ML20116E817
| ML20116E817 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 04/24/1985 |
| From: | ESSEX CORP. |
| To: | |
| Shared Package | |
| ML20116E807 | List: |
| References | |
| TAC-57368, NUDOCS 8504300432 | |
| Download: ML20116E817 (51) | |
Text
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Final Report TASK ANALYSIS AND VERIFICATION OF THE SNUPPS CONTROL ROOM Prepared For:
The SNUPPS Plants o Wolf Creek o Callaway 5 Choke Cherry Road Rockville, Maryland 20850 Prepared By:
Essex Corporation e 333 North Fairfax Street Alexandria, Virginia 22314 24 April 1985 SBa*
F 28 ear BI88lh
Final Report TASK ANALYSIS AND VERIFICATION OF THE
- SNUPPS CONTROL ROOM Prepared For:
The SNUPPS Plants o Wolf Creek o Callaway 5 Choke Cherry Road Rockville, Maryland 20850 Prepared By:
Essex Corporation 333 North Fairfax Street Alexandria, Virginia 22314 24 April 1985 0 <
, t,,
j APR 2 61985 6 SNUPPS 1
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- l TABLE OF CONTENTS' !
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1.0 INTRODUCTION
1 1.1 Background 1 1.2 Objectives 1 1.3 Team Composition 2 2.0 APPROACH 4 2.1 Assumptions 4 2.2 Task Analysis and Verification Procedure 4 2.2.1 Action-Information Requirements Details (AIRD) 5 2.2.2 Action-Information Requirements Summary (AIRS) 5 2.2.3 Cross-Check 5 2.2.4 Verification 6 3.0 RESULTS 9 3.1 Cross-Check Procedures 9 3.2 Verification 9 4A DISCUSSION 11
' APPENDIX I Human Engineering Finding Reports I-1 APPENDIX II ' Detailed Task Analysis and Verification Procedure 11- 1
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1.0 INTRODUCTION
1.1 Background
Events subsequent to the Three Mlle Island (TMI) accident have caused an increased awareness of the need for ensuring that nuclear power plant control rooms have been designed in accordance with principles of human factors engineering (life). This need has been articulated in Supplement I to NUREG-0737. One of the requirements in this document was that a system function and task analysis be performed as part of the detailed control room design review (DCRDR). This was to ensure that the necessary controls and displays for the successful mitigation of emergency events exist in the control room, and that they are designed to facilitate this mitigation.
In response to the requirements of Supplement I to NUREG-0737, SNUPPS sub-mitted a summary report of the status of the DCRDR for the Wolf Creek and Callaway control rooms. Included in this was the plan for performing the system function and task analysis. After review, the Nuclear Regulatory Commission (NRC) staff raised questions regarding the degree of 1) involvement by trained human factors engineers in the task analysis process, and 2) use of plant specific instrumentation and control documentation for the task analysis.
To further clarify these areas, SNUPPS contracted with the Essex Corporation for HFE support in the development and performance of a task analysis procedure to be used for the Wolf Creek control room. Results of this review apply to Callaway due to the similarity of the SNUPPS plants. This effort was initiated in September 1984 and completed in April 1985. This report documents the activities and results of the task cnalysis and verification.
1.2 Objectives The objectives of the task analysis and verification were to
- 1. Analyze the design requirements of the SNUPPS control room instrumen-tation and controls independent of plant specific design documentation that specifies such instrumentation and controls.
- 2. Verify the results of the task analysis on the Wolf Creek simulator.
- 3. Develop a list of discrepancies, if any, resulting from the verification process.
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Discrepancies were reviewed by the Human Factors Plant Review Group (HFPRG) and the results are presented under paragraph 4.0 Discussion.
1,3 Team Composition The team that participated in the SNUPPS task analysis and verification included SNUPPS Staff, the SNUPPS Human Factors Plant Review Group (HFPRG), members of the Wolf Creek procedures writing group and training group, and members of the Essex Corporation staff. The SNUPPS task analysis has been managed by the SNUPPS Staff organization, which is the central organization established by the SNUPPS Utilities to manage the design and licensing of the SNUPPS plants. The HFPRG is composed of engineering and operations experts from Kansas Gas and Electric Co. (Wolf Creek) and Union Electric Co. (Callaway). The primary Essex personnel involved included human factors engineers with up to six years of experience in nuclear power applications, and an Ex-SRO with four years experience in human factors. Table 1 lists the individuals on the task analysis team, and their areas of expertise.
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Table 1: Members of the SNUPPS Task Analysis Team Name Affiliation Area of Expertise LIrry W. Avery Essex Corporation Research Scientist, HFE
- Dale L. Pilsitz Essex Corporation Operations Specialist, HFE Walter T. Talley Essex Corporation Senior Scientist, HFE James O. Cermak SNUPPS Staff Nuclear Engineering D. Jeffrey Klein SNUPPS Staff Mechanical Engineering N. K. (Nick) Garg SNUPPS Staff Electrical Engineering M. H. Hellman Union Electric HFPRG, Electrical Engineering Bill O. Jessop Union Electric HFPRG, Operations &
Training D2vid E. Shafer ' Union Electric Licensing David E. Heinlein Union Electric HFPRG, Operations Duane V. Kern Kansas Gas & Electric HFPRG, Electrical Engineering C. Michael Estes Kansas Gas & Electric HFPRG, Operations &
Procedures Writers Group Joy C. Go' ode Kansas Gas & Electric Licensing Shannon Armstrong Kansas Gas & Electric Operations & Procedures Writers Group Rick Rayklewfoz Kansas Gas & Electric Operations i JImes Burns Kansas Gas & Electric Training Pete Martin Kansas Gas & Electric Operations f
!. D21e Moses Kansas Gas & Electric Training I
_ Mcnte Schmidt Kansas Gas & Electric Training David Fehr Kansas Gas & Electric Training 4
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2.0 APPROACH 2.1 Assumptions Prior to the development and application of the task analysis and verification procedure, certain assumptions were made by the task analysis team. The first of these tssumptions regarded the number of procedures necessary for complete coverage of the control and display design requirements necessary for the mitigation of emergency conditions. Inclusion of the following Westinghouse Emergency Response Guidelines (ERGS) in the task analysis covers approximately ninety percent (90%) of the control and displays required; E-0, E-1, E-2, E-3, E C A-0.0, and all the Function Restoration
- Guidelines (FRGs). To ensure that the remaining (= 10 percent) instrumentation and control requirements identified in the Westinghouse System Function Review and Task Analysis (SRTA) were included in the SNUPPS task analysis, a cross check procedure was included (see para. 2.2.3).
The second assumption regarded the applicability of the results to the Callaway control room. While the task analysis and verification were performed on the Wolf Creek plant, the Callaway control room is virtually identical, with the exception of certain plant specific panels that control electrical distribution and cooling water. In addition, as each plant has developed, they have communicated with each other to ensure the f*.lelity of their procedures, specifications, and other documentation.
The task analysis was performed in two major steps. First, generic data was dsveloped based on the ERGS (Rev 1). This data is directly applicable to both plants.
