgrades. corrective actions that were determined to be "Safety Significant" were reviewed for cost effectiveness and feasibility of installation on a conceptual design basis. The NRG submittal also stated that if it was determined that a proposed Those corrective action was not cost effective or feasible, then alternate corrective actions would be reviewed and assessed in accordance with the Nuclear Design Control Program. The proposed corrective actions were for the "Safety Significant" HEDs and no corrective actions were included for HEDs without "Safety Significance." Potential corrective actions without "Safety Significance" were to be reviewed as part of the normal Virginia Power program for plant improvements. The proposed corrective actions for HEDs with "Safety Significance" were separated into five implementation categories: Immediate "I", Short Term "ST", Long Term "LT", Normal Program "NP", and No Actions "NO". A total of 83 corrective actions were*identified. All corrective actions designated "I" (34) were completed (Ref. NRG letter 89- 743, dated December 14, 1989). Of the remaining corrective actions, 15 have been completed and are referenced on the Status Report in NRG letter 92-131A. Thirty-five (35) CAs are considered still VARP08.B7S 1
outstanding and remain to be completed. This reassessment addresses the 35 remaining corrective actions which are designated short term, long term, and normal program and are included in design change packages and Type I and II studies in various stages of completion. A number of the corrective actions were deferred during the 1989-1992 time frame to avoid excessive control room activity during the outages. Experience has shown that some of the originally proposed modifications are no longer applicable due to the implementation of subsequent station design modifications and coordination of control room _improvements with changes from other programs such as RG-1.97, ERF, Emergency Operating Procedures Upgrades, Human Performance Evaluation System, and Simulator Training. The 35 corrective actions were reassessed to determine if the CAs are still applicable and that the benefit of a number of the proposed modifications is commensurate with the cost and/or impact on plant operation. The CA reassessment consisted of a detailed evaluation of the remaining CAs and associated HEDs. I The review and reassessment was performed in accordance with the methodology outlined in Section II and was consistent with the original CRDR Program Plan. A description of the CAs and associated HEDs and the results of the detailed corrective action evaluations with conclusions/recommendations are provided in Section II. Based on the results of the corrective action evaluations, the reassessment dispositioned the 35 remaining CAs as follows: Justification provided, no modifications required* 23 Recommendation provided, modifications required 12 Total CAs 35 The corrective actions which do not require modification have been justified as follows: VARP08.B7S 2
- 1. Technical Justification The reassessment for these corrective actions has concluded that there is no safety significance, low potential for error and the consequences of error will not risk injury to the public/plant personnel or damage to equipment. Therefore, modifications are not required.
- 2. Cost Versus Benefit Justification The reassessment for these corrective actions has concluded that the originally proposed modifications and alternate modifications that were investigated, do not provide appreciable benefit to the improvement of plant safety, Operations or human engineering principles which are commensurate with the projected total cost of the modification.
The conclusions/recommendations section of each corrective action evaluation sheet provides details of the justification and/or modification .
- VARP08.B7S 3
II. CORRECTIVE ACTION EVALUATIONS The remaining corrective actions (CAs) that were identified at Surry during the NUREG-0700 Control Room Design Review (CRDR) to resolve human engineering
- discrepancies (HEDs) were reassessed to determine if the CAs are still applicable and that the benefit of a number of the proposed modifications is commensurate with the cost and/or impact on plant operation. Experience has shown that some of the originally proposed modifications are no longer applicable due to the implementation of subsequent station design modifications and coordination of control room improvements with changes from other programs such as RG-1. 97, Emergency Response Facilities (ERF), Emergency Operating Procedures Upgrades, Human Performance Evaluation System (HPES), and simulator training. Reassessment of the remaining corrective actions is being undertaken to address these concerns.
II.A Methodology The corrective action reassessment consists of a detailed evaluation of the remaining corrective actions and associated HEDs. The applicable NUREG-0700 sect.ions, identified in the HED, were reviewed to confirm that the discrepancy* correlated to the guidance document and was applicable to the proposed corrective action. A procedures and programs review was conducted to determine if the original corrective action and HED findings were enveloped, impacted, and/or addressed under other programs. This included a review of EOPs and EPIPs to determine if the equipment identified in the corrective action was required to be operated under EOPs and the review of recent LERs and station deviations to determine if the discrepancy was previously documented by the HPES. In addition, programmatic issues including RG-1.97, Appendix R, and Emergency Response Facilities (ERF/SPDS) were reviewed to identify if the corrective action was addressed and/or coordinated with control room improvements implemented under these programs. e VARP08.B7S 4
The corrective actions were then evaluated in relation to specific system/component function and task requirements to identify safety significance, ~ potential for error, and consequences of error. The criteria used to perform these assessments was consistent with the original CRDR task plan and is described below. II.A.l Safety Significance The criteria for assessment of safety significance relate to whether or not the affected component or components are part of a safety-related system. Important considerations include:
- Whether the component is qualified as R.G. 1.97 equipment
- Whether the component is qualified as lE equipment
- Whether the component is necessary for recovery from an accident II.A.2 Potential for Error Assessment Criteria The following criteria were considered in assigning the Error Potential rating:
- 1. The nature of discrepancy, including the following factors:
(a) The impact of the discrepancy upon the operator's ability to perceive and discriminate input information. Considerations include: Whether required information is provided. The effect of the discrepancy upon the operator's ability to locate, read, and interpret displays of interest. The effect of the discrepancy upon the operator's ability to see and hear. (b) The impact of the discrepancy upon the operator's ability to process information. Considerations include: The likelihood of exceeding the operator's information processing capability. The likelihood of causing confusion or distraction. VARP08.B7S 5
Operator fatigue or discomfort which may be caused by the discrepancy .
- (c)
Additional processing steps or processing errors which may be introduced by the discrepancy. The effect of the discrepancy upon the operator's ability to perform required actions. Considerations include: Whether required controls are provided. The effect of the discrepancy upon the operator's ability to locate the control. The effect of the discrepancy upon the operator's ability to use the control.
- 2. Conditions of stress which may exist when associated tasks are performed.
- 3. The past occurrence of errors as a result of the discrepancy.
- 4. The degree and prevalence of the deviation.
- 5. The familiarity of the components and systems involved.
- 6. The frequency with which the associated components and systems are used.
II.A.3 Consequence of Error Assessment Criteria The following criteria were considered in assigning the Consequence of Error rating:
- 1. The risk of injury to the public.
- 2. The risk of injury to plant personnel.
- 3. The potential effect of the error upon operating margins to safety limits.
- 4. The importance of the components and systems involved.
VARP08.B7S 6
- 5. The availability of alternative systems and components.
- e 6. The ability of automatic protective features to compensate for the error.
- 7. The ability of the operator to detect the error.
- 8. The ability of the operator to recover from the error.
- 9. The potential for the error causing additional errors.
- 10. The risk of equipment damage.
II.B Corrective Action Reassessment Summary Table A summary of all remaining corrective actions, associated HEDs, including descriptions, and conclusions/recommendations based on the reassessment are provided in Table II.B. II.C Corrective Action Detailed Review The detailed reassessment for each CA is provided in the following sections. e VARP08.B7S 7
III. REFERENCES
- 1.
2. NUREG-0700, "Guidelines for Control Room Design Reviews." NUREG-0737 Supplement 1 "Clarification of TMI Action Plan Requirements."
- 3. Virginia Power letter to NRG Serial No. 87 dated March 1, 1984.
- 4. Virginia Power letter to NRG Serial No. 86-171 dated March 31, 1992.
- 5. Virginia Power letter to NRG Serial No. 92-131 dated March 3, 1992.
- 6. Control Room Design Review Task Plan.
- 7. Control Room Design Review Final Summary Report for Surry Power Station Units 1 & 2.
- 8. RG-1.97 Technical Report No. PE-0014, Rev. 1.
e 9. RG-1.97 "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following An Accident."
- 10. Emergency Procedures, Surry Power Station, Units 1 & 2.
- 11. Emergency Contingency Actions, Surry Power Station, Units 1 & 2.
- 12. Function Restoration Procedures, Surry Power Station Units 1 & 2.
- 13. Emergency Plan Implementing Procedures (EPIP), Surry Power Station Units 1 & 2.
- 14. CRDR AIRS Actions, Surry Power Station Units 1 & 2.
- 15. NUREG-0696 Computer Input/Output List Surry Power Station Units 1 & 2.
- 16. Design Reference Procedures, Surry Power Station Units 1 & 2.
VARP08.B7S 8
- 17. Technical Specifications, Surry Power Station Units 1 & 2.
- 18. Updated Final Safety Analysis Report, Surry Power Station Units 1 & 2.
- 19. Nuclear Control Room Operator Development Program, Manuals NCRODP-22, 23, 24, 26, 29, 38, 40, 41, 46, 51, 52, 55, 61 & 68.
- 20. 10CFR50 Appendix R Report, Surry Power Station Units 1 & 2.
- 21. Q-List, Surry Power Station Units 1 & 2.
- 22. Virginia Power, Nuclear Design Control Program.
VARP08.B7S 9
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B CA2E Provide meter for total auxiliary 20002018 Displayed values require operator 0700, 6.S.1.2.b No modification required. feedwater flow. conversion 6.S.1.2.c DC-88-27/28 CA6E Demarcate and add colored background 20A0130S Lack of demarcation lines 0700, 6.6.6.2.a Modification required; relabel ASP per Virginia on Auxiliary Shutdown Panel same as DC-88-25/26 Power Labeling Standard. MCB. Tape is to be removed and replaced with orange and purple color dots on labels. Coordinate with CA24E. CA9E Provide pressurizer spray valve position 20A0204S Required displays and indications missing 0700, 6.1.1.1.a No modification required. indication w/ red/green lights. from Control Room 6.S.1.1.b,e 6.S.4.1.g 22A03206 Lack of Feedback indicating process/ 0700, 6.9.3.1.c.2 direction of parameter change DC-88-29/30 CAIOE Perform study of annunciator alarm 20A02106 Annunciator tile legends ambiguous/too 0700, 6.3.1 thru 6.3.4 Modification required; relabel/group specific alarms study. wordy. and install annunciator silence feature. 20002120 No distinctive coding for extended duration ilium. during norm op. 20002121 No reflash capability on annunciator system. 20002122 Ann. tile does not bum steadily when there is flasher failure. 20A02101 Annunciator tile engraving too small. V'ARPOS. B7S--O
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B
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CAIOE (Cont) 20A02102 Annunciator tile illuminations indicate 0700, 6.3.1 thru 6.3.4 Modification required; relabel/group specific alarms normal conditions. and install annunciator silence feature. 22A02906 Alarms for units sound alike. 20A02103 Annunciator placement not consistent between units.
,,, 20A02119 lli/l:lc: of grouping by system function.
20A02125 No auditory signal priority coding of annunciator alarms. 20A02903 No audible alarm cleared signal for annunciator system. 20A02302 System/Equipment status is inferred by indicator light being off. 20B03005 No*silence function on annunciator response controls. 22A02110 Number of tiles per annunciator light board. 22A02111 Dual meaning tile legends. 22A02112 Inadequate width-to-height ratio on annunciator characters. 22A02115 Letter spacing-inadequate spacing ;;n annunciator tile lines. VARPOS.B7S--0 2
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B CORRECTIVE CA' ASSOC. HED ACTION NO. DESCRIPTlON . HEDs . DESCRIPTION REFERENCES CONCLUSIONS/RECOMMENDATIONS CA!OE (Cont) 22A02116 Silence controls for annunciators. 22A02123 No printout for multi-input annunciator. CAllE Rescale auxiliary feedwater flow 20A02216 Scale range inappropriate, need range 0700, 6.5.1.2.d.1 Modification required; change meter scale to 0-400 indicators (linear, 0-500 gpm - expanded 6.5.1.2.d.2 gpm. increments of 10 gpm). 20A02230 Display output does not allow accurate 0700, 6.5.1.2.a reading 23002243 Unit value progression 0700, 6.5.1.5.c DC-88-27/28 CA12E Redesign Permissive Status Lights to 20A02303 Permissive status light indications are 0700, 6.5.3. l.c Modification required; re-engrave approximately 15 ensure consistency in terms of messages, inconsistent status lights per unit consistent with EOPs. illumination sequence, location and arrangement. 20A02315 System/equipment status is inferred by 0700, 6.5.3. l.c indicator light being off 22A02308 Legend message contains more than three 0700, 6.5.3.3.b.5 lines of text 6.6.4.2.d.3 20A01313 Incomplete standardization among panels 0700, 6.8.2.4.a of unit 1/2 OC-90-04/05 CA15E Rearrange EDG /f3 panels to be similar 20A03033 EOG panels 1 and 3 arranged differently 0700, 6.4.1.1.c.2 Modification required; change meter scales. to EOG #1 and EOG #2 and label from 1 and 2 6.4.2.2.c. l accordingly 6.4.2.2.c.3 DC-88-25/26 V ARP05.B7S-O 3
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE II.B CORRECTIVE CA ASSOC: HED ACTION NO. DESCRIPTION HEDs D!:JSCRIPTION REFERENCES CONCLUSIONS/RECOMMENDATIONS CA17E Change flow indication for CVCS 20A03405 No feedback that pushbutton controls 0700, 6.4.3.1.b Modification required; evaluate instrument setpoint charging and letdown (0-300 gpm) (FT- have been activated inaccuracies and change meter scales to 0-200 gpm. 1122/2122) 20A02214 Scale ranges inappropriate, need narrow 0700, 6.5.1.2.d. l,2 ranges expanded 20A02208 Scale ranges too narrow, wide range 0700, 6.5.1.2.d.3 indication not provided DC-88-27/28 CA18E Change existing annunciator for Safety 20A03406 No feedback that pushbutton controls 0700, 6.4.3.1.b Modification required; add SI initiation and SI Injection actuation to Train "A" actuation have been activated DC-90-04/05 block annunciation for each train. only. Add new annunciator for Train "B" Safety Injection actuation. CA19E Rewire Pressurizer Heater Control 20Bl2305 Pressurizer heater control status light 0700, 6.5.3.1.c No modification required. switches so that RED light is not indication meaning inconsistent w/other 6.6.6.3 defeated when switch is in pull-to-lock controls 6.5.1.6.d.1,3 position and green light is extinguished. DC-90-04/05 CA22E Remove unnecessary indicating lights 22A01308 Inconsistent meaning/application of color 0700, 6.5.1.6.c.2 Modification required; relabel indicating lights. from heat tracing panel. coding within/among systems 6.4.2.2.f.1 6.5.1.6.f. l,3 DC-90-04/05 CA23E Modify EDG megawatt, Megavar and 22A02086 Displays on VBS too low/high to be 0700, 6.1.2.2 No modification required. RPM indication on EDG panels to viewed from normal viewing area 6.1.2.5.b improve viewing. Coordinate with CAISE and CA75E. 22A02314 A few non-legend indicator lights do not 0700, 6.5.3.2.a. l HED deleted during original CRDR. have apparent meaning DC-88-25/26 CA24E Determine displays that most 22A02088 Displays on VBS too low/high to be 0700, 6.1.2.2 No modification required. significantly affect plant safety on viewed from normal viewing area 6.1.2.5.b Auxiliary Shutdown Panel and modify to DC-88-25/26 improve viewing. Coordinate with CA6E. VARP05.B7S-O 4
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B
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- CA27E Provide better functional arrangement of 23001225 Related control/display grouping 0700, 6.8.1.1.a,b No modification required.
SI/CLS controls. DC-88--04/05 CA29E Perform study to correct Control Room 20000009 Control Room glare 0700, 6.1.5.3.f No modification required. glare/lighting problems and implement improvements. 20000008 Abnormal Control Room illumination 0700, 6.1.5.3.a levels 20000001 Control Room ambient lighting too 0700, 6.1.5.7.a.2 variable 20000003 Operations not verified under emergency 0700, 6.1.5.3.a lighting 20000014 Ambient lighting varies significantly in 0700, 6.1.5.3.d Control Room. Noticeable glare 6.1.5.3.b 6.1.5.3.a CA36E Redesign Auxiliary Ventilation Panel. 20003016 Controls that must be operated 0700, 6.8.3.1.c No modification required. Consolidate indication and controls for simultaneously located too far apart common ventilation equipment on single board and provide mimic. 20A01215 Inadequate control and display grouping 0700, 6.8.2.1.a.2 20A03209 Containment recirculation fans logical 0700, 6.8.2.2.a arrangement and layout 23003019 Functionally grouped controls 0700, 6.8.2.1.a.2 22A013IO lllogical arrangement of controls and 0700, 6.8.2.2.a displays 22A03215 Mirror imaged components 0700, 6.8.2.3.b 22F23026 Ventilation panel controls for Unit 2 0700, 6.8.2.1.a,b,c inconveniently located VARP05.B7S-0 5
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B CORRECTIVE ./ CA.< Assoc. ... .........*. ¥1? ' . .. I*
- PESGRIP11Ql'f . HEDs ...
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Perform labeling study to determine 20A01101
.. ..... // DESCRIM'!ON Components on boards not appropriately/
0700, REFERENCES 6.6.1 thru 6.6.6 coN¢j:.tJSIONS/llElCOMMENDATJ:ONS No modification required. labeling needs and concerns of clearly labeled. operations. Relabel boards to 0700 guidelines. 20A01143 Component labels are not specific. 20A01148 Unnecessary information on labels. 22A01108 Major labels are not always used where necessary. 22A01126 Control positions not identified on some discrete functional control. 22A01133 Some labels have improper character stroke-widths. 22A01149 Inadequately labeled process controllers. 20A01311 Incomplete standardization among panels of Units 1 and 2. 22A01109 Subordinate labels are not always used where necessary. 22A0l1IO A few components have no component label. 22AOll 11 Labels repeat information. 22AOI 129 Letter heights not same for all labels within same hierarchical level. V ARP05 .B7S-0 6
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE II.B CORRECTIVE CA . ASSOC; . HED
-AcirON N<( . .*. /< DJ3$CRjPT,CpN *.* !Jl:iQs . .i. **. PE$G~PN REFERENCES CONCLUSIQNS/RECOMMENDATI9NS * * .
CA38E (Cont) 22A01137 Temporary labels do not conform to good HF principles. 22A03101 Inconsistent open and close position labels on process controllers. 22A01112 Some labels are not sized according to their hierarchical level. 22A01114 Some labels are not positioned to provide adequate label usability. 22A01120 A few labels are misspelled. 22A01130 Some labels have light characters on a dark background. 22A01145 Illegible labeling. 23AOI006 Demarcation 22A01122 Symbols are not used consistently. 22A01123 Some labels use roman numerals. 22A01124 Labels are not located above functional groups they identify. V ARP05.B7S.Q 7
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE II.B CORRECTIVE CA ASSOC. HED ACTION NO: .* DESCRIPTION * .... HEDs .* DESCRIPTION REFERENCES CONCLUSIONS/RECOMMEND,\TIONS CA38E (Cont) 22AOl 132 Incorrect character widths used for some labels. 22A01146 Incorrect labeling. 20A02042 Mirror imaged displays. 22A01144 Insufficient control position label visibility. 22A01301 Inconsistent meaning/application of color coding within/among systems. 22A01304 Distinctive enhancement techniques are not used for emergency controls. 22A02311 A few non-legend indicator lights do not have apparent meanings. 22A02313 A few non-legend indicator lights do not have apparent meanings. 22A03208 Control positions on key-operated controls are not labeled. 23A03210 Position indication. 23A03213 Throttle vs. momentary contact switch. VARPOS .B7S-0 8
CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE II.B CORRECTIVE CA .. ASSOC. HED ACTION NO. ... DESCRIPTION I:IEDs,. DESCRIPTION REFERENCES CONCLUSIONS~COMMENDATIONS CA38E (Cont) 20A02017 Multiscale indicators not operationally beneficial to operators. 22A02603 Arrowheads not used to indicate mimic flow directions. 22A03403 Messages on pushbutton contain more than 3 lines of lettering. CA39E Selectively investigate for Lamp Test 20A01216 No lamp test 0700, 6.4.3.3.c. l No modification required. capability, any safety systems with 6.5.3.1.a.2 legend lights that have single bulbs and that are not normally illuminated. CA41E Provide visual displays and indications 20A02005 Required displays and indications are 0700, 6.1.1.1.a No modification required. missing from Control Room primary missing from Control Room 6.5.5.1.b,e area. 6.5.4.1.g 20A02052 Required displays missing from Control 0700, 6.5.1.1.b Room 22A02027 Indication needed in Control Room 0700, 6.5.1.1.b CA42E Provide expanded scale for chemical 20A020IO Scale range inappropriate, need narrow 0700, 6.5.1.2.d. l,2 Modification required; indicator scale marking. addition tank level on RWST recorder. ranges expanded CA43E Provide valve position indication on flow 20A02035 Required displays and indications missing 0700, 6.1.1.1.a No modification required. controllers with red/green lights. from Control Room 6.5.1.1.b,e 6.5.4.1.g 22A03216 Lack of feedback indicating process/ 0700, 6.9.3.1.c direction of parameter change 20A02050 Required displays and indications missing 0700, 6.1.1.1.a from Control Room 6.5.1.1.b,e 6.5.4.1.g VARP05.B7S-0 9
\. *
- CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE II.B CORRECTIVE CA ASSOC.
. . .... .HED .
ACTION Nd; :. DESGRIPTIQN HJ3Qs . * * .. . DESCRIPTION REFERENCES CONCLUSIONB/RECOMMENDATIONS CASIN Replace trend recorder continuous flow 20A02403 Recorder pens clog, ink smudges paper 0700, 6.5.4.1.a No modification required. pens with felt tip cartridges, as required. 20A024IO Inadequate contrast- ink colors 0700, 6.5 .4.2.a.2 23A02415 Poor contrast on pen recorder between 0700, 6.5.4.1.a ink and paper CA53E Provide permanent installation of SG 20A02414 Recorders not located in primary 0700, 6.5.4.1.h No modification required. Level Narrow Range trend recorder on operating area bench board near Feedwater Control station. 22A02082 Displays not adequate in range, not 0700, 6.5.1.2.d.3 supported by auxiliary instrumentation DC-88-27/28 CA54E Perform studies to change setpoints, as 20A02904 Too many nuisance alarms in Control 0700, 6.3.1.2.a. l No modification required. necessary, on nuisance alarms in Control Room, no lock-out capability provided Room. CASSE Make control switches for the steam 20A03011 Control configurations do not match 0700, 6.4.1.1.c.2 No modification required. supply to the Steam Driven Aux other controls for same function 6.4.2.2.c.l,2 Feedwater Pumps the same as other DC-88-04/05 valve control switch. CA59E Relocate annunciator pushbutton controls 20A03069 Controls may be accidently activated 0700, 6.4.1.2.g Modification required; relocate annunciator on bench boards for ease of access. because of position on Control Board. DC-88-04/05 controls. CA61E Rearrange accumulator test line isolation 20V13022 Accumulator test line isolation valve 0700, 6.8.2.1.a No modification required. valves control switches. controls inconveniently located 6.8.2.1.b 6.8.2.1.c 20003017 Control switch layout is inconsistent 0700, 6.8.2.3.a DC-88-04/05 ' CA66E Provide SG wide range level indicators 22A02058 No positive indication that instruments 0700, 6.5. l. l.f No modification required. and condenser vacuum indicators on right have failed vertical board. 22A02075 Displays not precise or accurate enough 0700, 6.5.1.2.a DC-88-27/28 V ARP05.B7S-0 IO
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- ;,.*-*;:,:, *, *,*.,.,:r¢~t?tr Relocate high range radiation monitor trend recorders lower on panel. If
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TC:F*' tt****;*JX CORRECTIVE ACTION REASSESSMENT
SUMMARY
TABLE 11.B
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22A02087 r* r*r
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n Displays on VBS too high to be viewed from normal viewing area 0700, 6.1.2.2 6.1.2.S.b
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No modification required.
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feasible, add two recorders. DC-88-27/28 I, CA72E Replace existing trend recorders with 22A02409 Scales printed on chart paper are not 0700, 6.S.4.1.b No modification required. I' recorders that can be read easily. same as scales on recorder 20A02003 Multiscale indicators not operationally 0700, .6.S.l.S.f 1:1 beneficial to operators DC-88-27/28 CA74E Rearrange switches so accumulator fill 22A03034 Improper control location 0700, 6.8.2.2.b No modification required. valves are above accumulator drain DC-88-04/0S valves improve labeling. LER-81-0391036-0, 9/3/81 CA7SE Modify EDG Speed and Voltage control 22A03601 Control does not increase when turned 0700, 6.4.2.1 Modification required; install label on EDG speed switch positions and labeling so raise is clockwise or right control switch. to right, lower is to left. Also, include DC-88-25/26 Main GEN VOLT REG control switches Coordinate with CA1SE and CA23E. CABOE Improve operability of main steam 23003046 Missing controls 0700, 6.4.1.l.a No*modification required. PORVs and provide status on shift turnover sheet. DC-90-14-3 CASIE Provide remote throttle capability (trip 23003047 Missing controls . 0700, 6.4.1.l.a No modification required. I' close) to Bypass Valves for Main Steam ;! Trip Valves on Benchboard in vicinity of I Trip Valves. CA82N Upgrade simulator controls and 23A01002 Simulator/CR Standardi:r.ation 0700, 6.8.2.4.b Modification required; add engineering units lo instrumentation to reflect current control specific indicators. Continuous simulator upgrades room. Prior to installation in the CR, under normal programs. modifications will be evaluated to determine the necessity and feasibility of installation in the simulator first. 2300110S Units of measure 0700, 6.S.1.1.b 6.S.1.4.a 6.6.1.l VARPOS.B7S-0 11
Il.2 CORRECTIVE ACTION EVALUATION
- CANO.:
CA DESCRIPfION: EQUIPMENT MARK NO. 2E Provide meter for total auxiliary feedwater flow. HEDNO. FI-FW 100 A,B,C 20002018 Il.2.1 BED REVIEW - ORIGINAL FINDINGS HED No. 20002018 - Displayed values require operator conversion. (NUREG-0700 Sections 6.5.1.2.b, 6.5.1.2.c) Operator interviews and validation surveys identified indicator displayed values which required conversion in order to use the information in EOPs. Virginia Power's original CRDR assessment team reviewed the various displays and concluded that a separate total auxiliary feedwater flow indicator was required. Total auxiliary steam generator feedwater flow is not displayed in the Control Room. At present, there are three square root scale indicators per unit, monitoring AFW flow to each steam generator. The indicators are mounted on vertical section 1-2 of the main control board, Unit 1. It is difficult for operators to obtain quick, accurate total AFW flow readings from the existing indicators. Operator conversion to obtain total AFW flow does not comply with NUREG-0700, paragraph 6.5.1.2.b. DC-88-27/28 were prepared to install the total auxiliary feedwater flow indication .
- n~2.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs IXI YES D NO D N/A The monitoring of total auxiliary feedwater flow is required in several EOPs. For example, l-E-0, 1-E-l, 1-FR-Hl,, l-E-3, ECAs, ES, etc.
RG-1.97 DYES IXI NO D NIA Aux. feedwater flow (FI-FWlOOA,B,C) is variable D21 Category 2. However, total aux. feedwater flow is not a RG-1.97 requirement. Auxiliary feedwater flow rate values 350 gpm, 550 gpm, 70 gpm, 700 gpm and 500 gpm are EOP setpoints. EPIPs 0 YES IXI NO ON/A LERs/IOERs DYES IXI NO O NIA Total auxiliary feedwater flow indication is not used No LERs/lOERs concerning the monitoring of total in the EPIPs. auxiliary feedwater flow were found. APP.R DYES IXINO ON/A HPES/STA DEV/SOER DYEsJXlNO DN/A Total auxiliary feedwater flow is not required for No station deviations or SOERs were found concerning Appendix R safe shutdown. the monitoring of total auxiliary feedwater flow. ERF/SPDS DYES IXI NO D NIA TECH SPEC ITEM IXI YES D NO D NIA Total auxiliary feedwater flow is the not ERF computer. The operability requirements of the auxiliary feedwater However, auxiliary feedwater flow is in the ERP-Point system and instrumentation is defined in TS 3.6.D. IDs, FIFWOOlA, FIFW002A, FIFW003A. VARS0l.B7S-l
\
II.2.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE The flow requirements for AFW are based on a total flow to intact steam generators. EOPs 1-E-1 and 1-E-2 require the operators to maintain 350 gpm until level is greater than 9% in at least one SG. For a loss of normal feedwater (LNFW) Condition II event (no MSLB or FWLB), the total flow is that flow to all three SGs. For other events (i.e., FWLB and MSLB), the flow requirement is 350 to intact SGs. A corrective action similar to Surry Correction action CA2E was implemented at North Anna Unit 2. After the modification was implemented at North Anna Unit 2, IR-4874B was initiated to address problems associated with the total AUX FW flow indication. These problems included:
- a. The individual loop flow signals have large uncertainties (+/-72 gpm) at low flows (less than 100 gpm). To account for these uncertainties, minimum required total flow values, as read on the total flow indicator, would need to be raised to values higher than the capacity of a single motor driven pump.
- b. Minimum required total flow is based, for most cases, on flow to intact steam generators. The total flow indication includes flow to all steam generators, regardless of status.
IR-4874B has been reviewed for applicability to corrective action CA2E at Surry Power Station. Based on a review of the loop accuracy calculations 14937.70-C-2, 3, 4, and 8, it is concluded that Surry will experience problems similar to those encountered at North Anna Unit 2 and addressed in IR-4874B. The loop accuracy of the total flow indicator at Surry would be approximately
+/-54 gpm during normal operating conditions at a flow rate of 450 gpm and up to +/-200 gpm during abnormal conditions (DBE) at flow rates of 450 gpm.
Safety Significance - The auxiliary feedwater flow indication is safety related and used in various EOPs for heat removal following accidents. Potential In Error - The operators are required to sum the individual auxiliary feedwater flow indicators to determine total flow to the SGs. The potential for operator error is increased due to conditions of stress and the ability of the operator to process information. However, the installation of total auxiliary feedwater flow indicators could also result in errors due to large instrument inaccuracies and plant configuration (intact/faulted SGs) during the event. Consequences of Error - The consequences of an error when determining the total auxiliary feedwater flow rate would be potential failure to maintain minimum auxiliary feedwater flow to SGs during accidents. A total AFW flow indicator would only be useful if the flow going to a faulted SG or broken feedline has been isolated and the total flow indicates the flow to the intact steam generators. Based on Calculation 12846.58-US(B)-055, Rev. 0, the maximum flow to all 3 SGs with 3 AFW pumps running is approximately 1025 gpm, therefore a range of 0-1500 is adequate. However, with only two or one AFW pumps running, the total flow is between 388-677 and the minimum required is 350 gpm. Therefore, expected operating range is 350-700 gpm during the transient. 11.
2.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion, sufficient information is presented to justify not implementing CA 2E and not installing total auxiliary feedwater flow rate indication. The total auxiliary feedwater flow indicator could provide ambiguous information for any operating conditions. For cases where the required information is total flow to intact steam *generators and flow to a faulted generator exists, the total flow indication would be invalid. *
- V ARS0l.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION INlJREG.-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST D RG-1.97
- D LERs/IOERs/SDRs D ITRAINING MODUIES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
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VALlDATION OF I-LIMN Revision fl ENGit'IEERJNG SUIT ABLTIY 3 March 1984 At'<O. , VALIDATION CF CONTRCL \' RCX>M f"U'CTIONS APPENDIX B9 HED REPORT (CONTINL£0) S\J f\~ { /oN I T'S I jc9.. PLANT/U'1IT t-£:D NO.: f .I- / /0 f) SUGGESTED BACKFIT: c_),~,,_ ~ t;;; "'- ~~ ~-v,..,... . g) REVIEW AND DISPOSITION: B9-2
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VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5.1 GUIDELINE COMPLIANCE CHECKLIST 6.5.1.2 USABILITY OF DISPLAYED VALUES Scales should be graduated and numbered so that readings are rE!lated in a direct and practical way to the operator's tasks.
- a. SCALE SELECTION-Scale units should be consistent with the degree of precision and accuracy needed by the operator. '
- b. ELIMINATION OF OPERATOR CONVER*
CA !2.E SION-AII displays should indicate values r in a form immediately usable by the operator without requiring mental conversion.
- c. PERCENTAGE INDICATION-Percentage indi*
cation may be used when the parameter is meaningfully reflected by pe~ntage;
- d.
- SCALE RANGE-Scales should be selected to:
( 1) Span the expected range of operational parameters, or (2) Employ *appropriate scale ra~ging tech*
- e.
(3) niques, or Be supported by auxiliary wide-range instruments. SCALE SIZE-Scale ranges may be expanded (or contracted) .by multiplying or dividing indicated scale values by powers of ten. All such scales should be clearly marked as to whether the indicated values should be multiplied or divided, and the factor involved (e.g., 10, 100, 1000).
- f. S~NSITIVITY-Display dynamic sensitivity should be selected to minimize the display of normal random variations in equipment performance.
6.5-3
PAGE No. 12 VOLIAN ENTERPRISES DATE 4/29/92 Surry (lA) - Unit 1 - SETPOINT DATABASE REPORT PROCEDURE USAGE SET POI NT PROCEDURE USAGES FOLDOUTS/CONTINUOUS ACTIONS PAGE FOR 1-ES-0.4 FOLDOUTS/CONTINUOUS ACTIONS PAGE FOR 2-ES-0.4 K.6 l-ECA-1.1/21 l-ECA-3.1/26 l-ES-1.2/21 1-FR-P.1/18 1-FR-P.1/25 K.7 1-E-3/17 1-ECA-3.3/30 1-ECA-3.3/39 K.8 1-ECA-1.1/15 l-ES-1. 2/24 1-FR-:-I.3/16 1-FR-P .1/6 K.9 l-E-3/38 1-ES-0.4/Procedure Steps/1 l-ES-0.3/1 1-FR-1.3/10 2-ES-0.4/1 K.10 l-E-3/38 1-FR-1.3/10 K.11 1-ECA-3.1/19 1-ES-1.2/14 K.12 l-ECA-3.1/19 1-ES-1.2/14 1-FR-H .1/25 K.13 l-ECA-3.1/19 1-ES-1.2/14 K.14 1-ECA-3.1/19 l-ES-1. 2/14 1-FR-H .1/25 K.15 l-ECA-3.2/12 K.16 1-ECA-3.2/12 K.17 1-ECA-3.1/20 l-ES-1.2/15 K.18 1-ECA-3 .1/20 l-ES-1. 2/15 1-FR-H.1/26 K.19 l-ECA-3.1/20 l-ES-1. 2/15 K.20 l-ECA-3.1/20 1-ES-1.2/15_ l-FR-H.1/26 K.21 l-ECA-3.2/13 K.22 l-ECA-3.2/13 L.1 l-E-3/23 L. 2 l-ECA-1.1/Attachment 1 L.3 l-E-1/20 L.4 1-E-0/14 1-E-0/20 1-E-0/26 1-E-D/29 1-E-1/3 1-E-1/6 1-E-3/7 1-E-3/21 1-ECA-0.0/4 1-ECA-0.2/6 1-ECA-0.2/6 1-ECA-D.1/9 1-ECA-0.1/9 1-ECA-1.1/5 1-ECA-3.3/4 1-ECA-3.2/5 1-ECA-3.3/6 1-ECA-3.1/11 1-ES-0.1/1 1-ES-0.2/6 1-ES-0.1/9 l-ES-1. 2/7 1-ES-1.1/19 1-ES-3.1/5 1-ES-3.2/5 1-ES-3.3/5 1-FR-C.1/9 1-FR-H.1/1
Page No. 13 VOLIAN ENTERPRISES/ Surry (lA) 04/29/92 EDP SETPOINT - DATABASE REPORT DESCRIPTION SETPOINT DESCRIPTION SETPOINT VALUE REVISION NUMBER used to determine if normal charging can be established to minimize leakage of reactor coolant. K.19 Reactor coolant subcooling requirements for establishing normal 185'F 11/30/89 charging for forced circulation, subcooled recovery methods, including allowance for normal channel accuracy and post-accident transmitter errors. This value is used to determine if a charging/SI pump can be stopped to minimize leakage of reactor coolant. K.20 Reactor coolant subcooling requirements for establishing normal 190'F 11/30/89 charging for natural circulation, subcooled recovery methods, including allowance for normal channel accuracy and post-accident transmitter errors. This value is used to determine if a charging/SI pump can be stopped to minimize -leakage of reactor coolant. K.21 RCS subcooling requirement for establishing normal charging for 105'F 11/30/89 saturated recovery methods, including allowance for normal channel accuracy. This value is used to determine if normal charging can be established to minimize leakage of reactor coolant. K.22 Reactor coolant subcooling requirements for establishing normal 185'F 11/30/89 charging for saturated recovery methods, including allowance for normal channel accuracy and post-accident transmitter errors. This value is used to determine if normal charging can be
- L.1 L.2 established to minimize leakage of reactor coolant .
Minimum charging -fl ow necessary to prevent flashing in the letdown in the letdown line. Charging flow is established at this value while the eves is aligned for normal operation. Minimum SI flow necessary for decay heat removal. This value is used to conserve makeup water supply following a loss of 25 gpm Curve 07/21/88 07/21/88 emergency coolant recirculation. L.3 Minimum LHSI pump flow which indicates injection into the RCS. 1000 gpm 04/02/92 This value is used to determine if the LHSI pumps are injecting.
,.-r L.4 Minimum AFW flow requirement necessary for a secondary side heat 350 gpm 11/30/89 sink with normal containment conditions and no RCPs running.*
This value is used to ensure adequate AFW flow for decay heat removal.
~ L.5 Minimum AFW flow requirement necessary for a secondary side heat 550 gpm 04/02/92 sink with normal containment conditions and all RCPs running.
This va 1ue is used to ensure adequate AFW fl ow for decay heat and pump heat removal.
.-., L.6 Minimum feed flow which can be verified in the control room. For 70 gpm 04/02/92 certain multiple failure events, this minimum flow is maintained to a faulted steam generator to prevent steam generator dryout. ~L.7 Feed flow corresponding to the flow capacity of two motor-driven 700 gpm 07/21/88 AFW pumps at the SG design pressure. This value is used to to verify adequate secondary side heat sink following an ATWS with RCPs running.
L.8 Charging flowrate comparable to normal charging/SI pump mini flow. 60 gpm 07/21/88 Charging flow is established at this value prior to re-establishing normal CVCS alignment to prevent pump operation above its shutoff pressure . L.9 Minimum indicated Service Water flowrate to each recirculation 2000 gpm 07/31/91 spray heat exchanger. This value is used to ensure proper line up of the Service Water flow path to heat exchanger.
Page No. 14 VOLIAN ENTERPRISES/ Surry (lA) 04/29/92 EDP SETPOINT - DATABASE REPORT DESCRIPTION SET POINT DESCRIPTION SETPOINT VALUE REVISION NUMBER L .1 O Maxi mum 1ow-head SI pump fl ow to protect aga i.P'1t purr.11 ri:rc.,ut 3500 gpm 07/21/88 during transfer to hot leg recirculation. _,,111?' L. 11 Minimum AFW fl ow requirement necessary fonl'a sec<Jnda; y side heat 500 gpm 04/02/92 sink with adverse containment conditions and ~o RCPs running. This value is used to ensure adequate AFW f; ,*, for decay heat removal. L.12 Minimum charging flow to ensure adequate boration. 75 gpm 11/14/89 L.13 Minimum feed flow which can be verified in the Control Room with 126 gpm 04/02/92 adverse containment conditions. For certain multiple failure events, this minimum flow is maintained to a faulted steam generator to prevent steam generator dryout. L.14 Minimum SI flow before TSC should be consulted to determine if 150 gpm 11/14/89 the SI pumps should be throttled, or if charging flow should be initiated. L.15 Main steam flow corresponding to the maximum steam dump to 1. 0 E 6 PPH 10-01-91 avoid main steam isolation at high steam flow coincident with low Tavg, including allowance for normal channel uncertainties. This indicated value is used to prevent automatic main steam isolation, and termination of steam dump during controlled cooldowns. L.16 Minimum Main Feedwater flow which can be verified in the control 0.7E6 pph 07/31/91 room. An attempt is made to achieve this minimum flow following loss of Auxiliary Feedwater flow, and prior to establishing bleed and feed cooling during a loss of secondary heat sink event. M.1 Containment high-high pressure setpoint. This value is used as 23 psi a 07/21/88 an entry.. condition for CSP-Z.l, "Response to High Containment Pressure. M.2 Containment pressure setpoint for actuation of containment spray. 23 psia 07/21/88 This value is used to determine if containment spray should be actuated. M.3 Maximum containment pressure for stopping the containment spray 12 psia 11/14/89 pumps. This value is used to determine if containment spray pumps can be stopped to minimize RWST depletion and NaOH addition. M.4 Containment pressure setpoint to reset the containment high 14 psia 11/14/89 pressure signals. This setpoint is used to reset the HIGH-1 and if* HIGH-2 containment pressure signals when the containment pressure is reduced below this value. M.5 Containment design pressure. This value is used as a RED PATH 60 psia 07/21/88 entry condition to CSP-Z.l, "Response to High Containment Pressure". M.6 Radiation level setpoint for post-accident containment radiation 2 R/hr 07/21/88 monitoring. This value is used as an entry condition to CSP-Z.3,"
"Response to High Containment Radiation Level".
M.7 Containment radiation level for isolation of containment. This 10 R/hr 07/21/88 value is used to determine if all containment penetrations should. be isolated to limit radiological releases following a loss of a 11 AC power. M.8 Containment water level just below design flood level, including 7 .2 ft 07/31/91 allowance for normal channel accuracy. This value is used as an* entry condition to CSP-Z.2, "Response to Containment Flooding". M.9 Containment sump level necessary for containment sump 2.5 ft 07/31/91
NUMBER PROCEDURE TITLE REVISION 7 1-E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 18 of 21 STEP ACTION/EXPECTED RESPONSE i--~~--1 RESPONSE NOT OBTAINED i--~~~~~~- CAUTION: Alternate water sources for AFW pumps will be necessary if ECST level decreases to less than 20%.
*29. CHECK SG LEVELS:
a) Any Narrow range level - a) Maintain total feed flow GREATER THAN 9% greater than 350 gpm until narrow range level in at least one SG is greater than 9%. b) Check emergency buses - BOTH b) Locally isolate AFW header on ENERGIZED deenergized bus if necessary to control level:
- l-FV-141 for H bus
- l-FV-1.56 for H bus
- l-FV-171 for H bus
- 1-FV-140 fo~ J bus
- l-FV-155 for J bus
- 1-FV-170 for J bus c) Control feed flow to maintain c) IF narrow range level in any SG narrow range level between 9% continues to increase in an and 50% uncontrolled manner, THEN GO TO l~E-3, STEAM GENERATOR TUBE RUPTURE, STEP 1.
- 30. RESET SI
NUMBER PROCEDURE TITLE REVISION 6 1-E-l LOSS OF REACTOR OR SECONDARY COOLANT PAGE 4 of 25 STEP ACTION/EXPECTED RESPONSE i--~~--i RESPONSE NOT OBTAINED i--~~~~~~-- CAUTION: Alternate water sources for AFW pumps will be necessary if ECST level
. decreases to less than 201.
- 3. _CHECK INTACT SG LEVELS:
a) Any narrow range level - a) Maintain total feed flow GREATER .THAN 9% [321) greater than 350 gpm [492 *gpm] until narrow range level greater than 91 [321] in at least one SG. b) Check emergency buses~ BOTH b) Locally isolate AFW header on ENERGIZED deenergized bus if necessary to control level:*
- l-FW'-141 for H bus*
- 1-FW'-156 for H bus
- l-FW-171 for H bus
- l-FW'-140 for J bus
- 1-FW'-155 for J bus
- l-FW-170 for J bus*
c) Control feed flow to maintain c) IF narrow range ievel in any SG narrow range level between 91 continues to increase in an [321) and 501 uncontrolled manner, THEN GO TO l-E-3, STEAM GENERATOR TUBE RUPTURE, STEP 1 .
NUMBER PROCEDURE TITLE REVISION 6 l-E-3 STEAM GENERATOR TUBE RUPTURE
. PAGE
- STEP ACTION/EXPECTED RESPONSE i--~~--1 RESPONSE NOT OBTAINED 8 of 32 J--~~~~~~--
CAUTION: Alternate water sources for AFft1 pumps will be necessary if ECST level decreases to less than 20%.
- 7. _CHECK INTACT SG LEVELS:
,a) Any narrow range level - a) Maintain total feed flow GREATER THAN 9% [32%] greater than 350 gpm [492 gpm]
until narrow range level greater than 9% [32%] in at least one intact SG. b) Check emergency buses - BOTH b) Locally isolate AFW header on ENERGIZED deenergized bus if necessary to control level:
- l-FV-141 for H bus
- 1-FV-156 for H bus
- l-FV-171 for H bus
- l-FV-140 for J bus
- l-FV-155 for J bus
- l-FV-170 for J bus c) Control feed flow to maintain c) IF narrow range level in any narrow range level between 9% intact SG continues to increase
[32%]
- and 50% in an uncontrolled manner, THEN RETURN TO Step l.
- 8. RESET SI
I- 1400 WESCHLE.R VX-252 INDICATO.R INOICATOR TAC NO. \.ABEL ON INOICA TOR INOICATOR L.OCA TION 1-FW-Fl-1000 AUX F'O WTR VE:RT. BO.
~ 1200 TOTAL FLOW 1-2
.§.
[rl. err 1000 5
- ei I.I..=
i- 800
~ i-. GPM
! 111 600 ti
- 0 .
~ 400 NOTES
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- 2. Sl2E ~ NUMBER$ ~INl~UM, OOiHIC F'ONT
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IIIOlfTHCA/IDUNAPOIM Memorandum
- To From.
Distribution L. M. Kolonay, INJNW Innsbrook Technical Center November 20, 1990 PROPOSED SCOPE CHANGE DC-87-30/31 AUXILIARY PBEDWATER FLOW INDICATION IR 4874B NORTH AHHA POWER STATION
.The purpose of this memo is to request concurrence to revise the scope of the subject design change to delete the installation of the total auxiliary flow indicator.
1.0 BACKGROUND
The subject design change was developed to implement CRDR corrective Actions CAJE and CAllE (see Attachment 1, excerpt from letter to NRC 85-268C, dated June JO, 1986). These corrective actions were proposed to resolve HED's 10002241 and 10A02272o (Attachment 2). Although neither of these HED's specifically cites the lack of a total flow indicator as a problem, the corrective action identified by the Human
- Engineering Discrepancy Assessment Team (HEDAT) included provision of a total flow indicator. It is presumed that this was done because the AFW flow requirements contained in the EOP's are generally stated in terms of total flow and a total flow indicator would relieve the operator of the task of computing the total.
In accordance with the corrective actions, DC-87-30/31 accomplishes the following: Linearizes the individual AFW flow signals to the indicators. Expands the range from o - 400 gpm too - 500 gpm. Revises the indicator scales to be linear with increments* of 10 gpme Adds an indicator to display the total of the three loop flows. This design change was implemented for North Anna Unit 2 during the recent outage (DC 87-Jl)o I LMK/psj:ll2090c APl'EH ~ r'J. 4
- 2.
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2.0 PROBLEM ENCOtJN'l'ERED . Description During a review of EOP's to identify revisions which migpt be required as a result of DC-87-31, it was realized that use of the total flow indicator for EOP's would be impractical for the following reasons:
- a. The individual loop flow signals have large uncertainties at low flows (less than 100 gpm). To account for these uncertainties, minimum required total flow values, as read on the tota.l flow indicator, would need to be raised to values higher than the capacity of a single motor driven pump.
- b. Minimum required total flow is based, for most cases, on flow to intact steam generators. The total flow indication includes flow to all steam generators, regardless of status.
Due to the concerns described above, the EOP's for Unit 2.were written to use only the* individual loop flow indicators .* source of Problem This design change retains the existing method of determining flow by mea.suring the differential pressure across a primary flow element (orifice). In this method, the differential pressure developed is proportional to the square of the flow. This relationship is illustrated in Attachment 3. As can be seen from this illustration, a small change in differential pressure at the lower extreme represents a relatively large change in flow. As a result of this relationship, the uncertainty in indicated flow increases as flow decreases as illustrated in Attachment 4. (Based on calculation EE-032 Rev. 2). As shown on Attachment 4, an individual loop flow indication could be as high as 72 gpm when actual flow is zero. As currently designed, the total flow indicator receives a signal which is the sum of the individual loop flows. For situations involving zero flow in any individual loop, the value displayed on the total flow indicator could be in error by +/-72 gpm or more. In addition, the total flow indicator will display the sum of all loops which could include flow to faulted steam gene.raters *
- LMK/psj:112090c DCP f~~ 2.:
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3.o ALTERNATE SOLO'l'IOHS Redesign Total Flow Circuitry The total flow circuit could be redesigned such that the
- unreliable portion of the flow range_ is excluded from the summing operation. The hardware choices for such a modification are limited due to the need to use qualified equipment which is compatible with the Westinghouse 7300 system. The desired change could be achieved by replacing the square root extractor cards with function generator cards or by adding these cards
- downstr_eam of the square root extractors.
This alternate is not recommended for-the following reasons: a) The total flow indica.tion would still be invalid for cases where total flow to intact steam generators is required and flow to a non-intact generator exists. b) Replacing the square root extractor cards with function
. generator cards would result in a co;mplex calibration p_rocedure. The square root curve would need to be approximated by straight line segments set up by adjusting eight gain and eight bias controls for each card *
- c) Adding*the function generators downstream of the square root extractors would increase the parts count for each loop and thus decrease reliability.
Revise EOP's The EOP's could be revised to accommodate the limitations of the total flow indicator. Either the required minimum flow values could be raised to account for the applicable uncertainties or restrictions on the use of the total flow indicator could be identifie~. This alternate is _not recommended. Raising minimum flow requirements to account for the applicable uncertainties would result in requirements for two motor-driven pumps to be operable for certain EOP's which currently require only one. Adding cautions or restrictions on the use of the total flow indicator would add to the operators mental workload during an emergency. -.This is contrary to the intended purpose of the indicator. l+PPEr-t:>I 'I. -t. "2.
- LMK/psj: 112090c * !)( fJ q I - 2.a'f Po.,- 2z.. cf 7~
3
4.0 RECOMMENDATION NES recommends that the total AFW flow indicator not be installed in Unit 1* (DC 87-30) and be removed from Unit 2 at the next opportunity. Justification for not installing the total auxiliary flow indicator is based on the following: a) The specific problems identified in HED's 10002241 and lOA02272 have been corrected by: Expanding the individual loop flow range to 500 gpm. Linearizing the indicator scales and marking in 10 gpm increments. Revising applicable EOP' s to reflect minimum AFW flows. of 100 gpm in lieu of 25 gpm. b) The total auxiliary flow indicator does not provide unambiguous information for all credible situations. For cases where the required information is total fl.ow to intact steam generators and flow to a faulted generator exists, the total flow indication would be invalid.
- 5.0 ACTION REOOBSTED Those on distribution are requested to indicate concurrence with the above recommendation by signing in the appropriate space below.
If you have any questions or require further information, please contact me at Innsbrook extension 2217. fl.f PE,-/bi ,c. .,f. 2. D c.i' 'f I -20~ LMK/psj:ll2090c p""'5'"" 23 S "? o 4
- Prepared By: P r o j e ~ E ~ n ~
Concurrence: ~~~~' I i-,t,.Ja _
~
=-1--,-.,....__--J Supervisor Pro?,ect~ gineering Concurrence: )t/ J 6. . *_t,._~_.
_ _ _1_ _*___
}. ./)____________,I / / I loI 1 ' .!1 Superintendent-Nuclear Site Services Date Concurrence: :D~ / 11)2el 'Q S uperinten ent o
' d fE .
ngineering ' Date if Concurrence: -~e;giifij~t~-===--.:.---___,I~ Asst. Sta~~gr. Operations & rJt31 /ch~* Maintena ce concurrence: ..:J:e.:) / l~'lJ Asst. Station Mgr. Nuclear Safety & ate Licensing
- Concurrence; Mana i~ NuclearEngineering
/ ,, *11.,"0 Date Distribution: Mr. E. s. Grecheck, INJNW Mr. R. w. Riley, INJNW Mr. M. w. Gettler, NAPS Mr. o. A. Heacock, NAPS Mr. R. o. Enfinger, NAPS Mr. J. A. Stall, NAPS cc: Mr. M. G. Pinion, IN2NW Mr. w. o. Corbin, INJNW Records Mgmt., NP-69.2, INGW
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AHACHHfNf I 1AOL E r SR- 1 .* r*l u -~. sthlAl NO. 85-26RC ~ tJ TMLE FSR-1 *-./, I '*' COIITROI. ROIII 0£SIGN REVIEli "'* Ir "' FINAL SIIIWIY REPollT om ANNA PdlER STATION UNITS I Am 2
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<t PROPOSED CORA£CTIV£ ACTIONS All) HRnntATIIII SOIEIU.E CORRECTIVE ASSOCIATED JUSTIFICATION FOR PARTIAL OR ACTION I PROPOSED CORRECTIVE ACTION SCHEOOLE HEOS NON~CORR[CTION or HEO CAI£ Perform*study to address htgh ,..,tent ST/ST 10000012 noise tn control rOOllli lt*tt cnntrol 10000005 room access and tnvesttgate other noise IOA02.901 reduction techniques and hnplement
' reconmendations. Adjust a lanns to be 10 OD(A) above ambient noise level.
