ML20024C145
| ML20024C145 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/07/1983 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-0896, RTR-NUREG-737, RTR-NUREG-896, TASK-1.D.1, TASK-TM GL-82-33, SBN-530, NUDOCS 8307120312 | |
| Download: ML20024C145 (140) | |
Text
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Pub 5C Service of New HampeNro (617) - 572 5100 July 7, 1983 S BN-530 T.F. B7.1.2 United States Nuclear Regulatory Commission Wa shing ton, D. C. 20535 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter, dated April 14, 1983, " Response to Generic Letter 82-33; Supplement I to NUREG-0737," J. DeVincentis to G. W. Knighton
Subject:
Seabrook Station Control Room Design Review
Dear Sir:
In Reference (b), it was indicated that a report on the results of a Detailed Control Room Design Review as required by NUREG-0737 (Item I.D.1) and its Supplemer.t 1 would be subditted by August 31, 1983.
In fulfillment of this commitment, we have enclosed ten (10) copies of our report entitled, "Seabrook Station Control Room Design Review."
The enclosed report also addresses the Safety Evaluation Report (NUREG-0896), Outstanding Item #19 (reference Section 18).
Please notify me if additional information is required prior to your on-site review which has been scheduled for July 26-28, 1983.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY d Bukz John DeVincentis Project Manager ALL/pf Enc losure cc: Atomic Safety and Licensing Board Service List f I 8307120312 830707
{DRADOCK 05000443 PDR 1000 Elm St.. P.O. Box 330. Monchester. NH O3105. Telephone (603) 669-4000 TWX 7102207595
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William S. Jordan, III, E:quira Ms. Oliva L. Toch
- Harmon & Weiss Designated Representative of 1725 I Street, N.W. Suite 506 the Town of Brentwood Washington, DC 20006 R.F.D. 1, Dalton Road Brentwood, NH 03833 Roy P. Lessy, Jr., Esquire Office of the Executive Legal Director Edward F. Meany U.S. Nuclear Regulatory Commission Designated Representative of Washington, DC 20555 the Town of Rye 155 Washington Road Robert A. Backus, Esquire Rye, NH 03870
. 116 Lowell Street P.O. Box 516 Calvin A. Canney Mancehster, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Department of the Attorney General Augusta, ME 04333 Dana Bisbee, Esquire Assistant Attorney General Mr. John B. Tanzer Office of the Attorney General Designated Representative of 208 State House Annex the Town of Hampton Concord, NH 03842 5 Morningside Drive Hampton, NH 03842 Anne Verge, Chairperson Board of Selectmen Roberta C. Pevear Town Hall Designated Representative of South Hampton, NH 03842 the Town of Hampton Falls Drinkwater Road Patrick J. McKeon Hampton Falls, NH 03844 Selectmen's Office 10 Central Road Mrs. Sandra Gavutis Rye, NH 03870 Designated Representative of the Town of Kensington David R. Lewis, Esquire RFD 1 Atomic Safety and Licensing Board East Kingston, NH 03827 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Jo Ann Shotwell, Esquire Assistant Attorney General Mr. Angie Machiros Environmental Protection Bureau Chairman of the Board of Selectmen Department of the Attorney General Town of Newbury One Ashburton Place, 19th Floor Newbury, MA 01950 Boston, MA 02108 Maynard B. Pearson Senator Gordon J. Humphrey 40 Monroe Street U.S. Senate Amesbury, MA 01913 Washington, DC 20510 (Attn: Tom Burack)
Senator Gordon J. Humphrey 1 Pillsbury Street Diana P. Randall Concord, NH 03301 70 Collins Street (Attn: Herb Boynton)
SEabrook, NH 03874-Richard E. Sullivan, Mayor Donald E. Chick City Hall Town Manager Newburyport, MA 01950 Town of Exeter-10 Front Street Exeter, NH 03833 m
w SEABROOK STATION CONTROL ROOM DESIGN REVIEW m
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TABLE OF CONTENTS Page I.
I N TROD U CT I O N.....................................................
1 II.
RACKGR0UND.......................................................
2 III.
DISCUSSION.......................................................
3 IV.
OVE RALL B OARD AS SE S S ME NT.........................................
10 V.
GENERIC HEDS.....................................................
12 VI.
SPECIFIC HEDS....................................................
25 VII.
APPENDICES.......................................................
63 A.
Survey Team Membership and Qualifications B.
Survey Team Training C.
Operator Interview Form D.
Control Room Survey Checklist E.
List of Procedures F.
Procedure Talk-Through Example
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SEABROOK CONTROL ROOM DESIGN REVIEW I.
INTRODUCTION In resportse to the NRC task action requirements established in NUREG-0737 and its Supplement 1, Public Service Company of New Hampshire (PSNH) has conducted a Control Room human factors design review. This review has identified potential Human Engineering Discrepancies (HED) in the design of the Seabrook Station Control Room. These potential HEDs which were identified have been reviewed to see if they affect the safe operation of the plant. Those that did were, in turn, evaluated to see if there was a need to make modifications in procedures, in training, or to the Control Board.
NUREG-0700, Guidelines for Control Room Design Reviews, Draf t NUREC-0801, Evaluation Criteria for Detailed Control Room Design Review, and the GE BWR Owners Group Criteria were used as a base for the development of our own criteria for the review. After our criteria were developed, they were used for the review process.
The review process was divided into several parts - operator interviews; a Control Room survey which include hardware, control boards and panels, and alarm system; and procedure walk-through and talk-through sessions.
The Control Room survey operator interview and the procedure talk-through and walk-through portions of the review have been completed. The potential human engineering discrepancies have been listed, and appropriate fixes developed for them where it has been judged necessary. Many of these changes are underway at this time because of schedule commitments.
Some items will not be evaluated at at this time. These are items which require the Ccatrol Room to be complete and the plant operational.
Included are such items as noise studies, communications evaluation, HVAC evaluation and Control Room operational procedures for shif t change. These items will be reviewed during the plant's initial i
operating cycle, and any necessary changes will be implemented.
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II.
BACKGROUND A.
Industry Human Factors Activity l
Since TMI, increased emphasis has been placed on human factors engineering within the industry. New industry groups have been formed and workshops have been conducted. Many projects aimed at increasing the understanding of operator performance and decision making have been initiated by EP,RI and by INFO. The Westinghouse owners' Group has developed Task Analyses and Emergency Operating Procedures for their plants. The BWR Owners' Group has taken the initiative in performing Control Room design reviews on BWR plants. Yankee Atomic Electric Company (YAEC) and PSNH have taken an active role in all of these activities - most notably the BWR Owners' Group Control Room design review, the INPO activities and the Westinghouse effort.
The reason for this increased emphasis is the perceived need to increase the effectiveness and performance of the operator. Some of the specific areas now being addressed include the layout of control panels and work stations, adequacy of the information presented, Control Room staffing, training of the operators, and emergency procedures used by the operators. The objective of this activity is to decrease the probability of operator error and to improve the detection and correction of operator errors.
B.
Prior Control Room Design Review Activity The Main Contral Board (MCB) for Seabrook has undergone extensive design reviews during the course of its development. The basic layout of the MCB was developed by YAEC and PSNH, assisted by United Engineers and Constructors (UE&C).
i Two major reviews of the MCB for operability and maintainability were performed. The first major review was performed in the time i
period from June - August, 1975. A full size mockup of the MCB was l
reviewed by personnel from YAEC, Central Maine Power, PSNH and
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UE&C. These persons had extensive engineering and operating experience, much of it obtained in other operating nuclear plants.
This expertise ensured the performance of a thoreigh operational analysis and review. This review process resulted in significant changes and improvements to the MCB. Details of this review are on file at YNSD offices.
The second major review of the MCB was performed in October of 1980, and included changes recommended by the Seabrook Operations Department. These changes were developed as a result of the acceptance testing of the Seabrook Station Simulator.
Participating in this review were YAEC, PSNH and UE&C. Details of the results of this review are siso on file at YNSD offices.
Although not formally called " Human Factors" reviews, these reviews did in fact address many human factors concerns. In addition, YAEC/PSNH involvement has been maintained throughout the development of Control Board philosophies.
III. DISCUSSION The present detailed Control Room design review for Seabrook Station has been accomplished in accordance with the guidelines provided in the referenced NRC documents. Specifically, the design review responds to the requirements contained in Section 5 of Supplement 1 to NUREG-0737, Generic Letter 82-33.
The objective of the Seabrook Station Control Room design review is to improve the ability of nuclear power plant Control Room operators to prevent accidents or cope with accidents if they occur by improving the information provided to them. This design review identifies any modifications of Control Room configurations that the review team feels will contribute to a significant reduction of risk and enchancement in the safety of operation. Decisions to modify the Control Room have included and will continue to include consideration of long-term risk reduction and any potential temporary decline in safety af ter modifications resulting from the need to relearn maintenance and l.
a operating procedures. This will be carefully reviewed by persons competent in human factors engineering.
A.
Review Teams Qualified multi-disciplinary review teams using a review program incorporating accepted human engineering principles have been established.
Management Review Team A management team composed of representatives from YAEC and PSNH was established to review the overall progress of the Control Room review. The team members have expertise in the areas of operations, administration, and project management.
Survey Team Composition The survey team for the Seabrook Station Control Room review consisted of a core group of persons experienced in program management, plant operations, instrument and controls engineering, and human factors engineering. This core group was aided as required by persons experienced in other disciplines.
Seabrook Station, through Yankee Atomic Electric Company, contracted with the firm of Thomas B. Sheridan Associates to provide human factors engineering expertise. The qualifications of the survey team are contained in an appendix to this report.
B.
Function and Task Analysis l
Function and task analysis has been done by the Westinghouse l
Owners' Group to be used both in the performance of a Control Room human factors review and in the development of Emergency Operating
~ Procedures (EOP).
These were available to our Human Factors consultant for his use during the review of Seabrook Station. It was determ*,ned by our consultants that task analyses, procedure,_
talk-throughs and follow-up walk-throughs must be considered as a single inseparable effort. They consider that a proper model of operator action can best be obtained by observations based on actual talk-throughs and walk-throughs of procedures. The talk-throughs involved senior Seabrook operating personnel and the HFE consultants. The purpose of the talk-throughs and subsequent walk-throughs was to: (a) simulate actions by operators in operating, managing and maintaining safe operation of the plant; (b) identify errors stimulated by design inadequacies; (c) exercise most elements of the Main Control Boards that are frequently used, or for which human error probably is considered significant due to high usage or potential impact on plant operation.
The actual talk-through was an unconstrained step-by-step, very detailed reconstruction of anticipated operator actions in implementing each procedural step. Note taking of data was used to document this process.
Selected procedures were executed in real-time walk-throughs at the culmination of the task analysis - talk-through phase. The main purpose was validation of observations made during the preceding phases and to bring out time critical effects that may not have been noticeable during the non-real-time analysis.
The real-time walk-through observations were non-intrusive (no operator commentary). Unusual effects noticed during the walk-throughs were analyzed during the " post-hoc" evaluation sessions. The HFE consultant and review team personnel participated in the " post-hoc" evaluation sessions to assure completeness and objectivity of the evaluation.
The above process served also to identify any missing displays and controls. Additionally, an inventory of the Control Room instrumentation was used extensively during this review.
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C.
Operator Interviews Since Seabrook is not yet an operating plant, operator interviews were, of necessity, conducted differently than if it were operating. The Operation's staff does consist of many senior people with operations experience on other plants and with limited experience on the simulator. To make use of this experience, some of these operators were interviewed during the review process.
These interviews were structured based on formats developed by various human factors groups, modified as needed to take into account the fact that Seabrook is not an operating plant.
Questions on training and the use of the simulator were emphasized. The final format was developed jointly by the Control Room review team and the human factors consultant. A copy of this interview form is included as an appendix to this report.
The interviews were conducted by the human factors consultant to assure a reasonable level of independence. The results were used to discover potential HEDs and to assess those potential HEDs previously discovered.
D.
Survey of the Control Room Hardware The survey of the Control Room hardware was conducted on the Seabrook simulator. This simulator is an exact duplicate of the Seabrook Unit 1 MCB and is used extensively in the training of the operators. The layout of the Simulator Room and the environmental aspects (lighting, sound, etc.) duplicate those of the Main Control Room as auch as possible.
The survey was performed by a team of engineers, operators, and human factors specialists. The team was trained in both the simulator and classroom in what to look for while examining the Board panel by panel. An agenda for the training session is included as an appendix. _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _____ _-_.
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Team members were divided into pairs, usually an operator paired with an engineer or human factors specialist; and different pairs were assigned to different panels. These pairs employed common checklist / rating forms developed by the human factors consultant and YAEC, and made notations of human engineering deficiencies on those forms.
Photographs of each panel were taken for documentation purposes.
These were used to document what was reviewed and in the assessment process as required to assess potential human engineering discrepancies.
E.
Assessment The potential human engineering discrepancies have been assessed, and a determination made as to which are significant and should be corrected. The assessment process included an evaluation with respect to the importance of the HED in contributing to operator error; and with respect to the appropriate schedule for modifying the Control Room to rectify the HED.
The review team took the raw data from the Control Room Review and organized it in a logical manner. A thorough assessment was then carried out by the core group mentioned previously. The remainder of the team that participated in the actual review was available on an as-needed basis for assistance in assessing discrepancies in their areas of expertise.
For all discrepancies, an assessment of the consequences was made by the core group. This assessment took into account whether or not the potential operator error was detectable and/or correctable, the system consequences as a result of the error, and the potential for serious system consequences. This assessment was the first step in the classification of HEDs..
These discrepancies were then evaluated for possible correction by the review team. Discrepancies were prioritized according to their potential for operator error by the review team. Emphasis was placed on any significant discrepancies for possible correction.
Alternatives auch as enhancement, design change, procedure change or no change were considered for each discrepancy. This final report details all discrepancies, the disposition of each discrepancy, and the logic for the disposition.
The cumulative impact of minor HEDs was assessed for each board section by taking all the HEDs for that particular section and looking at their interaction with each other.
For ease in discussion of the potential Human Engineering Discrepancies (REDS), they have been divided with two sections, Generic and Specific. In the Generic section, the problem is stated, then those examples that appeared on the board are listed.