S:cond, the data was made plant specific by using plant operations and procedure writing pirsonnel. During this process, Callaway operations and engineering personnel were involved to ensure that the data reflected their plant. All findings from the verification on the Wolf Creek simulator and control room were reviewed by Callaway personnel to
! cnsure applicability to their plant. Therefore, this task analysis documents the instru-mIntation and control design requirements, and any discrepancies from those require-
! mants, for both the Wolf Creek and Callaway control rooms.
l 2,2 Task Analysis and Verification Procedure The task analysis procedure, developed by Essex Corporation and the SNUPPS staff, extracted generic operator action and information requirements from the Westinghouse Owners Group Emergency Response Guidelines and Background documents, converted the requirements to a plant specific level, and documented the results for use in the 4
verification process. The following paragraphs briefly describe the procedure; Appendix 11 contains the detailed procedure.
2.2.1 Action-Information Requirements Details (AIRD)
AIRD forms (see Figure 1) were prepared by Essex Corporation for each step, caution statement, and note in Revision 1 of Emergency Response Guidelines (ERGS) E-0, E-1, E-2, E-3, ECA-0.0 and all the Function Restoration Guidelines. Review of the AIRD forms was conducted by the Human Factors Plant Review Group (HFPRG), SNUPPS Staff cnd Essex Corporation personnel on December 18th and 19th,1984. During this review the generic task analysis was made plant specific.
2.2.2 Action-Information Requirements Summary (AIRS)
To develop the AIRS forms (see Figure 2), the SNUPPS Staff developed a computer program sort. All behavioral elements from the AIRD forms were transformed into sorted order on the AIRS forms. This formed the basis for an instrument and control specification. Wherever feasible, the SNUPPS abbreviations list was utilized to aid in standardizing abbreviations.
Based on our nuclear and HFE experience, Essex estimated what the operators might expect for valve response times. These estimated response times were then compared to actual response times from the plant specific valve in service testing program for each valve safety related by function during the March 5, 6, and 7,1985 validation of the SNUPPS task analysis performed by the Human Factors Plant Review Group. This effort was to identify valves that have an actual stroke time significantly different than cperator expectations. Identifying these valves will alert the operator of unusual response times and therefore avoid the potential for confusion.
- 2. 2.3 Cross-Chec'k Upon completion of the action and information requirements summary on the AIRS fctms, the inventory of parameters to be observed and/or controlled was compared to the instrumentation and control requirements listed by Westinghouse in its System Function Review and Task Analysis (SRTA) of the basic version of the ERGS. This cross check
-included insttumentation and control requirements for the foldout pages from E-0, E-1, and E-3 series guidelines and foldout pages for guidelines ECA-2.1, ECA-3.1, and ECA-3.2. This cross check identified instrument and/or control requirements not yet included in the SNUPPS task analysis. The identified differences were listed individually on 5
additional Action Information Requirements Details (AIR'D) forms and Action Information Requirements Summary (AIRS) forms so they would be included in the verification process. In this way, all instrumentation and control requirements were addressed.
2.2.4 Verification The verification was performed in two phases. First, over March 5, 6, and 7,1985, the HFPRG reviewed the Wolf Creek simulator and control room using the data from the AIRS. This phase included interviews of Wolf Creek operations personnel. The verification summary block on each AIRS form was completed at this time. If existing instrumentation and/or controls fulfilled the action-information requirements listed, a check was inserted in the " Pass" column. If the existing information controls did not fulfill the action-information requirements listed, the " Fall" column was checked. Essex then generated a Human Engineering Finding (HEF) form (r.efer to Appendix I), reviewed the AIRS, and generated additional HEFs based on information gained during the meetings to convert the generic AIRDs to plant specific.
The set of failed AIRS forms provided the basis for the HEFs. This set was supplemented by additional findings resulting from the interviews.
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ACTION INFORMATION REQUIREMENTS DFTAILS (AIRD) sheet of PLANT; WOLF CREEK. SNUPPS UNIT: ORIGINATOR: BATE:
REVIEWEft: DATE:
STEP NO:
j STEP OSJECTIVE: l REMARKS:
SEHAVIORAL ELEMENTS l -
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/ / / // =
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l Figure 1: Sample AIRD Form t
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SHEET cf.__--..
ACTION-INFORMATION REQUIREMENTS
SUMMARY
(AIF5)
FLANT: SNUPPS (WOLF CREEL) ORIGINATDR:__________- LATE ._____
REVIEWERS -_______- _-_DATE ______
SOET PLOct i SUFMARv OF REOUIREMENr5 p(03
! REOS TYPE: : I VAuuE/RANSE __-____ ______
! Sv5 TEM: 1 I UNITS __ _ . _ _ ___________
I COMFONENT: : I FRECISION _ _
I FARAMETER: I 8 RESPONSE TIME: _ _ _1 3 - -__-.
8.__ .-- ! -
-_---... _ .--...-=.
REMARLS: I VERIFICATIDN
SUMMARY
BLOCV
! DEVICE I I
- 1.
- See AIRD
- I.D. No f PANEL f BDM* IFAS5! FAIL; f f I i '
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INDIVIDLAL DETAILS STATE / UNITS / TREND ERG STED ACT VERE DIFECTION VALUE RATE FREC RED COMMENTS b
Figure 2: Sample AIRS FORM 8
3.0 RESULTS 3.1 Cross-Check Procedures As a result of the cross check between the AIRS forms and the Westinghouse SRTA, including foldout pages for E-0, E-1, E-3, ECA-2.1, ECA-3.1, and ECA-3.2, two additional control requirements and seven additional instrument requirements were identified.
These additional requirements were incorporated into the Task Analysis data base: AIRDs and AIRSs. This process ensures that all instrumentation and control requirements were addressed.
3,2 Verification The verification process produced eleven findings that resulted in a Human Engineering Finding (HEF) report being completed. The completed HEFs are presented in Appendix I. The findings are briefly described below.
- 1. ECA 0.0, Step 23 requires BIT temperature indication in the control room. None is provided.
- 2. E-0, Step 13A and E-3, Step 13A, require main steam readings of 615 psig, however, control room indicators are graduated in 20 psig incre-ments. A reading of 615 psig could not, therefore, be read accurately.
- 3. ERGS require plant setpoint settings of 615,1185, and 1235 psig to be read in the control room. Indicator graduations are presented in 20 psig increments.
- 4. FRH.1, Steps 5 and 18 require an indication of feedwater isolation reset.
This indication is not provided on the main control boards.
5.- The plant specific requirement for CCW flow indication to the RCPs, as identified in Rev. O of the KGE EOPs, is approximately 40 GPM. The indicators on the main control boards are scaled in MPPH.
- 6. KGE procedure E-1, Step 13A, requires operator action at greater than
- 535 GPM. The control room indicators are graduated in increments of f 100 GPM. Therefore, this value of 535 GPM can c.M be read accurately.
- 7. In the emergency mode (fast close), the me.in steam isolation valves and feedwater isolation valves close in less that five seconds. But in the normal mode (slow open/close) they clos in approximately five minutes.
- 8. The ERG background documentation for ?'R-C.1, Step C-lb, lists CCW to RHR heat exchanger flow as an instrumentation requirement. No instrument for this exists in the control room.
