ML20209G870
| ML20209G870 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/31/1987 |
| From: | NEBRASKA PUBLIC POWER DISTRICT |
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| Shared Package | |
| ML20209G869 | List: |
| References | |
| TAC-64721, NUDOCS 8702050479 | |
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SUMMARY
(G This report summarizes the work performedoon the Cooper Nuclear Station (CNS) Detailed Control Room Design Review (DCRDR) from the time the supplement to the summary report was issued (February 1986). This report addresses the concerns of the NRC (and of their consultants from the Lawrence Livermore National Laboratory) resulting from their review of the supplement report and their preimplementation audit of the DCRDR program in May 1986. This report focuses on the following tasks that have been completed. o Survey of operators communications while wearing self-contained breathing apparatus, o Survey of the human factors and technical consistency of the SPDS against the control room panel information and the EOPs. o Selection of design improvements as they relate to updating CNS Human Factors Standards and finalizing the design modifications of the annunciator warning system. o Documentation of the preimplementation and (7-)
,) postimplementation verification activities used in the review of the DCRDR design modifications.
o Establishment of a DCRDR training program for the operators and Shift Technical Advisors (STAS) to provide the necessary training on the DCRDR improvements, o Implementation of the DCRDR enhancements and modifications that have been completed by the end of the 1986 refueling outage and providing a schedule for implementing the remaining corrections. Details of these items and other related tasks are identified in this report. l NPPD has attempted to satisfy the DCRDR program requiremants and meet the NRC concerns in a manner that ensures plant safety, work quality and smooth plant operation. With the exception of the annunciator warning system Human Engineering Discrepancies (HEDs), NPPD developed resolutions j and detailed designs for the HEDs of six (6) panels and implemented these corrections in the 1986 refueling outage. NPPD, in accordance with CNS DCRDR schedule, is planning to develop and implement the necessary design corrections g scheduled in the 1988 refueling outage (February to March 1988). The results of the enhancements and modifications, 11 5
completed by the end of the 1988 refueling outage will be O reported to the NRC sixty (60) days following the 1988 outage, in a DCRDR supplement report. The results of other DCRDR tasks that are underway or planned in 1987, as described in various sections of this report, will also be included in the 1988 supplementary report. 4 e I h f O i e I f i j 1 i 111 i
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INTRODUCTION ([ In reponse to the NRC action plan resulting from the TMI-2 accident (Ref. .1), and the follow-up clarifications of NUREG-0737, Supplement 1 (Ref. 2), NPPD has submitted its ~ plan (Ref. 3) for implementing NUREG-0737 related programs. 4 In'accordance with the implementation schedule for the , DCRDR, NPPD submitted the Cooper program plan for conducting
- ' the DCRDR (Ref. 4). The DCRDR program plan described the methodology and documentation the District intended to follow to meet the NRC guidelines of references 5, 6 and 7.
The NRC approval of NPPD's program plan was received in June 1984 (Ref. 8). On November 27-29, 1984, the NRC staff and contractor personnel from Lawrence Livermore National Laboraty (LLNL) conducted an on-site in-progress audit of the CNS DCRDR (Ref. 9). A CNS DCRDR Summary Report was issued, as scheduled, in February 1985 (Ref. 10). i The NRC review of the CNS DCRDR Summary Report and the Technical Evaluation Report-(TER) provided by the NRC contractors (Ref. 11 and 12) were issued in September 1985. A number of concerns and recommendations were identified in O these reports. In a letter to the NRC staff, dated April 1985 (Ref. 13), NPPD stated that a summary report supplement addressing NRC conerns of References 9, 11 and 12 would be issued by February 1986. By letter from NPPD to the'NRC, dated February 27, 1986, NPPD submitted their supplement to the summary report (Ref. 14). This supplement addressed each of the issues raised in references 9, 11 and 12, and NPPD plans for resolving these issues. The overall schedule for implementing the design ~F corrections for CNS Human Engineering Discrepancies was . included in this supplement. , On May 13-16, 1986, the NRC staff and their contractors from the LLNL conducted an on-site preimplementation audit of the 1 CNS DCRDR. NPPD DCRDR activities and the associated reporting requirements were discussed with the staff during 4 the audit. In the concluding remarks that followed this audit, the NRC staff indicated that the NPPD DCRDR program has generally satisfied the requirements. However, several t concerns remained. These concerns and NRC review of the . DCRDR program were sent to the district in the NRC letter of November 4, 1986 (Ref. 15), together with the attached LLNL Technical Evaluation Report dated September 29, 1986.
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A second supplement to the summary report, addressing the O' staff concerns of reference 15, is to be submitted by NPPD on January 31, 1987. NPPD plans for DCRDR related modifications to the Cooper control room during the 1986 refueling outage need not be impacted by the submittal of this supplemental report. This report provides the documentation of the DCRDR work performed by NPPD during the year 1986, that: (1) addresses the NRC concerns of reference 15, and (2) provides the DCRDR results that have been achieved since the date of issue of the DCRDR supplement to the summary report of February 1986. v
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/"T - TABLE OF CONTENTS U
Section Page INTRODUCTION iv
- l. DCRDR REVIEW TEAM 1
- 2. FUNCTION AND TASK ANALYSIS (F&TA) 3
- 3. COMPARISON OF DISPLAY AND CONTROL 5 REQUIREMENTS WITH CONTROL ROOM INVENTORY
- 4. CONTROL ROOM SURVEY 6 4.1 Survey of Operators Abilities 6 to Communicate While Wearing Self Contained Breathing Apparatus (SCBA) 4.2 Survey of the Safety Parameter 8 Display System (SPDS)/ Plant Management Information System (FMIS)
() 5. ASSESSMENT OF HEDs 10
- 6. SELECTION OF DESIGN IMPROVEMENTS 11 6.1 Upgrade of Control Room Design 11 Standards 6.2 Design Improvements of Ongoing DCRDR 12 Activities 6.3 Design Improvements of Annunciator 16 Warning System HEDs
- 7. VERIFICATION OF DESIGN CORRECTIONS 23 7.1 Preimplementation Verification 23 Activities 7.2 Postimplementation Verification 24 (Validation) Activities O
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- _ , . - _ . _ _ - _ _ . . . . . , _ _ - - _ _ - _ - , . _ - _ - . , _ . . . . . _ _ . _ . . - _ _ - _ _ , . . _ _ . - , . ~ . .,. __ ._..._ _
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TABLE OF CONTENTS (continued) Section Page
- 8. COORDINATION OF CONTROL ROOM IMPROVEMENTS 26 WITH CHANGES FROM OTHER PROGRAMS 8.1 Operator Training Relating to DCRDR 26 Control Room Modifications 8.2 Operator Training HEDs and 30 Corrective Actions
- 9. OTHER DCRDR ACTIVITIES 31 9.1 Operator. Experience Review of 31 Other Plants
- 10. DCRDR RESULTS 32 10.1 DCRDR Enhancements and Modifice.tions 32 Completed by End of 1986 Refueling Outage 10.1.1 VBD-S Implemented Enhancements 36 O and Modifications 10.1.2 VBD-J Implemented Enhancements 39 and Modifications 10.1.3 Panel 9-3 Implemented Enhancements 41 and Modifications 10.1.4 Panel 9-4 Implemented Enhancements 45 and Modifications 10.1.5 Panel 9-5 Implemented Enhancements 48 and Modifications 10.1.6 VBD-R Implemented Enhancements 52 Modifications 10.2 Planned DCRDR Corrections & Schedule 55
! 11. REFERENCES 63 l O vii
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v APPENDIX A. SAFETY PARAMETER DISPLAY SYSTEM (SPDS) HEDs B. ADDENDUM TO CNS CONTROL ROOM HUMAN FACTORS ENGINEERING (HFE) STANDARDS C. MULTI-INPUT ALARMS IDENTIFICATION AND PRIORITIZATION D. DCRDR VALIDATION CHECKLIST i l- E. DCRDR OPERATOR TRAINING LESSON PLAN AND PARTICIPANTS f' HANDOUT F. IMPLEMENTED CORRECTIONS BY END OF 1986 REFUELING OUTAGE G. HED CORRECTIONS & SCHEDULE i H. CROSS REFERENCE SER/TER TO SUPPLEMENT II i O I
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i I i r i i I viii l i i
t 1.0 DCRDR REVIEW TEAM l NPPD, in performing the DCRDR tasks identified in various sections of this report, has maintained the same DCRDR personnel structure as stated in the supplement to the summary report (Ref. 14). The existing DCRDR program structure and personnel are noted in Figure 1.1. The teams are structured as follows: A. DCRDR core team under the direction of the CNS Operations Manager, with the following responsibilities:
- HED identification and assessment Resolution of enhancements / modifications
- Development of integrated conceptual drawings
- Verification and validation of HED corrections
- Development of training plan on HED corrections and conducting the DCRDR training B. Engineering / Implementation Team under the direction of the DCRDR Program Manager, with the following responsibilities:
- Detailed design engineering of HED corrections
( - Development and updating of control panel drawings Development of implementation plan and schedule
- Implementation of HED corrections C. Supporting Personnel Personnel with specialities in Licensing, Training, Computer Support. I&C Engineering and NUREG-0737 Program Integration provide the necessary support to the DCRDR core team and the engineering / implementation team.
The DCRDR team personnel interface,on a regular basis. A formal meeting is held in the 1st or 2nd week of each month at Cooper Nuclear Station. 1 I - 1-j
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FIGURE 1.1 A (/ DCRDR PROGRAM STRUCTURE AND PERSONNEL PROGRAM MANAGER PROGRAM MANAGER Operations /Enchancements Engineering / Implementation R. Brungardt R. Boyle ASSISTANT PROGRAM NUCLEAR ENG CONTRACT MANAGER DEPT SUPPORT SUPPORT M. Sparr/ S. McClure Black & Veatch D. Bnmer Engineering I J. Hackney M. Parr (Electrical (I&C Eng) Engineering) CORE REVIEW TEAM () R. Brungardt (Operations Manager /SRO) M. Sparr (Assistant to Operations Mgr) J. Peaslee (Surveillance Coordinator /SRO) M. Parr (I&C Engineering) H. Jantzen (I&C Supervisor) R. Krause (Operations Engineering) D. Brmer (Operations Support Supervisor /SRO) R. Black (Operations Supervisor /SRO) M. Aburomia-GE (System Engineer) J. Seminara (Human Factors Specialist) Other SRO/ROs as needed SUPPORTING PERSONNEL R. Boyle (Senior Staff Engineer) K. Walden (Licensing Manager) M. Boyce (Licensing Engineer) E. Hummel (Operations Enuineer) C. Goebel (computers Anolications Su[urvisor) R. Jansky (Operations Training Supervisor) S. McClure (Nuclear Engineering Manager) J. Meacham (Senior Manager of Technical Support Services) () S. Dua-GE (Plant Analysis Services Manager) J 2. (^}
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FUNCTION AND TASK ANALYSIS (F&TA) The NPPD process for the F&TA was reported to the NRC in the DCRDR Summary Report (Ref. 10). The process was applied to CNS plant specific Emergency Operating Procedures (EOPs), and the results were included in Reference 10. At the time this analysis was performed, Rev. O of the E0Ps (dated 4/6/84) was used. The NRC, in their in-progress audit of the DCRDR program, discussed the methodology and accepted the F&TA results (Ref. 9). The CNS E0Ps were revised subsequent to the original F&TA and prior to being implemented in September 1985. The F&TA was subsequently updated to Rev. 1 of the E0Ps dated August 1985, and the results of this updated F&TA were discussed < with the NRC during their pre-implementation audit (Ref. 15). A total number of 77 HEDs resulting from the F&TA were included in Appendix E of Reference 14. NPPD is continuing with their commitment to complete the items remaining from the F&TA, and address the NRC concerns of Reference 15, as follows: 2.1 F&TA on Other Procedures Implicitly Referenced in the E0P's () Normal plant procedures referenced in the E0Ps constitute mostly system operational procedures (16 procedures) in addition to four normal shutdown procedures and two abnormal procedures. F&TA on the systems operational procedures was j performed in the original analysis reported in the summary report (Ref.10) as an integral part of the F&TA on the E0Ps. Operator steps relating to the use of plant systems during emergencies were listed in the task analysis sheets, and j were subjected to F&TA as the E0P steps. For the remaining procedures referenced in the E0Ps, the
- F&TA is presently being conducted with an expected i completion date of June 1987. The results of this activity will be reported to the NRC in the next supplement to the summary report.
l 2.2 F&TA For Alternate Shutdown Panel (ASP) and Station Blackout Procedures l At the time of the writing of this report, ASP procedures had not been approved. F6TA on the ASP procedures will be performed before September 1987. Station blackout of the Cooper Nuclear Station is presently under investigation and is to be followed by procedure writing. F&TA on station blackout procedures will be O' completed 60 days following the approval of these procedures.
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a 2.3 F&TA On Existing Emergency Procedures (EP) (J') F&TA on the Emergency Procedures is in progress. Priority is being given to those procedures expected to be unaffected by the development of the station blackout procedures. Results of the F&TA on EPs will be reported in the next supplement report.
;2 . 4 F&TA On Revised EOPs As noted previously, the F&TA was performed on Rev. 1 of the E0Ps, which was implemented in September 1985. Following the issue of any significant revision to the E0Ps, the F&TA will be reviewed to demonstrate that the analysis is still applicable.
O 4 4 4 I)# 3. COMPARISON OF DISPLAY AND CONTROL REQUIREMENTS WITH CONTROL ROOM INVENTORY NPPD F&TA methodology in comparing the display and control requirements with the control room inventory has been described in References 10 and 14, and was discussed with the NRC staff during their preimplementation audit (Ref. 15). The methodology is based on the DCRDR team performing a walk-through of the control room panels and documenting the displays and controls inventory and their characteristics that are available to meet the operator steps in the E0Ps. Comparison of the instrument requirements against the control room inventory resulted in the F&TA HEDs that have been documented in Reference 14. i NPPD will continue to utilize the same methodology in completing the remaining F&TA on those procedures noted in Section 2 above. The results of this task will be reported on the same schedule as items 2.1 to 2.4 described previously. O O E CONTROL ROOM SURVEY i ( 4. 4.1 Survey of Operators Abilities to Communicate While Wearing Self Contained Breathing Apparatus (SCBA) During the NRC on-site audit of the CNS DCRDR program (Ref. 15), the NRC auditors expressed their concern regarding the schedule for the survey of communciations while wearing SCBA. NPPD committed to expediting this survey, and including the survey 4 results in Supplement II of the CNS DCRDR report. On June 24, 1986, the DCRDR team performed this survey in the Cooper control room. Operators were asked to wear the SCBA that l are available in the control room, and operator-to-operator-communications and operator use of the control room communication equipment were observed by the team. The team noted that the 1 operator's ability to communicate is considerably reduced, because the SCBA interferes with oral communication and is not equipped with voice diaphragas. In conformance with the DCRDR program identifying and documenting the human engineering discrepancies (HEDs) in the control room, this discrepancy has been documented and an HED sheet was completed as noted in the
. HED Record Number 621 below.
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- COOPER NUCLEAR STATION 01/14/87 DETAILED CONTROL ROOM DESIGN REVIEW HED3 i
R: cord No. 621 ED NO: 3525S ESCRIPTION: DIFFICULTY IN VOICE COMMUNICATION AMONG OPERATORS WEARING PROTECTIVE GEAR. HED SOURCE: CR SURVEY CRS CHECKLIST: N/A PEF: _ N/A HUMAN FACTOR TOPIC: COMMUNICATIONS NUREG-0700 SECTION: 6.2.1.8 (SEE COMMENTS) PANEL ID: N/A RELATED SYSTEM (S): PROTECTIVE CLOTHING SUBSYSTEM: COMMUNICATION EQUIPMENT COMPONENT ID: HEADSETS te VOICE DIAPHRAGMS IMPLEMENTATION ACTION: FIX TYPE OF CORRECTION: DESIGN MOD. PRIORITY OF MODIFICATION: II SCHEDULE FOR IMPLEMENTATION: 1988 REFUELING
REFERENCES:
HED RESOLUTION: REVIEW THE DESIGN OF EXISTING
~s PROTECTIVE GEAR FOR THE PURPOSE OF
' INSTALLING HEADSETS AND VOICE
' DIAPHRAGMS. PURCHASE NEW EQUIPMENT IF EXISTING EQUIPMENT CANNOT ME MODIFIED.
VERIFICATION NEW HED7 Y/N: IMPLEMENTATION DATE: VALIDATION: MISC / COMMENTS: EMERGENCY FACE MASKS SHOULD DE EQUIPPED WITH DIAPHRAGMS THAT ARE SPECIALLY DESIGNED TO TRANSMIT SPEECH. THE DIAPHRAGMS SHOULD DE ADLE TO SEPARATE VOICE FROM EXHAUST VALVE ACTION. / _ _ ._ - . _ - - _ _ _ . _ . ~ _ . _ . . _ _ _ . - _ 4.2 Survey of the Safety Parameter Display System (SPDS)/
' - ' Plant Management Information System (PMIS)
The SPDS/PMIS was developed for NPPD (Ref. 16) by Science Applications International Corporation (SAIC). SAIC prepared
; human factors plans for both the SPDS and PMIS (Ref. 17), which were used as templates to cover all human factors efforts i performed over the course of the SPDS/PMIS project.
The human factors plan for the SPDS was developed to follow the requirements for SPDS as contained in NUREG 0737, Supplement 1. , This human factors plan has as its emphasis, that the SPDS - displays the appropriate information required by the operational ;
; personnel and that the information is displayed in a manner.that.
allows the man-machine interfaces to work in a smooth and efficient manner. i The human factors plan for PMIS was developed to address both: 1 (1) the human factors principles to be used during the i development of display formats provided with the PMIS and (2) the methodology to be used for performing a human factors review of
, all generic displays and control of the PMIS.
1 { SAIC, as part of the human factor plans for the SPDS and PMIS,
- developed human factors engineering guidelines based on NUREG 0700. These guidelines were used during both the design and
! testing phases of the SPDS/PMIS. < 1 l NPPD, in their supplement to the summary report (Section 4 of
- Ref. 14), committed to perform a Human Factors Engineering (HFE) survey of the as-built SPDS displays. The NRC during their on-site preimplementation audit of the DCRDR program (Ref. 15) requested that NPPD survey the entire PMIS/SPDS against accepted human factors engineering standards. This survey is to ensure
- consistency of the SPDS/PMIS displays with the control room boards and the E0Ps. NPPD has therefore taken the following
{ actions: i- ! A. Secure SAIC to perform a post-development review of the SPDS ]' displays. A compliance checklist based on NUREG-0700 was used to perform this review. This evaluation (Ref. 18) was conducted by SAIC and NPPD personnel and consisted of the following: l
- 1. The " Compliance Checklist" forms in the " Human Factors Plan" (Ref. 17) were used to direct the review to the j proper sections of the " Human Factors Plan" (HFP).
l 2. The recommended guidelines in the appropriate sections
- of the HFP were then compared against each SPDS i
i () display. '
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' /~T 3. Results of these comparisons were documented using the
(_/ " Compliance Checklist" forms.
- 4. Discrepancies and deviations were further noted and explained, as needed, using the "Non-Compliance Explanation" forms,.also-from the HFP.
Human Engineering Discrepancies (HEDs) were created from the discrepancies resulting from the evaluation. These HEDs and a copy of the SAIC compliance checklist are contained in Appendix A. B. Perform HF and technical review of the consistency of the SPDS displays against CNS HFE Standards, control board information and the E0Ps. This task has been conducted by the DCRDR team members (Ref. 19). A consistency checklist (using NUREG-0700 and NUREG-0835 as guidelines) was developed and used during this evaluation and discrepancies were documented. HEDs were created from the evaluation discrepancies and are contained in Appendix A as well as a copy of the consistency checklist. The PMIS displays were not reviewed and e';aluated at the time of. the SPDS consistency check evaluation. NPPD plans to review and evaluate the PMIS displays following the addition of the new software and associated displays relating to class "A" dose O- assessment model (to be completed by Dames & More in 1987). This review is to ensure human factors engineering principles were adhered to and consistency with the control room panels and Emergency Operating Procedures is maintained. Subsequent to the review and evaluation of the PMIS displays, NPPD will conduct a walkthrough of the E0Ps to check usability of the SPDS and PMIS in conjunction with control boards. Results of the PMIS review and evaluation and the walkthrough of the E0Ps will be~ reported in the DCRDR Supplement III to the Summary Report, to be submitted following the 1988 Refueling Outage. Regarding the HEDs resulting from the two evaluations conducted on the SPDS displays, many of the discrepancies have previously surfaced in the ongoing internal critique of SPDS and through the E0Ps integration. NPPD believes that although a number of discrepancies were identified in the SPDS evaluations, the SPDS/PMIS remains a viable and useful tool for control room operators. I \ I i 9-
- 5. ASSESSMENT OF HEDs The NPPD Human Engineering Discrepancy (HED) assessment process has been described in the DCRDR Summary Report (Ref.