In the Specific section we include those which are not related to any generic problem. A preferred resolution has been developed for each potential HED.
A priority has been assigned to each HED.
This priority is a rating of the importance of the potential HED in contributing to operator error and the appropriate schedule for implementing any necessary modification. The Importance and Schedule categories follow here:
Importance 1.
Significant potential for uncorrected operator error and risk of serious consequences.
2.
Some potential for uncorrected operator error and risk of moderate consequences. No risk of serious consequences.
3.
Little or no potential for uncorrected operator error and risk of consequences. Rectification of HED should enhance operator training and satisfaction.
Schedule A.
Before startup, initiate as soon as possible.
B.
Before startup, but some further study and engineering will be required.
C.
First outage.
D.
Indefinite at this time.
E.
Will not be done.
F.
Verification Each selected improvement has been verified to inaure. hat it will provide the necessary correction and can be introduced into the Control Room without cresting an unacceptable human engineering discrepancy in itself. Such improvements have been coordinated with changes resulting from other programs.
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OVERALL BOARD ASSESSMENT The results of the above efforts are included in Sections V and VI of i
this report. In it are included the potential HEDs discovered, the selected design improvement for correction if necessary, and a justification for those not corrected.
I We found that the general layout and organization of the Seabrook Control Room is excellent; the front panels being benchboards with all displays and controls of engineered safeguard systems located to the far left, the reactor and primary system located to the lef t center, the turbine generator and secondary system located to the right center, and the electrical system located to the far right. Associated with each of the four main sections is a video alarm system display and contiguous i
keyboard, as well as some redundant hard-wired alarm and status lights.
In the center are four video displays that may be used for monitoring elarus, as well as for call up of other variables, plant diagrams, trend plots, logic trees, and the management of these. Two large video displays to the left and right may be used flexibly.
4 Back panels generally contain only those controls and displays not needed frequently or in a hurry in emergencies or used in conjunction with front panel displays and controls.
A novel color coding scheme for indicators uses a pink scale background for temperature, light blue for flow, light green for level, and light i
yellow for pressure. The red / white safety train color coding of components is effective, and is well presented.
We feel that the board will adapt well to generic labeling and demarcation. Considerable flexibility is anticipated with the use of the Video Alarm System. Altogether, we find that the board is well layed out and designed.
Several items have not been included in this document because they are I
not yet ready for review. They are:
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o Video alarm system, SPDS and associated computer aids to operator.
o Hard-wired annunciators.
o Auditory signals, communications within and outside the Control Room, acoustic noise.
o Radiation Monitoring System.
o Lighting, except to a limited degree.
Heating, ventilation and air conditioning.
o Control Room access and architecture relative to supervision, o
storage of emergency equipment, escape, limiting access of unauthorized persons, rest room and eating facilities.
Storage of operating procedures and keys, tagging, shif t turnover o
and other administrative procedures.
o Remote shutdown panel.
These will be revjewed and included in later supplements to this report.
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V.
GENERIC HUMAN ENGINEERING DISCREPANCIES A.
Anthropometries Some lights, controls and indicators are outside the standard anthropometric bounds.
1.
Annunciators Resolution:
See Item I.D.1.
2.
Top row of indicators on all panels.
Resolution:
On the front panels those indicators are presently ammeters.
The quantitative values are not important with the exception of Tave and Tref. These are large enough to be seen clearly. Priority 3E.
3.
Status lights - lettering is small and the lights are high.
Resolution:
This is a deviation from human factors criteria. An effort has been made to limit the number of words to those necessary and effective. The tiles have been grouped to establish a pattern which will serve the operator as a recognition tool.
An identification has been added to the tile layout. If a particular light is out, the operator will approach the board to read it.
If he cannot read it directly, he will use the identification matrix to locate it on a hand-held hard copy located at the board. A method will be devised to keep these hard copies available at the board. Priority 3B. -
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'4 Some CRT displays are high on the board.
Resolution:
The data on these CRTs are for the convenience of the operator and consist of auxiliary information that he wishes to have available as an operational aid. All important information appears on other, more centrally located CRTs.
The Video Alarm System indications on the CRTs are large enough to be read easily. Priority 3E.
5.
Some controls on bottom of sloping section are beyond the reach criteria.
Resolution:
When questioned, operators had no problem with this potential HED. Therefore, no change needs to be made. Priority 3E.
B.
Status Lights In general, all status light panels are confusing in arrangement and wording.
Resolution:
Arrangements and wording are being checked and changes made as neces sary. Demarcation is being added. Priority 1B.
C.
Demarcation and Labeling 1.
An identification of functional groups should be developed-for all panels as necessary, using demarcation lines and hierarchical labeling. -.
Resolution:
i This will be done. Priority 1B.
D.
Annunciators 1.
The 3/16" type on the simulator is too small to read.
Resolutior.:
Make the type as large as possible but no less than 1/4",
consistent with not crowding the edges or compromising the abbreviations used. Priority 2B.
2.
The abbreviations are inconsistent.
Resolution:
Develop and use consistent abbreviations. Priority 3B.
3.
There is no easily visible tile location matrix.
Resolution:
Develop an easily visible tile location matrix. Priority 3B.
4.
Alarm setpoints are not shown on the tiles.
Resolution:
This information will be made available to the operator in readily accessible documents. Priority 3A.
I 5.
The first out priority does not address Safety Injection.
There is no indication of the cause of an SI actuation. A first out indication should be developed.
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Resolution:
First out indication for SI actuation will be developed.
Priority IB.
6.
There is no unique audible signal for first out indication.
Resolution:
A unique audible signal will be developed for first out.
Priority IB.
E.
Abbreviations 1.
Abbreviations must be made more consistent between board labels, status lights, annunciators and procedures to the extent possible in the Control Room.
l Resolution:
The operating staff will develop a list of consistent abbreviations to be used throughout the Control Room where possible. Priority 38.
F.
Labels 1.
Tabs on label plates for vertical indicators are fragile.
They can easily break when tab is removed to zero the indicator.
Resolution:
Instruct the operator / technician on the proper method of removal. Priority 3A.
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2.
Labeling is unclear on critical MOVs which have redundant sets of indicating lights.
Examples:
SI injection valves V-77, 102 4
Resolution:
Labels have been clarified, and operators have been informed as to what the two sets of lights mean. Priority 2A.
3.
Labels are unclear and/or confusing and do not provide the information required.
Examples:
Panel A/B, Controllers RH-FCV 606, 607, 618, and 619. Panel A/B, Containment Spray Isolation Valves. Flow arrows on RCP supply should be labeled RCP-1A, RCP-1C.
Annunciator panel, RELIEF / SAFETY VALVE OPEN.
i Resolution:
The labels will be reviewed to provide the information required. Priority 2A.
G.
Indicators 1.
It is difticult to read the labels on those indicators low on the vertical section of the control board.
Resolution:
(a) On the MCB, a plastic filler has been placed under the nameplates, changing their orientation to vertical, and making them visible. l i
(b) Make the same change on the simulator. Priority 3A.
2.
There is poor contrast between the red pointers and the pink background for dual temperature indicators.
Resolution:
(a) On the MCB, use a lighter shade of pink for the background. Priority 3B, (b) On the simulator, leave as is as it is not a major problem. Priority 3E.
3.
Technical Specification alarm levels and operating bands are i
not shown.
Resolution:
Operating plant management will determine what, if any, markings are necessary. These will be shown on the indicators. Priority 2B, Examples:
LI-4079 (CST level)
LT-2607 H.
Mimic 1.
Line widths are not right. Some are too large. The line width is not diversified enough. Thinner lines should be used for minor flows. _
Resolution:
Although the simulator and the MCB are different (1/4" and 3/8") the main flow mimic on both is ok as is.
Auxiliary flow simic should be approximately 1/2 the size of the main flow mimic. This will be changed. Priority 2B.
2.
Color contrast is not good in some areas. Examples are use of black arrows on brown mimic, and use of the same color for different flow paths in a simic.
Resolution:
We will investigate the problem and develop better contrasts by using both color and width variations. Priority 2B.
3.
Paint is chipping off the brass mimic on many of the panels.
There is some concern over the durability of the painted brass.
Resolution:
Either another material will be used or the brass will be periodically repainted as needed. Priority 2B.
4.
Arrows are missing on various simic sections.
Resolution:
Add arrows to simic. Priority 2B.
1.
Controllers 1
-1.
Auto / manual labels are difficult to see from a standing position. They are small, and tend to fall off easily. -.
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Resolution:
This is a problem with the brand of controller. The operators will be trained to be aware of the problem. The labels will be taped or glued in place. Priority 3B.
2.
Some Hagan valve controllers turn left to open, some turn right.
Examples: RHR Hx outlet valves SI accumulator N vent 2
Resolution:
This will be corrected so that the open direction is consistently to the right. Priority lA.
Resolution:
3.
On manual controllers, push buttons for " increase" and
" decrease" are difficult to distinguish from " manual" and
" auto".
Resolution:
We will investigate changing lens colors or using better labeling. Priority 3B.
4 Hagan controllers do not have valve position lights associated with them. Also, the % open indication is a demand signal, not position feedback.
Example: HVC 606 (RHR temperature control)
Resolution:
The only time that valve position lights could be helpful is during start up of the systems. The majority of the time there would be two lights lit anyway, as these are modulating valves. Flow indication exists for all these valves.
The procedure will be written to verify that flow exists.
The operators will be trained to recognize the situation.
Additionally, the operators will be trained to realize that the % open indication is a demand signal, not a position feedback and the nameplate will be changed to indicate DEMAND. Priority 2A.
J.
Record ers 1.
The design of the Foxboro edgewise recorders does not allow for easy reading of the scale. There is also some delay before the trend indications can be seen.
Resolution:
Train the operators to be aware of this problem. Critical trends can be repeated on a CRT whea 'eeded.
Priority 3A.
2.
The type and size of chart paper is not indicated on the recorders.
Resolution:
Place stickers with this information on the interior of the recorders so they can be seen when recorder is pulled out.
Priority 2B..
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3.
Normal and abnormal ranges are not indicated.
Resolution:
Operating plant management will determine what, if any, markings are necessary. These will be shown on the indicators. Priority 28.
4.
Recorder scales have not been reviewed yet because they were not available. However, some examples seem to deviate from accepted methods.
Resolution:
After installation, all recorder scales will be reviewed for correct correlation with respective indicators. Priority 2B..
5.
Unused recorder pens should have no scales.
Resolution:
Scales will be removed. Priority 3B.
K.
Lighting 1.
There is a glare on indicators, recorders, and CRTs.
Resolution:
A study will be made of the glare problem and the methods that can be used to reduce it.
Some of this work can be done now, some must wait until the Control Room is complete.
Priority 3C. -.
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Controls 1.
Trip / reset function is inconsistent.
Resolution:
a.
We will investigate the use of push buttons.
b.
Make switches consistent with respect to direction of trip and reset.
c.
Investigate the use of switch handles that are different from other board switches. Priority 1B.
3.
Switch handles are inconsistent with respect to function and type (pistol grip, etc.).
Examples:
S, T, and P safeguards actuation and reset switches on Panels A and B front 011 lift pump switches RMW-P-16A and 16B SB-P-171A, B SF-P-10A, B Turbine trip push button Resolution:
We will make them as consistent as possible, consistent with logic and electrical function. Priority 2B.
4.
Some switches placed on the rear of the horizontal panel require excessive force to place in pull-to-lock position.
i Resolution:
This is overcome by using proper lifting procedure. This operation is not a normal procedure. The switches will wear in as they are operated. No change needs to be made.
Priority 3E.
M.
Bulbs 1.
There is no lamp test function for board indicating lights other than status and annunciator lights.
Resolution:
The watch turnover procedure addresses the condition of lights on the Control Board. The person taking over the watch reviews the board to see the status of the plant. He checks the pumps that are supposed to be running and the valve position. If a light is not on, a new bulb will be inserted. At that time, any burned out lights will be found. Priority 3E.
2.
Bulb covers on status lights, lamp test buttons and valve push buttons are difficult to remove. Valves could be moved by accident when changing bulbs on Master Specialty switches.
Resolution:
The operators will be made aware of the problem an.a part of their training program and will use appropriate caution when changing bulbs. Priority 2E.
3.
Bulb replacement on annunciators and status light s requires stepping on the Control Board.,
Resolution:
Purchase special stepladder for bulb replacement.
Priority 1A.
1 N.
Master Specialty switches are used for lamp test buttons, channel selector switches, and valve switches without any distinguishing characteristics between switch types.
Resolution:
Devise a method for differentiation, such as a different colored bezel. Priority 28.
O.
Tank level indicators should have " gallons" on scales, as Technical Specifications and procedures call for action based upon gallons.
Resolution:
Tank level should be in units consistent with Technical Specifications and procedures. If % is chosen, then engineering units should also be marked on the indicator scale. Priority 2B.
P.
All three-way valves have a problem in that they are always open one way or another, yet use red green lights to show indication of open direction (green means OPEN here). This is confusing. An example is the letdown heat exchanger valve CSV 170.
Resolution:
Changes will be made to obtain an obvious correspondence between mimic, light, and switch position. An amber light will be used for the abnormal lineup. Priority 1A.
a VI.
SPECIFIC HUMAN ENGINEERING DISCREPANCIES A.
Panels A and B Front 1.
The arrangement of switches and mimic of the safeguards panel on both A and B are confusing, with a lot of mirror imaging used.
Resolution:
Develop a layout that addresses the confusion problem.
Priority 1A.
2.
On Panel B, the present layout of the accumulators (A-C-B-D left to right) is confusing.
Resolution:
The recommendation of the Human Factors Review Group is to change the layout to A-B-C-D left to right. This eliminates the problem. Priority 3A.
However, the decision has been made not to make the change.
The justification is that significant layout changes to MCB Section BF have been made to address the confusing arrangement and mimic on Sections AF and BF (HED, Page 25, A.1).
The A-C-B-D accumulator layout is acceptable for the following reasons:
1 1)
The priority is 3A.
The Human Factors Review Group agrees there is little or no potential for uncorrected operator error and risk of consequences.