CA2£ Conduct study to identify I/ST 10000505
- conmuntcattnn syste*s problems and 100007.02 implement reconmendations. 10000203 10000204 10000205
.. 10000206 Resca 1P Aux ii tary feedwater flow ST 10002241 tnd(cators (lJnear 0-500 GPM Increments of 10 GPH). Coordinate with CAIi! (IOA0227.2).
(A4N Provide step-stool and use existing
- strip chart recorder for determining IOA02021 Condensa le Storage Tank 1eve l.
Coordinate with CAJRN (iOA02023). 1111. R or 70
WRIH f TIVf ASSOCIATED JIIS Tl r ICAT ION f OR PARTI Al OR ACTION I
-*--------- PROPOS[D CORR[CTIVE ACTION SCUEDUL[ HEOS NON-CORRECTION Of HEO ~~ Provide meter for Total Auxtllary feedw~ter flow f0-1500 GPH).
Coordinate with CAJE (10002241). ST JOA02?.72
,..J CAI.?[ Provide direct valve posttfon SJ Indication wfth RED/GREEN lights IOA02274 "ii-
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CAIJE Relocate Casing Cooling components to ST IOA()2402 Safeguards Panel
- CAl4E Perfonn study of Annunciator Alal"'l'I Syste1111 ST/LT IOA02911 and implement upgrades as necessary IOA02106 IOA02107 IOA02l04 IOA02905 IOA02912 IOA02916 12A02I09 12A0211 I 12A02112 12A021 ll 12A02114 12A02115 12A02116 12A02117 12A02118 12A02119 12A02121 12A02918 IOAOIOOI IOAOI002
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~ c~IERIIE DISCRE:lQNCY RE:ll:Jlr.
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- APPENDIX 89 HUMAN ENCI"EERJNC OISC:REPANCY (t-EC) REPORT r . '
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- ORJGINATOR: -~--* _?,
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( l) ?vo \l~e..... d_ +D l ().,~ lJ ,t( ~ w / I*1V\1A-v -s~-t.. ( O ~ \5oo~ j
- 89-2
M DP /FLOW RELATIONSHIP 80 70 60 50 z: 3:: <( g ~ 40 LL 30 20 10 0 5 10 15 20 25 30 35 40 45 50 DP (% SP.I)
f-i z AUX FW; FLOW INDICATION s u
~
ERROR VS FLOW f-i 80
~
70 \
\
60 \
\
+ ERROR LIMIT
\
50 \ - ERRO.R LIMIT 3: \ 0 _J 40 \ LL \ 30 \ ..... 0 w 20 J--
<( .--.... . 10 U.L 0 Q_ 0
- z
- '~ --
-10
. z.:
- -20 ,,.....-....***--***-***-****** -***-- -
0::: 0 -30 Cl'.: Cl'.:
/
w -40 ..-'
,1
-50. .i I
-60 ....../
.-70 .....
-80 0 1 00 200 300 400 500 50 1 50 250 350 450 ACTUAL FLOW (GPM)
- 11.6 CORRECTIVE ACTION EVALUATION CANO.: 6E CA DESCRIPTION: Demarcate and add colored background on Auxiliary Shutdown Panel same as MCB.
Tape is to be removed and replaced with orange and purple color dots on labels. Coordinate with CA24E. EQUIPMENT MARK NO. HED NO. Auxiliary Shutdown Panel Components 20A01305 11.6.1 HED REVIEW - ORIGINAL FINDINGS HED No. 20A01305 - Lack of demarcation lines. (NUREG-0700, Section 6.6.6.2.a) As identified in th~original CRDR Label and Location Aids Survey, the Auxiliary Shutdown Panel was not provided with lines of demarcation to enclose functionally related controls and displays. The lack of demarcation could result in a delayed/incorrect operator response. DC-88-25/26 would demarcate and provide a colored background on the Auxiliary Shutdow11 Panel consistent with Main Control Board standard for colored padding. New labels in accordance with Virginia Power Standard STD-GN-0036 would also be installed. The DCPs were not implemented .
- 11.6.2 EOPs HED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW 0 YES IXI NO O NIA The ability to quickly locate controls and perform orderly cold shutdown functions is identified in abnormal RG-1.97 DYES main control room.
IXINO ON/A All RG-1.97 display instrumentation is located in the procedures and FCA (fire contingency action). EPIPs 0 YES ONO IXl NIA LERs/lOERs DYES IXl NO D NIA Not applicable to Auxiliary Shutdown Panel. No LERs/IOERs concerning the ability of an operator to locate specific controls or view displays on the Auxiliary Shutdown Panel were found. APP.R IXl YES ONO ON/A HPES/STA DEV/SOER DYES IXI NO D NIA The need to locate system controls are important for No station deviations/SOERs were found concerning the Appendix R and orderly safe shutdown of the plant. ability to differentiate ASP controls .
- ERF/SPDS DYES D NO l&l NIA ERF /SPDS is not associated with Auxiliary Shutdown Panel.
VARS01A.B7S-l TECH SPEC ITEM Spec. items. DYES IXl NO D NIA The controls and instruments on the ASP are not Tech.
Il.6.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE The corrective action indicates color coordination/demarcation by system and power supply . Safety Significance - The auxiliary shutdown panel (ASP) contains Class IE components. Potential for Error The potential for error is high for power supply and low for system differentiation. Power Supplies The Abnormal Procedures (APs) require the operator to determine which bus is available. Presently, the ASP component labels are not provided with power supply information. Background color demarcation in the Control Room provides the operator the ability to distinguish between areas of
-control between the vertical boards and benchboards. In the Control Room, it enhances the operator's ability to locate systems on multipanels; however, the ASP is a single panel with limited functions and demarcation is not required.
Consequence of Error - The consequence of an error due to the lack of power of supply information would be a delay in operator response to operate a particular control. Il.
6.4 CONCLUSION
S/RECOMMENDATIONS Due to consequences of error in determining power availability at the ASP when performing APs, it is recommended that the ASP component labels be revised to indicate' channel/train color. The legend plates and labels will be "ngraved in accordance with the Nuclear Design Control Program. The demarcation of the ASP in color by system is not required for the following reasons:
- 1.
2. 3. ASP is a small single function panel vs. the control room panels which are large multi-function panels . ASP has single functions No simulator training problems or documented errors were noted .
- V ARS01A.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D I EOPs/EPIPs D I I ERF/SPDS D I
- Q-LIST RG-1.97 D
D ILERs/IOERs/SDRs D ITRAINING MODULES D ITECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
- SURRY TITLE
~IT I CODE A
~IBILITV NOTED JAN ASSESSfEN'T STATUS 2 Q 19Sf LAST REVIEW DATE H.W.t 2Wl3e5 UO< OF DEAARCATI~ LINES II -S 87/11/85 IU!AN ERROR:
DELAYED/INCORRECT CPERATDR REPOHSE. ff+ PROBWI DESCRIPTIDk: WIARCATIDN LINES NOT USED C>>I 111T SHIJTilOil\ PANE!.. e70il PARAS~ MJl'JER: o.Ei.o,i:.R SI.SGESTED MOO IT: DEIIIARC HOl ~ ~rt. ti.l~,r.ATI~ PiEtD FDR O~/?UftiU TAPE/ARROWS USED TO ASSOCIATE CT!l. S61TCIS W/ PROC CTRLS
..+ DlSPuS!ililh:
/ Dc~R~f4Te & H!)jj COi.OR ~ATC.U:S Hi! Oft ,~a. iR,,E 1S TD l!C RE.IIIOVED & lleP'.~ED ,,,, DRANlr- & PiJIPi.£ 00..DR DOTS ON LABEL DATA CO.aCilLJ!'; ~.SCRIPTlrr.. ~ CQDE ltll'Uiu T...-6.1 !..A=LS W..11 !.OC~'!'lDN IUDS SURYE~
ITEMS 1NIJCn..\'ED: MRI( NIJIIB:ii LOCATIDr- ~N'T MME SVSiEtll SIJBSYSTE" DEM~ Lltc:S ff Nill lH Jr.v FILE t
~~J.~vk. wti l,Z-4-G, (zz-M-Z068)
*)
l May 198:5
- HUMAN E.NGlNEE°RlNG DISCREPANCY (HEO) REPORT 20AO- l3~5 ORIGINATOR: -"J)....:;..s;::,c,._ _ _ _ _ _ __ HEO NO.: -~D...111,S_-~,b_____
VALIDATED BY: _ _ _ _ _ _ _ _ __ DATE: a) HED TITLE: ~19Ck Or l>EHA/fC,,,TIQIU L.t..VE"5. b) ITEMS JNVDL VED: k At./.. CtJMPO-UENTS o,v ~ SNVT'OoWN
- c) PROBLEM DESCR.lPTION AND 0700 PARA. NUMBER: (~G.G. ~q)
/)E/ll?AAC~ TltJN ~.IA/c$ ,Vo T U.SED ON No T SNvrD~c.,),IIJ PANEL.
d) OAT A COLLECTION DESCRIPTION At<O CODE NJMBCR: T~~./ t::JSSElfV;tfTION e) SPECIF"IC HJMAN ERROR(s):
* /)E~l'f Yet>/ /A./Ct:Uf /(JEC r OPE,#f,'f Toll. AE.SPoNSE -
- 99-1
l May 198'3
- HED REPORT (CONTINUED)
Swlf yfeoT SHVTl)ou.JN
. PLANT/UNIT HED ND.: J)S -\ b f) SUGGESTED BA.CKFIT: (&.{;.,;,.q)Ao,l .
/'91°/J~ f' /)EHl'IRCIIT#J/V OM ~ S Nv,l)oe,,i/J Pl1"h~~ *
,N1.s .,,.,,., Y E~.,,,,_,/,s,lfrc ,,,v£cD
- Fentf ol'fl'IAJG, e j p,,1_1f P~ c CCOl,V(;. TIIPc l'IIVO lt//lU)uJ.S u~ISI> T~ l'ISSoc,A~
Ct,IV TR. 11
- 1. stAJ, re HF s "", rH Plf e,c ~s s co 1Jrte. ,,, c. F1t.s,*
- - 89-2
l May 1963
- HLJMAN EN~lNEERJNG OJSCRCPANCV (HED) REPORT ORJGlNA TOR: _,.0),c;,..__ 5_______,.___ HED NO.: DS -2\
VALIDA TED BY:
----------- DATE: ,3/o,hr a) HED TITLE: /I rEw /Pt77"'1A' fl s:Et:~c-rc;~ COIVrlf'OL S NAt/E b) ITEMS JNVDLVED:
DISC1$._~E THurfB RoTAlf't' COJ!1.rrlfo~3 OA/ ~ SNuTOt,'<JN PANEt., :
**Mc v- Fw-~61 O
* ;v,ov-Fw-~5, S
- l'-f" \I - FW -;251 F
* .;1 ... C H-.P-.tC.
- . * ;t-CH-t°-~ D c) PROBLEM DESCR1PTJON AND 0700 PARA. NUMBER:
/'O/IVrE#'e l'l1VD/t:,.Tr'Dl'V5 A~E' Nl'OOEN (li,;,1.fl.( 5
'5f d 1) t::>A'AAJG-E / Putf Pte 'r/1/~E
- d) DAT A COLLECTION DESCRIPTION AND CODE NJMBE:R:
CoA/7/folS T/'-~/, t::JB5E~I/A'T'4!f1A,,,1 e) SP£CFIC t-1.JMAN ERROR.(1): f'~;t!C,N(o Ce11v,lfOI- ~N wltoAJ('; l°oS ,r~t,AJ e>.te /11/S/,lf/ TElfP~E TAT/~N
.OF P/"iES~IVT CDNTl't"I. l"'o~,r~O"-'*
- 99 .. 1
l Me~ l9D
- HC.D REPORT (CONTJNLJEO) -
- Sv~J:17'.~r .s,vvroo..,,., I-ED ND.,
PL.ANT UNIT t)S-9-l
~~5 d Q f) SUGGESTED BA.CKF"JT: (~
lf'~H"Y~ n91°E AS NECG'SS/11.A'
....y re EXPt:1.SE SuNTCH ;t-~o~ l°t'JNvTE,tS.
-~
HED NO. l) s --1 , 1
,. . VJRCINIA POWER CONTROL ROOM DESIGN REVIEW .2 OA O _ rJ 95 HUMAN ENGINEERING DISCREPANCY (HED)
RECOMMENDED RESOLUTION ST AT ION /UN IT ____ s*___v<._V"_r'_y.,.__U_r_1_; _s__(_l. *. .-"'2______ _1 MARK NO. ITEM DESCR_I_P_T-IO_N_ _ /J_LA_K_i_/i-./l-r_,V_.._,_(_t_&/l._f-_/_::,_v_J_1"----f-o-,-,-E'-(-k 4~"J CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) 0 rJ C D / o v- C o/e I r, . ,2 (' c o ~ j(J ,. r e W ~ I/ I I
- 1 COMMENTS:
ORIGINATOR _ _'i3_.__ F._._H_;_I/_ _ _ _DATE REVIEWED_ _1_--_q.....-____'F_5_ __
LABELS AND LOCATION AIDS 6.6 / LOCATION AIDS 6.6.6 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.6.6.1 NEED FOR LOCATION AIDS Operator performance can be enhanced through the use of location aids such as demarcation, color, and mimics. GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.6.6.2 DEMARCATION
- a. USE-Lines of demarcation can be used to:
(1) Enclose functionally related displays. (2) Enclose functionally related controls. (3) Group related controls and displays.
- b. CONTRAST-Lines of demarcation should be
- c.
GUIDELINE visually distinctive from the panel background . PERMANENCE-Lines of. demarcation should be permanently attached. COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.6.6.3 COLOR Color should be dedicated to specific functions or conditions throughout the control room in order for- the code to elicit the expected operator response. The color coding scheme should be used consistently throughout the control room. Refer to Guideline 6.5.1.6 for specific recommendations on the use of color .
- 6.6-24 *
*:"/;,.'~?'.~(-:**~/tt\' :*.J~\'.;:*, .;*
' 125**~
2'-4"
~ 5 3/4" I* 5 1/2" I 5 1/r I 5 1/2' 5 3/4' 1
~
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- Pl Pl I ~ r~>.
- I 1s 11 11 11 r::t .,:;!t~t(c'tJk: ~:'J~til ,~.
- ----~~- .
72
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[!j [!j f!J f!j CS 798 I II CS 79C CS 79D *
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L;_J ~ fi!, 12:. HJ Fo ON L'/ p~, oi:- 'P ~ C. se, &2.b:.. z...- G"-41.01 I I I FcA w E!J t?JI~ l----~----l=R:--~:zzzzzq I .
- 1:s!l 1:~11:;~1: 1::11:!11::; I.
Li----,--~~~;;;;J *',. ~-
- __ ,. c_o. - - - ~ - - - - -
I I
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- r. ,*.* /;f~<-*:'. ;;
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- 'f({\i
- ,:t~tj
- I 'al i\'.
**10* I ln T . ~:~-
iT I
~,..,
_l AUX SHUTDOWN PANEL ~ '~-.
- 1. CHARACTER HEIGHT=0.75", CHARACTER ~~TH=0.5",
STROKE WIDTH=0.125". Yi TYPE "s-JVi PANEL IDENTIFICATION _l_ .l*- -.- - - - - - - ~ _ [ _ 3" .... , 1/8"
. 3/32"
.r FIELD 1 { TD AUX FW PP ~1/16" FIELD 2 { SOV,-MS2028 DC2-2 Cl(T7 ..
19/32" T FIELD 4 *
- 1. FIELD 1: CHARACTER HEIGHT=l/8", CHARACTER WIDTH=S/64", GENERAL NOTES:
STROKE WIDTH=0.020". . 1. CHARACTER WIDTH SHALL BE MINIMUM 3/5 OF THE HEIGHT.
- 2. FIELD 2: CHARACTER HEIGHT=3/16", CHARACTER WIDTH=l/8", 2. CHARACTER SPACING: ONE STROKE WIDTH.
STROKE WIDTH=0.040".
- 3. WORD SPACING: ONE CHARACTER WIDTH.
- 3. FIELD 4: CHARACTER HEIGHT=0.080", CHARACTER WIDTH=0.050", 4. LETTERING FONT: FIELD 2-FOUR LINE HELVETICA, OTHERS-STROKE WIDTH=0.015". ENGINEERING GOTHIC.
- 5. FOR FURTHER DETAIL, REFER TO VIRGINIA POWER STD-GN-0036.
TYPE "S-1 "; CONTROL DEVICE NON SAFETY RELATED SWEC 14937.70 DC-88-26-2 _l_l- * - - - 3 " - - ~.. ,_[ 3/32" " 5/1s" I T~--------' pp DISCH PRESS 13 ~ ~/B
= f 3/32"
.--~------~~--.r--~-r------------lvl 3 FULL SCALE SKETCH - SH.1 NAMEPLATE STYLES FOR
~
2 AUX SHUTDOWN PANEL l:v CHARACTER HEIGHT=0.1250", CHARACTER WIDTH=5/64", SURRY POWER STATION STROKE WIDTH=0.020". 0 APPROVED FOR CONSTRUCTION UNIT NO. 2
"",ss,.,c=,,..,._or_o_c_-s=r:=~=-:TI=-;;,____----"=~="--"-'-==--+----VI-R_GI_N_IA_PO_WE_R___~ ~
TYPE "S-2"; CONTROL DEVICE S_TONE & *WEBSTER ENGINEERING COR~. DWG. ~ BOSTON, MASS NO. S8826-2-E-905 REV..~~I
*-----*- ------ * * * - - - - - - - *- - - - . --- - - DESIGNED BY _____ DRA\liN BYD.TITUS DSGN CHK'D BY CHK'D BY ______ J
,* ***- **., r ,*~ ~ , , ,( .,:*-~*,. 'fr*""*'< ~;.*,,--_. , .-. ,*:,,, ...
Il.9 CORRECTIVE ACTION EVALUATION CANO.: 9E CA DESCRIPTION: Provide pressurizer spray valve position indication w/ red/green lights. EQUIPMENT MARK NO. HEDNO. 1-RC-PCV-1455A,B 20A02045 1-RC-PCV-2455A,B 22A03206 Il.9.1 BED REVIEW - ORIGINAL FINDINGS HED No. 20A02045 - Required displays and indications missing from Control Room. (NUREG-0700, Sections 6.1.1.1.a, 6.5.1.1.b,e, and 6.5.4.1.g. HED No. 22A03206 - Lack of feedback indicating process/direction of parameter change. (NUREG-0700, Section 6.9.3.1.c.2) As identified during the original CRDR display surveys and through operator interviews, pressurizer spray valve position is not available in the control room. At present, the sole operator aid to determine spray valve position is implied by the output signal meter provided on each pressurizer pressure auto-manual control station. One potential cause of a low (or high) pressurizer pressure condition can be* attributed to a failure of either spray valve to respond to the pressurizer pressure control system demand signal. Since the control system does not provide feedback of actual valve position, there is no definitive manner to determine which valve has failed. The indicating lights being added by DC-88-29/30 will provide positive indication for the operator to determine a failed valve and enhance op~r response in initiating appropriate corrective action .
- DC-88-29/30 was not implemented.
Il.9.2 EOPs BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW lxlYES DNO DN/A RG-1.97 DYES IXINO DN/A The pressurizer spray valves are operated and verified Pressurizer spray valve position indication is not a closed in several EOPs including l-E-0, l-E-3, RG-1.97 variable. 1-ES-1.2. EPIPs DYES D NO Iii N/A LERs/IOERs DYES lxiNO DN/A Pressurizer spray valves are not used in performing No LERs were found concerning the pressurizer spray EPIPs. valve operation or position indication. AP,P. R DYES lxiNO ON/A HPES/STA DEV/SOER DYES lxlNO DNtA Pressurizer spray valves are not Appendix R safe No station deviations/SOERs were found pertaining to shutdown components. the operation of the pressurizer spray valves. ERF/SPDS DYES lxiNO DNtA TECH SPEC ITEM Ix! YES D NO D NIA
- Pressurizer spray valve position is not required in ERF or on SPDS.
VARS01B.B7S-l The operability of the pressurizer spray valves are defined in TS 3.1.A.3.a.
Il.9.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE i The pressurizer spray valves are used for RCS pressure control. The spray valves are operated and verified closed in several EOPs including l-E-0, 1-E-3 and 1-ES-1.2. The valves are controlled from manual-auto control stations on benchboard 1-1 and respond to the pressurizer pressure control system demand signal. The original HEDs identified that the pressurizer spray valve control stations do not include position indication. This reduces the ability of the operator to determine if a valve has failed. The failure (open) of a pressurizer spray valve may result in a decrease in reactor coolant system pressure. During plant conditions, when RCS pressure is decreasing, by procedure, the operators through a process of elimination identify the cause of decreasing pressure. This includes verifying spray valve controller demand is zero, monitoring the rate of RCS pressure decrease, observing pressurizer spray valve temperature indication (TI-1451, 1452), verifying containment status and confirming pressurizer PORVs/block valve status. Once the decrease in RCS pressure is determined to be caused by a failed open pressurizer spray valve, RCPs A & Care selectively secured. Safety Significance The pressurizer spray valves are safety related for RCS system pressure boundary and designated non-safety related with special regulatory significance for pressure control. The valve actuators are non-safety related. The pressurizer spray valves are not required to function to mitigate the consequences of accidents. Potential for Error The potential for error with no pressurizer spray valve position indication is increased based on the operator's ability to determine plant status and perform required actions. However, the addition of red/green position
- indicating lights would not provide additional information to the operator in the event the valve failed in mid position, as both indicating lights would be illuminated. No station deviations were found concerning the operation of the pressurizer spray valves. In addition, the procedures and corrective actions described above reduce the potential for error.
Consequences of Error - The consequences of error due to the pressurizer spray valves not having position indication would be a delay in operator response. The corrective actions taken by the operators during the conditions of a failed pressurizer spray valve ensures no risk of injury to the public/plant personnel or damage to equipment. Il.
9.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussions, sufficient infonnation is presented to justify not implementing CA9E. The EOPs direct the operators to perform specific tasks and take appropriate corrective action to a pressurizer spray valve failure to recover from plant conditions and ensure that there is no risk of injury to the public/plant personnel. In addition, the Surry simulator has the capability to override the pressurizer spray valve hand controller and simulate valve failure. This provides the operators with specific training in the response to the plant conditions described above. The reassessment process for this corrective action included a qualitative analysis to determine if the benefit of the proposed corrective action was commensurate with the total projected cost of the modification. Based on this evaluation, it has been determined that there is no appreciable benefit to the improvement of plant safety, operations or human engineering principles, which justifies the projected high cost of the modification . VARS01B.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D IEOPs/EPIPs D I
.IERF/SPDS D I
- IQ-LIST RG-1.97 D I
D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
88/23/85 ~ 7 SURRY UNIT 0 CODE A HOHD -I*A~. ,..,
.,, L, '- *-. .... ...r 0 ~:,::;:.- IHI/,
ASSES&E~T LAST REYIEw TITLE flESP()cSlBILITY STATUS DATE 20A0.2eo4S REIMrtED DISP'..AYS AND INDICATIONS ARE ,.ISSI"6 FRO!! CR, I -1 87/11/85 tt.- eRROR: D8.AY /ERROR lh CP. RESP0NS£. - tH PROBI-EI! DESCRl?TION: VISIA DISPLAY /JNDICSITir,.i NECESSARY TD f!EET TASK R@i.lIRBENTS NJT PRESENT IN CR. 87N PARASRAP!-1 NUJllliER: fi,1,1,1,A Ei.5.1.1.l! 6,5,1,1,E 6.5.4.1.6 S!JSSESTED BAC~F;i: PRL!Vl~ CR ~lih Y!SuA.. DIS?i.AV/l~DICATION LISTED, fff D!SPCISITIOt.: .
/ wCU"i:.t,;TaJ lr.-v.:,._vli.3 fll..:i Dt-PilESS WE TO ~ Cf lNillC Li W STATuS. PROVIDE POS flNAi.Cl6 W POSli lliDIC. e-100r;.
DATA COi.:..ECTli:,S DESCRIPTI~ AhD CODE fUUEk: T?-5. l Dl~I.AYS &,iii\l:Y
- - TP-9.2 \IERlFICATIOH 11iD ~IDATit'J,1 REIIIA~S:
Pl-e77-SS. <SEE Pl~ 1~~3ai&ll. ITEP.S I!WO..~: MR-< ~R LOCATlO!I ~tiii ~ SYSTEII! PRZR SPRAY Y ff hl1T Ill lNY FILE *
\
_,.'- 1 c--~.:.......,... L.. -::. .
/
""l- c;, ...p Q_ /\
\
.....:> *' i, I.*~ ,
TP-5.l OISPL.AYS l May 1983
- APPENDIX 89 HUMAN ENGINEERING DISCREPANCY (HED) REPORT
'SLJt:.1!..Y !uv,r~
PLANT UNIT I } J,
/
. (
ORIGINATOR: LJ '-.r~,*;) I;_ tJ. g.u
\
HED ND.: p,- - J 7 VALIDATED BY: . DATE: r G.-,.,,..S_ ), 0 .' ' 2t4.
.* * . I ').* * . L . ...,.
a) HED TITLE: __J_,-:."J 1 ~..>,..*.,'-)-I' .,A...,v;.. . --~- "'T J°:>J.>.-y1 A...,.,;, ; -, ... .Jo. *
,,i~/'e::+-v,,"i:: ~ :,*}v--J... r c.;:;tA..~\....c /l ,-.--..~~
I b) ITEMS INVDL VED:
~ WJ....0...Jv..;.); J..-:v- .
- *c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER:
c... K c,,f".iTJ.-..a . c,,,-~ /.,._;:;,; f"~~ ~ .,vv-..J..,,_,,...w,i_,,j_,,J;...,:.,,
,-{°"i /"U-r~ +-u ~~ arJ)J.).A
-~....,.,_;J~,_, fQ-tJ)....~ ~ . &J~~~ /c.'*1~
1)./Jv. U1--*4 >>..,_v.- ~ /L.L-<:Jj_,..,~ .-c'~-<-0~= U c0~ ~ b, ~- \.!. jj d) DAT A COLLECTION DESCRIPTION AND CODE NUMBER:
&')J~u c i - J ~ -! PS-._ I 13 ,~ (._~ ~)
e) SPECinc HUMAN ERROR(s): j'tu~ ~ Q._, ~r.j O>-----~ I c*1../ JU~ .A~ ~ . r* ~-t.\.tAJ:r , .:, ' ...---u-~~ ! - . . ~ d..JJ~ L7c *.::A),*. J_
~~~~~~M *
- B9-l
TP-5.l DISPLAYS l Mey 1983
- APPENDIX B9 HED REPORT (CONTINUED)
;-\J(Z.f~.Y!utv,rr PLANT/UNIT 1 $;) HED ND.: p:r_/7._-7 f) SUGGESTED BACKFIT:
~-t ;.).... _:u!. "'v,_ ...>~:._rMJ..J~.r~~ /~_,v...,~) °'t"..t!l
-* *-~fr _,t.,_,"'")~*-~ J;l/\ ~.,. .. e ~ ~ _)..,,-4:X.t..J. c...~
L)......!:.._. n n ~*~).--...J ,.-,.,:l~__u.},- u: ~ A _..r,_,_j_,_,__JJJ.,.,..:;,;-
. . 4 . J ~ ~ /.J:e?:,J~ o.--J. / ~- L: f ~ ~
-~b.l}~~l~ ~~4~~
g) REVIEW AND DISPOSITION:
- B9-2
\ ---r' I I
(' .f; .*
.. .. . - "\ - - -r- . . .Y'1 .i.......__* *
~ ~~ ~X-~A.l~--
** I
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. r
.*I I
i _ .. __ i. fv\A tN FvJ. ~ ~c,.. *_13y P..fi-S ~ ___. :vA L-"vE _.-.. p_(.....o-* w_-_!...: **-** -.:_ *-* __
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177 TP-1.2 ANll-RCPOtwETRICS l Mey 198)
- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (I-ED) REPORT b) ITEMS INVOLVED:
s ..u__ oJT~....,JJ .).,~.
- l*,-7 . cs
- TP-1.2 ANTl-ROPOtCl'Rl 1 May 198:5
- H APPEND(~D)
ED REPORT
- s. v ~ ,z vL~~7 ~rr I ~ :,,
I-ED N0.1
. P;;r:- ::lO
- 89-2
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- SJRRT UNIT 2 CODE A
~IBILITV ASSESSIIENT STATUS eb/23/85 LAST REVIEW DATE PASE S TITLE
~ LACi< Cf FEEDBP.D< !NDICATIN6 PROCESS/DIRECTI~ CF PARA!':ETER [)RiSE, *I -1 17/11/BS
~ t.RROR:
DELAY/ERi!ilR lN D P ~ H* PROli'- DESCRIPTION: THE Ut:i B~ CTRL ACTIYATIOt. I u..Tl~TE SYS STATE I Nl HIED FEEDBOCK lNDIC'.ATlNS PROCESS & DIRECT IF PA~ DtEE 070\1 PARAGRAPri ~!'<:
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- b) JTEMS INVOLV£D: .
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- c) PROBLEM OCSCRIPTJON AND D700 PARA. NUMBER:
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- B9-l
. . .. )17 APPENDIX B9 HED REPORT (CONTINUED)
-- Surrv1 _1.
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Hto No.: C!
- 2 D f) SUGGESTED BACKf"IT:
- 9) RtVItW AND DlSPOSITJON:
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'. . VIRGINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
RECOMMENDED RESOLUTION STATION/UNIT Su. r r v I {j~ ,* f .r I g 2. MARK No. Pc v -11ss A ~ a : Pc r-.2*1s-r IJ J. l
)
ITEM DESCRIPTION Pres.sin-- i r of' I'"' s pr~ ~ V,z Iu f ,L 0 I
~
CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS: Pr-ovide* Vn~lo&. vol11e Pp,i1/o.,_ IQ,, frtD.S.!().Y;~~r COMMENTS: - - - - - - - - - - - - - - - - - - - - - - - - - - ORICINATOR _ _ t._. _F._._H_;_f/_*___ DATE REVIEWED 7- IO - E1 b
. CONTROL ROOM WORKSPACE 6.1
- GUIDELINE 6.1.1.1 ACCESSIBILITY OF INSTRUMENTATION/
N/A Yes GENERAL LAYOUT 6.1.1 COMPLIANCE CHECKLIST No Reference/Comment EQUIPMENT
- a. PRESENT IN THE CONTROL ROOM-Control room instrumentation and equipment should *.
include all controls and displays needed for ( 1) detection of abnormal conditions, and (2) bringing the plant to a safe shutdown condition. I
- b. ARRANGED TO FACILITATE COVERAGE-Operators should not have to leave the primary operating area (see Exhibit 6.1*1) to attend to control room instrumentation on back panels during operational sequences in which con-tinuous monitoring or the timing of control actions may be critical. I I
BACK PANEL AREA Exhibit 6.1 *1. The primary operating area is physically arranged such that it can be visually accessed from a central point within that area. 6.1-1
.*. -., VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5.1
- GUIDELINE 6.5.1.1 a.
INFORMATION TO BE DISPLAYED TASK ANALYSIS-An11Ysis of operator tasks N/A COMPLIANCE CHECKLIST Yes No Reference/Comment in relation to system engineering and system functional objectives is recommended as the surest means of establishing operator infor-mation requirements.
- b. COMPLETENESS OF INFORMATION-Visual displays provided in the control room should give operators all the information about system, status and parameter values that is needed to meet task requirements in normal, abnormal, and emergency situations.
- c. UNNECESSARY INFORMATION - Efficient performance requires not only display of all needed information but also avoiding the display of extraneous information in the prime operating area.
- d. REDUNDANCY-Redundancy in the presen-tatiqn of information items should be limited to cases* where needed for backup or to avoid excessive operator movement.
- e. DEMAND INFORMATION VERSUS STATUS INFORMATION-Demand information shows that equipment has been commanded (by control settings or otherwise) to a particular state or level. It shows only what is.
demanded-not what is actually being realized,. Status information shows the state or level actually in effect. ( 1) To prevent operator confusion, it is essential that displays be identified as to whether they reflect demand or actual status. ' (2) Visual display of actual system/equipment status shou Id be displayed for al I important parameters. 6.5-1
VISUAL DISPLAYS 6.5 GRAPHIC RECORDERS 6.5.4 COMPLIANCE CHECKLIST N/A Yes No Refentnce/Comment 6.5.4.1 GENERAL CHARACTERISTICS OF GRAPHIC RECORDERS (Cont'd)
- f. EASE OF ROUTINE REPLENISHMENT-Recorder design should permit quick and easy :
replenishment of paper and lnk. .
- g. USE-As a general rule, recorders should be.
used to record trend information and material which may be needed for later reference.
- h. PLACEMENT OF RECORDERS-As devices which must be verified and attended by the operator, graphic recorders should in principle be located within the primary operating area rather than on back panels.
- i. PAPER-SPEED ADJUSTABILITY-Not only I should high paper speed option be provided to run out records for detachment, but a selection of lower speeds should be available to permit .
adjustment of the
- time scale so that rate-of- I .--~.
I i change information can be indicated. ! . . : *.../
. *./
- j. ANNOTATION-It should be conve_nient to annotate recordings with date and time II markings, with paper speed if varied from normal, with parameter identification, or with any other relevant information.
- k. VISIBILITY-Recorder design should ensure that all data will be visible through the window of the recorder and not require open-door operation to expose it.
6.5-26
-** GUIDELINE CONTROL-DISPLAY INTEGRATION COMPLIANCE CHECKLIST 6.9 DYNAMIC CONTROL-DISPLAY RELATIONSHIPS 6.9.3 . ~ :..:_ _,,..
6.9.3.1 GENERAL MOVEMENT RELATIONSHIPS Y;*ic response of a display to control movements
;,i'1,,::id be consistent, predictable, and compatible with the operator's expectations. The following principles apply to general movement relationships.
- a. ROTARY CONTROLS-Rotary controls should turn clockwise to cause an increase in parameter value. The associated display movements should be as follows:
( 1) Linear scales, up or to the right. (2) Digital displays, increasing in value. (3) Strings of indicator lights, bottom-to-top or lefMo-right. (4) Circular meter pointers, clockwise.
- b. LINEAR CONTROLS-Linear controls should move up or to the right to cause an increase in parameter value. The associated display relationships should be:
(1) Linear scales, up or to the right. (2) Digital displays, increasing in value. (3) Strings of indicator lights, bottom-to-top or left-to-right.
- c. DISPLAY RESPONSE TIME LAG-In some cases there will be a time lag between the actuation of a control and the resulting change in system condition. That condition should be reflected by displays in real time.
( 1) There should be no time lag between system condition change and display indication. (2) When there is a time lag between control actuation and ultimate system state, there should be an immediate feedback indi-cation of the process and direction of parameter change .
- 6.9-12 .:_,;
NUMBER PROCEDURE TITLE REVISION 7 l-E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 14 of 21 STEP ACTION/EXPECTED RESPONSE ,..._~~-- RESPONSE NOT OBTAINED....-~~~~~~--
- 21. CHECK PRZR PORVs AND SPRAY VALVES:
a) PRZR PORVs - CLOSED a) IF PRZR pressure* less than 2335 psig, THEN manually close PORVs. IF any valve can NOT be closed, THEN manually close associated block valve. I!'. block valve can NOT be closed,~ GO TO l-E-1, LOSS OF REACTOR OR SECONDARY COOLANT. b) PRZR spray controls - DEMAND AT b) IF PRZR pressure less than ZERO 2235 psig, THEN' manually close valves .
*** .-_i::,, ..
IF valves can NOT be closed,
.Ilifili stop RCP supplying failed spray valve:
- A RCP for l-RC-PCV-1455A
- C RCP for l-RC-PCV-145SB
~
NlHBER PRfXEIXJRE TITLE REVISION EP-1. 00 REACTOR TRIP/SAFETY INJECTION 1.03 PAGE p R ~>J , ov£ Is.SUE: EoP 9 of 15 STEP ACTION/EXPECTED RESPONSE ......~ ~ - - - f RESPONSE NOT OBTAINED..,...~~~~~~- 19 CHECK PRZR PORVs AND SPRAY VALVES: a) PORVs - CLOSED a) IF PRZR pressure less than 2335 psig, THEN manually close PORVs. IF any valve can NOT be closed, THEN manually, close its block valves. IF block valves can NOT be closed, THEN GO TO EP-2.00, LOSS OF REACTOR OR SECONDARY COOLANT, STEP 1 *. b) PRZR spray valves - CLOSED b) IF PRZR pressure less than 2260 psig, THEN manually close valves. IF valves can NOT be closed, THEN stop RCP(s) supplying failed spray valve(s). NOTE: Seal injection flow should be maintained to all RCPs. 20 CHECK IF RCPs SHOULD BE STOPPED: a) CHG/SI pumps - AT LEAST ONE a) Do NOT stop RCPs. GO TO RUNNING Step 21. b) RCS subcooling - LESS THAN 25 b) Do NOT stop RCPs. GO TO (70] op Step 21. c) Stop all RCPs d) RCS pressure - LESS THAN 1575 d) GO TO Step 21. PSIG e) Close miniflow recirc PREVio us
NUMBER PROCEDURE TITLE REVISION 6 l-E-3 STEAM GENERATOR TUBE RUPTURE PAGE
- STEP ACTION/EXPECTED RESPONSE i---~~--4 15 of32 RESPONSE NOT OBTAINED.,__~~~~~~--.
- 18. __DEPRESSURIZE RCS TO MINIMIZE BREAK FLO'W AND REFILL PRZR:
a) Normal PRZR spray - AVAIIABLE a) GO TO Step 19. Observe CAUTION prior to Step 19. b) Spray PRZR with maximum available spray until PJ:ri of the following satisfied:
- PRZR level - GREATER THAN 731
[651]
- RCS subcooling based on CETCs
- LESS THAN 3o*F [85~F]
- BOTH of the following exist:
- 1) RCS pressure - LESS THAN RUPTURED SG(s) PRESSURE
- 2) PRZR level - GREATER THAN 111 [421]
c) Close PRZR normal spray valves c) Stop RCP(s) supplying failed open spray valves:
- A RCP for 1-RC-PCV-1455A
- C RCP for l-RC-PCV-1455B d) GO TO Step 21. Observe CAUTION prior to Step 21
NUMBER PROCEDURE TITLE REVISION 6 1-ES-l. 2 POST LOCA COOLDOWN AND DEPRESSURIZATION PAGE 13 of 23 STEP ACTION/EXPECTED RESPONSE .._..~~-- RESPONSE NOT OBTAINED i--~~~~~~--. CAUTION:
- If all RCP seal cooling had been previously lost, the affected RCP(s) should NOT be started without prior status evaluation.
- On natural circulation, RTD bypass temperatures and associated interlocks will be inaccurate, NOTE: RCPs should be run in the following order of priority to provide PRZR spray: C, A.
- 19. CHECK RCP STATUS:
- a) RCPs - AT LEAST -ONE RUNNING* a) Do the following:
- 1) Establish conditions for starting an RCP IAW l-OP-5.2.1, STARTING ANY RCP.
- 2) IF conditions can be established, ~-start one RCP AND GO TO Step 21.
- 3) lI an RCP can NOT* be started, THEN GO TO Step 20.
b) Stop all but one RCP c) Close spray valve(s) on stopped RCPs d) GO TO Step 21
PROGRAM HPT21516 Q-LIST
SUMMARY
REPORT 03/31/92 17:oz PAGE 238 STATION: SURRY PONER STATION VERIFIED COMP QA CATEGORY COMP QA CATEGORY COMP QA CATEGORY QA FUNC DEFINITION FUNC DEFINITION FUNC DEFINITION REFERENCE ASSOCIATED COMPONENT ID. CAT il'IPTS ID. NOMENCLATURE 1 1 2 2 3 3 DRAHING COMPONENT ID PC-1444C/R SR 01-RC -PCR -1444C INPUT MODULE, CONTROLLER CNVT 5.1.4.A 5965034 01-RC -PC -1444C PC-14440/R SR 01-RC -PCR -1444D INPUT MODULE CNVT 5.1.4.A 5965034 01-RC -PC -1444D PC-1445A/R SR 01-RC -PCR -1445A INPUT MODULE . CNVT 5.1,4,A 5965D34 01-RC -PC -1445A PC-1455A/R SR 01-RC -PCR -1455A INPUT MODULE, I/V CNVT 5.1.4,A 5965D35 01-RC -PC -1455A PC-1456A/R SR 01-RC -PCR -1456A INPUT MODULE, I/V CNVT 5,1,4,A 5965D35 01-RC -PC -1456A PC-1456C/R SR 01-RC -PCR -1456C INPUT MODULE, I/V CtlVT 5, 1,4.A 5965D35 01-RC -PC -1456C PC-1457A/R SR 01-RC -PCR -1457A INPUT MODULE, I/V CNVT 5.1.4.A 5965036 01-RC -PC -1457A PC-1457C/R SR 01-RC -PCR -1457C INPUT MODULE, I/V CNVT 5.1.4.A 5965D36 01-RC -PT -1457 PC-1458/R SR 01-RC -PCR -1458 INPUT MODULE CNVT 5.1.4.A 5965D34 01-RC -PC -1458
- 472/R NSQ 01-RC -PC -
0 -RC -PCV -11i55A ODULE, I/V VALVE, PRESSURE CONTROL CNVT RCPB 5.1.1.H 5965D51 11448-FM-86B 01-RC -PC -1472 01-RC -E -2 PCV-RC-1455A SR 11448-FH-86B S1 01-RC -E -2 CV-RC-1455B PCV-RC- 4 SR 01-RC -PCV -145 B 01-RC -PCV -1455C VALVE, PRESSURE CONTROL VALVE, PRESSURE CONTROL RCPB 5. RCPB 5,1.1.A *" 11448-FH-86B 01-RC -PCV -1456 PCV-RC-1456 SR 01-RC -PCV -1456 VALVE, PRESSURE CONTROL RCPB 5.1.1.A 11448-FH-86B 01-RC -PCV -l455C PCV-RC-1473 - C ;ecy - ~... VALVEz PB~~~YBE_ oNTRoL YPB 5.1.3.H ll448-FH-86B 01-RC -HCV -1550 PCV-RC- 455A 01-RC -PCV0-1455A OPERATOR, DIAPHRAGM VLVC 5. 11448-FH-86B 01-RC -PCV -1455A PCV-RC-14558 01-RC -PCV0-1455B RATOR, DIAPHRAGM .1.1.A 11448-FH-868 01-RC -PCV -1455B C OPERATOR, DIAP VLVC 5. ll448-FH-86B 01-RC -PCV -1455C PCV-RC-1456 SR 01-RC -PCV0-1456 OPERATOR, DIAPHRAGM VLVC 5.1. LA 11448-FH-86B 01-RC -PCV -1456 PCV-RC-1473 SR 01-RC -PCV0-1473 OPERATOR, DIAPHRAGM VLVC 5.1.2,H 11448-FH-86B 01-RC -PCV -1473 PI-1402 SR 01-RC -PI -1402 INDICATOR, PRESSURE INDI 5, 1,4.8 5965D41 01-RC -PT -1402 PI-1402-1 SR 01-RC -PI -14021 INDICATOR, PRESSURE INDI 5.1.4.B 5965D41 OI-RC -PT -00065 PI-1404 SR 01-RC -PI -1404 INDICATOR, PRESSURE INDI 5.4 RCPB 5.1.1.A 11448-FH-86A 01-RC -PT -1449 PI-1405 SR 01-RC -PI -1405 INDICATOR, PRESSURE RCPB 5. f.1.A INDI 5.4 11448-FH-86A SZ PI-1444A SR 01-RC -PI -1444A INDICATOR, PRESSURE MESI 5.1.4 IND! 5.4 5965034 01-RC -PT -1444 PI-1445 NSQ 01-RC -PI -1445 INDICATOR, PRESSURE tlESI 5.1.4 INDI 5.4 5965D34 DZ-RC -PT -14445 PI-1458 NSQ 01-RC -PI -1458 INDICATOR, PRESSURE MESI .5.1.4 INDX .5,4 5965D34 01-RC -PT -14588 PI-14588 SR 01-RC -PI -14588 INDICATOR, PRESSURE MESI 5, 1.4 . INDI .5,4 5965D34 01-RC -PT -1458B PI-1472 NSQ 01-RC -PI -1472 INDICATOR, PRESSURE INDI 5.2.3 5965051 01-RC -PT -1472 PM-1402 SR 01-RC -PH -1402 ISOLATOR, SIGNAL EISO 5.1.4.A 5965041 01-RC -PT -00065 PM-1403 SR 01-RC -PH -1403 ISOLATOR, SIGNAL EISO 5.1.4.A 5965D41 01-RC -PC -14038 'PH-1444 SR 01-RC -PH -1444 ISOLATOR, SIGNAL EISO 5.1.4 5965D34 PH-1444G SR 01-RC -PH -14446 SUMMATOR, SIGNAL SUHH 5, 1.4 5965034 01-RC -PH -1444J Pl1-1444H SR D1-RC -PH -l444H SUMMATOR, SIGNAL SUMH 5.1 .4 5965D34 01-RC -PCV -1455A PH-l444J SR 01-RC -PH -1444J SUMHATOR, SIGNAL SUMH 5.1.4 5965D34 D1-RC -PCV -1455B PH-1444K SR 01-RC -PH -l444K SUMHATOR, SIGNAL SUMH 5. 1 ,4 5965D34 Ptl-1445 SR DI-RC -PH -1445 SUMHATOR, SIGNAL SUMH 5.1.4 5965034 DI-RC -PC -1445A PM-1451A SR DI-RC -PH -t45IA CONTROLLER, LEAD LAG CTRL .5. t .4.A 5965D36 OI-RC -PC -l457C PH-1455 SR DI-RC -PH -1455 ISOLATOR, SIGNAL IEISO 5.1.4.A 5965D45 01-RC -PC -1455A
- PH-1455A SR 01-RC -PH -1455A CONTROLLER, LEAD LAG CTRL 5.1,4.A 5965D35 01-RC -PC -1455C
11.10 CORRECTIVE ACTION EVALUATION
- CA NO.:
CA DESCRIPI'ION: EQUIPMENT MARK NO. lOE Perform study of annunciator alarms. BED NO. Multiple (See II.10.1) 11.10.1 BED REVIEW - ORIGINAL FINDINGS HEDNos. 20002120 20A02103 22A02906 22A02115 20002121 20A02106 22A02110
- 22A02116 20002122 20A02119 22A02111 22A02123 20A02101 20A02125 22A02112 20A02302 20A02102 20A02903 22A02114 20B03005 See Attachment 10. lA for individual HED titles
- 11.10.2 BED REASSESSMENT - PROCEDURES/PROGRAMS ~VIEW EOPs mYES ONO ON/A Associated alarms are used in the EOPs, including l-E-0, 1-FR-C.1 RG-1.97 DYES mNo DN/A Alarms are not used for Control Room RG 1.97 Monitoring EPIPs mYES ONO ON/A LERs/IOERs DYES IXI NO D NIA The loss of all main control board annunciator No LERs/lOERs were identified regarding alarms and plant computer during a transient the main control room alarm system is classified as a site area emergency; without a transient, alert APP.R DYES IXI NO ON/A HPES/STA DEV/SOER DYES IXINO DN/A The control room alarm system is not an Appendix "R
- Station deviation 1-90-0465 was found concerning Safe Shutdown System the control room alarm system, however it was associated with the silence reset pushbutton on a local beat tracing panel in the aux. bldg.
ERF/SPDS DYES IXI NO D NIA TECH SPEC ITEM DYES IXINO DN/A The plant annunciator system is not part of The plant annunciator system is not identified in ERF/SPDS the station technical specification VARS01C.B7S-l
ATTACHMENT 10.lA HEDNo . Description 20A02101 Annunciator tile engraving too small _ 20A02106 Annunciator tile legends ambiguous or too wordy 22A02112 Inadequate letter height on annunciators 22A02114 Inadequate width-to-height ratio on annunciator characters 22A02115 Inadequate spacing between annunciator tile lines 22A02116 Silence controls for annunciators 20A02103 Annunciator tile placement not consistent between the units 20A02119 Lack of tile grouping by system function _20002121 No reflash capability on annunciator system 20002122 Annunciator tile does not bum steadily when there is a flasher failure 20A02125 No auditory signal priority coding of annunciator alarms 20A02302 __ . System/equipment status is inferred by indicator light being off 20A02903 No audible alarm cleared signal for annunciator system 20B03005 No silence function on annunciator response controls 22A02110 Number of tiles per annunciator light board exceed 50 22A02111 Dual meaning tile legends 22A02123 No printout for multi-input annunciator 22A02906 Alarms for units sound alike 20002120 No distinctive coding for extended duration of illumination during normal operations 20A02102 Annunciator tile illuminations indicate normal conditions.
- V ARS01C.B7S-l
11.10.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- A Type II annunciator study was performed to evaluate nineteen HEDs identified by the CRDR Program, and determine a means of correcting the discrepancies. The results of the Type II Study indicate that the replacement of the system would resolve the nineteen identified discrepancies and provide a more reliable, adaptable and maintainable system.
Subsequent to the Type II Study, a cost benefit/analysis was prepared to explore alternate solutions. The Type II Report provides justification for not performing modifications for the following HEDs as summarized below: 20002120 No distinctive coding for extended duration illumination during normal operation. This HED is presently being corrected by station operations via Admin. Procedures. 20A02102 Annunciator tile illuminations indicate normal conditions. This HED has been addressed by station personnel via the EWR process. 22A02110 Number of tiles per annunciator light board exceed 50. NUREG-0700 did not exist when Surry's annunciator system was specified and manufactured. However, with 64 tiles per light board, the intent of this HED to provide segregation of annunciators into groups is met. No additional action is required, only a complete annunciator replacement could resolve this HED. SEE ATTACHED PAGE, II.10.3 continued 11.
10.4 CONCLUSION
S/RECOMMENDATIONS Based on the data provided and costs associated with the total replacement of the existing alarm system, it is more cost effective to enhance the existing alarm system. The proposed enhancements will improve operator interface by
- 1) annunciator tile replacements, relocation, and 2) addition of master silence .
- Recommend the following HEDs groups A-C to be corrected:
HED Group A 20A02101 Annunciator tile engraving too small 20A02106 Annunciator tile legends ambiguous or too wordy 22A02112 Inadequate letter height on annunciators 22A02114 Inadequate width-to-height ratio on annunciator characters 22A02115 Inadequate spacing between annunciator tile lines. The above five HEDs are closely related and can be discussed concurrently. To resolve the above HEDs the annunciator tiles would need to be re-engraved to enlarge lettering that is too small, too ambiguous or too wordy. The re-engraving would provide adequate spacing between annunciator lines and correct engravings where width-to-height ratios were inadequate. Where possible, all re-engravings would be completed under STD-GN-0036, titled, "Equipment Labeling and Tagging" which will provide consistency between tile engravings. It should be noted that the study identified a problem with the physical size of the actual annunciator tile. According to the study, the existing tile size is too small to conform to the lettering guidelines as outlined in NUREG-0700. However, the study did outline and detail a compromise which uses new letter heights and space dimensions and a standard set of annunciator acronyms. SEE ATTACHED PAGE, 11.10.4 continued
- VARS01C.B7S-1
ATTACHMENT 11.10.3 (continued) 11.10.3 NUREG-0700 REVIEW - TASK ANALYSIS/EOPs/SAFETY SIGNIFICANCE/FEASIBILITY WALKDOWN 20A02903 No audible alarm cleared signal for annunciator system. No additional action is required, this item has not
.been identified by Operations as being a significant problem and the operators are trained not to rely on a "ringback" feature. During accident conditions, the additional audible tones could actually add confusion to the control room operators and delay corrective actions.
22A02302 System/equipment status is inferred by indicator light being off. Burned out alarm tile bulbs which would falsely indicate a normal status, have been addressed by the requirement that each oncoming operations shift conduct an annunciator lamp test at the beginning of the shift and replace all burned out bulbs at that time.
- 20A02125 No auditory signal priority coding of annunciator alarms. Although modifications could be made to add different tones between new alarms, cleared alarms and also different audible tones for establishing levels of alarm priority; the study questioned the value of this modification because the number of different audible tones could actually slow the operator's response time if there were too many sounds for the operator to differentiate. _This could actually create a new HED which would obviously be counter-productive to this effort.* Therefore, no work will be required on this item. However, HED 22A02906 will address the audible tones between Units 1 and 2.
20002122 Annunciator tile does not bum steadily when there is a flasher failure. This item has not been identified by operations or maintenance personnel as a problem area. Therefore, no work will be required on this item.
- Periodic and planned maintenance of the annunciator system will continue to detect .component failures.
20002121 No reflash capability on annunciator system. The present system design combines multiple field contact (parallel or series combinations) in remote field locations and sends a single input (either open or closed) via a two conductor cable to the annunciator input cabinet. Therefore, if reflash capability were to be added, each field contact must be routed individually to the annunciator input cabinet resulting in many new cable runs to the control room. This scenario would be applicable for either the existing system or for a new annunciator system. Also, included in Exhibit A6 of the subject study is a Multiple Alarm Input Analysis which studied all multiple input alarms and determined that the present system is designed such that no reflash feature is required. This is due to the fact by design, that the control room operator normally has independent indication of the individual alarm input parameters in the control room. 22A02111 Dual meaning tile legends 22A02123 No printout for multi-input annunciator These two HED's both deal with annunciator tiles which have more than one possible meaning for the operator to discern. For example, the alarm which is engraved "BA TK lA HI-LO LVL" alerts the operator to a level problem in the boric acid tank. The operator now must ascertain if the level is either** high or low by checking the appropriate level indicator in the control room. This action has been and remains an acceptable solution in these situations. For those instances where no indicators or system parameters are available for the operator to check, alarm response procedures are provided such that the operator will be able to determine which input may have caused the annunciator to alarm followed by sending an operator to the remote location to verify the problem and perform corrective action. 22A02906 Alarms for units sound alike Presently, both Unit 1 and Unit 2 main control board annunciator system provide an audible tone when in the alarmed condition making it difficult to ascertain which unit is in the alarm condition. This could
- VARSOl C.B7S-l possibly create confusion between the operators and potentially slow the operators' response time. Based on discussions with Operations & Simulator Support personnel, and one location of each unit's annunciator horn, it has been determined that confusion does not exist and operator response is not reduced.