10). The application of this process to the assessment of the HEDs resulting from the F&TA, control room survey and the operating experience review has been included in the supplement to the summary report (Ref. 14). -The NRC has reviewed and approved the DCRDR assessment process (Ref. 12). With the exception of a few HEDs that were assesed to be of low safety significance and required reassessment, NPPD overall assessment of HEDs with respect to safety significance has been accepted (Ref. 15). NPPD is planning [ to continue the same process with any new HEDs that will be identified throughout this program. The results of the assessment of those HEDs referenced in various sections of this report that have been reassessed or newly identified are: A. The inability of the operators to communicate while wearing self-contained breathing apparatus (Section 4.1) was assessed to be of safety-significance. ( Correction will be made to modify the existing equipment or purchase new equipment by the 1988 refueling outage. B. The discrepancies resulting from the human factors and technical review of the consistency of the SPDS against control room information and the E0Ps (Section 4.2) are assessed as noted in Appendix A. Those items that need further assessment together with the PMIS survey will be completed in 1987, and the results will be reported in the 1988 supplement to the summary report. C. The presence of many multi-input alarms in the control room and their lack of reflashing capability (Section 6.3) has been assessed for safety significance. Action will be taken to correct priority "1" multi-input alarms during the 1988 refueling outage. Other discrepancies related to the annunciator warning system will be corrected as detailed in Section 6.3 of this report. O 10 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
(~} 6. DESIGN IMPROVEMENTS
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6.1 Upgrade of CNS Control Room Human Factors Engineering Standards and Imglementation Guidelines Revision "0" of the subject document, issued August 1985, represents a first cut at standards and guidelines that served as the basis for the CNS control. room enhancement efforts. It was anticipated that as enhancement design and implementation experience were acquired, the subject document would need to be refined and elaborated. A revision of the present guidelines, that will take advantage of our recently acquired enhancement implementation experience (October-December 1986) is scheduled during the year of 1987. Revision 1 of the guidelines will serve as the basic guidance document for the ongoing enhancement design effort scheduled for the 1988 refueling outage. Appendix A of the Lawrence Livermore National Laboratory Technical Evaluation Report, dated September 29, 1986 (Ref. 15), listed concerns related to Revision 0 of the subject standards and guidelines. Appendix B of this document indicates modifications to the CNS standards that address the concerns that have been raised. O i O
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~h 6.2 Design Improvements of Ongoing DCRDR Activities (G
The NPPD process for developing design improvements for the ongoing DCRDR activities continues to follow the design improvement procedures noted in Section 6 of the supplement to the summary report (Ref. 14). Referring to the DCRDR organization chart of Figure 1.1, Section 1, the core team and the engineering / implementation team function as follows: A. The core team reviews the list of HEDs and their intended resolutions, develops the necessary enhancements in terms of demarcation lines, mimics, meter banding, labeling, color coding, etc., rearranges the placement of controls and indicators to meet the HF standards, and locates the new instruments of RG 1.97 and of the DCRDR. The core team then issues: (1) the final HED sheets, (2) conceptual panel drawings (in the form of computerized graphics, half-scale mockups or design drawings) indicating the enhancements and modifications, and (3) an integrated list of the required meter and chart recorder enhancements. B. The engineering / implementation team reviews the core team output, develops detailed implementation plans, performs analyses in support of design, issues detailed drawings, initiates purchase requisitions and issues Oe design change (DC) documents identifying the procedures to be followed in implementing the changes. Splitting the design improvements between the core team and the engineering / implementation team, and classifying their responsibilities as noted above, has resulted in the smooth operation of the design corrections. Design improvements scheduled for correction in the 1st refueling outage (Ref.
- 14) have been implemented on schedule (1986 Refueling).
With respect to the design improvements for those discrepancies identified in Sections 4.1 and 4.2 of this report, the following resolutions have been taken.
- 1. For the difficulty in communications while wearing SCBA, Section 4.1, the design of the protective gear will be reviewed for the purpose of installing headsets and voice diaphragms. New equipment will be purchased ff existing equipment cannot be modified.
- 2. For the SPDS human engineering discrepancies and lack of consistency with the control boards, Section 4.2, resolutions have been identified and corrections are scheduled as noted in Appendix A. As a part of standardizing the planned corrections for the 12 -
/~} 2. (continued) U SPDS/PMIS, Rev. 1 of the CNS Human Factors Engineering Standards will include a section on enhancement guidelines for the CRT displays and their consistency with the control room (Item 4 of Appendix B). For the HED concerns identified by the NRC in Appendix B of the Lawrence Livermore National Laboratory Technical Evaluation Report (Ref. 15), modified resolutions have been developed and included with their associated HED sheets. The modified resolutions are noted in the HED master list of Appendix G and are identified by "*". A cross-referencing of the NRC Appendix B HED concerns (Ref. 15) with CNS DCRDR modified resolutions of Appendix G is noted in Table 6.1. O O 13 -
1 TABLE 6.1 CROSS-REFERENCING OF NRC HED CONCERNS AND MODIFIED RESOLUTION / ACTION OF THE HED NRC,HED of Concern Modified Resolution / Action: Comments (Appendix B, (Referenced Page No, Reference 15) Appendix G) 173SS P. 3 Modified Resolution , 89SS P. 4 Modified Resolution & Schedule i 116S P. 5 Modified Resolution 26T P. 8 Modified Resolution 186SS P. 6 Modified Resolution 349SS P. 7 Modified Resolution 2 11S P. 9 Modified I Resolution i ! 105S P. 10 Modified Schedule 111 P. 12 Modified Schedule 9SS P. 13 Modified Resolution. Other related controls' HEDs are identified in: 1) HED record #344 P. 59, Appendix G
- 2) HED record
#361, P. 70, Appendix G O
14 -
,/ TABLE 6.1 (continued)
CROSS-REFERENCING OF NRC HED CONCERNS AND MODIFIED RESOLUTION / ACTION OF THE HED NRC.HED of Concern Modified Resolution / Action Comments (Appendix B, (Referenced Page No. Reference 15) Appendix G) 101 P. 19 Modified Resolution & Schedule 36SS P. 21 Modified Resolution, Refet to Section 6.3 of this report 54SS P. 29 Modif ied Resolution 29T P. 26 Modified Resolution i i i I i I. l w _ - .. - - -. _ - ..-.,..- - _ -, .-- -
' ~ 6.3 Design Improvements of Annunciator Warning System HEDs v The Cooper DCRDR survey and function and task analysis have identified several HEDs associated with the control room annunciator warning system. These HEDs encompass the following generic problems:
- 1. Annunciator alarms not consistently prioritized for required response level by legend plate color.
- 2. Annunciators not grouped above their related controls and displays.
- 3. Annunciator nomenclature, acronymns, or abbreviations are not standardized.
- 4. Annunciators not provided with alphanumeric code for prompt response.
- 5. Annunciator response. system not consistent among panels.
- 6. Annunciator response controls not coded for ease of recognition.
gs 7. No standard gnide for writing annunciator procedures is (,) in use. i
- 8. Multiple choice indications used on alarm , tiles.
- 9. Alarms do not reflash for second alarm input.
For each of the discrepancies listed above, with the exception of items 8 and 9, resolutions were identified and design corrections were made or are planned, as noted in the HED sheets of Appendix G. The NRC, in their preimplementation audit of CNS DCRDR program (Ref. 15) requested that NPPD finalize the design improvements of all the annunciator warning system HEDs and provide a schedule for correction. This section of the report addresses the corrections planned for the multi-input alarms and their lack of reflashing capability for a second alarm input. The Cooper control room alarm system has been surveyed for the identification of these multi-input alarms and their associated number of inputs. A total of 326 multi-input alarms were identified, with the number of inputs varying from 2 to 274. Appendix C gives a listing of those multi-input alarms on the control room panels, together with the number of associated inputs. 16 -
T The NPPD plan of action for correcting these multi-input alarms is based on prioritizing them with respect to their safety significance. The criteria for prioritization are based on the importance of the alarm in promptly alerting the operator to the possible initiation of an event or of the abnormal operational status of critical equipment. The specific criteria for the prioritization are given in Table 6.2. Based on these prioritization criteria, high-priority multi-input alarms will be corrected first followed by low-priority alarms. Appendix G gives the results of the prioritization criteria shown in the last column of the multi-input alarm tables. Table 6.3 gives a summary of the multi-input alarms per panel and their prioritization. The NPPD plan for design correction of the multi-input alarms and the schedule for implementation is summarized as follows:
- a. Priority "1" multi-input alarms will be split into single-input alarms, with corrections to be implemented in the 1988 refueling outage,
- b. Priority "2" and'"3" multi-input alarms need to be further evaluated to determine which of the following options is appropriate:
- 1) Providing reflashing capability
- 2) Splitting into single-input alarms
- 3) Leave as is Corrections, if any, will be implemented in the 1989 refueling outage.
The NPPD decision to further evaluate priority "2" and "3" multi-input alarm corrections is based on the need to further investigate the options available for alarm improvements (Ref. 21 and 22). These options will include the possibility of retrofiting the existing system with reflashing capability, incorporation of additional CRTs on the control boards or operators desks and/or providing sequence event recorders for the printing of alarm logs. The results of this investigation will be completed before the 1988 refueling outage, and will be reported to the NRC in Supplement III to the DCRDR Summary Report. In implementing the splitting of priority "1" multi-input alarms (Refer to Table 6.4 for listing), additional alarm boxes will need to be provided in the control room. This may entail providing 2nd level alarm boxes to be located above the existing ist level alarms, as noted in Figure 6.1. () The addition of new alarm boxes will take into account the results of the evaluation of Priority "2" and "3" multi-input alarms. 17 -
l In addition to the priority "1" multi-input alarm modifications, present implementation plans call for the existing alarms to.be upgraded with respect to their prioritization, tile legibility and legend clarity, relocation of tiles, and keying procedures to tiles. The schedule for these corrections is the upcoming refueling outage (1988 Refueling). O 4 4 i i O t - 18 - I 4 l
-,,,.,,m, -,,-w , , , ,, . . ., ,,,,_w-.. ,ma.- . . --.- ,.------>n.,r,-,--w--,,,,em,,,...,---~m--,----,n,- - , , - _ ,,,,,.e,. -,.----,-_,.~,,m,y,,.w, m- _ ,-.,y ,w-. -n'
__ .-. -- _ =_ -.
/~N TABLE 6.2 MULTI-INPUT ALARMS - PRIORITIZATION CRITERIA PRIORITY 1 A. Alarms that alert operators to entry into an emergency per CNS EOPs an'd EPs.
B. Alarms that alert and inform of the status of RG 1.97 category 1 parameters. C. Alarms associated with plant conditions requiring reactor scram in accordance with plant procedures or Technical Specifications. PRIORITY 2 A. Alarms alerting the operator that essential safety-related equipment is exceeding its operational limits. B. Alarms that alert and inform of the status of RG 1.97 category 2 parameters. () C. Alarms associated with plant conditions which may require reactor scram (depending upon the degree of.the abnormalities) PRIORITY 3 All remaining multi-input alarms. , i 19 -
E a TABLE 6.3
SUMMARY
OF MULTI-INPUT ALARMS PER PANEL
& THEIR PRIORITIZATION NUMBER OF MULTI-INPUT ALARMS I PANEL PRIORITY 1 PRIORITY 2 PRIORITY 3 9-3 6 18 30 , 9-4 4 10 28 i
9-5 -- 11 19 I VBD-A -- 3 34 i VBD-B -- 1 32 i VBD-C 2 14 58 VBD-S -- -- 1 . VBD-M -- 6 9 l
; VBD-J 1 4 3 VBD-R 2 --
22 ! VBD-Q 2 2 -- > l VBD-H -- 2 -- VBD-K -- -- 2 l --- i j TOTAL 17 71 238 I O 1
4 TABLE 6.4 PRIORITY "1" MULTI-INPUT ALARMS AND THEIR ASSOCIATED NUMBER OF INPUTS ALARM NO. OF INPUTS
- 1. High Area Temp, Panel 9-3 31
- 2. Reactor Bldg High Radiation, 10 Panel 9-3
- 3. Supp Chamber Lvl'Hi/Lo, Panel 9-3 2
- 4. Refuel Area High Rad, Panel 9-3 2
- 5. Radwaste Bldg High Rad, Panel 9-3 9
- 6. Turbine Bldg High Rad, Panel 9-3 5
- 7. Off Gas Vent Pipe High-High, 2 Panel 9-4
- 8. Liquid Process High Rad, Panel 9-4 2
() 9. Off Gas High Rad, Panel 9-4 2
- 10. Reactor Bldg Vent High-High Radiation, 2 s Panel 9-4
- 11. Emergency Service Transformer Trouble, 6 ,
VBD-C .
- 12. Startup Service Transformer Trouble, 6 VBD-C I
- 13. RX Bldg Pump Rooms Temp. High, 5 VBD-R i
- 14. RX Bldg Differential Press Too High/ Low, 2 VBD-R !
- 15. RX Bldg Supp Chamber Water Hi Temp, 16 VBD-J l
- 16. Aug. Radwaste Vent Activity High, VBD-Q 3
- 17. ERP Discharge Activity High, VBD-Q 3 0
O O O l t l l1 l FIG. 6.1 CCNCEPTUAL CUTLINE OF THE 2ND LEVEL ALARM BOXES - AND THEIR ASSOCIATED SINGLE INPUT ALARMS SRVs EUPPR AREA Mst AREA crrtuEm PeCCESS PCOL TEMPERATURE RAD RAD RAD RAD i TEMP 1 - c uve. amn. ur uva. ===. l l ll 3 P14. 9-3 N P4 b w A i 1 E
- 5 1
CCCPER NUCLEAR STATION CDNTROL RDOM
- 1st t 2nd Level Alar n Systens g Y
l i i !,
, I lln-n.
m 3
- n a i
l ER
=
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g's 7.0 VERIFICATION OF DESIGN CORRECTIONS 7.1 Preimplementation Verification Activities The NPPD procedure for verification of design changes before implementation was included in Appendix F of Reference 14, and was discussed with the NRC staff during the preimplementation audit (Ref. 15). This process consists mainly of: A. Independent Design Verification - the design verifier independently verifies that all applicable items listed in the design change package are in accordance with the station Design Change (DC) procedure (Ref. 23). B. DCRDR Team Verification - the DCRDR team members review the Design Change package to ensure that the Design Changes are in accordance with the HED resolutions and incorporate CNS human factors engineering standards. For each of the panel Design Changes implemented in the 1986 refueling outage (Refer to Section 10.1), the DCRDR team has reviewed the following documents for verification: (p) Design drawings: reviewed for the relocation of affected components, demarcation lines, mimic arrangement, color coding and label placement. HED final resolutions: Reviewed for final versus intended resolution, and that the correction does not create a new HED. Verification review comments for each of the panels were forwarded to the design engineer responsible for the DC. Following resolution of the verification comments, the DC was sent to the Station Operations Review Committee (SORC) for review and approval of design implementation. DCRDR verification of the HED correction was documented on the HED sheets and a verification sign off (see Appendix F) was included in the DC package. V 1
r- 7.2 Postimplementation Verification (Validation) Activities b) The post implementation verification of the design improvements was conducted in a manner similar to the praimplementation verification described in Section 7.1. QC verification and testing requirements were included in the Design Change (DC) package to verify the correctness of the implemented corrections as measured against the criteria and design details included in the DC package. The DCRDR team had the responsibility to validate that the implemented enhancements and modifications correct the HED and do not create new HEDs. In validating the implemented panel changes, the DCRDR team developed and utilized the validation checklist given in Appendix D. The implemented changes were checked for: A. Relocation, Addition or Removal of Components Validation is in accordance with the components' modifications included in the DC for this panel. B. Panel Layout Panel layout, functional grouping of displays and 7- controls, and mimic arrangements were validated against (j the panel detailed design drawings, the criteria listed in the validation checklist, and human factors standards. C. Controls Controls enhancements and modifications were validated against the criteria listed in the validation checklist and human factors standards. D. Meter and Chart Recorders Corrections were validated against the criteria listed t in the validation checklist, and with the display l enhancements included in the'DC. i l i E. Indicator Lights Corrections were validated against the criteria listed in the validation checklist. - F. Labeling l
~
Corrections were validated against the criteria listed in the checklist, human factors standards and the label f~h change document. U 24 - l
^^ G. Annunciators Corrections were validated against the criteria listed in the validation checklist and human factors standards. Many of the annunciator corrections are scheduled for implementation in the 1988 refueling, and therefore, validation of the annunciator warning system was not completed in the 1986 refueling outage.
The DCRDR team, in a walkthrough observation of the upgraded panels, completed the validation checklist for each of the panels. They documented compliance with the standards, or identified the items that have not been completed or were implemented incorrectly in the remarks column of the checklist of Appendix D. Only a few items relating to the absence of scale banding of several meters, incorrect label placement for two meters, and incomplete demarcation were identified through the validation process, and are being corrected by the station. HED implemented resolutions were also validated by the DCRDR team, and the validation of the HED corrections are being documented on the HED sheets. A validation signoff (See Appendix F) is included in the DC { package. O i lO
COORDINATION OF CONTROL ROOM IMPROVEMENTS WITH CHANGES O 8. FROM OTHER PROGRAMS 8.1 Operator Training Relating to DCRDR Control Room Modifications i l Operator training on the DCRDR improvements took place during.the 1986 refueling outage in six (6) training sessions. The DCRDR training program was mandatory for licensed operators and shift technical advisors. The DCRDR team members, working with CNS training department personnel, prepared the necessary training material and conducted the training in accordance with NPPD training , standards (Ref. 24). The DCRDR training material consisted of: A. Lesson Plan The lesson plan is the primary training tool used by the instructor in guiding the training process. It identifies the training objectives, program references and guidelines, training aids and the lesson material. The DCRDR lesson material covered the following
-subjects:
() - Human Factors Engineering / History and Technical
Background
NPPD DCRDR Effort CNS Human Factors Engineering Standards Panel Changes Scheduled for Implementation in the 1986 Refueling Outage. l Appendix E gives details of the lesson plan that has been used in the DCRDR training. 4 B. Training Aids Transparencies of the lesson plan and 1/2-scale mock-ups of the control room panels implemented in the 1986 refueling were used in the training sessions. The panel mock-ups identify: a) The new positions of the
- relocated or modified components, b) Panel layout in E terms of functional grouping and mimic arrangement, c) Enhanced meters and recorders, d) New labeling used.
Figure 8.1 shows panel 9-5 mock-up. i O
+
C. Participants Handout A participants handout was used to supplement the lesson plan. The handout contained a description of the improvements in terms of the enhancements and modifications implemented on each of the panels. The handout also included a checklist that licensed operators and Shift Technical Advisors (STAS) were required to complete in the control room. The checklist documented the walk-through of each of the upgraded panels and their affected system procedures. Appendix E includes the participants handout used in the DCRDR training. During the training session and in describing the enhancements and modifications performed on each of the panels, the participants assembled in the front of the panel and the instructor pointed out the changes on the panel mock-ups (see Figure 8.2). In the process of discussing the HED corrections, minor enhancements for the RHR and RWCU mimic arrangements (Panels 9-3 and 9-4) were suggested by the operators. The DCRDR team assessed these new operator inputs, and on-the-spot design corrections were implemented. During the DCRDR training, the operators expressed enthusiasm for the panels upgraded layouts and for the implemented resolutions of the HEDs. f) V 1 4 a
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Jr' 8.2 Operator Training HEDs and Corrective Actions NPPD assessment and correction of the DCRDR HEDs has emphasized the development of good human factors and has stressed performing the necessary enhancements and modifications to resolve the discrepancies. As a part of the stated resolution of the majority of the HEDs, operator training is to be conducted to ensure operators familiarity with the changes before plant startup. The operators are made aware of these kinds of changes and the resolutions for HEDs through the DCRDR training described in Section 8.1 of this supplement report. Four HEDs have resolutions requiring additional operator training not covered in the DCRDR training of Section 8.1
, above. These HEDs and their corrective actions are:
o HED 22T, Record No. 198, P. 117'of Appendix G, which as a resolution requires training for operators to ensure 7 the meaning of and the determination of reactor , suberiticality, is covered in licensed operator initial, requalification, and E0P training. 3 Criticality and suberiticality are taught through reactor physics instruction and reactor startups, performed both at CNS and the simulator. E0P training at the simulator provides various emergency scenarios which exercise E0P steps. requiring the operator to determine suberiticality. o HED II, Record No. 254, P. 117 of Appendix G, which has a stated resolution that training is to be provided by a plant specific simulator. NPPD is currently in the
. process of securing a plant specific simulator with an ,
estimated date of operability in 1990. I o HED 5SPDS and 19SPDS, P. I and 4 of Appendix A, are
- related to the SPDS computer displays. Licensed operators were initially trained on all SPDS displays.