2)
Accumulators are. passive devices. There is no chance for uncorrected operator error in the event of an accident as all actions required for injection are taken during startup.
3)
The A-C (Train A) B-D (Train B) layout emphasizes the train assignment of the isolation valves.
If accumulators are moved, major separation barrier rework and additional switch and indicator movements will be necessary.
3.
RCS wide-range (0-3000) pressure indicators on Panel C/D front are not close enough to RHR and SI controls to give proper feedback.
Resolution:
Add indicator to Panel B left. Priority 1B.
4.
Controllers RH-FCV 606, 607, 618, 619 are not labeled properly.
Resolution:
Generic Item I.F.3.
The labels will be clarified. Priority IB.
1 1
-25a-i i
5.
Nitrogen supply valves to containment nitrogen header (containment isolation valves) and accompanying simic are placed in an inappropriate location.
Resolution:
Place them with the PRT mimic on C front. Priority 2A.
6.
The labels on containment spray isolation now indicate 1/2 which is ambiguous. They should indicate that both switches must be actuated.
Resolution:
Clarify the label and the procedure. Generic Item I.F.3.
Priority IB..
7.
Feedback to SI reset is poor, with status light going out.
Resolution:
A positive form of feedback has been provided. A status light now goes on for SI reset.
8.
Status light panels for Train A and Train B are reversed with respect to the controls and annunciators.
Resolution:
Reverse them to correspond with the panel layout, A-B left to right. Priority 1A..
9.
Two status lights say "SI Actuation". One is mislabeled.
Resolution:
i
{
\\
l The mislabeled light will be labeled correctly. Priority 1A.
-2 6-
^
10 On status lights, A and B are used for both train and phase designation.
Resolution:
This is a common designation (the Westinghouse philosophy throughout their systems) and is familiar to operators. This will be pointed out in training. Priority 3E.
11.
Scale on Containment Building recirculation sump indicator is not easily interpreted (3, 6, 9), instead of (2-4-6) or (5-10-15).
Resolution:
This indicator has been removed from the board, and the information is now available on the computer. The units will be checked to insure they are correct. Priority 1A.
12.
The Containment Building spray signal reset controls are crisscrossed.
Resolution:
They will be zearranged. Priority 1A.
13.
Train A actuation signal resets P and T should be interchanged.
Resolution:
They will be interchanged. Priority 1A.
- 14. There is a need for a sensitive containment pressure (scale 0-5 psi) indicator on the front panel to read to one-half PSI as required by emergency operating procedures. l
Resolution:
There is presently an indicator on the back panel. This will remain there. A narrow-range indicator will be added to panel BF adjacent to the existing containment pressure indicator. Priority IB.
- 15. There is a need for a con.tainment pressure recorder on the front panel to avoid running to panel GR during E0 procedure. This should be a wide-range recorder (e.g., 0-60 Psig).
Resolution:
Because redundant recorders are required by Regulatory Guide 1.97, one recorder will be added to Section BF, and the existing recorder will be moved from Section GR to Section BF.
Priority IB.
16.
There should be a narrow-range indication of containstnt recirculation sump level. The procedure says to check it.
Resolution:
The need is to check Containment Building level. Because of the design of the sump, sump level is not the best indication of this. Containment Building level is already indicated and recorded. The procedure will be changed to require checking of Containment Building level, not containment sump level.
Priority 2A.
17.
An RWST level recorder should be on front of Panel B.
Resolution:
Because redundant ' recorders are required by Regulatory Guide 1.97, two recorders will be added to Section BF.
Priority 1A.._-
Resolution:
Repositioning of the status lights and special marking now indicates the proper sequence. The procedures and operator training will address the use of the status lights. Priority IB.
- 19. There is insufficient alarm or feedback, re: containment radiation for operator at Panel A or B.
There is a danger of i
the alarm being canceled and missing a high radiation signal.
Resolution:
The Radiation Monitoring System, including alarms, will be addressed in a future supplement to this report. Priority 2B.
B.
Panel C Pront 1.
The lights for control switch CS9404 (valve V309) are not installed.
Resolution:
This is a three-way valve. Lights will be installed.
Priority 2A.
2.
The arrangement and mimic from CS7320 to large arrow could be cleaner. The locations for RCP oil lift pump switches and RMW to RCPs should be swapped for cleaner arrangement.
Resolution:
Arrangecent and mimic have been reviewed. A less confusing I
arrangement has been worked out and will be implemented.
Priority 35.
s 3.
NR PZR level (all 3) should be grouped together and separated from WR level. Wide-range label should say " COLD CALIBRATION".
Resolution:
These changes will be made. Priority 2A.
4.
PZR spray line temperature indicators should be revised.
They presently are Loop 3-Loop 1, L to R.
Resolution:
They have been changed to 1-3, L-R on the simulator. They will be changed on the MCB. Priority 3A.
5.
The RCP seal water supply flow indication and control valves should be closer to RCP controls (now on D front).
Resolution:
This panel has been rearranged. Repositioning of controls and new mimic have clarified the operation. Therefore, these can be left as they are. Priority 3E.
6.
The narrow-range scales on seal return recorders should read 0-1 gpm linear to allow proper startup condition at 0.2 gpm.
It would be better if both narrow and wide were on the same recorders. Scale range 0-6 is ok on wide range so long as it is linear.
Resolution:
Change the recorders as indicated above. Priority 2B.
I.
7.
The flow arrow on RCP supply to spray valve controllers should be labeled RCP-1A, RCP-lC.
Resolution:
1 l
The labeling will be changed. Priority 2A.
8.
The RCP ammeters have too insensitive a scale to distinguish limits on current. They need narrow range.
Resolution:
Procedures should be reviewed to insure this is necessary.
Band the normal range af ter this is determined during plant startup. If it is determined after startup that a narrow-range indicator is necessary, it will be added.
Priority 3C.
9.
The RCP flow meter reads in %, and should read in gpm.
Resolution:
All low flow reactor trip setpoints are based on % flow.
Therefore, the % flow is correct, and should remain.
10.
On the PZR pressure scale, the pointer partially covers the numbers.
Resolution:
Dual indicators force compromises. The operator is not bothered by this. While the indicator is not the best, it is adequate. Priority 3E.
1 11.
PZR level is a narrow-range recorder with a 0-100% scale.
Resolution:
This is not a wide-range scale. The operators will be trained to recognize this. Priority 3E.
- 12. On RCFV2881, the label says AUTO, but switch has only two positions.
Resolution:
The simulator has the wrong switch. It will be replaced.
The MCB has the correct switch. Priority 2A.
C.
Panel D Front 1.
The CVCS component arrangement and simic are confusing.
Resolution:
This section has been reviewed and will be rearranged to eliminate the confusion. Priority lA.
2.
Nuclear instrumentation block switches should be demarcated.
Resolution:
Suitable demarcation will be added. Priority IB.
3.
Containment isolation verification difficult if status lamps are not functioning. There is not one panel that has all the containment isolation valves together.
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Resolution:
We have investigated the possibility of grouping all together, and have placed all valves not needed in a simic on B rear.
4 The reactor trip lights have B on the top in Panel D and A on top in Panel A.
Resolution:
Reverse so that A is on top on Panel D also. Priority 1A.
5.
There is a need for Rx trip bypass breaker status indication.
Resolution:
Provide such indication. Locate it next to the Rx trip breakers and separate from them. Priority IB.
6.
On thermal regeneration system three white lights on selector switch are not labeled, therefore are not clear.
Resolution:
The lights will be labeled. Priority 1B.
Additionally, this needs further study to see if other controls are needed. Priority 3C.
7.
Charging pumps are L to R, B to A instead of A to B.
Resolution:
This was included in the general review of the arrangement of CVCS system. It will be changed L-R, A-B.
Priority 1A. __
l 8.
Need Tave PAM recorder or Te and Th on the same recorder to verify Tave decreasing to 557 degrees as required in EO procedure. Need degrees Fahrenheit scale on this recorder.
Resolution:
Make Tave recorder into PAM recorder. Priority 2B.
9.
Adjustment of boration-dilution is difficult without insdvertent alteration of count when window is raised; also, decimal point is not indicated; need to specify units (gallons).
Resolution:
This is a continuous operation, with a potential for error.
We will either rework window or look for another type of controller. Priority 2C.
- 10. % delta flux indicators do not show + or - on the scale.
Resolution:
We will add +/- indication. Priority 1A.
11.
There is a need for current and historical indication of %
delta flux as a function of power and setpoints displayed continuously.
Resolution:
This information can be supplied in several ways, either in the computer or by recorder. This will be studied to see which is more appropriate. Priority 3B.
1
- 12. Need a narrow-range (0-100 F) delta T indicator and l
l recorder for natural circulation conditions.
Resolution:
We will add required indicator and recorder. Priority 1A.
- 13. On the Tracor NR-45 it is impossible to tell which pen is selected by which switch. It is better labeled on the MCB.
With the door closed, the scale is obscured by door frame; glass on scale has poor transparency.
Resolution:
The labeling on the simulator will be upgraded. The door will be either rebuilt or removed. Priority 2B.
- 14. Tracor recorders NR-47 and NR-45 red pens are hard to change.
Resolution:
This is a function of recorder design. Operators will learn to do it correctly. Priority 3E.
15.
Correlation is reversed between the selector switches and channels for the delta T bypass selector switches and the Tave/ Tref recorder channel : select switches.
Resolution:
The nameplates will be re-labled to clarify the correlation and the functional interface with the respective recorders.
Priority 1A.
- 16. Mode switches for boration are 6 positions. It appears that the indicating lights have been removed.
Resolution:
The control switch for the system has indicating lights.
This is only a mode switch and does not require lights. This is consistant with the philosophy that mode switches do not have indicating lights. Priority 3E.
- 17. There is no status indication for motor generator sets, including status of both output breaker and tie breaker.
Resolution:
Add a computer alarm for MG set breakers open. Priority 2B.
18.
Should in-out direction of control rod drive joystick be reversed? This should be resolved by a poll of the operators; there is no "right answer".
Resolution:
Poll shows operators divided 50/50 on this question. The joystick will be made push-IN, pull-OUT. Priority 2A.
- 19. The reactor trip status panel needs regrouping and possible rewording.
Resolution:
The status panels will be reviewed and regrouped.
Priority IB. _
20.
It could be difficult to see rod position display from the side. The display is large and takes up valuable real estate requiring nuclear flux and power indicators to be moved up on the panel.
Resolution:
This is a vendor-supplied panel. It can be seen, and the operators will learn to use it effectively. The other indicators are readily visible. Priority 3E.
- 21. The boron dilution alarm is at 1.5 times shutdown count rate. Should there be an interlock or trip in addition?
Resolution:
This is used only in the re-fueling mode. There is an audible count rate monitoring this at all times. The alarm is to notify operator that he is making a mistake. There is no need fc r any other trip or interlock. Priority 3E.
22.
It is hard to check that rod groups are within one step of each other as required in procedures. Cannot see odd numbers on IRPI, must depend upon alarm.
Resolution:
r The alarm is there to depend on.
There is digital indication that the step signal has been received. No change is needed. Priority 3E.
- 23. RCP seal injection flow indication is DCBA.
Resolution:
Simulator is ok.
The MCB will be changed to ABCD.
Priority 2A. f
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D.
Panel E Front 1.
The Emergency Feedwater System simic needs to be reviewed and revised.
Resolution:
Mimic will be added as necessary, and appropriate colors will be used to more effectively indicate flow for this =ystem.
Priority 2B, 2.
The mimic line for SG feed should come in at center rather than edge.
Resolution:
Move to center. Priority 2A.
i 3.
The bottom row of indicators are mirror imaged and should be made L-R.
There are inconsistent relationships between the j
top two rows of indicators (e.g., fluws, levels, pressures).
They should be consistently L to R.
Resolution:
These will be changed as noted above. Priority 2B.
4 4.
The T-switch and the MSIV isolation switch are mirror-imaged.
Resolution:
These will be changed to avoid the mirror image. Priority 1A.
i 5.
Steam flow and feed flow indicators are ABCD; SG channel selector switches are 1, 2, 3, 4; all of Channel 1 should be together, all of Channel 2 together, etc., for each steam generator. _.
Resolution:
The channel selector switches will be revised to match corresponding indicators. Priority 25.
6.
Nameplates are above control switches, below indicators and recorders.
Resolution:
The nameplate is consistently below the indication (lights on switches). This is consistent, and r.ot a problem. No changes will be made. Priority 3E.
7.
It is hard to read rates of temperature change and pressure change for cooldown and heatup because of the difficulty in reading edge-wise recorders.
Resolution:
The computer has a program for heatup and cooldown rates.
This function will be made available on the CRTs. Priority 2A.
8.
No flow indicator exists for startup feed pump.
Resolution:
The need for this is under study. Priority 2D.
9.
The main turbine impulse chamber pressure is mislabeled, possibly should be SG reference level.
Resolution:
.The indicator will be re-labled to be Program Level.
Priority 3A.
- 10. Train A EFW valve indicating lights should be revised.
)
Resolution:
They will be changed to either L-R; or open-top, closed-bottom. Priority 1A.
11.
SG B and C recorders should be moved one slot over.
Resolution:
They will be moved. Priority 1A.
- 12. SG PAM recorders should be ABCD, with level and pressure on each, or else get levels and pressures together with Generic labels.
Resolution:
The resolution of this item requires a detailed study of train assignments and power sources. This will take some time to do.
Priorit'y 28.
- 13. There is a need for DP seter plus/minus 0 - 300 psi to go with PIS07 and 508. Need better way to watch SG feed and main steam delta P.
Requirement is to hold the programmed AP across feed regulator valves. This is especially needed if auto system fails.
Resolution:
One indicator will be added. Priority 2B.
14.
Push buttons for feed reg. valve block valves are too close to edge.
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-4 0-
Resolution:
These will be guarded. Priority 2B.
15.
There are no board indicating lights for. steam dump, only status lights.
Resolution:
Existing status lights will be made red and green.
Atmospheric steam dump will be distinguished from condenser steam dump by labeling and demarcation. Priority 1A.
16.