ATTACHMENT 11.10.4 (continued) 11.
10.4 CONCLUSION
S/RECOMMENDATIONS
- Proposed Solution - The annunciator tiles will be re-engraved which will significantly improve their visual characteristics.
HED Group B 20A02103 Annunciator tile placement not consistent between the units Lack of tile grouping by system function 20A02119 The above two HED's both involve relocation of annunciator tiles and thus will be discussed together. As indicated, a lack of consistency in regard to tile placement exists between the units which can lead to confusion and also an improvement could be made to relocate tiles closer to the systems for which they represent. Proposed Solution - Relocate tiles accordingly. Once an agreement is reached between Engineering and Operations as to the best tile relocation arrangement, the modification will require internal wiring changes to the annunciator logic cabinets as well as physically moving the annunciator tiles. No new cables will be required for this change. HED Group C 20B03005 No silence function on annunciator response controls Operators are unable to silence the alarm audible during transients. The noise from a spurious alarm can cause confusion and distraction to an operator during transients. Adding the silence feature will allow the alarm tile to continue to flash after the audible alarm has been silenced.
- Proposed Solution - The existing annunciator system .will be modified to install a silence feature using hardware (audible driver card, speakers, etc) available from the original equipment manufacturer which is compatible with the operation/function of the existing annunciator system.
V ARS01C.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST D RG-1.97 D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
- ./ 0 Itl.7;;-
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tll"1N EN6l~RIN5 DISCiE~Y fa:PORT 88/23/B5 PAS: 24 SURRY ~IT 8 CODE A ASSESSP!eNT ~1' REVIEW TITLE RESPDhSlB!LIT~ STATLS DATE ~1'!6 APHJNCIATOR TILE LESENDS MBISUOOS/TOO WORDY, II -5 15/28/85
~ ERROil:
l'RY C&f.JSE DELAY/ERRORS l~ OPER~TOR Rc:S?ONSE, H+ PRO&..EM DESCRIPTIDh:
~IATDR TlLE. L.EixkDS ~RE APIBltiAlJS ~ TOO l<<JilDY.
l!7lile PARASR/lP!i Nll!DER: 6.3.~.4.A . SLJ,36£STEi) BACl<Fli: PERF!J~~ "1t., STuDY 70 ucTEil111lrc CuRRi:CT WORl>lN& FO!! liAPID/IUORATE CCW,RcHENSio,j OF TILE IIESSAGES. RELABEL TILES DISPOSITI!ltl:
/DcFER, EVA..UATED AS wuoiS'!-cAS: &:c~Rlu, ht~ TO LOOK ATEA Tli.E I.Ju>ER Dc.1AlLED ~ STANDAilDIZATlllti/LJ,?SRADE PROO; ,
DATA CDU.£CTil:'1 DESCRIPTIOh Ali>> CODE ~II: TP-ti. l LA&:!.& AND LCICAl i£Jt,; AIDS Sll!IYCY T?-3,1 ~ICIATO~ SYSTEl!S REViE&I
*REl'RRKS:
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f . 177 TP-6.l LABELS ~ LOCATION* AIDS 1 May 198:5 APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT
---..ED NO.: P~- ~ s::
~ rl~,*1,rir 04:8 C b) ITEMS INVOLVED:
-* c) PROBLEM DESCRIPTION AND 0700 PARAo NUMBER: d) DAT A COLLECTION DESCRIPTION AND CODE NUMBER:
~~ ~ -7f-6-;./.8J(i) f (13).
e) SPECIFIC HUMAN ERROR(&):. ~ t...,'it
~ ~ ~ ~lo-v ....VV.....--v ~
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177 TP-6~1 LABELS~ LOCATION AIDS l May 198) -* s () eg '-I I APPENDIX B9 HED REPORT (CONTINUED) V NI ffi , PLANT UNIT r ;,. HED NO.: f.+ - rs-
- 89-2
HED PRIORITY RECORD J HED *i;1t;; *"2..1 ¢~ I
~-iS'
~
- 1. DOCUMENTED ERROR? YES Zo DOCUMENTED UNSAFE YES CONDITION OR TECH.
~
SPEC. VIOLATION?. S. HIGH SAFETY IMPORTANCE NO
. (PAM OR 1E)? . ,. ERROR POTENTIAL? , 2 I LOW * ~ ~ -HIGH L
- 5. CONSEQUENCE OF ERROR: 2 ' 6 --1_
HIGH C&'flDOtlT tit ltO IIO
/
177 TP-6.l LABELS At-o LOCATION AIDS. l May 198:S
- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT
' . . I . I b) ITEMS INVOL V...ED:
~1*~
B9-l
177 . TP-6.l LABELS Al'O LOCATION AIDS l May 198)
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- B9-2
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WAUDATCD~V:______________ . ______ DATE: 3-.£2-6$ a) Ha> TITLE, --------------I~:l..l\..:f?>~g,~M~S..i.....1..1'f0.,&,lR~\)_u;:i.\..Ll,,\,.....C,~-$D~\)"-l;l\,)""-l,t)"-*..:..~~\....
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. * *177
- s APPENDIX B9 HEO RtPORT {CONTINUED)
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PLA IT HEDND.: C-gi f) SUGGESTED BACKF'IT:
- C..~tJ~f: TDNG ~ ~"-'L\.16 ~Nl~(?,U IJq ~~
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207 TP-l.6 AMBIENT t<<>ISE l May 1983 APPENOIXB9 SAMPLE t-ED REPORT F'ORM
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g) REVIEW AND DISPOSITION:
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HED PRIORITY RECORD
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< \\\ -
- 1. DOCUMENTED ERROR?
.....__________~ YES
- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE NO
- 4. ERROR POTENTIAL? 5 _!_
HIGH
- 6. CONSEQUENCE OF ERROR:
5 -'- HIGH
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CATEGORY I ND ND ND I.
- SuRRY ~IT e aiDt A ASSESSIEHT 88/cl/85 LAST REVlal
!)AS£ 1S l£D NO TITLE IIESPClcSIBILITY STATUS DATE ~,21~a ~~ D!STJNCT!'.'E CODINl3 FOil EXTE'ulED DuRATi1"1 lU.LlllllN l>URihc NOffll OP ENS II -5 S7/11/85 H.JMN ERROR:
JnAY/ERROR lN CP RESPrJSE. Ht PROBLEII DESCRIPTION: AIKIN TILES DO NJT, li!VE DISTltelTIVE CODI NS FDR lliORWL [P, CP D¥NIT DISTJNSUJSH NlRML. ~ EIERSOCY CONDITION S70e PARAS~ NtJMEtrt: fi,3,3.c.F,1 S(S;ES'?'ED &ACKFI1: E&T~:.!S~ ~ill. CC-.1i1Cl'..illl WAY If CiIDiN6 DR ~Rl'.ll'c Cf TILES N!ilCtl ARE TO iE 11.1.LMlNATED FOR EXTEHDED DIJRATIDI'\, Hf ul~lTIDh: RcrtR TO Pl-115 (21H02l~) ~ Pl-2 l2~10l) ~!ATOR STUDY. I)l;ITA CCUECTlQt. DESCRIPT HIN ~ CilDE ~ru
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ORIGJN~TOR*: J. ' J"'1 1"*' t* * '
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.177 l Me)* 19B3 APPENDIX B9 HtO RtPORl (CONTINUE:D)
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DELAY lN OP ~ tff PROIUI! DESCRIPTION: Nu lllD S16fA PRIORITY CODIMi USED FOR 1NCOIIIN6 ~ARIIIS. CPS CAfft1T DIFFERENTIATE lllll!E JIIPORTIWT FID! LESS, e7H PARASRHDr ~ k : . o, 3.1, 4.A. l b,3, l,4,A,, SU51r-5TED BP.i:~FIT: AAih'lDE AUDITuRY SI~ PRIORIT~ CODING CH?ABI~IT1ES FOR ANN SYS ~AII..S IN ICCORDANCE './ fi,2,2,YH Cf 9790*
.-.. Dlei(J~ITIOI'.:
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APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (Ha)) REPORT Sv~,ty Iv NTTS I PL'.ANT/UNIT . V:l HEO NO.: p.:! - S- a_ DATE.: 0
~ !!;", /
9 2 Lj b) ITEMS 'iNVDL VED:.
~~
I ~** c) PRO EM DESCRIPTION ANO D700 PARA. NUMBER:
/. J\.,;, . .. . ~~ ~ ~ ~ ~ . ~J"'-
~~ ~ . 6-11\),,,,;;rr.,~~ .
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- - ,-kL Tu t>-1 rJ\...lJ_Ji-i...~' ~ J ...:J J..,_\ U cL-t~..tJ~~ .-'\.::t;,_ ...:t.:.1. luJJ.A.~*-
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TP-3.1 AN'-1..J'CIATOR SYSTD-1 l May 1_983 APPENDIX 89 HE:0 RCPOR T (CONTINL.£0) . . .
. Su llt<v/UPIG I § -t HED NO.: PI - S'd.
PLANT/UNll . f) SUGGESTED BACKF"JT: r.f~
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- B9-2
- SJRRY TITLE
~lT e CODE A RESPC>>IS1BH.ITY ASSc'.SSIIIENT
. STATUS LAST.Rz:VIEW DATE
~ 3 NO ~DIBLE IUIR!Hl.EARED SI6Mt.. FOR ~CIATOR SYSiE", ENS II -5 81/l!7/BS
~ ERROR:.
DELAYS lN IJIEAATDR RESPO'lSES f+f PROBLB! DESC.RIPTIOt.: Tt£RE 15 1£1 AUD1l!LE tl..£A!!Eli IUIRI! 516N/L !l. ANNLJ,j SYS CM1 Vl&JIL IUIR!! - Ll6t!TS lllES 0JT liiEH CLEARED. I uee PARASRAP!l NUMBER: 6.3. l.~.~
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lhVcSiltiAT~ *t~*~lTY Or- lhS1i:...Lllti:i Ci..t~if::rt k:...liilr. &I& DP.TA COiJ..ECTiill ~C!U~Tlur. *"ll ~ NuRt£k: TP-3.l ANNUNlClATOR SYSTtlllS AtVIEw REl!Afo{&: Pl-1;,0 JUSTIFY l/: ~r lroTucD IPl-:50) ITEMS it.VO...~: f!Hij~ ~ER LCi:~110!. CO!IIPONElll ~ SYSTEI! SUBSYST91 H MJT IN !NV Fli.E t
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, ~ ' TP-3.1 NH..N:lATDR SVS'TEM 1 May l9B)
, APPENDIX 89 HUMAN ENGJNEERING OISCREPANCV (HED) REPORT d) DAT A COLLECTION DESCRIPTION AND CODE NUMBER:
.(rp..rJ?J~ ~..N-~--rf ,, I 8~
- B9-l
TP-3.1 NN..J'CIATOR SYSTEM 1 May 198) APPENDIX: B9 HED REPORT (CONTINUED) S,H:tRY LJJNITT ' ~ ~ HED NO.: f -T - [-:"0 PLANT/UNIT
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REVIEW AND DISPOSITION: 89-2
HED PRIORITY RECORD HEDI er- S-i) *1
- 1. DOCUMENTED ERROR? YES
- 2. DOCUMENTED UNSAFE ,YES CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE
. (PAM OR 1E)?
NO
'Q C. ERROR POTENTIAL?
LOW 2 3 Q) 6 ......L. 05 HIGH
- 5. CONSEQUENCE OF ERROR: 1 2 3 _.!_
LOW HIGH NED IIO e&'fEQOll't' I 'e. CATUOR't' 1111 NO
- ASSESSEl'T LAST R:-VIEW TITLE RESPOkSIBILITV STATUS DATE 2iBe30e5 NO SIL.ENCE FLJjCTION ON IWNtliCIATOR RESPONSE cr,mns II -5 8&/8£>/SS
~ ERi!OR:
IIRY C'AJSE DELAY /ERRiJR IN DPEAATCili ~SDON:i Iii.ii: iu 1115ti i.£\1£1.S Cir hDiE,
~ PRO&..B! DESCRIPTlOh:
~. OORi.S. HAYC: NJ SEPARATE SILEtCE CAPABILITY, ~IN6_Ll6riT TO Fl.ASH WriILE "'1RN IS Sl!.Bfl, 87N PARASAA!irl IUIBE~:
b,3,4, 1,A.1 b,3.4.1.A.2 SU56ES7ED BA~IT: PROVIIE Shi~£ CAPABli.ITV FO~ ~liUlt:::IATOR RE~: COfliRQi..S, t++ DISPOSITIOI'.: Plluvlil: 61:.1~i:. CAAAi-l:..iiY A.'iil CON5i!D:li 5~C7:D lilt.&BA;;;t( FEATiJRE. DATA Cill.ECTIOl'i DESCRIPT!O!i ~ Cul:c IU~fl:
~1.£> A!".B!Ett1 Mi!S: &urt\1£Y TP-3.l ~lClATui! SYSTE*S REYIE~
REIIARi<S: Pl-i37 .
!TEJIIS l N\lili.\'Eu:
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207 TP-le6 AMBIENT N:>ISE 1 May 1983
- APPENDIXB9 SAMPLE HED REPORT FORM b) ITEMS INVOLVED:
~ /64f-r--r't--;JJ.- c,..;r\..f'>-1~
- c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER:
~ . . ) ~ CJ.~ ~ ~ /1.AA.~ u.., I U ( J ~
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~ J C'+ J
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- *. B9-l
*)
2t'7 TP-1.6 AMBIENT NJISE . 1 May 198) APPEN0IXB9 SAMPLE I-ED REPORT (CONTINUED)
'SLJ!f.r2..Y4i.ti1rrs 1~). HED No.: fr -,37 PLANT UNIT f) SUGGESTED BACKFlT~ . J. - . ,
. :.f~-~o_,~~~\v~
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g) REVIEW AND DISPOSITION: ~:.5 ~((),J-.OJ.., .;,~u_.. o..yn.~1li~ E (O'Y\\'1W' ~~j ~chd.. h(\~\?o.t.'(:.. 0-.~~
- 89-2
HED PRIORITY RECORD
. *1
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YES
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SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE NO
. (PAM OR 1E)?
,. ERROR POTENTIAL? , 2 a -'- LOW HIGH
- 6. CONSEQUENCE OF ERROR: 1 2 -L Low HIGH
- ASSESSl!:N'!' IJIST ltVIEW TITLE RE~SIBi~ITY STA!US DATE w:10211e ltJll&ER OF TILES PER "-B EXCEED se. I! -5 16/@S/85
~ ERROR:
DELAY lt. uP ~ E . <DELAY IN LDCATl1'1S/lDc'11TlFYlN6 ALARlili. t+t PROill.Ell! DESCRIPTIOh: EAOi ~ CON1AIN5 IClRE T~ 5iJ TILES, ~ A. B. C, D, 6, 11, J&K l1AVE 64 Tii.ES C8X8l AL.IIS E&f hA'vE ~ TILES l8Xlil, 87N PARAGAAPti NINER: o.3.3.l.D, l Slli36£STED ~IT: FUNCilONt!w.-Y SROuP AND DtAAi!CATE Ft.BS. c-tt DISPOSITIOII: REFER TO !Mi.1'11ClATDR &TIJDY PHIS (~106> DA:A COL.i.ECTIDN DESCRI~Tl~ ~ CODE N'JPIBER:
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I TP-3.1
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- APPENDIX B9 HUMAN ENGINEERING DlSCREPANCV (HED) REPORT .
*1,\
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\0
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........., - - - - - Ha) NO.: _3_~_l_-_Cf_ __
VALIDATED BY: DATE: a) Hto TITLE: ~"'.ht rt{ -r&Jµ .P..vv I/LB f&egd, 60 b) ITEMS JNVDL VED:
- c) PROBLEM DESCRJPTJON AND D700 PARA. NUMBER: [ t,.3. 3.3 d{1 J]
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e) SPECIFIC HUMAN ERROR.(l}o
- 89-1
. TP-3.1 NH..J'CIATOR SYSTEM 1 May 198)
- APP£NOJX B9 HtO RtPORT (CONTINUED)
PLANT/UNIT 3_f..:..'1 HED NO.: ----~---- f) SUGGCST£D BA.C~nT: RtVJtW AND DlSPOSJTlON:
- 89-2
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DELAY IN CP ~ fft PROBl.91 DESCRIPTION: IUL-fEANlrE, JOt-SPECIFIC Til.E IIESSSASES. 1700 PARAEIIAPri NlJ!i,Efl: Ei.3.3.4.C SUSS£Si@ BACl'J n:
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- TP-6. l CONVENTI~o SURVEY
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TP-:S.1 AtH..N:IATOR SVSTEM 1 May 198::S
* .5v~ev APPENDIX 89 HUMAN ENGINCERJNG 01SCREPANCV (HCC) RE_PORT
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B9-l
TP-3.1
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- APPCNDIX B9 HE:0 RE:POR T (CONTJNL.£0)
PLANT/UNIT HED NO.~ 3 *{ - ( f) SUGGESTED B.O.CKFlT:
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DWlV It. OP£RATOR RE~. H+ PROBLE!". DESCRIPTION: LETTER r1T Cf .~*: ~ ~ STA DIST!i'a cXCEEDS 50" IMXVIEWIN6 DISTIWCE FOR .29" HI6H LETIERIN6l, 8700 PARASRAPH NIJIIIR: 6.3.3.S.A.1 SuSGE57ED BAC>{FIT: IE-E.~AAVE TILES TO flit, e7~ SUIDa!NES. H+ DISPOSITIOII: REFER Tu P,.,,.utt:lAiO~ STuDY Pl-El5 (2e~2l~) DATA CClU.ECTION Dt:SCRIPilil'i ~ CODi: ~R: TP-3,l ~IC]Aiu~ SVSTc!l!S !eY!~~
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TP-3.1
. AN'U'CIATOR SYSTEM l May 198)
- HUMAN ENGJNE:E:RINQ DISCREPANCY (HEO) REPORT -
*APPENDIX B9 ANT/UNIT
'i,, ~,.
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ORIGINATOR: _.Jr,____,1Yl_4.....H.,..iL..,un...._ _ _ _ __ HEO NO.: -~----\_\-_1_2, _ __ VALIDATED BY: DATE: a) HED TITLE: Jvrvhrµ@ rl,;itu. llpl/q}zi ~ / J n ~ b) ITEMS INVOLVED:
- _c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER:
/t;t1.vt. kr7t ~ an-,w~ "kW .u . ~o:
l/p,3, 3,5 a{rJ/ 11,J ~a.41..fa.n~ ~ #1'. ar/t'W~ acknou~d~ ~ tr, a?UJ. a . ~ _tdt J.i~d6 so" ,,PJlz.id,
..,ia '1fu MaJttmr.vm.. ~ d,1.tifrlr.,cJ:,, IM, *2.tJ" .Aj1 Jdt:.u:n, .
d) OAT A COLLECTION DESCRIPTION AND CODE NUMBER:
~ /, 1-1/-
e) SPECIF"lC HUMAN ERROR.Cs): A, l..L I ,.. , I
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- 89-1
TP-3.1
~IATOR SVSTEM l May 1963
- APPENDIX B9
- HED REPORT (CONTINUED)
PL.ANT/UNIT HED NO.: 3, \ -1 &-
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- REVIEW AND DISPOSITION:
*-u=-- 6
- B9-2
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DATE PAS: 57 22A02114 INUlEQlj!TE WIDTH-TH£16HT RATIO O!'l ~IATOR ~ R S . ENS II -5 86/86/85 ltJIIIAt. ERROR: DELAY /ERiluR lN OP li:6"0NSE:. t+t ?ROBLE..: DESCRiPTil:tl: NJfERAL W1DTtHCH£I&!T liATID IS LESS T!IIH 3:5. IT IS 2:5 RtiD CHARACTERS ~P.R LIJ<<S AhD NP.RROii. 87N PARASRAP!i NiJl!fiR: Ei.3. 3, 5.D. 3 Sl&iESiED BAOOIT: ii:P.-HCE *I HLiS 1riAT nAV:. CQRR:.Ci 671110 E:iJID£-i~S ~~\ll:D MJIIERA.. 6iIDTri-Tu-r£l6if.' M"."IO OF 3:S. t+t DISPOSITIOh: REFER TO AWJNCIATOf< STUDY i:iER Pl-85 (28Ai2116), DATA Cll.!.ECTit,i DESCRIPTION AtJ> CODE Ni.lMBER: TP-3.l ANNiJN!CIATuR SYSTE11£ Rc:Vltlirl
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TP-3 ..1 NH..l'ClATOR SYSTEM 1 May l9B)
*APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT \ \ '-\,
I.A"'\ , 'l,., S'uR~y {l//JIT ~ "°'~l"- PLANT/UNIT 1-- ORJC.INATOR: _ ...fn ......~Dal.H~--*~;...;*
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VALIDATED BY:. DATE: a) HED TITLE: J!n£R1-1?u4tl IJ),dih-frrlktip..b f@ P?7 ~ncud,( Ck,,q4ty b) ITEMS INVOLVED: au 11-?'ma~ Laau.:n, .
- c) PROBLEM DESCRIPTJON AND D700 PARA. NUMBER:
N ~ ~-iz;-/.feifd .Atitic ~..h.4<J #lttn, 3:s * ..u ~ {u,.3.3,5"d(a) I
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d) OAT A.COLLECTION DESCRIPTION AND CODE NUMBER:
.a,.,-4 e} SPECiFlC: HUMAN ERROR(~):
(4! ( ~~ ~ **. / ~Vi..t-'J J.;\.L, ff~--*- ~i t'cJ }-...l .:fC';..!J
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- B9-l
TP 3.1
- 0
~TORSYSTEM 1 May l9B) * . APPENDIX 89 HE:O REPORT (CONTINUED)
PLANT/UNIT HEONO.~*Si.l- ~ f) SUGGESTED BA.C~nT: Ey1La W .LJJCkL'- ..W.U., il.4.-t ~ C:tu.t ct: 01 DLJ ~UALL/
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.. ~ ~*~
REVIEW AND DISPOSITION: . ~ - S
... *-. -;... ,,, *\ iPl,, '.- - - - - - -
- 89-2
- SURRY TITLE llilT 2 COD£ A RESPOhSIBILITY ASSESS!IENT STATUS LAS";' R:::."VIEW DATE 22Ae2115 LETIER SPAC1NtrltilllEOLIATE SPACIM3 DN ~IATOR TILE Llt£S, ENS II -5 16/86/85 K>>. ERROR:
!!'=..LAY 1111 DP RE~.
H+ PROBLEM DESCRIPTION: SPACE BEiWEE" L}ll;S r,,>. ~}ATOR TILES ,.ea*, IS LESS T~ llHE tfLF Tl£ DilRACTER 1£l6HT 11/2 (f .2e*=.1e*i. 87~ PARAS~ Hl.iMIIEk: 6.3. 3. S.ll.b SlJ66ESTED ilAOO n: RE-:HSAAY~ IM~lATuR Tl~S 10 J'.Ef'! lll7~ &JlIIEd!S, H+ DISPOSITlil!I:
~-eR TO ~ui-ClATOR b:~DY Pl-65 l~~lebl DHTP. COu.ECTiuN DE&Clii.-n~ AND CODE U.1£~:
TP-3, l AMi!JNlClATD~ &Ytfftll!ii kEY!:11
- 1191ARKS:
3.1-& ITEII.S ltiVIA..YED: IIIARK NUl!B:R LOCATION COf'PlltQ'T NAl'i SYSTE!I! SUBSY5T9I
~ TILES H ~i lN INV FlLE t
TP-3ol
#N.N:IATOR SYSTEM . l May 1983
- APPENDIX: B9 HUMAN ENGJhEERJNG DISCREPANCY (HE:D) REPORT
,,vV""
I\.\\~ ORJGJNATOR: _ _ 7?z
..........,_../J,....iq!lt(.~44e'=:....i---- HED NO.: ~. [ - G VALIDATED BY: DATE:
a) HEO TITLE: tlcttt:.. Mf'~ - Jn:z#fl{all 6,(dW-izg fin d-nnanc1~ Af; 4il4 b) ITEMS INVOLVED: an-nt.t~~
- c) PROBLEM DESCRJPTJDN AND 0700 PARA. NUMBER: [6',3. 3,5dt~Jl T)l.l, -o/'aU- ~~ 6dl / U z , , n u ~ 1..du (. t;B' ).)..1.
PM ../luz,,n 67U, h.ai/ ;1u ~actJt Jtuj'Lt ti 61 *2 ~ ,, = ,, ,o :>. d) OAT A COLLECTION DESCRIPTION AND CODE NUMBER:
'J7'~tU77'..l7;.,C l)cr >a, B I. /-'I e) SPE.CIF"IC HUMAN £RROR(a): -
__ .. ~**- ----*---*--*---- -----*--*-*- **-*--.- ........ *- .. l TP*l.1
~IATOR SYSTEM 1 May 1983 APPENDIX B9 HE:D RtPOR T (CONTINLED)
~NO.:~ J- b PLANT/UNIT f) SUGGESTED BA.CK.nT:
RE:VJE:W .ANO DISPOSITION: 'e ~(_ e / I 89-2
- SURRY LttlT 2 cmE A ASS£5Sfll.£!'.'1' 88/23/65 LAST RMEW r.n.e,-
.....:* 59 TITL.£ ~SlBlLITY STA'!'US DATE c.:Ae2!16 SILENCE CONiROLS FOii ANNut.CIATORS. I! -s
~ ERROR:
IE.AV IN S1L.a.c1N6 IWAlL.ABL.E ~NJNCIAiOR ~ARIII. ff+ PROitift DESCRIPTI~: THE~ CTRL.S [lt,j BBS B=.LCIW fU J AND C, RESPECTIVELY, DO t(JT ~ ~ SIi.ENCE CONT~. 8700 PAIIASRAPH NI.J!&Ek: Ei.3.4.1.A. l
&.166ESTED ~ I l :
PRCNIDE AMf~'SCIATLiR S!LEr.-:E Pi&m:J!'TO,-. HjR US C.: & J,
<1+1 DISPOSITIOI,:
REFER TO Pl (2eB03~51 DATA COL.LECTI&. DESCIUPTiON P.l(D CODE Nl.iflllf!: TP-3,1 ~~ICiATOR SYSiil'i:i REVlEw ITEMS IIWfLYED: MRI< IIIJIIIBER l.OCATION ~Et.IT hWE SVSTE!I! SIJBSVST91 JWN CTR1.S H tc'.IT lN INV Fll.E t
- ....... ,"91"1 .. - .... - - . . . . - ~ - -. . . . - * * * * * - *~*
TP-3.1
~lATOR SYSTEM l May l9B3
- .APPENDIX B9 HUMAN ENGINtCR.ING DISCREPANCY (HID) ~ORT *
- >ue14:Jvmr ,z: * . 1;
~/Z,
\ \{p
-ANT/UNIT S \l - e ORJGINA.TOR: _7(/.......,.,._.{)_a_i~'f... @-'/r(,.-y_ _ _ _ _ __ HCC> NO.:
VAUDA.TED BY: DATE: a) HE.D TITLE: 4<&,'tV'.L ~ u l Jk">- r 4tkr'ILl?'!IYUlt'k4 b) ITEMS JNVDL vtD: (ltrv,w'nC(aibi ~ hi Bu-d,bf.;zf'M. c) PROBLEM DE.SCRJPTJON AND 0700 PARA. NUMBER: J /;,.1.~./(). {rJ]
- 9t'I Me. Pf:nc), botJrdS Jiu a?VnU~ ~ ,.lte.u>w /JLB :r IVM C,,-,-----,, Al~LJ~,i.llHL do no-t
..,Ap.,ii, a.,,..,.,,,,U11C,(U'ft! ..4i1.u1Cl, ~~.
d) OAT A COLLECTJCN DESCRIPTION AND CODE NUMBER: bwi,~ ~ !3-Cf. "15 e) SPtCIF"IC HUMAN £RROR(1):
- B9-l
TP-3.1
~IATOR SYSTEM 1. May l9B) .
- APPENDIX B9
~E.D RE.~OR T (CONTINUED)
HED NO.: 3~ l- B PLANT/UNIT f) SUGGE.STE.D BA.C~nT: R.CVIE.W ANDDlSPOSITJON: jJ - 5
- B9-2
e.8/E3/e5 l'V\::= SURRY IJN!T 2 COD£ A A:SSESS"!Eti".' LAST REYIEw TITLE RESPUICS!B~LITY STATUS 1)1:lTE 22Aecl23 NO PRINTClJT FOR IU.TI-1NPUT ~IATOR. II -5 17/11/85
~ ERROR:
DELAY /ERROR IN CJl RESPONSE, fft PROEl.BI DESCRIPTIOtt: IUll-lt.>uT f.ffl.JtlClATuR liCES ~T ~~ /UR.~ ~Rl~TOUT. l~lLITY TD DEiER,llNc: liHICtl IUlR'- ~ Ek ~TIVATED. uee PARASRAPH NOOIER:
- 6. 3.1. 2. C. 2 Sliti6ESTED BACKF IT:
INSTAi..L PRl~TULJT C~l~m::; Fili< l'n.li..iHN*'I..'i ~lAi'i)ffS, fft DISPGSITIDh:
~ER TO Pl-85 l~le&J ~ Pl-2 1~2101) kNN'."t:lATO~ STUDY, DATA CD..i.ECTIOI> DESCR!PTiO!i At>D CODE lli.Jl".iik:
Tt:i-3.1 ~lClATDR ~YSTEMS RE~lE~
- RBIARKS:
C-17 ITEll!S Ht~. .Y'-.JI: M~ ~ i i LOCATION ~ T r.A,,E ~YSTEIII ff hOi lh lffY Fli..E I
Ji7
- APPCNDJX B9 HUMAN ENGINEERING DlSC-.RtPANCV fHEO)-RtPO~T SuR-S?.~ 2.
PL.ANT /LNIT 2 2 A-Dot 21-Z.5 ORJGINA.TOR: j . LO 0,-RA N t£O NO.~ --iC--- J.._____
..L.\
VAUDATEOEV, .. DATu 3~ B-- f\S
., I-ED TITLE, No mi tnotrr l::QR MVL1,-,Nru1 ANNPN t -;ro Dfss..
t,) JTEtJIS INVC1VCO:
- c) PROBLEM DESCRJPTJON AND D7DD PARA. NUMBER: ~ . :*..
I .: .:_ ,.:: , Mu \t,:,Nf~ "*1~tJOPc-ToRS l)Q
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/ :
ff_.lK100T \ !°': _\~.* ~-; ' - . *:, . :.. - d') OAT A CCLLECTJON DESCRIPTION ANO CODE NUMBtR:
~,
r'\*---- ...... .
\..., J::._ \ * : '* .. . - ~
~
- i I
e) SP£Clnc HUMAN ERROR~'):
- r-.. .
IQC. '9
l Me)* l9B) APPENDIX B9
- HED RtPOR T (CONTJNUEO) s~ (~~}~ HED NO.: ,C- \]
f) SUGGESTED BACKf"IT:
\ *,,:_!,-***. . . . .,. . _*.. ;. ,.,; r
. *~
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g) RtVJEW AND DISPOSJTJON:
- l£D NO S!JA~Y TITLE
~IT 2 CD~ A RESPOkS!BlLITY ASSESS~r.1 STATUS LAS: REVIEW DA'!£
~ ~ FDR ~ITS ~ ~IKE, ENS II -S 97/11/85
~ ERROR:
~USION OVER illt!!C~ SYSTcMlllll?ONENT A..Af<II! IS !WNDIN6 FDR.
+tt PRO&.EM DESCRIPTIOI:
JWMJICIATDR URIIS FDR IMITS AUX VENT ~AR'-5 ~ HI Rre.iASEOUS EFFLUENT RAD ~ ~D ~IKE, 971!0 PAAASRAPH ~R: o,2.2.2.A
!iJSSESTED ~FIT:
~ TOt¢ Ci ~ c~I'*1 tASY Dlf~Ett:.~T!ATlOti [; SO:.IIWS,
**+ DISPOSITIOII:
REFER iO Pl-85 C2We1e6l IIETAILED ~lATOR STUDY. DATA CDU.ECTlCiN DESCRIPTlClN ~D CD!'.i N!Jlf£R: TP-2.1 COM.Jt,,iCATIClhS !iURYEY ITEMS INVCL~: IJ!Rr< h!JfllBER LOCATll'Jh ~T ~ SV11Tt11 tt hOT Ill INV FIL£ t tt NOT Ill lNV FILE
- ff f(JT lN lNV Fl:.E *+
l Mey 1983 lt.. l\~;~NOIX B9 T (CONTJNUCD)
\ :::! -('~~
PLA JT
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- c. .
I-ED NO-~ ____ "."9-°',1.-___------- o~"fEi _:,*£2,B'2 - XOR !),)'1 > 5DOY!I . .
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- -(o.,.~.~
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*r
- HED NO SURRV TITLE UNIT 0 CODE B RESPONSIBILITY ASSESS~f\T STATUS eB/23/85 LAST REVIEW DATE PAGE 74
~302 SVS/EOt..lIP STATUS IS JNl=ERRED BY INDICATOll LJGt,;T BEiha OF.: Et.B I -2 08/S7/85 HUIIIAl'i ERROR:
- ERRORS JN OPERATOR RESPONSE FRi:iri: ER!hlNEOUS ASSIJ r.PTIONS [IF PLANT STATUS DuE TO BURNED OUT BULBS t+t- *' PROBLEfl! DESCRIPTIDti:
SVSTEM/EQJIPl!ENT STATUS IS INFE.RRcD itV JNl}lCATOk LI&iT itr:IN~ [F~. INSTEAD o: lLLlJll!lNATED, 0700 PARAGRAPH NlJIIIBEk: E:.. 5.3.1. C Si.J56ESTED BAD<FIT: EVA:..U'lTE CONSC:Du:.NCE.S OF l'IISJi.t~,r,-:~1 DtJE 10 11il!:i J;Rub..ill'i A~ii 1c: POT£~TIA- HAZARD, REVERS~. REMARI<&: Pl~B ITEIIIS 1NVil'..V£D: SI i~ll:~ IT£111S INVl'l.VED:
. ~RK NI.Jll'.B~R LOCATION CCff/WNE~i NA*.: svsm, SUBSVSTEJli Flo,v HI STP! ~ ff l't!Ji IN lNV FlL.C t .
LO STIii PRESS NOT IN It.~ FILE
- ff LDT~~ H hOi l~ l~v FILE+
Lo ?t1' ?ttess 1-\ 'D1t./UN.~ ~'
TP-5.1 DISPLAYS
- l May l9BJ
~- r APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT - Su r1.//2. Y(uN1rs*
- I i l*
1,?:>v 1,0~o . . 1.*,})l f"\i, PL.ANTIUNIT ORIGINATOR: ~~ HED NO.: f:I - ~~
- VALIDATED BY: ~ DATE: ~ 1,,, t9P'H a) HED TITLE: _ AM~ /414~ t::1'""t:litiA ,M v4i1>1>_M
__),l ,Mdhv-£:g-'-J*J,J: ),0 a-( 1* b) ITEMS INVDL VED: ~- c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER:
~~~ 0-U ~ JLJ . _:1~
~~~~°11~~
* * - l,,f,3,/c_ - -
d) OAT A COLLECTION DESCRIPTION AND CODE NUMBER: C r ~ ~ -Tfl~tJ.3::J.(').J e) SPECIF"JC HUMAN ERROR(1): ** M ~~~~-A_~_*.., ...).A./,f- f *';' .'. J_. *_.,e.'....fU-1-' :......
~ . )2)-1,-.:r I f D-*\
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B9-l 1 _..Q./\.11 ,C'"-v...C v *.v:; ~*-1.,*11.1-j -' *: _,
TP-5.l DISPLAYS l May l9B3 =** *APPENDIX B9 HED REPORT (CONTINUED) Su!<rt..y/u1Y1n I PLANT/UNIT 5 l, HED NO..: PI - "s, (. \,,' B9-2
PI-~? c*"1~1">,..,,I.*~:~---~~ ~ ~ ~ P - j ) J - ---~--. ce _
HED PRIORITY RECORD
- HEDI
~
- 1. DOCUMENTED ERROR? NO
- 2. DOCUMENTED UNSAFE NO ES CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE
. (PAM OR 1E)?
NO
~
C. ERROR POTENTIAL? 1 LOW 2 3
- I HIGH
- 5. CONSEQUENCE OF ERROR: 1 LOW 2;0-c 5 -L HIGH CA'flEGDIIY I NO NO ltO IIO
HED-NO. fI -f'S
........VIRCiNIA 0 POWER.
.:l. o A.o - J I o (o
.. . CONTROL ROOM DESICR REVIEW
- ~&J~~i'Cioc;{~i§ES$rcru' HUMAN (HED)
STATION/UNIT . .S &A..-~ *1 i ~. 2-
-------+1-----------
MARK N O . - - - - - - - - - - - - - - - - - - - ITEM DESCRIPTION !Inn va' ; a-f Ir >fy.s+e~ CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS)
**pe ,- £ D"" ro si u. J t *(o .:
COMMENTS: - - - - - - - - - - - - - - - - - - - - - - - - - - ORIGINATOR /. ( /(,r/
- DATE REVIEWED Q I
/tt;; /f5 AM
nc.1,,,1 l'IVo ( ..L - ~ _.. VIRGINIA POWER CONTROL ROOM DESIGN REVIEW .2.0Ao -:2106 HUMAN ENGINEERING brSCREPANCY (HED) RECOMMENDED RESOLUTION s_* ST AT ION /UN IT _ _ _ ....;LA.~v......r...,.v____6""-l'j"""M~'~' I t~-2.----- 1_.r_...:./.... MARK NO. - - - - - - - - - - - - - - - - - - - ITEM DESCRIPTION
//~11 LHT r- ,a f ~t'" Se,Jen-7 CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS Per !oy ~ s-f t,f Iv ff): * ,Id/ f/.. &,J I
r l'f' 1j,.r, I J Ye 11la.rl.,, I) I cl ri~ Lei< {/ Cf T '.s rf~ ~""... ~v c~ />-v~uf ~,, . r r , COMMENTS: . ,IJ /I U iµ o~/:7 w ; I/. c on f'o,-,..., f I r,,ry,...,e,f ~. Aw,
.a££,-ev1~f1°0n.s 11 lfCrPl'I '#/.!' 'S7, ' J i/1 (7JhftJ,,.
fo Jlt>. b~fr s~~r&J I{? vi.sd? ORIGINATOR_ F,_,_!-!~/_//______DATE REVIEWED __,__?_,__ ({-/£ - &' S 7, Prov ,J f:: *
- loc. k. - i~
().. t)V / oc. k -o~ le(J.f&J..ve fo
& keef 0. / a:v &,v\.. o v... e) V" l/ ovk. ./-/.. ~ () /4 r--. f', o~ c ;'-;f ; DW?
This I e4.:J.- &A. .... '(!_ wo..J/ L~ Use} rJv.. r ;"'et !')1.a ; j ena vice. c w~e"" ~t~;rm~ IS II-\ viee,J o.f fflairifeto~c.e.
ANNUNCIATOR WARN.ING SYSTEMS 6.3
** GUIDELINE VISUAL ALARM SUBSYSTEMS 6.3.3 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.3.3.4 VISUAL TILE LEGENDS
- a. UNAMBIGUOUS - Annunciator visual tile legends should be specific and unambiguous.
Wording should be in concise, short messages.
- b. SINGULARITY -Alarms which refer the I I operator to another, more detailed annunciator I panel located outside the primary operating area should be minimized. !
C. SPECIFICITY -Tile legends should address I I specific conditions; for example, do not use I one alarm for HIGH-LOW, TEMPERATURE* I l PRESSURE.
- d. ABBREVIATIONS-Abbreviations and acro- I nyms should be consistent With those used elsewhere in the control *room. I
*. *"\
6.3-17
ANNUNCIATOR WARNING SYSTEMS 6.3 ,.:-~
. :--,J VISUAL ALARM SUBSYSTEMS 6.3.3 *: *7
- GUIDELINE.
6.3.3.2 VISUAL ALARM RECOGNITION AND IDENTIFICATION COMPLIANCE CHECKLIST Specific guitjelines for visual recognition and identi* fication of alarmed tiles follow:
- a. FLASHING - The specific tile(s) on an annun-ciator panel should use flashing illumination to indicate an alarm condition.
- b. FLASH RATE - Flash rates should be from three to five flashes per second with approxi-mately equal on and off times.
- c.
- FLASHER FAILURE - In case of flasher failure of an alarmed tile, the tile light should illuminate and burn steadily.
- d. CONTRAST DETECTABILITY-There should be high enough contrast between alarming and steady on tiles, and between illuminated and 0
non-illuminated tiles, so that operators in a normally illuminated control room have no problem c;liscriminating alarming, steady-on,
}!~
'**.:~; .
and steady-off visual tiles.
- e. "DARK" ANNUNCJATOR PANELS-A "dark" annunciator panel concept should be used. This means that under normal operating conditions no annunciators would be illumi-nated; al I of the visual tiles of the annunciator panels would be "dark."
- f. EXTENDED DURATION ILLUMINATION-If an annunciator tile must be "ON" for an extended period during normal operations (e.g., during equipment repair or replacement),
it should be: ( 1) Distinctively coded for positive recog-nition during this period, and (2) Controlled by administrative procedures.
- ._./
8.3-14
- ****~* -**** - .' . :: .
... '* .* ~-. .ANNUNCIATOR WARNING SYSTEMS 6.3 GENERAL SYSTEM CHARACTERISTICS 6.3.1 COMPLIANCE CHECKLIST
.N/A- Yes No Reference/Comment 6.3.1.2 ALARM PARAMETER SELECTION (Cont'd)
- c. . MULTICHANNEL OR SHARED ALARMS (Cont'd)
(2) Where multi-input annunciators must be used, an alarm printout capability should be provided. The specifics of the alarm should be printed on an alarm typer with sufficient speed and buffer storage to capture all alarm data. (3) A reflash capability should be provided to allow subsequent alarms to activate the auditory alert mechanism and reflash the
*visual tile even though the first alarm may not have been cleared.
- d. MUL Tl-UNIT ALARMS-Multiple-unit nuclear power plants may contain plant systems that are shared by two or more units. The status of any such equipment should be provided in all control rooms *
(1) Alarms for any shared plant systems should be duplicated in all control rooms. (2) When an item of shared equipment is being operated from one control room, a status display or signal should be pro-vided in all other control rooms which could potentially control this equipment. 6.3-5
ANNUNCIATOR WARNING SYSTEMS 6.3 VISUAL ALARM SUBSYSTEMS 6.3.3
- GUIDELINE 6.3.3.2 VISUAL ALARM RECOGNITION AND IDENTIFICATION COMPLIANCE CHECKLIST Specific guidelines for visual recognition and identi*
fication of alarmed tiles follow:
- a. FLASHING - The specific tile(s) on an annun-ciator panel should use flashing illumination to indicate an alarm condition.
- b. FLASH RATE - Flash rates should be from three to five flashes per second with approxi-mately equal on and off times.
- c. FLASHER FAILURE - In case of flasher failure of an alarmed tile, the tile light should illuminate and burn steadily.
- d. CONTRAST DETECTABILITY -There should be high enough contrast between alarming and steady-on tiles, and between illuminated and non-illuminated tiles, so that operators in a normally illuminated control room have no problem c;iiscriminating alarming, steady-on,
- ifI~
<.:;.) .
and steady-off visual tiles.
- e. "DARK" ANNUNCJATOR PANELS.:..A "dark" annunciator panel concept should be used. This means that under normal operating conditions no annunciators would be illumi-nated; all of .the visual tiles of the annunciator panels would be "dark."
- f. EXTENDED DURATION ILLUMINATION-If an annunciator tile must be "ON" for an extended period during normal
- operations (e.g., during equipment repair or replacement),
it should be: (1) Distinctively coded for positive recog-nition during this period, and (2) Controlled by administrative procedures. 6.3-14 ...
-~~
I
- -~.)
GUIDELINE CONTROL ROOM WORKSPACE 6.1 GENERAL LAYOUT 6.1.1 COMPLIANCE CHECKLIST 6.1.1.3 FURNITURE-AND EQUIPMENT LAYOUT Placement and spacing of equipment depends on control room configuration, manr:iing, and other design features. Thus, guidelines are stated in terms of minimum spacing considerations for common equipment arrangements and use situations. Main-tenance and testing of equipment has not been considered, and may require larger clearances than the minimums suggested.
- a. VIEWING-Desks and consoles placed in the primary operating area should permit operators at those desks and consoles full view of all con-trol and display panels (including annunciator j
panels) in the primary operating area (see Exhibit 6.1*2). . (./ 9 L-Shape
'ii U-Shape Concentric Wing Exhibit 6.1-2. Control board configurations and desk placements .that facilitate sight and voice con~.
- 6.1-3
ANNUNCIATOR WARNING SYSTEMS 6.3 VISUAL ALARM SUBSYSTEMS 6.3.3 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.3.3.5 VISUAL TILE READABILITY
- a. DISTA.~CE~The operator should be able to read all the annunciator tiles from the position at the work station where the annunciator acknowledge control is located.
(1) Letter height should subtend a minimum visual angle of 15 minutes, or .004 x viewing distance. The preferred visual angle is 20 minutes, or .006 x viewing distance. (2) Letter height should be identical for all tiles, based on the maximum viewing distance. Separate calculations should be made for stand-up and. sit-down work stations.
- b. TYPE STYLE-The size and style of lettering should meet the following: .
.:*~-
( 1) Type styles should be simple. . '*
*<.1)*!
(2) Type styles should be consistent on all visual tiles. (3) Only upper-case type should be used on visual tiles. I
- c. LEGEND CONTRAST-Legends should pro-vide high contrast with the tile background.
(1) Legends shou Id be engraved. i (2) Legends should be dark lettering on a
- light background. I 6.3-18
*,.. _/
PANEL LAYOUT 6.8 LAYOUT ARRANGEMENT FACTORS 6.8.2 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.8.2.4 STANDARDIZATION When a precedent has been established in the arrangement and location of controls and displays, that standard practice should be followed unless other crucial considerations necessitate a change.
- a. PANEL TO PANEL STANDARDIZATION-Standardization should be maintained where similar functions or panels are located at several work stations or units and must be used by the same personnel.
- b. SIMULATOR-TO-CONTROL ROOM STAN*
DARDIZATION-Standardization should be maintained where simulators or procedure trainers are used that simulate the actual operational equipment*
- 6.8-9
.:. GUIDELINE PANEL LAYOUT GENERAL PANEL LAYOUT 6.8.1 COMPLIANCE CHECKLIST 6.8 Reference/Comment 6.8.1.1 ASSIGNING PANEL CONTENTS Controls and displays should be placed within the control room at locations which promote efficient procedures, safe operation, and maximum operator awareness of the current system condition. There are three general methods for achieving this con-dition. They are: (a) grouping by task sequence,
~b) grouping by system function, and (c) grouping by importance and frequency of use.
- a. GROUPING BY TASK SEQUENCE-Controls and displays should be assigned to work stations so as to minimize operator movement.
To the extent practical, this assignment should consider both normal and emergency pro* cedures. It should be practical to perform all frequently occurring routine tasks, and time-sensitive emergency tasks, with a minimum of human movement from panel to panel.
- b.
- GROUPING BY SYSTEM FUNCTION-Within the constraints of grouping by task sequence, controls and displays should be assigned to panels in functional groups related to system structure. This grouping should promote easy understanding of the relationship between controls and system, and should assist graphic or pictorial display of system relationships.
- c. GROUPING BY IMPORTANCE AND FRE-QUENCY OF USE-Within the constraints of grouping by task sequence and by system function, controls and displays should be assigned to panels depending on their impor-tance and frequency of use. Controls or displays which are neither important to plant safety nor frequently used should be installed in secondary panel locations.
II
- 6.8-1
ANNUNCIATOR WARNING SYSTEMS 6.3 GENERAL SYSTEM CHARACTERISTICS 6.3.1 GUIDELINE COMPLIANCE CHECKLIST 6.3.1.4 PRJQRI.TIZf.TION
... J Because of the large number of annunciators typically found in control rooms and the likelihood that numerous alarms may come in concurrently, some logical prioritization should be applied such that operators can differentiate the most important or serious alarms from less important ones.
- a. LEVELS OF PRIORITY
( 1) Prioritization should be accomplished using a relatively small (2-4) number of priority levels. (2) Prioritization should be based en a continuum of importance, severity, or need for operator action in one or more dimensions, e.g., likelihood of reactor trip, release of radiation. Exhibit 6.3-3
! * \~
provides an example of prioritization
- .*:::..... . ,*: based on three levels of prioritization .
- FIRST PRIORITY ALARMS
- Plant shut down (reactor trip, turbine tripl
- Radiation rele111e
- Plant conditions which, if not com,cted immediateiv, will result in automatic plant shutdown or l'Bdiation relese, or will require manual plant shutdown.
SECOND PRIORITY A!,.ARMS
- Technical specification violations which if not corrected will require plant shutdown
- Plant conditions which, if not corrected, may lead to pl-;.nt shut down or radiation rele-THIRD PRIORITY ALARMS
- Plant conditions representing problems (e.g., system
- degradation) which affect plant operability but which should not lead to plant shutdown, radiation releme, or violation of technical specifications Exhibit 6.3-3. Three-level annunciator prioritization example.
,:** 6.3-7
ANNUNCIATOR WARNING SYSTEMS 6.3 GENERAL SYSTEM CHARACTERISTICS 6.3.1 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.3.1.5 CLEARED ALARMS Alarms that ,bave cleared should initiate an audible signal and activate the alarmed and acknowledged visual tile in some way to provide positive con-firmation.
- a. AUDITORY SIGNAL-Cleared alarms should have a dedicated, distinctive . audible signal which should be of finite duration.
- b. VISUAL SIGNAL-The individual tile should have one of the following:
( 1) A special flash _rate (twice or one-half the normal flash rate is preferred, to allow discrimination), or (2) Reduced brightness, or (3) A special color, consistent with the overall control room color coding scheme, pro-.
- duced by a differently colored bulb behind the tite.
6.3-9
ANNUNCIATOR WARNING SYSTEM 6.3 .-~
*,.- \
OPERATOR RESPONSE SUBSYSTEM 6.3.4 *-.~1 GUIDELINE COMPLIANCE CHECKLIST 6.3.4.1 CONTROLS Controls for operator response to the annunciator system 'in'dude silence, acknowledge, reset, and test controls. (See Exhibit 6.3-5.)
- a. SILENCE (1) Each set of operator response controls should include a silence control.
(2) It should be possible to silence an auditory alert signal from any set of annunciator response controls in the primary operating area.
- b. ACKNOWLEDGE (1) A control should be provided to terminate the flashing of a visual tile and have it continue at steady illumination until the alarm is .cleared.
(2) Acknowledgement should be possible only at the work station where the alarm originated .
- c. RESET (1) If an automatic cleared alann feature is not provided, a control should be pro-vided to reset the system after an alarm has cleared.
(2) The reset control should silence any audible signal indicating clearance and should extinguish tile illumi_nation. (3.) The reset control should be effective only
-
- at the work station for the annunciator panel where the alarm initiated.
- d. TEST (1) A control to test the auditory signal and flashing illumination of all tiles in a panel should be provided.
(2) Periodic testing of annunciators should be required and controlled by administrative procedure. 6.3-20
\J
-ANNUNCIATOR WARNING SYSTEMS 6.3 VISUAL ALARM SUBSYSTEMS 6.3.3 GUIDELINE COMPLIANCE CHECKLIST NIA Yes No Reference/Comment 6.3.3.3 ARRANGEMENT OF VISUAL ALARM
-TILES..... r* **
- a. MATRIX ORGANIZATION*- Visual alarms shou Id be organized as a matrix of visual alarm tiles within each annunciator panel.
- b. FUNCTIONAL GROUPING-Visual alarm tiles should be grouped by function or system within each annunciator panel. For example, area radiation alarms should be grouped on one panel, not spread throughout the control room.
- c. LABELING OF AXES
( 1) The vertical and horizontal axes of annunciator panels should be labeled with alphanumerics for ready coordinate designation of a particular visual tile. (2) Coordinate designation is preferred on the
- left and top sides of the annunciator panel *
(3) Letter height for coordinate designation should be consistent with a subtended visual angle of at least 15 minutes as viewed from a central position within the primary operating area.
- d. PATTERN RECOGNITION-When a panel contains a number of simultaneously illumi*
nated visual tiles, pattern recognition can help in diagnosing and mitigating problems. Pattern recognition can be facilitated in annunciator panels by meeting the following criteria: (1) The number of alarm tiles and the matrix density should be kept low (a maximum of 50 tiles per matrix is suggested). (2) Tiles within an annunciator panel matrix should be grouped by subsystem, function, or other logical organization. 6.3-15 . --*- *.- ..-.. - ., . . ;:\:, *.*, ;** *:. :"*. '***: . - -... .