- 9. The background documents for eight of the ERGS lists CCW flow to seal water heat exchanger as an information requirement. No instrumen-tation for this information is provided in the control room.
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- 10. The background document for ERG E-3, Step 2, lists steamline radiation monitors as an instrument requirement. None is provided in the SNUPPS control room.
- 11. Wolf Creek Rev 0 procedures' value for spent fuel poollevel is expressed in units of feet. The control room indication for this value does not read out in feet.
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4.0 DISCUSSION As the results section indicated, based on the verification using the information-control design requirements developed during the SNUPPS task analysis eleven findings were ' identified. Each of these discrepancies were assessed by the HFPRG for safety significance and impact, and responses generated by SNUPPS and utility personnel. These rzsponses and corrective actions as necessary are presented below.
Finding 1: Boric acid is no longer required for the BIT (refer to FSAR section 6.3.2.2), therefore, BIT temperature indication is not required.
No further action will be taken.
Finding 2: The value of 615 psig is a Tech Spec value required by the ERG for steamline low pressure safety injection. Bistable signals at this setpoint are input to control room annunciators and the reactor partial trip status panel SB069. Based on training, control room operators are alerted to these two sources and do not require an indicator scale that can be read exactly at 615 psig. In 2,.
addition, operators are trained to monitor these parameters and take appropriate action, as necessary. No further action will be
.taken.
Finding 3: These are plant specific design setpoints requested in the ERG; the latter two represent the lowest and highest safety valve setpoints. These numbers represent general values for the operators to begin depressurizing the secondary system, there-fore, these values are not required to be read to the indicated level of precision. In addition, operators are trained to monitor these parameters and take appropriate action, as necessary. The steamline low pressure safety injection setpoint (615 psig) is discussed in finding 2, above. No further action will be taken.
Finding 4: Indication is provided on back panels SA75A and B. In addition,
[ the ERG provides continglencies in the event that feedwater isolation cannot be reset. No further action will be taken.
l Finding 5: CCW HI/LO flow alarms are provided in the control room. In l- addition, proper valve alignment or indication of flow on EGFI 128 l or EGFI 129 ensures proper flow to the RCPs. UE and KGE will revise their procedures accordingly.
Finding 6: Both utilities procedure step will be revised to read " minimum RHR pump flow which indicates injection into the RCS" readable on the indicator scale provided on EJFI-618 and EJFI-619 on RL-017.
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Finding 7: The associated pushbuttons used for the " emergency" mode are engraved " FAST CLOSE" and the associated pushbuttons used for
, the " normal" mode are engraved " SLOW OPEN" and " SLOW 4 CLOSE" to remind the operator of different valve response times.
No further action will be taken.
i Finding 8: CCW to RHR heat exchanger. flow indication is available locally and on the BOP CRT located in the control room. In addition, annunciators 51A and 53A alert the operator to HI LO CCW flow conditions and RHR inlet / outlet temperature indication across the heat .exchangers is available in the control room. No further action will be taken.
Finding 9: Annunciator 54F "CCW SEAL HX FLOW HILO" used in conjunc-1 tion with establishment of proper valve alignment will ensure adequate corrective action by the operator. Local flow indication is also available and adequate as the operator is not required to take any immediate actions. No further action will be taken.
Finding 10: Steamline radiation monitors are suggested as a means for .
detecting a steam generator tube rupture. The following may be used by SNUPPS operators to aid in determining a ruptured steam generator:
o Indication of blowdown radiation i
o Analysis of samp!es taken from steam generators o Unexpected rise in affected steam generator level o Indication of condenser offgas radiation o- Indication of radiation detected by PORV monitors (if dis-charging).
. No further action will be taken.
l Finding 11: Control room indicator is in inches. - Both utilities will revise their plant specific procedures to read this value in inches.
I After review of these responses, Essex Corporation feels that they are adequate to address the human factors issues raised by the findings discussed in paragraph 3.2
( Verification.
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APPENDIX I HUMAN ENGINEERING FINDING REPORTS
HUMAN ENGINEERING FINDING REPORT NO: 1 PLANT.UNITNolf creekDATE: 3/8/85 A . i sitz REVIEW NAME: Task Analysis Verification BIT Temperature Indication c) HEF TITLE:
b) ITEME INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheet 4 Information Category, BIT Temp'rature l
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l c) PROBLEM DESCRIPTION:
ECA 0.0, step 23 requires BIT Temperature indication in the control room. None is provided.
O C2MMENTS:
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HUMAN ENGINEERING FINDING REPORT Ns: 2 PLANT UNITpolf CreekDATE: 3/8/85 REVIEW NAME: Task Analysis Verifftation
- ! in Steam Line Pressure Instrumentation Graduations c) HEF TITLE:
b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheets 13 & Information Category AB PI 515A, 516A, 514A RLO26 25 AB PI 524A, 525A, 526A AB PI 534A, 535A, 536A AB PI 544A, 545A, 546A 1
l c) PROBLEM DESCRIPTION:
E-0, step, 13A and E-3, step 13A require main steam readings of 615 psig, however, I control room indicators are graduated in 20 psi increments. A reading of 615 psig could not, therefore, be read accurately.
I C C*iMMENTS:
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HUMAN ENGINEERING FINDING REPORT N!: 3 PLANT UNITFolf creekDATE: 3/8/85 REVIEW NAME: Task Analysis Verification ORIGINATOR: D. Pilsitz c) HEF TITLE: Main Steam Line Pressure Instrumentation Graduations b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheets 22 6 Information Category AB PI 515A, 516A, 514A RLO26 23 AB PI 524A, 525A, 526A AB PI 534A, 535A, 536A AB PI 544A, 545A, 546A l
l c) PR BLEM DESCRIPTION:
1 ERG's require plant setpoint settings of 615 psig, 1185 psig and 1235 psig to be read in the control room. Indicator graduations are presented in 20 psi increments.
l Q CCMMENTS:
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HUMAN ENGINEERING FINDING REPORT NO: 4 PLANT UNIT: Wolf creelOATE: 3/8/85 ORIGINATOR: D. Pilsitz REVIEW NAME: Task Analysis Verification Feedwater Isolation Reset c) HEF TITLE:
b) ITEMS INVOLVED:
l l TEM TYPE NOMENCLATURE LOCATION PANEL Sheet 39 Information Category SB-HS-17 RL018 SB-HS-18 I
c) PROBLEM DESCRIPTION:
FRH.1, steps 5 and 18 require an indication of feedwater isolation " reset". this indication is not provided on the main control boards.
d) CCMMENTS:
Cannot tell if signal is reset until operator attempts to operate valves.
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HUMAN ENGINEERING FINDING REPORT N7: 5 PLANT UNIT: Wolf Cree'CATE: 3/8/85 ORIGINATOR: D. Pilsitz REVIEW NAME: Task Analysis Verification a) HEF TITLE: CCW Flow to RCPs b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheet 255 Information Category EG FI 55A EG FI 128 EG FI 129 c) PROBLEM DESCRIPTION:
Plant specific requirement for CCW flow indication to the RCP's, identified in revision 0 of the KGE E0P's as 40 GP11, is not compatible with existing indicators on the main control boards. Existing indication is in FTPH units.