Status lights for FW flow and bypass valves should be red -
green instead of white.
Rasolution:
I These will be changed to red green. Priority 1A.
- 17. There is no narrow range indicated on wide-range SG scale.
Resolution:
The indicator will be banded. Priority 2C.
18.
SG feed indicators do not read in gpm, which is asked for in procedures.
Resolution:
The scale is correct, in Ibs-mass / hour. The procedure will be changed to lbs-mass / hour. Priority 3A.
conditions.
i t
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Resolution:
The need for this will be assessed during startup. If the automatic level control on the bypass does not work as designed, then an indicator will be considered. Priority 2C.
20.
On SG pressure recorders C and D, red pen is FW, blue pen is STM. These should be reversed.
Resolution:
They will be reversed. Priority 38.
21.
The push buttons for the three-element control system for level should be relocated below the corresponding level indicator.
Resolution:
The push buttons will be relocated. Priority 2A.
E.
Panel F Front 1.
Turbine stop and control valve status lights are lacking for verification of turbine trip.
Resolution:
The stop valves have status lights. The contrsi valves have Closed indication on the meter for use as a backup. Nothing else is needed. Priority 3E.
2.
Digital vide-range condenser pressure should be 0 - 30 inches Hg vacuum..
I
Resolution:
The MCB is correct. The simulator will be changed. Priority 3A.
3.
Tave indicator should go over the condenser vacuum indicator to make location consistent with Panel D.
Resolution:
The positions will be reversed on Panel F.
Priority 3A.
4.
The condenser vacuum pump needs labels to identify multiple red lights.
Resolution:
This is a unique case. Special labeling will be provided.
Priority 2A.
5.
Reheater steam supply for MSRs - lines of demarcation should be placed around 1 and 2 (West) and 4 and 3 (East).
Resolution:
Demarcation will be added. Priority IB.
6.
Turbine lift pumps A-H lo press status lights are amber instead of white.
Resolution:
.The status lights will be changed to white. Priority 3A.
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7.
On the turbine control panel, where lettering is in the middle of split window push button, some lettering is difficult to read.
Resolution:
This is an annoyance, but not a major problem. It is a panel supplied by the turbine vendor. The operators will learn to use it.
Priority 3E.
8.
The lube oil pump should be relabeled to be consistent with procedures (notor suction pump, Step 6.11.3 of ON1031.02).
Resolt tion:
Procedures and labels will be changed to be consistent.
Priority 3B.
s 9.
There is a need to jog MSIV bypass to prevent water hammer.
Resolution:
Throttle capability exists on MCB. Simulator is wrong and will be programmed to provide the throttle capability.
Priority 3A.
10.
Condenser ABC vacuum and mechanical vacuum pump are in inches of Hg ABS. Procedures are written in inches Hg vacuum.
These should be consistent.
Resolution:
These indicators will be changed to inches Hg vacuum.
Priority 3A. -
- 11. AC amp indicators should be separated by component (2 groups).
Resolution:
There is room to move heater drain indicators over, have separator between condensate and heater drain pumps. This will be done. Priority 3A.
12.
Turbine megawatt has poor scale.
Resolution:
This is a vendor-supplied meter. There are other megawatt indications that the operator can refer to.
Leave as is.
Priority 3E.
- 13. Meters with 0,4,8,12, etc., should have 2.6.10, etc., added.
Resolution:
The room is there. The changes will be made. Priority 3A.
- 14. Turning gear motor indicator needs improving. There is a need to differentiate the small motor from the large motor.
Should third light be green, or is this a proper design for a sequencer?
Resolution:
I This is a labeling problem. Correct labels will be added.
Priority 2A.
15.
The turbine speed indicator should have 1800 marked on scale.
I l
Resolution:
This will be marked on scale. Priority 3A.
-4 5-
- 16. White and blue lights for auto volt adj., man volt adj., gen.
field ground exciter field ground are not standard or consistent with other indications.
Resolution:
These switches are used infrequently and under very controlled conditions. The blue light will be changed to white. The white lights will be labeled to reinforce their special meaning. The operator will be trained to recognize this. Priority 3A.
- 17. The gen. breaker control switch interferes with the indicating light below it.
Resolution:
This is a hardware problem. A longer stem could be used, extending the switch further out from the board. Priority 3B.
18.
Some turbine controllers and push buttons 3" from edge.
Resolution:
These are startup control switches, not used at power.
However, there is some potential for affecting the T-G if they were inadvertently operated. Provision of a guard of some sort will be investigated. Priority 3D.
- 19. The operator needs more positive indication of hotwell conditions. Hotwell makeup and reject valve indications are not available.
Recommendation:
Add valve indicator lights. Priority 3C...
20.
There is no turbine generator emergency bearing oil pump header pressure indication available in the Control Room.
Resolution:
This pressure and others are available locally. The need for indication in the Control Room will be assessed during the first operating cycle. If changes are needed, they will be made. Priority 3C.
- 21. Waterbox vacuum breaker valves have one switch to close/open all valves.
Resolution:
These valves are normally operated together. If it is necessary for maintenance, the valves can be individually operated locally. Priority 3E.
22.
Main generator transfer voltmeter should indicate high or low.
Its scale is poor, should have 5 marks between 5 units. Need range switch?
Resolution:
The voltmeter should not indicate high or low. This is not a consistent reading, as it is related to the relative positions of the adjusting switches. There is no need for extra marks between the units. Operating procedure and training will insure that a null is maintained. Transfer will occur ocly at the null point. The range switch is not necessary. The auto and manual switches will be adjusted to maintain the null at all times. Priority 3E.
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- 23. Need demarcation on panel between turbine generator lif t pump status lights and those for generator exciter field de-excite relay.
Resolution:
Demarcation will be added. Priority 38.
- 24. The EBOP (emergency bearing oil pump) switch is not clear when on auto spring return to auto position.
Resolution:
This is clear on MCB. Switch has pointer. The simulator switch will be changed. Priority 3A.
25.
On the simulator, the Generator H2 pressure' units are in amps. The MCB indicator is missing.
Resolution:
Correct units. Add MCB indicator. Priority 3B.
F.
Panel C Front 1.
Demarcation / mimic are needed for air system and electrical system.
Resolution:
Demarcation will be added. Priority IB.
2.
Spacing is too close in CW intake area.
Resolution:
Smaller mimic will be used to clean this up.
Priority 2B.
l
3.
SW-V-15,16,17,18 mirror-imaged, but mimic is clear.
Priority 3E.
Resolution:
No change is required because mimic is clear.
4.
Unit 1/2 displays should be distinguishable by demarcation lines or other means, especially for isolated controls.
Resolution:
Demarcation will be added. Priority IB.
5.
Bus 3/4 displays should be distinguishable by demarcation lines.
Resolution:
Demarcation will be added. Priority 3B.
6.
Units 1 and 2, Fan 51B control should be white light instead of red. This indicates that control power is available.
Resolution:
The light will be changed. Priority 3A.
7.
Circulation water LI-6026, 6038 have improper scale divisions (now is 5 units per 8 feet).
Resolution:
The scale vill be changed. Priority 3A.
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-4 9-
8.
Cooling tower instrumentation is mirror-imaged.
1 Resolution:
The mirror-imaging will be corrected. Priority 2B.
i 9.
Service water pump discharge valves SW-V-2, V-22, V-29, and V-31 give no direct indication that they are open. That "V-2 CLOSED" and "V-29 CLOSED" status lights go out is not considered to be a satisfactory indication.
Resolution:
Add green / red lights in the simic for these valves. There is no control from the MCB, but the operator should know the position. Priority 3A.
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- 10. Alarm annunciators for Panel C functions are located on F1 annunciator.
Resolution:
Demarcation will be added as necessary. Priority 3B.
C.
H and I Front 1.
Train B DG mimic is red on MCB. It should be white if possible.
Resolution:
The 4 uimic will be changed to white. Priority 3A.
2.
Switch colors are not appropriate for DGs; should be red for A, white for B.
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Resolution:
MCB is ok.
The simulator will be changed. Priority 3A.
3.
Nameplates and control switches are not color consistent.
Resolution:
MCB is ok.
Simulator nameplates are ok; but switches will be changed. Priority 3A.
4.
GE meters not numbered.
Resolution:
They will be numbered. Priority 3A.
5.
DG fuel oil storage tank level indicator does not indicate minimum level; scale should be in gallons.
Resolution:
The scale will be changed. Priority 3A.
The minimum level will be determined and marked. Priority 2B.
6.
The Pointer obscures numbers on circular meters. Red pointers might improve the situation.
Resolution:
They can read easily. They will be left as is.
Priority 3E.
7.
DC manual and auto volt and speed adjust increase to left, dheresse to right.. j i
i Resolution:
They will be. changed to increase right, decrease lef t.
Priority 1A.
8.
All meters fail at zero (or let graduation), not below 0.
Resolution:
This is acceptable. Operator training will cover the fail potition for indicators. Priority 3E.
9.
Indicating lights above 345 kV breakers do not follow standard convention. Blue light should be above red / green, not in line. Also, if red and green lights indicate control power, why is another light needed?
Resolution:
The blue lights are all right as is, in line. They do not detract from the operators understate.ing of the system. The blue lights indicate that the MCB has control of the breaker.
The red / green lights indicate position of the breaker. The blue lights are necessary, and the operator will be trained in their use. Priority 3E.
10.
All disconnect switches should read open/close instead of trip /close.
Resolution:
The MCB is ok.
The simulator will be changed. Priority 3A.
11.
The switch handle of the DG manual volt adj. partially obscures indicating lights of DG gov. mode selector.
l l,-
Resolution!
This is no problem and will be lef t as is.
Priority 3E.
12.
There are no pointers (only targets) on some GC switches.
Resolution:
The target provides sufficient indication of switch position. Priority 3E.
- 13. The pointer on the DG main volt adjust is not painted white, and there is no pointer on shaft.
Resolution:
Paint white mark on the switch. Priority 3A.
14.
VS-9965, SNS-9880, SNS-4737-1 and SNS-9736-1 switch handles hide pointer.
Resolution:
Paint white mark on switch handles. Priority 3A.
15.
Both DC emergency start and emergency stop buttons should be more uniquely identified.
Resolution:
Demarcation will be added. Priority IB.
16.
There is a need for unique identification labels for Buses E5 and E6 indicators to identify them as emergency buses.
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Resolution:
Unique labels will be added. Priority 2A.
17.
There are no " diesel trouble" or general status lights on VAS. If there is trouble, the " ready for auto start" light goes off. ShculJ have a "DG not available" light which comes on.
Resolution:
This' status light will be added. Priority 1A.
18.
Annunciator Panels UA 54 and 55, 480 volt Buses 51, 52, 53 and Buses 61, 62, 63, 64 do not inform the operator which bus is low.
Resolution:
Two voltmeters with selector switches will be added, one for each train. These will provide indication of bus voltages.
Priority 3B.
- 19. Emergency DGs do not have transfer voltmeters. There have been instances where operator did not know if the regulator was following incoming voltage or not.
Resolution:
Indication is available. Better labeling will be added, and the operator will be twained on the operation of the system.
Priority 3A.
20.
The DG 1A governor mode select should be auto / manual, not droop /isochronous.
- i
Resolution:
This will be changed. Priority 3A.
21.
Many labels are missing on Section G of MCB. They must be added.
Resolution:
Labels will be added. Priority 3A.
H.
Panel A and B Rear 1.
There is a need for demarcation between BTRS, SG blowdown, containment isolation valves, and boron measuring system switches.
Resolution:
Demarcation will be added. Priority 2A.
2.
Containment isolation valve positions are inconsistent, re:
train correspondence to physical inside-outside of containment.
Resolution:
The operator looks to insure that all are closed (green). If one does not shut, then he shuts it.
It does not matter if it in inside or outside, the operator response is the same.
Therefore, this can be left as is.
Priority 3E.
3.
It is hard to get visual verification of containment isolation, have to read labels. Could put demarcation lines a
around set of containment isolation valves which need to be checked closed.
r Resolution Demarcation will be added. Priority 28.
4.
There is no flow sinic except safety system leak test section; check consistency with main panel spent fuel pool, etc.
Resolution:
Mimic should be added to the BTRS, SG Blowdown, and Spent Fuel Pool sections. Priority 38.
5.
SG indicators are not in line with blowdown control; they should be moved left.
f.esolution:
They will be moved. Priority 2A.
6.
There is no label on temperature of spent fuel pool.
Resolution:
The MCB is ok.
A label will be added to the simulator.
Priority 3A.
7.
There are no escutcheons on SFP switches 10A, 10B.
Resolution:
The MCB is ok.
The simulator will be fixed.
8.
The sinic in SI test panel is confusing.
l _-
r.
Resolution:
Mimic will be changed to relieve confusion. Priority 2A.
9.
The accumulator symbol is upside down, but if it is turned around it would read from wrong side.
Resolution:
This is not a problem on the MCB. The simulator will be changed. Priority 3A.
10.
No accumulator levels are available from back panel.
Resolution:
These are not needed. Indicators are available on the front panel. At present, it appears the required evolution can be accomplished using the front panel indicators.
I.
Panel C Rear 1.
EAH-DP-29A has wrong control-display correspondence (open left, auto right).
Resolution:
This will be corrected. Priority 3A.
2.
There is an odd-sized nameplate on cooling tower switchgear.
Resolution:
There is no room for a larger size. It is legible as is.
Priority 3E. - _
c,.
3.
Should inches WC be indicated on meter rather than H 07 2
Resolution:
l The procedure calls for indication to be inches WC.
Priority 3E.
4 Four containment and Control Room ventilation isolation reset switches should be uniquely identified.
Resolution:
These will be demarcated. Priority 1A, 5.
Purge vent has no lights.
Resolution:
This is a mode switch only. The control switch has indicating lights. The mode switch does not need them.
Priority 3E.
6.
FN 2A,B,C,D switches not color coded or labeled to show trains.
Resolution:
They do not need to be.
Priority 3E.
7.
Demarcation and labeling need to be addressed.
Resolution:
These will be addressed during generic demarcation and labeling effort. Priority 2B.
F.
J.
Panel C Rear 1.