~ . .. ~ -:, *.* *: .*...
ANNUNCIATOR WARNING SYSTEMS 6.3 VISUAL ALARM SUBSYSTEMS 6.3.3 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.3.3.4 VISUAL
. . TILE r ... LEGENDS
- a. UNAMBIGUOUS - Annunciator visual tile legends should be specific and unambiguous.
Wording should be in concise, short messages.
- b. SINGULARITY -Alarms which refer the operator to another, more detailed annunciator panel located outside the primary operating area should be minimized. . '
I
- c. SPECIFICITY -Tile legends should address specific conditions; for example, do not use I
I I one alarm for HIGH-LOW, TEMPERATURE-PRESSURE. Il I ;
- d. ABBREVIATIONS-Abbreviations and acro-nyms should be .consistent With those used elsewhere in the control *room. *1 i
. *~*
-:. 6.3-17
~
ANNUNCIATOR WARNING SYSTEMS 6,3 :~. VISUAL ALARM SUBSYSTEMS 6.3.3 .--~--.':}
- GUIDELINE 6.3.3.5 VISUAL TILE READABILITY
- a. _o_~STAN9;_-The operator should be able to COMPLIANCE CHECKLIST N/A Yes No Reference/Comment
.. *~-
read all'the annunciator tiles from the position at the work station where the annunciator acknowledge control is located. (1) Letter height should subtend a minimum visual angle of 15 minutes, or .004 x viewing distance. The preferred visual angle is 20 minutes, or .006 x viewing distance. (2) Letter height should be identical for all tiles, based on the maximum viewing distance. Separate calculations should be* made for stand-up and sit-down work stations.
- b. TYPE STYLE-The size and style of lettering should meet the following: .
( 1) Type styles should be simple. .... ~,. (2) Type styles* should be consistent on all visual tiles. (3)
- Only upper-case type should be used on
- visual tiles.
- c. LEGEND CONTRAST-Legends should pro-vide high contrast with the tile background.
( 1) Legends should be engraved. i (2) Legends should be dark lettering on a light background. \. 6.3-18
.,!~ ANNUNCIATOR WARNING SYSTEMS 6.3 VISUAL ALARM SUBSYSTEMS 6.3.3 COMPLIANCE CHECKLIST 6.3.3.5 VISUAL TILE READABILITY (Cont'd)
- d. LE.ITER ... *DIMENSIONS AND SPACING-Recommended dimensional characteristics of legend lettering and spacing are as follows:
( 1) Stroke-width-to-character-height ratio should be between 1 :6 and 1 :8. (2) Letter width-to-height ratio should be between 1 :1 and 3:5. (3) Numeral width-to-height ratio should be 3:5. (4) Minimum space between characters should be one stroke width. (5) Minimum space between words should be the width of one character. (6) Minimum space between lines should be _..... -~'-.\ one-half the character height. i'--~~- ::~./ ( .* 6.3-19
ANNUNCIATOR WARNING SYSTEM 6.3 .-*~ OPERATOR RESPONSE SUBSYSTEM 6.3.4 :.~-; GUIDELINE COMPLIANCE CHECKLIST NIA Yes No Reference/Comment 6.3.4. 1 CONTROLS Controls for operator response to the annunciator system include silence, acknowledge, reset, and test controls. (See Exhibit 6.3*5.)
- a. SILENCE
( 1) Each set of operator response controls should include a silence control. (2) It should be possible to silence an auditory alert signal from any set of annunciator response controls in the primary operating area.
- b. ACKNOWLEDGE (1) A control should be provided to terminate the flashing of a visual tile and have it continue at steady illumination until the alarm is cleared.
(2) Acknowledgement should be possible *.-~~\ only at the work station where the alarm '~:./:,.,). originated . \. l;I
- c. RESET (1) If an automatic cleared alarm feature is not provided, a control should be pro-vided to reset the system after an alarm has cleared.
(2) The reset control should silence any audible signal indicating clearance and should extinguish tile illumination. (3) The reset control should be effective only
- at the work station for the annunciator panel where the alarm initiated.
- d. TEST (1) A control to test the auditory signal and flashing illumination of all tiles in a panel should be provided.
(2) Periodic testing of annunciators should be required and controlled by administrative procedure. 6.3-20
/
,.-~.
~* :-* - ANNUNCIATOR WARNING SYSTEMS GENERAL SYSTEM CHARACTERISTICS 6.3.1 COMPLIANCE CHECKLIST 6.3 N/A Yes No Reference/Comment 6.3.1.2 A_LARM PARAMETER SELECTION (Cont'd)
- c. MULTICHANNEL OR SHARED ALARMS (Cont'd)
(2) Where multi-input annunciators must be used, an alarm printout capability should be provided. The specifics of the alarm should be printed on an alarm typer with sufficient speed and buffer storage to capture all alarm data. (3) A reflash capability should be provided to allow subsequent alarms to activate the auditory alert mechanism and reflash the visual tile even though the first alarm may not have been cleared.
- d. MULTI-UNIT ALARMS-Multiple-unit nuclear power plants may contain plant systems that
. ', are shared by two or more units. The status of any such equipment should be provided in all
- control rooms .
( 1) A Iarms for any shared plant systems (2) should be duplicated in all control rooms. When an item of shared equipment is being operated from one control room, a status display or signal should be pro-vided in all other control rooms which could potentially control this equipment.
- 6.3-5
- .~: .......:~------***-.. : *--:.::.. . .. :.':
;.* ***-.*~.:..~ ... _,..;:.: . ~ .. -.......... * :.. ....
COMMUNICATIONS AUDITORY SIGNAL SYSTEMS 6.2.2 6.2 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.2.2.2 SIGNAL MEANING
- a. The meaning of each auditory signal should be clear and unambiguous.
*b. Similar auditory signals must not be contra-dictory in meaning with one another. -
- c. Auditory signals intended to alert the operator to a malfunction or failure must be different from routine signals such as bells, buzzers, and normal operating noises.
- 6.2-15
- 6.5.3.1 CHARACTERISTICS AND PROBLEMS OF LIGHT INDICATORS_(Cont'd) N/A Vn 'No VISUAL DISPLAYS LIGHT INDICATORS 6.5.3 COMPLIANCE CHECKLIST Refllrance/Comment 6.5
- c. PRECAUTIONS TO AVOID MISINTERPRE*
TATION'* ( 1) . System/equipment status shou Id be inferred by illuminated indicators, and never by the absence of illumination. (2) Provisions (design or procedural) should be made* to prevent interchanging indicator lenses.
- d. USE AS ALERTING INDICATORS-Alerting the operators to unfavorable status should be a function of the annunciator system and not assigned to light indicators
- I
- 6.5-21
. VI-RGINil\ poyµ_ __
SURRY POWER STATION EMERGENCY PROCEDURE
- NUMBER 1-E-0 PROCEDURE TITLE REACTOR TRIP OR SAFETY INJECTION (Yith 5 Attachments)
REVISION 7 PAGE 1 of 21 PURPOSE To provide guidance to verify proper response of the automatic protection systems following manual or automatic actuation of Reactor Trip or Safety Injection, to assess plant conditions, and to identify appropriate recovery procedures. LEVEL 2 GOMTROLLED ms1R1BUT10N ENTRY CONDITIONS
- 1) Any of the following symptoms th~t require a reactor trip are present, AND a reactor trip has NOT occurred:
- Reactor protection system setpoint(s) - EXCEEDED
- Turbine protection system setpoint(s) above P EXCEEDED
- 2) Any of the following symptoms that indicate a reactor trip has occurred:
- Any RED reactor trip first out annunciator - LIT
- Rapid decrease in neutron flux level - INDICATED
- All shutdown AND control banks - INSERrED
- All rod bottom lights - LIT I.
- Reactor trip AND bypass breakers - OPEN I
i
- 3) Any Safety Injection system actuation setpoint(s) - EXCEEDED i
! 4) Any of the following symptoms that indicate safety injection has occurred: I
-=
- Any SI first out annunciator - LIT
- UISI pumps - RUNNING
- 5) Transition from another procedure.
DATE APPRO~ED CHAI
~STATION NUCLEAR SAFETY 1-/~-i"Z.,
AND ERATING COMMITTEE
NUMBER PROCEDURE TITLE REVISION 7 1-E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE ...-~~---i RESPONSE NOT OBTAINED t--~~~~~~---. [ 3] VERIFY POWER TO AC EMERGENCY BUSES: a) AC emergency buses - AT LEAST a) Try to restore power to at ONE ENERGIZED least one AC emergency bus.** IF power can NOT be restored to at least one AC emergency bus, THEN GO TO l-ECA-0,0, LOSS OF ALL AC.POWER, STcEP 1. b) AC emergency buses - BOTH b) Do the following for any EDG ENERGIZED which has failed to start:
- 1) Put EDG in EXERCISE.
- 2) Push START button.
- 3) Put EDG in AUTO .
- [ 4]
----*~~
CHECK IF SI INITIATED: a) Check SI indications:
- Safety Injection System a) Check if SI is required as indicated by any of the following:
Initiated annunciator (A-F-4)
- LIT
- Low PRZR pressure,
- I.HSI pumps a RUNNING
- High CTMT pressure,
- High steamline differential pressure,
- High steam flow with low Tave or low line pressure.
IF SI is required, THEN manually initiate.
!E SI is NQ! required, THEN GO TO l-ES-0.1, REACTOR TRIP RESPONSE, STEP 1.
b) Manually initiate SI
/
NUMBER PROCEDURE*TITLE REVISION 7 l-E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 6 of 21 STEP ACTION/EXPECTED RESPONSE - - - - RESPONSE NOT OBTAINED 1--------- [11] CHECK IF MAIN STEAMLINES SHOULD BE ISOI.ATED: __..,.IP.., a) Check if ANY of the following a) GO TO Step 12. annunciators - LIT
- Hi Steam Flow & Lo Steam Pressure OR Lo Tavg (E-F-10)
- CLS HI-HI Train A (B-C-4)
- CLS HI-HI Train B (B-C-5) b) Check MSTVs - CLOSED b) Manually close valves.
c) Check Hi steam flow SI - c) GO TO Step 12. ACTUATED d) Verify RYST crosstie valves open
- l-SI-SOV-102A
- l-SI-S0V-102B
- 2-SI-S0V-202A
- 2-SI-SOV-202B e) Put BOTH RMT mode transfer switches in REFUEL
- VIRGINIA PO.,vER COMPANY ADMINISTRATIVE CONTROL UPGRADE PROGRAM (ACUP)
CROSS REFERENCE INDEX
- Page 73 Report Date 04/10/92 NOTE: Check controlled procedure index to determine current procedure status (e.g., approved, deleted etc.)
Dlspo Effect Station Proc No Station Pree Title Code ACUP Procedure ACUP P~ure Title Date TmnsHlon Status SUADM 13 OPERATIONS DEPARTMENT - 2 VPAP-1402 CON'fROLOFEQUIPMENT,, 05/31/90 11-IIS PROCEDURE HAS BEEN OPERATION, MAINTENANCE TAG-OUTS, AND TAGS REPLACED BY VPAP-1402, ANDTAGGING VPAP-1405,0PAP-0010, AND VPAP-1405 INDEPENDENT VERIFICATION 07/01/90 OPAP-0011 OPAP-0010 TAG-OUTS 05/31/90 OPAP-OOH SPECIAL ORDER TAG CONTROL 04/15/<)l SUADM-0-15 NUCT..EAR RJEL HANDLING I VPAP-1406 CONTROL OF NUCLEAR 12/'}fj/89 11-IIS PROCEDURE HAS BEEN AND ACCOUNTABILITY MATERIAL REPLACED BY VPAP-1406 IN ITS ENTIRETY
Il.11 CORRECTIVE ACTION EVALUATION
- CANO.:
CA DESCRIPI'ION: EQUIPMENT MARK NO. llE Rescale auxiliary feedwater flow indicators (linear, 0-500 gpm - increments of 10 gpm) HEDNO. 20A02216 23002243 1-FW-FI 100 A,B,C 20A02230 Il.11.1 BED REVIEW - ORIGINAL FINDINGS HED No. 20A02216 - Scale range inappropriate, need range expanded. (NUREG-0700, Sections 6.5.1.2.d.1, 6.5.1.2.d.2) HED No. 20A02230 - Display output does not allow accurate reading. (NUREG-0700, Section 6.5.1.2.a) HED No. 23002243 - Unit value progression (NUREG-0700, Section 6.5.1.5.c) Operator interviews and validation surveys determined that the indicator scale range required expansion for an operator to read maximum auxiliary feedwater flow when all AFW pumps are running. The scales of the Unit 1 AFW flow indicators 1-FW-FI-lOOA,B,C are 0-350 gpm (square root). In addition, the existing square root indicator scales make it difficult for operators to obtain accurate flow readings as required by the ER Gs when observing the low end of the indicator scale. The existing scales do not provide the required degree of accuracy for the operator. This violates NUREG-0700, sections 6.5.1.2.a and 6.5.1.5.c which requires unit graduations to follow a specific progression or multiple of 10. DC-88-27/28 were prepared to change the range of the steam generator AFW flow indicators from 0-350 gpm (square root) to 0-500 gpm (linear), and replace the existing scales with linear scales in 10 gpm increments. Il.11.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs IRIYES DNO DN/A RG-1.97 mlYES DNO DN/A Auxiliary feedwater flow rate is monitored in several Auxiliary feedwater flow is variable D21, Category 2. EOPs, examples include l-E-0, l-E-3, 1-FR-Hl, ECAs, RG-1.97 requires range to be 0-110% of design flow. ES, etc. Minimum auxiliary feedwater flowrate of Design flow is the maximum flow anticipated during 70 gpm is an EOP setpoint (1-ECA-2.1, 1-FR-H.5) normal operation. EPIPs DYES mlNO DN/A LERs/lOERs DYES ml NO D NIA Auxiliary feedwater flow indication is not No LERs/IOERs concerning the monitoring of used in the EPIPs. auxiliary feedwater flow were found. APP.R DYES mlNO DN/A HPES/STA DEV/SOER DYES mlNO DN/A Auxiliary feedwater flow is not required for No station deviations or SOERs were found concerning Appendix R safe shutdown. the auxiliary feedwater flow indicators. D NO D NIA ERF/SPDS ml YES TECH SPEC ITEM ml YES D NO D N/A Auxiliary feedwater flow to the steam generators The operability of the auxiliary feedwater pumps and is in the ERF computer; Point IDs FlFWOOlA, 002A, instrumentation is defined in TS 3.6.D. 003A. VARS01D.B7S-l
11.11.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The auxiliary feedwater flow indicators are monitored in several EOPs and used to verify minimum design basis auxiliary feedwater flow to SGs during accident conditions. The individual auxiliary feedwater flow rate to each SG may vary between approximately 125 gpm to 350 gpm, depending on the number of auxiliary feedwater pumps running. A range of 0-400 gpm, is required due to the pegging of these meters during a start of all three pumps on a safety injection signal. This range also satisfies the RG-1.97 requirement which is 110% of design flow.
EOPs 1-ECA-2.1, 1-FR-H.5 and 1-FR-H.1 (continuous action page) requires the operator to maintain a minimum auxiliary feedwater flow rate of 70 gpm to affected SGs or SGs with narrow range level < 9 %* The existing indicator scale is difficult to read at low flow rates and determine if this minimum setpoint is satisfied. An auxiliary feedwater flow indicator scale with 10 gpm increments would allow the operator to easily determine flow rate. Safety Significance - The auxiliary feedwater flow indicators are safety related and used in several EOPs for accident mitigation. Potential for Error - The existing square root indicator scale increases the potential for error based on the operator's ability to determine plant conditions/setpoints and process information. The potential for error. is high. Consequences of Error - The consequences of not easily reading auxiliary feedwater minimum flow rate is a delay in operator response when confirming auxiliary feedwater flow and not being able to determine the flow rate at the upper range of the scale.
- 11.
11.4 CONCLUSION
S/RECOMMENDATIONS It is recommended that the auxiliary feedwater flow indicator scales be replaced with a scale having a range of 0-400 gpm. This is based on the importance of this indication and the ability of the operators to determine minimum and maximum auxiliary feedwater flow rates during accident conditions on the existing meters. The DC-88-27 /28 recommended modification included the replacement of the auxiliary feedwater flow transmitters. During the CRDR reassessment, the capability of the existing transmitters to support a range of 0-400 gpm was evaluated. The existing transmitters are adequate for a maximum range of 0-400 gpm.
- VARS01D.B7S-l
/. * *\,. * . . jf* *: 'J-::>:~~ :::_1_1~:i~~m~~1,~i*{*. . :*;-;:.** **. * *: ;'* * * * :* J
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- D EOPs/EPIPs ref. D ERF/SPDS D
- Q-LIST IRG-1.97 D
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- CHECKLIST
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. e700 PA~RAPri HOOIER:
6, 5.1. a. ll, l 6.5.1.~ 1), c: Sll66ESTED BAC,<m: E\/A..UAT~ FDR APPRDfllHATi:lllESS OF SCHi.E liANBE, REPLACE lilTtl III~ ~ SCfLE. DI~IT10tl:
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~. c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER: s~ ~ ~ u-o ~ - '1'-"- ~ J
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- 1. DOCUMENTED ERROR~ ~ YES
- 2. DOCUMENTED UNSAFE - / ~ YES CONDITION OR TECH.
SPEC. VIOLATION?" NO
- 3. HIGH SAFETY IMPORTANCE
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~SSIENT LAST REVIEW TITLE RESPOhSIBlLITY STATUS DATE 20Ae2"23e DISPLAY ClJTPIJT DCES NOT Ai..LOw ACCURATE READINS ENS II -5 87/11/85 K.Mfl ERROR:
DI~Y lNTER~RE,ATJOt,i ERiKlil, Ht PROBLEPI DESCRIPTI~: ERGS l~ifl{SJ REG READ1"6 r;: 25 (3el 6Pfil FD FI.W TD S6S.EX1ST1Mi 5aLE NJT ICCIJIR:Y, JNTEIMU Till Lo, 8780 PARASRA?rl NOOtR: Ei.S.1,2.A SIJSBESTED BACi<Fil: PROVIDE bULE 10 ~ uPtNATDR Tu READ 25 l.3el 6Pfil ~LCM,
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- HED NO., _\J ___r_- .le...
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- ASScSSIENT STATUS e8/23l8S LAST leVIEw DATE PAS£ 64 23M2243 I.JilT Yft.UE PR06RESSIC1\. II -5 88/17/85 KM. ERROR:
READIMi ERROR
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SF-i::flt FL.D IND PRu6RiSScS 111 UhllS It 7 r;PK. SLmSSJVE WlUcS lHDir.ATED BY UNIT &RADS &OU PR!:silESS BY IRPIKSl i71W PARA6RAPri NOO£R: 6.5.1. S. C
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Pt<"~i:D: SUt..ES lir.i:iCri lNCf<~t itY UtiiiS C~ 5 ~*
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REFE~ Tu Pl-71 l~lbl, DATA Cll.l.ECTluN DESC!UP1 !Oh ~ COllE ~ ! i : TP-9.a VERIFICATION PttD VA~Ia~TI~ l!EflAro<S: VD-08-2!1 PROB DESC: IJ!',j:i'rS ~ 1.2,5,10 Coii trJ...TF'L: TPII:~. ITEJIIS IWCLVED: l!AilK hi.Jll!B:f< LOCHTI~ COl!PQt,le.NT ~ SYS:Elli Fl-fit-2NA M hO"i llii JII\I .Fl~ t Fl-fw-2NB M NOT lN INV FILE
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- HUMAN ENGINEERING OJSCREPANCV (HED) REPORT . . "',i.0 \
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-177 APPENDIX 89 HED REPORT (CONTINUED)
<iJv<r~T/LNIT 1-£D NO.: YfJ-8
. f) SUGGESTED BACKF'IT:
g) REVIEW AND DISPOSITION:
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..... VJRCINIA POWER
' CONTROL ROOM DESIGN REVIEW ;2.. ()Ao -2.2.1,.
HUMAN ENGINEERING DISCREPANCY (HED) RECOMMENDED RESOLUTION
.STATION/UNIT __ ._.- * ~0V..v-f"y ()YI.if S + J. 2 .
MARK NO.*
- FT- j 00/1, B ,C ; 4' '
~ FT-.). 00 /I, 7 f, C ITEM DESCRIPTION /114Kifie rtl Fee./wl)fer
- Flow I
CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTION~
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- *** * .i COMMENTS:
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ORICINATOR_ _ E_._F...., ___tl_,_I_/___DATE REVIEWED *,r 7- ?S ,,,'
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VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5.1 GUIDELINE COMPLIANCE CHECKLIST 6.S.1.2 USABILITY OF DISPLAYED VALUES Scales should be graduated and numbered so that readings are related in a direct and practical way to the operator's tasks.
- a. SCALE SELECTION-Scale units should be consistent with the degree of precision and CAllf.
- accuracy needed by the operator.
- b. ELIMINATION OF OPERATOR* CONVER*
SION-AII displays should indicate values in a form immediately usable by the operator without requiring mental conversion.
- c. PERCENTAGE INDICATION-Percentage indi*
cation may be used when the parameter is meaningfully reflected by pe~ntage;
- d. SCALE RANGE-Scales should be selected to:
(1) Span the expected range of operational parameters, or (2) Employ appropriate scale ranging tech* niaues. or (3) Be supported by auxiliary wideQrange instn.iments.
- e. SCALE SIZE-Scale ranges may be expanded (or contracted) by multiplying or dividing indicated scale values by powers of ten. All such scales shou Id be clearly marked as to .
whether .the indicated values should be multiplied or divided, *and the factor involved (e.g., 10, 100, 1000).
- f. SENSITIVITY-Display dynamic sensitivity should be selected to minimize the display of normal random variations in equipment performance.
6.5-3
VISUAL DISPLAYS 6.5 . . *--:-:-.,_ PRINCIPLES OF DISPLAY 6;5.1 ***.;;.;.*."/ COMPLIANCE CHECKLIST 6.5.1.5 SCALE MARKING (Cont'd) N/A Yes No Reference/Comment
- b. GRADUATION HEIGHT-Graduation heights as a function of viewing distance should be as indicated in Exhibit 6.5-4.
VIEWING INDEX HEIGHT DISTANCE (inches) (feet) MAJOR INTERMEDIATE MINOR 1'h or less 0.22 0.16 0.09 3 or less 0.40 0.28 0.17 6 or less 0.78 0.56 0.34 12 or less 1.57 1.12 0.65 20 or less 2.63 1.87 1.13 Exhibit 6.5-4. c*. VALUES INDICATED BY UNIT GRADU-ATIONS-Successive values indicated by unit graduations should be one of those shown in Exhibit 6.5-5 or those values multiplied by some power of 10. :5~
/
GOOD FAIR 2 3 4 5 2 4 6 8 10 5 10 15 20 25 20 40 60 80 100 10 20 30 40 50 Exhibit 6.5-5. Recommend progression of values (from McCormick, 1976).
- 6.5-8
NUMBER PROCEDURE TITLE REVISION 6 l-ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS PAGE 3 of 25 STEP ACTION/EXPECTED RESPONSE 1--~~---4 RESPONSE NOT OBTAINED i--~~~~~~--, CAUTION: A minimum of 105 gpm [168 gpm] feed flow must be maintained to each SG with a narrow range level less than 9% [32%].
- 2. CONTROL FEED FLOY TO MINIMIZE RCS COOLDOYN:
a) Check cooldown rate in RCS cold a) Lower feed flow to 105 gpm legs - LESS THAN lOO~F/HR [168 gpm] to each SG. GO TO Step 2c. b) Check narrow range level in all SGs - LESS THAN 50% c) Check RCS hot leg temperatures
- STABLE OR DECREASING b) Control feed flow to maintain narrow range level less than 50% in all SGs.
c) Control feed flow or dump steam to stabilize RCS hot leg temperatures .
NlMBER PROCEil.iRE TITIB REVISION 2 1-FR-H.5 RESPONSE TO STEAM GENERATOR LOV LEVEL PAGE 3 of 4 STEP ACTION/EXPECTED RESPONSE t--~~"""'""1 RESPONSE NOT OBTAINED I--~~~~~~-. CAUTION: AFV flow should NOT be established to any faulted SG that has been isolated unless needed for RCS cooldown.
- 3. CHECK AFFECTED SG(s) SECONDARY IF pressure in affected*SG(s)
--SIDE INTACT: . decreasing in uncontrolled manner OR completely depressurized, THEN
- Pressure in affected SG(s) - do the following:
STABLE OR INCREASING a) Check affected SG(s) isolated:
- Pressure in affected SG(s) -
GREATER THAN 100 PSIG 9 Steamlines (* 11 Feedlines
- b) IF affected SG(s) isolated, THEN RETURN TO procedure and step in affect.
IF NOT, THEN GO TO l-E-2, FAULTED STEAM GENERATOR ISOLATION, STEP 1.
- 4. __ CHECK AFY FLOY TO AFFECTED SG(s) -
- IF affected SG(s) wid~ range level GREATER THAN _105 GPM [168 GPM] greater than 11% [26%], THEN establish AFY flow to refill affected SG(s).
IF affected SG(s) wide range level less than 11% [26%], THEN establish AFY flow to affected SG(s) at a rate NOT to exceed 105 gpm [168 gpm] per SG.
- 5. __CONTINUE FILLING AFFECTED SG(s)
UNTIL NARROY RANGE LEVEL GREATER THAN 9% [32%] (
Dti TE :L / l O/</;,:: .......... _......................-......_.... .... .... ... . .. ................................... **- ............... *-* .............. -** ... **- .................... *-* ............................. *-* .................. -** .................................. ,.., ........................ -** ................ -** ........................... -* .............. **- .. - **- ........... -** ................... *-* .......... ~-* ... -* ..... -* . r, ,., l *..,,: .. 1::,1) .;;.,,::. 44 *lb odu,,,.,.,,,,.,,, .. , *n*-**** _,,,,,, .. ,,,.. ,,,,,.,,,,,,,, _,,,., ,,,,,,,,,.,,,.,,,,,,,,,,,, .. ,, ..,,,,,,,.,,,,, *H ,.,.,,,o,m**0'*""' .... ,,, . .,,,.,,,.,,,..,,,,, .. , , .. ,_..,..,.,,,, .. ,..,.,,.,,,,,,, .. ,,_,.,,.,.,.,.,,00,,, ,.,,,,,,,.,,,.,,,_,,,,, .. ,,,, S C U H Dt1TF L B 1'\ INS'I h:IJ HIOH 1.. 0\i.! lESTEIJ l l.. N Rt'\NC:iF lNSTFWMFNT IN'.iTl\:LWiFNT PO I NT INPUT I M UNCtli'N RANGE Rr'.',Nf;E J [I NUMBI:]:: N I( N E I( l.. 0 00 "'"' * "**N * * , ,,.. **** ,,,. "'"", ,. N***- - * ' " ' ' " ' " **-******** ... , , . . . ., , , . . , - * ,,,. ,,., ,.., , .. , - , - , , ,, .. ., ,,. ,,,, * * * * * - " ' ' *** """"' ,_. , , , ******** , . , -
- o**ONN or,,,,,..,,, .. w-o * * * * * * ' " ' ' , , , , . , . . , , , , _ , - * * . . , , , , , , , , . , . , , , , . , , * * * . . , . , , , , . , . , , . , , , . . , , . ' ' ' " ' " ' **** . . _ , , , " ' ' , . . , . , . , _ , . , . _ , , , . ' ' " , , , , , , .. - *-* '" *** * * ' - * , , , , ,. . , ** ' ...., " ,,.. ,,, _,,.,,,,, .., *-**-**'" O*O _ , , , , . _ , .. , *- N*' ' - * * , , , . , , ,. ' ** , . , , , .. , .. , *** *** **' ** * * - ' ' ' ,.,.
0 CNTMT IR PRESSURE (RD> <> 1 0:1. 1 .. *0bDC {if.:,. () (). 0 F'~Hi': PlLViOO?f.1 :I.EiOl .... OJ.(1 :l.**I..Vi +*T**.. lOOi'I CNTMT SUMP WTR TEMP (RD) :I. ()~? 1-**0bOC ::100. 0 0" () ULGI' T1RG001A 1S0l-02A 1 .. RS-RTD .. *150A 0?****04***f~6 01 1 (\';*
, ... , 1 ... w;uc 1.!:i() .. 0 0 .. 0 Lll:"Gr*
T:I.C'.;OOJh :1.!:i()J .. ,o:xi l"*CG**l;:Tl}*JOOA Rl*.!GT TEMF'EJMTllRE (RDi 1S01-04A l-RC-Fr-1414 f/CS LDOP t, FUH,,t (F:0) :l. (),l 1 *-*0!:iOC 1;::0.0 () "(l PCT RCS LOOP B FLOW <RD) 1. 0!5 1.... 0,:*;uc 1. :,:'0" <) ()" 0 F'CT RCS LOOP r FLOW (RD> 1 06 1 .. *0::iOC l?O.O 0 "() 1:ocT F1RC010A 1S01-06A 1-RC-FT-1434 1... Obi.IC 1.()0 .. 0 ().. 0 f-'CT I...JC~:;oOJt1 :I.GOl .... O'/A :l.**C!:i**Ll*-*1001*~ RWST LEVEL (RD) <> :I. ()7
- l()(). 0 0 .. 0 ,:,i:: r L1FW002A 1S01-08A 1-FW-LT . *Ji71 BG t', NI~ LEVEL HU)) <> ,:)?***04*-!:U, 01 1 ()!;;) 1**.. 0l:iDC 1* .. 0bDC 1.()0 .. 0 0 .. 0 1-'CT L1FW006A 1S01-09i'1 1 .. FW*LT-1484 SG R NR LEVEL CRDi <> 1. 09 1..1FWO:I.OA 1S0l-*l0A .1. .. FH-Ll-1494 SG C.NR LEVEL (RD) <> 0~~--04* *H6 () 1 :I. :1.0 1 ** .. (i:50C 100 .. 0 o. o PLT LOUP f-l wr;: T COLD mD) <> 0:?***04**~M 1 ll 1*-*0bDC 700 .. 0 () n 0 [IFGF T1RC004A :I.S01-11A 1-RC-Tf-1410 ()1
'f:1.Rl:OObt, 1!:;0t***:1.?l, *1 ... r::c . . Tl*:***l. 11:1.:::: I... UDF' ?\ ~,IF{ HOT LEO TEMP *:RD) <> O? .... ();J,{::6 O:L .1. :1.:2 1 **()\:iUC 700. () () "0 DEGF
- I. :i.3 :1.***0!:.il."IC J. I)() n () (). 0 !"CT llRC003A 1Ei01-18A 1-RC-1...1-145?
F:I.F!1lOOi.i-'1 :I.DOl* .. :l.*it, l***F~I .. F'!"***:i.OOt, SG ~ AFW fl..OW (RD> 00-00 01 :I. 1.1\ 1 .... ()t50C 3!.:iO"O o. 0 !WM 1SOl-:l.bA l-RC-*F'T-1456 PRES~URIZER NR PRESSURE (RD) 1 1!::i 1 .... 0!::iDC ?!:;oo. o 1700.0 P::IIO
- I.* 16 ;:'.00. 0 o.. o l<!IG 1 :1.7 :L**.. ObDC 1.bO .. O O .. *O !"!HO J. :Ll.:: :L**():'iOC :1.00 .. 0 ()" 0 F'CT 1..:1.u;oo1.,:*, :U30:l.***:l.1*::i:i :1.*Cfl**I. i'**:1.0:1. F/t:FIH::L.lNE l'!(\Tt:r:: C/.)T L.El.!1:L ,:i-::O) 0?***04 .. {M O:l 1 19 :I. ,.. ()bl ,c: 400 .. 0 . ,c, .o llF.UF TJI..NOO.lt1 :U:iOl .. *l'/i\ :l *!.M*F(il}*.IC*O:!.? CO!'fi(:Ih!M[IH Tl*l*iPEFi:/\TI.JRE (h:D:* .10*-:I.? *:::!U O:l
Dl\lE :L/.1.0/(i';? f;i.Jb:l'~V 1*,!Uh:FG 1M'/<'.i COMl'*'UTl:1:;: lNPl.ll/OUTPUT l..JfiT
'.1HLET 1 OF THE 1'*\N(1LOG JNPlH CONIIEN::.iED REPOIH LIM!{, HUl::I.. INf{ *1 Cll<:,h!NEL. '.HWT 1*;1*,
- I. ,::*,::. 4 l.,O l li2 F
**. I D<HF L INSlh:U HIGH LUM r:>l'WH P(l I NT JHPUl POINT DESCRIPTION lESTED J R<)NGF lNSTFWMENT Il*~~\Tlil.JHENT UN i TS J [I NUME:EF-: N,,
UNCONV RANGE Rr1NDF I*, "i :1.r~co~::uh V:i?4***:t4t1 1--:;:c *TF ..*1 11G:? PRZR SPY LN LOOP B TEMP (RD> 08-08 . *90 01 2 14 1-0bOC 600. () 1. 00 .. 0 Dl::i:iF T:I.Cll002?, 1~;24 ... Jf:it", :I.* Cl+*n:: ... :J.:J.4:::: 08-08**90 01 2 15 1-0BDC :~ ()(). () TJCl*IOO:::i'.l :1.s?4 .... J61'\ 1 .... ,:,;i-1--.. r[ .... J :1.4() REGEi~ Iii( LDl*l LM THiP <RD) os--0::: ... 90 01 :;.*. 1,.s :1.-.. 0!:,nc ,.SOO. () l 00. 0 DFGI* T:1.Ci-100-llP, :1.~l?4***:1.ll1 1 .. CH-.. TL ..**:1.:J.2:::: li:EG1*:N HX rn.rru:T TEMP (f.:[I) 08-08-90 01 2 :J.7 1-05DC 600.0 JOO .. 0 Ul:.GF F:1.CliOOlf.i 11:*::-:'.4 ..-:I.Uii :L .. *CS .. *FT .... 100(1 CNTM1 SPRAY PUMP 1A FL.OH (RD> 08-08**90 01 2 18 RMRKSE 0.0 (il*'l"i F1RH001A :J.S02*-01A 1-RH-F*r-1605 R[SIOUAL HX BYPASS FLOW CWT) 01-08 .. *86 01 3 01 1-050C 0 .. 0 13PM Tl RI 1001 f-1 rno;;~- . 02(1 :I. "*W*I*** T[ .... 160{, W IR H:{ OUlL.ET TEMPER/.'ffl.lli'.E rnn () 1**0G**IJ6 01 ::l o:t 1***0bDC 400. (i bO. 0 [IFGl* P1SX002A :LS02-08A :L-SI .. *PT-1921 ACCI.IN T r~,NJ*: 1 PREBSURE (!,IT) 0:1.-08-86 01 3 03 1-050C 800.0 o. o r*:nc P1Sl006A 1S02-04A 1.. *Sl-Pl-1929 <:i'.l. **08 *86 1) :L ::: 04 1 ***051:tC f::00. 0 0.0 l**SIG 1.:1.SIOO:?A :LS02 .. 05A. 1-SI-*Lr-1920 ,;CCIJi' lUUYfDf*;: Tl'1NI( 1 LEl)F.l. rnr:i 1 01-08*86 01 3 05 :L-050C 100.0 0 .. 0 F'CT L1SIOO~A 1S02-06A :J.* .. Sl . Ll'-1921 ,~CCUMULA TOR Ti'il'll( 2 UJ,lE'L (If!'> OJ-09* .. 86 01 3 06 1-05DC 1. 00. 0 0. 0 l**i:T L1SC006A 1S02-0J~ 1-SI-LT .. *1928 t1CClli*lUL.1Yr1:m T:'\N)( B l..[l)EL (~In 01-09**86 01 3 07 1-05DC 100 .. 0 o.o r*n L1FW004A 1S02-08A 1-FW-Ll-147? SG A WR LEVEL CWT> <> 100. 0 o. o r-*cr LtCIIOO?t, :u:;o:>*O?t'.', .L**[Jl ..*LT**l:1.1!:i Wil...llME co;..n1;:D1. TM*II( L.El)IJ_ (\*IT) Ol-.. 09*F:(, ,:)1 ::1 09 :L*-*O\:iOC 100 .. 0 o. o r*n P1Sl004A 1S02-10A 1-Sl-PT-1925 01 *.. 0'7'* *:::!6 0 :L '.:: 10 1 .... 0bl.JC f::l()().() o. o ::-::au F:lF~*lOO?(\ :1.no:~ ..*l:i.l\ :1.-*F!*l**F'f**:l.OOi:; SG 8 AFW FL.OW !WT) 00-00 01 3 1:1. :1.-0GDC ,3!'::o. o 0 .. 0 bf'M M:I.NMOOJA 1S02-:l.2A N42 10-08**86 01 3 12 0-0GLJC 1?0.0 0 .. 0 PCT M1NN008A 1S02-:l.3n N32 NLIJfF:Dr*l ll.UX f;r:: f..ElH:l. (!.-!T) t0-?2*-86 01 3 :1.3 0-050[: 6 .. 0 0 .. 0 1.!JGCPG M1NM006A 1S02 . *14A N36 N:C:UlliD/,1 I'* U.J>! H~ 1..E'.lEI.. (11.IT:, J0-22**86 01 3 14 0-0bLJC *-* 11. .. 0 I. OGi\MP
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£0'd ll:llOl 1 WESCHLER ;iX-252 INDICATOR REPLACE; DIAL CARO EXISTING 1..ASELS INDICATOR ON 'THE F'OLLOWINO ON INOIC.A TO~ L.OCA TION \.._....-- 500 INOICA TORS AS SHOWN (NO CHANGE) 1-FW-F'l-100A AUX S'IM OEN 1A F'D WTR FlOW ,-2eo.
VE~T. I 400 1-FW-F'l-iOOB AUX S'TlJ GEN 19 V£Ri. BD. I I ro WTR FLOW 1-2 1-FW-Fl-,ooc .4.UX S' G£N 1C VERT. ao. F"D W1R F'LOW 1-2
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- 3. GRAOJJA TION LINE: SI ZE:S:
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11.12 CORRECTIVE ACTION EVALUATION CA NO.: 12E CA DESCRIPTION: Redesign Permissive Status Lights to ensure consistency in terms of messages, illumination sequence, location and arrangement. EQUIPMENT MARK NO. HEDNO. 20A02303 20A02315 Various permissive, status, bypass lights 22A02308 20A01313 11.12.1 BED REVIEW - ORIGINAL FINDINGS HED No. 20A02303 - Permissive status light indications are inconsistent. (NUREG-0700, Section 6.5.3.1.c) HED No. 20A02315 - System/equipment status is inferred by indicator light being off. (NUREG-0700, Section 6.5.3.1.c) HED No. 22A02308 - Legend message contains more than three lines of text. (NUREG-0700, Sections 6.5.3.3.b.5 and 6.6.4.2.d.3) HED No. 20A01313 - Incomplete standardization among panels of Unit 1/2. (NUREG-0700, Section 6.8.2.4.a) SEE A'ITACHED PAGE 11.12.1 continued
- 11.12.2 HED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs DYES IXINO ON/A The permissive status lights are used in EOPs (i.e.,
1-ES-0.2). The permissives are also utilized in OPs particularly* during plant startup and shutdown. RG-1.97 purposes. DYES IXINO ON/A The permissive status lights are not used for RG-1.97 EPIPs 0 YES IXI NO O NIA LERs/lOERs DYES IXINO ON/A The permissive/status lights are not described in the No LER.s/IOERs were found concerning the permissive/ EPIPs. status lights, however, during the original CRDR it was reported that the plant had been tripped erroneously due to existing displays. APP.R DYES IXI NO D NIA HPES/STA DEV/SOER DYES lxlNO DN/A The permissive status lights do not impact the Station's No station deviations or SOERs were identified compliance with Appendix "R" to 10CFRSO. regarding the permissive, status, or bypass lights. ERF/SPDS DYES lxlNO DN/A TECH SPEC ITEM DYES Ix! NO D NIA
- The permissive status lights are not related to ERF/SPDS.
VARS01E.B7S-1 The permissive/status lights are not Technical Specification components.
- 11.12.1 HED REVIEW - ORIGINAL FINDINGS (Cont'd)
During the original CRDR display and labeling surveys, it was determined that the status lights do not follow a consistent pattern of desired status (some lights are illuminated, while others are oft). The permissive lights contain more than three lines of text which may result in operator delay or response in reading the description. The arrangement of status lights between Unit 1/Unit 2 panels is nonstandardized and may possibly cause confusion to operators. DC-90-04/05 would implement the following: For trip, bypass, and permissive status lights on the Main Control Room Vertical Board 1-2, redesign lamp sequence such that lamps are
- on to indicate abnormal conditions and extinguished to indicate normal conditions during on-line plant operation. Also, rearrange the trip, bypass, and permissive status light*
windows to provide a sequence that extinguishes the lamps from top to bottom as the unit ascends from refueling shutdown to power operation. In addition, new re-engraved lenses would be installed .
-i
- V ARS01E.B7S-l
11.12.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- Although the current trip, bypass, and permissive status light are not sequenced, emergency and operating procedures state whether the status lights should be illuminated or dark, operators are trained on the existing configuration. The engraving on several status lights is not consistent and new engraved light lenses should be installed.
Safety Significance The permissives are nonsafety related components, however, during the CRDR previously performed, operators reported it was difficult to read engraving and have subsequently tripped the plant due to error. Potential for Error The potential for error is high if the labeling of status lights is not clear and if the operator has difficulty in his ability to read the associated display. Consequences of Error - The consequences of error would be the potential misoperation of system controls. Automatic protective fel!tures are available to compensate for this error . 11.
12.4 CONCLUSION
S/RECOMMENDATIONS Based on the above information and subsequent reviews, it has been determined that approximately fifteen status light windows should be engraved using consistent nomenclature as specified in the EOP/OPs. The re-engraving of the status lights will reduce the potential for operators to misinterpret the information presented on the status light lens. The CRDR reassessment has determined that the engraving on the Unit 1 and Unit 2 permissive status are consistent, therefore HED 20A01313 is closed .
- V ARS01E.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION INUREG-0700 SECTIONS D I EOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
10/7/86
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NOTED .i AN A.SSESSIENT 88/cl/85 ~ 2 ') 19~~ LAST REVIEW l3 H.W.B. TITLE IIESPOhSlBILITV STATUS DATE 20Ae2383 PERlll1SSIIJ£ STATlJS LISHT INDICATIONS ARE JNCONS!STENi, Il -s 88/@7/85 K.M-. ERROR: IIAY CAt.6E DAl!A6:. TO SYSTEIII ~ ~Y/ERROii lN ~AATDR ~
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StJiltE STATUS LI6HTS INDICATE DESIRED STATLIS IIEN Ll6HTS ARE ILLIJ!lNATED, DTtERS lt£N TtEY ARE OFF, S7~ PARAGRAP!i Nlt!EcR: D,5,3.1,C Si.:36ESTED BRC!<FIT: Il:.'"TER'-l~ ll!OST AilvAtiTAai:M COHIIITIONS FO~ Ci< 1,ii:RSIJNN8. FOR VEiilFICATI~ Dr STATLIS AND USE IIWSISTENTLY TttRUOIJT,
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TP-5.l DISPLAYS l May 1983 APPENDIX 89
- HUMAN ENGINEERING DISCREPANCY (HEO) REPORT * ; D?
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sv erev lu/11 u;,,s t PLANT UNIT 1.l "2,.0 r>- ORIGINATOR: f).,4,,..0 ) Ili ~ HO) NO.: pr. - 6 ~ . VALIDATO)BY: ~ DATE: ~ - / in!y a)HEOT~TLE: . ** St:i&r,.a~ ~ (k'.\6, ~4~ I b) ITEMS INVDL VEO: f~~~~(,}2-e) SPECIF"JC HUMAN ERROR(s):
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TP-5 ..l DISPLAYS l May 198) ~* APPENDIX B9 HED REPORT (CONTINUED)
!u1<,?,V(\J1JtTS I*~ 6
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HED PRIORITY .RECORD (* I HED' (.pq
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE YES YES CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE. NO
. (PAM OR 1E)?
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- 4. ERROR POTENTIAL? __L_
LOW 2 a
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- 5. CONSEQUENCE OF ERROR: 1 caw 2 3 0 5 -L.
HIGH s::ATEDOIIY I NO 1K)
- lt:ISESS!L'i.1-: ;.AS".' ii:v:i Ew TITLE RESPONSIBILITY STArus i, DATE
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III-9 "8/97/85 lt.M ERPCOR: cJ\)G ERll'JRS lh OP RESPONSE FRQII ER!IOIIEOUS RS&Jl!PTIOIIS OF iJ!JflT STATIJS DUE TO lllRNcD OJT BIUS, fff PRDEl..BI DESCRIPTI~: SYST~/EM?IENT STATUS IS 1,-.""ERi!ED BY INDICAT[)R LI611i BE1fl6 !FF INSTEAD ~ IL.W(I~TED. 07~ ~RAS~ NilUiEII: D.5, 3.1, C SU66ESTED BAD<FIT: . Ev~..:JPiE CONSEif.F.1;::s ~.: *r:.1::E"'="' ::r..F- T~ T~~= .. ~~!:!;.£* ~ r= ~~TE~-:-!q_ ~zci:m, :i:-v:~ss. (. fft DISPOSITHli\:"fiwo.Qc-e, i'T.ft.\-'u1i.-J a.C':. 1,e. ~;..u.lvuO.. t;c: ~;~i;r(20~~~im\l)~a> DATA CO'..i..ECiI~ DESCRIPTION ~ CODE iUBER: TP-5.l DI~AVS SLIRVEY ITEMS llWOL~: MIit( ttJ!II.BcR LOi)lTir,. ~JN:t.'!' ~ SYSTE1 SUBSYST91 PEll!IIS ST LTS ff NJ: lh INV rli.E
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TP-5.1 DISPLAYS l May 1983
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APPENDIX B9 HED REPORT (CONTINUED) y/u O'tTS. I PLANT/UNIT
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- LAST REVIEW mu RESPOhSIBILITV
- STATUS DATE
~3@8 l.ESEND* 1ESSA6E CQIITAINS MORE ~ TltNEf L.lfES OF TEXT. II -6 85/82/85
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DELAY IN ~ RESPONSE. fff PROILEM DESCRIPTION: LESEND !IESSASE CONTAINS l(li!E 1~ T~i!EE LINES OF Text. 07io0 ~RAGRAP>i NOOIEli: 6.5.3.3.B.5 6.6.4.~.u.3 SUS6ESTED BACKFIT:
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V 177.' TP-5.1 DISPLAYS l May J9R3 APPENDJXB9 HUMAN ENGINEERING OJSC"'.REPANC:V fHE:D) REPORT Pl.ANT/~
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VAU DATED B V:
- 4. ~~ DATE:
a) ~D TITLE: LE6-EN~ ~e.~s~ Co.rt~,..,s., b) ITEMS JNVOL VCD: LE.G-E..,b 1..1'1K't~ ~t::c..,10~ Lf, (,~,p s,~.,.v~ Llv\.l"t\ f1"IP .!"'Ttt"f"~ L.,lv\,i,.tJ
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d) DAT A COLLECTION DESCRIPTION ANO CODE NUMBCR: DISf<J.'f > ,p ~. I ~ "!), 1'2 e) SPEClrJC HUMAN ERROR'sl:
. 177
.- TP-.
- DISPIAYS l May 191
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. .VIRCINIA POWER
- CONTROL ROOM DESIGN REVIEW 2 0,4 ~- /JD 7 HUMAN ENGINEERING DISCREPANCY (HED)
RECOMMENDED RESOLUTION STAT ION /UN IT _ _ _ S____v_.._.,,_,y___u__* +_1_______ _n_;__ MARK NO. 1TEMD ES CR IP TIO N Trip, Bu/Jv[5 B ferY"J;S.ri.1.- Sia.fv.r L;rldr r 1 1r
- CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS)
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COMMENTS: 0R1G1NAT0R_*_ _ B_._F_.__/j__;__/_/___oATE REv1eweD_ _1. . ~__J_o_-~?_£' ___
VISUAL DISPLAYS 6.5 CA\2t LIGHT INDICATORS 6.5.3 6.5.3.1 CHARACTERISTICS AND PROBLEMS OF COMPLIANCE CHECKLIST LIGHT INDICATORS (Cont'd) NIA Yes 'No Reference/Comment
- c. PRECAUTIONS TO AVOID MISINTERPRE* .
TATION * ( 1) System/equipment status should be inferred by illuminated indicators, and never by the absence of illumination. (2) Provisions (design or procedural) should be made* to prevent interchanging indicator lenses.
- d. USE AS ALERTING INDICATORS-Alerting the operators to unfavorable status should be a function of the arinunciator system and not assigned to light indicators
- I I 6.5-21
VISUAL DISPLAYS 6.5
*~
LIGHT INDICATORS 6.5.3 . '*
;i COMPLIANCE CHECKLIST N/A Vn No Reference/Comment 6.5.3.3 DESIGN AND USE OF LEGEND LIGHT INDICATORS (Cont'd) t:*. LEGEND DESIGN
( 1) General legend design should be consistent throughout the control room. (2) Lettering should be simple, and should* follow Guideline 6.5.1.3 for style and size. I (3) Symbolic legends should be clear and I
- unambiguous as to their meaning; I I J (4) Text should be short, concise, and i I II unambiguous.
I (5) Legend messages should contain no more I than three lines of text. I I I
/ (6) Nomenclature and abbreviations should be standard, and consistent with usage .. I throughout the control room and in the I
- CA 12 E. procedures. I *. ,. \
I (7) Legends should be worded to tell the status indicated by glowing of the light. I !
- c. DISTINGUISHABIUTY FROM LEGEND i PUSHBUTTONS-1 lluminated legend indicators should be readily distinguishable from legend I pushbuttons by form, size, or other factors.
- d. COLOR CODING-The co}or of the legend !
i background under transillumination should I conform to the general color code established I for the control room. (See Guideline 6.5.1.6.) I
- 6.5-24
... *, ..... ~** - . . . . . .. ..........*.
LABELS AND LOCATION AIDS 6.6
--- " LABEL LETTERING 6.6.4 GUIDELINE COMPLIANCE CHECKLIST 6.6.4.2 STYLE Recommended character styles are shown in Exhibits 6.5-1 and 6.5*2.
- a. CHARACTER SELECTION (1) Labels
- should be prepared in ~pital letters.
(2) The design of letters and numerals should be simple and without flourishes or serifs*. 1----t---+--+-----------,
- b. CHARACTER WIDTH
( 1) Letter width-to-height ratio should be between 1:1 and 3:5. (2) Numeral width-to-height ratio should be 3:5 except for the numeral "4" which should be one stroke width wider and the
- numeral "1" which should be one stroke in width *.
- c. STROKE WIDTH-Stroke width-to-charac.ter height ratio should be between 1:6 and 1:8.
- d. SPACING (1) The minimum space between characters should be one stroke width.
(2) The minimum space between words should be one character width. * (3) The minimum space between lines should f be one-half of the charact~r height. I '----.____.__ _,_________ --i l L-Prl2E. ~. 6.6-21
..:***=****. *-*- **- ... -*. ' .. . ... . - ........ .-... - .
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GUIDELINE
. PANEL LAYOUT LAYOUTARRANGEMENTFACTORS 6~2 6.8 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.8.2.4 STANDARDIZATION When a precedent has been established in the arrangement and location of controls and displays, that standard practice should be followed unless other crucial considerations necessitate a change.
- a. PANEL TO PANEL STANDARDIZATION-Standardization should be maintained where similar functions or panels are located at several work stations or units and must be used by the same personnel.
- b. SIMULATOR-TO-CONTROL ROOM STAN-DARDIZATION-Standardization should be maintained where simulators or procedure
\. trainers are used that simulate the actual operational equipment.
\ \
6.8-9
NUMBER PROCEDURE TITLE REVISION 5 l-ES-0.2 NATURAL CIRCULATION COOLDOWN PAGE 6 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED i--~~~~~~-. CAUTION:
- On natural circulation, RTD bypass temperatures and associated interlocks will be inaccurate.
- SI actuation circuits will automatically unblock if PRZR pressure increases to greater than 2000 psig or RCS Tave increases above 543°F.
- 9. BLOCK HI .STM FLOW LO TAVG SI:
a) Turn both HI STM FLOW & LO TAVG OR LP switches to block I b) Verify Permissive Status light b) RETURN TO Step 7. F LIT
- 10. DEPRESSURIZE RCS T0.1950 PSIG:
a) Check letdown - IN SERVICE a) Try to establish letdown. IF letdown can NOT be established, THEN use one PRZR PORV. GO TO Step 11. b) Use auxiliary spray c) Turn off PRZR heaters as necessary i" lii u
NUMBER PROCEDURE TITLE REVISION 5 l-ES-0.2 NATURAL CIRCUIATION COOLDOWN PAGE 7 of 14 STEP ACTION/EXPECTED RESPONSE 1--~~---1 RESPONSE NOT OBTAINED t - - ~ ~ ~ ~ ~ ~ - - .