Operator training will continue on these displays in j further initial and requal training. i As these HEDs are being resolved, the DCRDR team will evaluate the implemented training resolutions and verify / validate that the proper resolutions of the HEDs exist. l i t l l ; t
-,____.,,,_,_,,,,,__,,_,.,_.....,_,_,-r
.,...,_,,____,,-m,____,,_, , . _ . _ _ . , _ _ . . . , , , , , _ _ , _ . _ _ . _ , _ . . , ,
f-') 9. OTHER DCRDR ACTIVITIES LJ 9.1 Operating Experience Review of Other Plants Per.the commitments listed in reference 14, NPPD obtained DCRDR summary reports from three (3) BWR-4 plants similar to Cooper, in order to review and assess the relevance of the operating experience reviews performed by each of these utilities to the CNS DCRDR program. These summary reports were reviewed to identify any Human Engineering Discrepancies (HEDs) that were resultant from these utilities' review and evaluation of historical documents such as Licensee Event Reports (LERs) and scram reports. The review conducted by NPPD of these summary reports as a whole, however, did not produce enough adequate information on HEDs to be of use in the CNS DCRDR. As an alternative, NPPD acquired abstracts from seventy nine LERs related to operator errors from six BWR 4's written during a period from 1984 through September, 1986. These LERs are presently under review by the DCRDR team. The results of the review will be reported in the DCRDR Supplement III Report. O O I l l { I i l l i C) fs 10. DCRDR RESULTS v-10.1 DCRDR Enhancements and Modifications Completed By End of 1986 Refueling Outage The Cooper Nuclear Station Detailed Control Room Design Review (DCRDR) program was implemented to identify existing design deficiencies in the control room, to correct deficiencies identified, to improve station reliability and safety through better man-machine interface, and to generate design standards for future control room modifications. These goals were achieved through the application of Human Factors Engineering (HFE) principles using NUREG 0700 Guidelines as the primary basis for determining whether modifications were warranted. Panel improvements were made in nine major areas; (1) functional grouping of related controls and displays, (2) lines of demarcation to enclose the functionally related groups, (3) hierarchical labeling to identify system, subsystem, and component functions, (4) replacement of deficient meter scales and zone marking of displays to provide easier identification of the parameter status, (5) replacement of several obsolete or difficult to read instruments with more reliable devices, (6) the installation of field instrumentation outside the (). control room to provide additional parameter information to the o p e r a *: o r , (7) the removal of instrumentation and controls no longer required for operation, (8) differentiation of pump and fan controls from other controls by using a yellow color ring for CR2940 switches and a yellow band on the handle on an SBM switch, and (9) painting the panels to provide an overall better appearance. During the fall 1986 outage these improvements were applied to six control room panels. They are the 9-3, 9-4, 9-5, VBD-S, VBD-J, and VBD-R panels. The 9-3 panel provides control of two Residual Heat Removal (RHR) systems, the High Pressure Coolant Injections (HPCI) system, the Automatic Depressurization System (ADS), two Core Spray (CS) systems, and the Main Steam Isolation Valve (MSIV) system. The 9-4 , panel controls the Reactor Core Isolation Cooling (RCIC) ! system, Primary Containment (PC) system, Radwaste (RW)
- system, Reactor Water Clean Up (RWCU) system, and two Reactor Recirculation pump (RR) control systems. The 9-5 panel is the Reactivity and Startup Feedwater control panel. VBD-S is the station sump control panel. VBD-J is
- the Suppression Chamber pressure relief and temperature 1 monitoring panel and VBD-R is the station HVAC control panel.
l The specific changes to each panel will be discussed in Sections 10.1.1 through 10.1.6. The following generic approach for modifying each panel was used. Upon obtaining ! the proper clearance orders, any controls or displays which I - 32 - i
l
'1 l
l l INSERT"10.1 (CONTINUED) l were to be relocated or were considered to be an obstruction-to modifying the panel were removed. Removal consisted of lifting. cabinet wiring at the terminal strip, marking each wire with the. terminal number and leaving the wiring connected at the device. The device is then tagged with its
-item number, placed in a dust tight plastic bag and stored in designated storage cabinets. Once devices are removed, any equipment still required to be operable while the modifications are being made are then made operable by installation of electrical jumpersoor temporary control '
stations. Actual panel changes are then made using a portable hydraulic milling machine. The machine provides the cut outs for relocation of devices, new installations, and the repair of the panel surface by filling the space where devices are no longer to be located. This repair to the panel surface is done by first machining the lip of the existing space to provide a .125 inch width step around the space to be filled. A patch piece is then fabricated to the same shape as the area to be filled with a step opposite that of the panel surface. Once all patch plates are confirmed to fit properly, nelson studs are attached to the
- plates and the plates are clipped and torqued into place.
This results in making a semi-smooth panel surface. At this ; time the paint booth is set up to enclose the panel. The O booth is equipped with an independent exhaust system consisting of an exhaust blower located on the roof of the control' building connected to the paint booth via twelve inch elephant trunk duct which maintains the booth at negative pressure to remove all dust and paint vapors. To prepare the panel for painting, all toles are covered with masking tape as are all devises that have not been removed. ' Automotive body filler is applied to the seams of the patches and sanded to a smooth finish. The panel surface is then sprayed with a sealer, primer, and three coats of finishing paint. After a twenty-four hour drying period, controls and instruments are installed and terminated per the new panel arrangement drawings. Temporary controls are removed at this time. After reassembly of the panel is completed, new black on white labels lines of demarcation, and flow path mimics are applied. Meter scale replacement and enhancements are also completed. The demarcations and ' mimics are provided using premium grade pressure sensitive film which is self adhesive and bonded with a heat gum. j Calibration of instruments and system testing is now performed and the panel is declared operational. This l process to panel modifications worked well with minor difficulties encountered. Future large scale panel rearrangements shall be implemented in this manner. l (Photocopies of Panels During Implementation of Design > i- Modifications, are shown in Figures 10.1 and 10.2) l I - 33 -
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r's 10. DCRDR RESULTS (continued) 10.1.1 VBD-S Implemented Enhancements and Modifications The panel modifications during the 1986 outage began with vertical board S. This panel provides capability to operate the turbine / generator, reactor building, control building, yard and elevated release point (ERP) sump pumps. The panel also contains the torus area level indicator, the annunciator response controls for annunciator S-1, and the pump start counters and run hour meters for the elevated release point sump pumps. To perform the required modifications, twenty-three control switches and associated status lights, and five panel instruments were temporarily removed. Electrical jumpers were installed in twenty-two control circuits to maintain automatic operation while modifications were being made. Actual changes to the panel consisted of relocating the Yard Electric Manhole Sump Pumps W and Y controls with the other yard equipment to form a functional system group. Because of this re-arrangement, space was made available to raise the Elevated Release Point start counters and run hour g- meters above their associated sump pump control switches \ j) forming another sub group of associated controls and displays within the Yard Area system. A standardization is being made at all control panels as to the arrangement of the annunciator response controls. The standard is now a triangular arrangement where the acknowledge push button is on the left, the reset push button is on the right, and the test push button is below and centered between the other two push buttons. To conform with this arrangement, the test push button una relocated to ita proper position. To , provide additional parameter information to the operator four new level indicators were added to this panel. The meters reflect the levels of the four reactor building floor drain sumps in the quads of the reactor building. They are also set up to indicate up to seven feet above the tops of the sumps to monitor for flooding'of the quads. The associated level transmitters are installed to meet and exceed Category 2 criteria of Regulatory Guide 1.97. Division separation is in compliance with IEEE 384-1981 (Independence of Class IE Equipment and Circuits) and Regulatory Guide 1.75 (Physical Independence of Electric Systems). Electrical loading calculations, cable tray loading, seismic loading, and environmental calculations were performed to assure reliable operation of the instrumentation. The final change to the panel consisted of replacing the \- Torus Area level transmitter. The previous system consisted of a bubbler system with an ON/0FF switch at panel VBD-S. The new instruments are now continuously operating with the 36 -
- 10. DCRDR RESULTS (continued)
(. 10.1.1 VBD-S Implemented Enhancements and Modifications range expanded an additional two feet, or seventeen feet total. Added to the Torus Area level loop is an alarm module which provides an alarm at Annunciator S-1 upon detection of level. To provide space for the new alarm the Augmented Radwaste HVAC trouble alarm has been re-located to Annunciator R-1 of panel VBD-R which is the HVAC panel. Because of this change out of Torus Area level instrumentation, the ON/0FF switch at VBD-S was no longer required and has been removed. Upon completion of panel modifications, the panel was painted and enhanced per the Cooper Nuclear Station Control Room Human Factors Engineering Standards and Implementation Guidelines. (Figures 10.3 and 10.4 show photos of the upgraded panel. Appendix F gives a listing of VBD-S HED Implemented Corrections.) 0\ v l l l O O
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7g 10. DCRDR RESULTS (continued) 10.1.2 VBD-J Implemented Enhancements and Modifications Panel VBD-J is the Suppression Chamber pressure relief control and temperature monitoring panel. The panel also provides indication as to the position of the inner and outer railroad air lock doors of the reactor building and the personnel airlock door of the drywell. Five major improvements were made to the layout of this panel. Prior to modification, the eight division I and , eight division II suppression pool water temperature indications were all indicated and recorded on one Leeds and Northrup Speedomax 250 recorder. This has now been changed with the addition of another Speedomax 250 recorder so that the division inputs are separated. The recorders are positioned side by side for easy comparison with division I on the left and division II on the right. To facilitate the installation of the additional suppression pool water temperature recorder, two other recorders PC-PR-20 (Torus Pressure) and PC-TR-21 (Torus Temperature) were relocated to the center right area of Vertical Board J. The pressure recorder is positioned on the left next to the suppression chamber pressure relief controls, which in turn, (s} provides feedback indication when operating the valves. f Another discrepancy with the original layout of this panel l was the location of recorder PC-TR-23 (Torus Air Temperature) being at approximately thirty inches above the floor, making it difficult to read. This recorder has been elevated to a position approximately forty-five inches above the floor. The final modification to this panel involved the reactor building inner and outer railroad airlock doors and the drywell personnel air lock door. The original design was confusing in that different indications meant a different status of the door depending on which door was being monitored. The railroad airlock doors each had one light. When the light was on, the door was open. When the light was off, the door was closed. The drywell personnel airlock door also had one light. However, its operation was bright and dim illumination meaning open and closed, respectively. All three circuits were modified and standardized for this ! reason. Each door now has dual indication, red and green lights reflecting open and closed indication. Upon completion of modifications the panel was painted and f- enhanced per the Cooper Nuclear Station Control Room Human ()3 Factors Engineering Standards and Implementation Guidelines. (Figure 10.5 shows photos of the upgraded panel. ' Appendix F gives a listing of VBD-J HED Implemented Corrections.)
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Panel 9-3 Implemented Enhancements and Modifications Panel 9-3 was the largest and most complex, and required the largest number of modifications. This panel is the primary Emergency Core Cooling System (ECCS) panel containing both Residual Heat Removal (RHR) systems, both Core Spray-(CS) systems, High Pressure Coolant Injection (HPCI), _ Automatic Depressurization System (ADS), and Main Steam Isolation Valve (MSIV) control. The RHR and CS systems required the most extensive. changes, while minor changes occurred to HPCI, ADS, and MSIV. Twelve control switch relocations were made to the A-RHR system. These changes were reflected in the Containment Spray Cooling mode, Suppression Chamber cooling, Low Pressure Coolant Injection, minimum-flow, pressure reducing, and heat exchanger vent and drain systems. These changes were required to form functional groups and to provide less complex flow path mimics. One other major improvement to the A-RHR system was the relocation of.the RHR Service Water o Booster Pumps controls from back panel vertical-board M - (Closed Cooling Water System) control panel to the-9-3 panel. This was a beneficial change as th,ese pumps are
,O_ required for the operation of the RHR system to provide adequate cooling water to the RHR heat exchangers which, in turn, remove decay heat from the vessel. The problem with the original _ design was that the pumps and associated motor amp meters were located on panel VBD-M, whereas the flow control and flow indication is on panel 9-3. This required two control room operators to line up and place the system into operation.
The A Core Spray system control layout was completely rearranged. All the control switches were relocated. The new arrangement provides bottom of bench board to top control for spray initiation to the vessel, with flow path mimics and mimics reflecting minimum flow and test configurations. One panel indicator not associated with the Core Spray system but located within this panel area, NBI-DPI-93 (Jet Pump Deviation Head Differential Pressure), was permanently removed from the panel as its services were no longer required for operation. I The Automatic Depressurization System (ADS) needed no control switch rearrangement. All improvements were provided in terms of enhUncements, such as subgrouping the Low-Low Set Logic valv'es separately from the other pressure relief valves and changing the tailpipe pressure Illuminating indicators from blue to amber to conform with the Cooper Nuclear Station Control Room Human Factor Engineering and Implementation Guidelines. The tailpipe i 6
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10.1.3 Panel 9-3 Implemented Enhancements and Modifications indicators were also changed from a normally lit when no pressure detected status, to a normally off status. The tailpipe indicators will turn on when pressure is detected in the tailpipe. The liigh Pressure Coolant Injection (llPCI) system required minor component relocations. Two pressure indicator l locations were changed to allow for demarcation between I water and steam side instrumentation. The annunciator l response controls for the 9-3 panel annunciators are located within the llPCI portion of the panel. These switches were rearranged to confrom to the Cooper Nuclear Station standards. Other improvements to the HPCI system include flow path mimics for steam flow to the llPCI turbine and flow f path mimics for injecting water into the vessel. including [ test configurations. 1 I The B-RilR system required relocation of sixteen control l switches. The changes to this system were the same as the A system except for the Shutdown Cooling Mode of the RilR l system. The injection for this system is through two valves (-) which are common to both RilR loops. These valves are identified through the use of labels and flow path mimics. One other switch common to both RilR loops is the heat exchanger differential presure controller select switch. This switch was relocated from the RilR-A section of panel 9-3 to the RilR-B section to comply with electrical power separation criteria. One panel indicator and two control switches were removed form this section of panel 9-3. Indicator PC-P1-512B (Drywell Pressure Indicator) was removed and replaced with a new Foxboro recorder. Headspray inboard and outboard control valve switches and associated status lights 32 and 33 were removed due to the deletion of that RilR system function. I The B Core Spray system has been rearranged so that the control switch position is identcal to that of the A Ccre Spray system. Fo switch position changes were made to the Main Steam Isolation Valve system. All improvements to this system were in terms of labeling and demarcation. (Figures 10.6 and 10.7 show photos of the upgraded panel. Appendix F gives a listing of Panel 9-3 IIED Implemented Corrections.) D O
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_ 10. DCRDR RESULTS (continued) w 10.1.4 Panel 9-4 Implemented Enhancements and Modifications The panel 9-4 modifications are reflected in changes to the Reactor Core Isolation Cooling system, Primary Containment, Radwaste, Reactor Water Cleanup, and both Reactor Recirculation systems. The systems on this panel are not as complex as those on previous panels; therefore, changes were not as extensive. The Reactor Core Isolation Cooling (RCIC) system did not require any component relocations. All improvements were enhancements. Demarcation was applied to separate the water and steam instrumentation. Flow path mimics were applied to provide easier operation of the turbine and pump lineup controls. All labels were replaced with black on white labeling, and several meter scales were replaced and zone marked to allow for easier determination of parameter status. The Primary Containment (PC) system also did not require any component relocations. One existing patch plate was removed and panel surface repaired. Enhancements included demarcation, minimal flow paths, and new and additional labeling. ('} \~/ The Radwaste (RW) system had several minor component relocations. The control switches for valves A095 and A083 were swapped so that they lined up with their respective pumps. The Radwaste bypass alarm switch was relocated from just below annunciator 9-4-1 to the low center area of the vertical board portion of this system allowing easier accesse The annunciator response controls for the 9-4 annunciators are located in this section of the panel. These switches were repositioned to conforn to the CNS standard configuration. Other improvements to this system include lines of demarcation and new black on white hieravehical labeling. The Reactor Water Cleanup (RWCU) system received the most extensive changes on the 9-4 panel. Every control switch has been repositioned to create a top of bench board to bottom sequence of operation for the system. Flow path mimics and new lables have also been applied to enhance system operation. Improvements to both Reactor Recirculation pump control systems were all enhancement in nature, other than the swapping of location of two recorders and the addition of four Foxboro recorders as part of the Regulatory Guide 1.97 program. Demarcation and other color coding tecnniques were used to achieve the desired system imprivements. (Figures 10.8 and 10.9 show photos of the upgraded panel. i Appendix F gives a listing of Panel 9-4 IIED Implemented l Corrections.)
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- 10. DCRDR RESULTS (continued) 10.1.5 Panel 9-5 Implemented Enhancements and Modifications The 9-5 panel provides various system capabilities to monitor and. control the nuclear fission process within the vessel. The'various systems include the Control Rod Drive (CRD), Neutron Monitoring (NMS), Rod Sequence Control (RSCS), and Vessel Level Control. The panel also provides several protection capabilities, such as Manual Scram, Standby Liquid Control (SLC) injection, and the SCRAM Discharge Volume Level system. The modifications to these various systems were fairly extensive and diverse in nature.
Preparations have been made to centrally locate the seven 4 group isolation inputs to panel 9-5. . Presently only the group one input is operable however all panel work is
- complete with only field modifications to be made. The i panel arrangement consists of dual indication for both channels of each group.
l The master recirculation flow controller has been repositioned from the left center bench portion of panel 9-5 to the far left area. This was due to this controller being operated in conjunction with the recirculation controls
,( ) situated on panel 9-4.
The three associated Rod Sequence Selector Controls were repositioned approximately twelve inches to the left on the center bench board area of 9-5 to allow for standard arrangement of the annunciator response controls. The sixteen local power range meters on 9-5 were replaced l with new Sigma Lumigraph bar graph indicators. The previous j meters were inadequate and of poor design. 1 Another improvement made to the 9-5 panel was lowering the 4 vessel level controller and two manual / auto stations from the upper vertical area to the bench board area of the panel. The controllers are now easier to monitor and operate at their new location. The Control Rod Drive System saw the repositioning of both pump control switches and their respective discharge valve status lights. Final modifications to the panel consisted of repositioning the Turbine Steam Flow / Shutdown level recorder selector > switch, the Reactor Water Level Selector Switch, and the one or three element level control selector switch within the
'i reactor level monitoring area. Previously there did not appear to be any methodology as to the control display arrangement.
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s Final improvements to the panel included demarcation of the various systems and-subsystems, herrarchical labeling using black on white labels, meter scale replacements and enhancements, and painting of the panel. (Fugures ~ 10.10, 10.11, and 10.12 shows photos of the upgraded panel. Appendix F gives a listing of Panel 9-5 HED Implemented Corrections.) 1
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- 10. DCRDR RESULTS (continued)
.Q 10.1.6 VBD-R Inglemented Enhancements and Modifications Vertical Board R is the station HVAC control panel. This includes the Turbine / Generator ~ building, Reactor building, Control building, and the fan coil units for each reactor j building quad, HPCI room and steam tunnel. Also included on j this panel are the annunciator response controls for annunciators R-1-and R-2.