Mimic is not needed, but demarcation and generic labels are required.
Resolution:
Demarcation and labels will be added. Priority IB.
2.
The new MSIV test panel needs to be checked when installed.
Resolution:
This will be checked when it is installed. Priority 2D.
3.
The vibration monitor lights are hard to change.
Resolution:
I&C will be trained to do it.
Priority 3E.
4.
The switches for emergency trip are not protected from inadvertent operation.
Resolution:
The new MSIV panel will be checked to see if this is still a problem. Priority 2D.
I K.
Panel H and I Rear l
l l'
1.
The turbine eccentricity recorder is located low on the panel.
Resolution:
l l
l Infrequent use makes this acceptable. The computer is l
available to provide information. Priority 3E.
l l
2.
There is no indication of what the white lights tell you for the extraction steam valve test or the FW isolation valve test. In one case it means the valve is closed. In the other it means the valve is 90 % open.
Resolution:
The white light means only that the test has been successful. Procedures will be clarified to say this. No change is necessary. Priority 3E.
3.
It is possible for turbine supervisory and conductivity recorders to print over each other.
Resolution:
This is a common probles with this type of recorder. The information is available from other sources. Priority 3E.
4 The new fire panel needs review.
Resolution:
The panel will be reviewed when it is available. Priority 2D.
5.
SG recirculation and drain pump controls should be located on FFl or BR panel near SG blowdown system.
Resolution:
These controls will be moved to BR.
Priority 3B.
l 6.
Six vital bus voltage indications are desirable. Only alarms
(
exist now.
! l l
Resolution:
These indications will be put on the computer with an analog indication on the CRT. Priority 3R.
7.
Turbine supervisory or equivalent computer display should be more accessible to operator on startup on front of panel.
Numbering scheme seems poor. How much can be done on CRT display, and is CRT trending better for this purpose? RPM does not agree with RPM meter on turbine control panel.
Cannot read vibration with sufficient accuracy. Turbit.e supervisory needs general review.
Resolution:
This review will be done after plant startup. Any required changes will be made later. Priority 3C.
8.
" Core monitor" should be relabeled to be other than " core".
Resolution:
This is familiar to operator, leave as is.
Priority 3E.
9.
Bus ground meters, cond. recorder, turbine supervisory recorder are not identified by labels.
Resolution:
Labels will be added. Priority 3A.
10.
Conductivity colors need to be marked with index on the recorder window.
Resolution:
This will be done. Priority 3A.
ra 1
- 11. Labels missing for DC bus, vital and non-vital.
Resolution:
Labels will be added. Priority 3A.
- 12. Recorder on IR specifies "shell"; the procedure calls for
" metal temperature".
Resolution:
The procedure will be changed. Priority 3A.
- t
4 APPENDIX A I,
SURVEY TEAM MEMBERSHIP AND QUALIFICATIONS 1
h 6
I.
I I
e 9
4 i
r-
)
Survey Team Members E. A. Sawyer - Team Leader Yankee Atomic Electric Company Provides Project Management experience W. C. Alcusky - I&C Engineer Yankee Atomic Electric Company Provides I&C and Human Factors experience A. Miller - I&C Engineer Yankee Atomic Electric Company Provides I&C and Human Factors experience J. L. Peterson -- Shift Superintendent Seabrook Station Staff Provides Operations experience M. J. DeBay - Unit Shift Supervisor Seabrook Station Staff Provides Operations experience M. R. Breault - Unit Shift Supervisor Seabrook Station Staff Provides Operations experience.
S. F. Urbanowski - Electrical _ Engineer Yankee Atomic Electric Company Provides Electrical Engineering experience t
i
~ Pt L. Anderson - Sys,tems Engineer Yankee Atomic Electric Company Provides Systems Engineering experience T. B. Sheridan, SCD -- Human Factors Consultant Thomas B. Sheridan Associates Provides Human Factors Engineering experience D. D. Lanning, PhD - Human Factors Consultant
. Thomas B. Sheridan Associates Provides Human Factors Engineering and Operations experience M. M. Danchak, PhD - Human Factors Consultant Thomas B. Sheridan Associates Provides Human Factors Engineering and Computer Technology experience Notes:
1.
Resumes for Sheridan, Lanning and Danchak are attached here.
2.
Various other operators and engineers were available and were used during the review process.
Summary Resume of Thoms B. Sher! dan, s
Thomas B. Sheridan was born in Cincinnati, Ohio, Dec. 23, 1929. He attended Purdue i
University (B.S. 1951) and, after two years in military service (aeronedical Laboratory, Wright Patterson Air Force Base, Ohio) attended the University of California, Los Ang31es (M 9. 1954) and M.I.T. (Sc.D. 1959).
His program at M.I.T. was interdependental bstween systems' engineering and psychology, with one year spent in cross-registration ct Harvard University.
For most of his career, Dr. Sheridan has remaine.d at M.I.T., where until recently j
ha was Professor of Mechanical Engineering and is now Professor of Engineering and
' Applied Psychology. He heads the Man-Machine Systems Laboratory and teaches both 3
grcduate and undergraduate subjects in Man-Machine Systems. He is a Faculty Associate i
of the M.I.T. Science, Technology and Society Program.
He helped develop a new inter-dspartmental graduate degree program in Technology and Policy, and has taught the core caninars for that program.
He has also taught control, design and other engineering 4
l subjects.
l He has served as vis'iting faculty member at the University _of California, Berkeley, Stcnford University, and the Technical University of Delft, Netherlands.
Dr. Sheridan's research has been on mathematical models of human operator and cocio-economic systems, on man-computer interaction in piloting aircraf t and in super-4 vioing undersea and industrial robotic systems, and on computer graphic technology for information searching and group decision-making. He is author, with W.'R.
- Ferrell, i
of Man-Machine Systems: Information, Control and Decision Models of Human Performance, M.I.T. Press, 1974, 1981 (published in Russian, 1980) and co-editor of a 1976 Plenum Prass book, Monitoring Behavior and Supervisory Control.
I He has been active in the Institute of Electrical and Electronics Engineers, was
}
formerly editor of the IEEE Transactions on Man-Machine Systems, is past president of
{
ths IEEE Systems Man and Cybernetics Society, served as Chairman of the IEEE Committee on Technology Forecasting and Assessment and was chairman of the 1981 IEEE Workshop i
'on Human Factors in Nuclear - Safety. lle 'is-also a Fellow of the iluman Factors Society, and in 1977 received their Paul M. Fitts Award for contributions to education. He is' 4
l Associate Editor of Automatica and on the Editorial Advisory Board of Computer Aided t,
Danign.
I
.Dr. Sheridan has served on the Accident Prevention and Injury Control Study Sec-l tions of the National Institutes of Health, the NASA Life Sciences Advisory Committee, the-NSF Automation Research Council, the NASA Study group on Robotics, the U.S. Con-grass OTA Task Force on Appropriate Technology, and the NSF Advisory Committee on l~
Applied Physical, Mathematical and Biological Sciences. He is a member of the Comittee on Human Factors and the Ad Hoc Committee on Aircrew-Vehicle Interaction, both of.the National Research Council.
4 1
His industrial consulting activities have included: The General Motors Corp.
j (auto safety); General Electric Co. (telemanipulators); C.S. Draper Laboratory (de-cign of astronaut interface.for Apollo guidance system, industrial robots); Biody-i namics, Inc. (biomedical and human factors); Public Broadcast Service (TV audience fesdback); National Bureau of Standards (ind'ustrial robots); Group Dialog Systems, Inc. (group meeting and decision technology); Northrop Aircraft (pilot workload);
i Babcock'and Wilcox Co. (industrial instrumentation); Lockheed, General Physics, Amsrican Electric Power, Consumer's Power, Gibbs and Hill, Virginia Electric Power, Gantral Public Utilities, Stone and Webster, the BWR Owners' Group, Brookhaven N2tional Laboratory and Electric Power Research Institute (man-machine aspects of nuclear plant safety).
Dr. Sheridan is married'and hhs four children.
,4.
14 D I'i c i nedume David D. Lanning (Ph.D. 1963, M.I.T.)
Professor Lanning's ficids of interest are the areas of Applied Reactor Nucicar Engineering, Reactor Operation and Safety.
He worked at the MIT Reactor in the areas of teaching; research, and reactor operation from 1957 to 1965, and returned to MIT in 1969.
At present, he is the Graduate Admissions Offi-cor for the Nuclear. Engineering Department as well as continu-ing his teaching and research.~ He was in charge of the, now completed, core modification design and installation for the MIT Reactor.
He also worked at the research laboratories in Richland, Washington from.1951 to 1957 and from 1965 to 1969.
In the' latter period, he worked for Battelle-Northwest as a manager of the Reactor Neutronics Section which included the utilization and operation of the High Temperature Lattice Testing Reactor (HTLTR) and the utilization of the Physical Constants Testing Reactor (PCTR).
He currently teaches a course in " Reactor Operations" and a course in " Nuclear Power, l
Reactors'."
His most recent sponsored re* search and consulting sctivities have been in the area of power reactor and research reactor core design, t'ransient analysis, control system studies and safety assessments.
Recent Specific Consulting 1.
Member of the Safety Audit Com,mittee for the Northern States Power Company Monticello Nuclear Generating Plant (BWR).
2.
Member of certain Design Review Boards for the Stone G Webster Engineering Corporation.
3.
Consultant for Argonne National Laboratory working on utili-ation of low enriched uranium for research and test reactor -
fuels.
4.
Review of Reactor Safety Related Information for the Boston Edison Company.
~
5.
Member of the General Public Utilities Ad Hoc Committee to review the Man-Machine Interface and Operator Training.
(TMI-2 Review) l 6.
-Consultant to the BWR Owners Group for Generic Control Redh Reviews.
7.
Coordinator of an independent consulting group to assist Boston Edison in Training:for Core Damage Recognition and Mitigation.
l l
l l
VITA _
b MICHAEL M. DANCHAK Office Residence The Hartford Graduate Center 3 Stevens Place Computer and Information Science Rocky Hill, Connecticut 06067 275 Windsor Street (203)529-7769 Hartford, Connecticut 06120 (203)S49-3600 EMPLOYMENT SYNOPSIS 7/78 - Present DIRECTOR OF STUDIES Computer and Information Science The Hartford Graduate Center Hartford, Connecticut 7/74 - 7/78 SUPERVISOR - DISPLAY SYSTEMS Instrumentation and Control Engineering Nuclear Power System Combustion Engineering, Incorporated Windsor, Connecticut 9/69 - 7/74 GRADUATE STUDENT Rensselaer Polytechnic Institute Troy, New York 6/55 - 9/69 COMMISSIONED OFFICER United States Marine Corps EDUCATION DOCTOR OF PHILOSOPHY, Nuclear Engineering 1974-Rensselaer Polytechnic Institute Troy, New York 1972 MASTER OF SCIENCE, Nuclear Engineering Rensselaer Polytechnic Institute i
Troy, New York 1965 BACHELOR OF SCIENCE IN ENGINEERING, Aerospace and Mechanical Sciences Princeton University Princeton, New Jersey
VITA of MICHAEL M. DANCHAK Page 2 PERSONAL DATA Date of Birth:
March 28, 1944 Social Security: 200-34-8514 Place of Birth: Coaldale, Pennsylvania Marital Status:
Married Professional Affiliations:
Institute for Electrical and Electronic Engineers The Human Factors Society Instrument Society of America Association for Computing Machinery Society for Information Display RECOGNITION Listed in Who's Who in the East Atomic Energy Commission Traineeship, 1972 - 1974 National Defense Education Act Traineeship, 1969 - 1972 Elected to Tau Beta Pi, 1970 Naval Reserve Officer Training Course Scholarship, 1961 - 1965 EMPLOYMENT HIGHLIGHTS 1978 - Present The Hartford Graduate Center Involved with curriculum development and management as yiell as teaching courses on computer graphics, data structures, man-computer interactions and related areas in the graduate program.
Established a computer graphics laboratory that includes a color display system and use the laboratory in ongoing education and research.
Primary interests include. color graphics and man-machine interactions.
7/74 - 7/78 Combustion Engineering, Incorporated Primary design responsibilit, for the computer generated color display system used in advanced power-plant control rooms and the attendant human factors aspects.
Performed extensive evaluations of available display and computing equipment, devised and tested new display techniques, established
~
procedures for designing display pages and served as a resource for all human factors concerns.
O i*
VITA of MICHAEL M. DANCHAK Page 3 1972 - 1974 Rensselaer Polytechnic Institute Designed and implemented an interactive computer graphics system for use in nuclear research as part of the doctoral dissertation requirements.
This included all' hardware, interfacing, software and human factors.
considerations.
Was also a teaching assistant in both undergraduate and graduate courses and a part-time programmer for the New York State Radiological Health Laboratory.
Thesis:
The Assessment and Modificaiton of Neutron Cross Sections Via Interactive Graphics.
1969 - 1974 Rensselaer Polytechnic Institute Developed a mathematical model to predict the re-entrant hole effects in three-dimensional pulsed neutron assemblies, qualified for a Senior Operator License on the RPI Critical Fecility (research reactor) and served as a teaching assistant in a special progre.m for disadvantaged students.
Thesis:
The Re-entrant Hole Effect in Pulsed Neutron Assemblies.
1965 - 1969 United States Marine Corps Was initially responsible for the day-to-day operaticn and training of the first tactical unit armed with the REDEYE Missile.
Later assigned as Officer-in-Charge of the school which trained Marine Corps personnel in the use of the REDEYE.
RECENT PROFESSIONAL ACTIVITIES Reviewer of human factors related papers for Nuclear Safety, 1978.
Invited participant, Man-Machine Interface Forum sponsored by Foxboro Corporation, June 10, 1978.
Member of the Implementation Subgroup, Association for Computing Machinery Special Interest Group for Graphics (SIGGRAPH) CORE System.
Consultant to the Idaho National Engineering Laboratory on computer dis-play design for nuclear power plant control.
Received a research contract from Idaho National Engineering Laboratory to study display of multivariate data on Cathode Ray Tubes (1980).
Participated in a research contract to study the role of the operator in Nuclear Power Operations with RPI faculty, funded by Oak Ridge National Laboratory (1980).