- 11. BLOCK LO PRZR PRESSURE SI:
a) Verify Permissive Status iight a) Continue depressurization. C LIT 'wHEN Permissive Status light C-3 is lit, THEN do Steps llb and llc. b) Turn both LO PRZR PRESS & STM HDR/LINE .6.P switches to BLOCK c) Verify Permissive Status light C LIT
- 12. MAINTAIN RCS CONDITIONS:
a) RCS pressure - at 1950 psig b) Pressurizer level - at 22% c) Cooldown rate in RCS cold legs
- LESS THAN 25 °F/HR
- 13. MONITOR RCS CODI.DOWN:
a) CETCs - DECREASING b) RCS hot leg temperatures - DECREASING c) RCS Subcooling based on CETCs
- INCREASING
- 14. INITIATE ATTACHMENT 1 i
11.15 CORRECTIVE ACTION EVALUATION CANO.: 15E CA DESCRIPI'ION: Rearrange EDG #3 panels to be similar to EDG #1 and EDG #'2 and label accordingly.
/
EQUIPMENT MARK NO. HEDNO. 20A03033 11.15.1 BED REVIEW m ORIGINAL FINDINGS HED No. 20A03033 - EDG no. 3 panels (3-1, 3-2) are arranged differently from 1 and 2. (NUREG-0700, Sections 6.4.1.1.c.2, 6.4.2.2.c.1 and 6.4.2.2.c.3) CRDR controls surveys identified that the emergency diesel generator control panels EDG 3-1 and 3-2 are not arranged similarly to EDG panels 1 and 2. This discrepancy could cause delay and/or errors in operator response due to lack of conformance with operator expectations and does not conform to NUREG-0700 guidelines (6.4.1.1.c.2). In addition, different size controls and coding*_parameters are used (6.4.2.2.c.1 and 6.4.2.2.c.3). DC-88-25/26 were prepared to install new EDG panels 3-1 and 3-2 in the control room. The new panels would be arranged similarly to EDG panels 1 and 2. In addition the layouts of the local EDG control panels (1 DIP-DGRH, 2 DIP-DGRH) would be revised. The DCPs were not implemented.
- 11.15.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs !mYES ONO ON/A Instruments and Control devices on the EDG #3
. are used for verification of EDG operation RG-1.97 IXIYES ONO ON/A EDG #3 Panels contain instruments for monitoring RG-1.97 variable D-35F, EDG load .
and setpoints in various EOPs including 1-ECA--0.1, 1-ECA-0.0, and l-E-1. EPIPs 181 YES ONO O NIA LERs/IOERs DYES IXINO ON/A EDG #3 Panel meters are used to verify No LERs were found applicable to the control of the emergency classifications for EDGs. electrical failure (Tab H). APP.R IXJYES ONO ON/A HPES/STA DEV/SOER DYES IXINO ON/A EDG #3 Panels are Appendix "R" No applicable station deviation/SOERs reports were related equipment. found. IXIYES ERF/SPDS DYES l&INO ON/A TECH SPEC ITEM ONO ON/A The EDG Panels are not part of the EDG #3 Panels are required by technical ERF/SPDS systems. specifications. VARS01F.B7S-1
11.15.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The EDG control panels in the control room are used by the operators to control and monitor the operation of the station emergency diesel generators and associated 4160V emergency buses. These panels are used during the performance of various EOPs and EPIPs.
Safety Significance - The EDG panels contain safety related, Class lE components that are also required for R.G. 1.97 and accident recovery functions. Potential For Error - Discrepancies existing between the two EDG panels for the most critical control switches for emergency bus breaker operation and EDG control are minor. The location of the grouping of meters needed to verify EOP parameters for EDG Watts, Vars, and speed are different between the two panels, however, the style of these meters on each panel is the same and no other meters of this style are located on either of the panels. The uniqueness of the style of these meters on each panel reduces the possibility of operator error. The panel location of the reserve station service bus amps and the EDG output amps is similar with respect to the top and vertical panel boundaries. The same is also true for the synchronization voltage meters. This relationship aids the operator in finding the correct meter. Other meters on these two panels have faces that uniquely identify their functions, which also aids in correct meter identification. Based on the above, the potential for operator error due to this HED is considered low. During the CA reassessment it was noted that the EDG watts and vars meters on the EDG panels do not have consistent scale units. EDG panel 3-1 and 3-2 have megawatts/megavars units, EDG panels 1 and 2 and the local EDG control panels have kilowatts/kilovars. The potential for error is increased when the meters scales are not consistent. Consequence of Error - Operator errors* in the control of the EDGs or misinterpretation of associated displays may result in misoperation of the emergency buses, which in tum may result in the failure of plant protective equipment to perform their intended safety functions. However the
- probability of an error resulting from the controls arrangement is low. In addition the consequences are reduced due to the availability of protective features. The consequences of error due to the inconsistent power/vars meters between EDG panels is a delay in*
operator response when determining displayed values. II.
15.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion, sufficient information is presented to justify not implementing this corrective action.
. --~
The potential for error is low based on the minor differences between the EDG control panels. However, it is recommended that the EDG panel indicators (watts/vars) be modified (replaced) to be consistent between EDG panels. The reassessment process for this corrective action included a qualitative analysis to determine if the benefit of the proposed corrective action was commensurate with the total projected cost of the modification. Based on this evaluation, it has been determined that there is no appreciable benefit to the improvement of plant safety, operations or human engineering principles, which justifies the projected high cost of the modification .
- VARS01F.B7S-1
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST D RG-1.97 D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
- J}_r
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JSE'
. 8812318:,__,,~ .. ~9 "TED I A " 1 ? ", ~ .. :,,: H.\lL.,
SURRY lliIT e CODE R Nu ._I * :,; .:..i ..; ,., ASSESSfl:tff !AST REVIEW TITLE RESPOISIBILITY STAnJS DATE 2@Ae3e33 BER6EliCV DIESEL. Mt£1.S l ~ 3 AR~ DIFFERE.~TL.Y FROfi! 1 AND 2. II -S IU/17/85 KM ERROR: IELAY DR ERROR IN OPERATOR liESPDNSES tff PlllrtlM DESCRIPTIDh: aER6fN'.:V DlESa PANELS 1 AND 3 A l i ~ DIFFERENTLY e1ee PARAl3RAPl'I NUGEA: ri.1t.1.1.c.2 o.4.c:.2.c.1 E>.'l.,.~.c.a SUSGESi'ED BAC~!i: AE-ARij~ iO A COHS,STANT PATTERt. AC:IIO$ PIWtl.S fff D!SPOSITiilh: fl , i ._ f)
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TP-4. l ~'TRul..S SiJII\IEY REIIARi<S: PI-tile IIEB'IT 1B ~16N RESP FOR AAkiWS01cN I 5ldll¥ IP/ll Pi Ei2 >- ITW IN\11l.\D: Ml!I< UBER LOCAT l!),i CDIJICINth1 ~ SYST91 ED6 Phi.. 1 ff MJT lN lNV FILE* EDS Pk. 3 ff r<<JT IN INV FILE
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TP-A.l CONTROLS 1 May 1983 ~ *. APPENDIX B9 HUMAN ENGJNCERJNG DISCREPANCY (HEO) REPORT TR 1Z y I ON 11] I r1 ~ '2 0 Pi
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.__i V PLANT/UNIT I ORIGJNATORi £')_\ e d62S) )~ HEP NO.: P7 - bJ .
VALIDATED BV: ~.. i DATE: ~,,, 1; /'z P!:/ a) HEO TITLE: Y'ti1?i& r ~ ~ c ~ . ~
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~ c *
,~ \-n., ~ ~1;.i-y b) ITEMS INVOLVED:
£_µ_~~
c) PROBLEM DESCRIPTION AND 0700 PA~A. NUMBER:
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d) DAT A COLLECTION DESCRIPTION AND CODE ~MBER~ c : , - ~ ~ -TPLf,18(!3) e) SPECIFIC HUM~N ERROR(1):
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.:ONTROLS 1 May 198)
APF'ENDIX B9 HED REPORT (CONTINUED)
$ ut t.y(v1J JTS I ~- ~ HE:D NO.: PJ:- ' ~
PLANT UNIT f) SUGGESTED BACKF'IT: g: REVIEW AND DISPOSITION:
- B9-2
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1[~~- HED PRIORITY RECORD HEDI ________.I
~-~__'2.. . ~oA-o ~;>033
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE CONDITION OR TECH.
.~ YES YES SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE
. (PAM OR 1E)?
NO G)
** ERROR POTENTIAL?
LOW 2 a 0 I HIGH
- 5. CONSEQUENCE OF ERROR:
mw 1 2 I 0 I ...i_ HIGH
.. leD C&TIDOIIV I IIO IIO
. . . . HED NO. fJ:t2..-~
. .VJRCINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
J..0,10- 3DJJ
- RECOMMENDED RESOLUTION STATION/UNIT *JurY-tL {j h *,* f- .r l 2 J
MARK NO. ITEM DESCRIPTION Eme.,.1ercy ~,esp( 0:en e,-p_-fu.,- 41-- 3 Panels CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS: Re o.Y" [ Q nge tti e i hstrLA Vt1 ~-a.-f i o- '1 &/ L D ..._f.,..ol.r O 'l the "[;"w.ev-j~,,,cr ~l~.Jel G-enen,.10..- #] fa~efs 1o~ /,pfi* Uri ; -f .r I & .2. fo be C o ri s i sf P~ w i i /.. f/,e () r r,,,>'ffn., e...f o t +le Fri,erJe,,r:~r ./J;esel G:enr,..~10 ... #-/ ah/#~ &"els. ORICINATOR /J,, £ JI,*// DATE REVIEWED_---Si::f~-__:;;;)._;._:/_-~f~S_ __
- GUIDELINE CONTROLS SELECTION OF CONTROLS 6.4.1 COMPLIANCE CHECKLIST 6A N/A Yes No Reference/Comment 6.4.1.1 GENERAL PRINCIPLES Controls should* be selected to ensure ease of ope,ation and to minimize operator errors.
- a. ADEQUACY-Each control should be adequate for the function it performs.
( 1) It shou Id provide a sufficient range of control. (2) It should be easily adjusted with the required level of precision. I
- b. ECONOMY-Each control should be necessary, and the simplest effective control for the task concerned.
(1) There shou Id be a good reason to require a control for the function concerned. ., (2) (3) (4) Duplication of controls should not occur, except for a specific reason. The precision and range of a control should not greatly exceed the need. Selected controls should be economic of I I space.
- c. HUMAN SUITABILITY - Controls selected should be suitable for operator use in a control room environment, and should be suited to the anthropometric and ergonometric character-istics of the expected operator population.
( 1) Each control should be recognizable in terms of its function. (2) . Each control should be of the type normally anticipated for the operation concerned. This means conforming to operator expectations, matching to other controls for the same function, and generally conforming to conventional practice.
\_. c.oa.n. Ec.T\ vc ACTIOtu C.A l SE
- 6.4-1
-. CONTROLS 6.4 DESIGN PRINCIPLES 6.4.2 GUIDELINE COMPLIANCE CHECKLIST 6.4.2.2 CODING OF CONTROLS Coding methods (e.g., size, color) for a particular application should be determined by the relative advantages and disadvantages for each type of coding. Exhibit 6.4-3 is provided as a general guide-line for control coding evaluation.
- a. CONSISTENCY-The coding system should be uniform throughout the control room.
- b. LOCATION CODING-Controls should be located so as to be easily° related to functions and functional groupings. Controls with similar functions should be in the same location from panel to panel. (See Guideline 6.8.2.3.)
- c. SIZE CODING
( 1) No more than three different sizes of controls should be used for discrimination by absolute size. (2) Controls used for performing* the same i function on different items of equipment I iI should be the same size. (3) When knob diameter is used* as a coding parameter, differences between diameters should be at least 0.5 inch. (4) When knob thickness is a coding pa~ rameter, differences between thicknesses should be at least 0.4 inch.
- d. SHAPE CODING -When possible, controls should be differentiated by shape. In par-ticular, controls which may be manipulated in a "blind" fashion should be shape coded. For example, where an operator must simultane-ously observe a display and move a control which is outside his field of view, the controls should be shape-coded . and separated
- by distance. Control shapes should be:
( 1) Visually identifiable. (2) Tactually identifiable. AC,\O\~ CA\ 5 E
- 6.4-7
NUMBER ATTACHMENT TITLE REVISION 1-E-l 6 STOPPING UNLOADED EDGs ATTACHMENT PAGE 2 1 of 2 CAUTION: *The ~DGs should NOT be stopped until the CTMT is sub-atmospheric. NOTE:
- Only one EDG should be stopped at a ti.1]1.e.
- EDG 1 should be stopped before EDG 3.
- 1. Verify that the base tank fuel oil level is greater than 290 gallons.
- 2. Push both ENGINE STOP pushbuttons simultaneously to initiate the engine cool down and stop sequence.
CAUTION:
- If an auto-start signal is received while the EDG is in the cooldown cycle, the EDG speed* will __ increase to between 870 and 910 rpm. If the EDG speed does not stabilize between 870 and 910 rpm, the SPEED CONT switch must be used to adjust EDG speed .
- The engine is in Governor Fast mode when in AUTO, resulting in speed adjustments being very sensitive. Changes made with the SPEED CONT switch should be small to prevent engine overspeed.
- 3. Verify engine speed decreases to betwe~n 470 and 490 rpm.
- 4. Depress the Auxiliary Trip Reset pushbutton and verify that the assoc*iated amber light goes OFF:
EDG l - Diesel Generator Isolation Panel in Unit 1 ESGR EDG 3 - Unit 1 EDG 3 Control Panel in the MCR
- 5. Verify that the EDG stops after a 9 1/2 to 13 1/2 minute cooldown period.
- 6. Verify or adjust the SPEED DROOP control on the UG-8 Governor to zero.
NOTE: Governor alignments will be performed by the Maintenance Department.
- 7. Verify scribe marks on the governor gears are aligned.
- 8. Verify governor SPEED KNOB is at the scribe mark on the dial .
~.-- .. -*.***** ., ..- ...........
. -.. ~- *- ~ . :_ *. . '. . ..,. .......,.,, , ........... ~**.--* ........... _,,,.--.- ......,..._....... ,..-~-- *:-:-**---** -** .~ .., ...... ... -**
NUMBER PROCEDURE TITLE REVISION 5
- l-ECA-0.l STEP LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED ACTION/EXPECTED RESPONSE i--~~~ RESPONSE NOT OBTAINED PAGE 3 of 16 1--~~~~~~-,
CAUTION:
- The load placed on any energized emergency bus should NOT exceed 1200 amps, when energized from offsite power.
- The load placed on any _EDG should NOT exceed 2750 KW.
- 2. MANUALLY LOAD THE FOLLOWING EQUIPMENT ON ENERGIZED AC EMERGENCY BUS:
a) Align and start CHG pump:
- 1) Check valve alignment: 1) Manually align valves .
* ~ CHG pump miniflow RECIRC valve(s) - OPEN
- CHG pump RWST suction valves - OPEN
- 1-CH-MOV-lllSB
- 1-CH-MOV-lllSD
- CHG line isolation valves
- CLOSED
- 1-CH-MOV-1289A
~ l-CH-MOV-1289B
- 2) Start one CHG pump b) Start Safeguards area exhaust fan c) Start at least two CRDM fans
1'."UMBER PROCEDURE TITLE REVISION 5 l-ECA-0.0 LOSS OF All. AC POWER PAGE 15 of 16 I STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED..._~~~~~~.....
- 25. CONTROL STEAM FLOY TO STABLIZE SG PRESSURES CAUTION:
- The load placed on any energized emergency bus should NOT exceed 1200 amps, when energize~ from offsite power.
- The load placed on any EDG should NOT exceed 2750 KY.
- 26. _VERIFY FOLLOYING EQUIPMENT LOADED Manually load equipment and refer ON AC EMERG~CY BUS: to Attachment 5.
- CHG pump SY pump
- CHG pump CC pump 480 VAC MCCs Vital bus UPS Gai- tronics Station radio booster 2 Control Room chillers One Unit 1 MCR AHU and one Unit 2 MCR AHU
- One Unit 1 ESGR AHU and one Unit 2 ESGR AHU
- Aux Vent filtered exhaust fan
- Turning Gear oil pump
- Turbine Turning Gear
- Common Radiation monitoring cabinets
- Semi-Vital buses rf!i*
- ** *r * *** *
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11.17 CORRECTIVE ACTION EVALUATION CA NO.: 17E CA DESCRIY.l'ION: Change flow indication for eves charging and letdown (0-300 gpm) (FT-1122/2122). EQUIPMENT MARK NO. :QED NO. 20A03405-FI-1122A,B 20A02214 20A02208. 11.17.1 BED REVIEW - ORIGINAL FINDINGS HED No;- 20A03405 - - No feedback that pushbutton controls have been activated. (NUREG-0700, Section 6.4.3.1.b) HED No. 20A02214 - Scale ranges inappropriate, need narrow ranges expanded. (NUREG-0700, Section 6.5.1.2.d.l.2)
. HED No. 20A02208 - Scale ranges too narrow, wide range indication not provided.
(NUREG-0700, Section 6.5.1.2.d.3) The CRDR Review Team determined that the scale range for the charging system flow indicator should be evaluated for any operating conditions .
- 11.17.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs jg!YES ONO ON/A Charging flow is an BOP setpoint and is required to be monitored in several EOPs.
RG-1.97 IXIYES ONO ON/A Charging system flow indication (Fl-1122A, B) is a R.G.-1.97 D-27 variable. l-E-3, 1-ECA-1.1, 1-ES-0.1, 1-ECA, 3.1, 3.3, etc. EPIPs 0 YES IXI NO O NIA LERs/IOERs DYES IXINO ON/A The flow indication for eves is not identified in the No LERs/lOERs were found pertaining to the charging EPIPS. system flow instrumentation. APP.R IXIYES ONO ON/A HPES/STA DEV/SOER DYES IXINO ON/A Flow loop 1122B is on the Auxiliary Shutdown Panel. No station deviatioris/SOERs were found pertaining to Range change will be same as Control Room indicator. the charging system flow instrumentation. ERF/SPDS IXI YES D NO D NIA TECH SPEC ITEM IXIYES ONO DN/A Charging line flow (FI-1122) is an input to the ERF. Charging flow instrumentation is required to be Point I.D. No. F1CH003A. available per T.S. 3.2.B.6 .
- VARS01G.B7S-l
Il.17.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- FI-1122 provides indication of charging line flow rate in the control room. Indication is also available in the ERF and P250 plant computers.
The CRDR corrective action reassessment team evaluated the range requirements of the charging line flow indicator. A range of 0-200 gpm is required based on a normal flow of 45-90 gpm, a minimum flow of 25 gpm (prevent flashing of the letdown stream, downstream of the letdown orifices) and the requirement to read a minimum of 150 gpm when evaluating RCS leakage. In accordance with AP-16, when RCS leakage exceeds 150 gpm, safety injection is manually initiated. Safety Significance - FT-1122 is safety related for R.G.-1.97 and is on the EQML. The flow indicator FI-1122 is designated NSQ (Cat. 2 variable for R.G.-1.97). Potential for Error - The potential for error is increased based on the inability of the operators to read setpoint values. Consequences of Error - The consequences of error of not being able to read the charging line flow rates at the high/low range would be the inability to determine extent of RCS leakage above 150 gpm and determine minimum charging flow to prevent flashing of the letdown steam respectively. Based on telephone conversations with Mr. Mayo Oppenheimer (Nuclear Analysis and Fuel), the charging flow setpoint value of 25 gpm does not include taking into account instrument inaccuracies. The calculations (14937. 70-C-17) prepared for DC-88-27/28 show that the accuracy of the control board indicator is approximately +/- 17 gpm at a flow rate of 30 gpm during normal operation. During abnormal plant conditions (DBE), the accuracy is +/- 40 gpm. These accuracy calculations included a square root extractor in the instrument loop and represents the worst case. The setpoint should be revised to include instrument inaccuracies . Il.
17.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion, it is recommended that the charging line flow indicator scales be replaced with scales having a range of 0-200 gpm and revise the charging line flow instrument setpoint (25 gpm) to include instrument loop inaccuracies. If the value is changed to approximately 50 gpm, to account for loop tolerances, then the use of the square root scale is acceptable .
- VARS01 G .B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D I. EOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
W/i5/5w
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ltJfllAt; ~halit:R:NG D!&:il:;.~cy R:Jof A / 1E . 88/23/85 PAGE 41 SUliRY l.l(iT e CODE A ASSESSl!Etcl LAS'T Re-VIEW TITLE -RESPONSIBILITY STATUS DATE
~ NO FEEDBAD< THAl PUSHBIJTT(>>j C()(TRil.S KWE BEEh ACTIYA'iED, II -S 85/28/85
~ ERROR:
MY CAUSE DELAYS/ERRORS IN~ ~ Ht PROu!I! DESCRiPTiiJh: CPERATORS 1iAVE f() Fw>~ T~T P\JSl1BllTT~ COH'TR[>..S l1AVEBaN ACTlvATED. e1ee PARA>31oi11, Nlll&Efl: o,41,.:i, 1,B 5Lii36£STED BACl{FIT: AOJLiST iO &>Oi fc£Sl5T~.:;t: ioiid't D::liRt:SSlNG II.EIS, Et&IRE IIERIUDlC MlhTtNANCt ~ ~ ~1ROL.S.
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DATA CO..:.ECTirt, DESCR!PT!ON JriD CODE NJMl:iEil~ TH, l CUNTROJ..S SURVEY IT~:3 lN\l[LVEI,: MRK li.M&c~ LOCATION. ~NT~ SYi,TEII SWISYST91
!Hi LIIE FLO ff NJT lN INV Fli.E t
TP-4.1 CONTROLS 1 Mey 1983
-** APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED' REPORT
, n t "7 ~
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B9-1
- TP-A.l
.:ONTRCLS l May 1"983 .
APrENOlX B9
- HED REPORT (CONTINUED)
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- 6_7..,_____1
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- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE CONDITION OR TECH.
SPEC. VIOLATION?.
.~ YES YES
- 3. HIGH SAFETY IMPORTANCE -NO
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;.(l;:~ l~
~IBILITY STATUS DATE
~14 ~ AAN6ES JNAPPRCWRIATE. NEED NARROil ~SEX~. II "'11 82/1S/BS
~ ERROR:
DE.LAY /ERROR JN DP ~ E . f+f PROBt.9 DESCRIPTIDli:
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TP-5.l DISA..AYS l May 198} ~- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPeRT Su I'( (?. Y / V~//TS I $ :1.
* - PLANT/UNIT ORIGINATOR: ' ( ~ J ~,R 9 /,dJ HED NO.: P-;; - 7 I "')
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TP-5.l DISPLAYS l May 1983 -. APPENDIX B9 HED REPORT (CONTINUED)
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- 1. DOCUMENTED ERROR? YES
- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH.
e SPEC. VIOLATION?"
- 3. HIGH SAFETY IMPORTANCE
. (PAM OR 1E)?
NO
, it~
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LOW 2 I
- l!)-L HIGH N
- 5. CONSEQUENCE OF ERROR:
toW 2 CV
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.. TITLE
- tiff: e CODE B ASSESSEl"il "8/23/85 LASi RtlllEW
~ 133 l£D NO RESPC!(SlBILITY STATUS DAT£ ~
SCA'...£ ~ 5 TOO 11ANR!li,c WI~~ ltdllCATll)j NOT PROVIDED. 1
----- 82/14/85
~ ERROR:
DaAY /ERROR lN OP ~ E . Ht PROiUI'! DESCRIP!llli: SCAl.i5 RAASES TOO 1'!RR'uw ruil IIIA11U DISPiJIYE.D V&UJES. SIP?ORTih'G I.IDE IIAA6t lNST!iiJlaTS .OT PROVIDED IN CR. e70i! PAKAS~ ~ I i :
- 6. 5. l.c::.D,J SI.EGES1t.D BAC!\F IT:
Piiij\1111: iilir.-R~ l'4Siic~t,,iATli;., 1LJ ~;:,ii~i 1tiH:il lrwlCAillll\, t+t DISPOS!THIII~ ADD W'i f-300 S:,1, DATA W-!.fi:il!A DESCii!~Tl!:P.i ~ COIJE N!Jlli,Eli: TP-S,l DI~VS &JRv:Y TP-9.2 VERiFlC&!Tll3t',i A!.iJ IIALlDATit,,, RtMRKE: P1;?c-1ii. ITa!::i lNvuLvt.11:
~KIi ~i:il LOCl.fflu,, CO,,.,U,.~i fllAl!c SVST:111 H MJT IN lNV FlLt f
TP-5.l DISPLAYS l Mey 1983
- - Su ti@ Y APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT lu1v7cs:
PL.ANT UNIT 1 S~ t- 0
. V., o**.
, v i,OJ,
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. .*. *t-,
f '-
- - \..:
oRIGINAToR: £~""; ~ HED NO.: Px - 7 ~ . . . . * :-- ,', VALIDATEDBY:~*0<2- - DATE: ~/~,r/f('f:/ .,,'"* e) HED TITLE: S ~ il.. ~ M . C},, 61:- ~ 41-4 //4 A:::Y,,t:;. a_j_ ~u A °7 '2,. .~Yi k:, h'i ~
- b) ITEMS INVOL VECr.
~~~.
d) OAT A COLLECTION DESCRIPTION ANO CODE NUMBER:
~~ ~ - T f S-,!/3l( !Lf)~ T/1,9, 9 8~(17) l~ V#-(rkf.rH\ - Tl7 'f. t .,
e) SPECIFIC HUMAN ERROR(s): ... I )-,_c, I l .-'>-'-'-: ~ ~ ~ ~ IC L~ J:...V:.l-"" ~ C>f. ;,.-...(, *:; . -~
. ,. ~- :_,;.:*~rL-t'Y\../'~ ~).$.. n* :""'--! J..v:L.~ .. .1.
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TP-5.l DISPLAYS 1 Mey 1983 -* ;:, \J APPENDIX B9 HED REPORT (CONTINUED)
,1.. (< 1/ /UN ITS PLANT/UNIT I ~ ri HED NO.: /~r-- 7 ,s g) REVIEW AND DISPOSITION:
- B9-2
( -- -*--:*--- i
* ~ i Q..<.).. "to-t, ~~ ~ -* .,._.,!
/ ~ - , ~ ~ -~~~t.. - 1.
~~. I N*c e ~E TH c 'f..MJ, L.. .. co v F't.:~ f<c c.s:,!2.2J rs- IZ. ~ f, <c I . u.s', l\
* . I _ ~\~ ~ *R.-vt~o.i.. '-':~ f*,c( (NoD) 5:) Rc..f' Se:-~L- A* _F.f(.T!"S.cl..S~t__QE~~-E:-~--S~~-s~~
~c.c~~ c,.,v...:o.5 :; ,.)~ V " ~
°~~
_ _ __ _ _( C_o~D£riS~~-~~-~~~~i:ss; ;;.~ -~~-~~;~;-;__ {.s~ *V t..) 7.1: f<. c...P e,o~Potvetvr *C.oOL-tAI c- __ {A.;)~ f c_) __ -:_ o~-l~-G) S~t
>c:.L-f) ~" f~~
___ . . J~,! VelV7IJ..A TJo}J __ $i_ST£ M. ...~_.C...,;.tJTA//JM IZNT_. PQ1'Cr-f: ~
------- ~ --- -* .. - .
J9, GA;V,,.,. L L..f;ve-L-. J.N!J!C..AJ1.o) _____ . -* *--------- - ----* ------
HED PRIORITY RECORD '1,1, () ~ f)f\ 0,, I 1,, HED'
--*'--r
./1 V
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE CONDITION OR TECH. 0
@ YES YES SPEC. VIOLATION?
- 3. HIGH SAFETY IMPORTANCE NO
. (PAM OR 1E)?
- 4. ERROR POTENTIAL? 1 2 3 LOW '
- 5. CONSEQUENCE OF ERROR: 1 LOW 2 @ 4 & _§__
HIGH NED CATEGOll'I' I CATIEGOll'I' 111 NO NO NO
a '*
- I HED NO. /'I- 7/-//
VIRGINIA POWER CONTROL ROOM DESIGN REVIEW :J0,40-.J"J. /'( HUMAN ENGINEERING DISCREPANCY ("HED)
- RECOMMENDED RESOLUTION STATION/UNIT Su .,-r y MARK NO. . E I - . I { 'l.. 'L ;. FT-2/L.'l_
ITEM DES CR IPT ION _ ... C. .h__o_,,..._9.....i__ _l____;.._V\__e__F___(__o_l..)_ _ _ _ _ _ _ __ N.;,.* 7 f CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) CLaL-i~t'/ fAe Yahti(' J ot fl.e~e s/r-i'¥J' I lo 0-300,eh-zu v.> i fl it;/;ce-f ;'i>r.. {)); fl [I ec.f a t sc~le. COMMENTS:~--------------------~----- ORIGINATOR _ _..... B____, _r:_,!l_t"_/I___DATE REVIEWED_--"-R_-_2.....;._7_..;-~-~---
. ~--.......... *-*-*** ......... .
- GUIDELINE VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5.1 COMPLIANCE CHECKLIST 6.5.1.2 USABILITY OF DISPLAYED VALUES Scales should be graduated and numbered so that readings are related in a direct and practical way to the operator's tasks.
- a. SCALE SELECTION-Scale units should be consistent with the degree of precision and accuracy needed by the operator.
- b. ELIMINATION OF OPERATOR CONVER*
SION-All displays should indicate values I in a form immediately usable by the operator without requiring mental conversion.
- c. PERCENTAGE INDICATION-Percentage indi-cation may be used when the parameter is meaningfully reflected by pe~ntage;
- d. SCALE RANGE-Scales should be selected to:
(1) Span the expected range of operational parameters, or I (2) Employ appropriate scale ranging tech- i niques, or . (3) Be supported by auxiliary wide-range instruments.
- e. SCALE SIZE-Scale ranges may be expanded iI (or contracted) by multiplying or dividing indicated scale values by powers of ten. All i such scales should be clearly marked as to I whether .the indicated values should be multiplied or divided, and the factor involved !
(e.g., 10,100, 1000).
- f. SENSITIVITY-Display dynamic sensitivity should be selected to minimize the display
- of normal random variations in equipment performance.
- - 6.5-3
'iii!f.'iilll.\!!!"""~*... LlRCOlOA
*
- lA 7
164 168 1 1 1 60.000000000 60.000000000 0.0066666667 0.0066666667
***,,...~L'i:-R~C;_:O~Offl0:.A...-...,.,..~~~"'~~w~P~~~.2..~'1~~~~~~},~,,tt.os:.q.4,J.CU;a ** ~IIIEN AS BUI!,. T HHEN AS BUILT
,ilt,{,;llfflt'.i,¥~.'!'~~*~t*,..~~.'::'t~~r..;~r.1;"!:"'*..:*,1(,:,~.~~~~-~~:-.--*".~.,,*.~/,,"';,""."'°?*~
----------------------------------------------------------------------------------------------------------------------------------- 6 S8510-l-E-9 S8510-l-E-10 1-~-,.~ .. ~.-:-::
7
* *s,
.::;,,~r.-.~.~-""~'--~---*"'"":Ol"""-*""o,,,...,--=*.._...,......,_....,.,,___
. . .-.~..*..
- l 82 81 4 85 60 l 62 32 44 46 5
- POINT INPUT INSTRUMENT MARK POINT DESCRIPTION DATE TESTED L
I S U H B A L C N INSTRU RANGE HIGH INSTRUMENT INSTRUMENT LOH ENGR UNITS
- ID NUMBER NUMBER N K
I N K N E L UNCONV RANGE RANGE L1RC009A 1Sll-18A RVLIS TR-18 RVLIS DYN HEAD LEVEL CPL)<> 11-11-88 02 4 18 0-lODC 120.0 0.0 PCT
- FlCCOOlA FlCC002A 1S26-03A 1S26-04A l-CC-FT-121 l-CC-FT-122 CCH TO RECIRC AIR FLOH INLJ CC TO RECIRC AIR FLOH INL) 07-11-86 12-22-87 07 07 l
1 03 04 l-05DC l-05DC 1500.0 900.0 o.o* 0.0 GPM GPM
~ FlCC003A flCC004A 1S26-09A 1S26-10A l-CC-FT-130A l-CC-FT-1308 CHGRG PMP CC PUMP 2A FLOH !NL)
CHGRG PMP CC PUMP 2B FLOH INLJ 00-00 00-00 07 07 l 1 09 10 l-05DC l-05DC 100.0 100.0 0.0 0.0 GPM GPM TlCCOOlA TlCC004A 1S26-01A 1S26-05A l-CC-RTD-122 l-CC-RTD-125A CCH TO RECIRC AIR IN TEMP INLJ CC PUMP 2A DISCH TEMP (NL) 07-11-86 00-00 07 07 l l 01 05 l-05DC RMRKS 100.0 150.0 O.O 0.0 DEGF DEGF
.. TlCC005A TlCC002A 1S26-06A 1S26-02A l-CC-RTD-1258 l-CC-RTD-126 CC PUMP 28 DISCH TEMP INL)
CCH TO RECIRC AIR OUT TEMPINLJ 00-00 07-11-86 07 07 l 1 06 02 RMRKS RMRKS 150.0 100.0 0.0 0.0 DEGF DEGF lJ FlCHOOlA FlCH002A 1Sl2-11A 1S03-13A l-CH-FT-1110 l-CH-FT-1113 BORIC ACID BYPASS FLOH INLJ BA TO BLEND SYSTEM FLOH IHT) 02-18-86 02-10-86 03 01 2 4 11 13 l-05DC l-05DC 200.0 10.0 0.0 0.0 GPM GPM
- tJ r~r.HOP3A FlCH004A 1S05-08A 1S03-l4A l-CH-FT-1122 l-CH-FT-1150 CHARGING LOOP FLOH IBLJ LOH PRESSURE LETDOHN FLOH IHTJ 01-07-86 02-10-86 01 01 4 7 08 14 l-05DC l-05DC 150.0 150.0 0.0 0.0 GPM GPM jt FlCH005A
-*L.:.C.1(.. l:..>.
1S27-08A 1S05-11A l-CH_;FT-1160 l-CH-LT-1112 LOOP FILL HEADER FLOH IHTJ VOLUME CONTROL TANK LEVEL IBLJ 12-20-88 01-07-86 07 01 2 7 08 11 l-05DC l-05DC 120.0 100.0 0.0 0.0 GPM PCT
** LlCH002A
?lCHOOlA 1S02-09A 1S02-19A l-CH-LT-1115 l-CH-PT-1121 VOLUME CONTROL TANK LEVEL IHTJ CHARGING PUMP PRESSURE IHT) 01-09-86 01-09-86 01 01 3
3 09 19 l-05DC l-05DC 100.0 3500.0 0.0 0.0 PCT PSIG
*ii)
- 'lo':H002A
-'t~C.!IC'~2A 1S02-20A 1Sl9-08A l-CH-PT-1145 l-CH-RI-1118 LP LETDOHN LINE PRESSURE IHT)
RCS LETDOHN HIGH RANGE INLJ <> 01-09-86 01-24-86 01 03 3 3 20 08 l-05DC 0-05DC 600.0 6.0 0.0 1.0 PSIG LOGCPM II s :rm E irr: 11
- Iii i i Iii- lZWW n t ** . . . *: .,. - .~ r
PROGRAM HPT21516 Q-LIST
SUMMARY
REPORT 03/31/92 17:02 PAGE 57 STATION: SURRY POHER STATION VERIFIED COMP QA CATEGORY COMP QA CATEGORY COMP QA CATEGORY QA FUNC DEFINITION FUtlC DEFINITION FUNC DEFINITION REFERENCE ASSOCIATED COMPONENT ID, CAT HPTS ID. NOMENCLATURE 1 1 2 . 2 3 3 DRAWING COMPONENT ID fE-CH-1147 SR 01-CH -FE -1147 ELEMENT, FLOH SYP8 5,1.3.E* SENS 5.4 11448-FM-BBA 01-CH - -17 FE-CH-1150 SR 01-CH -FE -1150 ELEMENT, FLOH SYPB 5,1.2,E SENS 5,4 11448-FM-888 01-CII -FT -1150 I-CH-FE-1154A SR 01-CH -FE -1154A ELEMENT, FLOH SVP8 5,1.1.0 SENS 5,4 11448-FM-88C,S2 01-CH -FT -1154A 1-CII-FE-115<18 SR 01-CH -FE -11548 ELEMENT, FLOH SYP8 5.1.1.0 SENS 5.4 11448-FM-88C,S2 01-CH -FT -11548 1-CH-FE-1155A SR 01-CH -FE -1155A ELEMENT, FLOH SYPB 5.1.1.0 SENS 5.4 11448-FM-88C,S2 01-CH -FT -1155A 1-CII-FE-11558 SR 01-CII -FE -11558 ELEMENT, FLOH SVPB 5.1.1.0 SENS 5.4 11448-FH-88C,S2 01-CH -FT -11558 1-CH-FE-1156A SR 01-CII -FE -1156A ELEMENT, FLOH SVPB 5,1.1.0 SENS 5.4 11448-FM-88C,S2 01-CH -FT -1156A 1-CII-FE-11568 SR 01-CH -FE -1156B ELEMENT, FLOH SVPB 5.1.1.0 SENS 5,4 11448-FM-88C,S2 01-CII -FT -11568 FE-Cll-1160 SR 01-CH -FE -1160 ELEMENT, FLON SVPB 5.1.2.G SENS 5.4 11448-FM-888 OI-CH -FT -1160 01-CII-FE-1180 SR 01-CH -FE -1180 ELEMENT, FLOH SYPB 5.1.3.E SENS 5.4 11448-FM-88A 01-CH -P -2A 01-CH-FE-1181 SR 01-CH -FE* -1181 ELEMENT, FLOH SVPB 5.1.3.E SENS 5.4 11448-FH-888 01-CH -P -1A 01-CH-FE-1182 SR OI-CH -FE -1182 ELEMENT, FLOH SVPB 5,1.3.E SENS 5.4 11448-FM-888 01-CH -P -18 OI-CH-FE-1183 NSQ 01-CH -FE -1183 ELEMENT, FLOH SVP8 5.2 SENS 5.4 11448-FM-888 01-CH -P -1C FI-CH-100 SR 01-CH -FI -100 INDICATOR, FLOH SVP8 5.1.2.G INDI 5.4 11448-FH-888 01-CH -TK -2 _..;F~I,..-...,1.;.1.,.1o~-----..:N~s~o~1;..-,;C;;;H~-F~-~~~-~IN!N.0.1...Icc~ATTooRR', fF!L.2!:L..:....o***
* . ----~~-M~E-s~i,...L;.;*_
4-----.M?.'E~Sa;:I-'5,....:..:;2.-- 5965004 o1-c11 -FT -1110 FI- 22A NSQ O -CH -FI -1122:A- 0 n ,.1. !>.~ INDI 5.lt* ' * - - * * ~ - * . . _ , _ _ ...! i 9 6 ~ 0 0 01-CH -FT -1122
...~I~-=--;1~1~2f.28~----~N~S~Q~0{.1-:;C~H:...::-;F~I_:-~1-i1~2;;28r-=---~D~I~C~A~~-;!°~-----EM~ES~IH5~.~2~---_,;I~~N:D~I..;5;:_;.4;_..-----------5965D10 01-CH -FT -1122 FI-112<tA NSQ O - -1124A INDICATOR, FLOH MESI 5. NOi 5.li"" -~-;nu 01-CH -FT -1124 FI-11248 NSQ 01-CH -FI -11248 INDICATOR, FLOH MESI 5.2 INDI 5.4 5965006 01-CH -FT -1124 FI-1127A NSQ OI-CH -FI -1127A INDICATOR, FLOH MESI 5.2 INDI 5.4 5965006 01-CH -FT -1127 FI-11278 NSQ 01-CH -FI -11278 INDICATOR, FLOH tlESI 5.2 INDI 5.4 5965006 01-CH -FT -127 FI-1130A NSQ 01-CH -FI -l130A INDICATOR, FLOH HESI 5.2 INDI 5.4 5965006 01-CH -FT -1130 FI-11308 NSQ 01-CH -FI -11308 INDICATOR, FLOH MESI 5,2 INDI 5,4 5965006 01-CH -FT -1130 FI-1147 SR 01-CH -FI -1147 INDICATOR, FLOH INDI 5,4 SYP8 5.1.3.E 11448-FH-88A 01-CII -FE -1147 FI-1150 NSQ 01-CH -FI -1150 INDICATOR, FLOH MESI 5.2 INDI 5.4 5965009 01-CH -FT -1150 FI-1160 NSQ 01-CH -FI -1160 INDICATOR, FLOH MESI 5.2 INDI 5.4 5965012 01-CH -FT -1150 FIC-CH-1154 SR 01-CH -FIC -1154 CONTROLLER, FLOH INDI RCP8 5.1.1.D INDI 5.<+ 11448-FH-88C 01-CH -FIC -1154 1-CH-FIC-1155 SR 01-CH -FIC -1155 CONTROLLER, FLOH INDI RCPB 5.1.1.D INDI 5.4 11448-FM-BBC 01-Cll -FIC -1154 FIC-CH-1156 SR 01-CH -FIC -1156 CONTROLLER, FLOH INDI RCP8 5.1.1.D INOI 5.4 11448-FH-BBC 01-CH -FIC -1154 1-CH-FL-1 SR 01-CH -FL -1 FILTER, BORIC ACID SYPB 5.1.3.D FILT 5.4 11448-FH-88A 01-CH -P -2A 1-CH-FL-2 SR 01-CH -FL -2 FILTER, REACTOR COOLANT SYPB 5.1.2.G FILT 5.4 11448-FM-888 01-CH -TK -2
'I-CH-FL-3 SR 01-CH -FL -3 FILTER, SEAL HATER SVPB 5.1,2.G FILT 5.4 11448-FH-88B 01-CH -E -1 1-CH-FL-4A SR 01-CH -FL -4A FILTER, SEAL HATER SYPB 5.1.2.G FILT 5.4 11448-FH-888 01-CH -FL -48 1-CII-FL-48 SR 01-CH -FL -48 FILTER, SEAL HATER SYPB 5.1.2.G FILT 5.4 11448-FM-888 01-Clf -FL -4A 1-CH-FL-5 SR 01-Clf -FL -5 FILTER SVPB 5.1.3.E FILT 5Jt 11448-Flf-88A 01-CII - -120 FM-111 O NSQ 01-CII -FM -1110 CONVERTER, FLOH CNVT 5.4 MESI 5. 2 5965004 01-CH -FI -1110 FM-1113 NSQ 01-Clf -FH -1113
- CONVERTER MESI 5.2 CNVT 5.4 5965004 OI-CH -Fe -1113 FM-1114 NSQ 01-CH -FM -1114 SUl1t1ATOR, SIGNAL MESI 5.2 SUMM 5.4 5965004 01-CH -FC -1114 FH-11220 NSQ 01-CH -FH -11220 SUMMATOR, SIGNAL MESI 5.2 SUIIM 5.4 5965010 01-CH -IIIC -1122
;rn~1220/R NSQ 01-CII -FM -11220/R INPUT MODULE MESI 5.2 CNVT 5.4 5965010 01-CII -FM -11220
PROGRAM HPT21516 Q-LIST
SUMMARY
REPORT 03/31/92 17:02 PAGE 58 STATION: SURRY POHER STATION VERIFIED COMP QA CATEGORY COMP QA CATEGORY COMP QA CATEGORY QA FUNC DEFINITION FUNC DEFINITION FUNC DEFINITION REFERENCE ASSOCIATED COMPONENT ID. CAT HPTS ID, NOMENCLATURE 1 1 2 2 3 3 DRAHING COMPONENT ID FQ-1114 NSQ 01-CH -FQ -1114 POHER SUPPLY MESI 5.2 POii 5,4 5965004 01-CH -FIT -1114 FQ,-1122 l~SQ 01-CH -FQ -1122 POHER SUPPLY MEsI*s.2 POH 5.'* 5965D10 01-CII -FC -1122A FQ-1124 NSQ 01-CH -FQ -1124 POHER SUPPLY MESI 5.2 POH 5.4 5965D06 01-CII -FC -1124 FQ-1127 NSQ 01-CII -FQ -1127 POHER SUPPLY MESI 5.2 POl'I 5.4 5965D06 01-CII -FC -1127 FQ-1130 NSQ 01-CH -FQ -1130 POl'IER SUPPLY MESI 5.2 POW 5.4 5965D06 01-CII -FC -1130 FQ-1150 NSQ 01-CH -FQ -1150 POHER SUPPLY MESI 5.2 POii 5.4 5965D09 01-CH -FC -115D FQ-1154A NSQ 01-Clf -FQ -1154A POHER SUPPLY MESI 5.2 POH 5.4 5965D11 '01-CII -FC -1154A FQ-1154B NSQ 01-CH -FQ -1154B POHER SUPPLY MESI 5.2 POH 5.4 5965D11 01-CH -FT -1154B FQ-1155A NSQ 01-CH -FQ -1155A POHER SUPPLY 11ESI 5.2 / POH 5.4 5965D11 01-CH -FT -1155A FQ-1155B NSQ 01-CH -FQ -1155B POHER SUPPLY MESI 5.2 POii SA 5965D11 01-CH -FT -1155B FQ-1156A NSQ OI-CH -FQ -1156A PO~IER SUPPLY MESI 5.2 POH 5.4 5965DI 2 01-CH -FT -1156A FQ-1156B NSQ 01-CH -FQ -11568 POHER SUPPLY MESI 5.2 POH 5.4 5965D12 01-CH -FT -11560 FQ-1160 NSQ 01-CH -FQ -1160 POHER SUPPLY MESI 5.2 POH 5.4 5965D12 01-CH -FC -1160A FR-1113 NSQ 01-CH -FR -1113 RECORDER, FLOH MESI 5.2 RECD 5.4 5965D04 01-CH -FT -1113 FR-1154A NSQ 01-CH -FR -1154A RECORDER, FLOH MESI 5.2 RECD 5.4 5965D11 01-CH -FT -11548 FR-11548 NSQ 01-CH -FR -11548 RECORDER, FLOH MESI 5.2 RECD 5.4 5965D11 01-Clf -FR -1154A FT-1110 SR 01-CH -FT -1110 TRANSMITTER, FLOH MESI 5.2 SYPB 5.1.3.E 11448-FM-888 01-CH -MOV -1350 FT-Ctl-1113 SR 01-CH -FT -1113 TRANSMITTER, FLOH; HAG MESI 5.2 SYPB 5.1.3.E XSIG 5.4 5965D04 01-CH -FCV -1113 F -CH-1114 NSQ 01-CH -FT -1114 _.I.B~~J;!;IJil;fu..f!.OH INDI MESI 5.2,5 JS.IG....5A_,.___ .,._~... . .... .. . .. .... - -. . . .. .. 5965D0ft_______ 01-CH -YC -1114 FT-1 22 "*-**=w--sir-1ff=clf"::-rr-=n2T TRANSMITTER, FLOH --ME°Qif"57L "/ MESI 5.2,2 XSIG 5.4 11448-FM-BBc.=:::::::::,.
-1124 TRANSMITTER, FtoR HESI S.z SYPB-!J-:-t-:z:o--~***-* ***xstt'**s:-,r*------ ... 5%51JO'G"___ 01-CH -FT -1124 FT-CH-1127 SR 01-CH -FT -1127 TRANSMITTER, FLOl1 MESI 5.2 SYPB 5.1.2.G XSIG 5.4 5965D06 01-CH -FT -1127 FT-CH-1130 SR 01-CH -FT -1130 TRANSMITTER, FLOH MESI 5.2 SYPB 5.1.2.G XSIG 5.4 5965006 01-CH -FT -1130 FT-1150 SR OI-CH -FT -1150 TRANSMITTER, FLOH MEQR 5.1. 7 MESI 5.2.2 XSIG 5.4 114ft8-FM-88A 01-CH -FI -1150 FT-Cll-1160 SR 01-CH -FT -1160 TRANSMITTER, FL011 MESI 5.2 SYPB 5.1. 2.G SENS 5.4 11448-FM-888 01-CH -FC -1160A 01-CII-FT-1181 NSQ O1-CH -FT -1181 TRANSMITTER, FLOH SYPB 5.4 XSIG 5.4 STRU 5.2.6 11448-FM-888 01-CII -P -1A 01-CH-FT-1182 NSQ 01-CH -FT -1182 TRANSMITTER, FLOH SYPB 5.4 XSIG 5.4 STRU 5.2.6 11448-FM-888 01-CH -P -18 01-CII-FT-1183 NSQ 01-CH -FT -1183 TRANSMITTER, FLOH SYPB 5.4 XSIG 5.4 STRU 5.2.6 11448-FM-88B 01-CII -P -IC IICV-CH-1104 SR 01-CH ~IICV -1104 VALVE, HAND CONTROL;GLOBE SYPB 5.1,3.D AFLO 5.4 11448-FM-888 01-Clf -TI< -1c HCV-CH-1105 SR 01-CH -HCV -1105 VALVE, HAND CONTROL,GLOBE SYPB 5.1.3.D AFLO 5,4 11448-FM-BBA 01-CII -TK -1B HCV-CH-1110 SR 01-CH -HCV -1110 VALVE, HAND CONTROL;GLOBE SYPB 5,1,3,D AFLO 5.4 11448-FH-BBA 01-CII -TK -IA
'IICV-CH-1137 SR 01-CH -IICV -1137 VALVE, HAND CONTROL; GATE RCPB 5,1,1,A ISO 5,4 11448-FH-BBC 01-CII -E -4 HCV-CH-1142 SR 01-CH -IICV -1142 VALVE, HAND CONTROL; GATE SYPB 5.1.2.G ISO 5.4 1144B-FH-88C 01-CII -E -3 IICV-CH-1166 SR 01-CH -HCV -1186 VALVE, HAND CONTROL; GATE SYPB 5.1.2.G FLOC 5.4 11448-FM-BOB 01-CII -FCV -1160 HCV-CH-1200A SR 01-CH -HCV -IZOOA VALVE, GLOBE HAND CONTROL ISO 5.1.2.G SYPB 5.3.4.A 11448-FM-88C,S1 01-CII -HCV0-1200A HCV-CH-12008 SR 61-CH -IICV -1200B VALVE, GLOBE HAND CONTROL ISO 5.1.2.s
- SYPB 5,3,4,A 11448-Fl1-88C,Sf 01-CH -IICV0-120DB IICV-CH-1200C SR 01-CII -HCV -12ooc VALVE, GLOBE HAND CONTROL ISO 5.1.2,G SYPB 5.3.4.A 1144B-FM-88C,S1 o1-CH -11cvo-12ooc IICV-Cll-1201 SR 01-CII -IICV -1201 VALVE, HAND CONTROL;GLOBE RCPB 5.1,1,A ISO 5.1,2,G 11448-FM-68C 01-CII -E -4 IICV-CH-1244
- SR 01-CII -IICV -1244 . VALVE, HAND CONTORL;3-HAY SYPB 5,1,2.G ~ FLOD 5.4 11448-FH-BBA 01-CH - -14
- 11cv-c11-1303A SR 01-CH -IICV -1303A VALVE, HAND CONTROL;GLOBE RCPB 5.1.1.D ISO. 5.4 1144B-FH-8oc 01-CH -HCV -13038
Page: 82 APPENDIX 8. 1
- Variable Classifications Category Variable Description D*26 2 2
CONTAINMENT SUMP WATER TEMPERATURE Mark NLSlber 2*RS*RTD-250A 2-RS-RTD-2508 2 2-RS-Tl*250A 2 2-RS*Tl *2508 2 2*RS*TT-250A 2 2-RS*TT-2508 D-27 2 MAKE-UP FLOW IN 1-CH*F-1122 2 1*CH*FC*1122 2 1*CH-FC*1122A 2 1*CH*FC-1122A/R 2 1-CH-FC-11228/R 2 1*CH*FE*1122
- 2 2
2 1*CH*FI*1122A 1-CH*FI-11228 1-CH*FQ-1122 2 1-CH*FT-1122 2 . 2-CH*F-2122 2 2-CH*FC-2122 2 2*CH*FC*2122A 2 2*CH.* FC* 2122A/R 2 2*CH-FC*2122B/R 2 2-CH*FE-2122 2 2*CH*F1*2122A 2 2*CH*F1~2122B 2 2-CH*FQ-2122 2 2-CH*FT-2122 D-28 2 LETDOWN FLOW OUT 1-CH*F-1150
.YSTEM DESCRIPTION 3.3.5 Flow Contrcls
- a. IT-122 This flow transmitter on the charging line upstream of the regenerative heat exchanger transmits a signal to a controller locatec in the control racks, and a flow indicator in the main control room.
The co~troller regulates throttling valve FCV-122 in the chargir.g line to maintain a preset charging flow. A Reactor Coolant System pressurizer water level controller (LC-459F) ,. in response to pressurizer.level error between actual level and programmed level, generates. a signal to reset the charging flow setpoint increasing or decreasing charging flow in order to rest:.:ire pressurizer level to its programmed setpoint. The pressurizer level controller is provided with adjustable maximum and minimum flow limits that can be preset and fixed on initial calibration of the plant. Maximum flow is not
- limited. Minimum flow, however, is limited to approximately 15 gpm to ;revent flashing downstream from the letdown orifices.
Approach to either of these points initiates an*alarm in the I I main co~trol room. Also located in the control room is a "manual" leading station providing for remote manual control of cont:-:;l valve FCV-122 until the system permits switch over to the "a'..:tomatic" mode of control.
- b. FT-150
~his f:~~ :~ans~itter on the letdcwn line cio.rnstream from the ncn-:-eger.erative heat exchanger transmits a signal to a flow ir.~~cat~r located in the main control room. This indicat::~ ~er~its t~e cnerator to nonitor letdown flow. This instruoc:-.: alsc provides a high a:arm in the main control roo~.
a!,S"'."iNGt-<CL:SE EL!:CTRIC CORPORATION
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SUCLE.A.R E?iERGY SYSTE~S
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- APPENDIX 8. 13 Technical Report No.