[ l Many panel changes were made due to the poor layout of devices and the fact that there were twenty holes to be filled because of the removal of deleted controls prior to this design change. Additional panel changes were made due i to the removal of five additional controls per this design , change. ! Due to the services the panel provides, sev al heating and ventilating units were required to be operational while modifications were being made. This was accomplished by installing electrical jumpers in control circuits and by temporarily relocating the turbine, reactor, and control
- building differential pressure indicating controllers on a
, . cart behind the panel. .
\/ Control building HVAC modifications consisted of lowering t
the differential pressure-indicating controllers six inches to provide easier operation and monitoring, and the relocation of seven control switches and associated status l lights. This was necessary to allow subgrouping within the
- system between the main supply fans, control room supply fans, and computer room supply fans. One other change to
- the control room HVAC was modification to the electrical circuitry of emergency supply fan 1-BF-C-1A and exhaust fan 1-EF-C-1B. This modification provides an interlock between the two fans so that exhaust fan 1-EF-C-1B will shutdown whenever supply fan 1-BF-C-1A is started, thereby satisfying the requirement that all return air from the control room and cable spreading room be recirculated when a high radiation condition is detected in the suction duct to the control room.
The reactor building HVAC modifications included an almost complete re-arrangement of controls. The new arrangement , allows for subgrouping the reactor building fans, the fan coil units of the quads, and the MG set ventilating . isolation system. The new arrangement flow path mimics were applied to simplify the operation of the various subsystems. 1 In addition, the reactor building differential controller
- was lowered to the same elevation as the control building controller. Provisions have been made to relocate the four reactor building differential pressure indicators from 4 -
52 -
1 l 10. DCRDR RESULTS (continued) 10.1.6 VBD-R Implemented Enhancements and Modifications vertical board G to vertical board R, however, the actual relocation has not yet been made.. No component changes were-made to the quad fan coil units, however, subgrouping, demarcation, meter scale replacement and enhancements were performed. i Improvements to the turbine / generator llVAC system were provided through labeling and demarcation. No component re-locations were performed other than the lowering of its
' differential pressure indicating controller, j (Figures 10.13 and 10.14 show photos of the upgraded panel.
Appendix F gives a listing of VBD-R HED Implemented Corrections.)
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t 10.2 Planned DCRDR Corrections & Schedule NPPD submitted the overall schedule for implementing the llED design corrections in the DCRDR supplement to the summary report (Ref. 14). From the time the supplementary report was issued (February 1986), many HED. corrections were implemented and the schedule for the remaining control room improvements has been altered slightly. The changes in the schedule are a result of:
- 1) a discussion with the NRC during their pre-implementation audit, and 2) matching the time schedule requirements for implementing the DCRDR design modifications with the plant upcoming refueling outages' durations. Specifically, the new schedule is modified to include:
Closing out the HED corrections for panels VBD-S, J and R and panels 9-3, 9-4, and 9-5 that were implemented in the 1986 refueling. Other IIEDs relating to these panels (mainly annunciator warning sys tem IIEDs) will be implemented in the 1988 refueling outage (noted as 2nd refueling in Ref. 14). Implementing IIED corrections for panels VBD-H, A, B and C and 9-02, 9-21, 9-10 and 9-11 in the 1988 refueling outage. For the remaining panels; VBD-K, M. P1 , P2 , Q,G, and Fire Panel, lied corrections will be implemented in the 1989 refueling outage (noted as 3rd refueling in Ref. 14). O< - Advancing the date for improving the emergency and control room lighting from the 1989 refueling outage reported in reference 14 to the 1988 refueling outage. This change in schedule reflects NPPD's effort to meet the NRC request for accelerating the schedule for the control room lighting upgrade (Ref. 15). Correcting the procedures llEDs by the 1988 refueling outage in order to coordinate with other procedure upgrade programs scheduled in 1987. The major milestones for the control room corrections and their updated schedules are given in Table 10.1. Detailed implementation dates of the DCRDR improvements are given in the IIED mas ter list of Appendix G. O O O O TABLE 10.1 CNS DCBDR PPO.TECT MTTE6 & SCHEDULE __ CRDR MODiflCATION PAGE1 RES PER REM 1986 1987 1988 1989j SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ JAS 0ND JFM AMJ JAS 0ND JFM AMJ JAS OND JFM AM Sheu t Start IEY PROJECT MILESTONES ShuuDown-> c StartUi> Shut Dowri7 r Start Uo Dovrra. Mo
~
- 1. V BD E DC35-15D_
A. EfGNEERING 100 0 - M B. INSTALL ATION 100 0 M C. CLOSE OUT DC 60 i
- 2. V BD J DC85-15E A. EfGNEERING 100 0 m .
m B. INSTALL ATION 100 0 M C. CLOSE OUT DC 40 i
- 3. 9-31.RC DC85-15F B&V A. EfGNEERING 100 0 m --
- 9. INSTALL ATION 100 0 m C. CLOSE OUT DC 200 i e
- 4. 9-4 LRC DC85-15G B&V A. EfGNEERING 100 0 -
- 8. INSTALLATION 100 0 C. CLOSE OUT DC 150 i REVISION 4 JFM AMJ JAS 0ND JFM AMJ J 'A S 0ND JFM AMJ JAS OND JFM AMJ 12/22/16 1986 1987 1988 1989
O O O 4 TABIE 10.1 C3 DCRDR PRCLTECT MTTRMIES & SCHEIXJIE
- CPDR MODiflCATION PAGE 2 RES PER REM 1986 1987 1988 1989 4
SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ JAS OND JFM AMJ JAS 0ND JFM AMJ JAS OND JFM AM-snut 5 tart:
! icy PROJECT MILESTONES Shui Down-t x-Start Uc ShJt Down 7 .r-St vt Up Dowrs r- Up
- 5. 9-5 LRC DC85-15H B&V .
4 A. ENGNEERING 100 0Im B. INSTALL ATION 100 0 m . C. CLOSE OUT DC 100 i i
- 6. VED-H DC85-151 B&V A. ENGNEERING 450 <_ i i
35 i i ) B. INSTALL ATION i i I C. CLOSE OUT DC 75
- 7. VED-M DCSS-15J B&V 295 i i A. ENGNEERING B. INSTALLATION 25 i i C. CLOSE OUT DC 50 ,
S. VED-K DC85-15K B&V i i A. ENGNEERING 235
- i i
, B. INSTALL ATION 20 i C. CLOSE OUT DC 40 i l PEVISION 4 JFM AMJ JAS OND JFM AMJ J'A S 0ND JFM AMJ JAS 0ND JFM AM. 12/22/86 1986 1987 1988 1989
,/ ,
V V (J TABLE 10.1 C!S DCRDR P.N MILESTOES & SCHEDULE CPDR MODiflCATION PAGE 3 RES PER REM 1986 1987 1988 1989 SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ JAS OND JFM AMJ JAS 0ND JFM AMJ JAS OND JFM AM dnut star KEY FROJECT MILESTONES Shui Down -p s-Start Ut Sh;t Down 7 .r-Start Up Down c- Vo
~
- 9. VED-R DC85-15L B&V A. ENGNEERING 100 0 m B. INSTALL ATION 100 0 C. CLOSE OUT DC 40 t i
- 10. 9-2 DCSS-15M B&v A. ENGfJEERING 200 i i B. INSTALL ATION 50 s i C. CLCSE OUT DC 20 i i
- 11. 9-21 DC85-15N B&Y A. ENGNEERING 240 i B. INSTALL ATION 50 i i C. CLOSE OUT DC 60 f7
- 12. 9-10 DC85-150 B&V A. ENONEER!NG 450 i i B. INSTALL ATION 40 i i C. CLOSE OUT DC 100 3 REVISION 4 JFM AMJ JAS 0ND JFM AMJ JAS 0ND JFM AMJ JAS OND JFM AM 12/22/E6 1986 1987 1988 1989 O O O i
1 TABLE 10.1 CNS DCRDR PInTELT MIIES'IONES & SCHEDCLE CRDR MGDIFICATION PAGE 4 RES PER REM 1986 1987 1998 1989 l SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ JAS OND JFM AMJ JAS OND JFM AMJ JAS OND JFM AM dnur start' iTY PROJECT MILESTOUES Shut Down-L -Start Ut Shat Down 7 .I-Start i.lo Dow rL .r- Up
~
- 13. 9-11 DC85-15P B&V A. ENGNEERING 185 i i j B. INSTALL ATION 20 i i i
C. CLOSE OUT DC 40 [] l i 14. VBD 0 DC85-150 B&V A. ENGNEERING 185 i i B. INSTALLATION 20 i i C. CLOSE OUT DC 40 C-i
- 15. VED-G DCSS-150 B&V i
1 A. ENGNEERING 160 i i i i B. INSTALL ATIOri 20 4 C. CLOSE OUT DC 30 C: 0
- 16. R ALNG DCSS-15C
- 4. ENGNEERING 50 i i i '
B. INSTALLATION . 5 i C. CLOSE OUT DC 10 i i FEVISt0N 4 JFM AMJ JAS OND JFM AMJ JAS OND JFM AMJ JAS 0ND JFM AM. I 12/22/95 1936 1987, 1988 1989 1 O O . O TABE 10.1 CE DCRDR PIRTECT MIEM & SCHEDUE CRDR MGDIFICATION PAGE 5 PER REM 1986 1987 1988 1989 RES SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ JAS 0ND JFM AMJ JAS 0ND JFM AMJ JAS 0ND JFM AM onut star-PEY PROJECT MILESTONES Shot Dover r- StartUt Shat Down 7 J-Start 40 Dow n .r- Un
- 17. AflNUNCI ATOR DC35-15 A _ B&V A. EPGNEERING 260 i i B. INSTALL ATION 40 i i C. CLOSE OUT DC 40 i i
- 18. FIRE P ANEL DC85-15B B&V A. EtGNEERING 370 ,
i i I I B. INSTALL ATION 70 C. CLOSE OUT DC 30 r i
- 19. EMER& CONTROL RM LIGHTS i
A. ENGNEERING DCSS-15Y 250 B. INSTALL ATIOri 60 i i C. CLOSE OUT DC 40 i i
- 20. ABC)C85-15V B&V A. ENGNEERING 95 i B. INSTALLATION 20 i i C. CLOSE OUT DC 20 n FEVIS10N 4 JFM AMJ JAS OND JFM AMJ JAS OND JFM AMJ JAS OND JFM AM 12/22/95 1986 1987 1988 1989
TABIE 10.1 CNS DCRDR PRCLTECT HILES'IONES & SOEDULES CRDR t10DiflCAT10N PAGE 6 RES PER REM 1986 1987 1988 1989 SCHEDULE 12/11/86 EtlG COM MHR$ JFM AMJ JAS OND JFM AMJ JAS 0ND JFM AMJ JAS 0ND JFM AM dnut str IGY PROJECT MILESTONES Shot Down-t .s- Stwt Uc Shat Down 7 a-Stwt Up Dow 1 L. .r-- Un
- 21. CNTFL RM COMM-G AITRONIC .
A. ENGNEERING DC85-152 100 i B. INSTALL ATION 30 i i C. CLOSE OUT DC 20
- 22. MISC. CRDR ETNIORMENT UPGRD A. ENGNEERING 300 i i B. INSTALL ATION 100 [
C. CLOSE OUT DC 50 g
- 23. PUSH TO TEST L AMPS A. ENGNEERING DC85-15X 160 B. INSTALLATION 40 i i C. CLOSE OUT DC 40
- 24. CLEN4 UP HED'S P ANEL 9-3 A. ENGNEERING DC85-15FF 150 I i B. INSTALL ATION 30 I I C. CLOSE OUT DC 10 REVISl0N 4 JFM AMJ JAS OND JFM AMJ JAS OND JFM AMJ JAS OND JFM AM 12/22/86 1986 1987 1988 1989 10 O O TABIE 10.1 CNS DCRDR PICTECT MILES'IONES & SCIIEDUIE CRDR f10DiflCATl0N PAGE 7 RES PER REM 1986 1987 1988 1989 SCHEDULE 12/11/86 ENG COM MHRS JFM AMJ OND JFM AMJ OND JFM AMJ JAS OND JFM JAS JAS AM ,
dnut ser KEY PROJECT MILESTONES Shot Dovrrt r Stwt Oc Sh;t Down 7 . -Stwt Up Dow y1 r-- Up
- 25. P AfJELS P1 & P2 DC85-1500 i
A. ENGriEERING 100 i i B. INST ALL ATION 30 i i
; C. CLOSE OUT DC 20 i i
- 26. CLE AN UP HED'S P AfJEL 9-5 A. ENGINEERING DC85-15HH 150 i B. INST ALL ATION 30 i i i C. CLOSE OUT DC 10 1
l 4 REVISION 4 JFM AMJ JAS OND JFM AMJ JAS OND JFM AMJ JAS 0ND JFM AM 12/22/86 1936 1987 1988 1989 1 l
- 11. REFERENCES ..
( v
- 1. NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident," May 1980, Rev. 1, August, 1980.
- 2. NUREG-0737, Supplement 1, " Clarification of TH1 Action Plan Requirements--Requirements for Emergency Response.
Capability (Generic Letter 82-33)," December 17, '982.
- 3. " Response to NUREG-0737, Supplement'1, Emergency '
Response Capability, Cooper Nuclear Station," letter from J. M. Pilant (NPPD) to D. G. Eisenhut (NRC), dated April 15, 1983.
- 4. " Pro; ram Plan for Detailed Control' Room Design Review, Nebraska Public Power District, Cooper Station.. dated February 1984, submitted by letter from J. M. P11 ant (NPPD) to D. G Eisenhut (NRC) dated March 1, 1984.
- 5. NUREG-0700, " Guidelines for Control Room Design Review", September 1981.
- 6. NUREG-0800, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants",
Section 18.1, " Evaluation Criteria for Detailed Control ] ) Room Design Reviews (DCRDR)", September'1984.
- 7. "NRC Staff Review of the BWR Owners' Group (BWROG)
Control Room Survey Program (Generic Letter 85-18)", letter from D. G. Eisenhut (NRC) to BWR Licenses, Applications, and Construction Permit Holders, dated April 19, 1983.
- 8. " Review of the Cooper Nuclear Station Detailed Control Room Design Review Program Plan Submittal", letter from D. B. Vassalo (NRC) to J. M. Pilant (NPPD) dated. June 4, 1984.
- 9. " Detailed Control Room Design Review In-Progress Audit Report", (Ref, audit conducted November 27-29, 1984),
letter from D. B. Vassallo (NRC) to J. M. Pilant (NPPD) dated March 20, 1985.
- 10. "NUREG-0737, Supplement 1--Detailed Control Room Design Review (DCRDR) Summary Report", letter from J. M.
P11 ant (NPPD) to D. B. Vassallo NRC) dated February 4, 1985.
- 11. " Technical Evaluation Report (TER) Detailed Control Room Design Review, Nebraska Public Power District, Cooper Nuclear Station", Lawrence Livermore National O Laboratory, March 76, 1985.
- 63 -
,s 11. REFERENCES (continued) s'
- 12. " Detailed Control Room Design Review (DCRDR) Evaluation of Summary Report", letter and attachment from D. B.
Vassallo (NRC) to J. M. Pilant (NPPD) dated September 5, 1985..
- 13. " Detailed Control Room Design Review (DCRDR)
In-Progress Audit Report Response", letter from J. M. Pflant (NPPD) to D. B. Vassallo (NRC), dated April 30, 1985.
- 14. " Cooper Nuclear Station Detailed Control Room Design Review, Supplement to the Summary Report", letter from J. M. Pilant (NPPD) to D. R. Muller (NRC), dated February 27, 1986.
- 15. " Detailed Control Room Design Review - Safety Evaluation", letter and attachment from W. O. Long (NRC) to J.M. Pilant (NPPD), dated November 4, 1986.
- 16. " Detailed Descriptions of the Displays for the Cooper Nuclear Station Safety Parameters Display System (SPDS)", Nebraska Public Power District, Plant Management Information System, Cocper Nuclear Station,
() Document No. 503-8500000-78, dated February 1985.
- 17. "lluman Factors Plan SPDS Iluman Factors Plan, PMIS Iluman Factors Plan", Nebraska Public Power District Plant Management Information System, Cooper Nuclear Station, Document No. 503-8500000-77, dated April 1984.
- 18. "lluman Factors Engineering Review of the Cooper Nuclear Station SPDS Displays", Science Applications Inc.
(SAI), Memorandum from S. S. Almodorar to J. C. Murphy, June 16, 1986.
- 19. "SPDS Consistency Check Against Control Room Panels and E0Ps - Discrepancy Items", General Electric Company, Letter Report from D. Shrader and M. M. Aburomia to C. Goebel and M. Sparr, December 1, 1986
- 20. " Cooper Nuclear Station Writer's Guide - Manual for Preparation of Procedures", Cooper Nuclear Station Document Rev. O, March 1986,
- 21. NUREG/CR-2147 " Nuclear Control Room Annunciators:
Problems and Recommendations", September 1981. O v
- 11. REFERENCES (continued)
.O
- 22. NUREG/CR-3217, "Near-Term Improvements for Nuclear Power Plant Control Annunciator Systems", April 1983.
- 23. " Station Design Changes". Cooper Nuclear Station Engineering Procedure 3.4.
- 24. " Training Materials Standards". Cooper Nuclear Station Training Department Instruction TDI-301, i
O h r l l 1 0
I I i h I , t I, . f d i $ i I 1 ; i I l i 9 l APPENDIX A SAFETY PARAMETER DISPLAY SYSTEM (SPDS) f 1 Q HEDs AND COMPLIANCE CHECKLIST l i
- A.1 SPDS HEDs (p. I to 13) !
} A.2 HF COMPLIANCE CHECKLIST (p. 14 to 30) A.3 CONSISTENCY CHECK ITEMS (p. 31)
/
i t a i e f a 2 a L !O f t i f 2
,m., ., - - ,___.mm..__--- .,....-_#%.__my..,,m- ....m, ,_-.,r-._ m,,,,_o.,m_m_,m.m.,-,m, ,m, . , , , , , . ,,, , , , . _ . _ , _ _ _ , ,
Ch J %) %' APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT 2ECORD CHECK- NUREG- ENHANCEMDT CATEGORY LTL W.EN-No.* LIST 0770 HED DISPLAT / / TATION HED DESCRIPTICN ITEM SECTION ID. ID. MODIFICATION ?RIORITY ACTYON SCHEDt*LE RESOLUTION / NOTES 622 CHARACTERS HARD TO READ SAI 1.1.1.A 6.7.2.1 1 GENERIC TO MODIFICATION II DESIGN MOD 1988 INTEGRATE WITH CONTROL
- DUE TO GLARE SAI 1.1.1.B SPDS ALL DISP uYS REFUELING ROCM LIGHTING IMPROVEMDTS IMPROVDtENTS.