C; COMMENTS:
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HUMAN ENGINEERING FINDING REPORT l l
6 PLANT UNIT: W If CreekOATE: 3/8/85 N5:
REVIEW NAME: Task Analysis Verification RHR Pump Flow Indication Increments c) HEF TITLE:
b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheet 284 Information Category EJ-F1-618 RL017 EJ-FI-619 4
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C) PROBLEM DESCRIPTION:
KGE procedure E-1, step 13A requires operator action at greater than 535 GPM.
Control Room indication is in 100 GPM increments, therefore, this valve cannot be i read accurately.
O COMMENTS:
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HUMAN ENGINEERING FINDING REPORT N2: 7 PLANT. UNIT: Wolf cree 1@ ATE: 3/8/85 ATOR: D. Pilsitz REVIEW NAME: Task Analysis V lve Response Times c) HEF TITLE:
b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Information Category MSIV RLO26 AB HIS-11, 14, 17, 20 W Isolation Valves RLO26 AE HIS-39, 40, 41, 42 l
I c) PR!BLEM DESCRIPTION:
In the emergency mode (fast close), Main Steam Isolation Valves and Feedwater i Isolation Valves close in less than 5 seconds. In the normal mode (slow open/close) they close in approximately 5 minutes.
l d) CSMMENTS:
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HUMAN ENGINEERING FINDING REPORT N2: 8 PLANT UNITFolf CreekDATE: 3/8/85 Task Analysis ORIGINATOR: D. Pilsitz REVIEW NAME:
c) HEF TITLE: CCU Flow to RHR Heat Exchanaers b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheet (8) Information Cateogry C
c) PR38LEM DESCRIPTION:
FR-C.1, step C-lb, ERG Background document lists CCW to RHR heat exchanger flow indication as an instrumentation requirement. No instrument exists in the control room.
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d) COMMENTS:
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HUMAN ENGINEERING FINDING REPORT N2: 9 PLANT. UNIT.Molf CreekDATE: 3/8/85
. i sitz REVIEW NAME: Task Analysis c) HEF TITLE: CCR Flow to Seal Water Heat Exchanner l
b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Sheet (9) Information Category l
c) PR2BLEM DESCRIPTION:
ERG background documents for 8 ERG's lists CCW Flow to Seal Water Heat Exchanger as en information requirement. No meter is provided in the control room.
C COMMENTS:
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f HUMAN ENGINEERING FINDING REPORT l
NO: 10 PLANT UNIT: Wolf cree @ ATE: 3/8/85 REVIEW NAME: Task Analysis a) HEF TITLE:
Steam Line Radiation llonitors b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Information Category c) PROBLEM DESCRIPTION:
Background document for ERG-3, step 2 lists steamline radiation monitors as an ,
instrument requirement. None is provided at Wolf Creek.
NUREG-0700 (6.1.1.1.a) d) COMMENTS:
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HUMAN ENGINEERING FINDING REPORT i NO: 11 PLANT.UNITb'olf CreekDATE: 3/8/85 i
Task Analysis ORIGINATOR: D. Pilsitz REVIEW NAME:
Spent Fuel Pool Level Indication a) HEF TITLE:
b) ITEMS INVOLVED:
ITEM TYPE NOMENCLATURE LOCATION PANEL Information Category c) PROBLEM DESCRIPTION:
Wolf Creek procedure values for spent fuel pool level is expressed in units of feet.
Control room indication for spent fuel pool level does not read out in feet.
NUREG-0700 (6.5.1.lb) d) COMMENTS:
1-11
APPENDIX II I
DETAILED TASK ANALYSIS AND VERIFICATION PROCEDURE l
Attachment to SLNRC 85-11, 04/01/85 Procedure previously transmitted by SLNRC 84-121, 10/10/84 PROCEDURE FOR PERFORMING TASK ANALYSIS (AND VERIFICATION) FOR THE SNUPPS DETAILED CONTROL ROOM DESIGN REVIEW MARCH 1985 A
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., r TABLE OF CONTENTS t
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1.0 INTRODUCTION
1 2.0 PROCEDURE 2 3.0 INPUT DOCUMENTATION 9
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. APPENDICES A. FORMS
- 8. VERB LIST C. SYSTEM ABBREVIATIONS D. EXAMPLE l
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1.0 INTRODUCTION
The purpose of the Task Analysis is to identify action and information requirements necessary to perform selected tasks.
The SNUPPS Task Analysis is based on a subset of the West-inghouse Owners Group (WOG) Emergency Response Guidelines (ERGS), Revision 1 for the identification of operator tasks.
The review team assembled to carry out the task analysis will consist of utility engineering and operations personnel, members of the SNUPPS Staff, and the human factors consultant.
Action and information requirements are developed independent of existing control room instrumentation. These requirements are then compared against control room components and hardware to verify that required control and instrumentation are available and compatable with operator needs.
Any detected inconsistencies will be treated as findings and handled in a fashion similar to that described in the SNUPPS Summary Report. Findings, resolutions and an implementation schedule will be reported to the NRC in a closing report, scheduled for submittal in April 1985.
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2.0 PROCEDURE 2.1 General Instructions The task analysis procedure is a descriptive process which extracts generic operator action and information requirements from systems function data (as represented by the WOG ERGS), converts these requirements to a plant-specific level, and documents the results in an auditable, tabular format for use as an input into the verification process, paragraph 2.2.6. l These proceduras are organized into six major activ-ities whici are-
- 1. Develop a list of tasks from the WOG ERGS.
- 2. Generate a list of generic actions and information requirements for each task, organized by task for ERG's E-0, E-1, E-2, E-3, ECA-0.0, and all the Function Restoration Guidelines (FRGs).
- 3. Convert the generic list to a plant-specific list.
- 4. Reorganize the listing 50 that all action requirements of a given type and all information requirements of a given type are collected together. Type refers to a group of action or information requirements which all have the same system, plant component, and parameter (see detailed procedures, paragraph 2.2).
- 5. Summarize each action type and each information type in list form.
- 6. Compare the summary requirements to the existing con-trol room design.
2.2 Detailed Procedures l 2.2.1 Collect Materials Obtain a copy of the WOG ERGS, Revision 1 and the four-volume set of related background documents.
L 2.2.2 Complete Action-Information Requirements Details (AIRD) i Forms l
2.2.2.1 General - Fill out one AIRD form for each step identified from the ERGS as oetailed below.
Caution and note statements will be included I as appropriate. Implied tasks, such as to visually verify that a required action has i taken place, will also be included as appro-priate. Certain information, particularly plant-specific, technical specification defined 2
operating values, will not be available during this step. This information will be obtained when converting the generic AIRD forms to a plant-specific application. Fill in the appro-priate information on the AIRD forms sequentially, starting with the top area of the form first and completing the tabular information last. Number all AIRD forms sequentially. The following paragraphs explain each blank of the form.
2.2.2.2 Originator - Originator to enter his name ar today's date.
2.2.2.3 Reviewer - Reviewer to enter his name and today's date. The human f actors consultant will either be the Originator or Reviewer.
l 2.2.2.4 ERG Number - Enter the ERG number currently being analyzed.