\
Control Room Design Review \ Charging System Flow Indicators, not capable of displaying maximum flow values NUREG-0700 Surry Power Station Nuclear Engineering Power Engineering Services
- Prepared By:
.Virginia Power April , 1990 Reviewed By: .>r?f r~ Ell'/ Fol!.D"'I I -=c;;_-.:....'/_'1--.....::fa....::'O_
Date Approved By: - - - - - - - - - - - - - - - - - - - - / ---...,.....--- Date QA Category Safety Related Key Words: Control Room Design Review Corrective Action - CA17E Human Engineering Discrepancies HED 20A03405 18284A-1493770-B1 FINAL DRAFT
I-
- Title TABLE Or CONTENTS INTRODUCTION 1.0 PURPOSE
- 2. 0 BACKGROUND 3.0 METHODOLOGY 4.0 RESULTS 2
5.0 CONCLUSION
S 2 6.0 ATTACHMENTS 3
. _. 18284B-1493770-B1 i FINAL DRAFT
- INTRODUCTION 1.0 PURPOSE The purpose of this Technical Report is to document the development and and acceptability of justification for not implementing portions of Corrective Action CA 17E, which was proposed to resolve Human Engineering Discrepancy HED 20A03405 - "Range of the Charging System Flow Indicator."
2.0 BACKGROUND
The Control Room Design Review (CRDR) was conducted at Surry Power Station with NUREG-0700, Guidelines for Control Room Design Review; NUREG-0801 Evaluation Criteria. for Detailed Control Room Design Review; and Supplement 1 to NUREG-0737, Requirements for Emergency Response Capability (Generic Letter 82-83), as guidance. The survey was conducted using measurements, observations, questionnaires/interviews, and documentation reviews. Using this process, numerous deficiencies were documented, includ-ing this HED. HED 20A03405: Range of RCP Seal Water Flow Indicators FI-1122A,. B (Unit 1) and FI-2122A,B (Unit 2) are unsatisfactory. 3.0 METHODOLOGY In order to comply with NUREG-0700, 0801, and Supplement 1 to 0737, STD-GN-0005 (Human Factors),. the scale range of the charging system flow indicators was to be expanded. Also, :the scale was to be changed from square root to linear, allowing operators to more easily read flow values over the full range of the charging system operation. Design Change Packages 88-27-1 for Unit 1, and 88-28-2 for Unit 2, (Recorder and Flow Indicator Modifications), were being prepared in accordance with STD-GN-0001, and would include the task of charging flow scale range expan-sion and linearization. A 30 percent Project Design Review Meeting was held at the Station. The meeting was attended by Operations, Construction, and Engineering personnel. Each of the corrective actions that were grouped into DC-88-27-1 were discussed. The proposed changes affecting corrective action CA17E (Charging System) are summarized as follows:
- a. Rescale the charging system flow indicators from 0-150 gpm to.
0-300 gpm linear.
- b. Linearize the indicator scales Virginia Power was to investigate the feasibility of the flow rate changes.
--* 18284C-1493770-B1 FINAL DRAFT
- 4.0 RESULTS A recent,.- memorandum (Attachment 1, Item 3) form the Systems Engineer, indicates that rescaling of the flow indicators would not be feasible.
Changing the scale from 0-150 gpm to 0-300 gpm would be too broad a range for the small flow anticipated during system operation (normal flow is ..::...- 45 gpm). A Notes of Telephone Conversation (Attachment 2), signifies that the current range (0-150 gpm) of the charging line flow indicators is correct and should not be revised. However, the indicator scales should be changed from square root to linear, thereby fulfilling a prior commitment; which will allow operators to more easily read flow values of the charging system operation over the complete range of flow conditions.
5.0 CONCLUSION
S Only partial implementation of corrective action CA 17E ( linearization of scales) is required, because of the following reasons: 5.1 NUREG-0700, Sections 6.5.1.2d.1 and 6.5.1.2d.2, state that
*" [scales should be graduated and numbered so that readings are related in a direct and practical way to the operators tasks, ...
- d. Scale Range - Scales should be selected to:
2. Span the expected range of operational parameters, or Employ appropriate scale ranging techniques.]" Existing_ scales are in compliance with the _above-mentioned sec-tions of NUREG-0700. 5.2 Memorandum from Systems Engineer, which indicates that expanding indicator range to 0-300 gpm would be too broad a range for this application. The flow indicators pointer would remain at the lower end ( less than one fourth) of full scale. Therefore, readability would be decreased; which will increase the probabil-ity of operators taking incorrect readings. Normal engineering practice is to utilize instrument scales which allow pointers to be approximately mid scale during normal operations. 5.3 Notes of Telephone conversation; which indicates that the normal charging line flow rate is 45 gpm, and current indicator range is suitable. This action will allow the normal flow of 45 gpm, as well as the emergency operating procedure setpoint value flow rates of 25 and 60 gpm to remain in the lower half of the indicator scale; and be easily read by the operator .
- 18284C-1493770-81 2 FINAL DRAFT
- 6.0 The corrective action which should be taken is to replace the flow indicator square root scales with linear scales of (0-150 gpm).
ATTACHMENTS 6.1 Memorandum dated April 4, 1990, from: T. DiVecchia to: R. Arsenault 6.2 Notes of Telephone conversation - dated April 19, 1990, between T. DiVecchia and W. Thomson .
- 18284C-1493770-B1 3 FINAL DRAFT
- Memorandum prt, S1 fJ ~ tA-11.rJ."' 4 ;cJ.!8~, ~~
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- FINAL DRAFT
NOTES OF TELE?HONE CONVERSATION STONE & WEBSTER ENCi NEER iNC CORPORATION P4'0Rn l ,*,~4~J,*, PO\'IEN: ;:;,,,-1g~J ut11-; 1 1 i PACE (
- _ OF /
SURRY POWER STATION - UNITS 1 & 2 CALL DA TE ;I /;?1fb TIME 7;.:j Q 8;.-,
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New Won: Authcrized Preparer 11 ~- * 'YTe.. C Uow,JG:'.'b.::: By above:_ _ _ _ __ Proj. Engro ~ _ _--'!_...,..______
*cc:: Ccna.rrer,c::e R~ired fOlf' new wont authorized and *CECYNeil-7 technical bid evaluation.) *CB.arunu~7 *
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Job Book Cs) - March 2.7, 1990 FINAL DRAFT
Il.18 CORRECTIVE ACTION EVALUATION
- CA NO.:
CA DESCRIPI'ION: 18E Change existing annunciator for Safety Injection actuation to Train "A" actuation only. Add new annunciator for Train "B" Safety Injection actuation. EQUIPMENT MARK NO. IIED NO. SI Reset/Actuate Pushbuttons (Train A/Train B) 20A03406 Il.18.1 HED REVIEW - ORIGINAL FINDINGS HED No. 20A03406 - No feedback that pushbutton controls have been activated. (NUREG-0700, Section 6.4.3.1.b) The original CRDR determined that the operator is not provided with visible indication that the pushbutton control has been depressed which may cause delays and or errors in operator response. The proposed modification would provide separate Train A/Train B Safety Injection Actuation alarms .
- Il.18.2 IIED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs IXI YES D NO D NIA Multiple procedures, 1-E-O RG-1.97 DYES 18:JNO ON/A The SI controls are not R.G. 1.97 variables.
EPIPs 0 YES IXI NO O NIA LERs/lOERs O YES IXI NO D NIA The SI control pushbuttons are not identified in the No LERs/IOERs were found concerning SI controls. EPIPs. APP.R 0 YES IX) NO D NIA HPES/STA DEV/SOER DYES IXINO ON/A SI controls are not Appendix "R" related or appear on No station deviations/SOERs were found as a result of auxiliary shutdown panel. not having feedback of SI controls. ERF/SPDS IXI YES D NO D NIA TECH SPEC ITEM DYES IXJNO ON/A SI signals (TR A & TR B) are in ERF as points SI controls are not Tech Specification related. X1SI009D, X1SI010D .
- V ARS01H.B7S-l
Il.18.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The current means of feedback indication provided to an operator when the manual pushbutton controls for safety injection actuation are pressed, are the control room annunciators alarm nos. 1A-F4 "SIS INIT," and lE-AlO, "SI MAN !NIT." Either SI Train A or SI Train B pushbuttons on the benchboard will cause the alarms to annunciate.
Operators are trained to operate both train A and train B pushbuttons to initiate SI. The ERF computer also provides information regarding Train Affrain B SI actuation. When SI is reset, both Train A/B SI reset pushbuttons must be operated to clear the alarms. The manual SI reset pushbuttons are reset as required in various operating procedures. Both SI reset pushbuttons must be operated to clear the SI alarms. SI reset data is also available in the ERF computer. During the CRDR reassessment, it was determined that a single annunciator window 1A-E4 "SIS Blocked" exists. Two separate windows "SIS Blocked TR A" and "SIS Blocked TR B" would provide additional information/feedback to an operator regarding safety system status. Safety Significance - The SI actuation/block controls are safety related, Class lE. Potential for error - ---sI Reset - The potential for error due to lack of feedback of the SI reset function is low based on operator actions taken during resetting SI. The operators depress both SI TRA/TRB reset pushbuttons. The feedback is the extinguishing of the TRA and TRB alarm lights. SI Initiate - The potential for error due to a common SI TRA/TRB annunciator is increased due to the delay in operator response when determining status of safety system actuation. The operators are presently trained in response to a lost safety train which is considered a probable event. SI Blocked - The potential for error is high, based on no positive indication that a safety train is not operable. Consequence of error - SI Reset - The consequence of error would not risk injury to the public or station personnel/ equipment as an attempt would be made to operate/shutdown equipment and verification/self-checking of the alarm window would alert an operator that both reset pushbuttons had not been depressed. SI Initiate - The consequences of error due to not having separate SI Initiate TRA/TRB alarms would be a delay in operator response following accidents. The operator would be required to determine safety system initiation by observing the status of individual SI components. SI Blocked - The consequence of error is the inability of the operator to determine if both trains of SI are blocked. A SI train unblocked may result in inadvertent safety injection actuation during plant shutdown. Il.
18.4 CONCLUSION
S/RECOMMENDATIONS Based on the information provided above, even though no documented errors exist resulting from the failure of an operator resetting SI, *the addition of separate annunciators for Train A/Train B safety injection initiation and Train.A/Train B safety injection blocked would be beneficial to operators. The addition of these alarms will reduce the potential for error and minimize the consequences of error, therefore it is recommended that these modifications be implemented .
- V ARS01H.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D EJ.
- CHECKLIST
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- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH.
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- 3. HIGH SAFETY IMPORTANCE NO
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- 5. CONSEQUENCE OF ERROR: 2 3 5 _L.
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ORIGINATOR _ _ ...i;.z:.-F. g-=* ......_...._/1_,_.h.._'I_ _ _DATE REVIEWED -'.: J' -2 7- /£' - .,*- .2£~:__~.~~ls.2t:~~:,~_:LL::"~~,;~:~-e**~.i:.~;~'.:2~1.-~::.:.
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GUIDELINE CONTROLS PUSHBUTTON CONTROL SPECIFICATIONS 6.4.3 COMPLIANCE CHECKLIST 6.4 N/A Yes No Reference/Comment 6.4.3.1 PUSHBUTTON DESIGN PRINCIPLES
- a. POSITION-Pushbuttons in a row or matrix should be positioned in a logical order, or in an order related to the procedural seauence. I
- b. INDICATION OF ACTIVATION-To ensure that the operator knows that a pushbutton has II been pressed far enough for activation, a positive indication should be provided in the form of a snap feel, an audible click, or an
.I '
I I I integral light. I I I
- c. PUSH BUTTON SURFACE-For best operation, I
I II the surface of a pushbutton should offer slip II resistance, or be concave. I iI
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, X1TB017D rn;;'.:~-on SV2***:<B u.) TURBINE BTOP V/-ll... VE SRI.J (PU 07**1 l***S'O 02 8 07 0 ?-4 lJDC () Cl..0S((1 OPEN X1.TG0090 1s:!~3 .... 07::1 A~T~~---XB <:L) AUTO STOP hHT?***XB OIL PMP (NU 07***1"/*-()() 02 07 r\
.::. :?4 VDC () NORM LOW
, XlTG01.lD 1B?~-3***0H:l. :-,1,,::~***XE: (1) TURBINE ffTOP l,,1AL.VE SI..L.. (PU 07-17***90 ()2 B 08 0 ;::.1 l,![IC () CLOSED OPEN X1T0008D 1 G:?3*-0l{~} AST~!****XE: (:I.) AUTO STOP <-)BT;~***XB OIL F'MP <NU 07*** 1. "/***90 ()2 B ()Cl
*-* 2 :?4 VDC () HORM f..(ll,I
, XHGOHiD rn;;: ::J *-09 ::i S\J.1-*:<E: 0.) TUl";;EcINE BTDP Wll... \JE SRL (PU 07*-17*** 1/() ~)2 t:)
*.* 09 2 ?.<J 1,,1[1C () Cl.. OtlEU OPEN X:IVE:001.D 1S?3**10l VE: 1.-*Il MM! SN VB 1****II l<iANl.lAL. XFRB (PU 07*** 1. "/**90 02 f! 10 0 ?*'I VDC () TO rn*.,1 TO SOL.A
, X l l)B002D 1.823*-10? VB l***II WlN S~l VE: l ***I I Mf-1NI.JAI.* XFFW (Pl... ) 07*** 1 /*-~'() ()~~ H lO 1 ?4 VDC () TO S0Ll*, TO JNl,I XJE:'*,'OOW 1S?3~-tO~~ ET-Ct-\E:****:lB 1?!5 V WC> OISTIHN Ci~B :I.H (PU 07***1 "/*-90 02 8 :1.0 *,:..~ ?4 '-lDC () <.l2!WDC >J.2!:NDC
, ~,lFvl006[1 1.S~~:3-281 :t*-*rn--MOV-.1.5lB AFW PMP MEf.'1DER VAL.1,,1E BG C <PU ()7--11*** 1/0 02 r:;: 28 0 :I. ~~OVAC 0 Fl.ILL. 1) .. [1 M Fl.. CL[!
11.19 CORRECTIVE ACTION EVALUATION
- CA NO.:
CA DESCRIPfION: 19E Rewire Pressurizer Heater Control switches so that when the switch is in the pull-to-lock position, the green light is extinguished. EQUIPMENT MARK NO. BED NO. 14A12, 14Bl2, 14C12, 14J9, 14H2 20B12305 11.19.1 BED REVIEW - ORIGINAL FINDINGS HED No. 20B12305 - Pressurizer heater control status light indication meaning inconsistent w/ other controls. (NUREG-0700, Sections 6.5.3.1.c, 6.6.6.3, and 6.5.1.6.d.1, 3) The CRDR displays and conventions survey identified that the pressurizer heater (control and backup) Green - indicating lights do not extinguish when the switch is placed in the PULL-TO-LOCK position which is not consistent with other controls. DC-90-04/05 was issued which rewired the lights to be extinguished when the selector switch (main control room and auxiliary shutdown panel) is placed in the PULL-TO-LOCK position. The DCP was never implemented .
- 11.19.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs l&I YES ONO O NIA Pressurizer heater status is not an EOP setpoint.
Pressurizer heater control and determining pressurizer RG-1.97 IX) YES ONO O NIA Pressurizer heater status is RG-1.97 variable D-13 and provided in ERF. Power (KW) is used to determine heater status are included in several EOPs for natural status and functioning heater, not indicating lights. circulation and pressurizer pressure/level control. Ref. l-E-3, 1-ES-0.1, 0.3. EPIPs DYES ONO IXIN/A LERs/IOERs DYES IXI NO ON/A The pressurizer heaters are not identified in the EPIPs. No LERs/IOERs were found concerning the operation of the pressurizer heater controls. APP. R IXJYES ONO ON/A BPES/STA DEV/SOER DYES IXINO ON/A Pressurizer heaters (backup groups) are controlled from . No station deviations/SOERs were found concerning the the auxiliary shutdown panel. The pressurizer heaters operation of the pressurizer heater controls. are not required for Appendix R safe shutdown. ERF/SPDS IXIYES ONO ON/A TECH SPEC ITEM IXIYES ONO ON/A Pressurizer heater backup group status (power 4i KW) is TS 3.1.A.5 requires that 125 KW of heaters be provided in the ERF. Point ID QIRCOOlA, QIRC002A operable. VARS01J.B7S-l
11.19.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- Pressurizer heater status and control is required in several EOPs. In addition, the pressurizer heaters must be operable (125 KW) per Technical Specification 3.1.A.5 for the reactor to be critical.
Pressurizer heater status is a RG-1.97 variable D-13. This variable is satisfied by the pressurizer heater backup group power inputs to the ERF. The specific NUREG-0700 guideline referenced requires that system/equipment status be deduced by illuminated indicators and never by the absence of illumination. The present convention for pump control switches is that when in the pull-to-lock position, the indicating lights are not illuminated. The switch handle position is indicative that the component is inoperable. Current Control Room practice is to place a small red square magnet adjacent to the control switch when equipment is inoperable (Plant Status Log). When the control switch is taken out of pull-to-lock position, the component is returned to service and the indicating lights will be illuminated providing equipment status. The control switches for the pressurizer heaters are not similar in function to other pull-to-lock controls and are operated differently. Placement of the control switch in lock-out or pull-to-lock position does not infer the availability of the heaters. The green indicating light remaining lit when in these positions provides information to operators that control power is available to the heater controls and that heaters are operable per Technical Specifications. The heaters would only be declared inoperable when the _associated control switch was placed in pull-to-lock or lock-out position in conjunction with the use of the red magnets. All heaters (proportional and backup) are used for normal plant operation. Backup heaters A and E are powered from the emergency buses and are used for emergency operation .
- During a walkdown of the pressurizer heater control switches in the Control Room, it was observed that only the proportional pressurizer heater has a pull~to-lock control switch and the other heaters (backup) utilize a lockout control switch. The proportional pressurizer heater control switch is a pull-to-lock, off, auto, on, spring-return to auto switch. The backup heater control switches are lockout, off, auto, on, four position maintained switches.
Safety Significance The pressurizer heater backup groups are safety related. Pressurizer heater status is a RG-1.97 variable D-13 (KW). Potential for Error The existing operation of the pressurizer heater status light and pull-to-lock switch position is consistent with ~eater controls and would not result in an operator being misled regarding the availability of the heaters. The potential for error is low. Consequences of Error - The consequences of error due to the illumination of the green indicating light when in the pull-to-lock position would not result in injury to the public/plant personnel or damage to plant equipment. 11.
19.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion, sufficient information is presented to justify not implementing the proposed changes which would. No station deviations, LERs/SOERs, or operational/safety concerns were
- noted concerning the pressurizer heater controls .
V ARS01I.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION INUREG-0700 SECTIONS D IEOPs/EPIPs D IERF/SPDS D
- IQ-LIST RG-1.97 D
D LERs/IOERs/SDRs D ITRAINING MODULES D ITECH. SPECS. D IDRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
)
. ~-
_./
. ~ "' r .,..,,.1,... Hu:,..
SURliY IA!T e CODE A NOTED I J A,,: ~ *_: '.j'.": ;!':.'..., AS_6:SS!11EN1 LAST. REVIE'lrl TITLE RESPurlS!B;LJTY STATUS DATE 2iB~2305 PRZR HTR CT~ STATLJS LT INDIC '6Wlh6 INtn.:SISTENT W/ 0Tt£R CTR!.S. EhS I! -s fa7/ll/SS
~ ERROR:
ERROR lN uP RESPONSE, fff PRO~ !)1:-SCRIPTIDN: It. PUU.-TC'r-LOCK PO:i"TH, STATl.6 LTS 11:MIH LIT TO JNDICATEBR!(k FEEDIN6 HTR CTR.. CIRCS IN CUlSED CiR O'Eti. e1ee PARAS~ NIJo'Ek:
- b. 5. 3, l, t; b.:i. b, .3 £>, 5, l,b.L. l 6.5.1.6.D.3 suasESTED B'lv<FI1:
~..r. bR*.E'I ~-" CTR.. IS liLJLl.-T~..O:K. EXTINSUI&o ~ l 6~t- STAT i.TS JN P-T-~
lkS:A-.. 3RD LT FOR Biil\R i:LDSED, fft DISPOSiTIDh:
/ EXilNmi!&.- itED/B'1N STATLIS !JS lN. Pi.il-TC-~~,{ K~~~ l l~STIU 3RD WHITE STAT LT iO INDICATE BRr<R Ci.CSE liHEt.: ;.:T, DATA Cu:.L.E.:'T!OII DESCRIPTI~ AND CODE Ni!M:EII; rl""5, 1 DIS?L.AVS &u11V:Y r~a. ! i:uNVEt.TICINS SUINEY T~.2 ~lil;ICATlDN k'.i> vA..IDATl~
fil:AA!v<~: PH!7H2 !5:~ Vi-71H IE:~'11, Pl-70-3 !2i~~I),
!TE~~ IhvilL.~::D:
If!~~ Nt.ffliicK ~ui:l,iT~ut. ~Ulltfii hAa.c SYSTE~ SJBSYSTEM PRZii hTRS So ~(Jc\
~ _( 0 c_,~.
. \
1i7 APPENDIXB9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT . 5
~ /o-,._d~ .*
t'd- JI. .:.x
~LANT/Ufil . {P~ PI~10)
ORIGINATOR: £-~Lr. ~ . .
- t£D NO.: _tl.OB I-;?30S VALIDATED BY: OAlE:
~t£DTITLE:*~~~~
~ ' *~g)d ~.
b) ITEMS INVOLVED:
~~
Su ~ :;o~ o S ~ </ (t..8 ~ , IJ-eBtn/~ i Ver)
,2()/j:J-:i~c, C, ( A~ Fw ~ )
e) SPECIFIC HUMAN ERROR.Cs):
* * #It I
/?1~ ~a,u.u.. ~ ~~ ~ ~
d~.. (I (
- B9-l
171 .( . APPENDIXB9 HED REPORT (CONTJNLED) _ t-Eo N*a.: ~~B! -:J~a.s' (P/r; .. f'I- lo) r I 99 .. 2
v-- - - HED PRIORITY RECORD
*.i HED ,, , D I 0.
YES
- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH. .. .
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE NO
. (PAM OR 1E)?
** ERROR POTENTIAL? 1 2 & g LOW .. HIGH
- 5. CONSEQUENCE OF ERROR: 5 f;*
iiiGii 110
- (-
J.
- E-~-
ef( b - 0
... HED NO. f'I- 7u-2
. . . .. VIRCINIA POWER
- 2. CB/-).. 'l-o ~
CONTROL ROOM DESICN REVIEW
,,,- HU.MAN ENGINEERING DISCREPANCY (HED)
RECOMMENDED RESOLUTION
)
- _ ) !l~)~~-9----~~.........,:;.p-~~~~~~----~~...;...;.;*~__t ____ fA
?tel ;.r . ~ ti.
ci,i t. I li
; I
.?
*Z COMMENTS:-------------------------~---~--------~-------------------~
ORICINATOR RF Iii!/ DATE REVIEWED * *r- 2;:- f.s-,
.,,.-.--.)
- ~:
*---~
. . *..-~ .
~ .
VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5.1 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.5.1.6 COLOR CODING (Cont'd)
- a. REDUNDANCY-In all applications of color coding, color should provide redundant information. That is, the pertinent information should be available from some other cue in addition to color.
- b. NUMBER OF COLORS (1) The number of colors used for coding should be kept to the minimum needed for providng sufficient information.
(2) The number of colors used for coding should not exceed 11.
- c. MEANING OF COLORS (1) The meaning attached to a particular color should be narrowly defined.
_ ....,.,,\
)
(2) Red, green, and amber (yellow) should be reserved for the following uses: Red: unsafe, danger, immediate operator action required, or an indication that a critical parameter is out of tolerance. Green: safe, no operator action required,
' I or an indication that a parameter is within tolerance.
Amber (yellow): hazard (potentially un-safe), caution, attention required, or an . I I indication that a marginal value or I parameter exists. I d. CONSISTENCY OF MEANING ( 1) The meaning assigned to particular colors should be consistent across all applications within the control room. (2) The meaning of a particular color shouid remain the same whether applied to panel surfacas or projected in signal lights or on I CRTs . I
- 6.So11
1---:*** VISUAL DISPLAYS 6.5
.--~
PRINCIPLES OF DISPLAY 6.5.1 *.. :f
*/
COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.5.1.6 COLOR CODING (Cont'd)
- d. CONSISTENCY OF MEANING (Cont'd)
(3) The meaning of a particular color should CAIC\E
..... remain the same both within and among
- the various systems to which it is applied.
- e. PRINCIPLES OF CO.LOR SELECTION (1) The primary principle which should be applied in selecting colors for coding purposes which do not have the immediate safety implications of red, green, and amber is to ensure that each color is recognized as different from any other. Exhibit 6.5-7 lists 22 colors of maximum contrast. Each successive color has been selected so that it will contrast maximally with the color just preceding it and satisfactorily with earlier colors in the
- list. The first 9 colors have been selected ;.:,~*::\
I so as to yield satisfactory contrast for **} red-green-deficient as well as color-normal observers. The remaining 13 colors are useful only for color-normal observers. (2) Colors selected for coding shou Id contrast well with the background on which they appear. (3) Ambient lighting .in the area in which color coding is used will influence the apparent color of the coded element (especially for surface colors). Each color selected for coding should be evaluated under all illumination con-ditions under which it is used. 6.5-12
* *F* """:*** * * * * ** ** .,. -. * *... ****- ... *,,- * * : * * * * * *** *,, * * - '*
VISUAL DISPLAYS 6.5 LIGHT INDICATORS 6.5.3 6.5.3.1 CHARACTERISTICS AND PROBLEMS OF COMPLIANCE CHECKLIST LIGHT INDICATORS (Cont'd) N/A Yes 'No Refen,nce/Comment
- c. PRECAUTIONS TO AVOID MISINTERPRE- .
TATION CA IC\E .... ( 1) System/equipment status shou Id be
.. inferred by illuminated indicators, and never by the absence of illumination.
(2) Provisions (design or procedural) should be made* to prevent interchanging indicator lenses.
- d. USE AS ALERTING INDICATORS-Alerting the operators to unfavorable status should be a function of the annunciator system and not assigned to light indicators. I !
- 6.5-21
LABELS AND LOCATION AIDS 6.6 / LOCATION AIDS 6.6.6 GUIDELINE COMPLIANCE CHECKLIST Reference/Comment 6.6.6.1 NEED FOR LOCATION AIDS Operator performance can be enhanced through the use of location aids such as demarcation, color, and mimics. GUIDELINE COMPLIANCE CHECKLIST N/A Yn No Reference/Comment 6.6.6.2 DEMARCATION
- a. USE- Lines of demarcation can be used to:
( 1) Enclose functionally related displays. (2) Enclose functionally related controls. (3) Group related controls and displays.
- b. CONTRAST-Lines of demarcation should be ....::---....
visually distinctive from the panel background .
- c. PERMANENCE-Lines of demarcation should be permanently attached.
GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.6.6.3 COLOR Color should be dedicated to specific functions or conditions throughout the control room in order for the code to elicit the expected operator response. The color coding scheme should be used consistently throughout the control room. Refer to Guideline 6.5.1.6 for specific recommendations on the use of color .
- 6.6-24
- NUMBER PROCEDURE TITLE REVISION 6
l-ES-0.1 REACTOR TRIP RESPONSE PAGE 7 of 15 STEP ACTION/EXPECTED RESPONSE i--~~--1 RESPONSE NOT OBTAINED 1----------------.
- 8. ~CHECK PRZR PRESSURE CONTROL:
a) Pressure - GREATER THAN a) Manually initiate SI. GO TO 1715 PSIG l-E-0, REACTOR TRIP OR SAFETY INJECTION, STEP 1. b) Pressure - STABLE AT OR b) IF pressure less than 2235 psig TRENDING TO 2235 PSIG and decreasing, THEN:
- 1) Verify PRZR PORVs closed: IF any valve can NOT be closed, THEN manually close associated block valve.
- 2) Verify PRZR spray valves demand at zero. IF valves can NOT be closed-;--THEN do the following:
- a. Stop RCP supplying failed spray valve:
- "
- A RCP for l-RC-PCV-1455A
- C RCP for 1-RC-PCV-1455B
- b. Defeat TAVG and ~T control for affected loop.
- 3) Verify PRZR heaters on.
IF pressure greater than 2235 psig and increasing, THEN:
- 1) Verify PRZR heaters off.
- 2) Control pressure using normal spray.
IF normal spray NOT available and normal letdown is in service, THEN use
. auxiliary spray.
IF auxiliary spray NOT available, THEN use one PRZR PORV . . . -.,
NUMBER PROCEDURE TITLE REVISION 4 NATURAL CIRCULATION CODI.DOWN 'W'ITH STEAM VOID IN RX l-ES-0.3 VESSEL PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE .--~~--1 RESPONSE NOT OBTAINED 1--~~~~~~--
- 4. CONTROL PRZR LEVEL:
a) .Level - GREATER THAN 20% a) Control charging and letdown to raise PRZR level to greater than 20%. b) Level - LESS THAN 90% b) Do the following:.
- 1) Turn on PRZR heaters to maintain PRZR pressure stable,
- 2) Lower PRZR level to less than 90% by one of the following:
- Control charging and letdown .
~ Continue cooldown to shrink RCS inventory.
- 5. CHECK RVLIS UPPER RANGE INDICATION Repressurize RCS to maintain RVLIS
- GREATER THAN 77% upper range greater than 77%.
RETURN TO Step 3. f.
NUMBER PROCEDURE TITLE REVISION 6 1-E-3 STEAM GENERATOR TUBE RUPTURE PAGE
- STEP ACTION/EXPECTED RESPONSE i--~~---4 26 of 32 RESPONSE NOT OBTAINED t--~~~~~~---.
CAUTION: RCS and ruptured SG(s) pressures must be maintained less than 1035 psig.
- 33. CONTROL RCS PRESSURE AND MAKEUP FLOY TO MINIMIZE RCS TO SECONDARY LEAKAGE:
a) Do appropriate action(s) from table: I RUPTURED SG(s)*NARROY RANGE LEVEL PRZR LEVEL .. INCREASING DECREASING OFFSCALE HIGH
- LESS THAN 241
[55%) Raise RCS Makeup Flow Depressurize RCS Using Raise RCS Makeup Flow Raise RCS Makeup Flow Maintain RCS And Ruptured SG(s) Step 33b Pressures Equal BENEEN 241 [55%) Depressurize Turn On Maintain RCS And AND 501 [60%) RCS Using PRZR Ruptured SG(s) Step 33b Heaters Pressures Equal BENEEN 50% [60%)
- Depressurize Turn On Maintain RCS AND 731 [65%) RCS Using PRZR And Ruptured Step 33b Heaters SG(s) Pressures Equal
- Lower RCS Makeup Flow GREATER THAN )31 Lower RCS Turn On Maintain RCS And
. [ 651] Makeup Flow PRZR Ruptured SG(s).
Heaters Pressures Equal b) Use normal PRZR spray IAY b) IF normal letdown in service, Step 33a .TI!fili use auxiliary spray. IF NOT, THEN use one PRZR PORV .
R1MS003A 276 1 2.5 0.0005 l'lllEN "AS BUILT" 12846 .50-EKS120
. . J04A 277 1 2.5 0.0005 HHEN "AS BUILT" 12846.50-EKS120
.- Wsoo1A 278 l 2.5 0.0005 HHEN "AS BUILT" 12846.50-EKS120
- 1 82 81 4 85 60 6
1 62 32 44 46 5
- INPUT INSTRUMENT MARK POINT DESCRIPTION DATE TESTED L
I S C U H i3 A
*L N INSTRU RANGE HIGH INSTRUMENT LON INSTRUMENT ENGR UNITS
- NUMBER NUMBER N K
I N N E K L UNCONV RANGE RANGE
- MlNM013A 1S01-23A 1-PRO-NMl EXCR NTN FLUX SOURCE IRDJ <> 10-12-88 01 l 23 RMRKSC 5.0 -1.0 LOGCPS 1t MlNM016A MlNM014A 1S02-17A 1S02-16A l-PRO-NM2 l-PRO-Nl12 EXCR NEUTRON FLUX HIDE IHT) <>
EXCR NTN FLUX SOURCE (HT)<> 09-24-88 09-24-88 01 01 3 3 17 16 RMRKSC RMRKSC 2,301 5.0
-8.0
-1.0 LOGPCT LOGCPS lit vt~~~OlA
*:1RC002A 1Sl5-16A 1Sl5-17A 1-RC-CT-lRCPlA 1-RC-CT-lRCPlB RCS PUMP A LOAD (NL)
RCS PUMP B LOAD INL) 01-21-86 01-21-86 03 03 4 4 16 17 0-lODC 0-lODC 1200.0 1200.0 0.0 0.0 AMPS AMPS
,. YlRC003A QlRCOOlA 1Sl5-18A 1Sl3-22A 1-RC-CT-lRCPlC l-RC-CH-14PH RCS PUMP C LOAD INL)
BKUP PRZR HTR lH BUS PHR IORl 01-21-86 11-06-88 03 02 4 5 18 22 0-lODC 0-lODC 1200.0 500.0 0.0 0.0 AMPS KH
~ QlRC002A FlRC004A 1Sl4-22A 1S01-04A l-RC-CH-14PJ l-RC-FT-1414 BKUP PRZR HTR lJ BUS PHR IPL)
RCS LOOP A FLOH (RD) 04-20-88 02-04-86 02 01 7 l 22 04 0-lODC l-05DC 500.0 120.0 0.0 0.0 KH PCT
'if FlRC005A FlRC006A 1S27-01A 1S05-19A l-RC-FT-1415 l-RC-FT-1416 RCS LOOP A FLOH IHT)
RCS LOOP A FLOH IBL) 03-11-86 01-07-86 07 01 2 7 01 19 l-05DC l-05DC 120.0 120.0 0.0 0.0 PCT PCT
** FlRC007A FlRC008A 1S01-05A 1S27-02A l-RC-FT-1424 l-RC-FT-1425 RCS LOOP B FLOH IRD)
RCS LOOP B FLOH IHT) 02-04-86 03-11-86 01 07 l 2 05 02 l-05DC l-05DC 120.0 120.0 0.0 0.0 PCT PCT
- 1' FlRC009A
. . FlRCOlOA 1S05-20A 1S01-06A l-RC-FT-1426 l-RC-FT-1434 RCS LOOP B FLOH IBLJ RCS LOOP C FLOH (RD) 01-07-86 02-04-86 01 01 7
1 20 06 l-05DC l-05DC 120.0 120.0 0.0 0.0 PCT PCT
- FlRCOllA FlRC012A 1S27-03A 1S05-21A l-RC-FT-1435 l-RC-FT-1436 RCS LOOP C FLOH IHT)
RCS LOOP C FLOH IBLJ 03-11-86 01-07-86 07 01 2 7 03 21 l-05DC l-05DC 120.0 120.0 0.0 0.0 PCT PCT t, FlRCOOlA
**FlRC002A 1S05-09A 1S05-12A l-RC-FT-1961 l-RC-FT-1962 RCS A COLD LEG SI FLOH (Bl)
RCS B COLD LEG SI FLOH (BL) 10-11-86 10-11-86 01 01 7 7 09 12 l-05DC l-05DC 600.0 600.0 0.0 0.0 GPM GPM
- Page: 65 variable Classifications 0*11 2 APPENDIX 8.1 Category Variable Description PRIMARY SYSTEM SAFETY RELIEF VALVES Mark N~r 1*VHS*Yl*100C:
2 1*VHS*YY* 100A* 1 2 1*VHS*YY* 100A*2 2 2*HIS*HUX*12A 2 2*VHS*CABL*LN 2 2*VMS*YE*200A*1 2 2*VMS*YE*200A*2 2 2*VMS*YE*200B*1 2 2*VHS*YE*200B*2 2 2*VMS*YE*200C*1 2 2*VMS*YE*20DC*2
- 2 2
2 2*VMS*Yl*20DA 2*VHS*YI*200B 2*VMS*Yl*200C 2 2*VHS*YY*200A*1 2 2*VMS*YY*200A*2 0*12 A*13 PRESSURIZER LEVEL (SEE A*13) 0*13 2 PRESSURIZER HEATER STATUS* SEE VARIABLE REVIEY PACKAGE 2 PRESSURIZER HEATER STATUS 1*MIS*MUX*13A 2 1*MIS*MUX*14A 2 1*RC~ C\I* 14PH 2 1*RC*CY*14PJ 2 2*M1S*MUX*13A 2 2*MIS*MUX*14A
- 0*14 2
2 3 QUENCH TANK LEVEL 2*RC*C\1*24PJ 2*RC*C\1*2RPH 1*RC*L*1470
- 3. The steam volume must be large enough to accommodate the surge resulting from the design step-load reduction of load with reactor control and steam dump without the water level reaching the high-level reactor trip point.
- 4. The steam volume must be large enough.to prevent water relief through the safety valves following a loss of load with the high water level initiating a reactor trip.
- 5. The pressurizer does not empty following reactor and turbine trip.
- 6. The Safety Injection Signal (SIS) is not activated during reactor trip and turbine trip.
To account for these factors and to provide adequate margin at all power levels, the water level in the pressurizer is programmed as a function of average reactor coolant . temperature. High or low water level error signals result in the control actions which maintain pressurizer pressure and level. The limit on the maximum water level in the pressurizer ensures
- that the initial safety analysis assumptions are valid while also ensuring a steam. bubble is formed in the pressurizer and avoiding solid system operation.
The pressurizer heaters are single-unit, direct immersion heaters which protrude into the pressurizer through sleeves welded in the lower head. Each heater is internally restrained from high amplitude vibrations and can be individually removed for maintenance during plant shutdown. Approximately 30 percent of the heaters are *connected to proportional controllers which adjust the heat input as required to account for steady-state losses and to maintain the desired steam pressure in the pressurizer. The remaining heaters, referred to as backup heaters, are connected to on-off controllers. These heaters are normally energized but are turned off by a low-low pressurizer level signal. A low-low pressurizer level signal deenergizes all heaters to prevent heater burnout. The requirement that 125 kW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at hot" standby. These heater banks are designated 11 A" and 11 E 11 , and they can be controlled from MCR (BBl-
- 1) or from Aux. Shutdown Panel. Following 4 loss of offsite power (Loop) event, a 180 second time delay prevents reenergizing the II A II and 11 E" banks to prevention load of EDG when it assumes the emergency bus load.
NCRODP-38-S Page 80 03-31-92
- b.
c. the reactor is critical, or the RCS is not connected to the RHR System;
- 3. safety valve lift settings maintained at 2485 psig ( +/- 1 percent).
Below 350°F the RHR System removes decay heat and thus controls temperature and pressure. Above 350°F two safety valves have the capability to relieve the maximum pressure surge caused by a complete loss of load. Technical Specification 3.1.A.4 requires that loop stop valves remain open unless the RCS is connected to an operable RHR System. This specification ensures a decay heat removal mechanism is available to the core when the RHR System is not operable. Technical Specification 3.3 requires that the feeder breaker to the loop stop valves (and bypass relief'Iine. isolation valves) be locked in the open position during power operation, ensuring a core cooling flow path .
- Technical Specification 3.1.A.5 requires a minimum shutdown margin unless a bubble exists in the pressurizer, spray is available, and 125 kW of heaters powered from an emergency bus are operable. The steam bubble requirement ensures critical operations do not occur with a solid RCS. The 125 kW of heaters is the minimum heater capability to maintain natural circulation following a loss of offsite power.
Technical Specification 3.1.A.6 requires the following:
- 1.
- Two PORVs and associated blocking valves must be operable whenever the reactor K.tr is greater than 0.99.
- 2. With one or more PROV(s) (or blocking valve(s)) inoperable, the valve must be restored to operating status within 1 hour.
If the PORV is inoperable, the associated blocking valve is shut and power is*. removed from its motor operator. If the blocking valve is inoperable, power is removed from the PORV solenoid valves . NCRODP-38-S Page 153 03-31-92
- 4. Reactor Coolant Loops TS 3.1-4 10-24-:-90 I Loop stop valves shall not be closed in more than one loop unless the Reactor Coolant System is connected to the Residual Heat Removal System and the Residual Heat Removal System is operable.
- 5. Pressurizer
- a. The reactor shall be maintained subcritical by at least 1% until the steam bubble is established and the necessary sprays and at least 125 KW of heaters are operable.
- b. With the pressurizer i~operable due to inoperable pressurizer heaters, restore the inoperable heaters within 72 hours or be in at 1*
least hot shutdown within 6 hours and the reactor coolant system
- temperature and pressure less than 350°F and 450 psig, respectively, within the following 12 hours .
- Amendment Nos. 148 and 144
MA'r'-14-1992 09:39 FROM STONE & WEBSTER
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11.22 CORRECTIVE ACTION EVALUATION
- CA NO.:
CA DESCRIPTION: EQUIPMENT MARK NO. 22E Remove unnecessary indicating lights from heat tracing panel. HEDNO. Load Frequency & Heat Tracing Panel 22A01308 Il.22.1 BED REVIEW - ORIGINAL FINDINGS HED No. 22A01308 - Inconsistent meaning/application of color coding within/among systems. (NUREG-0700, Sections 6.5.1.6.c.2, 6.4.2.2.f.1 and 6.5.1.6.d.1.3) The original eRDR finding identified that the indicating lights on the heat tracing panel did not conform to guidance provided in NUREG-0700 regarding indicating light convention.
- Il.22.2 HED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs 0 YES IXI NO D NIA EOPs only address H 2 Analyzers.
RG-1.97 DYES ONO IXIN/A Heat Tracing is not associated with R.G. 1.97. EPIPs 0 YES IXI NO O NIA LERs/IOERs DYES IXI NO D NIA Heat tracing is not identified in the EPIPs. No LERs/SOERs were found concerning heat tracing circuitry or alarms. APP.R 0 YES IXI NO D NIA HPES/STA DEV/SOER DYES IXINO ON/A Heat tracing is not required for Appendix R safe No station deviations/SOERs were found regarding the shutdown. heat tracing system. ERF/SPDS DYES IXI NO D NIA TECH SPEC ITEM IXI YES ONO D NIA Heat tracing is not associated with ERF/SPDS. Section 3.2-2 eves 3.3-1 Safety injection
- 3. 7-2 Instrument systems VARSOIK.B7S-l
11.22.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The existing red indicating lights on the Load Frequency Control and Heat Tracing Monitoring Panel in the control room glow dimly under normal conditions. When one of the heat tracing monitored panels/cabinets senses an alarm condition, the associated light will glow brightly. When the CVCS Heat Tracing Alarm annunciates (technical specification alarm), the operator can use these lights to determine which local panel(s) caused the alarm. An operator can then be dispatched to the indicated Heat Tracing Panel to determine the specific alarming circuit.
Although the red lights perform two means of indication (i.e. dim lights - normal, bright lights - alarm, the operators are accustomed to responding to the alarm and performing procedural corrective actions. This dim-bright feature is explained in detail in the annunciator response procedure for the CVCS heat tracing alarm. In addition, the operability of the CVCS heat tracing is verified during technical specification flowpath operational walkdowns (OCS,6) once every shift. Safety significance - The heat tracing system is a supportive system for safety related systems. Potential for error - The potential for error is low as the alarm and indicating light combination provides adequate operator information. An operator has the ability to locate the bright-dim indicating light easily based on grouping of all heat tracing lights on the heat tracing monitoring panel. Consequence of error - The consequence of not responding to a loss of heat tracing is of importance. However, local readings are taken manually each shift and process instrumentation is available for additional information .
- 11.
22.4 CONCLUSION
S/RECOMMENDATIONS Based on the above information, it is recommended that the red heat tracing lights remain on the heat tracing panel. Further justification is provided based on no identified station deviations or operator errors with the existing installation were found and that the individual heat tracing circuits are mdnitored locally each shift. It is recommended that new labels be installed on the panel to ensure that heat tracing system components are consistent with current labeling requirements of STD-GN-0036. Operators are trained that a red dim light indicates normal heat tracing system operation and a bright red light is indicative of an alarm condition .
- VARS01K.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST IRG-1.97 D
D ILERs/IOERs/SDRs D I1RAINING MODULES D ITECH. SPECS. D ~ IDRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
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- '7 TP-8.1 CONVENTIONS l May 1983 APPENDIX 89 .
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- RECOMMENDED RESOLUTION ST AT I ON /UN IT _ _ _ S_u_,,_r..,./..._. .IJ
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MARK NO. 1TEM DESCRIPTION _ _ fj___ 1_~_/r.._r!(__ P__ l,l-__ c_~_ _ S___-f-a_i__.s---'/....d.,___/4__,_____A_P..."'..;;e....,(_ _ tA. CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) Ctr1 .~-e I C iv c "";f y '( I
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- COMMENTS:
DATE REVIEWED 6 r.S
.VIRCINIA POWER HED NO. f, I -I-~,
CONTROL ROOM DESIGN REVIEW 2 2 Ao- 1.J~. HUMAN ENGINEERING DISCREPANCY (HED) RECOMMENDED RESOLUTION STATION/UNIT SlA""'Y J,,;is ( J,_ 2
---"---+, ---------------
MARK NO. 1TEM DESCRIPTION ___ F__t~o.....0_£__ (_Q__ o__f_____f__o_r._e........(_*- - - - - - 1 ___ ,,....__:f.....,,_- CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) Ch Oi1,rtd c_ ~ v cv1 , *i r T i1 .s "- cl f /.4 Ii- t..li ,-{ e / f , t. t 1 ( .r e/tf;t (p
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0R1c1NAT0R /3. r H; 11 DATE REVIEWED ' - 7-?S
CONTROLS 6.4 .* :~'-,
- 6.4.2.2 CODING OF CONTROLS (Cont'd) e.
00©0© ROTATING KNOB SHAPE OPTIONS (Cont'd) DESIGN PRINCIPLES 6.4.2 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment
.o(h).
[JI] (i) m [] (j) (k) w(1) Fractional Rotation Knobs: These knobs are for use on controls that do not require twirling or spinning, for which the adjustment range is less than one full turn; and for which the knob position is not a critical item of information. Exhibit 6.4-5. Shape-eoded knobs-fractional rotation. (n) (o) (p) (q)
.jSJ
- Detent Positioning Knobs: These knobs are 'i;~...._:.)
for use on discrete setting controls, for which position is critical. Exhibit 6.4-6. Shapeoeoded knobs-detent positioning.
- f. COLOR CODING
{1) Color coding should follow the recom~ mendations of Guideline 6.5.1.6. (2) When color coding is used to relate a control to its corresponding display, the same color should be used for both the control and the display. (3) The color of the control should contrast with the panel background. {See Guide-line 6.1.5.6.e.)
- - - - CA 2'2..E..
6.4-10
VISUAL DISPLAYS 6.5 PRINCIPLES OF DISPLAY 6.5. 1 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.5.1.6 COLOR COOING (Cont'd)
- a. REDUNDANCY-In all applications of color coding, color should provide redundant information. That is, the pertinent infom,ation should be available from some other cue in addition to color.
- b. . NUMBER OF COLORS
( 1) The number of colors used for coding should be kept to the minimum needed for providng sufficient infom,ation. (2) The number of colors used for coding should not exceed 11.
- c. MEANING OF COLORS (1) The meaning attached to a particular color should be narrowly defined.
(2) Red, green, and amber (yellow) should be reserved for the following uses:
' I Red: unsafe, danger, immediate operator action required, or an indication that a.
critical parameter is out of tolerance, Green: safe, no operator action required, I or an indication that a parameter is within tolerance. Amber (yellow): hazard (potentially un-safe), caution, attention required, or an . I indication that a marginal value or I parameter exists. I
- d. CONSISTENCY OF MEANING (1) The meaning assigned to particular colors should be consistent across all applications within the control room.
(2) The meaning of a particular color shouid remain the same whether applied to panel surfaces or projected in signal lights or on I C~Ts. I
- - - - - CA'22E..
- 6.5-11
VISUAL DISPLAYS 6.5 .--~ PRINCIPLES OF DISPLAY 6.5.1 ** .. .1 C,A22E. */ COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.5.1.6 COLOR CODING (Cont'd)
- d. CONSISTENCY OF MEANING (Cont'd)
(3) The meaning of a particular color should remain the same both within and among the various systems to which it is applied.
- e. PRINCIPLES OF COLOR SELECTION
( 1) The primary principle which shou Id be applied in selecting colors for coding purposes which do not have the immediate safety implications of red, green, and amber is to ensure that each color is recognized as different from any other. Exhibit 6.5-7 lists 22 colors of maximum contrast. Each successive color has been selected so that it will contrast maximally with the color just preceding it and satisfactorily with earlier colors in the
- list. The first 9 colors have been selected : .* :~::\
I so as to yield satisfactory contrast for *._;: red-green-deficient as well, as color-normal observers. The remaining 13 colors are useful only for color-nom,al observers. (2) Colors selected for coding should contrast well with the background on which they appear. (3) Ambient lighting in the area in which color coding is used wil I influence the apparent color of the coded element (especially for surface colors). Each color selected for coding should be evaluated under all illumination con-ditions under which it is used.
- . -~* ....:***** - .. -~ **: -. ****. ****- .***:- .. ......... *****-
6.5-12
The OT (overtemperature), SP (setpoint), and UT (undertemperature) LEDs are both in red color, either one will illuminate to indicate that an abnormally high or low temperature condition exists; the SP LED is in green color and will illuminate to indicate that power is applied to the heat tracing cable. The high and low temperature alarms are set to annunciate at 180°F and 125°F for the normal panels (the" "A" panels) and 180°F and ll5°F for the backup panels (the "B" panels). The operating temperature setpoint for the normal supply panels is 150°F. The operating temperature setpoint for the corresponding backup panels is 125°F. Actuation of an Undertemperature or Overtemperature alarm on any CVCS heat tracing panel is indica_ted in the MGR on the heat tracing section of the Load Frequency Control and Heat Tracing Monitoring Panel (LFCHTMP)*. The following heat tracing panels and cabinets are monitored on the LFCHTMP (see Table 22-1 for panel cabinet locations):
- 1. HTP-2Al, -2A2, -2A3, -lAl (spare), -1A2 (spare), -2Bl, -2B2, -2B3, -
lBl (spare), -1B2 (spare), -5; and
- 2. HTC-1, -2, -3, -4, -5, -10, -11, -12, -14, -15, -16, -19.
The HTP-2Al, -2A2, -2A3, -2Bl, -2B2 and -2B3 panels have had a design change installed so that only those circuits that are Safety Related (see Tabl~ 22-3) send a signal to the LFCHTMP in the MGR. Also when one of these circuits alarms a signal is sent to the CVCS Heat Tracing Trouble alarm (VSP-E8) in the MGR. The red indicating lights on the LFCHTMP glow dimly under normal conditions. When one of the monitored panels/cabinets senses an alarm condition, the associated light will glow brightly. When a eves Heat Tracing alarm annunciates, the operator can us_e these lights to determine the panel(s) which caused the alarm. An operator can then be dispatched to the indicated Heat Tracing Panel. to determine the alarming circuit. Application of power to the individual heat tracing circuit is controlled by the ON/AUTO/OFF toggle switch on the individual heat tracing circuit control module. In the ON position, the heat tracing cable is always energized. In the
- NCRODP-22-S Page 6 04-05-91
TABLE 22-2
- Heat Tracing Set Number POwffiR SUPPLIES (Continued)
Power Supply HTC-3 MCC-lBl-lA, breaker 24B HTC-4 MCC-lJl-1, breaker 84B HTC-5 MCC-lHl.-1, breaker 82A HTC-10 MCC-2Jl-2, breaker 31B HTC-11 MCC-lHl-1, breaker 12A HTC-12 MCC..:1B2-2A, breaker 13B HTC-13 MCC-lGl-1, breaker 42A
- HTC-14 HTC-15 MCC-1Al-2A, breaker 15A MCC-lAl-1, breaker 12B HTC-16 MCC-2Cl-l, breaker 33B HTC-19 MCC-2Bl-3A, breaker 13B HTC-20 MCC-lGl-lA, breaker 15B.
- NCRODP-22-S Page 4 12-11-90
TABLE 22-3 SAFETY RELATED CIRCUITS Heat Tracing Panel Circuits HTP-2Al l - 38, 44, 46-53 HTP-2A2 l - 39, and 44-46 HTP-2A3 2 - 15 HTP-2Bl l - 38, 44, 46-53 HTP-2B2 l - 39, and 44-46 HTP-2B3 2 - 15 NOTE: Only these circuits are used to cause alarm indication
- on the Load Frequency Control and Heat Tracing Monitoring Panel, and as input to the the Main Control Room .
eves HEAT TRACING TROUBLE alarm in
- NCRODP-22-S Page 5 12-11-90
11.23 CORRECTIVE ACTION EVALUATION
- CANO.:
CA DESCRIPfION: 23E Modify EOG megawatt, megavar and RPM indication on EOG panels in Control Room to improve viewing. Relocate indicators similarly on the local control panel in Diesel Generator Room. Coordinate with CA15E and CA75E. EQUIPMENT MARK NO. HEDNO. EDG No. 1 & 2 Control Panels, 1/2DIP-DGRH local 22A02086, 22A02314 panels 11.23.1 IIED REVIEW - ORIGINAL FINDINGS HED No. 22A02086 - Displays on EOG too low/high to be viewed from normal viewing area. (NUREG-0700, Sections 6.1.2.2 and 6.1.2.5.b) HED No. 22A02314 - A few non-legend indicator lights do not have apparent meaning. (NUREG-0700, Section 6.5.3.2.a.1) This HEO was deleted during the original CRDR and therefore was not included in the CRDR reassessment .