623 LL5INANCE MEASUREMDTS SAI 1.1.1.C 6.7.2.1 2 GENERIC TO ENHANCDtENT A FIX 1988 PERFORM LLN. INANCE REQUIRED SAI 1.1.1.D SPDS ALL DISPLAYS REFUELING MEASURDtENTS AND ASSESS SAI 1.1.1.F RESULTS 6I4 COMPUTER RESPONSE TIPE SAI 1.2.7.A 6.7.1.7 3 GENERIC TO MCDIFICATION II CORRECTION 1986 SPDS DISPLAYS kTRE MADE SLOW SPDS ALL DISPuYS MADE REFUELING MEMORT RESIDENT 625 PRINTER OUTPUT SHOULD 3E SAI 1.2.9.B 6.7.3.1 4 GENERIC TO MODIFICATION II OTHER 1988 EVALUATE THE NEED FOR A IN COLOR SAI 1.2.9.C SPDS ALL DISPIAYS MOD REFCELING COLOR PRINTER 626 SYSTEM ALARM AREA (SSA) SAI 1.2.10.E 6.7.3.2 5 CENERIC TO ENHANCDENT A FIX 1988 THE 'E' ALARM WILL SIGNAL IS SUBTLE SPDS ALL DISPLAYS REFUELING BE MADE MORE VISIBLE IF POSSIBLE. INITIAIJ REQUAL SPDS TRAINING COVERS THIS ALARM. 627 OPERATOR CC!CiUNICATION SAI 1.3.1.E 6.5.1.1 6 GENERIC TO EN10LNCEMENT A FIX 1989 THE SOFTWARE WILL BE AREA (OCA) DOES NOT SPDS ALL DISPLAYS REFUELING CHANGED SO THAT THE NAYE ALWAYS DISPLAY THE NAME OF THE DISPLAY IS SHOWN IN OF THE CURRENT DISPLAT THE OCA AREA 628 THE " CORE C0 CLING" SPDS SAI 1.3.2.F 6.5.1.2 7 GENERIC TO ENHANCEMDT A CORRECTION 1986 PROBLEM IDENTIFIED AS BOX FLICKERS BETWEEN SPDS ALL DISPLAYS MADE REFUELING INPUT SIGNAL FROM TLV CREEN AND YELLOW DIFFERENT SOL 1tCES - SOFTWARE CHANGED TO UTILI:E ONE INPLT SIGNAL
- SPDS HED RECCRD NUMBERS FOLLOW OTHER HED RECORDS (TOTAL 621) 0F APPENDIX G e m ^^
O O O 2 -- APPENDIX A SPDS SURVEY RESULTS AND ASSESSHENT RECORI) No. CllECK- NilREG- ENilANCEENT CATECORY IMPIIHEN-I.IST 0700 IIED DISPLAY / / TATION llED DESCRIPTION ITEM SECTION ID. ID. HODIFICATION PRIORITY ACTION SCllEpill.E RESOLUTION / NOTES 629 Ti!E TICK HARK ABOVE Tile SAI 1.1.4.A 6.7.2.4 8 SPDS10 ENilANCDIEtrr A FIX 1988 Tile NUMERAL "15" WILL BE Hi!HERAL "15" IN Tile APRH SPDS REF11ELING MOVED To Tile RIGIT SO T11A1 BAR CilART IS AT AN ANCII IT l.INES IIP WITil Tile VERTICAL TICK HARK. Tile ANCIID TICK HARK WILL BE REMOVED. 630 Tile IABEI. "A1.1.-RODS-IN" SAI 1.1.4.1 6.7.2.4 9 SPDS 10 ENilANCDfEffr A CORRECTION 1986 "CONVt0L ROD POSITIONS" SEEllS 10 llAVE N0' SPDS SPDS 20 MADE REFUELINC tlSED RATHER 111AN TECllNICAl. REASON TO BE SPDS 21 "ALL-RODS-IN" IlYPilENATED 631 Tile NiftlFit1CAI. VAI.llE SAI 1.1.4.A 6.7.2.4 10 SPDS 20 ENilANCEMENT A FIX 1988 Tile SCIENTIFIC FORMAT WII.I.: LISTFD FOR SRH SPDS SPDS 21 REFT 1ELING BE USED FOR Tile VALUE ClfRRENT VAI.UE IS SPDS 24 111SPl.AYED IN ".1714E5" SPDS 25 10ialAT WillCil IS NOT AS SPDS 29' EASY TO l'NDERSTAllu AS Tile SPDS 2A/28 , SCIENTIFIC FORilAT, "1.234E5" 632 Tile REACTOR PERIOD ' SAT 1.1.4.A 6.7.2.4 11 SPDS 20 ENilANCEMElfr A CORRECTION 1986 RX PERIOD TNDICATION INDICATIONS IS NOT AS SPDS SPDS 21 HA')E REFUELING REMOVED FROM DISPLAYS, N(n - ItSEFIII. AS IT IS DISPl.AYED HECESSARY INFORMATION FOR NOW DISPLAY 633 Tile CENERAI. READABil.1TY SAI 1.1.4.A 6.7.2.4 12 SPDS 20 ENIIANCEHEMT A FIX 1988 TICK HARKS At3 SCALE 0F Tills DISPI.AY NEEDS SPDS SPDS 21 REFUELING VAIJIES WILL RE ADDED 1D THPROVEHENT 1HPROVE THE DISPLAY
O Uh. U i APPENDIX A SPDS SURVEY RESULTS AND ASSESSIIENT RECORD NO. CllECK- IlDREG- ENilANCEMENT CATECORY THPI.EHEN-I.lST 0700 llED DISPLAY / / TATION llED DESCRIPTION ITEtt SECTION ID. ID. HODIFICATION PRIORITY ACTION ScilEDIll.E RESottfr10N/ NOTES 634 Tills DISPIAY AND Tile SAI 1.1.4.E 6.7.2.4 13 SPDS 20 ENilANCEMEfff A FIX 1988 Tile DISPIAYS WILL BE
" REACTIVITY SPDS SPDS 21 REFUEL.TNG CilANCED BY ADDING CONTROL-TREND" Colli.D IEHARCATION LINES, OR BY PRESENT IDErrilCAI. DATA 1H HnVING INDICATORS CLOSER A fl0RE CONSISTFilT WAY OR TOCFTIIER IN A FE)RE READALI.E FOPH 635 Tile INCit/HINUTE IABEl. SAI 1.1.4.A 6.7.2.4 14 SPDS 22 EHilANCEHEttr A FIX 1988 Di!E TO SPACE RF.STRTCTIONS Silot'LD BE IN ONE I.INE CCI SPDS SPDS 10 RERIELING ON HOST DISPLAYS, Tile RATilER lilAN ON 'IV) AND SPDS 20 IABEI. CAN NGT BE PUT ON i Silotti.D READ XXX/HIN SPDS 21 ONE I.INE, IIDWEVER XXX/H WILI. BE CilANCED TO READ XXX/HIN 636 SOffE TICK HARKS ARE SAI 1.1.4.A 6.7.2.4 15 SPDS 22 ENilANCEHENT A FIX 1988 TICK HARKS WILL BE ADDED HISSING IN llAR CliARTS SPDS SPDS 24 REFUEL 1HG WilERE POSSIBI.E SPDS 26 637 DECmAL PolNTS ON NUMBERS SAI 1.1.4.J 6.7.2.4 16 SPDS 22 ENilANCEMEKr A FIX 1988 11tE DECIMAL POIKrS WILL BE DO NOT LINE UP SPDS REFUELING Al.1CNED 638 HISSING PERIODS IN Tile - SAI 1.1.4.K 6.7.2.4 17 SPDS 22 ENilANCEMENT A FTX 1988 PERIODS Wii.L BE ADDED AS DISPl.AY SPDS SPDS 23 REFilELING NEEDED THROUGil Tile DISPIAY SPDS 26 SPDS 27 SPDS 28 SPDS 29 SPDS 39 639 TilERE IS A CRollP OF FOUR SAT 1.1.5.C 6.7.2.5 18 SPDS 22 ENilANCEllENT A FIX 1988 TIIE AREA OF TIIE FollR INDICATORS IN A DISPLAY SPDS REF1tELING INDICATORS WILL BE WillCll IS IX)MINATED BY A OltrLINED HIMIC AND BAR CllARTS
g g (X 4 f ) (w- ) Q) \J APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT l RECORD CHECK- NUREG- ENHANCEMENT CATEGORY IMPLEMEN-50.* LIST 0770 HED DISPLAY / / TATION HED DESCRIPTION ITEM SEC* ION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE RESOLUTION / NOTES 640 THE DISPLAY LOOKS VERY SAI 1.1.5.M 6.7.2.5 19 SPDS 22 ENHANCDiENT A NO NONE LICENSED OPERATORS HAVE CROWDED SPDS SPDS 28 ACTION BEEN TPAINED ON THESE DISP!AYS IN THE INITIAL SPDS TRAINING - FURTHER INITIAL AND REQUAL SPDS TRAINING WILL CONTINUE TO ) TRAIN OPERATORS ON THESE I DISPLAYS I 641 THE "RPV PRESSURE" SAI 1.1.5.C 6.7.2.5 20 SPDS 23 ENHANCEMENT A FII 1988 "RPV PRESSURE" WILL BE INDICATION GETS LOST IN CCI SPDS REFUELING REPOSITIONED TO LMPROVE THE UPPER, LEFT-HAND ITS VISIBILITY > CORNER OF THE DISPLAY 642 THERE IS AN EXTRA "100" SAI 1.3.2. A 6.5.1.2 21 SPDS 23 ENHANCEMENT A FIX 1988 THE EXTRA "100" SCALE MARK ) SCALE MARK AND A MISSING CC 6 SPDS REFUELING WILL BE REMOVED AND A
" 100" SCALE MARK
- " 100" SCALE MARK ADDED 643 THE " CONTAINMENT SAI 1.1.4.A 6.7.2.4 22 SPDS 24 ENHANCEMENT A NO None THE ARROW REMAINS PADIATION" HAS AN ARROW SPDS SPDS 25 ACTION BENEFICIAL EVEN THOUGH TO ILLUSTRATE RADIAIION NO RATE OF CHANGE RATE OF CHANGE, BUT IT VALUE IS DISPLAYED.
HAS NO RATE-OF-CHANGE VALUE DISPLAYED ALONG WITH THE ARROW 644 THE "DRYWELL PRESSURE" IS SAI 1.1.4.A 6.7.2.4 23 SPDS 24 ENHANCEMENT A CORRECTION 1966 THE INDICATION WAS CHANGED INDICATED IN " PSIA" SPDS SPDS 25 MADE REFUELING TO "SPIG" VHEN THE DRYWELL SPDS 26 PRESSURE INSTRUMENT WAS SPDS 27 CHANGED FROM " PSIA" TO SPDS 3B "PSIG" SPDS 3A SPDS 33
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o j y r T i i 1 APPENDIX A I SPDS SURVET RESULTS AND ASSESSMENT i RECCRD CHECK- NUREG- ENHANCEMENT CATEGORY IMPLEMEN-I NO.* LIST 0770 HED DISPLAY / / TATION , HED DESCRIPTION ITEM SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE RESOLITTION/ NOTES 645 THE " ISOLATION GROUP SAI 1.1.4.M 6.7.2.4 24 SPDS 24 ENHANCEMENT A FIX 1988 REP MCE "ISOUTION GROUP 4 DEMAND STATUS" LABEL DOES CC 1 SFDS SPDS 25 REFUELING DE W S STATUS" WITH ., NOT REFLECT CURRENT SPDS 26 "ISouTION GROUP SIGNAL" WORDING SPDS 27 646 NOT ENOUGH ORDINATE SAI 1.1.4.A 6.7.2.4 25 SPDS 25 ENHMCEMENT A FIX 1988 INCLUDE INTERMEDIATE ! VALUES ARE SHOWN ON THE CC 5 SPDS 27 SPDS REFUELING NUMBERS AT "40" ON DW l TREND GRAPH PRESS, "200" ON DW TEMP. AND "-100" ON SUPPR POOL TEMP 647 DEMARCATION AND SPACING SAI 1.1.5.C 6.7.2.5 26 .SPDS 26 ENHANCEMENT A FIX 1988 DEMARCATION AND SPACING l OF INFORMATION BLOCKS ARE SPDS REFUELING. WILL BE IMPROVED , NOT CLEAR t i 648 GROUPING IS NOT CLEAR SAI 1.1.5.C 6.7.2.5 27 SPDS 27 ~ ENHANCEMENT A FIX 1988 CROUPING WITHIN THE SPDS REFUELING DISPLAT WILL BE IMPROVED 649 LINES FROM THE VALVE SAI 1.1.4.A 6.7.2.4 28 SPDS 28 ENHANCEMENT A CORRECTION 1986 THE LINES WERE t MIMICS DO NOT POINT TO SPDS MADE REFUELING REPOSITIONED FOR ! THEIR CORRESPONDING BAR IMPROVEMENT l CHARTS AS CLEARLY AS THEY j COULD 650 LABELS DO NOT COVER AS SAI 1.1.4.N 6.7.2.4 29 s SPDS 28 ENHANCEMENT A FIX^ 1988 WIDER ONE-LINE LABELS MUCH AS THE WIDTH OF THE SPDS REFUELING ~ WILL BE PLACED IN THE I DATA FIEIS AS THEY COULD DISPLAT WHERE POSSISLE. i I j f 4 4
- , ,. m - . . . . _ -
APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT RECORD CHECK- NUREG- ENHANCEMENT CATEGORY IMPLDIEN-NO.* LIST 0770 HED DISPLAY / / TATION HED DESCRIPTION ITEM SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE RESOLUTION / NOTES 651 GENERAL READABILITY OF SAI 1.1.5.C 6.7.2.5 30 SPDS 28 ENHANCDIEhT A FIX 1988 INTEGRATE WITH HED THE DISPLAY COULD BE SPDS . REFUELING _29 SPDS TO ENHANCE t IMPROVED. SUBCROUPS OF READABILITY OF DATA ARE NOT EASILY DISPLAY SPOTTED , 652 SOME SCALES IN THE BAR SAI 1.1.4.A 6.7.2.4 31 SPDS 29 MODIFICATION II OTHER 1989 INTEGRATE FIX WITH HED's CHARTS SHOW MORE SPDS SPDS 2A/2B MOD REFUELING 32 SPDS, 34 SPDS, NUMERICAL VALUES THAN 58 SPDS, 59 SPDS, { OTHERS 60 SPDS AND 62 SFDS ! 653 TOP AND BOTTOM OF THE BAR SAI 1.1.4.D 6.7.2.4 32 SPDS 29 MODIFICATION. II OTHER 1989 INTEGRATE FIX WITH HED's SCALES ARE VERY DIFFERENT SPDS SPDS 2A/2B IMD REFUELING 31 SPDS, 34 SPDS, -1 EVEN THOUGH THE FULL 58 SPDS, 59 SPDS, RANGE FOR ALL BAR CHARTS 60 SPDS AND 62 SPDS ARE VERY SIMII.f.k i i 654 "SJAE EFFLUENT" " CURRENT SAI 1.1.4.A 6.7.2.4 33 SPDS 29 ENHANCDiENT A CORRECTION 1986 THE ARROW'S SHAPE IMPkOVED VALUE" ARROW LOOKS LIKE A SPDS MADE REFUELING WHEN COMPUTER RESPONSE , DIAMOND AND NOT A TIME WAS IMPROVED TRIANGLE 655 " CURRENT VALUE" ARROWS SAI 1.1.4.A 6.7.2.4 34 SPDS 2A/2B MODIFICATION II CORRECTION 1986 THE ARROW'S SHAPE IMPROVED ARE MISSING Ok MISSHAPEN SPDS MADE REFUELING WHEN COMPUTER RESPONSE l TIME WAS D: PROVED. CURREhT l VALUE ARROWS ARE NOT MISSING. 656 THE DRYWELL PRESSURE SAI 1.1.5.C 6.7.2.5 35 SPDS 3B ENHANCEMENT A FIX 1988 THIS AREA WILL BE BOXED IN DISPLAY IS NOT EASILY SPDS SPDS 3A REFUELING OR RELOCATED TO IMPROVE FOUND VISIBILITY OF DKfWELL PRESSURE a l
- i
O O O i APPENDIX A l SPDS SURVEY RESULTS AND ASSESSHENT , RECORD NO. CilECK- NIIREC- ENilANCEMENT CA1ECORY 1HPI.EHEN-LIST 0700 IIED DISPLAY / / TATION llED DESCRIPTION ITEll SECTIDN ID. ID. HDDIFICATION PRIORITY ACTION SCilEDillE resol.UTION/ NOTES 657 THE AI.PilABETIC SAI 1.1.5.C 6.7.2.5 36 SPDS 3B ENilANCEHEttr A FIX 1988 TilESE ALPilABETIC , DESIGNATORS "A" AND "B" SPDS SPDS 3A REFUELING IV.SICHA1DRS WILL BE PLACED ARE IDST Ill TIlE LABELS IN Q110TES TilEY ARE IN 658 Tile "Il0TE" TO Tile IISER IS SAI 1.1.5.C 6.7.7.5 37 SPDS ~37 ENilANCEMElfr A FIX 1988 Tile DISPLAY WII.L BE NOT CIEARI.Y llEFINED AND SPDS REFilELING CllANCED SO 111AT 111E NOTE
" ENGINEERING l.IHIT lilCil Will NO IDNGER BE FOR DRYWElL..." IS APPLICABLE AND CAN BE AWFWARD To READ REMOVED 659 Tile I.DCARITilHIC SCAI.E IIAS SAI 1.3.2.D 6.7.2 38 SPDS 38 ENilANCEMENT A CORRECTION 1986 Tile EX11tA TICK MARKS WERE EXTRA TICK HARKS AND TIIE SPDS MADE REFUELING REMOVED .'ND ABSCISSA MARKS i ABSCISSA VAI.IIES ARE CENTERED UNDER Tile PROPER ENTERED llNDER Tl!E WRONC TICK HARKS TICK HARKS 660 Tile DISPl.AY IS DIFFICitt.T SAT 1.1.4.A 6.7.7.4 39 SPDS 39 ENilANCEMENT A FIX 1988 Tile RPV PRESSl!RE AND 1.EVEL TO READ AND Tile sal 1.1.4.E 6.7.2.5 SPDS REFUELING Wil.L BE CROUPED FUR INFORitATION IT IS SAI 1.1.5.A 1HPROVEMElff - Tile TII.ES COI4VEYING IS NOT EASY To SAI 1.1.5.B WIII REHAIN AS IS SO *IU GitASP HA1NTAIN CONSIS1ENCY RF"IVEEN Tile DISPLAY AND E0P'S 661 11A.10R SilBCROUPS IN Tile SAI 1.1.5.C 6.7.2.5 40 SPDS 39 ENilANCEMElfr A FIX 1988 SUBCRollPS WILL BE DISPLAY Sil0VI.D BE SPDS REFilEl.1 NG SEPARATED HORE Cl.EARLY SEPARATED I 662 Tile 500 PSIG TICK CC 6 6.7.2 41 SPDS 10 ENilANCEMENT A FIX 1988 Tile TICK MARK WILL BE MARK DOES NOT & 4.4.3.2 SPDS SPDS 24 REFUELING CllANGED TO 450 PSIC CORRESPOND TO Tile NUREG VALUE RllR AND CS PRESSURE 0835 PERMISSIVE VALUE OF 450 PSIC
G L . APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT RECORD CHECK- NUREG- ENHANCEMENT CATEGORT IMPLEMEN-50.* LIST 0770 HED DISPLAT HED DESCRIPTION
/ / .TATION ITDI SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDUI.E RESOLUTION / NOTES 663 NO WARNING LOW SETPOINT CC 4 6.7.2 & 42 SPDS 10 ENHANCEMENT A FIX 1988 A WARNING LOW SETPOINT OF FOR RPV PRESSURE IN MODE 4.4.2.2- SPDS I NUREG REFUELING 935 PSIG WILL BE USED FOR 0835 RPV PRESSURE WHILE IN MODE 1
664 THE POSITIONS OF CC 5 6.7.2.4 43 SPDS 20 ENHANCEMENT A FIX 1988 INDICATOR BOXES "ANY APRM SPDS SPDS 21 THE BOIES WILL BE SWAPPED - INOPERATIVE", " ANT SRM REFUELING INTEGRATED WITH HED 13 SPDi INOPERATIVE", "ANY APRM UPSCALE", AND " ANT SRM UPSCALE" ARE INCONSISTENT AMONG THE BAR AND TREND DISPLAYS 665 NORMAL LEVEL VALUES OF CC 6 6.7.2.4 44 SPDS 22 ENHANCEMENT A FIX 1988 INCLUDE A NORMAL VALUE OF WATER LEVEL NOT SHOWN ON SPDS NARROW RANGE INDICATIONS REFUELING 36" ON NARROW RANGE A, B AND C INDICATIONS - INTEGRATE
'WITH HED 15 SPDS.