2.2.2.5 Step Number and Objective - Enter the ERG step number and objective for the step currently being analyzed. Caution and note statements are considered as a separate step and should be numbered C# or Ne, respectively, where # repre-sents the next step number to be encountered.
2.2.2.6 Behavioral Elements - There is at least one task required for every step listed in the ERG's. The i tasks are divided into two categories: 1. " Action /
Expected Response," and 2. " Response Not Obtained".
The AIRD BEHAVIORAL ELEMENTS table separates these two categories of tasks by a horizontal dotted line, to be entered by the Originator.
Based upon the ERGS and their related background
! information, identify all behavioral elements for each task and list each element in the AIRD BEHAV-10RAL ELEMENTS table. A behavioral element is defined by the various behavioral and physical properties of an action requirement or an infonna-tion requirement. Each of the colisnn. entries are explained in detail below. Continue making addi-tional behavioral element entries until all elements for a task are listed, then proceed to the next task. Column entries for each element are:
- 1) Action. Number each substep as it appears with-in the ERG. Some substeps constitute a single task, other substeps are made up of more than one task.
l I
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- 2) Verb. Enter a verb from the verb list (in Appendix B) which best describes the required operator activity. This verb will either describe an action that must be performed or a method for acquiring information. Note that at this level of behavioral definition, a require-ment for an operator to direct someone else to perform an action is considered an action element. You may note in the comments column that an operator directs someone to perform this action, however, maintain strict compliance to the verb list for this column at this stage in the analysis. ,
- 3) System. Enter the abbreviation for the SNUPPS plant system for this element. System abbrevia-tions are listed in Appendix C.
- 4) Component / Equipment Number. Enter the plant compon-ent name for this element if applicable. If there is no identifiable component, enter NA. Do not enter any device, instrument, or control n ee.
Enter the component's associated equipment number.
- 5) Parameter. Enter the parameter name for this element. This will usually be a condition or characteristic of the system and/or component such as temperature, pressure, flow, level, amps, volts, watts, etc.
- 6) Direction. Enter the " condition" of the parameter which may include one of the following:
- 1. Increasing 3. Greater Than (or Equal to)
- 2. Decreasing 4. Less Than (or Equal to) l 7) State or Value. Enter any identifiable state or l
value for the parameter. States may include:
- 1. Stable 5. Off l 2. Open 6. Running I
- 3. Closed 7. Stopped
! 4. On l
Values may include either a discrete numeric value or a range of numeric values.
l 8) Units / Rate. Enter the units and/or rate for the parameter's state /value. Units will be defined by terms such as lbs, psig, in, degrees F, etc. Rate will be units per some time unit (e.g., pounds /sec).
l l 4 1
- 9) Precision. Enter the precision at which the infor-mation must be presented or the action must be taken. This will usually be a plus or minus value and unit. In general, the first attempt at deter-mining precision should~ utilize the following formula:
P = 0.5 A l Where P = Precision, and A = Instraent Channel Inaccuracy This formula is based on the conservative assep- '
tion that precision should be selected such that it will contribute to less than or equal to 12% of l the total inaccuracy.
- 10) Trending Required? Enter Y or N for "yes" or "no." Generally, if the verb used for this ele-ment is " monitor," trending would be required.
Also, for information verbs other than monitor which have response times in excess of one or two minutes and changes in rates, trencing may be required. If in doubt, enter Y with a question mark (?) as a f1ag.
- 11) Comments. Enter any clarifying information or questions, including operating characteristics required by the ERG. This column is also used to cross reference other systems / components (e.g.
SG level affected by Aux. Feeowater flow), indi-cate implicit verify's and explain exceptions to accepted rules from this procedure.
- 12) On AIRS Sh. No. Leave this colen blank. It l will be completed under paragraph 2.2.4.2 l
- 13) Repeat 1) through 12) for each behavioral element for each task.
2.2.3 Develop Plant-Specific AIRD Forms l Working with designated plant personnel, review all AIRD l forms and modify them to accurately reflect the plant-l specific parameters, values, ranges, units, rates, or other differences from the generic. Enter a brief, concise explanation for all identified plant-specific differences.
2.2.4 Complete Action-Information Requirements Summary (AIRS) Forms 2.2.4.1 General. AIRS forms are used to collect together all behavioral elements of a given type, independent of what ERG, ERG steps, or task they may appear in (i.e. this forms the basis for an instrument and con-trol specification).
5
Behavioral element types that are the same are definec as having the following characteristics:
- 1) Their verbs agree as to class, e.g., they are either action verbs or information verbs (their verbs may De different within verb class.).
- 2) Their system, component, and parameter are all the same.
- 3) All other distinguishing features may be different.
2.2.4.2 Transcribe Behavioral Elements onto AIRS Forms -
Begin transcribing the detailed information for the first behavioral element from the AIRD form to the AIRS from in the following manner:
- 1) Number the first sheet as one, and all subsequent l AIRS forms sequentially. From the first AIRD
+ sheet, enter onto the AIRS form in the INDIVIDUAL DETAILS table all the available information con-cerning the first behavioral element on the AIRD.
At this time, determine the requirements type from the element verb (on the AIRD) and enter that in the 50RT BLOCK of the AIRS form. Also '
transcribe (from the AIRD) the system, component, and parameter onto the AIRS SORT BLOCK. Leave the SUt91ARY OF REQUIREMENTS BLOCK and VERIFICATION
SUMMARY
BLOCK blank at this time. When you have completed the first behavioral element, transcribe the AIRS sheet number into the last column (On IRS Sh. No.) of the AIRD form in line with that task.
- 2) Searching sequentially through the AIRD t'acks, find the next behavioral element that is of the same type as the element that you just completed.
It is the same type if it has the same require-ments type (defined by the element verb class) ana the same system, component, ana parameter. Enter all available infonnation for this element into l the INDIVIDUAL DETAILS table of the AIRS form.
Transcribe the AIRS sheet number into the last
(
column of that AIRD form in line with that task.
- 3) Repeat the previous step until you have searched through all AIRD forms, then set that AIRS form aside.
- 4) Obtain a blank AIRS form and number it as the next sheet in the AIRS stack. Repeat steps 1) through l
- 3) for the next type of task. When all tasks on the AIRD forms have AIRS sheet numbers in the last l column of the table, transcribing the elements onto the AIRS forms is complete. File all AIRD forms.
l l 6
- 5) Alternatively, a computer program may be utili-zed to sort the AIRD information ano provide a printout of the resultant AIRS forms. In this case, the ERG number, step number and informa-tion provided by the Behavioral Elements woulo be entered into a computer data base. The com-puter would then sort the data entries using the following priorities:
1st Sort Requirements Type 2nd Sort System 3rd Sort Component 4th Sort Parameter The SUPEARY OF REQUIREMENTS BLOCK and VERIFICA-TION
SUMMARY
BLOCK will be completed later.
2.2.4.3 Summarize Behavioral Elements - For each AIRS form, the human factors consultant (Originator) should I summarize the behavioral element coltsnn entries for Value/ Range, Units / Rate, Precision, and Trending Required. Enter these summaries in the appropriate p1 aces in the AIRS
SUMMARY
OF REQUIREENTS BLOCK.