Re'ceived a research contract from INEL to study the static and dynamic design considerations of Process Control Alarm displays (1981).
,3 VITA of MICHAEL M. DANCHAK Page 4
.g PUBLICATION AND PAPERS "The Rensselaer Interactive Graphics Analysis System," Transactions of the American Nuclear Society, June, 1974, 18, 159.
"A Simple Device Using Capacitance Switches for Data Entry in Man-Machine Systems," Nuclear Technology, September, 1974, 23, 337.
" Utilization of Interactive Graphics and Continuous Slowing Down Theory,"
Transactions of the American Nuclear Society, October, 1974, 19, 175.
i
" Effective CRT Display Creation for Power Plant Applications," Instrumen-tation in the Power Industry, 1976, 19, 87.
"CRT Displays for Power Plants," Instrumentation Technology, October, 1976, 23, 29.
"The Man-Process Interface Using Computer Generated CRT Displays,"
Instrumentation in the Power Industry, 1977, 20, 55.
" Alphanumeric Displays for the Man-Process Interface," Advances in Instru-
-mentation, 1977, 32, Part 1, 197.
"The Content of Process Control Alarm Displays," Advances in Instrumenta-tation, 1980,jM5, 101. -
" Techniques for Displaying Multivariate Data on Cathode Ray Tubes with Applications to Nuclear Process Control," NUREG/CR-1994, April, 1981.
"The Human Factors of CRT Displays for Nuclear Power Plant Control," in Advances in Nuclear Science and Technology, (Lewis and Becker, ed.),
1981, (to be published).
9 O
APPENDIX B i
l I
s SURVEY TEAM TRAINING I
e
-4 AGENDA FOR AUGUST 1 AND 2 BRIEFINGS l
RE: CONTROL ROOM REVIEW PLAN AND METHOD i
>p-i August 1, AM i
1)
Brief review NRC post-TMI Human Factor programs.
(Control Room Review 0700 and 0801, SPDS 0835, Tech. Support Center, Emergency Shutdown, Emergency Procedures, Probabilistic Risk Analysis) 2)
0700 Proposed plan - what we cannot do at Seabrook.
3)
Overview of our plan and how it differs from 0700.
4)
Schedule and participants 5)
Supporting documents (inputs)
(P&IE diagrams, abbreviations list, inventory of displays and controls, 0700) 6)
Forms to be filled out (outputs)
(Survey Checklist, Interview Forms, Procedures Talk /Walkthrough Forms, Charts of Control Panels)
August 1, PM 7)
Brief introduction to Human Factors a)
What is it?
questions and discussion b)
Who does it?
as per interest of group c)
How well does it work?
August 2, AM 8)
Detailed discussion of Control Room Survey a)
General approach and objectives b)
Use of checklist go through items one by one in front of control panels, find examples c)
Use of diagrams, charts of control panels, abbreviation list d)
Photographic recording e)
Secondary reference to 0700, f)
Assignment of 2-man teams to panels.
August 2, PM 9)
Detailed discussion of Operator interviews a)
General approach and objectives b)
Use of forms c)
Assignment of 2-man teams to Operators
- 10) Detailed discussion of talk /walkthroughs a)
General approach and objectives b), Choice of procedures
~
c)
Use of forms - meaning of columns relative to 0700 recommendations d)
Construction of task analysis and verification of what is available with what is required e)-
Real-time walkthrough and video recording
l
- 11) Special presentation / demonstration of alarm system - to be scheduled 8
whenever appropriate
- 12) Plan for subsequent talk /walkthroughs
- 13) Computation of data, consensus on discrepancies, scheduling, and preparation of report i
a
APPENDIX C 1
OPERATOR INTERVIEW FORM 4
V e
O\\ctq'L.
a p
I OPERATOR INTERVIEW DISCUSSION The purpose of the Operator Interview is to obtain direct operator and instructor judgment to aid in identifying potential deficiencies in the control room layout or design or in operating procedures that may result in confusion (mental activities), difficulty (manual activities) or distraction (the environment). Though only simulator experience on Seabrook is available, we nevertheless feel that such opinions provide valuable suggestions to the survey team.
Using the attached questionnaire, operators and instructors are asked to respond in writing based on their previous operational experience and knowledge of control rooms in general and their knowledge of the Seabrook control room and procedures in particular. The written responses will be reviewed by a survey team member during the oral interview and possibly augmented by spontaneous replies. If additional space is needed, the attached Comment Form is to be used.
The interviews should be conducted by survey team members with background or experience in operations, engineering or human factors with a position conducive to a free flow of information. It is expected that the oral interview will take one to two hours for each operator with the entire interview taking about one day.
Following the interviews, the survey team will consolidate the information obtained and analyze it to help identify specific areas of concern.
5,
I OPERATOR INTERVIEW y
INTRODUCTION TO QUESTIONNAIRE
/Y O 'ik License Held SRO Years Operational Experience
.b+
6IA fv&[4J Education / Degrees oe
- o M
Height d,J Weight
/f7 Age 32 Sex In response to a post-TMI NRC requirement, PSNH, along with other utilities, is conducting a control room review to identify and correct design deficiencies in the operator-control room interface to minimize the potential for human error. This review is performed by a survey team composed of PSNH and YAEC representatives and some human f actors consultants.
You are asked to complete the attached questionnaire basing your responses on your general operational experience and knowledge of what the Seabrook control room is or will be.
You may complete this questionnaire anywhere, but please do so without discussing your detailed responses with other operators co=pleting this survey. If additional space is needed, the attached Comment Form is to be used.
Following completion, a survey team representative will review your responses with you.
Upon completion of all interviews, the survey team will consolidate the information obtained and apply it in their evaluation of the control room for compliance with human f actor engineering principles.
This survey provides you with a valuable opportunity for applying your knowledge and experience toward insuring the best control room design. Your honest and forthright opinions are not only welcomed, but needed.
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A What do you consider will be the most difficult, confusing or unreliable system (or component) to operate and why?
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operate and why?
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Based on your operati'onal experience, does the Seabrook control room lack any controls or displays needed for response to normal or emergency gituations?
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E Are any important in,dicators out of visual accessability durf ng normal or emergency nperation?
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F Which controls are designed, positioned or labeled in a manner that increases the risk of inadvertent operation?
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What displays do you feel are unnecessary, provide unimportant information or needlessly clutter the control panels?
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H Which controls may be difficult to operate and why?
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Whitih recorders or indicators may be difficult or confusing t why?
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J Do you anticipate having any problems locating or using procedures or operational instructions and why?
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K What changes would you recoc=iend (or not recommend) in:
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I OPERATOR INTERVIEW QUESTIONNAIRE K6 communication systems 7,
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K13 furniture, equipment or workspace Y
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9 1 OPERATOR INTERVIEW Y
QUESTIONNAIRE L
With regard to the video alarm system:
L1 Are CRT displays:
organized into a logical set that is meaningful to the opers. tor
[ & f L.<> % S )
W designed with a format appropriate to their use updated at a rate suitable for the operator O
that use charts designed with the appropriate technique based on data and operator use Y'
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L2 Does documentation exist for each display page
. (sk ksj k
L3 Does the documentation specify:
the purpose of each page &
the content of each page the interrelationships between pages M
other?
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I OPERATOR INTERVIEW QUESTIONNAIRE N
General Comments:
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l v6a Gea ual SSA)E }ae~e W b}kt n&aas (wsuaid M
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.& - m s ic ; 9 n u e. 4 -
A/e d W w w/ k m w U Aew a
' d e>e LeAsmJ%&p m
()A.
//
dW/-
_7_
7 9
e APPENDIX D l
i CONTROL ROOM SURVEY CHECKLIST l
e e
-i em
--i e in
--is
d-
]M"r p
(Yt hs l El l, 7A III CONTROL ROOM REVIEW j
Panel [86/L7 A
PANEL LAYOUT and DESIGN Al For control panels:
A1.1 does the design generally meet measurement 4i 210 standards per the attached anthropometric diagrams (complete and attach)
Ga s: a c-u w e oqco
)
A1.2 have sharp cormers and edges been 43210 eliminsted?
9 C.' L TO
,f i'/s C L c: If (
5 A2 Are lines of demarcation, mimics or other graphic displays:
l t
i t'
III Control Rocn Review PANEL LAYOUT and DESIGN (Continued)
A PANEL (A1.1) Anthroponetric Diagram s
L s'\\
e annunciator height g
\\'
/
~
o Jb a
c control height d
l4 (minimax) depth b
display height (min / max) d I
k I
linits nessurement c:-:.ents dimensic.;
nin.
nax.
nin.
mu.
a 30 60 2.}
Ei b
30 68 b
i f
I l
f e
6 r.;
28 d
l 88 c
l
~~
~~
j t
C
(\\
v v
v C
h foot Space -
r,'
III CONTROL ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued)
A2.1 used to group similar display or control 4 3/2il 0 functions within system or component groupings i,
b.
a i, f,':.. m - t ss f s e.
s-g j *> !D.- (p,,
sc p.,,_
A2.2 used to distinguish between primary 4 3 2)1 0 and secondary flow paths y, a rta.
FMW g (.e.,, f O A2.3 visually distinctive between each other 4 3 2/1'0 and panel / background A2.4 used to provide rapid visual verification hl3210 of containment isolation hlf u;. ' r$nv l $ Ep c G a e,.(
~.., ; ce,s,,;/ a.
't e.
c
. ' 's
-ft.ip d o ',
-u s c n I.,, ve,,, *; :r,1 m
A2.5 permanent, easy to clean up and maintain 4 3 2!110 A2.6 laid-out so that flow paths and 4/3 2 1 0 arrangements are orderly and easily '
recognized
.,, <, - a.
n:
r..
- t. 'n, r_., ;.
s,-.,. -
- t. -
\\L -.. i.,.,. r-n A2.7 identical in layout for repetitive
/ 4 '3 2 1 0
.,. ;.i groupings of components
~
.,c y, r....,,,
, i -i. ~,.
.1..o r c.
f.
\\
m A2.8 clearly marked with arrows to show 4 3 2: 10 C
direction of " flow" l
'I
-$l.*hf I
,_n, \\ ;\\ l '*-l c'
t.
-w 1,4 ' eJ
_y
.. w G..
i III CONTROL ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued) 432[110 A2.9 Flow mimic lines identified with starting and end points 43h10 A2.10 used to integrate switches, pumps, manual and remotely-operated valves, isolation paths, etc.
S
%D NAs O O.O \\.)0k.UCC-01
- C'U tn
)v r,
A2.ll consistent in the application of symbols 4 3 2(110 for pumps, valves and other process elements A3 For controls and displays:
s 43-2;l0 A3.1 are they generally grouped by system (with identical layout for repetitive n N.it' [zktf E'**P'} 0'R r
sg %
r a c p \\ v:.
~
A3.2 is ordering for components of similar (4'3210 function conaistently from left-to-right or top-to-bottom Di t:
,e t,
r...-
j 3, y - *,
i '. y -
'^
m 4 3 2 1/0 A3.3 are groupir.gs arranged in functional or-
'~
sequencial relationsaips 4
)2 1 0 A3.4 when strings (6 or more) or matrices (greater than 4x4) of components of similar or common function are installed, are they visually distinguishable by lines-of-demarcation, hierarchical
[
labeling, color contrast, spacing, shape, etc.
?'
L ' il 3 (Lc.$
1%
V..f.
a
[s p e.,. j
,>. n _,J :,..,
-...t.
/
18 -
4 e
t III CONTROL ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued)
A3.5 are coding methods (color, knob type, 4 3 2 lio control type, display type) consistently applied
, w ? *- \\ : ~.>
' e., _,, (,, 2,
(, < r E%
r A3.6.are they generally located in zone "a"
43210 v
or "b" on the anthropometric diagram (see A1.1)
A3.7 are control components located dithin an 4'.3 2 1 0 arms reach of feedback indications?
7 L 3P
?. '
-g
- y ~
',r. o ct "?a r g c..
c. s, 9 c,7;
{ 4. ]
(> -:-
.,. :,. c j
/
/
A4 For color use:
A4.1 is use of colors consistently applied 4 3t2 1 0 for alarm prioritization, indicating lights, labels, lines-of-demarcation, legend plates, graphic displays, indicating devices, tags, etc.
(Complete list on next page) f
.g.,,. j -. - -
f,, U r g
i
- 7
'p - ~ ~,, _ ' c gs} '
A4.2 when there is a possible dual' meaning for.. - 43210 colors, is there an additional indication for visual distinction?
f a rt n/,I,
l
./
q.
f
.~
A5 Are labels, legend plates and escutcheons:
A5.1 used to identify system or component 43210
/~
- AS.2 used to identify display or control 432/10 function 1 " '
3 o
-./
I,
.p a
~
+,
h~
Ig
[~..
+
.v III C,0NTROL ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued)
A5.3 used to identify number of instrument 4 3 2 1:0 for maintenance / test purpose v
\\
AS.4 used to idenfify power source 4!3 2 1 0,
v l\\, ;;,
'fi f )
. e.,
s' AS.5 used to identify operational limits 43210 '
or warnings
/s AS.6 used to identify panel by number and j4:3210 function in generic sense g
A AS.7 consistent in nonencisture, use of 43210 acronyms, abbreviations, etc. (list V
on Comment Form and attach)
I
~
m..
~,,
{b f,
f f [Y,I'd S 7 kT
'(^_
' 't ', ';
'A
,.3 d;
- s
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J. %,,.,1
/ ? '. s.:~~~
~-
\\
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t.
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/
.e -.:).
s; c-s_
f
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m e
Y
(*
(
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Y.n htL*.u f I
Gr
),.,gr-( c.- p
(
i-W ') k'?
's'..
2 t,
III CONTROL ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued) 32$0 A5.8 consistent in type style and the A
application of type size (i.e., larger letters in headings, all letters same height, etc.)
em AS.9 visually distinctive (light letters on 43210 dark background or dark letters on light background)
A5.10 easily read when stationed at the panel 4 3 2/1 0 (see A1.1) 4
- AS.11 succinctly worded and clear with respect 4 3 2/1 0 to function or input signal
~
A5.12 consistently positioned above or below 43210 devices and readily associated with corresponding controls and displays t
AS.13 permanent but replaceable 432 10 AS.14 conspicuous and visually distinctive from 43210 the panel background s
AS.15 oriented to read from left-to-right?