666 NO DISTINCTION BETWEEN CC 6 6.7.2 & 45 Generic to MODIFICATION II OTHER MOD 1989 ASSESS FURTHER AND SCALE NUMERALS AND E0P 4.4.2.2- SPDS all displays ACTION LEVELS THROCGH REFUELING INTEGRATE WITH HED I42S ASSOCIATING THE LATTER WITH A SPECIFIC SYMBOL OR MARK 667 THE WARNING HIGH PRESSURE CC 4 6.7.2.4 & 46 SPDS 24 ENHANCEMENT A FIX 1988 SETPOINT ON THE "DRYWELL 4.4.2.2- SPDS SPDS 26 UTILIZE A WARNING VALUE OF PRESSURE" BAR IS NUREG REFUELING 0.6 SPIG IN THE DISPLAY INCONSISTENT WITH THE 0835 VALUE USED ON THE OVERVIEW DISPLAY
r
) l l APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT RECORD CHECK- NUREG- ENHANCEMENT CATEGORY DIPLEMEN-No.* LIST 0770 HED DISPLAY / / TATION HED DESCRIPTION ITEM SECTION ID. ID. MODIF! CATION PRIORITY ACTION SCHEDULE RESOLUTION / NOTES 663 THE NOMENCI.ATURE USED ON CC 1 6.7.2 47 SPDS 24 ENHANCEMENT A FIX 1988 REPLACE "CONTAINhENT
" CONTAINMENT RADIATION" SPDS SPDS 25 REFUELING RADIATION" WITH "DRYWELL 3AR DOES NOT DISTINGUISH RADIATION" 3ETWEEN PRIMARY AND SECONDARY CONTAIh? TENT 669 THE USE OF THE CC 1 6.7.2 48 SPDS 25 ENHANCEMENT A FIX 1938 USE " CURRENT VALUE" AND DO ABBREVIATION " CUR VAL" IS SPDS SPDS 27 REFUELING NOT ABBREVIATE WHERE NOT STANDARD POSSIBLE 670 THE RANGE FOR " MAXIMUM CC 5 6.7.2 & 49 SPDS 26 ENHANCEMENT A FIX 1988 REPLACE BAR RANGE OF 400*F DRYWELL TEMPERATURE" BAR 4.4.3.2- SPDS REFUELING WITH 350'F IS INCONSISTENT WITH NUREG PANEL INDICATIONS 0835 671 THE ALARM HIGH SETPOINT CC 6 6.7.2 & 50 SPDS 26 MODIFICATION II OTHER MOD 1989 ASSESS FURTHER AND FOR " AVERAGE SUPPRESSION 4.4.2.2- SPDS REFUELING INTEGRATE WITH HED 55T POOL TEMP" IS NUREG INCONSISTENT WITH E0P's 0835 ENTRY CONDITION 672 THE ALARM HICH SETPOINT CC 6 6.7.2 & 51 SPDS 26 MODIFICATION II OTHER MOD 1989 ASSESS FURTHER AND FOR " SUPPRESSION POOL 4.4.2.2- SPDS REFUELING INTEGRATE WITH HED SST LEVEL" IS INCONSISTENT NUREG WITH E0P's 0835 673 THE WARNING LOW SETPOINT CC 6 6.7.2 & 52 SPDS 26 MODIFICATION II OTHER MOD 1989 ASSESS FLTTHER AND FOR " SUPPRESSION POOL 4.4.2.2- SPDS REFUELING INTEGRATE WITH HED LEVEL" IS NOT AVAILABLE - 51 SPDS INCONSISTENT WITH E0P's
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O O O l APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT l'FCORD NO. CllECK- HUREG- ENilANCEMEtrr CATECORY THPl.EHEN-i LIST 0700 llED DISPLAY / / TATION ilED DESCRIPTIOff 11Ett SECTION ID. ID. HDDIFICATION PRIORITY ACTION SCllEDillE RESOLlrt10N/ NOTES 53 SPDS 26 ENilANCEMENT A FIX 1988 SPEI.T. OllT LIMIT WifERE 674 NON-STANDARD CC 1 6'.7.2 ARBREVIATIONS ARE REING SPDS SPDS 27 RERIELING POSSIBI.E AND IlSE SUPPR FOR IISED; LIH FOR I.lHIT, SUPP SPDS 28 SUPPRESSION ABBREVIATION FOR SUPPRESSION SPDS 33 675 NO DIFFERENTIATION CC 1 6.7.2 & 54 SPDS'26 ENIIANCEMENT A FIX 1988 CNANGE TITTE OF DISPLAY TD BETWEEN PRIMARY AND 4.4.2.2- SPDS REMIELING "PR1H CONTAlfetENT SECONDARY CONTAINMENT NUREG INTECRITY BAR" j 0835 676 NO DISPLAY IS AVATI.ARIE CC 6 6.7.2 & ss SPDS 26 HDDIFICATION 11 OTilER HOD 1989 DEVELOP A SECONDARY
]
TilAT CORRESPONDS TO Tilh 4.1 SPDS REMIELING CONTAIN>ENT DISPLAY AND j SECONDARY CONI'AINilFNT NUREG INTEGRATE WITil llED 142S 1 SEcTION iw luE E0P'S 0835 677 INCONSISTENT llSE OF CC 5 6.7.2 56 SPDS 28 ENIIANCEMENT A FIX 1988 IlSE " SUPPRESSION POOL t m ENCI.ATIIRE BE1 WEEN CC 6 SPDS REFilELING filHIC" INSTEAD OF SPDS, FOP'S, AND PANEL "SilPPRESSION CilAHRER INFORMATION HIMIC" - USE "10RUS l.1 HITS" INSTEAD OF SilPP CllBR LIMITS" 678 SETPOINTS FOR RARS A-II CC 5 6.7.2 & 57 SPDS 28 EHilANCEMENT A 'FIX 1988 HAKE SETPOINTS CONSIS1ENT ARE INCONSISTENT WITil Tile 4.4.2.2- SPDS RERIELING BE1 WEEN Tile 'IWO DISPLAYS SilPPRESSION POOL TEMP BAR NUREG USED IN DISPLAY SPDS 26 0835 i
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4 . APPENDIX A I SPDS SURVEY RESULTS AND ASSESSMENT RECORD CHECK- NUREG- ENHANCEMENT CATEGORY IMPLEMEN-0.* LIST 0770 HED DISPLAY / / TATION j HED DESCRIPTION ITEM JEC* ION ID. ID. MODIFICATION PRIOP.ITY ACTION SCHEDULE RESOLUTION /NCTES 679 ENTRY TO EMERGENCY AND CC 6 6.7.2 & .58 SPDS 29 MODIFICATION II OTHER MOD 1989 ASSESS FURTHER DISPLAYED INFORMATION FOR 4.2 - SPDS SPDS 2A REFUELING INTEGRATE WITH HED REACTOR EQUIPMENT COOLING NUREG SPDS 2B 142S (REC) EFFLUENTS NOT 0835
. AVAILABLE - INCONSISTENT WITH E0P's ! 680 ERP AND RX BLDG VENT CC 6 6.7.2 & 59 SPDS 29 MODIFICATION II OTHER MOD 1989 ASSESS FL*RTHER AND EFFLUENTS THAT ARE USED 4.2 - SPDS SPDS 2A REFUELING INTEGRATE WITH HED IN E0P's NOT AVAILABLE - NUREG 142S INCONSISTENT WITH EOP's 0835 i
j 681 MISSING INTERMEDIATE CC 5 6.7.2 60 SPDS 29 MODIFICATION II OTHER MOD 1989 INTEGRATE FIX WITH HED NUMERALS ON SCALES FOR SPDS SPDS 2A REFUELING 31 SPDS, 32 SPDS,
- A0G AND RX BLDG EFFLUENTS 34 SPDS, 58 SPDS, 4
59 SPDS, AND 62 SPDS i 682 SITE BOUNDARY RADIATION CC 6 6.7.2 & 61 SPDS 29 MODIFICATION II OTHER MOD 1989 INTEGRATE WITH i NOT AVAILABLE ON THE 4.2 - SPDS SPDS 2A REFUELING INSTALLATION OF CLSSS A i DISPLAY - INCONSISTENCY NCREG DOES ASSESSMENT MODEL { WITH THE E0P's 0835 J l f I 1
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APPENDIX A SPDS SURVEY RESULTS AND ASSESSMENT RECORD CHECK- NUREG- EhhNCEMENT CATECORY IMPLEMEN-NO.* LIST 0770 HED DISPLAY / / TATION HED DESCRIPTION ITEM SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE RESOLUTION / NOTES 633 IhCONSISTELT USE OF CC 5 6.7.2 & 62 SPDS 29 EhhNCEMENT A FIX 1988 THESE SETPOINTS WILL WARNING AND ALARM CC 6 4.4.2.2- SPDS SPDS 2A REFUELING BE MADE CONSIS m T SETPOILTS OF THE SPDS NUREG DISPLAYED VARIABLES 0835 AGAINST THE E0P ENTRY CONDITIONS AND PANEL HARDWIRED DISPLAYS 684 TWO-DIMENSIONAL PLOT IS CC 6 6.7.2 & 63 SPDS 30 ENHANCEMENT A FIX 1988 MAKE PLOTS CONSISTEXT INCONSISTENT WITH E0P 4.4 - SPDS REFUELING PLOT NUREG 0835 685 THE PERMISSIVE AND CC 1 6.2.2 64 All Level 3 ENHANCEMENT A FIX 1988 THE NONPERMISSIVE PORTION NONPERMISSIVE PORTIONS OF SPDS Displays REFUELING OF THE LEVEL 3 DISPLAY 2D THE PLOT ARE NOT LABELED PLOTS WILL BE LABELED 636 DARK BLUE COLOR CODING IS CC 3 6.7.2.7 & 65 All Level 3 ENHANCEMENT A 6 NO ACTION None OF THE AVAILABLE COLORS TO USED TO IDENTIFY THE 4.4.3.2 - SPDS Displays USE FOR THE NONPERMISSIVE NONPERMISSIVE REGIONS OF NUREG AREA OF THE 2D PLOT THE THE 2D PLOTS - 0835 DARK BLUE COLOR IS THE INSUFFICIENT CONTRAST MOST CONTRASTING BETWEEN LETTERING COLOR AND BACKGROUht 687 INCORRECT IDENTIFICATION CC 6 6.7.2 66 SPDS 33 ENHANCEMENT A CORRECTION 1986 THE IDENTIFICATION OF THE OF PRIMARY CONTAINMENT & 4.4 - SPDS MADE REFUELING DESIGN PRESSURE LIMIT AND EMERGENCY LIMITS - NUREG PRESSURE LIMIT IN THE EMERGENCY LIMITS FOR 0835 DISPLAY WERE CORRECTED DESIGN PRESSURE AND PRESSURE LIMITS ARE INCORRECTLY SWAPPED P
, _ _ . . _ . . . _ ~ . _ _ .
. . - . = _ _ _ _ ._
O O O APPENDIX A SPDS SURVET RESULTS AND ASSESSMENT RECCRD CHECK- NUREG- ENHANCEMENT CATEGORY LVLEMEN-NO.* LIST' 0770 HED DISPLAY '/ / TATION HED DESCRIPTION ITEM SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE- RESOLUTION / NOTES boS NOMENCLATURE FOR DISPLAY CC 1 6.7.2 67 SPDS 33 ENHANCD'ET A FIX 1968 USE " PRIMARY CONTA. ORIENT HEADING DOES NOT SPDS REFUELING PRESS LIMITS" AS A HEADLNG DIFFERENTIATE SETWEEN FOR THIS DISPLAY PRIMARY AND SECONDARY CONTAINMENT 689 THE 2D PLOTS FOR DW CC 5 6.7.2 68 SPDS 35 MODIFICATION II NO ACTION NONE THIS PLOT WILL BECOME HYDROGEN AND OXYCEN DO & 4.4 - SPDS SPDS 36. IMPORTANT WHEN EOP'S ARE NOT SERVE ANY FUNCTION AS NUREG UPDATED TO INCLUDE THE THE GRAPHS EXHIBIT NO 0835 HYDROGEN CONTROL SECTION CHANGE IN THE CONCENTRATION AGAINST DRYWELL PRESSURE 690 INCONSISTENT USE OF CC 6 6.7.2 69 SPDS 36 ENHANCEMENT- A FIX 1988 USE " TORUS" FOR NOMENCLATURE BETWEEN SPDS SPDS REFUELING SUPPRESSION CHAMBER AND THE E0P's 69I NON-STANDARD USE OF CC 1 6.7.2 70 SPDS 3A ENHANCEMENT A FIX 1988 USE RHR A. RHR B, CS A, EQUIPMENT ID's SPDS SPDS 38 REFUELING AND CS B FOR EQUIPMENT SPDS 39 ID'S - INTECRATE WITH HED 36 SPDS i l
A.2 CCMM.!ANCE CHECXLIST - - - - - - COMPLIANCE l No: wr;ta 1.1 CRT DISPLd GUI:ELINE3 Non-c:moiianca E.tplanation Section N/A' Yes Numoer 1.1.1 CRT Disolay Charactaristics . . . . . . . . . . ! A. Readanility ............. . B. Re fl ected Gl are. . . . . . . . . . . . I l C. Screen Luminanca . . . . . . . . . . . . . I I
- 0. Luminanca Contras: . . . . . . . . . . . . I I
--E. Geometric Dist:rtion . . . . . . . . . . . I i F. Resolution ............... I ' '
Regeneration Rata. . . . . . . . . . . G. ~ l I
. i H. CRT Display Controls . . . . . . . . . . I i 1.1.2 Symools and Characters ............
A. Symool Sf:e ............... l l B. - Alpha-Numoeric Charactar Sf:e. . . . . . . I I I C. Charactar Width-to-Height Ratio. . . . . . I I I
- 0. Streke-Width-to-Character-Hei I '
E. Graphics . . . . . . . . . . ght Ratio . .
....... 3 I F.-
Charactar and Symcol Separation. . . . . . i I
-G. Character Style Font . . . . . . . .... l tt2 =erator-oisa'er a 1 :$caa49-A. Viewing Distanca . . . . . . . . . . . .
B.- Viewing Angles . . . . . . . . . . . . . I C. Screen Lccation, Seatad Operators. . . . . I I
- 0. Screen Location, Standing Operators. . . . I I i
E. Mounting in Consoles . . . . . . . . . . . I I F. V i s i b i l i ty o f Da ta . . . . . . . . . . . . I I I 1.1.4 Data Presentaien or:::at . ........... A. Usability of Data ............ B. Illustrations .............. ' I Charactar Groucing . . . . . . . . . . . . C. I I Maintenance of Orcering. . . . . . . . . . D. I I E. ! Presentations of Identical Data. . . . . . ' ' ' F. Menu Designators . . . . . . . . . . . . . ' I I
-G. Lists .................. I ' I H. Taol es and Graohs. . . . . . . . . . . . . I 8 I Hyp ena ti o n . . ' . . . . . . . . . . . . . .
I. ' ' ' l J. Alignment ................ I i I l ' K. Periods ................. I ' ' L. S tandardi:ed . leids. . . . . . . . . . . . I ' ' l M. Data Greuo Lacel ing. . . . . . . . . . . . I ' ' O N. Label Placement. ............. ' ' ' O. L ab e l O ri en ta ti o n . . . . . . . . . . . . . ' ' P. Label H f gn11gn-ing . . . . . . . . . . . . I ' l ' l O. Coti en Lace! s . . . . . . . . . . . . . . . ' ' {
'M/A = Not a001icscle -ld-
A.2 CCMPt.IANCE CHECXLIST ..,.-p COMPLIANCE ! O
~ ' '
No: ..W ri te U l.1 CRT DISPLAY' GUIDELINES (CONTINUED) Non-compifance Explanation Section N/A* Yes Numoer _1.1.5 Screen Layout and Structuring . . . . . . . . . _ _ A. Organi::ation of Data . . . . . . . . . . . B. Location of Data Groups. . . . . . . . . . I C. Demarcation of Data Subgroups. . . . . . . I '
~
O. Use Frequency Ranking. . . . . . . . . . . I I
~
E. Alpna-Numeric Ranking. . . .'.'. . . . . . l ~ ~~ F. Separation of Paragraphs . . . . . . . . .
~ ~ G. Selection Designators. . . . . . . . . . .
H. P a ge D esi gna ti on . . . . . . . . . . . . . . I. Continuous Numbering . . . . . . . . . . . J. Placement of Instructions. . . . . . . . . K. Urgent Messages ............. i L. Use of Cursor .............. M. Screen Loading . . . ... . . . . . . . . . N. Trend Plot Scales. . . . . . . . . . . . . _ 1.1.6 Messages. . . . . . . . . . . . . . . . . ... . A. Messages, General. . . . . . . . . . . . .- - t __ B. Message Content. . . . . . . . . . . . . . O _-- _ _ c-0. use or aro ats C ontent o f P romp ts . . . . . . . . . . . . E. Prempt Infonnation Sequence. . . . . . . . _ F. Use of Error Messages. . . . . . . . . . . G. Error Correction Guidance. . . . . . . . . l _. H. Error Correction Ease. . . . . . . . . . . __I. System Status Feedback Messages. . . . ... I f J. Sel ection Feedback . . . . . . . . . . . . X. Delay Feedback . . . . . . . . . . . . . . L. Activity Completion Feedback . . . . . . . 1.1.7 Graphic Coding and Highlighting . . . . . . . . 1 A. Use of Highlighting ........... __. B. Consistent Approach ........... l
. _ . C. Contrast Enrichment ........... l
- 0. Flicker or Blinking ...........
[ E. Blink Rates. . . . . . . . . . . . . . . . l F. Inverse Video. . . . . . . . . . . . . . .
~ _ ~~ _ G. Use of Graphic Coding. . . . . . . . . . . I H. Graphic Code Consistency . . . . . . . . . I I I. Gecmetric Shace Coding . . . . . . . . . . I i
_ J.- Number of Symbols. . . . . . . . . . . . . I I r l K. U s e o f C ol o r . . . . . . ,. . . . . . . . . I I I L. Col or Meaning. . . . . . . . . . . . . . . I i ! M. Red-Green Ccmbinations . . . . . . . . . . < O- I I I l -
*N/A = Not applicable
A.2 CCMP'.IANCE C"ECXLIIT __ CCMcLIANCE l C~ No: Wr ta 1.1. CRT CISPLAY GUIDELI!iE3 (CCIITUlUED) Ncn-c:molianca J E.tplanatien Secticn N/A' Yes Num::er 1.1.8 Multi-P age C:nsiderations . . . . . . . . . . .
' A. Ocera:=r Memory. . . . . . . . . . . . . .
~~ '~-- -~
- 3. A u ci t Tra i l . . . . . . . . . . . . . . . . I I A C. l.ccation Refe-ences. . . . . . . . . . . . I I I
. Ocerat:r Centrol . . . . . . . . . . . . . ' ' '
.... -'~--..E. --
- t. caticn Consistancy . . . . . . . . . . . I I I
'N/A = Nc a;:clicable
A.2 CCMPLIANCE CHECKLIST _ COMPLIANCE No: Write O i.2. Car. DIS,tAv. aEtArED GuIDEtINES Non_com,14anc, Explanation Section N/A* Yes Numoer 1.2.1 Sof tware Securi ty . . . . . . . . . . . . . . . _. A. Au thori zati on. . . . . . . . . . . . . . .
~
B. , Secure S torage . . . . . . . . . . . . . . C. ' Editing ................. D. Acknowledgement. . . . . . ........ 1.2.2 Operator / Computer Dialogue. . . . . . . . . . .
~ ~~
A. Language Characteristics . . . . . . . . .
~ ~
B. Entry Length . . . . . . . . . . . . . . ."
~~~
C. 0. Abbreviations. . . . . . . . . . . . . . . I Error Avoi dance. . . . . . . . . . . . . . l 1.2.3 Prompting and Structuring . . . . . . . . . . . A. Operator Requests. . . . . . . . . . . . . Correction of Data . . . . . . . . . . . .
~
~ B. 1 C. Mode / File Display. . . . . . . . . . . . .
D. Specific Error Correction. . . . . . . . .
] 17- E. Entry File . . . . . . . . . . . . . . . . I O _
1.2.4 . Dete Entry - xeyeoeres
~
A. Alpha-Numeric Keyboard Arrangement . . . . B. Number Keyboard Arrangement. ....... C. Use of Multiple Keyboards ........ D. K ey Me a s u remen ts . . . . . . . . . . . . . , E. Key Displacement and Resistance. . . . . . I l F. G. Positive Indication. . . . . . . . . . . . I Keyboard Slope . . . . . . . . . . . . . . I
~
H. I. Visual Feedback. . . . . . . . . . . . . . 8 i Rel evant Keys. . . . . . . . . . . . . . . I I
. _ 1.2.5 Computer Function Control s. . . . . . . . . . .
~
A. Control Design . . . . . . . . . . . . . .
~^
B. Labeling and Ncmenclature. . . . . . . . . I I
~~ ~
C. 0. Master Control . . . . . . . . . . . . . . I Function Control s. . . . . . . . . . . . . 1.2.6 Other Control Devices . . . . . . . . . . . . .