Also, complete the Response Time entry with appro-
, priate system or component response times, e.g. time required for a valve to close. When all AIRS forms have this block completed, this step is complete.
There should be no entries for the VERIFICATION SUM-MARY BLOCK on the AIRS form at this time.
l 2.2.5 Cross Check for Completeness Upon completion of the AIRS forms, the inventory of parameters to be observeo and/or controlled will be comparea to the inventory of instrumentation and controls developed by West-1 inghouse in its SRTA (System Review and Task Analysis) of the j basic version of the ERGS. This identified inventory differ-i ence will be cross compared at the task level, utilizing the l task interchangeability data supplied in the SRTA, to Revision l 1 of the ERGS. As a result of this comparison, a supplemental l analyses will be performed for (1) each plant parameter not l
already analyzed, (2) each type of task not already analyzed, l and (3) each parameter value not enveloped by values already included in the analyses. These supplemental analyses will be.
performed utilizing the AIRD form for the ERGS not previously analyzed. The results will then be transferred to the AIRS forms.
2.2.6 Verify Results Utilizing plant specific documentation, control room simu-lator, etc., complete the VERIFICATION
SUMMARY
BLOCK on each AIRS form by indicating the existing control room instrument or control identification number for that instrument which l
l 7
fulfills the action-information requirements listed. In some cases, more than one instrument may be used to satisfy l a set of requirements (e.g. wide ano narrow range pressure indicators). Enter the control boaro panel number to indicate the location for that instrument. Check the " Pass" column if existing instrumentation fulfills the action-
! information requirements or the " Fail" column if it ooes not.
In the case of " Fail", a Human Engineering Finoing (HEF) should be generated for future review by the DCRDR Review Te am.
A representative completing the verification should enter his name as the Reviewer, and todays date.
The human f actors consultant will review the results and enter his name and todays date as the Originator. This is done because it was also the human f actors consultant to sunmarize the behavioral elements (paragraph 2.2.4.3).
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3.0 INPUT DOCUMENTATION
- 1) Westinghouse Owners Group Emergency Response Guidelines and Back-ground Documentation, Revision 1.
- 2) SNUPPS Abbrevi ation List.
- 3) System Piping and Instrument Diagrams.
- 4) Final Safety Analysis Report.
- 5) Westinghouse Owners Group System Review and Task Analysis Documentation
- 6) Other plant-specific documentation, as appropriate.
4 l.
_._.7 .,--. .-. ,.- v-, , - --- -ce- - + - - --- 'rv v -' "~ ----- ' ' - - - ' ' ' '" ~ -" ~ ' - '" " '
s 4
s APPENDIX A- FORMS l
1 i
A-1
ACTION-INFORMATION REQUIREMENTS DETAILS (AIRD) sewet of COLF CREEK,SNUPPS PLANT: UNIT: ORIGINATOR: DATE:
REVIEWER: DATE:
, ERG NO:
j STEP NO:
j OTEP OBJECTIVE:
j REMARKS:
! BEHAVIORAL ELEMENTS i
v c=;=r [
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SHEET of_______
ACTION-INFORMATION REQUIREMENTS
SUMMARY
(AIRS)
PLANT: SNUPPS (WOLF CREEK) . ORIGINATOR: ____________DATE: ______
REVIEWER: ______________DATE: ______
! REOS TYPE: : VALUE/ RANGE: _________________ l
! SYSTEM: I : UNITS: _______________________ l l COMPONENT: : PRECISION: ___________________
l
! PARAMETER: : : RESPONSE TIME: _______________ l l --------------------------------- l l ------------------- -----------
REMARKS: i~~~~~~~VEkiFibdTibU~5U5EdRE~ELUCK~~~~~~~~~~i
- 1.
- See AIRD ! DEVICE ! :
! I.D. No ! PANEL ! BOM# ! PASS! FAIL!
! ! ! I ! !
- - ----- ---- --------== ---------------
--=___=
STATE / UNITS / TREND '
ERG STEP ACT VERB DIRECTION VALUE RATE PREC REO COMMENTS
..e I
O A-3
l 1
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APPENDIX B. VERB LIST B-1 4 _
SYSTEM FU4CTION APC TASK ANALYSIS APPENDIX B -
~
BEHAVIORAL ELEMENT VERB LIST.
V rb Appliestion ' Definition Observe Info.[ Req.
~ ~ ~
To attend visually to.the presence of or the status of an object, indicatism, or event. -
Rc d InfoIReq. To examine visually information .ielc6 :le presented symbolically.
Monitor Info. Req. .jo . visually ke' e p track of an' object, E. indication, or event over time.
....Y . . .
Scan Info. Req. .To quickly examine en information source to nebtain a general impression.
Det ct E Info. Req. To"be aware of.the presence or absence of a visus 1 stimulus.
Stcrt f. Cont. Req. To manuaily or verbally initiate a simple or complex function, event,'er activity.
Step ConL Req. To manually or verbally' terminate a simple or complex function, event, er activity.
Open dont1 Reg. "
To manually or verbally %itIhi"a aI'mple or complex function, event, or.;imetivity which ultimately results in a plant copt' or hplant components (e.g., valve. . ' breaker,
- ).demper, etc.) to assume en open state.
I Close Cont. Req. . To manually or verbally innlate a almple or l
complex .. function, event, or activity which ultimatelph.gesults in a plant component or plant" components (e.g., valve, breaker, denyer..etc.) to assume a closed state.
I Adjust '
Cont. Req. To manuatiIor verbally initiate a almple or complex functionjiiiewent or activity which ultimately tosults inlTi' plant component or plant componenta,lig, .si!! pl. ant condition,
, status, or dynamW to charsge Meta.
N ; ,,'.-
B-2
9 APPENDIX C. SYSTEM ABBREVIATIONS C-1
STSlEn NAnt AB MAIN STEAn SUPPLY SYSTEM.
AL MAIN TUkr1NE b f b ten.
AD CONDENSAIL SYSTEn.
AE FEEDWAIEK sidTEn.
AF FELDWA'lkk HLAIER EXTNACTION,DRAING AND VLNTS SYS.
Ah CONDENdATE DeM1NtKALittk SydrLn.
AL AUXILIAhY FELDW4 TEN SYSTEM.
AN DLMINtkALIZED WATER SIURAGE AND TRANSFER SYSTEM.
AP CONDLNUATE STUNHUE AND TRANdi'ER LY5 ten.
AG CONDENSATL AND F LEDWAlth LHEn1 CAL ADDITIuN SYSTEM.
BB RLALTOR COULANI btLILM.
BU LHEMICAL AND VULunt CONIRUL SYSTEM.
BL kLnLluk NAALUF WATER SYSTEM. '
bn SILAN ULNERAION BLOWDOWN SYGTEM.
BN BuhAsED hEFUCLING WATLR STORACE SYSTEM.
CA blEAM SEAL S r d TEM.
Le M41N IURDINL LUBE DIL SYSTEn.
LL ULNhAAIUN HrukubEN AND CARBuN DIOXIDE SYCTCM.