4 3 2 li o s/ n\\
+
?~
Ill CCNTROL' ROOM REVIEW Panel A
PANEL LAYOUT and DESIGN (Continued)
A7 From the operator's primary control area:
?,
A7.1 is the path to the control panel 4 3 2 1:0 unobstructed
.s r
A7.2 are control surfaces visible 43210 s,
A7.3 are co==unications systems. accessible 43210
{ - \\> ^
, p,,,
s A7.4 are annunciator windows visible and 4;3 2 1 0 identifiable?
(__
n\\'
t *- r i y:
.r-U.7 ( ;
,s--
(>y ) ;-
', / -
A7.5 are co=puter console and output devices 4 3 2 1<0 accessible s
t I
5 1
~7f k AfD T/ M Cod g
g pi,W Lniusursig n.
III CONTROL ROOM REVIEW Psnel B
INSTRUMENTATION and HARDWARE B1 Are controllers that require manual operation:
Bl.1 easily reashed (see A3.6) 432(bO-
[ 6,\\f.I
- Bl.2 designed to facilitate precise control 432/1)0 where fine adjustments are required
~
f 3 )0 98 r
f f(,
.I'I W
l'
/
Bl.3 marked to clearly show manual or 4/
210
.i automatic mode I
jyt-/c-6/E { LI9 (/"Hi: Msw to n. ra?h xer mwh fnlk++' tep aLr x;r tyrarat rn m rrn~ wwa-P.c oriw
- Bl.4 provided with mechanical stops at the 432/110 beginning and end of travel u
]4)3210 Bl.5 provided with space for hand support?
/
!::11 n
,r m.y B2 Are indicating devices:
marked to show normal or abnormal, safe
/ 4T3 210 B2.1 or unsafe, or expected or unexpected range of operation where applicable
/>>>,?
y i.., e,3 g.e sir i is sie.
j_..
s B2.2 free from glare and parallax when 4 3r2!1 0 stationed at the panel (see A1.1)
?, ;,wi v..
i.-
,pr;..
- B2.3 scaled in process units that relate to 4 3 211 0 system operation
: ?
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1
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. -....... -~....
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- l 1
III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
,s B2.4 provided with visual contrast or 4324/0 distinctiveness between scale graduations, process units, numerals, background and pointer
/a B2.5 designed so that pointers do not obscure 4321:0 graduation marks, numerals or process f
7 4,[ 4M,de units (f,&, w c.-~ /
,,m, r,:r se.o.a a,a
<.o: na a^ ', L'" '
no r:c7 can..2 <W dur'J'A' M d"A
}
A u.c,o/.
bottom,to-top, left-to right or clockwise, j, -y'7 j f, ',
B2.6 designed so that pointers move from 4 3 2#110 c.
depending on the display design and orientation A
- B2.7 designed so that indicator direction 4 3 2 1:0 corresponds to control movement te s
- B2.8 easily correlated with backup 4 3 21110 v'
indications, especially those instruments with elevated zeros A
B2.9 aligned between pointer or moveable 4 3 2illo indicator and scale without need for
~
visual extrapolation B2.10 visually aligned and provided with 432hb0 identical scales to facilitate comparative v
reading in groups of similar displays -
j
v.
' t.
r III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
- B2.11 marked with subdivisions that are 4 3/2/1 0~~
consistent with the accuracy needed by the operator
$[C Noit'/>CSDL 6?. 3 1%
B2.12 scaled with a maximum of nine intermediate 4 3 2 il JO graduations between numbered markings u
\\
B2.13 scaled with subdivisions in decimal 43/2/10 multiples of 1, 2 or 5
- e
' ^ * " ' " ' '
r+ C,n rf ri. iW ts R no t*'.
- t; t: ca ver c c a:: p It uni 3i Deted N
B2.14 marked or color coded to provide visual 4 3 2<1)0 distinctiveness between the case, panel
~
or similar cocponents B2.15 carked with numerals oriented in an 4 3 2 110 upright position v
i A
4
- B2.16 designed so that a failure mode is evident
)3210 4
s' 7
- ,y,a -
t n :?t' i>:,ws > > c'm.5 i:.,
U-i i
/T I.i T
B2.17 marked or color coded to differentiate 4 3 2 ll0A between scales on multiple range meters s
1r/,,,>.b c,( v+,;.
- !.3
,,g L, ;
..,,[
,,,,..,, i
},
B3 i For recorder charts:
m B3.1 are printed values easily read and 4/3/2 1 0 t
.\\ v-distinguishable y
. \\ 'h. -
\\. '.
y;'. ;
.r.
7,
, ;,.,, a rg i,w gn ;.,:c
,2c: vsm i
v,.,
- ...,.,, s.., :-..:~,< > a w - :n:~ n ~,
%. a f.*. y*
,$, _ t g
- g ' J g #oG
( 0 90$
$O
.fk
$ ll' 808 oh I
.a e 26'-
1 III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
^
B3.2 are printing devices properly aligned 4 3 2/1)O such that printed value corresponds to scale value p
B3.3 is the alarm point identified and does it 43210 correspond to scale value SCd5
'O ' N C' # U '
ped i OCknRD?
pm;M =
P.<c s't,2
&G, unsis m
B3.4 is there adequate clarity of markings 432:110 on multi pen recorders L'
4
^
n
- B3.5 where fast tracking rates or trends are 4 3 2 1101 periodically required, is there Hi/Lo speed capability and do administrative procedures require chart notation
/T B3.6 is point select capability available on 4 3 2 ll0/
v' multi point recorders 4
?
B3.7 is recorder clearly marked indicating
[4/3210 proper type and size of chart paper
- ' 1
- )t.u
s
- B3.8 is paper replaceable without physically.
4 3 2 ilio _
disconnecting wiring or linkage h
- B3.9 can the ink supply be. maintained without 43'2(1/0 disconnecting wiring or linkage
$
- 11lb t. :'
- s s*,,'
l
" f/2 /
~*Gy,
,1 y (
4 III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
B3.10 are pen colors consistent from one 43210 recorder to another and/or is the color association unambiguous and clearly displayed L s ) r'.'l l m o ts,J c.
O n r. 4,,.u c rv a v,ya cy
- B3.11 does chart paper not bind, eliminating 43210 frequent manual corrections
,wg 9,s. ;,m.c;
< up &w ' ~
- B3.12 has administrative procedure been 43210 established for chart marking and used chart / record retention.
uW..
- cus T
B3.13 are they free from glare and parallax 4 3 2el:0 when stationed at the panel (see Al.1) u s
B3.14 are they marked to show normal or
{13210 abnormal, safe or unsafe, or expected or unexpected range of operation where applicable?
, tl J
~
I ',
i; B4 For indicating lights:
,3 B4.1 does intensity provide adequate visual 432/110 distinction between lit and extinguished J
lights 7
/s
- B4.2 does the use of lit indicating lights 4 3 2l1JO V
consistently indicate a positive state or positive response (an unlighted condition only indicates " power off") _ _ _ _ _ - _ _ _ _ _ - -
III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
B4.3 is the size and it. tensity of alarm lights 43210 adequate to command attention
(;>,_ : c.
,0;r
(,v, dr..' ' !)
- B4.4 is there a lamp test feature when the use 4/3)210 of dual or redundant indication is not applied Pi ~e L.
c it-i toto > >? rr':
,c.,2 sw.w, Ju n i /,'-
re.1 s77-Y a r*
p.,. v > jva..,,c u si.*s's
- B4.5 is bulb replacement easily and safely 4/3)210 performed
-s m w: uOt r
<*c 'th'!
g,n.; t o i: 1, c
.<t ilt, w
t'
. ui.
r e. <<
Ln.
n rr r u.~ m res et w.
a to.*r
/idfr?sen:n. V s u r**.
o l l /?*ffe '' UW
$;r,0 2 ?,.- Lsp ?* wf, /IS.L.*-ftgrsYi t /d t e r';
- c B4.6 are sets of lights in alignment to (4)3 2 1 0 facilitate comparison between related system elements 7 fn 'N /f, E s117E s>fn~/ 'l<M (TB d A
! 12d"f fr' **
7 S,.,
e,f;;;; 5 i; Mr ?
- c e-m ri?[
ise:i.n es rs' t Li I'"
-- y s-s y. r l' f
'7 d
- B4.7 is direct indication used in preference 43210 to implied indication that a function has been performed yo, a:o.
- B4.8 when direct indication is not practical, 43210 is there backup instrumentation to indicate that a function has occurred?
- ,. ) :;a a m ),<.)
B5 For switches:
$'g gs,y,,,,_,-
y,,,,3
,7.,o,gy;-
B5.1 do handles move consistently in the same 43210 direction in accordance with expectations (i.e., right for on or start; left for off or stop; center for tripped standby, or norcal; pull-to-lock, etc.)
s', c,v A
. W J'*
si.,y,,ori..nj,',r:,,-
/ *i'
-u,-
,.c
- -o.,,j a
w, a
,.i.
- t.,..
ro,p,.y u,,,,,
p,,,,e,i
,s p.ta. ;"
.:. ~.
?.'
- t irp.~
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- ptor-c $igij ec,,, i y y,1a,j pas:. art r 29 -
Je w-A M
4 J
m 5
m I
w
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$TA%I S*IlllC SC'WO ~ hbb LODC 70 VOt? blhWAfA'Hi Y Ob. $( h8 ddIJ dM [I. hiM h.
A Cmf af a #1 Ds,7E t' M TdAisJ k
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('LW.1 ECt.
Cn%vC t ICu T:
I I
[?,le) /0 DCl1N'T [7)11 (tC C A '
/Ak er. lit n1*Me"
- s. DC5(O
' f((f&[ pfpp 97) y (,L q %"gl sj4,**f)) g ff ff f* j),.$ff,'
fw e (fi'$8$ {
f* f.
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f $ /h $
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$f!='$'$f?$ fee (dj r*pl. $fAlA ?f //
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I p,,,,,- p,,, ~.--
f i.
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- f. p,
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TidWA 4 f[Wo#
,",, ;sj i ' ! ' = = =
/f fff[f j [s{f t} s )
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(Je f f **,0 *
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f ---
- 7)', s.iJ k^
1 l
. - _ _-,...,__,-. ~
L III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
B5.2 is each position clearly marked 4 3/
10 G -[5-2440 CL"Y Ccas 27a ;% nt1-2 Nd pe/HWCil n
B5.3 is each reachable at a normal operating 4 3 24110 distance l/
A B5.4 are handles that are located near the edge 432110/
of the control panels protected with a guard to prevent inadvertent operation A
- B5.5 do handles require normal hand pressure 4 3 2 (1 10 to operate (i.e., ao thumb-busters)
~
A B5.6 are handles durable and of adequate size 4 3 2/1/0 i,
- B5.7 is switching action responsive and precise 4 3 2/1'O B5.8 are associated displays, indicating 43211)0 lights, and labels free from visual
(/
obstruction by hand or arm when the switch is operated A
B5.9 is there adequate hand space between them 4 3 2 iU O L/ 1 J
i l
.a.
(.
\\
T III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
B5.10 is physical distinction provided between 4 3 2)1 0 pumps, valves, indicating lights, divisional separation, power source, etc.
-W t?c W.ori
'~,,r' l r.-i, o ;f, o.:,:t i.a
- - gu:,i?
'I B5.11 are handles or knobs shaped so as to 4 3!2 1 0 clearly indicate position without i
obstruction of legends or confusion of l
direction?
l 6 E 7 '- < '
/m n '
nc,-
.o. ; p ri,-
sm. i.; i,,
i l B6 Are switches for emergency or abnormal use (such as turbine trip, scram, emergency trip, etc.):
\\
B6.1 clearly marked 43210 4
(_
B6.2 protected from inadvertent operation 4 3 2 1.0
- p. V -
resort
-a v.-
B6.3 readily accessible 4 3 2 1?O
- B6.4 controlled by specific procedural 43210 instructions?
g,
.- J B7 Where key-lock switches are used:
s
- B7.1 is.immediate actuation not required during 4 3 2 l'0 plant operation I
B7.2 are keys conveniently located and 43210 immediately available J
(pV.
t l
31 -
)
b o
s III CONTROL ROOM REVIEW Panel B
INSTRUMENTATION and HARDWARE (Continued)
B7.3 are keys clearly identified for specific 43210 use s
l_ yQ f, J. ~s.t > *'
f
- B7.4 do procedures provide specific 43210
^
instructions for use 4
Y
$E
(_
et-p n
- B7.5 is switch action smooth and positive 4 3 2 /1 ;0 without use of excessive force?
e
/477 sh!/)f'AlcD g,/y,f.u
. r,
p bsI ! t-
{_ANAfssUC III CONTROL ROOM REVIEW
. r g'
\\,j(,S MC4/T i
Pane 1 C
NON-COMPUTER ALARM / STATUS LIGilTS Cl Are alarm / status lights grouped:
C1.1 within annunciator box by specific 43 10 systems FO:' con-oncx>T ew ifAcx cp' 'PG 7f'
?
26esmn' rr /rt w 7$4 f.a i.
j C1.2 above related controls and displays
[4)3210
~
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C1.3 such that warning and diagnostic alarms 4 3 2/1/0 are segr.agated from inf ormational and advisory displays?
C2 Are alarm / status vindows:
43bl0 C2.1 consistent in nomenclature, use of acronyms, abbreviations, etc.