- 11.23.2 IIED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs IXIYES ONO ON/A Instruments on the EDG panels are used for verification of EDG operation and setpoints in various EOPs RG-1.97 IXJYES ONO ON/A The EOG panels contain instruments for monitoring R.G.- 1.97 variable D-35F.
including 1-ECA-0.1, 1-ECA-0.2, l-E-1, and 1-ECA-0.0. EPIPs 0 YES IX) NO O NIA LERs/IOERs O YES IXI NO O NIA These indicators are not used for EPIP assessment. No applicable LERs/IOERs were found. APP.R IXJYES ONO ON/A HPES/STA DEV/SOER DYES IXINO ON/A The EDG panels are Appendix "R" related equipment. No applicable station deviation/SOERs reports were found. ,. ERF/SPDS O YES IX) NO O NIA The EOG panels are not part of ERF/SPOS. TECH SPEC ITEM IXI YES ONO O NIA The EOG panels are required to be operable per technical specifications. VARS01L.B7S-l
11.23.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE The EDG megawatt, megavar, and speed indicators are used by the operators to control and monitor the operation of the station emergency diesel generators. This instrumentation is used by the operators when operating the diesel manually during the performance of periodic test procedures. During tests, the diesel is manually loaded by the operator. During accident conditions, the diesel operation and loading is automatic. The operator is required to energize/de-energize equipment on the associated bus to adjust diesel load. Safety Significance The EDG No. 1 & 2 control panels contain safety-related Class lE equipment. NUREG-0700 Section 6.1.2.2 recommends as good practice, that indicators/components be within 70 inches from the floor for readability. The megawatt indicators that display specific values that are required to be read in EOPs. EOPs require the operator to maintain 2750 kW. Technical Specification Section 3.16c limits the continuous load on the EDG to 2750 kW. Potential for Error The potential for operator error due to meter height is low based on automatic protective features. Monthly EDG slow start tests (i.e., PTs 1/2/0-0PT-EG-001) have been performed without any documented errors or problems. Consequence of Error - The consequence of error due to indicator height would be a delay in operator response when determining load on the EDG. 11.
23.4 CONCLUSION
S/RECOMMENDATIONS Minor variations in the megawatt reading, resulting from parallax error (i.e., the next minor scale graduation lOkW) will not introduce any adverse affects on the operator's ability to maintain the EDG within rated load. Modifications to the EDG panels are not required based on the following justification:
- 1. No adverse affect from slight variations due to minimum parallax error (with minor scale graduation 10 kW).
- 2. No generator simulator training errors, or problems identified during monthly PTs.
V ARS01L.B7S-l
APPLICABLE HEDs WITH BACK-UP .o DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D CHECKLIST
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177 TP-1.2 l May 1983
- APPENDIX B9 HUMAN ENGINEERJNG DISCREPANCY (HEO) REPORT . .J:'\;;/~
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- 6. S. 3. 2, A. l SU66ESiED BACKFIT:
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- HUMAN ENGJNtERlNG 01SCREPANCV (HEO) RC"POR T 22..fArO- 25t>g PLANT/UNIT
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c) PROBLEM DESCRJPTJON AND D700 PAR.A. NUMBER: c:;; 53~G1 I Th"£ ~ /Sr£D /Nl>IC~'Tfh~ ~lf.Nr.S Alt'£ Ah:rr
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- l May l9S:3
- . APPENDIX B9 HED REPORT (CONTI~)
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- APPENDIXB9 HED REPORT (CONTINUED)
HEO NO.: fS- ~ f) SUGGESTED BACKF"IT1 ~53 :;2. q I
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VIRGINIA POWER CONTROL ROOM DESIGN REVIEW ;).cJ. /JO-.J0..]9 HUMAN ENGINEERING DISCREPANCY (HED) RECOMMENDED RESOLUTION
- STATION/UNIT . .Su
------,..----------------I" Y-11 ( g* l.
MARK NO. 1TEM DESCRIPTION fiJC- /1elj,nJ~ft .t&~dVdY- , ti-I \pe./ In/r-r,{o.,-.r 7 I 7 I I CHANCE DESCRIPTION (REC'OMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTION o/ e I-/. e E /)C,- t":.. ~ wa._ 11. ;*c"i().--J
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COMMENTS: ORIGINATOR_ _ 8__..._E.....~___H__;__//_____DATE REVIEWED 8'- t -; £"
-* GUIDELINE CONTROL ROOM WORKSPACE WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST Reference/Comment 6;1 N/A Yes No 6.1.2.2 STAND-UP CONSOLE DIMENSIONS
- a. CONSOLE HEIGHT TO SEE OVER-When it is necessary for a standing operator to see over the top, console height (with or without annun-ciator panels) should not exceed 58 inches.
- b. CONTROL HEIGHT-The. range of suitable control height on stand-up consoles is defined by the reach radius of the 5th and 95th percen-tiles (as defined in Exhibit 6.1-5). Measurements should be made using shoulder height and functional reach with the shoulder in line with the leading edge of the benchboard, as shown in Exhibit 6. 1-6. The exhibit shows the results of two console designs with differing bench-board slope and depth. Controls may be placed somewhat higher on consoles with shallower and/or more steeply angled benchboards, which allow the shoulder reference point to be *:**?\
_:...)*i.*
- closer to the back of the benchboard and to *
"1 . . .* '
the vertical panel. ( 1) The highest control on a stand-up console should be within the highest reach of the 5th percentile female without stretching or using a stool, ladder, etc. (2) The lowest controls on a stand-up console should be within the lowest reach of the 95th percentile male without bending or stooping.
- c. BENCHBOARD SLOPE - The benchboard slope, in conjunction with its depth, should result in all controls being within the reach .
radius of the 5th percentile female, as illus-trated in Exhibit 6.1 *6.
- d. CONTROL DISTANCE FROM THE FRONT.
EDGE OF THE CONSOLE (1) Controls should be set back a minimum of 3 inches from the front edge to protect against accidental activation.
- --~ ;
*/
- 6. 1* 16
.. **-*-' ....~*-..:..._~-~- **... *_ .....:...:._2_. *.-.:*** .. ___..*__..._._.*:'*:.** ... *:., ._.._*,.-...... ***
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CONTROL ROOM WORKSPACE N/A WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST Yes No Reference/Comment 6.1 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
- d. CONTROL DISTANCE FROM THE FRONT EDGE OF THE CONSOLE (Cont'd)
(2) No control should be more than 25 inches from the front edge of the console. This accommodates the maximum reach of the 5th percentile female adult as illustrated in Exhibit 6.1-6. INCHES
,oa 96 ........
84
' ' '\
SHOULDER FUNCTIONAL \ HEIGHT" R~ACH \ , FUNCTION.AL LIMITS ON 72 SHOULDER" , __ f _____ I 95TH REACH " CONTROL HEIGHT* PERCENTILE LIMITS ON li5IG_t!T_ 61 .s*: 3] O"' CONTROL* MALE 61.8-,'-++- 60 - * - - - *- -, -- 63 t
!::!_EIGHT MAX.
5TH 49.4-..__.__ ~.2_:: 48 M
- _ _~ ....._- I ~
MAX. PERCENTILE FEMALE 36 27 24 27 MIN. MIN. 12
- One inch added for shoe height.
Exhibit 6. 1-6. Reach capabilities and control height on stand-up consoles .
- 6.1-17
- 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
CONTROL ROOM WORKSPACE NIA Yes WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST No Reference/Comment 6.1
- e. DISPLAY POSITIONING-The principal factors*
I,,.,,,=.,=,=*="""'=====.,,,,, affecting the readability of displays, including annunciator tiles, are: (1) display height and orientation relative to the operator's line of sight when he/she is standing directly in front of the display; (2) display distance and orien-tation relative to the operator's straight-ahead line of sight when the operator must read the display from an off-side position; and (3) the size of display markings relative to the distance at which the display must be read. Marking/ character size is addressed in Guideline Section 6.5.1, and is not considered here. Except as specifically noted, measurements of angles should be made with the eye point in line with the leading edge of the benchboard. This is illustrated in Exhibit 6.1-7. (1) DISPLAY HEIGHT AND ORIENTATION (al . All dispiays, including annunciator tiles, should be mounted so that they are within the upper limit of the visual field (75° above the horizontal line of sight) of the 5th percentile female. (bl In addition, all displays and annunci-ators should be mounted so that the angle from the line of sight to the face plane is 45° or greater. The 5th percentile female determines the upper limit. The 95th percentile male determines the lower limit .
- 6.1-18 *-.. /
** ** ,* **u-*w*-****\'" .___ .~.-
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1 .2 UPPER LIMIT OF VISUAL FIELD UPPER LIMIT OF VISUAL FIELD
,.. INCHES
/
\75° 108 I
96 I I 84 ,, II EYE 11 HEIGHT /1 HORIZONTAL 72 69.f!:~- ___ _ _ ,!.0§.0~ EYE HEIGHT HORIZONTAL 60 L.QS_O~ 48 5TH 36 95TH PERCENTILE PERCENTILE FEMALE MALE 24
~ .
12 Eye height from Exhibit 6. 1,5: inch added for shoe height Q Angle would be too small for readability if display - ~ mountlld on vertical surface Exhibit 6.1-7. Display height and orientation relative to standing operator LOS {line. of sight), I
** 6.1*19
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
- e. DISPLAY POSITIONING {Cont'd)
(2) HORIZONTAL DISPLACEMENT-The oblique angle from the line of sight to a display located to either side of the working position from which the display must be read should be at least 45°. This includes annunciator tiles, which should be readable from the acknowledge button. (See Exhibit 6.1-8.) Di1Pl11YS: Max. Displacement 48 36 24 12 0 12 24 36 48 t I 7' I I '
' ~if J
x~o t
/ 24 0
' / 12 -~
' .. 'v / //, / . J :;*:->/
Eye reference point for meten, gauges, etc.* VEve rafarence point for annunciator tih11* 0
.'/
- For meten and other displays which may heve to be read while a control anywhere on the benchboard is operated, measurement should be made with the eye reference point in line with the leading edge of the b1mch*
board. For annunciator tiles, the eye reference point may be beck from the benchboard edge. The dinance back should be consinent with the ability of the 5th percentile female to reach the annunciator response pushbunons. 12 inches is e suitable nominal distance back for most consoles. Note: A wraparound panel would allow greeter displacement. Exhibit 6. 1-8. Limit on horizontal displacement of displays from straight-ahead line of sight at the required reading position.
- 6.1-20
- - --* .....- ............ *-**1' *, * -- ............ _ .... .. *-* ............-*****-*- ', ""* .* -.... _. . ...... "*-***** -- -
\
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST 6.1.2;2 STAND-UP CONSOLE DIMENSIONS (Cont'd) N/A Yes No Reference/Comment
- f. LATERAL SPREAD OF CONTROLS AND DISPLAYS-The operator should be able to perform task sequences at a given work station with minimum respositioning. The amount of I -
operator movement required depends on the arrangement of controls and displays, not simply on the lateral dimensio!ls of the seg-ments of the control board. The maximum '
. lateral spread of controls and displays at a single-operator work station should not exceed I 72 inches. II I
'I !
- g. FOOT ROOM-Enough foot room is needed to allow the operator to get close to the board I I I
I II without leaning. A clearance of 4 inches verti- i i cally and 4 inches horizontally is recommended. I I ., 6. 1-21
... *:'\
- GUIDELINE N/A Yes VISUAL DISPLAYS LIGHT INDICATORS 6.5.3 COMPLIANCE CHECKLIST No Reference/Comment 6.5 . ;
_/ 6.5.3.2 DESIGN AND USE OF NON-LEGEND LIGHT INDICATORS Non-legend light indicators are represented by conventional pilot lights, bulls-eyes, and jewel lights. Color may be provided by a tinted cover glass or by a layer of colored material inside the cover.
- a. IDENTIFICATION OF MEANING
( 1) Where meaning is not apparent, labeling must be provided close to the light indicator showing the message intended by its glowing. (2) The color of the light indicator when transilluminated should conform to the general code es.tabl ished for the control
*I room. (See Guideline 6.5.1.6.)
(3) The color of the light should be clearly identifiable .
- b. LIGHT INTENSITY -The illuminate<:! indi*
- cater should be at least 10% greater in light intensity than the surrounding panel (as measured by a spot photometer) .
- 6.5-22
- >. *- *-* *-~-- .* .*:._. *~----*; :c: .i~---~*. -~- *.. . . :* . ;. . .___-.:. . . ,._.,.; -. _._....,__ _
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1.2
. -~! **:.-_..,r*
GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.1.2.5 VERTICAL PANELS Exhibits 6.1-13 and 6.1-14 show common problems resulting from poor placement of controls and displays on vertical panels. The following limits are recommended.
- a. CONTROL HEIGHT (1) Controls should be placed in an area between 34 inches and 70 inches above the floor.
(2) Controls requiring precise or frequent operation and emergency controls should be placed in an area between 34 inches and 53 inches above the floor.
- b. DISPLAY HEIGHT (1) Displays should be placed in an area between 41 inches and 70 inches above the floor..
(2) Displays that must be read frequently or precisely should be placed in an area between 50 inches and 65 inches above the floor.
\,
\ ___ CO(UZ.ECTl vE ALTl o~ 2 Jf
- 6.1-29
-NUMBER PROCEDURE TITLE REVISION 5
-* 1-ECA-0.1 STEP LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED
~
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED PAGE 3 of 16 i--~~~~~~-- CAUTION:
- The-load placed on any energized emergency bus should NOT exceed 1200 amps, when energized from offsite power.
- The load placed on any EDG should NOT exceed 2750 KW.
- 2. MANUALLY LOAD THE FOLLOWING EQUIPMENT ON ENERGIZED AC EMERGENCY BUS:
a) Align and start CHG pump:
- 1) Check valve alignment: 1) Manually align valves .
- CHG pump miniflow RECIRC valve(s) - OPEN
- CHG pump RWST suction valves - OPEN
- 1-CH-MOV-lllSB
- 1-CH-MOV-lllSD
- CHG line isolation valves
. - CLOSED
- l-CH-MOV-1289A
- l-CH-MOV-1289B
- 2) Start one CHG pump b) Start Safeguards area exhaust fan
- c) Start at least two CRDM fans
NUMBER ATrACHMENT TITLE REVISION 1-E-l 6 STOPPING UNLOADED EDGs ATrACHMENT PAGE 2 1 of 2 CAUTION: The EDGs should NOT be stopped until the CTMT is sub-atmospheric. NOTE:
- Only one EDG should be stopped at a time.
- EDG 1 should be stopped before EDG 3.
- 1. Verify that the base tank fuel oil level is greater than 290 gallons.
- 2. Push both ENGINE STOP pushbuttons simultaneously to initiate the engine cool down and stop sequence.
CAUTION:
- If an auto-start signal is received while the EDG is in the cooldown cycle, the EDG speed will __ increase to between 870 and 910 rpm. If the EDG speed does not stabilize between 870 and 910 rpm, the SPEED 0
CONT switch must be used to adjust EDG speed.
- The engine is in Governor Fast mode when in AUTO, resulting in speed adjustments being very sensitive. Changes made with the SPEED CONT switch should be small to prevent engine over~peed.
- 3. Verify engine speed decreases to between 470 and 490 rpm.
- 4. Depress the Auxiliary Trip Reset pushbutton and verify that the associated amber light goes OFF:
EDG 1 - Diesel Generator Isolation Panel in Unit 1 ESGR EDG 3 - Unit 1 EDG 3 Control Panel in the MCR
- 5. Verify that the EDG stops after a 9 1/2 to 13 1/2 minute cooldown period.
- 6. Verify or adjust the SPEED DROOP control on the UG-8 Governor to zero.
NOTE: Governor alignments will be performed by the Maintenance Department.
- 7. Verify scribe marks on the governor gears are aligned .
- 8. Verify governor SPEED KNOB is at the scribe mark on the dial .
TS 3.16-3 08-02-90
- 2. If a primary source is not available, the unit may be operated for seven (7) days provided the dependable alternate source can be operable within 8 hours. If specification A-4 is not satisfied within seven (7) days, the unit shall be brought to the cold shutdown condition.
- 3. One battery may be inoperable for 24 hours provided the other battery and battery chargers remain operable with one battery charger carrying the DC load of the failed battery's supply system. If the battery is not returned to operable status within the 24 hour period the reactor shall be placed in the hot shutdown condition. If the battery is not restored to operable status within an additional 48 hours, the reactor shall be placed in the cold shutdown condition.
- 4. A train of the opposite unit's emergency power system as required by Section 3.16.A.S above may be inoperable for a pe_riod not to exceed 14 days. During this 14 day period, the following limitations apply:
a) If the offsite power source becomes unable to energi~e the opposite unit's operable train, operation may continue provided its associated emergency diesel generator is energizing the operable train.
- b) If the opposite unit's operable train's emergency diesel generator becomes unavailable, operation may continue for 72 hours provided the offsite power source is energizing the opposite unit's operable train.
c) Return of the originally inoperable train to operable status allows the second inoperable train to revert to the 14 day limitation. If the above conditions are not met, the reactor shall be brought to hot shutdown conditions within 6 hours and cold shutdown condition within the following 30 hours. C. The continuous running electrical load supplied by an emergency diesel generator shall be limited to 2750 KW .
.e.a.m The Emergency Power System is an on-site, independent, automatically starting power source. It supplies power to vital unit auxiliaries if a normal power source is not available. The Emergency Power System consists of three diesel generators for two units. One generator is used exclusively for Unit 1, the second generator for Unit 2, and the third generator functions as a backup
--for either Unit l or 2. The diesel generatoFS hav~ a continuous 2,000 hour rating of 2750 KW and a two hour rating of 2850 KW. The actual loads using conservative Amendment Nos. 143 and 140
TS 4.6-1 3-17-72 4.6 EMERGENCY POWER SYSn:M PERIODIC TESTING
/u:,-olicabilitv Applies to periodic testing and surveillance requirements of the Emergency Paver System.
Objective To verify that the Emergency Power System will respond promptly and properly when required. Soec!fication The follCW'ing tests and surveillance shall be performed as stated: A, Diesel Generators
- l. Tests and Frequencies
** Maznfally initiated start of tha diesel 1enerator, followed by manual synchronization with other pc,war
*o~cas and assumption of load by the diesel 1anarator up to 2750 .z.. Thi.L ~ will. b~ conducted mcnthly on uch di ... al 1e-nerator for a duration of 30 minutes. No?m&l station oparation will not be affected by this test.
.. J
TS 4.6*2 I b. 05-01-90 Automatic start of each diesel generator, load shedding, and restoration to operation of particular vital equipment, initiated by a simulated loss of off-site power together with a simulated safety injection signal. Testing will demonstrate load shedding and load sequencing initiated by a simulated loss of off-site power following I a simulated engineered safety features signal. Testing will also demonstrate that the loss of voltage and degraded voltage protection is defeated whenever the emergency diesel is the sole source of power to an emergency bus and that this protection is automatically reinstated when the diesel output breaker is opened. This test will be conducted during reactor shutdown for refueling to assure that the diesel generator will start within 1O sec and assume load in less than 30 sec after the engine starting signal.
- c. Availability of the fuel oil transfer system shall be verified by operating the system in conjunction with the monthly test.
- d. Each diesel generator shall be given a thorough inspection during
' 2. each refueling interval utilizing the* manufacturer's recommendations for this class of stand-by service. Acceptance Criteria The above tests will be considered satisfactory if all applicable equipment operates as designed. B. Fuel Oji Storage Tanks for Diesel Generators
- 1. A minimum fuel oil storage of 35,000 gal shall be maintained on-site .to assure full power operation of one diesel generator for seven days.
Amendr:1erl.t Nos. 141 and 139
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Il.24 CORRECTIVE ACTION EVALUATION CA NO.: 24E CA DESCRIPTION: Determine displays that most significantly affect plant safety on Auxiliary Shutdown Panel and modify to improve viewing. Coordinate with CA6E and CA21E. EQUIPMENT MARK NO. HEDNO. Pl-444A, Pl-464B, Ll-477B, Ll-467B, Ll-497B 22A02088 Il.24.1 BED REVIEW - ORIGINAL FINDINGS HED No. 22A02088 - Displays on Vertical Board Section too low/high to be viewed from normal viewing area. (NUREG No. 0700, Sections 6.1.2.2 and 6.1.2.5.b) DC-88-25/26 would relocate (5) indicators to a 25° tilted front panel section to improve readability. The DCP was not implemented.
- Il.24.2 BED REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs jg)YES ONO ON/A The auxiliary shutdown panel is operated under procedures O-FCA-1.00 and O-AP-20.00 RG-1.97 DYES ONO IXIN/A RG-1.97 is only applicable to Main Control Room instrumentation.
EPIPs 0 YES ONO jg) NIA LERs/IOERs O YES IXI NO O NIA EPIPs are not applicable to individual components on the No LERs or IOERs were found relating to readability of auxiliary shutdown panel. auxiliary shutdown panel information. APP. R
- IXIYES ONO ON/A HPES/STA DEV/SOER *DYES IXINO ON/A Indicators are used for Appendix R shutdown. No station deviations/SOERs were generated as a result of not being able to read instruments on Auxiliary shutdown panel.
ERF/SPDS IXIYES ONO ON/A TECH SPEC ITEM DYES ONO IXIN/A
- ERF points L1FW004A, LlFWOOSA, L1FW012A for steam generators wide range level only.
VARS01M.B7S-l The auxiliary shutdown panel is not Technical Specification related.
II.24.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- NUREG 0700 Section 6.1.2.S recommends in good practice that displays should be within 70 inches of the floor .
The displays on the ASP which deviate from this recommendation are Pressurizer Pressure, SIG press and S/G A,B, and C levels. (Top of indicators are approximately 88.S inches above the floor.) In review of the applicable FCA and AP procedures, it is identified that the worst case display values are for the operator to read 70% - 80% for the S/G levels. This reading is, out of all five indicators, at the higher range of the scale. Field walkdowns were performed to determine actual indicator display heights and viewing angles limits identified in NUREG-0700, Section 6.1.2.2. A walkdown of the panel shows no difficulty when reading these displayed values on indicators. Safety Significance .The indicators are Class 1E safety~related components. Potential for Error The potential for error is low when reading these indicators. The values which are to be read from these indicators are ranges and not specific setpoint values. Simulator training shows no errors experienced. No documented errors exist. Consequence of Error - Slight variations in the readings (within next minor graduation) will not have an adverse affect as the required values to be read are within a band and, therefore, no consequences of error.
- II.
24.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion. and the following, sufficient information is presented to justify not implementing this Corrective Action.
- 1. Procedures require reading a range, not a specific value.
- 2. The worst case reading indicators 70%-80%.
- 3. No documented errors
- 4. No simulator training problems were noted.
- 5. Slight variations in readings will have no adverse affect or system operation .
- VARS01M.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D Q-LIST D RG-1.97 D LERs/IOERs/SDRs D TRAINING MODULES D TECH. SPECS. D IDRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
SURRY ASSE&"'tlEl\'T LAS~ REVI:I. TlTLi RESPQt.SlBZLlTY .STATUS DATE ~DISPLAYS~ VBS TDD LCM/HIGH TO VE VIBIED F~ NORl'iAL VJEIIIN6 AREA II -5 e8/(!7/S5 . tlJIIR,j ERROR: lHRBlLITY TO lil:AD DISPlAYS. ff+ PROfUIII DESCRIPTI~: DISPLJIYS LOIIER TIAI 41" I ABOVE 70" CM<<>T BE \Ila.ED BY 5TH STll.E FEM-£ FROi\ f()fW'L VIEWIIE A!Bl. (FRONT OF BBi 8700 PAAA.";RAPtl MIER: 6.1.2.2 6.1.f.5.ll SU86£STED BAC!\~!T: D£TEAA!t DI5'1LAYS TriAi AFFE.C"f PL~T ~"E'TY & !Ei.OCATE TO til&iER/LOW:R LWlilON ON \IB TD ENSU~ EASE ~ VIEWI~. DATA COLLECTICll DESCri!PTHlN ~ CODE ~~111: T~l.c Atii~RO?O!l!ETRlCS SU~EY ITEMS lW"LL\'ED: ll!AR!< hU!l!i5Ef< LOCwi l~ COIIPOt¢" r ~ SYST111 Ll "'467B ff hu: lN lH\I F1:.£ t LI-477B ff NOT IN INV FILE t U-497B H J(IT IN l~v Fl~ t PI~ ff NOT I" INV FILE t Pl-464B. ff fi[)T IN IfN Fli.E
- G,ovc9.~tv4_ w:-~
177 TP-1.2 l May 1983
*- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT ~l)
'.':JO..
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Sue.e..y /2-PLANT/UNIT ORIGJNATOR: _ _ N_.__\::__\-rofs.::..ca~'t----- HED NO.: '.~ -1, VALIDATED BY:
--*--------- DATE: Ci\':\ \g4
&) HED TITLE: DI sPL.f:vs o N J.i;. B:Dc..eL f'e,,-)8-S e~,F"" ::roo L..OW p.,.:ic b) ITEMS lNVOL VED:
t)\<<; P\..PIY.S IN ~~ Pi-~"~C \_\5;.T c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER: C.., I. 'l. 'l. * * ~ 1. l. S""b 11 t*':::>P~s: Low~~ ~f\t.l "'-' Aa.>O A,Bov;: "1D "C.PrtJ~t:ri e.~ ,hewe.'O o"( "'M-t ~ 5.....-i A:~~,Jjl L' ~Mfti\.,- PROM NOlt-tAl.. v IE'"'"~'= ~e.e:r. lu~ ';:l,D,y-r 0~ S.~tl.~~~. 5-\0IJi..O t1bw~'"".1J'\ \.\-.1~"'~ n:r't e'° fllSO\.IG' 50 11 F\u. ~~Pl.f\'f$ 1S 41 1
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lg 511. d) DATA COLLEC.Tl::>~ DE:SCRJPTJON AND CODE NUMBER: TP 1.2.6~., ., . U)~l,.. ~001'""1 Si.,2111.y ~ ~,,a't~P.,,..~1'9> e) SPECJF'"lC H~M .O.N E:RROR(s): IN tlGI:. 1-:'y ib
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177 TP-1.2 1 May 1983 APPENDIX B9 HED REPORT (CONTJNLED) ' ~
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. . VIR-CINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
RECOMMENDED RESOLUTION
- STATION/UNIT
- Su .,,r,1 I £ .2.
MARK NO. 1TE M DESCRIPTION d:Ax ,* /oy v >({I, t,li/; ;,,.)1-~ Po."'~ ( o ;-:£ FC L r C7 r'.., ( 7 CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIO Rc? ;,v; -:>II e +-t e IO' C c~,.f ,*of C '"Ul ,*f ,,. .. .:1 *.~ . f'I~ I '
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- I":>. -11.~
iJ COMMENTS: f] _. /_ ORICINATOR ____,__f_,_,_f_,_1_ I * //
'---~DATE REVIEWED_ __..C....~_-.r,::;.,/---"-tf.;.,,;:'S::...----
- GUIDELINE CONTROL ROOM WORKSPACE WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6;1
- 6. 1.2.2 STAND-UP CONSOLE DIMENSIONS
- a. CONSOLE HEIGHT TO SEE OVER-When it is necessary for a standing operator to see over the top, console height {with or without annun-ciator panels) should not exceed 58 inches.
- b. CONTROL HEIGHT-The range of suitable control height on stand-up consoles is defined by the reach radius of the 5th and 95th percen-tiles {as defined in Exhibit 6.1-5). Measurements should be made using shoulder height and functional reach with the shoulder in line with the leading edge of the benchboard, as shown in Exhibit 6.1-6. The exhibit shows the results of -two console designs with differing bench-board slope and depth. Controls may be placed somewhat higher on consoles with shallower and/or more steeply angled benchboards,
- --~
which allow the shoulder reference point to be
; \_;
- closer to the back of the benchboard and to . ..*.J.*
the vertical panel. { 1) The highest control on a stand-up console should be within the highest reach of the 5th percentile female without stretching or using a stool, ladder, etc. (2) The lowest controls on a stand-up console should be within the lowest reach of the 95th percentile male without bending or stooping.
- c. BENCHBOARD SLOPE - The benchboard slope, in conjunction with its depth, should result in all controls being within the reach radius of the 5th percentile female, as illus-trated in Exhibit 6.1-6.
- d. CONTROL DJSTANCE FROM THE FRONT -
EDGE OF THE CONSOLE ( 1) Controls shou Id be set back a minimum of 3 inches from the front edge to protect against accidental activation. -* ,6, 1-16
-~ *J
.\ CONTROL ROOM WORKSPACE WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST 6.1 N/A Vn No Reference/Comment 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
- d. CONTROL DISTANCE FROM THE FRONT EDGE OF THE CONSOLE (Cont'd)
(2) No control should be more than 25 inches from the front edge of the console. This accommodates the maximum reach of the 5th percentile female adult as illustrated in Exhibit 6.1-6. INCHES 108 96 ........ ., SHOULDER HEIGHT*
" '\ \ FUNCTIONAL REACH
' '\
\
\ ,
FUNCTIONAi.. LIMITS ON 72 95TH REACH ' \ CONTROL SHO~DER' , HEIGHT 0 I __ f _____ PERCENTILE LIMITS ON MALE 61.B'.....___..._ -.:.;;-t-- - - tjslG_t!T_ 63 60 61 .8'! 3c:: O"'
-::t*- -~ - - CONTROL
~EIGHT 5TH 49.4'--'- - - -
PERCENTILE
\ I MAX.
48 9.4
- J _ _2c::
._ I / .M5A6X
- FEMALE 36 27 24 27 MIN. MIN.
12
- One inch added for shoe height.
Exhibit 6.1-6. Reach capabilities and control height on stand-up consoles *
- 6,1-17
- 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
CONTROL ROOM WORKSPACE COMPLIANCE CHECKLIST 6.1 WORK STATION DESIGN 6.1.2
- e. DISPLAY POSITIONING-The principal factors affecting the readability of displays, including annunciator tiles, are: ( 1) display height and orientation relative to the operator's line of sight when he/she is standing directly in front of the display; (2) display distance and orien-tation relative to the operator's straight-ahead line of sight when the operator must read the display from an off-side position; and (3) the size of display markings relative to the distance at which the display must be read. Marking/
character size is addressed in Guideline Section 6.5.1, and is not considered here. Except as specifically noted, measurements of angles should be made with the eye point in line with the leading edge of the benchboard. This is illustrated in Exhibit 6.1-7. (1) DISPLAY HEIGHT ANO .-.~ ORIENTATION (a) All dispiays, including annunciator
- )*'
tiles, should be mounted so that they are within the upper limit of the visual field (75° above the horizontal line of sight) of the 5th percentile female. (b) In addition, all displays and annunci-ators should be mounted so that the angle from the line of sight to the face plane is 45° or greater. The 5th percentile female determines the upper limit. The 95th percentile male determines the lower limit .
- 6.1-18
*-_.. /
- * - - * * * * * * - - - - - - - * * .. *****-'"'****-*---* -.~.~ **-**--- -***-- ...* *- ..... ,....; *.*.. , ... *-*-*** .., ....* -** **.. ****-*******- . .._ *.... * ... * ........... **......... - ... -.:.....* ,!',-* ........ -** _ ....... *****
.) CONTROL ROOM WORKSPACE WORK STATION DESIGN 6.1.2 UPPER LIMIT OF VISUAL FIELD
- 6. 1 UPPER LIMIT OF VISUAL FIELD
~ INCHES I - 1So 108 96 84 ,,
EYE ,, HEIGHT 1, HORIZONTAL 72 69.s.:i ____ _ _ .!:0!,0~ EYE HEIGHT HORIZONTAL L.QS_O~ 60 48 5TH 36 95TH PERCENTILE PERCENTILE FEMALE MALE Eye height from Exhibit 6.1-5: inch added for shoe height 24 12 Q Angle would be too smell for readability if display - ~ mounted on vertical surface Exhibit 6. 1-7. Display height and orientation relative to standing Qperator LOS (line. of sight}.
- 6.1-19
CONTROL ROOM WORKSPACE 6.1
- 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd)
WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment
- e. DISPLAY POSITIONING (Cont'd)
(2) HORIZONTAL DISPLACEMENT-The oblique angle from the line of sight to a display located to either side of the working position from which the display must be read should be at least 45°. This includes annunciator tiles, which should be readable from the acknowledge button. (See Exhibit 6.1-8.) Di1Plavs: Max.. Displacement 48 316 . 2f 112 0 12 24 36 I 7' I I I 7
/
/ /
/ ,
.. 'v /
" . Eye refentnce point for
, meten, gauges, etc.*
VEve reference point for ennunclat0r ti1i11*
- For meters and other displays which mey hllYtl to be read while a control anywhere on the benchboard is operated, measurement should be made with the eye reference point in line with the leading edge of the bench*
board. For 11nnunciet0r tiles, the eve reference point may be back from the benchboard edge. The distance back should be consistent with the ability of the 5th percentile female to reach the annunciator response pushbuttons. 12 inches is a suitable nominal distance back for most consoles, Not,: A wraparound panel would allow greater displacement. Exhibit 6; 1-8. Limit on horizontal displacement of displays from straight-ahead line of sight at the required reading position.
- 6.1-20 I"
*- * *~ _. _ _ .,.,,;,,.._. ___ . 1 * ~ ..... ~. *.. --- ....... * - ....... _ .... **
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1.2 COMPLIANCE CHECKLIST 6.1.2.2 STAND-UP CONSOLE DIMENSIONS (Cont'd) N/A Yes No Reference/Comment
- f. LATERAL SPREAD OF CONTROLS AND DISPLAYS-The operator should be able to perform task sequences at a given work station with minimum respositioning. The amount of I operator movement required depends on the -
arrangement of controls and displays, not simply on the lateral dimensions of the seg-ments of the control board. The maximum lateral spread of controls and displays at a single-operator work station should not exceed 72 inches. I I g, FOOT ROOM-Enough foot room is needed l I to allow the operator to get close to the board without leaning. A clearance of 4 inches verti-cally and 4 inches horizontally is recommended. I I II II i
/
./ 6.1-21
CONTROL ROOM WORKSPACE 6.1 WORK STATION DESIGN 6.1.2 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment
- 6. 1.2.5 VERTICAL PANELS Exhibits 6.1-13 and 6.1-14 show common problems resulting from poor placement of controls and displays on vertical panels. The following limits are recommended. *
- a. CONTROL HEIGHT (1) Controls should be placed in an area between 34 inches and 70 inches above the floor.
(2) Controls requiring precise or frequent operation and emergency controls should be placed in an area between 34 inches and 53 inches above the floor.
- b. DISPLAY HEIGHT (1) Displays should be placed in an area between 41 inches and 70 inches above the floor..
(2) Displays that must be read frequently or precisely should be placed in an area between 50 inches and 65 inches above the floor *
- 6.1-29
MAY 1~
- '92 10:33 SU!sRY SEN NUMBER PROCEDURE TITLE REVISION 1
0-FGA-1.00 LIMITING MCR F!RK PA~E 11 of 25 STEP ACTION/EXPECTED RESPONSE 1 - - - - - - t '.RESPONSE NOT OBTAINEI> ....-------....,,
- 21. _oN ENERGIZE.I) EMER.GENCY BUSES Q!!1X, OPEN SUPPLY .BREAUR. TO i.ESPECTIVE A:Ffi/ CROSS-CONNECT tO PREVENT SPURIOUS CROSS-CONNECT OPERATION
- MOV*FW'-160A 2Hl-232 e MOV*FW*l60B 2Jl-243
- MOV*FW-260A lHl-211
- MOV<FW-260B u1 .. 2141
- 22. _THR.OrrLE AN DISClfARGE MOVs TO Control SG levels~
MAiNTAIN SG v1!DE RANGE LEVEL BETilEEN 701 .AND 801 1E one Emergency Bus b de-enei:gizcd. 1 THEN locally isolate AUxiliary Feed Ya~er header ' containing corresponding MCJVs. *
- C)-FV-141 for H bus
- 0-FW-156 for B bus
* ()~.Fil-171 for H bus
* ()-FW-140 for J bus
* (hFQ'-15.5 for ;I bus
.
- 0-FW-170 for J bus 0
IF AN flow 1~ established. AND SG llide lla!ige levels can !!Q! be inaintdned above 70%; IHfili isolate blc;,wdcnm. coolers: : a) Close Slowdown Cooler A Isolacion. ()-BD-152. b) Close Blowdo~ Cooler B Isolation*, ()-JID-162. c) Close Blowdown Cooler C Isolation, ()-BDftl72
- MAY 19 '92 10:34 SUFRY SEN p 4.1'7 NUMBER P.ROCBDUR.E TITLE lUWI.SIOB l
0-FCA-l.00 LIMITING MCR. FIRE PAGJ:: 20 of:25 ACTI0Nj8XPECTED RESPONSE .__~~--"' RESPONSE NOt OBTAINED t--~~~~-..-~--
*************************************~~
CAUTION: Alte,:na.te water sotl.l:c~s fo~ the l.:E'W Pumps will be necessary if ECST level decreases to le.ss than 5 feet by local indication.
** * * * * * * * ** * ** * *** * .,,,-'ft * * * * * * * * * * * * * * * * * *'
- 35. _INITIA'IE RCS COOL.DOW:
a) Determine RCS cooldown rate IAW Attachment 3 b) Throttle Dump valves to establish RCS cooldown c) Maintain SG Wide Razige level betwean 701 and BOI d} Maintain RCS Cold Leg
'- temp~rature within limits .of Attachment :3 e) Adjust Charging and Seal Injection flow to 1114intain a
~table PRZR level J6. LO\lER RCS P.RESSURE TO 1950 PSIG
-!AV ATIACHMENT 3 I.
\,_./
MAY 19 '92 10:34 SUFRI' SEN P.5/7 NUMBER. PB.OCEDORE TITLE REVISION 1 0-FCA-1.00 LIMITING KCR FlRE
- ~
PAG:p: 21 of 25 STEP ACTION/EXPECTED RESPONSE
********~******************************
CAUTION: SI will automatically uPhloc~ if FRZR pressure increases above 2000 psig or RCS Iave increases above 543~F.
- 37. BLOCK SI:
a.) Verify RCS Hot Leg temperature a) R.ETtJim 'l'O Step 35.
- LESS THAN 543°F b) Verify R.CS pressure - b) RETOJlN TO Step 36.
LESS THAN 2000 PSIG c) Locally block SI LW A-cucbmenc 5
'- 38. CHECK RCS COLD LEG TEMPERATURE - Maintain cooldown To'lt:e
- 39.
~LESS THAN 450°F ES'l:~LISH ALTERNATE LETDOWN IAW
-ATTACHMENT 6 IAV Atcacbment 3 until Cold Leg eemperacure decreases to less ~ 450 *r.
- 40. _CHECK CSD BORATION:
a) Sample RCS or Let:down b) Verify I.CS Boron
- AT GOLD b) Do ~he following:
SHUTDOW CONCENTRATION
- 1) Verify initiated or ini~i-te
* ~rgency Boratlon.
- 2) tmEN Boron concencracian. .
adequate; ~ stop : Emergency Boracion. c) Stop Boration
M=IY 19 '92 10:34 SURRY SEN P.6/7 NUMISER. PROCEDURE TITLE REVISION .\_, . 0-AP-20.00 HA.IN CONTROL ROOK INACCESSIBILITY l PAGE; 7 of: 9 STEP AC'J:!ON/EXPECTED RESPONSE i------- RESPONSE NOT OBTAINED J------'-----. 12 . f.STABLISH REMOTE MONITORING IATi/ FCA-11,00, REMOTE MONITORING l 13
- CHECK LEVEL IN ALL SGs - BETWEEN Control A1!W £low using KFW .HOVs~
-70% AND 80%
NOTE: Steam Dump demand and AN make.up requiri::iuents ean be reduced by stopping RCP(s). One RCP should be left running. 14-. CHgCK RCS l'EMPEEATORE
- AT OR NEAR Locally operate steam dump~.
7°F
M=IY 19 '92 10:35 SURRY SEN P.7/7 NUMSER PROCEDURE TITLE REVISION l -~- 0-AP-20.00 STEP MAIN CONTROL ROOM !NACCESSIB.ILITY ACTION/EXPECTED RESPONSE* t----- RESPONSE NOT OBTAINED 1--------- PAGE 8 of :9
*****~*********************************
CAUTION: PRZR Heater Groups A atJd B have no automatic functions when operated f;rom the Auxi.liary Shutdown Panel. 'l"hese heaters i;;hQuld be secured 1.f PRZR level dec~eases to less than 15%.
- 15. _CHECK RCS LETDOW IN SERVICE USING Do the following:
- ERFCS IN TSC a) Locally elose ( )-CH.304 ta isolate charging.
b) Locally reduce RCP seal injeceion flow ~o 6 GPM using Seal Wacer to RCP valves:
..__.. * { )*Cll*294, A RCP
* ( )-CH~297, & RCP
* ( )-CH-300 1 C RCP c) Consult with TSC or plant staff on desired course of action.::
- Place alternat:e letdown in service !All D-FCA-1.00, LIMITING llGR FIRE, A'Ct.achment. 6. 1
- Initiat~ cooldown to control
. PB.ZR level
- d} GO TO St~p 17.
- 16. CHECK PRZR LEVEL
- BETWEBN 20 AND Control charging flow using 30% C )-CR-FCV*( )122.
- 17. CHECK PRZR. PRESSURE
- BETWE!N 2220 Operace PRZR. Heaters Groups
- AND 2250 PSIG A or E.
~.:. ...... :.-*~.:....... :..............__ a.-~.---; ....::_* .. ,.*,:*-.... . . **- .... _ .............. ___ **--~--- _._.s . . -****-***-- ..:*** .,.~ ...-.* ~.
----------------*-----~-~~::;.- ,;;**.. .-
i; '*.
'*l.
- . 9 1/4. 1 1/2 9 1/4. J
-.----r----f=-:.~~~-=-~~~~:-44_:5_/4_* ------+-----,
~~---~~~---i--~ ,*
0 0 0 l--1/t' PANEL CUTOUT FRONT ~EW __.......--c TYP JOI~ (AS 1 7/(r I Ls 112* INDICATOR MOUNTING BRACKEI
- 11.27 CANO.:
CORRECTIVE ACTION EVALUATION CA DESCRIPfION: 27E Provide better functional arrangement of SI/CLS controls. EQUIPMENT MARK NO. HEDNO. SI/CLS Selector Switches 23001225 11.27.1 HED REVIEW - ORIGINAL FINDINGS HED No. 23001225 - Related control/display grouping (NUREG-0700, Section 6.8.1.1.a,b) The CRDR surveys found that controls were not arranged and located in functional groups relating to systems. Several control switches and pushbuttons on the control room benchboard section 1-1 are not assigned to work stations so as to minimize operator movement or are not assigned to panels in functional groups related to system structure. The consequence - liniiting safeguards pushbuttons [manual containment spray initiation (PB-CLS-TR2A & 2B) and system actuation reset (CS-CLS-RA & RB)], the containment spray chemical additional tank control switches [recirculation pump (43-CS3) and isolation valves (CS-102A and 102B)], and the refueling water storage tank recirculating pumps control switches (43-RRA & RRB) are located with controls for the safety injection system. The safety injection system controls [manual safety injection initiation (PB-MSI-1&2), system actuation reset (PB-RSI-A&B), low pressurizer pressure SI block (43-SIB-Al & 43-SIB-Bl), and high steam line flow with low T-avg SI block (43-SIB-A2 & 43-SIB-B2] are located with controls for the consequence-limiting safeguards system. See attached sketches . DC~SS-04/05 were prepared to rearrange the subject controls. The DCP was not implemented. 11.27.2. HED REASSESSMENT a PROCEDURES/PROGRAMS REVIEW EOPs IXJYES ONO ON/A RG-1.97 DYES ONO IXJN/A The SI/CLS operate and reset pushbuttons are used in various EOPs. Examples include l-E-0, l-E-1, 1-ES-1.1, 1.2, 1-FR-Z.1. EPIPs DYES ONO IXJN/A LERs/IOERs DYES IKJNO ON/A No LERs/lOERs were found which relate to SI/CLS switch location/misoperation. APP.R DYES ONO IKJN/A HPES/STA DEV/SOER DYES IKJ NO O NIA No station deviations/SOERs were found relating to SI/CLS controls. ERF/SPDS DYES OONO ON/A TECH SPEC ITEM IKJYES ONO ON/A SI/CLS control switches are not inputs to the ERF. The operability of the SI/CLS systems are defined under Technical Specification Section 3. 7. VARS01N.B7S-1
11.27 .3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The SI/CLS operate and reset pushbuttons are required to be operated in various EOPs. The pushbuttons are not functionally grouped with the associated SI/CLS system controls.
Safety Significance Potential for Error The SI/CLS pushbuttons are safety related Class lE. The existing location and grouping of the SI/CLS pushbuttons affects the ability of an operator to perform required actions, and increases the potential for operator error. However, no LERs/SOERs documented errors are associated with this equipment. In addition, the SI/CLS pushbuttons are located within the proper color demarcated area of the benchboard for the SI/CLS system. The benchboards were not demarcated at the time of the original CRDR review. This reduces the potential for error.
. Consequences of Error - Due to the CLS pushbutton covers, inadvertent initiation* of CLS Hi/Hi-Hi is not postulated. The consequences of operator error due to SI controls arrangement would be a delay in operator response time. The consequences would be minor based on the availability of automatic protective features. In addition, the CLS pushbuttons have covers which would alert the operator and prevent inadvertent actuation.
SI/CLS are protective features which are initiated automatically when plant parameters are exceeded during postulated design basis accidents. The EOPs require the operators to verify that SI/CLS has been initiated automatically (annunciation). Regardless of SI/CLS automatic initiation, the operator is required
- to manually initiate SI/CLS. If SI/CLS has not been automatically initiated, the EOPs require the operator to check if SI/CLS is required based on plant conditions. If plant conditions indicate that SI/CLS is required, then SI/CLS is manually initiated. The operators are trained to initiate both Train A and Train B SI, CLS Hi and Hi-Hi pushbuttons.
The SI/CLS pushbuttons are manually operated only after the operator has verified annunciation or that plant conditions exist which are indicative of a SI/CLS. This verification process and self-checking will
.-~i reduce the potential for operator error. In addition, the CLS pushbutton covers alert the operator as to what system is being initiated and would eliminate the inadvertent operation of CLS. Also during simulator training, the SI/CLS pushbuttons are required to be operated many times. No documented errors concerning the operation of the SI/CLS pushbuttons were identified.
11.
27.4 CONCLUSION
S/RECOMMENDATIONS Based on the above discussion, sufficient information is presented to justify not implementing CA27E. It is recommended that during simulator training, the arrangement and location of the SI/CLS pushbuttons continue to be emphasized .
- V ARS01N.B7S-1
- . 11.
27.4 CONCLUSION
S/RECOMMENDATIONS (Cont'd) The reassessment process for this corrective action included a qualitative analysis to determine if the benefit of the proposed corrective action was commensurate with the total projected cost of the modification. Based on this evaluation, it has been determined that there is no appreciable benefit to the improvement of plant safety, operations or human engineering principles, which justifies the projected high cost of the modification .
- VARS01N.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D IEOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D Er LERs/IOERs/SJ;)Rs D TRAINING MODULES D TECH. SPECS. D DRAWING/SKETCH/MISC. CORRESPONDENCE D
- CHECKLIST
- ,'~
,, l liV02/.85 t>q;=: 2! A:iS~SB~~, ~AS* R:v!~w TITLE RESPONSIBILITY STATUS DATE II -5 87/11/85 It.MAN ERIWR: TE~Rlt... ERRORS - Dc:i.A1 It; &e:ARCH AND Rt:S?Ot6t Tl~. lff PROa.Efll DESCRIPTIOII: O.TRL.S/DISPS 5tO..LD BE ASS16NED TO iirt.S IN FLWCTIDt; 6ROLPS RELATED TO SYSTEfl STIU:TURE, (W/111 &~WT SRO.PSI,
~700 PAi1AeRAP>i ,..Uf'llif:11:
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/
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17:
- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT OR.JGJNATOR: -....-.-i,.,,-----;,~--- VP-,
VALtDATED B Y : - - + ~ ~ - - - - - a) t-£0 TITLE:* _.a.,;;::::,,,:;,=...;;~---=i:~~a;....i..."'-F-~__.;~~~---- b) ITEMS INVOL VEO: .
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177
- APPENDIX 89 HED REPORT (CONTJNL.£0)
,0vn~ t-ED NO.: Y(/- 2 PL~NT/~IT ~
- 89-2
HED PRIORJTY RECORD HEo*~D *~-s
- 1. DOCUMENTED ERROR? YES
- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE NO
. (PAM OR 1E)?
*. ERROR POTENTIAL? 2 I
~
'~..-L "Z_J HIGH
- 5. CONSEQUENCE OF ERROR: 2 I 6 _I_
HIGH
.. NED 110 CATEGOII'!' I CATIOOJIY Ill 110 ltO 0
'. ,; __-;.*, . ..:.*:. .. ~ ..... *.... * *. .. * ... , _;_ **--*~ *...-!~. __;.._~::::.:...::. ~* ...:. .....~*.* ..* *. *:* *. *..*...*...r.:. * - **. : . *-*. -;- .... *. .
- GUIDELINE PANEL LAYOUT GENERAL PANEL LAYOUT 6.8.1 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.8 6.8.1.1 ASSIGNING PANEL CONTENTS Controls and displays should be placed within the control room at locations which promote efficient procedures, safe operation, and maximum operator awareness of the current system condition. There are three general methods for achieving this con-dition. They are: (a) grouping by task sequence,
~b) grouping by system function, and (c) grouping by importance and frequency of use.
- a. GROUPING BY TASK SEQUENCE-Controls and displays should be assigned to work stations so as to minimize operator movement.
To the extent practical, this assignment should consider both normal and emergency pro* cedures. It should be practical to perform all frequently occurring routine tasks, and time-sensitive emergency tasks, with a minimum of human movement from panel to panel.
- b.
- GROUPING BY SYSTEM FUNCTION-Within the constraints of grouping by task sequence, controls and displays should be assigned to panels in functional groups related to system structure. This grouping should promote easy understanding of the relationship between controls and system, and should assist graphic or pictorial display of system relationships.
- c. GROUPING BY IMPORTANCE AND FRE*
QUENCY OF USE-Within the constraints of grouping by task sequence and by system function, controls and displays should be assigned to panels depending on their impor-tance and frequency of use. Controls or displays which are neither important to plant safety nor frequently used should be installed in secondary panel locations. 11*
- 6.8-1
NUMBER PROCEDURE TITLE REVISION 7 1-E-0 REACTOR TRIP OR SAFETY INJECTION PAGE 3 of 21 STEP ACTION/EXPECTED RESPONSE t--~~--t RESPONSE NOT OBTAINED t----~~~~~---. [ 3] VERIFY POWER TO AC EMERGENCY BUSES: a) AC emergency buses - AT LEAST a) Try to restore power to at ONE ENERGIZED least one AC' emergency bus.** IF power can NOT be restored to at least one AC emergency bus, THEN GO TO l-ECA-0.0, LOSS OF ALL AC POWER, STEP 1. b) AC emergency buses - BOTH b) Do the following for any EDG ENERGIZED which has failed to start:
- 1) Put EDG in EXERCISE.
- 2) Push START button.
- 3) Put EDG in AUTO.
[ 4] CHECK IF SI INITIATED: a) Check SI indications: a) Check if SI is required as indicated by any of the
- Safety Injection System following:
Initiated annunciator (A-F-4)
- LIT
- Low PRZR pressure,
- I.HSI pumps* RUNNING
- High CTMT pressure,
- High steamline differential pressure,
- High steam flow with low Tave or low line pressure.
IF SI is required, THEN manually initiate. IF SI is NOT required, THEN GO TO l-ES-0.l, REACTOR TRIP RESPONSE, STEP 1.
- b) Manually initiate SI
NUMBER PROCEDURE TITLE REVISION 6 1-E-l LOSS OF REACTOR OR SECONDARY COOI.ANT PAGE 13 of 25 STEP ACTION/EXPECTED RESPONSE ...,_~~--t RESPONSE NOT OBTAINED i---~~~~~~---. CAUTION: RCS pressure should be monitored. If RCS pressure decreases to less
' than 250 psig [475 psig], one UISI pump must be manually restarted to supply water to the RCS. *14. CHECK IF UISI PUMPS SHOULD BE STOPPED:
a) Check RCS pressure:
- 1) Pressure - GREATER THAN 1) GO TO Step 16.
250 PSIG [475 PSIG]
- 2) Pressure - STABLE OR 2) GO TO Step 15.
INCREASING b) Reset SI if necessary c) Stop UISI pumps and put in AUTO
- 15. CHECK SG AND RCS PRESSURES:
a) Check pressure in All SGs - a) RETURN TO Step 1. STABLE OR INCREASING b) Verify PRZR spray controls - b) Close PRZR spray valves. DEMAND AT ZERO c) Check RCS pressure - INCREASING c) GO TO Step 16. d) RETURN TO Step l
NUMBER PROCEDURE TITLE REVISION
~
]4'
. -- ~*.
l-ES-1.1 SI TERMINATION PAGE 2 of 24 STEP ACTION/EXPECTED RESPONSE i--~~-- RESPONSE NOT OBTAINED t----------. NOTE: Continuous Actions page should be monitored.