CD UtNENAIUR SLAL UIL SYLTCM.
LL blATUR Cuut1Nu WAILR SYSTEM.
CF LUBE UIL S TONALC,TRAN0FER AND f'URIFICATION SYG TCM.
C6 CONDENdtk Alk REMOVAL SYSILM.
CH MAIN TURBINL CONiRUL OIL SYSTEM.
CN DA LIRCULATING WATER SfSILM.
LA SERVICE WATEN SYSfEM.
EB CLOStD CoutlNU WAILR SfbiCM.
EC FUEL POOL CUOLINu AND CLLAN-UP SYSTEM.
EF EdblNilAL SLhVALE WAICR GrGTEn.
Eb CUMPONENT COULINu WHeth Sttltn.
LJ RESIDUAL HEAL NEMUVAL SYbiLM.
EM HIGH PRESSUht COULANI INJLLIION SYSlLM.
EN LUNIALNNENT SVRAY SYSTEM.
hP ACCUMULATOR SAFETY INJLL110N bfSTEn.
F4 AUril.1ANY blLAN ULNLRAiuN STCICn.
Fb AU41L1AkY bitAn Sfdttn.
FC AUX 1LIANT IUNPlNES.
FL AUAJL1ARY STEAN CHLMICAL ADDITION SYCTLM.
Fd GA PLANI HEATING SYSTEM.
GB CENlRAL CHILLED WATER SYSTEM.
GF MASCELLANLUUS BLDG HVAC.
GH kADWASTE BUILD 1Nu HVAC SYSTEM.
GA CONTROL BUILDING HVAC.
GL Aux 1LIARY BUILDING HVAC.
UM DIEEEL GENERATOR BUILDING VENTILATION.
UN CONTAINNENT LUULINU.
GP CONIAINMhNI INILGNAsED LEAN RATE TESTING SYSTEM.
Gk LONIAINMENI AIMubPHERL LONikUL SYSILM.
US LUNIALNnLN1 HfuhuuhN CONikOL SYSTEM.
Gl CUNTAINMENI PUkut.
HA UASEUUS RADWASTE SYSTEM.
HB LIQUID RADWASTE SYSTEM.
HC SOLID RADWASTE SYSTEM.
HD DECONTAMINATION SYSTEM.
ME BORON RECYCLE SYSTEM.c n - -
HF SECONDARY LIQUID WASTE SYSTEM.
JE EMERGENCY FUEL OIL SYSTEM.
KA CUMPkESSED AIR SYSTEM.-
AC FIRE PROTECTION SYSTEM.
KD DOMESTIC WATER SYCTEM.
KE FUEL STORACE, FUEL HANDLING 8 REACTUR SERV.SYGTCM.
MF CRANES, HOISTS, AND LLEVAluhd.
- KH SERVICE GAS SYSTEM.
AJ dTANDBY DIESEL ENGINE GrSTEM.
AS buLA CHEMICAL STORAGE AND llANDLING GYGTCM.
LA SANITARY DRAINACE SYSTCN.
LD CHLMICAL AND DETERGENT WASIE GrSTEM.
LE 01LY WASTE GYGTLM.
LF F LUUR AND EQUlf MLN T DRAINS Gf G fCM.
nA MAIN bbNCkATIUN br3TCM.
ns LxCIlAiION & VUL AGE HCCULAll0N bYGiEn.
MR GTARTUP TkANSFORnCR SYSTEn.
Ne LOWtk nEDIUM VULIAud SYbTCM.
NE STHNDB( GENENATUR CY C TEM.
NF LUAU SHEDDINO AND CMCRLLNCY LOAD GEGULNCING.
NU LOW VULIA6E (4UUVs GTLTCn.
NA 1MS-VOLT DL bfbikn.
NN INS t kunt.N I AU F0WLR SfSTLM 120 V.
PA HJbHEN MEDIUn VuLIAGE GYGTCn-13.uhV.
Pb LOWER MLD1Un VULIAGL (4.10AV) GTLfCM.
PG LUW VULTsut bYderd.
PJ JLUV DC btbidn.
PN INS ThunLtJ T AC l'LLLN GrCiCn.
Fu UNIN1thhUFi1DLL AL l'UWLR L f L i Ed.
UA N0hnAL Liuiti ING GT G TCn.
ue SimNDef LiuNeLNU GrLICn.
UU knkhbENCY LiuHilt4U bfGICd.
ut TELEPHUNE brLILN.
ut PUULAC AUDhLSL GYGiEn.
00 GNUUNDING S f S TEN.
GJ Hi.tEaE fkulECTION GYGTCM.
GN MISCLLLANEUUL EdOIPnCNT b(LTCM.
RD MLiEUh0 LOGICAL 1rJLTHUNCNT A T1un G r G ; Cn.
RJ BALANCE OF PLANI CUnPUTCR Gia:Ln.
RN PLAN T ANNUNCI A TON bYblCd.
i RL MAIN CONTNOL UUAND GYGfCn.
RM FNOCESS Lluu1U GanPLitJG G T GICn.
NP MISCELLANCuua L0t4 ThuL t'ArJCLG .
RR RT SAFETY A5btaanLN T CfGILn AND RADI0 ACTIVITY RELEASE INFORMATION SYSTE EMERGENCY RESPONSE FACILITY INFORMATION SYSTEM.
SA BOP ENGINELhED LAFLTY FCATURCG ACTUATION GYGTCM.
Sb NSbS Lbb AL fUATIUN AND HCAC TUR TkulLC TION G f L TCn. 1 SC ktACTOR IN3 s RuntNI A T1UN 3 rbiLM.
SD AhLA RADIAIIUN NUN 11UNiffG LTUTCM.
Sb EX-LUkt NEulhuN MUNilukING bfGICM. .
bF kkAtluk LisNINUL GYGTEM.
bb dE15n1C INSahunENTAI10N SYU1LM.
SJ NUCLEAR SAnFLINb & POSI ACCIDLN T GAMl LING CYGTEM.
SK POWER BLOCA SECUR11f bYSTEM.
SP PROCEGS AND EF FLudN T RADI A f10N nUNITORING GYGTCM.
Su LOOSE PARIS MONIIURING SYSTEM.
.Sk IN-CORE NEU TRON MON A TORING GYGTEM.