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changes or modifications (see A6)
- C2.5 succinctly worded and accurate with 43210 respect to input signal function
/)is!)",h. *]
's e
- s s e III CONTROL ROOM REVIEW Panel C
NON-COMPUTER ALARM / STATUS LIGHTS (Continued) l C2.6 provided with setpoints for parameters 43210 with multiple trip levels (water level, 7
vacuum, containment pressure, etc.)
i I
e C2.7 without multiple choice indication 432'10 (high/ low level / pressure) v C2.8 prioritized for required response level 43210 by legend plate color (preferred) or bulb color in accordance with color use
/ /^' ' ~ ' ' ' j standards (see A4.1)
C2.9 provided with an alphanumeric code in 4e3 2 1 0 addition to legends for prompt response and positive procedure identification?
fo: 3-
,3
,,,; ;.,, r py / r'A *' &
} s:s,
- s
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,r
APPENDIX E I
LIST OF PROCEDURES REVIEWED t
1
3 - Majsr Plsnt Evoluticna OS1000.01 Heatup from Cold Shutdown to Hot Standby OS1000.07 Approach to Criticality OS1000.02 Plant Startup from Hot Standby to Minimum Load 8 - Emergency Procedures OS1300 Rx Trip / Safety Injection OS1310 Loss of Reactor Coolant l
nS1320 Loss of Secondary Coolant OS1330 Steam Generator Tube Rupture OS1356.1 Pressurizer Flooding OS1356.3 Voids in the Reactor Vessel OS1342 Reactor Trip Recovery OS13ECA.2 Loss of All AC Power 14 - Operating Procedures ON1031.02 Starting and Phasing the Turbine Generator 4
ON1035.03 MFP
'A' Operations ON1038.01 Circulating Water System Startup ON1033.01 Mechanical Vacuum Pump Operations ON1031.01 Placing the Turbine Generator on Turning Gear ON1035.02 Startup Feed Pump Operations OS1001.05 Reactor Coolant Pump Operations OS1008.01 Chemical and Volume Control System Makeup Operations OS1013.03 RHR Train A Startup and Operations OS1007.01 Auto and Manual Rod Control OS1016.05 Service Water Cooling Tower Operation OS1026.01 Starting Paralleling Loading and SID of DCIA OS1023.67 Containment Ventilation Operations OS1027.01 Preparing a Steam Generator for Operation
a APPENDIX F i n-f, PROCEDURE TALK-THROUGH EXAMPLE e
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Page 1 of 1 STATION OPERATING PROCEDURE COVER FORM i
A.
IDENTIFICATION Nunbe r OS1027.01 Revision 00 Title PREPARING A STEAM GENERATOR FOR OPERATION Originator John Kinball i
B.
TECHNICAL REVIEU Title Signature Date Dept Supvr/11gr C.
QUALITY ASSURANCE REVIEW Title Signature Date D.
SORC APPROVAL SORC Meeting No.
E.
YNSD APPROVAL Titic Signature Date
_./
F.
APPROVAL AND I!!PLE!!ENTATION i
Station Superintendent Approved Date Review Due Date AQ l.02A
]
] [T Rev. O Also Available On
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Aperture Card 3-
-- { } L_
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011JECTIVI5 CRITERION Available l
Availabic COMMENTS l
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.k PROCEDURE NO.
OS1027.01 PACE 2 REVISION NO.
00 i
1.0 OBJECTIVE'S i
Tnis procedure will enable the operator to:
1.1 Drain a ster.m generator to the startuo operating band.
Fill a st[am geie'rator t'o'th'e startup operating band..,._ - T h
~
1.2 4
e%
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?.O REFERENCES
_. ~.. _ -. -
i 2.1 UE&C P&ID's 9763-F-804992, Rev. 2 9763-F-805037, Rev. 1 9763-F-804943, Rev. 2 9763-F-805039, Rev. 2 9763-F-805003, Rev. 4 9763-F-805636, Rev. 1 4763-F-805004, Rev. 4 9763-F-202074, Rev. 6 9763-F-805005, Rev. 4 9763-F-202076, Rev. 0 9763-F-805006, Rev. 4 9763-F-202079, Rev. 6 9763-F-805020, Rev. 3 9763-F-202084, Rev. 5 9763-F-805021, Rev. 3 9763-F-202086, Rev. 3 9763-F-805024, Rev. 4 9763-F-202110, Rev. O 3
ny 9763-F-805025, Rev. 4 A3=R "R:
2.2 UE&C Logics Tab 13 1
Tab'71
}
Tab 44 2.3 UE&C System Description Tab 3, Main and Auxillary Steam System Tab 21, Steam Generator Blowdown System Tab 94, Chemical Addition and Analysis System 2.4 Westinghouse Steam Side Water Chemistry Control Specifications:
Section 4 Protection Against Corrosion Section 7 Steam Side Water Chemistry Section 10 Steam ;Cenerator Protection during Inactive Periods i
2.5 Westinghouse Vertical Steam Generator Technical Manual 1440-C316.
3.0 PRECAUTIO!!S 3.1 Whenever possible, close the steam generator blowdown isolation valves in the following sequence to avoid a " water hammer".in the lines when blowdown is reinstated.
3.1.1 Close manual steam generator blowdown throttle valves.
3.1.2 Close steam generator blowdown isolation valves incide reactor containment (IRC).
3.1.3 Close steam nenerator blowdown isolation valves.
NOTE TIIE "UATER IIA!CfER" IS DUE TO THE BLOUDOUN RAPIDLY EXPANDING SINCE Tile l
DnUNSTREAM LINE OF THE ISOLATION VALVES WOULD BE DRAINED.
l
- Also Available On g
Aperture Card I,
- J i
OBJECTIVE l
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Available CHITERION l
Available COMMENTS l
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PROCEDURE NO.
OS1027.01 PACE 3 REVISION NO. _ 00 4
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3.2 Draining more than one steam generator requires that additional N available to supplement on site inventories (Later) amount.
2 be g
h 3.3 The electrical components of the system will de energize upon loss of
%/3 ciectrical power.
Redundant coergency power supplies are not provided.
J 3.4 Due to the heat load on PCCU, the capacity of the Steam Generator Blowdown System nay be limited during heat Water System tunnels and during the initial phase of plantof the Circulating treatment cooldown.
O 3.5 Do not exceed 99% of wide range level indication when filling the stean This avoids overstressing the main stean lines due to the generator.
added dead weight of a flooded line and reduces the potential of a secondary safety valve sticking open following disenarge of water or two phase flou.
3.6 Radiation element RE-6519 nust be functional at all times when using the Steau Cenerator Blowdown Recovery System or discharging to the N.
environnent via tae WIT pump discharge header.
3.7 The steam generator must be continuously sanpled whenever discharging steam generator water to the transition structure via the WIT pump N
i l
discharge header.
i 3.8 Do not open SB-V57, supply isolation for the steam generator blowdown evaporators /FDT's, if evaporator SB-EV-5A or SB-EV-5B is being purged
- 9 with nitrogen.
4.0 LI:llTATIONS AND SETPOTNTS 4.1 REF: (T.S.3.4.10.1)
The Reactor Coolant System temperature and pressure shall be naintained
}
within the limits of the operator's curve, Technical Data Book, page l
( La t e r ).
4.2 REF: (T.S.3.7.2) i i
The tenperature iof both the primary and secondary coolants in the stean The pressure in each side of the stean generator shall be deternined toge be < 200 psig at,least once prina ry and seconda ry coblantner brcqw*Fhen the temperature of either the is WO 4.3 A nitrogen header pressure of 2 to 5 psig must be maintained by employ-
/pd of autonatic pressure regulating equipment whenever the stean acnt generator is drained or in a partially drained condition.
gg -
4.4 Steam generator feedwater nust ocet the specifications of (Later).
g 4.5 Stean generator draining rate will not exceed 280 gpn.
/t/. p
' A discharge pernic is required prior to environnental discharge via the 4.6 UTT pump discharge header.
N[4 Also Available On Aperture Card I
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PROCEDURE NO.
OS1027.01 PAGE 4
(
REVISION NO.
00 4.7 The. Steam Cenerator Blowdown System is automatically shut down on a "T" g//j) signal or loss of air.
5,0 PREREQUISITES 5.1 The N2 System shall be o'perable as per procedure OS1024.01.
5.2 The RCS is in mode or 6.
5.3 The RHR is operable and mabitaining R'tS temperature and pressure within allowable limits of the sperator's curve.
&u 5.4 The Sample System is available as per procedure OS1053.02A.
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5.5 For draining a steam generator:
j 5.5.1 Blowdown evaporators SB-EV-5A and SB-EV-5B are not being purged.
5.5.2 The PCCW System is operable and supplying cooling water co the steam generator blowdown components.
5.5.3 RCDT and PRT are isolated from the N2 header when pressurizing the steam generator (s).
5.5.4 The Steam Generator Blowdown System is available per proce-dure OS1021.01.
5.5.5 Ensure a circulating water pump or service water pump is operating if discharging steam generator uater to the tran-sition structure.
5.6 For filling a steam generator:
5.6.1 The, Feedwater System is availabic from the startup feed pump (SFP) to the steam generator.
Theschamgeneratoratmosphericdumpvalveisoperablefor J,
5.6.2 over pressurization protection.
6.0 PROCEDURE A
6.1 Draining a steam generator to the startup operating band.
6.1.1.
Adjust NC-PCV-4602, N2 header pressure regulator, to establish a header pressure of 2 to 15 psig.
I 6.1.2 Open NC-V120 and NG-V121, N2 gas header containment isolation valves, and ensure the N2 gas header stablizes at 2 to 15 psig.
CAUTION Also Available On THE STkAll CENERATOR !!UST BE CONTINUOUSLY SA!! PLED Aperture Card TO ENSURE CONTENTS BEING DRAINED ARE WITilIN THE SPECIFICATIONS ESTABLISHED BY (LATER) DISCHARGE
(
REQUIRE!!ENTS I.
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PROCEDURE NO.
OS1027.01 PAGE 5 i
REVISION NO.
00 CAUTION ENSURE RADIATIch ELENENT RE-6519 IS OPERATIONAL TO TO PREVENT POSSIBLE RELEASE OF RADIOACTIVE MATERIAI
_ THE ENVIRONMENT.
6.1.3 Commence draining the stea'm generator to the transition structure as follows:
6.1.3.1 Open SB-V54, blowdown isolation to the UTT pump discharge header.
6.1.3.2 Shut SB-V354, Steam Generator Blowdown Recovery System supply header isolation.
6.1.3.3 Open FIL-V222 or WL-V223, vaste test tanks effluent isolation valve to the intake and discharge tran-sition structure respectively.
NOTE UNLESS HEAT TREATMENT OF Tile CIRCULATING WATER SYSTEH TUNITELS IS IN PROGRESS, WL-V223 WILL NORMALLY BE USED.
6.1.3.4 Open the stean generator blowdown isolation valve.
Steam Generator A B
C D
SB-V189 SB-V191 SB-V193 SB-V195 6.1.3.5 Open the steam generator blowdown IRC isolation valve.
Stean Generator A B
C D
SB-V1 SB-V3 SB-V5 SB-V7 6.1.3.6 Open the N2 supply valve and pressurize the desired steam generator.
- N2 Supply to Main Steam Loop 1
2 3
4 NC-V39 NC-V40 NG-V41 NG-V42 1
0
, NOTE I
_ f l'ONITOR Tile N2 !!EADER PRESSURE DURING DRAINING TO ENSURE A POSITIVE N2 PRESSURE OF 2 TO 15 PSIG IS MAINTAINED.
6.1.3.7 Slowly ope, the steam generator blowdown throttle valve to establish a flow of <280 gpm.
Steam Generator A B
C D
SR-V21 SB-V22 SR-V23 Sn-V24 Also Available On y
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OS1027.01 PAGE 6
^{
REVISION NO.
00 i
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6.1.3.8 Open SR-CV-6519, blowdown discharge to Service 1
)
{
tJater and Blowdown Recovery System control valve, I
from the MCB and place in AUTO.
6.1.3.9 Ithen the steam generator level is between 60 and 70%
I of wide range indication, stop draining the steam generator as follows:
6.1.3.9.1 Shut the steam generator blowdown l>
throttle valve.
S/G A
B C
D SR-V21 SB-V22 SB-V23 SB-V24 j
6.1.3.9.2 Shut the steam generator blowdown j'
IRC isolation valve.
S/G A
B C
D SR-V1 SB-V3 SR-V5 SB-V7 6.1.3.9.3 Shut the steam generator blowdown isolation valve.
S/G A
B C
D SB-V189 SE-V191 SB-V193 SB-Vl95 6.1.3.9.4 Shut SB-CV-6519, blowdown discharge to Service flater and Blowdown Recovery System control valve.
6.1.3.'10 Open SR-V354, Steam Generator Blowdown Recovery Systen supply header isolation.
6.1.3.11 Shut SB-V54, steam generator blowdown isolation to the llTT pump discharge header.
l 6.1.3.;12 Shut IJL-V222 or 11L-V223 whichever was opened in step
'j 6.1.3.3.
f
.i 6.1.3.:13 Shut the M2 supply valve to the affected steam I
generator.
!!2 Supply to Main Steam Loop-l 1
2 3
4 NG-V39 NC-v40 NC-V41 NG-42
[
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6.1.3.,14 Shut NG-v120 nd NG-V121, N2 gas header containment
[
isolation valves.
i.
6.2 Filling a Steam Cenerator to the Startup Operating Band.
l I
6. 2.1.
Notify [ chemistry to mix steam generator chemicals as per pro-cedure (Later) if required.
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OS1027.01 PAGE 7 REVISION NO.
00 Mtch 6.2.2 Shut both steam generatorgfeed pumps' discharge isolation valves f rom !!CB.
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I SCFP P-32A SCFP P-328 " M "'
~1'
FW-V2 FW-V13 CAUTION UNLESS BOTil PRDIARY AND SECONDARY WATER TE!!PERATURES ARE
>70*F.
USE Tile STEAM CENERATOR AT!!OSPHERIC DUMP VALVE FOR OVERPRESSURE PROTECTION. i a
6.2.3 Start the startup fecd pump per procedure OF1035.02 and establish a feed rate of (Later) gpm by throttling feed regu-lating valve bypass for appropriate steam generator.
Steam Generator A B
C D
LK-4210 LK-4220 LK-4230 LK-4240 6.2.4 Comnence adding chemicals to the steam generator per procedure ON1053.02 as required.
j 6.2.5 Fill and maintain the steam generator level between 60 and 70%
o f wide range indication.
6.2.6 Monitor steam generator pressure and vent as necessary with the a tmospheric dump valve.
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