~
A. Location . . . . . . . . . . . . ,. . . .
- 8. Speed .........: ........ I C. Accuracy . . . . . . . . . . . . . . . . . I i D. Displacement . .............. i I O
~
*N/A = Not applicable
A.2 CCMPLIANCE CHECXLIST
'O l.2 CRT DISPLAY RELATED GUIDELINES (CONTINUED)
COMPLIANCE a= an a Non-ccmoliance Explanation
. Section N/A* .Yes .Numcer 1.2.7 Ccmputer Response Time To Operator Queries . . .
A. Maximum Response Time . . . . . . . . . . . B. Response Delay Messages . . . . . . . . . . 1.2.8 Access Aids. . . . . . . . . . . . . . . . . . .
~ ~ ~
A. Computer System Procedures. . . . . . . . . B. Data Point Indices. . . . . . . . . . . . . ' 1.2.9 Printer Characteristics. . . . . . . . . . . . . ' A. Printer Applications ........... B. Display Copies .............. C. Fom of Printed Information . . . . . . . . D. P rinter Speed . . . . . . . . . . . . . . . E. Printer Operation . . . . . . . . . . . . . F. Print Copy Accessibility. . . . . . . . . . 1.2.10 Alarm Messages . . . . . . . . . . . . . . . . . --
'O ~~~~ ~
4.
~~B .
Aier= necores . . . . . . . . . . . . . . . Alarm Sequence'~. .'. .'.'.' .'. . . . . . C. Operator-Requested Printout . . . . . . . . D. Alarm Identificaticn ........... E. Alarm Discrimination ........... F. Consistent Terminology. . . . . . . . . . . 1.2.11 draph~and Table Requirements . . . . . . . . . . A. Shape of Function . . . . . . . . . . . . . B. Inte rpol ati on . . . . . . . . . . . . . . . I C. D. G ri d s . . . . . . . . . . . . . . . . . . . I _ Tables. . . . . . . s . .......... I
- 1.2.12 Use of Auditory Signal s. . . . . . . . . . . . .
l ' ~ A. Dedicated Use . . . . . . . . . . . . . . . B. Local i::ation. . . . . . . . . . . . . . . . l i C. Selection . . . . . . . . . . . . . . . . . I 1.2.13 Audi tory Signal Meaning. . . . . . . . . . . . . 1.2.14 Audi tory Coding Techniques . . ,. . . . . . . . . . A. Distinctive Coding. . . . . . . . . . . . . t B. Pulse Coding. . . . . . . . . . . . . . . . I I ! C. Frequency Change Coding . . . . . . . . . . I I Discrete Frecuency Coding . . . . . . . . . O. 1 -
. E. Coding by Intensity . . . . . . . . . . . . 8
*N/A = Not applicable 1
A.2 CCMPLIANCE CHEC:G.IST n COMPLIANCE () No: Wr1te 1.2 CRT DISPLAY RELATED GUIDELINES (CONTINU20) Non-compliance Explanation o Section N/A* Yes Numcer , 1.2.15 P.ropagation of Auditorf Signals. :. . . . . . . . 1 O A. Direction of Sound. . . . . . . . . . . . . B. Audibility. . . . . . . . . . . . . . . . . 1.2.16 Auditorf Signal Frequency. . . . . . . . . . . . A. Range . . . . . . . . . . . . . . . . . . . B. Bandwidth . . . . . . . . . . . . . . . . . " I 1.2.17 Auditary Signal Intensity. . . . ! . . . . . . . A. B. General Comfort . C. Maximum Intensity . . . . . . . . . . . . . I 1.2.18 Auditorf Signal Reliability. . . . . . . . . . . A. Failure of Alarm Circuitry. . . . . . . . . B. F al se Al a rms . . . . . . . . . . . . . . . . e
~3 C. System Test . . . . . . . . . . . . .... ~.)
1.2.19 Cl eared Al a rns . . . . . . . . . . . . . . . . .
- d. Audi torf S'ignal s . . . . . . . . . . . . . .
B. Visual Signals. . . . . . . . . . . . . . . 1 1.2.20 Auditory signal Detection. . . . . . . . . . . . A. I n te n s i ty . . . . . . . . . . . . . . . ~ B. Control . . . . . . . . . . . . . . . . . . .. C. Limits. . . . . . . . . . . . . . . . . . . I D. E. Detection Reset . .
................. I i
~
................. 8 i F. Identi fica tion. . . . . . . . . . . . . . . I i 1.2.21 Audi to rj Codi ng. . . . . . . . . . . . . . . . .
A. B. Local iza tion. . . . . . . . . . . . . . . . ~ l I P ri o ri ti z a ti on . . . . . . . . . . . . . . . I 1.2.22 P rio ri ti za ti o n . . . . . . . . . . . . . . . . . A. Levels of Priority. . . . . . . . . . . . . 1 B. P riori ty Codi ng . . . . . '. . . . . . . . . I I Ill (O >
*N/A = Not applicable
A.2 COMPLIANCE CHECXLIST 3 6SMPLIANct (V - 1.3 GENERAL OISPLAY GUIDELINES No: Writa Non-ccmpliance Explanation Section N/A Yes Numcer
-h3.1 Other Information to be Displayed ....... I l-A. Task Analysis . . . . . . . . . . . . . . .
B. "Coiipletene' s s of Information . . . . . . . . C. Unnecessary Infomation . . . . . . . . . . D. Redundancy ................ E. Demand Information Versus Status In fo ma ti on . . . . . . . . . . . . . . . . F. Display Failure . . . . . . . . . . . . . . - 1.3.2 Usability of Displayed Values ......... A. B. Sca l e Sel ec ti on . . . . . . . . . . . . . . Elimination of Operator Conversion ... - C. Percentage Indication . . . . . . . . . . I
- 0. Scale Range . . . . . . . . . . . . . . . . !
1 E. Scale Size ............... F. Sensi ti vi ty . . . . . . . . . . . . . . . . . I I i 1.3.3 R ea d a .... b i ..l i .ty ". . '. ' . . . . . . . . . . . . . . .
'A. Character Height . . . . . . .'. . . . . .
B. Type Style ................ ' i
-C.
D. Contrast . . .'. . . . . . . . . . . . . . 1 Character Dimensions and Spacing ..... I 1.3.4 Printing on the Display Face . . . . . . . . . .
*A. Provision of Needed Message . . . . . . . . '
B. Avoidance of Extraneous Iter:s . . . . . . . l
'C. B rev i ty . . . . . . . . . . . . . . . . . . l
- 0. Ab b revi a ti o ns . . . . . . . . . . . . . . . I E. Consistency with Precedures . . . . . . . . I F. Indication of Transformations Needed. . . .
1.3.5 Scale Markings . . . . . . . . . . . . . . . . .
~~ ~
A. Use of Graduations ............
~ B. Graduation Height . . . . . . . . ..... ! I C. Values Indicated by Unit Graduations ... I i D. Scale Ccmpatibility . . . . . . . . . . . . I I
~
E. Linear Versus Lagarithmic Scales. . . . . . I I I F. Multiscale Indicators . . . . . . . . . . . I I L.3.5 Color Coding ................. A. Redundancy ................ l () 8. C. Numcer of Colors ............ Meaning of Colors . . . . . . . . . . . . . . i I l l-
- *N/A = Not a;
- pliceble
A.2 CCMPLIANCE CHECKLIST COMPLIANCE 3 - (V ' 1.3 GENERAL DISPLAY GUIDELINES (CONTINUED) No: Wri te Non-compliance E.xplanation Section . N/A* Yes Numoer
~~
D. Consistency of Meaning .......... I f _ E. Principles of Color Selection . . . . . . . 1.3.7
~
Directionali'ty ~of Movement and Numbering with Fixed-Scale Moving Pointer Meters . . . . . A. Circular Scales . . . . . . . . . . . . . .
~~
- 8. Vertical Straight Scales. . . . . . . . . .
C. ' Horizontal' Straight Scales. . . . . . . . . - 1.3.8 Pointers . . . . . . . . . . . . . . . . . . . . A. ' Pointer Tip Form ............. B. Pointer Positioning Relative to Scale . . . C. Pointer Visibility ............ I 1.3.9 Zone Marking . . . . . . . . . . . . . . . . . . 1.3.10 Orientation of Markings on Fixed-Scale Meters . . . . . . . , . . . . . . . . . . . . . A. Numeral Orientation . . . . i . . . . . . .
- 8. Zero-Point Orientation ..........
'. C. End-Point Indication on Partial-Revolution Scales . . . . . . . . . . . . .
1.3.11 Moving-Scale Meters .............. 1.3.12 Characteristics and Problems 'of Light I n di ca tio rs' . . . . . ' . . i , ; . . . . . . . . .- A. Precautifons to Assure Availability ....
- 8. Precautions to Assure, Unambiguous
~~, ~
Sensing by Operators. . . . . . . . . . . . C. Precautions to Avoid Misinter-pretation . . . . . . . . . . . . . . . . . D. Use as Alerting Indicators ........ 1.3.13 Design and Use of Non-Legend Light _ Indicators . . . . . . . . . . . . . . . . . . . A. Identification of Meaning . . . . . . . . .
- 8. Lignt Intensi ty . . . . . . . . . . . . . . I I 1.3.14 Design and Use of Legend Light
- Indicators ...
A. Visibility Factors ............ O 8. Lesead oesis# ............... '
'fi/A = Not applicable
1 A.2 COMPLTANCE CHECXLIST CCFPLIANCE C<~s No: Welta 1.3 GENERAL DISPLAY GUIDELINES (CONTINUED) Non-compliance Explanation Section N/A' Yes Number C. Distinguishability from Legend D. Pushbu Color Coding tton s . . . . . . . . . . . . . . . . '
............... I I 1.3.15 General Characteristics of Graphic Recorders. . . . . . . . . . . . . . . . . . . .
A. Quality of Expendable Materals ... . . . . B. Scale Compatibili ty . . . . . . . . . . . . -1 C. Scale Design ............... I l D. Paper Takeup and Cutoff . . . . . . . . . . I I E. Availability of Expendables . . . . . . . . 8 I f F. Ease of Routine Replenishment . ...... I I G. H. Use . . . . . . . . . . . . . . . . . . . . I I f Placement of Recorders .......... I l i I. Paper-Speed Adjustability . . . . . . . . . I I t J. Annotation ................ I I ' K. Visibility ................ I I I 1.3.16 Specific Recorder Types ............ O (_/ A. Continuous Recorders ........... B. Discrete Recorders ............ I I 1.3.17 Use of Mimics ................. A. Color .................. B. Mimic Lines . . . . . . . . . . . . . . . . I I I l 1.3.18 Illumination .................
)
t
\
l A. Levels .................. ' l B. Uniformi ty ................ I I i C. Supplemental Light ............ 8 I i
- 0. Task Area luminance Ratios ........ I I (
E. Shacowing . . . . . . . . . . . . . . . . . I i i F. Glare . . . . . . . . . . . . . . . . . . . I i G. Re fl ectanc e . . . . . . . . . . . . . . . . 3 I i i H. Color . . . . . . . . . . . . . . . . . . . I I -I l V l ___ _
1 A.2 CCMP'.IANCE CHECXLIST Fs) COMPLIANCE s
"' No: Wrlte i 1.4 LABEL GUIDELINES Non-comoliance:
Explanation , Section N/A' Yes Numcer i 1.4.1 Need for Labeling . . . . . . . . . . . . . . . I 1.4.2 Hierarchical Scheme For Labels ........ A. Ranking ................. B. Letter Gradations ............ 'I i 1.4.3 Label Placement . ............... A. Normal Placement . ............ B. Panel Labeling . . . . . . . . . . . . . . I I C. Visibility Enhancement . ......... I 1
- 0. Proximity ...'............. '
E. Labels on Controls . . . . . . . . . . . . I F. Adjacent Labels ............. I 1.4.4 Labels Mounting ............... A. Integrity ................ B. Surface ................. 1.4.5 Label Spatial Orientation ' A. Horizontal Orientation ......... B. Curied Patterns ............. 1.4.6 Label Visibility ............... A. Other Infomation Sources
~ ........
B. Concealment ............... 4 I C. Controls . . . . . . . . . . . . . . . . . I I
- 0. Cleaning . . . . . . . . . . . . . . . . . '
1.4.7 Kinds of Infomation ............. A. P rimar/ Functi on . . . . . . . . . . . . . B. Secondary Function . . . . . . . . . . . . 1 1 1.4.8 Label Word Selection ............. A. Intended Action ............. B. Clarity ................. I I I C. Direct . ................. I I i-D. Meaning .................
- I I I E. Technical Tems ............. I I F. Spelling . . . . . . . . . . . . . . . . . I I
\
*N/A = Not applicable
A.2 CCMPLIANCE CHECXLIST CCMPLIAtiCT I (s) 1.4 LABEL GUIDELIllES ( C0ftTItiUED) No: Wri te tion-ccmpliance E.xplanation j Section il/A* Yes Nu=er 1.4.9 Label Consistency . . . . . . . . . . . . . . . l A. Administrative Cont: ci . . . . . . . . . . B. Internal Consi stency . . . . . . . . . . . I I C. Consistency with Procedures . . . . . . . I I 1.4.10 Label Symbols ... . ... . . . . . . . . . . A. Meaning ................. l B. Di stinguishabili ty . . . . . . . . . . . . ~ l I C. S tan da rd . . . . . . . . . . . . . . . . . I I
- 0. Consistency ............... .
i 8 E. Roman Numerals ............. I 1.4.11 Label Brevity ................ 1.4.12 Label Similarity ............... 1.4.13 Label Functional Groups . . . . . . . . . . . n f. Functional Relationships . . . . . . . . U B. Location ................. 1.4.14 Control Position Labeling . . . . . . . . . . . A. Position ................ B. Direction ................ I C. Visibility . . . . . . . . . . . . . . . . I 1.4.15 Access Opening, Danger, Warning, and Safety Instruction Labeling ............. l l A. Access Opening Labeis . . . . . . . . . . B. Danger, Warning, and Safety Instruct-ion Labeling . . . . . . . . . . . . . . . 1.4.16 Label Readabil i ty . . . . . . . . . . . . . . . l A. Character Height . ............ B. Contrast . ................ I 1.4.17 Lacel Character Style . . . . . . . . . . . . . A. Character Selection . . . . . . . . . . . . B. Character Width ............. I I ( C. Stroke Width . .............. I ' O. Spacing ................. I I I l
*:l/A = Not applicable A.2'CCMPUANCE CHECXLIST p COMPLIANCE d No: Welta 1.5 ASSOCIATED EQUIPMENT GUIDELINE Non-comoliance Explanation Section N/A' Yes Numcer 1.5.1 Anthrocemetric Basis for. E:;uipment Oimen-sions . . . . . . . . . . . . . . . . . . . . . l 1.5.2 Stand-Up Console ...............
A. Console Heignt to See Over . . . . . . . . B. Control Height . ............. I i ! C. Benchboard Sloce . . . . . . . . . . . . . I
- 0. Control Distance frem the Front Edge o f the Consol e . . . . . . . . . . . . . .*
E. Display Positioning ........... I F. Lateral Spread of Controls and Dis-plays. . . . . . . . . . . . . . . . . . . G. Fcat Room ................ I 1.5.3 Sit-Down Console Dimensions . . . . . . . . . . A. Console lleight to See Over . . . . . . . . B. Control Height . . ............ I C. Benchboard Slope . . . . . . . . . . . . . I
.0. .Contro1 Distance from the Front Edge of the Console - ...........
E. Display Positioning ........... I F. Lateral Spread of Controls and Dis-plays .................. G. Leg and Foot Rcom ............ I H. Writing Space on Consoles ........ _ 1.5.4 Sit-Stand Work Stations ............ l A. Control and Display Positioning ..... l B. Chair Heignt . .............. I I C. Xnee Rccm ................ I I 1.5.5 Vertical P anel s . . . . . . . . . . . . . . . . A. Control Heignt . ............. I B. Display Heign: .............. I ! 1.5.6 Use of Procedures and Other Reference Materials at Consoles . . . . . . . . . . . . . 1.5.7 Desk Dimensions . . . . . . . . . . . . . . . . t A. Working Space .............. B. Chair Positions ............. I l I C s l
*N/A = Nct aoplicaole j l l
A.2 CCMPLIANCE CHECXLIST 7s COMPLIANCE ! ( ,) NO: Writa 1.5 ASSOCIATED QUIPMENT GU*DELINE (CCNTINUED) Non-c mpliance E.xplana ticn Section N/A* Yes Numcer C. Operator Comfort . . . . . . . . . . ....
- 0. Dimensions . . . . . . . . . . . . . . . . . I I I
1.5.8 Chairs. . . . . . . . . . . . . . . . . . . . . . A. Mcbility . . . . . . . . . . . . . . . . . .
- 8. Backrests ................. I I C. A rmre s ts . . . . . . . . . . . . . . . . . . I
- 0. Cushioning . . . . . . . . . . . . . . . . . I E. Seat Area ................. ' ' '
F. Seat Adjustability . . . . . . . . . . . . . I I G. Featrests ................. ' I Os_ / i l I l l l l I i l \ 1 v) 1
*N/A = Not acclica.nle A.2 .CCMPLIANCE CHECXLIST
(', CCMPLEANCE V No: Writa 1.6 CCNTRCLS Non-ccmoliance Explanation Section N/A* ' Yes Numoer 1.5.1 General P rinciples . . . . . . . . . . . . . . . I I A. Adecuacy ................. l B. Economy . . . . . . . . . . . . . . . . . . I I C. Human Sui tabi l i ty . . . . . . . . . . . . . I I
- 0. Ccmpatibility with Emergency Gear . . . . . I I E. Durability ................ I i 1.6.2 Prevention of Accidental Activaton . . . . . . ,.
A. Proper Location ............. B. Fixed Protective Structures . . . . . . . . I H ' C. Movable Covers or Guards ......... I I ; D. Interlocking Controls . . . . . . . . . . . I I ' E. Resistance to Movement. .......... 8 [ F. Sequential Activation . . . . . . . . . . . I G. Choice of Action ............. { 1.6.3 Direction of Movement ............. 1.6.4 ('] Coding of Control s . . . . . . . . . . . . . . . I A. Consistancy . . . . . . . . . . . . . . . . B. Location Coding . . . . . . . . . . . . . . I I i C. Size Coding . . . . . . . . . . . . . . . . I i
- 0. Shape Coding ............... I I E. Rotating Knob Shape Options . . . . . . . . I F. Color Coding ............... I 1.6.5 Pushbutton Design Principles . . . . . . . . . .
A. Position ................. B. Indication of Activitation ........ I I C. Pushbutton Surface ............ I 1.6.6 Rcund Pushbutton ............... 1.6.7 Legend Pushbuttons . . . . . . . . . . . . . . . A. Discriminability ............. B. Legend .................. I I C. Provision for Lamp Failure ........ I I
- 0. Barriers ................. I I E. Legend Pushbutton Dimensions .......
I I ,ll O)
*N/A - Not acplicaole
A.2 CCMP!.IANCE CHECXLIST O) COMPLIANCE No: Write 1.6 CONTROLS (CONTINUED) Non-comoliance Explanation Secticn N/A* Yes Numcer 1.6.8 Rotary Control Design Principles ....... I A. Di rection of Acti va ti on . . . . . . . . . . B. Rotary Control Shace Coding . . . . . . . . C. Coding Specifications .......... 1.6.9 J-Handles ................... A. High-Torque Designs . . . . . . . . . . . . B. Low-Torque Design . . . . . . . . . . . . .* 1 1.6.10 Key-Operated Controls ............. A. Use . . . . . . . . . . . . . . . . . . . . B. Teeth: Single Row ............ C. Teeth: Double Row ............ D. On-Off Orientation ............ E. Key Removal ............... F. Labeling ................. G. Key-Operated Control Dimensions . . . . . . l'.6.11 Continuous Adjustment Rotary Control . . .* . . . A. Knobs .................. B. Position Indication ........... I I C. Dimensions ................ I ! D. Torque ........... ...... I I E. Continuous Adjustment Rotary O trols
. with Know Skirts .............