- 1. _RESET SI
- 2. _CHECK IF CLS CAN BE RESET:
a) CTMT pressure - LESS THAN a) GO TO Step 3. WHEN CTMT 14 PSIA pressure less than 14 psia, THEN do Steps 2b and 2c. b) Reset CLS if necessary c) Verify TV-IA-100 - OPEN c) Open valve TV-IA-100.
NUMBER PROCEDURE TITLE REVISION 6 l-ES-1. 2 POST LOCA COOLDOYN AND DEPRESSURIZATION PAGE 2 of 23 STEP ACTION/EXPECTED RESPO~SE .,..._~~---4 RESPONSE NOT OBTAINED t--~~~~~~~ CAUTION: If RYST level decreases to less than 22%, the SI system should be I' aligned for cold leg recirculation using l-ES-1.3, TRANSFER TO COLD LEG RECIRCUIATION. NOTE: Continuous Actions page should be monitored.
- 1. RESET SI
- 2. _CHECK IF CLS CAN BE RESET:
- a) CTMT pressure - LESS THAN 14 PSIA b) Reset CLS if necessary a) GO TO Step 3. lrlHEN CTMT pressure less than 14 psia, THEN do Steps 2b and 2c.
c) Verify TV-IA-100 - OPEN c) Manually open TV-IA-100.
r-(\J 0.. I 1.0 P*ZR "l,(55 Mt S.'1"4 f\.OW r ~"iloc.,< t,.K~T UIA <<Gt'fmA mg llol* ~Z&&
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- 0
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- 0 ti 0
- 11.29 CANO.:
CORRECTIVE ACTION EVALUATION CA DESCRIPfION: 29E Perform study to correct Control Room glare/lighting problems and implement improvements. EQUIPMENT MARK NO. BED NO. NIA See section II.29.1 below 11.29.1 HED REVIEW - ORIGINAL FINDINGS HED No. 20000009 - Control Room glare. (NUREG-0700, Section 6.1.5.3.f) HED No. 20000008 - Abnormal Control Room illumination levels. (NUREG-0700, Section 6.1.5.3.a) HED No. 20000001 - Control Room ambient lighting too variable. (NUREG-0700, Section 6.1.5.7.a.2)
- HED No. 20000003 - Operations not verified under emergency lighting.
(NUREG-0700, Section 6.1.5.3.a) HED No. 20000014 - Ambient lighting varies significantly in Control Room. Noticeable glare. (NUREG-0700, Sections 6.1.5.3.d, 6.1.5.3.b and 6.1.5.3.a)
- 11.29.2 BED.REASSESSMENT - PROCEDURES/PROGRAMS REVIEW EOPs DYES IXINO ON/A
*Control Room lighting is required during EOP operations.
RG-1.97 DYES ONO IXIN/A Control Room lighting is not applicable for compliance to R.G. 1.97. EPIPs DYES IXINO ON/A LERs/IOERs DYES IXI NO D N/A Control Room lighting is not addressed No LERs/lOERs were found concerning in the EPIPs. control room lighting. APP.R IXIYES ONO ON/A HPES/STA DEV/SOER DYES ~NO ONtA Control Room lighting is also used as No Station Deviations/SOERs were Appendix "R" emergency lighting. identified as a result of control room
. lighting problems.
ERF/SPDS DYES ONO IXIN/A TECH SPEC ITEM O YES IXI NO O NIA
- Control Room lighting is not associated Control Room lighting is not with ERF/SPDS. Technical Specification related .
VARSOlP .B7S-l
11.29.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- Corrective Action CA29E was to perform an evaluation of the control room lighting and glare to identify modifications necessazy to improve the lighting levels in the control room and reduce glare to comply with acceptable standards. A Type 2 lighting study was prepared in January 1989, which recommended: 1. Switching off alternate rows of lighting fixtures or, 2. Upgrading existing lighting system with fluorescent dimming. The selective de-energaation of lighting circuits would reduce the high normal illuminance level in the control room, however, this will not remedy the reflected glare problem. A special test was also conducted to evaluate the control room under emergency lighting conditions. Interviews with control room operators during the emergency lighting test indicated that the general reaction to the 50% lighting level was positive because of the partial reduction in horizontal benchboard luminance.
Safety Significance - Lighting is required in the control room for operators to perform necessary functions to control the plant during normal and emergency operating modes, therefore lighting is considered to be safety significant. Potential for Error - The potential for delay is high if the lighting (bright or dim) affects the operator's ability to locate, read and interpret displays. However, the potential for error is low with the current lighting design because glare and lighting brilliance can be counteracted by normal observation techniques. No reported instances of lighting causing an operator error have been reported. Consequence of Error - The consequence of error of the lighting due to excessive glare is dependent on the indication to be read. This may possibly result in an operator taking control action using data that was inaccurate.
- 11.
29.4 CONCLUSION
S/RECOMMENDATIONS A subsequent walkdown of the control room and discussion with operators determined that although the overall control room illuminance is high, the operators prefer the current control room lighting levels which does not result in reading errors, delays and errors in response, eye strain or fatigue. Due to the low potential for error and no reported cases of lighting having caused an. operator error, the control room lighting will not be modified and normal lighting maintenance will continue. The reassessment process for this corrective action included a qualitative analysis to determine if the benefit of the . proposed corrective action was commensurate with the total projected cost of the modification. Based on this evaluation, it has been determined that there is no appreciable benefit to the improvement of plant safety, operations or human engineering principles, which justifies the projected high cost of the modification.
- V ARS01P.B7S-l
APPLICABLE HEDs WITH BACK-UP D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
- Q-LIST RG-1.97 D
D I I LERs/IOERs/SDRs D I TRAINING MODULES D l TECH. SPECS. D ~ I ,. D DRAWING/SKETCH/MISC. CORRESPONDENCE I CHECKLIST
- SURRY lriiT e CODE B ASSESS1£t-'T LAST REVIEil TITLE RE~S!BILITV STATUS *DATE l!S/88/85 IIJIIIAti ERROR:
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* /11EA (>/l'LIG E/flfD/IS
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- APPENDIXB9 HED REPORT (CONTINUED)
SuRRY ~I i:t PLANT UNIT HEDNO.:
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~
f) SUGGESTED BACKFJT:
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g) REVIEW AND DISPOSITION:
6 a I HED PRIORITY RECORD
- HED II~~- \~
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE CONDITION OR TECH
- I
~
. SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE NO
- 4. ERROR POTENTIAL? 1 2 LOW
- 5. CONSEQUENCE OF ERROR: 1 2 LOW HED
~~~* YES NO I
CATEGOIIIV I I CATEGOIIIY ii CATEQOIIIY 111 NO NO NO
'-,*11.**._
HED NO. S-1::..1 A::- 7 VIRGINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
- RECOMMENDED RESOLUTION ST AT ION /UN IT _ _ _ _ _ _ _ _ _S._u_r_r-1--y_*_{_'I_,._,_1_*-_-_l_t_:;__
MARK NO. 1TEM DESCRIPTION C Dr* -( , (} / I::) Cu** CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) [ i C /, 1 1
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- c) PROBLEM DESCRIPTION AND 0700 PARA.o NUMBER: (~ 153'9 SEE ATTA.CHE!> P-'tG:.E Fo~ AELATEl> /vul'UEG 0700 EKH~/317' AND r'lf()8(E"1 l:>Esc,r,Pr~oN.
d) DAT A COLLECTION DESCRIPTION AND CODE NUMBER: nLV~*1/4'A71'tJP "rl°-/... 5 e) SPECIFJC HUMAN ERROR(s):
* ~E-"IDNVG, EA'~tJR S
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- B9-l
APPCNDIXB9 HED REPORT (CONTJ~UED)
.t&-9 SuRR 't' / IJ. 2.. HEDND.: ~
PLANT/UNIT c) PROBLEM OE_J;CRIPTJON AND 0700 PARA. NUMBER: . (~ / 53cv T* m.-----. 1Do1randln Wan.Ara
*TypelJfTa
........ Inwndad I ~ Mui-
"""" IIUtft
....... primary apenrti"I . .
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. . IES L;;trirw lvndbool:. 11181 ~licnion Volllffla.l
- E11hibit 6.1*22. Illumination leweb.
*_Th'£ Bl:IVCH,50,91'{/)S (SECTIONS f-1' "4Nb J-2) #~VE Z~LUH,N,lifAJCt
.l.eVEL s TH"9 T EXcEEl> TN hAX,,,~U,.., /ffECt:U'¥MEN()E!) PA/VE£ A~J::, SCA.l.c /,Vbi'Cl16ITI?/( HEAb/N6 /~~V,Y/.,V~'l/t::G -'.tvt!F~5 Bf' A.Sovr So%.
- A"fEtfll s A'E,tlf/ft TN/: ~/,'fc P;f'"'T't!=CT,t:,A,, .PAlf.l~~' AV T' <:"Ht,., ;0,9A/c£S (c..v.,1T 11,~ J jl!i~D /A/ F/i'OA.17' Or F/fo~T VEl'fT'~C,"ll. Cenv,lfol. &l"llfl>.S .
(se.c.T,oAJS 1-1 t-2 2-I l'fND ::z-:i..) H;fl/£ /~~e,,,,,.,;,1t.MIIVCE ~Evc~S - T'#;tlfT ~lfE ~IJWclt ' J T,_,,~~' 7h'E* h/.;V/.,..,~~ ~EC.~,,._,~...VOc;;-- - -"- JL~e.,,,..,/.,,e,,,,,.,~C'c ~EvG~ s rt?/( llj'E,9b/N(; ,/',;tfJ;f/lt>/.vlf/rTG#
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- AREIIS AT CiJ~P~rE~ COIV.So~ES ~,v,r /~2.) CD1V7AtU. ,V.i::,c:, *
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l May 19B3 I APPENDIXB9 HED REPORT (CONTINUED)
~-0.
SuBR"I 6' ~ PLANT UNIT 2 HEDND.: ~ f) SUGGESTED BACKFJT:
* /;f/("_J"r.f;"9Se .TL~V~/A/;t'l?;,t:?A.,,1 ;II/, A'lfE;t:; S ,v£.q~ F/,PE F'A't,~c'?7c;N r'A/VEL) A v r C'H£,Y r'ANl=~S {'-'" /,I' 2.), /iAJ?> rlf(M./T VElfTIC,eJL CONTl(ol. 801"1 IPDS (SE<:Til,!UVS /-/,. / - , , Z- l,1 z-.z),
'l>ECr! EASE :r~v,iV;1.1Vi/'fTi'e,,v OF 8E,,vc,y B,u'l,fl)S
- g) REVIEW AND DISPOSITION:
c:_~E, 9a. ..~~<ff\ °' \1~\..\,~ ::.\-111~ -\:-, ~~~~
- \::, ~b c.\,. °'"'~~ <;.s,~ \.e. c=\"" .- c:...\,._b "'-~ -s. e1-r J
c ~ c.,\,, o. ':-' "t s --\-~ \' ~\.:t ~' )c\- 11. <~ s .
HED PRIORITY RECORD
- HED # S)S - C\
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE YES YES
- CONDITION OR TECH.
SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE
- 4. ERROR POTENTIAL?
NO 1 2~ 4 5 8 6 LOW HIGH
- 5. CONSEQUENCE OF ERROR:
LOW 1 2 *QS
- 5 _J_
HIGH HED YES NO*
- CATEGORY I CATEGORY II CATEGORY Ill NO NO NO
- A5~5£*.:..,-r 1.,15~ rV1:w
- TITLE i!ESP[)tj5IBlLITY STATUS DATE ENG III-8 07/l~/B~
itl!IIAN ERROR: DWIY/cRRuil ltii ~ t i , ~Utillll:U EG1.?:ii)fl:Ni AA..FUILi!ilN
++* PRQBLE~ IlESCRIPTlil/1:
&Rl6rfi Lli,r1T1Hb CAIJSES a.~ Du1<1,-; Buui Nt~~~l'l:l'<li DIRT AND ~..BRlS FAI.I.S ON C:OlffRfr. IIOORDS, SOIE AREAS DARi<
07~ PP.~AG~ NL"'lrEk: b, l, :i. 7. H., t:iUoci:Si ~ &QC,(1, I"! : i):;j;uk* 1.j&,7i~ bi:JUT, iiiv!l:it 1.)t!"lii-o *1u ~1:*1 ~l(:~7~
++* Dli,IJ!i~lTlull:
;,:ii;uk~ 1..i:ri': i,,;: ):::.w, *,u 111 t-..t~/:it:;:-;..~. *J~ (..,;i.~6:.=i. urr:~ v,,.,\::i::b iu LlcHT f-11Tuls. 1=: 1iS-':,/l0, ~~0~00a19. >
DAT~ tuw.f.Ci1uN l.li:SCki~TiiJ,c ~D tuu: '<<.~Eh: i.,..~,l .w,J~~~H'~t Su!fV:~ ITEl':o IP111u..\1Eli: M~ MJ!lli,eR LOC~1ii31'4 C:U"rM:.t.T ~ SYS:E!li CR W~ i..1Nti .. hU* jt, l!'CV F.i:.E t DIFFUS ~S H NOT ll'k
- 1. DOCUMENTED ERROR?
- 2. DOCUMENTED UNSAFE
\ "t.,
- CONDITION OR TECH.
____ __.I
* ~
YES YES SPEC. VIOLATION?.
- 3. HIGH SAFETY IMPORTANCE "NO
. (PAM OR 1E)?
- 4. ERROR POTENTIAL?
LOW 1 2@ 5 *6 HIGH
- 5. CONSEQUENCE OF ERROR:
LOW 1 2(c) 4 5 J_ HIGH YES ND CATEGORY I CATEGDIIIY II CATEGDIIIY Ill ND ND ND ND 'e
REASSESSMENT OF PROBABLE ERROR AND DEVIATION -I HED t {Jr - I 2-
- 1. EXTENT OF DEVIATION NONE SOME COMPLETE FROM GUIDELINES 0 ,1 2 3 4 5 6
- 2. ERROR POTENTIAL LOW
--, 2 3 4 5 HIGH 6
- 3. CONSEQUENCE OF ERROR LOW HIGH
--r 2 3 4 5 6
,,_..,.. ACCEPTABLE RESOLUTION NO MODIFY RECOMMENDATION OR JUSTIFY AND DOCUMENT SIGNOFF: DLC-RTL DATE: _ _ _ _ _ __
- S~RRV Tli1.E UNiT i CCiI>t C ffE~!BlLITV A::,!:i;51:i!l'.:\T STATUS JIS: itE,V!E.;
DATE
- ------------------------ ---,.--- IlI-8 e11111ss tlfl!AN c.Riiuit:
ERRLI~ llR i;;..wiv 11'1 U>":ii~Tuk li:.i:iPO,.Sa;
+++ PRui!I..EII! DESCRIPTlilh:
~Lrii IiffFt.iitt.iiAilDi. UfCl.lrte lh t.~R Lltinil"6 Wll11i1~. i:f< Cl!'Eiam~ LII~Flw..T lN ~R U&iTlN6 i7~ PARHtiiiMPP, ~ i i :
- b. l.:,.;;.~
SUiiGESiED BACl{Fii: V:.ii:iFY/IM.i..~:*f! ~ii L~ili',iu11 ~~u,'l:;~ L~:1 t::11,t,it:i:~t :..l~T11<<, UlN/lUi:i'e
... DlS.iD~!Tlu~:
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- f<a!Ala{::
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117 TP-laS n.!.l.MINATION l Mey 198) ~- APPENDIX B9 HUMAN ENGINEERING DISCREPANCY (HED) REPORT b) ITEMS lNVDL VED:
~~
. ...- ~
~} )
TP-1.5 l7V l Mey 19S:5 n.LLMJNATION
~u B APPENDIX B9 HED REPORT (CONTINUED)
R(/LJN1r;s PLANT/UNIT I 'f a HED NO.: PI - 3 / g) REVIEW AND DISPOSITION: _Q_JJ rJµ_ j;c VtqVLt; 11 { B9-2
- hED NO ilTL.£ l'cESPOhSlBlLITV k:i!:i~l(:NT STATUS LAST !t:lllEw DATE III-B ,1,11185
~ERiWit:
Itl.AY/t.Kmik lh LIi' ~~.
+H Pf<ii&..E!li DESCR IPTI UII :
AR£~ OF Ci< OVER\..~ l!RiSrli, Ai81S f(Jf ll..LLll!lNATt.D cflAJ6ol.~AltS TO bE A SI6NIFI~T PR~ liiITH &.ARE. 07~ PAkASRA~ ~ k : b.1.~.3.u b.1.~.j.: b.1.s.~.~
!:iU66ESTED isAC~ Ii :
P=~*C,R~ :..l~:l~ STuilY 10 I,:T~ii!l:!'i: ~.:i:c.1~~c COw~~TlD!'c ACHON~. CORRECT AS REWIRED *
.,.. DlSUOSITlu/1:
fc:;;:ti< 11.i lib-:i (c~a,it;,:,1 f.11111 lJS;,.1~ (i:..~::i1, 11:TAi..:.D Ll&.,TlfiS &iuDY. ~ DATA Cu..i.ECTlON DE&CklPTiOrt ~ Culi ~k: T,;,..l, 5 li.Lll"'l~ATliY- b:.1~:Y Ri:l!AK'<fi: Pl-03ii. m.".s ih'.'&-~:
~it~ hu";!.'lik LOCHi.lflll L:!Jir,;.~,r r.Qo\: SY~1t~
CR~ Llaril ff hOT lh Ir.~ fl!.E
- 177 TP-1.5 n..LlMJNATION l May l9B)
-* APPENDIX B9 HUMAN ENGINEERING DJSCREPANCV (HED) REPORT b) ITEMS INVOLVED: G~~~ ((JVYlbt~ ~ d) OAT A COLLECTION OESCRJPTJON AND CODE NUMBER: -
& ~ ~ -TP I, s-B~(iJ;(~J,~C,)
*e) SPECJF'JC HJMAN ERROR(s):
:~\ t,;J#J-:- ,.>JJ~f ~ /~ ~~'-" ~ ef_r.,-Jx cJ
_ / ' ~ d..}->--L, ~ ~ .)A*-..OJrJ..)4 t,J\ ~ ~ . ) -. ..:., T~- /~.),._ c~iliJJf 1~~/c_,:,*1.,-'u..,.:t.4.~,
TP-1.5 177 l May 1983 D..Ll.MJNATION -* APPENDIX B9 HED REPORT (CONTINUED) s va.~vtu na t P ANT/UNIT
)' ~ HED NO.: f+ - 30 g) REVIEW AND DISPOSITION:
~f ~yo.JJ-. ~~ ~ti"+-i "1, ot) rJ.( .e pc..-1)
- ,&\Lfwiflj Jtl-'lllt{ ltiliti~, sh~ -
CclYYl~ 1-rJ.., w/ ()_r- \'2-B9-2
s - / J I LJS'-I D
,.. HED NO. S-12 /lJs-'t
.VIRGINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
~ODO - DO of{
- RECOMMENDED RESOLUTION . 2Doi.:, -;_00o~
STATION/UNIT ----------,.,._ ________ s~rry [/,,,; / _-. I !-2 MARK NO.
---------------------C iJ ,. () / f l ;~/,, -!/,.,,:
1T EM DESCRIPTION D *?) ,... CHANCE DESCRIPTION (RECOMMENDED RESOLUTION(S) AND OPTIONAL RESOLUTIONS) j>t' ,,. /h- :.-f t.f , f )
..., ff.,, ( ,:;,,_f,.-,( r I
/) -~ -)rrl!?-:f (),~/1.l t,.,1,/l fJ~ r>nu:l ?,....* /:,~
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i~li !;.it d: //~ s ,,JI; if s ,* f ;:, " ;. _,. ~" J' P rJ fhe s IA..l,. ~ J ~ I ~4 t*e (2J, i~.lic afor l,u*# f . fer ~l"'e.r , ,--~
; / '
r:c;,,\ -lirol ;, ,;.. wi 1/ bt lf?ct,-,,:.,.1-lt:.f,*~- ..* 41;/( b~ 0 I>. COMMENTS: - - - - - - - - - - - - - - - - - - - - - - - - - - - B_.__r_,__f_r/_1*_11_ 1 ORICINATOR _ _ _ _DATE REVIEWED 5' ?~
CONTROL ROOM WORKSPACE 6.1 ENVIRONMENT 6.1.5
- GUIDELINE 6.1.5.3 ILLUMINATION Adequate levels of illumination are necessary to COMPLIANCE CHECKLIST N/A Yes No Reference/Comment ensure that visual effectiveness is sufficient for task performance. While the following illumination levels should generally be observed, specific task situations may d_ictate other illumination levels.
- a. LEVELS- The recommended illumination levels, in footcandles, are listed in Ex-
.I hibit 6. 1-22. I Task llluminance, footcandles Work Area or Type of Task Mini, Recom- Maxi-mum mended mum Panels, primary operating area 20 30 50 Auxiliary panels 20 30 50 Scale indicator reading 20 30 50 Seated operator stations 50 75 100 Reading:
- Handwritten (pencil! 50 75 100
- Printed or typed 20 30 50 :,t*~,
Writing and data recording 50 75 100 *: ~~:: ./ Maintenance and wiring areas 20 ~o 50 .)
.r_._ ..
As above Emergency operating lighting 10 for area/ta,k (Source: Illuminating Engineering Society of North America,
/ES Lighting Handbook, 1981 Application Volume.I Exhibit 6.1-22. Illumination levels.
6.1-46
- ** *** r *. * *****, . . . . . . . . * *******-*- *.
.--.... CONTROL ROOM WORKSPACE 6.1
- 6.1.5.3 ILLUMINATION (Cont'd) t,, UNIFORMITY - The level of illumination should not vary greatly over a given work No ENVIRONMENT 6.1.5 COMPLIANCE CHECKLIST N/A Yes Reference/Comment station. I
- c. SUPPLEMENTAL LIGHT-Supplemental light-ing should be provided for personnel performing specialized visual tasks in areas where fixed illumination is not adequate. i
- d. TASK AREA LUMINANCE RATIOS-To I I
determine task lighting requirements, it is ! necessary to consider the levels of lighting I which surround a task. Great disparities be-tween task and background lighting can lead to I! I I adaptation problems. To ensure effective visual I performance, the task area luminance ratios in Exhibit 6.1-23 should not be exceeded. .l I
- e. SHADOWING-To reduce operator fatigue and I I Ii eyestrain, shadows should be avoided. I *I I
( 1) Ambient illumination should be provided I I . ! I i via indirect or diffuse lighting. I i (2) Labels, instructions, and other written I I i information should not be in shadowed positions. I I Luminance Arnt Ratio Task area versus adjacent darker 3:1 surroundings Task area versus adjacent lighter 1:3 surroundings Task area versus more remote darker 10:1 surfaces Task area.versus more remote lighter 1 :10 surfaces Luminaries versus surfaces adjacent 20:1 to them Anywhere within normal field of view 40:1 Exhibit 6. 1-23. Maximum task area luminance ratios. 6.1-47
CONTROL ROOM WORKSPACE 6.1 .~*:.~")...
.. . ~,
*....*.::_:_~ti ENVIRO_NMENT 6.1.5 COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.1.5.3 ILLUMINATION (Cont'd)
- f. GLARE-Glare increases the probability that an individual will misread a display or will fail to notice displayed information. Glare can also produce discomfort. Direct sources of glare include light emitted from luminaires, indicators, and displays. Indirect sources of glare include reflected light from all surfaces, e.g., painted, metal, glass. Glare should not interfere with the readability of displays, labels, or indicators.
- g. REFLECTANCE -The amount of reflected light is affected by illuminated surface colors. I .,
Reflectance should conform to the recom-mendations shown in Exhibit 6.1-24. (See also Exhibit 6.1-25.) .
- h. COLOR-:-Surface colors should be recognizable .
under both normal and emergency lighting conditions.
<....:: /
Reflec:tanca Color Raflectanee Surfaca Pref9rrad Permialble White., , .. , , . . . * * * . * . . . * * * .
- 85 Light:
aceiling 80% 60.95% Cream , , * . * . . * . * * * . . . . * . *
- 75 Grey , * , . , . * * * . * . * . * . * * * *
- 75.
Upper Wall 50% 40,60% Yellow,.,.,.,............. 75 Lower Wall 15-20% Buff. . . , * * * * . . . . * * * . * . * . , ,. 70 Green * . * * . * . . . . . * . . . * : . . * . 65 Instruments/Oisplays 80.100% Blue. . . . . * . . , * * . . . * . . * * * * . 55 Cabinet/Consoles 20-40% Medium: Yellow,................... 65 Floor 30% 15-30% Buff, , .** , .. , ** , . . * * . * . * *. . 63 55 Furniture . 35% 25-45% Gray * , , * * . . . . . . * * * . . . * * *
- Green. , , . . . , . * . . . . , * * . . . ,
- 52 Blue. * . . . . . . . . . . . . . . * . . . .
- 35 aRecommended reflectances are for finish only. Over-all aver- Dark:
age reflectance of acoustic materials may be somewhat lower. Grav * . * . . . . . . . . . . . . . . . . . . 30 The upper walls (one to two feet below the ceiling) may be Red . . . . . . * . . . . . . . . . . . . * . . 13 painted with the same paint as is used on the ceiling, Brown , , ; .. , *. . . . * . . . * . , .. , 10 Blue. . . . . * . . , . , , . . . . . , . , .. 8 Green, * , , *.. , , , . , , , . , . . . , . 7 Exhibit 6.1-24. Recommended workplace reflectance levels. Wood Finish: Maple. , .. , *.**. , , . , .. , , . , , 42 Satin'WOod , . , . . . . , . . * . . , , . . , 34 English Oak . , .. , . . . . , , . . . , , , 17 Walnut. , .. , . , * . . . . , .. , .*. , 16 Mahogany , . . . . . . , . . . . . , , ..* 12 Exhibit 6.1-25. Surface color reflectance values.
- ... *~ *~* . ... .. .. . . .. . . . .-*
6.1-48
~-
CONTROL ROOM WOR!{SPACE 6.1 ENVIRONMENT 6.1.5 GUIDELINE COMPLIANCE CHECKLIST 6.1.5.7 AMBIENCE AND COMFORT An effort should be made to create a pleasant and
- comfortable work setting *in view of the long hours and confining aspects of the control room operator's job.
- a.
- DECOR - Features to be considered include:
( 1) Colo*r coordination. (2) Use of color and lighting to create a cheerful atmosphere (without introducing glare and brightness to a degree that causes eye fatigue or an overly intense atmosphere). (3) Visual relief from arrays of instrumen* tation. (4) Comfortable seating. (5) Carpeting to lessen the fatigue of standing and walking.
- b. RESTROOM AND EATING FACILITIES
( 1) A restroom and kitchen or eating area (2) should be provided within (preferably) or near the control room isolation boundary. Since formal breaks are not scheduled in most control rooms, it is important that personnel .have access to these facilities without delay. It is preferable that they be used only by control room personnel. (3) Provision should be made for communi-
- cation if facilities are out of voice contact, so that an operator taking a break can be contacted as necessary by personnel in the control room. (See Guideline 6.2.1.7.)
- c. REST AREA/LOUNGE-Consideration should
. be given to providing a rest area (possibly in conjunction with the eating area) conducive to relaxation and revitalization, especially where shifts are long.
/
- 6.1-53
11.36 CORRECTIVE ACTION EVALUATION CA NO.: 36E CA DESCRIP'fION: Redesign Auxiliary Ventilation Panel. Consolidate indication and controls for common ventilation equipment on single board and provide mimic. EQUIPMENT MARK NO. HEDNO. 20003016 23003019 22F23026 VNT-X, VNT Panels 20A01215 22A01310 20A03209 22A03215 U.36.1 HED REVJEW - ORIGINAL FINDINGS HED No. 20003016- Controls that must be operated simultaneously located too far apart. (NUREG-0700, Section 6.8.3.1.c) HED No. 20A0121S - Inadequate control and display grouping. (NUREG-0700, Section 6.8.2.1.a.2) HED No. 20A03209 - Containment recirculation fans logical arrangement and layout. (NUREG-0700, Section 6.8.2.2.a) HED No. 23003019 - Functionally. grouped controls. (NUREG-0700, Section 6.8.2.1.a.2) HED No. 22A01310 - Illogical arrangement of controls and displays. (NUREG-0700, Section 6.8.2.2.a) HED No. 22A0321S - Mirror imaged components. (NUREG-0700, Section 6.8.3.b) HED No. 22F23026 - Ventilation panel controls for Unit 2 inconveniently located. (NUREG-0700, Section 6.8.1.a,b,c)
- 11.36.2 HED REASSESSMENT - PROCEDURES/PROGRAMS REVJEW EOPs l&:IYES ONO DN/A Verification of system and damper alignment, examples are lE-0, l-E-0, Attachment 2 RG-1.97 IX! YES ONO D N/A R.G. 1.97 Control Room ventilation damper position indicators (Cat. 2, D-34 variable). Misc. E (Cat. 2) variables - flow indication for vent. stack.
EPIPs DYES D NO !XI N/A LERs/lOERs DYES !XI NO ON/A Auxiliary ventilation panels controls/displays are not No LERs/lOERs pertaining to vent panel operation. identified in the EPIPs. APP.R IX! YES ONO O NIA HPES/STA DEV/SOER DYES IXINO DN/A Controls exist on vent. panels which are used in No Sta. Dev./SOERs applicable to Aux. Vent. Appendix R. panel operation. _ ERF/SPDS IX! YES D NO D N/A TECH SPEC ITEM IX! YES D NO D NIA
- Aux. vent, vent control indication in ERF /SPDS V ARS01Q.B7S-l T.S. Section 3.22.
Il.36.3 NUREG-0700 REVIEW - DISCUSSION OF SAFETY SIGNIFICANCE
- The auxiliary ventilation system at Surry Power Station has undergone significant upgrading (addition of several fans, dampers, associated controls, recorders, etc). Limited space on the original Units 1 and 2 Ventilation Panels (VNT) located in the Control Room necessitated an additional Auxiliary Ventilation Panel (VNTX) to provide control and system flow status of the modified common auxiliary ventilation system in the Control Room. The resulting arrangement of the existing ventilation panels does not comply with NUREG-0700 "Guidelines for Control Room Design Reviews.
- Control switches, indicating lights, and monitoring instruments which are necessary for operation of the common auxiliary ventilation system are split between two Control Room locations, the Unit 1 VNT Panel and the VNTX Panel. Control switches are inconveniently located, and indicating lights are not always above their associated control switches. Also, the existing pressure indicating controllers/flow indicators are arranged mirror image on the VNTX Panel. The original CRDR also identified controls that were not located conveniently or logically on the VNT Panels.
The CRDR Corrective Action identified as "NP" would consolidate indications and controls for common ventilation equipment on a single board and provide mimics. Safety Significance The auxiliary ventilation system is considered safety related. It contains controls, etc. powered from a variety of safety and nonsafety related sources. Technical Specification Section 3.22 requires that whenever either unit is in normal operation, with one train of the exhaust filter system inoperable, the inoperable train must return to an operable status within 7 days. The filter exhaust fans are also required to be operable during fuel handling operations to mitigate the consequences of a fuel handling accident. Various controls and indicators are considered necessary for a train of filter exhaust to be operable. Potential for Error The potential for error is low; the training manuals for the Ventilation and Auxiliary Ventilation systems adequately address operator actions to be taken during emergencies. In addition, there were no station deviations or operational problems noted during simulator training concerning the layout of controls on the VNT Panel. Consequence of Error The consequences of error due to location, arrangement, and grouping of controls on the VNTX and VNT Panels would be limited to a delay in operator response. The controls associated with safety-related ventilation system are automatic during - -) accident conditions. Therefore, there would be no risk of injury to the public or ;- I plant personnel or damage to equipment. -I I I Il.
36.4 CONCLUSION
S/RECOMMENDATIONS There are two alternative solutions considered to correct the problems identified by CA36E: Solution 1 - Install new Auxiliary Ventilation Panel (VNTX-F) Solution 2 - Use the existing ventilation panels and continue to implement operator training. The following is a discussion of each solution, its advantages and disadvantages. Solution 1 - Install New Auxiliary Ventilation Panel (VNTX-F). Solution 1 - The Auxiliary Ventilation Panel (VNTX) consists of two free-standing sections: an indicating and control section (Front Panel, VNTX-F), and an instrument nest and relay section (Rear Panel, VNTX-R) .
- VARS01Q.B7S-l
11.36.4 (CONT'D)
- This CRDR proposed modification will replace only the existing VNTX-F Panel with a new panel. The new panel will include all of the common Auxiliary Ventilation System control switches, indicating lights, and monitoring instruments of the existing VNTX-F Panel, with the addition of the control switches, indicating lights, and a monitoring instrument to be relocated from the Unit 1 VNT Panel (no devices are required to be relocated from the Unit 2 VNT Panel).
The four existing Unit 1 and 2 Post-Accident Monitoring (PAM) recorders currently located on the VNTX-F Panel shall be permanently relocated to their respective Unit Vertical Main Control Boards as a part of future main control board changes. The modification can be done with either unit in any mode of operation. It will involve, however, the temporary relocation of a limited number of selected control switches; indicating lights, and monitoring
*instruments (devices requiring relocation will vary depending on the selected operating modes) because of the limitations of Technical Specification Section 3.22 "Auxiliary Ventilation Exhaust Filter Trains," and the requirements of Regulatory Guide (R.G.) 1.52 "Design, Testing, and Maintenance Criteria for Engineered- . Safety-Feature Atmosphere Cleanup System Air Filtration and Adso11J.tion Units of Light-Water-Cooled Nuclear Power Plants."
The new cable routing for this modification will use new overhead conduit for the permanent wiring between the Unit 1 VNT and VNTX panels. The temporary wiring required for the relocation of selected Unit 1 VNT and VNTX panel mounted devices during modification will be field routed and supported as required, maintaining the proper separation . Advantages
- Proposed modification when implemented will resolve all HEDs associated with the subject Corrective Action, and improve visual presentation of ventilation panels.
Disadvantages .- ::. The engineering and implementation of the new VNTX-F Panel will be an expensive modification. Areas which significantly contribute to high cost include:
- Procurement and qualification of a new safety related Class 1E panel
- Installation of the panel and testing of all ventilation circuits.
- Conduit installation in the control room including installation of seismic supports. The area above the VNTX is congested and will require special support designs.
- Temporary relocation of identified control components during construction to maintain operation within technical specification. The temporary installation will. be required to satisfy seismic and separation requirements.
- Extensive simulator changes and operator re-training .
- VARS01Q.B7S-l
II.36.4 (CONT'D)
- Solution 2 - Use the existing ventilation panels and continue operator training .
Because of the high cost of new panel design and installation described above, justification of the existing design is adequate. Training and procedures minimizes the chances of an operator error. The following points are used in the justification of not implementing this modification:
- The seven HEDs associated with the ventilation controls and layout of the ventilation and auxiliary ventilation control panels were designated Category II-6 and II-7 in the HED priority' record. There were no documented errors, unsafe conditions or technical specification violations noted. The error potential and consequences of error was low. These facts result in a low priority level.
- The ventilation systems once initially aligned, are automatic and do not* require frequent manual operations.
- The auxiliary building ventilation system automatically aligns to the filters upon receipt of an accident signal. Operator action following an accident is confirmatory in nature to verify proper alignment of ventilation streams.
The reassessment process for this corrective action included a qualitative analysis to determine if the benefit of the proposed corrective action was commensurate with the total projected cost of the modification. Based on this evaluation, it has been determined that there is no appreciable benefit to the improvement of plant safety, operations or human engineering principles, which justifies the projected high cost of the modification. Final recommendation, based on the information provided in Solution 2 is to continue with training with appropriate procedures for the ventilation system which minimizes the chances of error. There are no documented errors, unsafe conditions or Tech. Spec. violations noted. Also, the HED's associated were rated low priority category (NP) in the original CRDR. The high costs of the original corrective action modification (replace ventilation panels) are not commensurate with the operational benefit that would be gained .
- VARS01Q.B7S-l
APPLICABLE HEDs WITH BACK-UP
- D DOCUMENTATION NUREG-0700 SECTIONS D EOPs/EPIPs D ERF/SPDS D
, .* Q-LIST D RG-1.97 D LERs/IOERs/SDRs D TRAINING MODULES D ITECH. SPECS. D InRAWING/SKETCH/MISC. CORRESPONDENCE D
*
- CHECKLIST
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- APPENDIX B9 HUMAN ENGlNEERJNG DISCREPANCY (HED\ REPORT
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S V ,t_P., Y /uN 17:i I ~ d HED NO.: pJ - II7 PLANT/UNIT B9-2
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1 May 1983 APPENDIX B9 HUMAN ENGJNECRING OlSCRE:PAt-CV (HEO) REPORT
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- HUMAN ENG1NtERJNG DJSCREPANCV (HEO) REPORT 5
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PLANT7UNIT HED NO.: DS-ll f) SUGGESTED BACKFlT:
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l May l9B)
- HJM.O.N ENc;JNEERING DJSCREPANCV (HEO) REPORT PL..AN1/UNIT L 2. A-0 .. 3'2.15 ORJGJNATOR*: ~.s
------------ . HtO NO.: _D_s=---~ z__
VALIDATED BY: a) HtD TITLE:
----------- - DATE:
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d) OAT A COLLECTION DESCRIPTION AND CODE NJMBCR: - e) SPECIFIC HJMAN CRROR(s'):
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. l May 1983
- APPENDIX 89 HED REPORT (CONTINUED).
PLANT HED ND.: t)S- ~J\ f) SUGGESTED BACKFIT: ~ 8';2. 3.b (Z) SUJ/,CN ~OC;/7/t,PS or /-Ps-;:--.y:i ANb /-.vs-r-¥ / 0~ SG(.)/'TCN _LOC"9-r'/ONS or e:,-P.s--F-~/ AN/)
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,;2-VS-/" Y4-g) REVIEW AND DISPOSITION:
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-~ .. .,o *.
- B9-2
- ~""s:"-5S*i!\~ LAST ii£V!:loi RESPO~SiB1LI1Y STATi.iS DP.TE II -7 0:/07/85
~ ERROR:
llELAY DR ERRu~ l~ ~KAiuf! iE!:iP~S Ht PttCiik.EtP, DESCRIPTlilh: UNIT f: VEJ.T ~ CONTi!IU L.W!Tc.D 1~ i,.IT 1 8700 PAfjAGRAIJ!-I ~ k : b.b.~.l,M ~.8.,.1.h b.b.~,l.~
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- 177 TP-1.2 ANTHROPO~TRICS l May 1983
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APPENDIX 89 :,..., . . HUMAN ENGINEERING DISCREPANCY (HED) REPORT Su,si<.y/u111,s.. I PLANT/UNIT 1 ,l b) ITEMS INVOLVED:
~>"- -~~ ~,
- - c) PROBLEM DESCRIPTION AND 0700 PARA. NUMBER:
~~ I ~
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' 177 TP-1.2 ANTHROPOtl,ETRICS l May 1983 APPENDIX 89
... HED REPORT (CONTINUED)
S u ls 1s ifLANT u M) T £: I ~ UNIT
;t_ HED NO.: p;z - I?
g) REVIEW AND DISPOSITION:
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- 1. DOCUMENTED ERROR? YES
- 2. DOCUMENTED UNSAFE YES CONDITION OR TECH.
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- 3. HIGH SAFETY IMPORTANC NO YES
. (PAM OR 1E)?
- 4. ERROR POTENTIAL?
LOW 1 2 3 4 (i) 6 HIGH
- 5. CONSEQUENCE OF ERROR:
LOW 1 2 ;@ 4 5 .J_ HIGH HED YES NO CATEGORY i
- CATEQOAY II CATEQDRY Ill I
ND NO NO NO -
/
H ED NO * ,'-:I - 1 : : - *_. VIRGINIA POWER CONTROL ROOM DESIGN REVIEW HUMAN ENGINEERING DISCREPANCY (HED)
- RECOMMENDED RESOLUTION
~
STATION/UNIT
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MARK NO. 1TEM DESCRIPTION _.1..,;/1-..:...]..../ _;c __*.;;;.o_~_l""\_v_"--___V_e._,-,,:{..........: l.;.c......1_:~_....;:;-'. _.___(..;;.o. . . . .1_r. . .....;)=L--- - - CHANGE DESCRIPTION (RECOMMENDED RESOLUTION(S} AND OPTIONAL RESOLUTIONS)
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- 1 ORIG INATOR_ __,,1,..2,;.__t_,-_'_l-1__i_I/_.....__ _DATE REVIEWED_ ___,:.</_-_.2~}...;-?~5_ _ __
PANEL LAYOUT 6.8 > .; SPECIFIC PANEL LAYOUT DESIGN 6.8.3 *-*" ' GUIDELINE COMPLIANCE CHECKLIST N/A Yes No Reference/Comment 6.8.3.1 SEPARATION OF CONTROLS Recommende9 minimum control separation dis-tances are shown in Exhibits 6.8-2 and 6.8-3. In most cases, control room operations will. require greater separation; The functional requirements that should be considered are:
- a. ACCESS - Control access should not be im-peded by any position of an adjacent control.
- b. INADVERTENT ACTUATION-Control actu-ation should not result in inadvertent actuation
- of an adjacent control.
- c. SIMULTANEOUS ACTUATION - Simultane- -
ous actuation of adjacent controls (where required) should be possible.
*:-**~....,___
.. . \
-.~
. -~: . **
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6.8-10
PANEL LAYOUT 6.8 LAYOUT ARRANGEMENT FACTORS 6.8.2 GUIDELINE COMPLIANCE CHECKLIST N/A Yes No 6.8.2.1 SEQUENCE, FREQUENCY OF USE, AND FUNCTIONAL CONSIDERATIONS The layout of panels is a compromise among a
.number of considerations. In some instances, various human factors principles will conflict, not only with
- each other but also with other design requirements.
Because it is* difficult to rate the conflicting con-siderations for importance, final decisions must be based on careful evaluation and sound judgment This subsection deals with the analysis of the factors of task sequence, frequency of use, and function.
- a. - SEQUENCE-Controls and displays which are used together during a normal task sequence should be grouped together.
( 1) Displays which are observed in a specified sequence, as during hot-leg temperature check for all reactor coolant loops, should be grouped together. It is desirable that they be positioned so that they are normally used in a left-to-right, top-to-bottom, or other natural sequence. (2) Controls which are operated in sequence, as in energizing a system or aligning a series of valves for a particular function, should be grouped together. It is desirable that they be positioned so that they are normally used in a left-to-right,
. top-to-bottom, or other natural sequence.
(3) When there is a set of related controls and displays, the layout of displays should be symmetrical with the controls they represent.
- 6.8-5
PANEL LAYOUT 6.8 LAYOUT ARRANGEMENT FACTORS 6.8.2 . -~*._..,;, COMPLIANCE CHECKLIST 6.8.2.1 SEQUENCE, FREQUENCY OF USE, AND FUNCTIONAL CONSIDERATIONS (Cont'd)
- b. FREQUENCY OF USE-Frequently used controls and displays should be arranged to reduce search time and minimize the potential for error during use.
( 1) They should be near the center of the preferred visual and manual areas. (2) They should be positioned so as to be easily identified.
- c. FUNCTIONAL CONSIDERATIONS- Func-tionally related controls and displays should be grouped together when they are:
( 1) Used together to perform tasks related to a specific function (e.g., operation of the residual heat removal system). (2) Identical in purpose {e.g., reactor coolant pumps). . *;:_)/
*-,,.,~
6.8-6
.... GUIDELINE PANEL LAYOUT 6.8 LAYOUT ARRANGEMENT FACTORS 6.8.2 COMPLIANCE CHECKLIST 6.8.2.2 LOGICAL ARRANGEMENT AND LAYOUT The arrangement of controls and displays should be logical, but should not compromise sequence of operations or functional integrity. Logical arrange-ments are generally based on operator expectations. In general, *operator expectations will be met when components have a left-to-right or top-to-bottom arrangement and are identified in alphabetic or numeric sequence. For example, four related dis-plays in a row should be designated A, B, C, D, or 1, 2, 3, 4; correspondingly, any controls related to these displays should also be designated A, s; C, D, and 1, 2, 3, 4. Well-designed system mimics will help to direct and satisfy operator expectations.
- a. ORDER AND LABELING - Components should be arranged left-to-right and/or top*to-
..... b. bottom, and _be identified in alphabetic or numeric sequence. OTHER EXPECTATIONS-Where operator expectations can be identified, other . components should be arranged to match these expectations.
- 6.8-7
~. GUIDELINE PANEL LAYOUT LAYOUT ARRANGEMENT FACTORS 6.8.2 COMPLIANCE CHECKLIST 6.8
~];.*"
.**J N/A Ves No Refer11nce/Comment 6.8.2.3 LAYOUT CONSISTENCY The location and* arrangement of recurring func*
tional groups and of individ~al components of those groups should be similar from panel to panel or within a panel.
- a. REPEATED FUNCTIONS-The layout of identical control or display sets should be consistent at all locations.
- b. MIRROR-IMAGING - Layouts of repeated functions should not be mirror-imaged.
c{r~~
- *-:~-~:. :;*
- 6.8-8
7 1-E-O REACTOR TRIP OR SAFETY INJECTION PAGE 12 of 21
- STEP ACTION/EXPECTED RESPONSE ...._~~~...j
- 18. __VERIFY VENTILATION ALIGNMENT:
RESPONSE NOT OBTAINED 1--~~~~~~--, a) Check all REFUEL SFIT MODE a) Do the following: switches - NORMAL
- 1) Notify Refueling SRO to stop refueling operations.
- 2) GO TO Step 19. WHEN fuel in safe condition, THEN do the following:
- a. Put all REFUEL SFIT MODE switches in NORMAL.
- b. Verify ventilation alignment IAW Attachment 2.
b) Verify ventilation alignment IAW Attachment 2
- 19. __VERIFY AC POWER ALIGNMENT:
a) Check all Station Service buses a) IF offsite power available,
- ENERGIZED THEN manually transfer to RSS.
b) Check reactor banks - TRIPPED b) Manually trip reactor banks.
- SR-12
- SR-22 c) Check Unit l Auto Start Block annunciator (VSP-J-2) - LIT d) Check Unit 1 RSST LTC time delay bypass light - LIT e) Check Unit 2 - SUPPLIED BY RSS e) GO TO Step 20.
E u f) Check Unit 2 RCPs - RUNNING f) GO TO Step 20. ,,H l-'.* g) Check Load Shed - INITIATED g) Initiate 0-AP-,10 .10, LOSS OF fl AUTO LOAD SHED. I\ j
NUMBER ATTACHMENT TITLE REVISION 1-E-0 AUXILIARY VENTIIATION SYSTEM 7 ATTACHMENT PAGE 2 1 of 2
'j TABLE 1 UNIT #l VENTILA.TION PANEL MARK NUMBER EQUIPMENT STATUS l-VS-F-4A & B OFF 1-VS-HV-lA & B OFF 1-VS - F- SA & B OFF.
l-VS-F-9A & B GREEN . 1-VS-F-59 GREEN - 1-VS-F-6 OFF 1-VS-F-39 GREEN . l-VS-F-7A & B GREEN l-VS-HV-5 GREEN r 1-VS-F-56A & B GREEN t GREEN !* ! l-VS-F-40A & B f! l-VS-HV-4 GREEN li 1) 11
~
2-VS-F-40A ORB RED 2-VS-HV-4 GREEN
uov*L ---* SURRY NUREG 0696 COMPUTER _INFUT/OUTPITT LIST SHEET l OF THE DIGITAL INPUT CONDENSED REPORT INSTRUMENT MARK NUMBER SORT Pl.CE n
- 1 82 81 4 85 60 6
l 62 6 3 33 1 1 1 0 7 8
~-
\1li1
- POINT ID INPUT NUMBER INSTRUMENT MARK NUMBER PO~NT DESCRIPTION DATE TESTED I N
K L s C u H B L N I N N E K L A s T A R T SIGNAL B I TYPE I N V E R s M A I N I T s T OPEN STATE DESCR CLOSED STATE DESCR T s T
- XlSH002D 1Sl2-071 l-SH-P-48 SER HATER-PUMP 48 (NL) 06-28-90 03 2 07 0 l20VAC K E 0 NT RUNNG RUNNING -*
~ :ilVGOOlD lSl0-023 l-VG-TV-109A PDTT VNT ISLN V (ORJ <> 11-20-85 02 2 02 2 120VAC l NFL CLD FULL CLD SlVGOOZD XlVMOOlD lSll-044 1Sl2-0ll l-VG-TV-1098 1-VMS-YE-lOOA PDTT VNT ISLN V (PLJ <> PRESSURIZER SV 1551A (NL) 11-20-85 02 06-28-90 03 4 2 04 01 3 0 120VAC 24 VDC l 0 N FL CLD FULL CLD FULL CLD NFL CLD -~ XlVM002D XlVM003D
~:vsoolD S1VS002D 1Sl2-012 1Sl2-013 1Sl5-231 1Sl5-233 l-VMS-YE-1008 1-VMS-YE-lOOC l-VS-AOD-105A l-VS-AOD-1058 PRESSURIZER SV 15518 INL>
PRESSURIZER SV 1551C INLJ CNTMT AIR CPRSR CUB EXH A (NL) CNTMT AIR CPRSR CUB EXH B (NL) 06-28-90 03 06-28-90 03 04-08-86 03 04-08-86 03 2 2 4 4 01 01 23 23 l 2 0 2 24 VDC 24 VDC 24 VDC 24 VDC 0 0 0 0 FULL CLD FULL .CLD NFL CLD NFL CLD NFL CLD NFL CLD FULL CLD FULL CLD -* SlVS008D SIVS009D SIVSOIOD SlVS005D 1S28-054 1S28-052 1S28-042 1Sl5-221 l-VS-AOD-106 1-VS-MOD-lOOA l-VS-MOD-1008 1-VS-MOV-lOlA SFGD l UNFLTR EXH ADD IORJ SFGD 1 FLTR EXH MOD A (ORJ SFGD l FLTR EXH MOD B (OR) CHGRG PMP CUB EXH DMPR A INLJ 00-00 00-00 00-00 00-00 03 03 03 03 7 7 4 7 05 05 04 22 3 l l 0 125VDC 125VDC 125VDC 24 VDC 0 0 0 0 FULL OPN FULL CLD FULL CLD CLOSED N FL OPN NFL CLD NFL CLO OPEN SlVS006D 1Sl5-222 l-VS-MOV-1018 CHGRG PMP CUB EXH DMPR B INLJ 00-00 03 4 22 l 24 voe 0 CLOSED OPEN
- SIVS007D 1Sl5-223 1-vs~MOV-lOlC CHGRG PMP CUB EXH DMPR C IORJ 00-00 03 4 22 2 24 voe 0 CLOSED OPEN ~-
-x1sI003D XlRS003D 1S07-021 1S07-022 l-14H3 l-14H4 LHSI PUMP lA SHITCH IORJ INSIDE RS PUMP lA SHITCH (OR) 10-29-85 02 10-29-85 02 l
l 02 02 0 l 24 VDC 24 VDC 0 0 NOT PTL NOT PTL P TO L P TO L . XlCS003D XlRS008D
-x1SI004D 1S07-023 1S07-024 1S08-021 l-14H5 l-14H7 l-14J3 CNTMT SPY PUMP lA.SHITCH IORJ OUTSIDE RS PUMP 2A SHITCH (OR)
LHSI PUMP 18 SHITCH (Pl) 10-29-85 02 10-29-85 02 10-29-85 02 1 3 1 02 02 02 2 3 0 24 VDC 24 VDC 24 VDC 0 0 0 NOT PTL NOT PTL NOT PTL P TO L P TO L P TO L
? -*
TS 3.22G1 03-02-92 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS Aoo ncabi !ity Applies to the ability of the safety-related system to remove particulate matter and ga*seous iodine following a LOCA or a refueling accident. Obiective To specify requirements to ensure the proper function of the system.
$Decification A Whenever either unit's Reactor Coolant System temperature and pressure is
- greater than 350°F and 450 psig, respectively, two auxiliary ventilation exhaust filter trains shall be operable with:
- 1. Two filter exhaust fans;
- 2. Two HEPA filter and charcoal adsorber assemblies.
B. With one train of the exhaust filter system inoperable for any reason, return the inoperable train to an operable status within 7 days or be in at least Hot Shutdown within the next 6 hours and in Cold Shutdown within the following 48 hours. v Amendment Nos. 167 and 166
TS 3.22-2 1-17-84 The purpose of the filter trains located in the auxiliary building is to provide standby capability for removal of particulate and iodine contam-inants from the exhaust air of the charging pump cubicles of the auxil-iary building, fuel.building, decontamination building,.safeguards build-ing adjacent to the containments, and the reactor containment (during shutdown) which discharge through the ventilation vent and could require filtering prior to release. During normal plant operation, the exhaust fro_m any one .of these areas can be diverted, if required, through the auxiliary building filter trains remotely from the c*ontrol room. The safeguards building exhaust and the charging pump cubicle exhaust are automatically diverted through th~ filter trains in ~he event of a LOCA (diverted on safety injection system signal). The fuel building:exhaust and purge exhaust are aligned to continously pass through the filters during spent fuel handling.
\. - ;.
High efficiency particulate absolute (HEPA) filters are installed before the charcoal adscrbers to prevent clogging of the iodine adsorbers. charcoal ads,orbers are installed to reduce the potential release of radioiodine to the environment. The Amendment No. 92 and Amendment No, 91}}