2.s
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APPENDIX D. EXAMPLE i
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ACTION INFERMATION escOUIRECENTS DETAILS (AIRD) Sheet of 2A-WOLF CREEK,SNUPPS UNIT:
PLANT: ORIGINATOR: DATE:
REVIEWER: DATE:
ERG NO: E .f CTEP NO- 2 STEP OBJECinVE: [kcM o f S G s a r e. no V f r l fe d FINAL GENERIC AND PLANT SPECifl0 RESSARKS:
BEHAVIORAL ELEMENTS v S E c *C E g voet d
f c ;_ ; - Parenooter D6eection
[ [ .[ [ Comments Ey T Equepsssent No g [ c d4 G- O bsetw c- AB *2G s Dec casiao 0 - l (47 0 lO 9 e e_ ss fSl{ T E BB oin, %,c ,b tiels.lLI}
O bse** A6 S*C'5 pe e. s s oc p.,5- m o ep go p4 EBB o t A.B.c.D urited G ObSetWC AS MStVs 9o5 C*5 ~ ~ ~ ~
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W- _ , _ - . _ _ . _ _ _ . . .__ ___ ____ _ _
l (Continusd)
SHEET 101 of_______
ACTION-INFORMATION REQUIREMENTS
SUMMARY
(AIRS)
PLANT: SNUPPS (WOLF CREEK) ORIGIN 4 TOR: ______[______DATE: , _ , ,
REVIEWER: ______________DATE: _ _ _ , , _ _
____________ggg;_g_ggp___________7 7_g ;_g _gg_ggg 7KEP 7g- _ 7 T l REOS TYPE: Infa : VA UE/ RANGE: ____Q _1 top _____ :
- l. SYSTEM: BB : : UNITS: _, _ _ _ _ _ _ _ _ ,_ n g,, _ _ _ ,, ._ ,_ _ _ !
! COMPONENT: RCS : ; PRECISION: _ _ , _ _ _ _2 [_ _ _ _ _ _ _ :
- PARAMETER: FRS : : RESPONSE TIME: _ _ _,}{f A _ _ _ _ _ _ _ l REMARKS: i~~~-~VEkiF5CETIbk~SbM5ARY~ELbCE~~~~~~ ~~I
- 1.
- See AIRD ! DEVICE i i :
l I.D. No l PANEL I BOM# ! PAS $!8~ AIL:
. ! E6 P1 M h"> . 4 W AO '
! ?Y : !
1 i ! ?
! l . l
! l l INDIVIDUAL DETAILS STATE / UNITS / TREND ERG STEP ACT VERB DIRECTION VALUE RATE FREC PED COMMENTS FR-I.3 6 B OSS 1800 FSIG 25 N FR-H.1 18 G OBS < 1920 PSIG 25 N FR-H.1 7 A OBS 1920 PSIG 25 N E-0 35 . MON < 250 PSIG 25 N FR-C.2 2 C OBS < 250 PSIG 25 N E-1 C9 . MON 250 FSIG 25 N FR-C.3 2 C OBS , 250 PSIG 25 N E-0 15 D OBS < 250 PSIG 25 N E-3 12 . MON < 250 PSIGWR 25 N E-3 17 B OBS < RUP SG FSIGWR -
N
- FR-P.1 C3 . OBS <. SETFNT PSIG -
N E-1 1 B OBS < [13503 PSIG 25 N E-3 1 B OBS . [t3503 PSIG 25 N E-0 21 B OBS < 13503 PSIG 25 N
- E-0 15 B OBS s [17003 PSIG 25 N FR-1.3 6 B OBS < C18003 PSIG 25 N E-1 C9 . MON < [2503 PSIG 25 N E-3 12 . MON < C2503 FSIGWR 25 N FR-C.2 2 C OBS < [2503 PSIG 25 N FR-C.3 2 C OBS < E2503 PSIG 25 N -
, E-0 15 D OBS -
C2503 PSIG 25 N FR-H.1 1 A 095 > -
PSIG 25 N
- FR-I.1 4 A OBS > 100 PSIG 25 N E-0 35 A OBS ? 250 PSIG 25 N E-1 9 A OBS > 250 PSIG 25 N E-1 13 A OBS > 250 PSIG 25 N E-! 12 A 085 -
250 PSIG 25 'N E-1 9 A 085 C2503 PSIG 25 N E-3 12 A MON > C2503 PSIG 25 N E-1 13 A 095 / C2503 PSIG 25 N FR-P.1 3 A OBS AND 2400 PSIG 25 N
- E-3 25 A OBS BETWEEN 0-3000 PSIG 25 N
- FR-I.O 6 A OBS BETWEEN 0-3000 PSI 25 N
- FR-I.3 9 A OBS BETWEEN 0-3000 PSIG 25 N ,
FR-1.3 18 OBS BETWEEN 0-3000 PSIG 25 N
- D-5
(Continued)
SHEET 102 cf_______
ACTION-INFORMATION REQUIREMENTS SUMMARv tAIRS)
PLANT: SNUPPS (WOLF CREEK) ORIGINATOR: DATE:
REVIEWER: _______________DATE: ______
I SOhT BLOCL ! EUMMARV OF REOL61 r4EMENT S b OCr. .
REOS TYPE: Info l i VALUE/ RANGE: _____q;jf_l?_,___ '
i SYSTEM: BB : i UNITS: _ _ _ _ _ _ _ _ _ _ f1Li _,f,f!6.W. d !
! COMPONENT: RCS i : PRECISION: ________I_'________,, l l FAPAMETER: PRS ! ; FESPONSE TIME: ____S /6---_.
- e----------.--.-------.---..------*
REMARKS: : VERIFICATION SUMW( t LLOO :
L F,'/ I LE
- 1.
- See AIRD _ . , _ _
l_ _ , , , _ l ._ L . No : CANEL
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~
/ I I
INDIVIDUAL DETAILS STATE / UNITS / TREND ERG STEP ACT VERB DIRECTION VALUE PATE PREC REO COMMENTS E-3 35 A OBS BETWEEN 0-3000 PSIG 25 N
- FR-I.3 19 9 OBS BETWEEN 0-3000 PSIG 25 N
- E-3 16 A OBS BETWEEN 0-3000 PSIG 25 N
- FR-P.1 5 . OBS BETWEEN 0-3000 FSIG 25 N
- E-3 17 B OBS BETWEEN 0-3000 PSIG 25 N
- E-3 18 B OBS BETWEEN 0-3000 FSIG 25 N
- FR-P.1 12 A OBS BETWEEN 0-2000 PSIG 25 N
- E-3 20 A OBS BETWEEN 0-3000 PSIG 25 N
- FR-P.1 3 A OBS BETWEEN L30- PSIG 25 N
- FR-H.1 19 F OBE DECREAS - - -
N E-3 29 9 OBS DECREAS -
PSIGWR -
Y E-3 29 B OBS DECREAS -
PSIGWR -
Y E-3 29 B OBS 2ECREAS -
PSIGWR -
Y FR-H.1 7 A OBS DECREAS -
PSIG -
N FR-I.3 18 OBS DECREAS 200 PSIG 25 Y t FR-I.3 19 B OBS DECREAS 200 PSIG 25 Y FR-P.1 21 A OBS INCREAS -
PSIG -
N E-3 29 B 085 INCREAS -
PSIG -
N FR-I.3 20 OBS INCREAS -
FSIG 25 i +
E-3 19 A 085 INCREAS -
PSIGWR -
N FR-I.3 6 C OBS INCREAS 50 PSI 25 N E-1 6 C MON STA/INC -
PSIG -
Y E-O 25 C MON STA/INC -
PSIG -
Y E-3 20 C OBS STA/INC -
PSIGWR - N E-1 6 D OBS STABLE -
PSIG ,
N I FR-P.1 23 B OBS STABLE -
PSIG - N E-O 25 D 095 STABLE -
PSIG - N I FR-P.1 23 B 055 W/IN LM -
PSIG 25 N
- FR-P.2 3 OBS W/IN LM -
PSIG 25 N
- D-6