1.6.12 Rotary Selector Controls ........... A. Selection ................ B. P o s i ti o n i n g . . . . . . . . . . . . . . . . ! C. Readaoility . . . . . . . . . . . . . . . . I
- 0. Posi tion Indication . . . . . . . . . . . . I I E. Dimensions ................ I i F. Mcmentary Contact Rotary Selector Controls. I I 1.6.13 Thumbwheels ..................
A. Visibility ................ B. Coding .................. I I 4 C. Continucus Adjustment Thumtwheels . . . . . ' ' l 0. Discrete Setting (stepped) Thumowheels .. I I l
'O :
*N/A = Not a::plicable
. A.2 COMP 8.!ANCE C'-iECXLIST COMPLIANCE s
No: Writa i 1.6 CONTROLS (CONTINUED) Non-compliance Explanation Section N/A' Yes Numcer h 1.6.14 Slide Switches. . . . . . . . . . . . . . . . , l A. Surfaces . . . . . . . . . . . . . . . . B. Dimensions . . . . . . . . . . . . . . . . . I 1.6.15 Toggle Switches . . . . . . . . . . . . . . . . A. Positioning ............... . B. Feedback . . . . . . . . . . . . . . . . . I C. Dimensions . . . . . . . . . . . . . . . . I 1.6.16 Rocker Switches . . . . . . . . . . . . . . . . A. Orientation ............... Indication of Activation . . . . . . . . . B. I i C. Resistance ............... I
- 0. Inadvertent Activation . . . . . . . . . . !
E. Rccker Switch Dimensions . . . . . . . . .. I 1.6.17 Single Control and Display Curve ....... A. Proximi.ty . . . . . . . . . . . . . . . . , B. Obscuration ............... C. Association ............... 1.6.18 Mul ti pl e Control s or Di spl ays . . . . . . . . . A. Multiple Controls, Single Display .... B. Single Control, Multiple Displays .... I C. Display Selectors ............ I 1.6.19 Location and Arrangement of Control-Display Groups. . . . . . . . . . . . . . . . . A. Functional Integrity .......... B. Sequence of Use ............. I l' 1.6.20 Single Panel Arrangements . . . . . . . . . . . - A. Display Above Each Control ....... . , B. Controls and Displays in Rcws ...... I i l C. Multi-Row Displays witn Single-Row Controls . . . . . . . . *. . . . . . . . . D. Consistant Practice ........... I ! E. Control / Display Packages . . . . . . . . . I i i O t.8.21 Co# trois >ae oisoters 1" seoerete aeoeis ... l A. Separated Controls and Displays ....- l . B. Facing Panels .............. I I
*N/A = Not applicable ,
A.2 CCMPLIANCE CHECXLIST p COMPLIANCE C 1.6 CONTROLS (CONTINUED) No: Write Non-complianca Explanation Section N/A* Yes Nunner 1.6.22 General Movement Relationships ......... I A. Rotary Controls .............. B. Linear Controls .............. ! C. Display Response Time lag ......... I I 1.6.23 Control Display Ratio . . . . . . . . . . . . . . A. B. Controls .................. Displays . . . . . . . . . . . . . . . . . . ! l C. Excess Precision . . . . . . . . . . . . . I D. Feedback . . . . . . . . . . . . . . . . . 1.6.24 Enhancing Recognition and Identification. . . . . A. Spacing. ... . . . . . . . . . . . . . . . . B. D emarca ti on . . . . . . . . . . . . . . . . I C. Col or Shadi ng. . . . . . . . . . . . . . . I D. Emergency Controls . . . . . . . . . . . . . I 1.6'.25 Demarcation . . . . . . . . . . . . . . . . *. . . O v A. use .................... % B. Contrast . ............. L i C. Permanence . . . . . . . . . . . . . . . . .
.... I I /~T .O "N/A = Not apolicable
l l l ( l A.3 CONSISTENCY CHECK ITEMS OF THE SPDS WITH CONTROL ROOM PANELS & EOPs NUREG-0700 NUREG-0835 CHECK ITEM SECTION SECTION
- 1. LABELING / ABBREVIATIONS 6.7.2
- 2. UNITS 6.7.2.4
- 3. COLOR CODING 6.7.2.7 4.4.3.2 O 4. SETPOINTS - ALARM CORRESPONDENCE 6.7.2 4.4.2.2 WITH CONTROL ROOM ANNUNCIATORS AND THE EOPs ENTRY CONDITION TO EMERGENCY
- 5. DISPLAY FORMAT COMPATIBILITY 6.7.2 4.4.3.2 BETWEEN THE SPDS AND HARDWIRED DISPLAYS
- 6. COMPABITILITY OF THE SPDS SAFETY 4.1 FUNCTIONS & DISPLAYED PARAMETERS 4.2 WITH THE EOP'S CONTROLLING PARAMETERS 4.4
O APPENDIX B ADDENDUM TO CNS CONTROL ROOM HUMAN FACTORS ENGINEERING (HFE STANDARDS) O l
APPENDIX B ah ADDENDUM TO CNS CONTROL ROOM HUMAN FACTORS ENGINEERING STANDARDS AND IMPLEMENTATION GUIDELINES
- 1. CONTROL CODING CNS control panels were reviewed to identify any control types that had not been listed in the Revision "0" of the standards. Based on this review, Table 3-1 of the standards has been augmented and is presented below.
O 1 i l l l l O 1
4 Table 3-1 CONTROL CODING Present Coding of Control Type System components Enhancement Pistol Grip o Pumps o Add yellow 1/2 inch o Fans tape band to pump 7 o Circuit Breakers controls as follows: C) o Seal-in Valves
' a' l RI oJ t
yellow band Star Shape Knob o Electronic Voltage o Replace star knob with Regulator yellow banded pistol
, o Selector Switch for grip for DEH Pumps ammeters and volt- o Use oval, fluted knob
~
meters for RX Inboard o DEH Pumps Injection Throttle o RX Inboard Injection valve ()- Valves (Both Seal-in and throttle o Use pistol grip for Seal-in-Inboard Injection Valve Oval Fluted o Throttle Valves Knob l Metal Gold Key- o RX Mode Switch o Place yellow tape band Lock pistol grip o SLC pumps across shank if pistol o REC /SW System grip for pump control Crosstie g o 345 KV Circuit Breaker Close {
,[ Permissive l
l ()
. 1
Table 3-1 (continued) CONTROL CODING Present Coding of Control Type System components Enhancement Round Pushbuttons o Annunciator Controls o Logic trips and resets o Test Circuits Square o DEH Controls o If square pushbuttons Pushbuttons o SRM/IRM Controls and square indicator and Control Rod lights are both used
,e wwoown Select Matrix and can be confused,
,JJ g fj .
code pushbuttons as follows: C O) N,_ ricw ,, s, . 4: Keylock Switches o Seal-in 2 position o Provide a locked switches for valves cabinet for storing o 3 position for keys when not in use containment spray control o DEH overspeed trip ter o Scram bypasses i Small Rotary o Small pumps o Provide white collar Selector switches o Valves - seal-in and for pumps 2 or 3 positions spring return o Add MGM (momentary) o Selector switches label notation for
-I o Relief Valves spring-return controls A o Isolation Logic Resets
' o Annunciator Panel l
Bypasses o / x o v/
Table 3-1 (continued) N/ CONTROL CCDING Present Coding of Control Type System components Enhancement Large Rotary o Drawer Function Selector o Tip Indexes /APRM, Switches LPRM's y # 4 o IRM Range Select 3 g\ I / 7 o Main Turbine Super-f/ 7 visory Panel
,% 9 o .' qqho Process Controllers .
Toggle Switches o Power On/Off o Turbine Supervisory g Panel-vibrations V o Dahl Controllers for RX feedwater pumps (~') o RPIS U Oval Knobs o Electrical Lockout Devices: 7 8i
- RFPs
- Main Generator
- 345 KV I - 4160 V Thumbwheel o Flow and water level controllers o Delta P controllers P
J
-4.
Table 3-1 (continued) CONTROL CODING Present Coding of Control Type System components Enhancement 3-Position o Controller Mode Select: Controller Normal, Manual Ealance, Rotary Selector Auto Switch
; O. -
2 & 4 Position 2-Position Joystick o APRM Channel Bypass Q o RBM Channel Bypass 4-Position O ! o IRM Channel Bypass o SRM Channel Bypass Illuminated o Manual Scram Raised Pushbutton i i l ! T-Handle o Generator Voltage Regulator I o Base Adjuster o Voltage Adjuster O
- 2. SEQUENCE OF CONTROL ACTIONS (n)
Item 6, page 2-7, of the Revision "0" of the standards is , modified as follows: Miscellaneous Cueine Technicues Where functional demarcation or mimic enhancements are not sufficient to clearly reveal the appropriate sequence of control actions, prominent numerals can be affixed to controls to indicate the sequence of required operator responses. This approach has been applied in guiding the sequence of manual operation of relief valves where the preferred sequence is indicated by affixing numerals 1, 2, 3,... to the protective covers of these switches. Similarly, the correct sequence of operation for auxiliary pump controls associated with HPCI and RCIC systems is indicated by placing distinctive numerals on the escutcheon plates of the relevant controls.
- 3. CONTROL ESCUTCHEON Revision "0" of the standards did not include sufficient guidance regarding control escutcheon plates. The following paragraphs will be added to Section 3, which addresses controls:
i
a. Escutcheon plates should be provided for all rotary controls to identify control options.
- b. Escutcheon labeling is normally white-on-black. Where the contrast of characters on background is impared by dirt or wear the escutcheon plates should be replaced to ensure good legibility.
- c. Escutcheon labeling shall consist of alphanumeric characters that are at least 0.125 inches in height.
- d. Where the control knob can potentially obscure the visibility of control option labeling on escutcheon plates, an extended labeling scheme, as illustrated in Figure 3-2 should be implemented.
- e. Escutcheon plate terminology shall be consistent with the standard abbreviation list. j 1
O
l l O BEFORE , AFTER LOWER RAISE N .
/
i O i l o 1 t O O; O
! Figure 3-2 Extended Labeling Scheme l
l l l l l l O v 7-- q yp-yg.+.---w--+y--- - - - , , ,,,-wg me.w .
~
- 4. PMIS/SPDS STANDARDS
'- Upon completion of the human-factors review of PMIS displays (Refer to Section 4.2), the CNS control room standards will be augmented to include enhancement guidelines for CRT. displays.
- 5. COLOR CODING OF LABELS Table 7-2 of the Revision "0" of the CNS Standards was abmiguous with regard to the color coding of labels for RESET controls. Reset controls will normally be identified with the standard black-on-white labeling. Only when the reset control is emergency-related, e.g., Group' Isolation Reset Switches, will the reset labeling be comprised of red characters on a white background. .
- 6. SYSTEM LABELS Section 6, which deals with labeling, in the revision "0" document will be modified to indicate that all labels, including major system labels, will be black-on-white labels with the exception of caution (black-on-yellow) and warning or emergency system labels (red-on-white).
4 7. NOMENCLATURE STANDARDS Cooper Nuclear Station procedures writer's guide contain a 4 list of nomenclature for plant systems and components (Ref. 20). This list was developed with the intention of identifying a component by the same name throughout the plant. The DCRDR team made use of this list in developing f an abbreviation list that was included in Attachment A of Revision."0" of the standards. Presently the nomenclature list is being expanded to include additional systems components and parameters' names that i were identified through the relabeling effort performed on ' the control room panels (September - December 1986). Revision "1" of the standards will include an updated ', version of the nemenclature list.
- 8. SYMBOLS A standard set of symbols has been established and are shown in Table 6.2. These symbols are being used in association
! with mimics. The symbols were selected to be consistent with those presented on P& ids. The use of symbols on the PMIS displays is still under review. Revision 1 of the CNS Control Room Standards will include standards and implementation guidelines relating to the use of symbols throughout the control room. Symbols standards will be O- added to Section 6 of CNS HF Standards on labeling. 1
1 TABLE 6.2 LIST OF SYMBOLS i O SYMBOL MEANING 4 Valve (Normally Open) Valve (Normally Closed) l Air Operated valve l
;; Restricting Orifice O .
Pump i ! l NF Turbine C 2 3 Heat Exchanger 1,2: Tube Side i 3,4: Shell Side
.-+4 l h t 2 i
- O -
_g-i
. . . . .- . .- . .. - - . . -. -- = = .
TABLE 6.2 (cont'd) LIST OF S*IMEOLS (continued) O SYMBOL MEANING Generator I/\/A1T > b T.] j v w y ,s o Power Transformer
. RG 1.97 Instrument
- 1
; O i
) . l l l l 1 l l l !O i 1
O i 1 APPENDIX C MULTI-INPUT ALARMS IDENTIFICATION AND j PRIORITIZATION i 4 i t O
,...r.-------,,,,...-,n,_,_ . .
..en ,.,--n-n n - n.-. -.n-,.._
APPENDIX C MULTI-INPUT ALARMS / NUMBER OF INPUTS AND PRIORITY PANEL 9-3 Item Alarm No. of
# Panel ID System Alarm Title Inputs
- Priority 1 9-3-1 2-3 RilR RilR A Valves Overload 17 3 2 9-3-1 2-4 CS Core Spray System I 2 3 Inject Valve Motor 1 Overload i 3 9-3-1 3-2 RilR RilR Systems I & II 3 2 Discharge & Shutdown Suction lleader fli-Press 4 9-3-1 3-3 RilR Containment Spray A 2 3 Inject /Viv Overload 5 9-3-1 3-4 CS Core Spray System I 3 3 Valves Overload 6 9-3-1 4-2 RilR RilR Cntmt Spray 2 3 Permissive Manual Override 7 9-3-1 4-3 RilR RilR A Injection Viv 2 3 Overload 8 9-3-1 5-3 RilR RilR System A Actuated 2 3 9 9-3-1 6-3 RilR RilR Pump 1A Pump Trip 5 2 10 9-3-1 7-2 RilR RilR Pump 10-lC Service 3 3 Water Trouble 11 9-3-1 1-3 RilR RilR Pump 111 Pump Trip 5 2 12 9-3-1 6-2 RilR RllR Pump 10-IA Service 3 3 Unter Trouble 13 9-3-2 5-2 IIPCI IIPCI Steam Line 2 3 Differential Press, liigh l
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
c MULTI-INPUT ALARMS PANEL 9-3 (continued) 5 ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 14 9-3-2 1-1 HPCI HPCI Turbine Tripped 7 2 15 9-3-2 1-2 HPCI HPCI Pump Discharge & 3 3 Steam Supply Vivs Overload 16 9-3-2 1-4 RHR RHR Pump B Service 3 3 Water Trouble .
17 9-3-2 2-3 HPCI HPCI Isolation Signal 2 2 Logic A/B Initiated i 18 9-3-2 2-4 RHR RHR Pump 10-10 Service 3 3 Water Trouble 19 9-3-2 4-4 ARW Main Steam Line Steam 64 3 Leak Augmented Radwaste Building
- C-4 i
4 h hs .i )
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-INPUT ALARMS PANEL 9-3 (continued)
/~')
v ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 20 9-3-2 4 RHR RHR HX Discharge Temp 2 2 A/B High 21 9-3-2 6-3 HPCI HPCI Valves Motor 7 3 Overload 22 9-3-2 6-4 RHR RHR HX Inlet Temp 2 2 A/B High ,
23 9-3-2 7-2 HPCI HPCI Pump Suction 2 2 High/ Low Pressure 24 9-3-2 8-1 HPCI Inverter Circuit 2 3 Failure 25 9-3-2 8-3 RHR RHR HX 2A/2B Out High 2 3 Conductivity 26 9-3-2 9-1 HPCI HPCI Logic Bus Pwr 2 2 m ) Failure / Aux Oil Pmp Cntrl Switch Locked Out 27 9-3-2 9-4 RHR RHR B Valve Overload 16 3 28 9-3-3 1-1 RHR Can'tainment Spray B 2 3 Inj. Valve Overload i 29 9-3-3 1-3 CS Core Spray Test Status 10 3 I O
- Subject to verification against number of sensors and trip setpoints in each of the alarn circuits.
. . _ , __ . _ __ , ._.. _ _ _ ___ ___. - . _ ~ . _
I MULTI-INPUT ALARMS PANEL 9-3 (continued) lr ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 30 9-3-3 1-2 CS Core Spray System II 2 3 Valve Overload 32 9-3-3 2-1 RHR RHR B Inject Valve 2 3 Overload 33 9-3-3 2-2 HPCI HPCI-M0-15 or 2 3 HPCI-M0-16 Not Fully Open 34 9-3-3 2-3 AREA TEMP High Area Temperature 28 1 -
RX BLDG 35 9-3-3 2-4 AREA RAD Area Rad Monitor 30 3 Downscale 36 9-3-3 3-1 RHR RHR System B Logic 2 2 q(, Actuated 37 9-3-3 4-1 RHR RHR Pump 3C Pump Trip 2 2 38 9-3-3 4-4 AREA RAD Reactor Bldg High 10 1 RX BLDG Radiation 39 9-3-3 5-1 RHR RHR Pump 3D Pump Trip 2 2 40 9-3-3 5-3 SUPPR Supp Chamber Lvl Hi/Lo 2 1 CHAMBER 41 9-3-3 6-3 SUPPR Suppression Chamber 2 2 CHAMBER Level High-Low O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
n MULTI-It:PUT ALARMS PANEL 9-3 (continued) U ITEM . ALARM # OF -
# PANEL ID SYSTEM ALARM TITLE -
INPUTS
- PRIORITY 42 9-3-3 6-4 AREA RAD Refuel Area High 2 1 Radiation 43 9-3 4 4-1 ADS Auto Blowdown 2 3 Timers Actuated 44 9-3-4 6-4 ADS Auto Blowdown In Test 4 3 Status ,
46 9-3-4 8-1 ADS Faulty Auto Blowdown 4 3 Test Procedure 47 9-3-3 8-4 AREA RAD Radwaste Bldg. High 9 1 RW BLDG Radiation 48 9-3-3 9-1 CS CS System II Inj. 2 3 Valve Overload O 49 9-3-3 9-3 RHR RHR HX A/B Steam Inlet 2 3 Drip Leg Hi 50 9-3-3 9-4 AREA RAD Turbine Bldg. High 5 1 TURBINE Radiation BLDG 51 9-3-4 1-1 125 VDC Auto Blowdown Cont 11 2 BUSES Power Failure 52 9-3 a 1-3 LOW-LOW Low Low Set A or B 5 2 SET VLVS Power Lost A OR 8 53 9-3-4 2-1 SRVs Safety or Blowdown 8 2 Valve Leaking 54 9-3-4 3-1 SRVs Relief Valve Open 8 2 55 9-3-4 5-2 SRVs Mn Stm RV Accum. Press 8 2 Low 56 9-3-4 9-1 CS OR AC Interlock 4 "3 RHR
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-IflPUT ALARMS PANEL 9-4 ITEM ALARM # OF
# PANEL ID ' SYSTEM ALARM TITLE INPUTS
- PRIORITY 1 9-4-1 1-4 RW R/W 25-17 Trouble. .s60 3 2 9-4-1 3-4 OG Off Gas Vent High/ Low 2 2 Flow
#3 9-4-1 4-4 OG Off Gas Vent Pipe 2 1 i
High-High Radiation 4 9-4-1 5-2 RCIC RCIC Pump Valves 3 3 Overload 5 9-4-1 5-4 OG Off Gas Vent Pipe High 2 2 Radiation 6 9-4-1 6-2 RCIC RCIC Valves Overload 8 3 7 9-4-1 6-4 OG Off Gas Vent 4 3 Downscale/Inap O l i 8 O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
n MULTI-INPUT ALARMS PANEL 9-4 (continued) U ITEM ALARM # OF
# PANEL ID SYSTEM ALARti TITLE INPUTS
- PRIORITY 8 9-4-1 7-4 OG Off Gas High-Low Flow 2 2 9 9 a-1 8-1 RCIC RCIC Turbine Tripped 6 2 10 9-4-1 8-4 OG Off Gas High Radiation 2 1 11 9-4-1 9-2 VESSEL Vessel Flange Seal 2 3 FLANGE Leak 12 9-4-1 9-4 OG Off Gas Rad, a 2 Downscale/Inop 13 9-4-2 1-2 RWCU Cleanup System High 2 2 Conductivity 14 9-4-2 1-3 RECIRC Recirc Generator A 8 3 GENERATOR Lockout 1
15 9-4-2 1-4 RECIRC Recirc Motor Generator 2 3 O ^ or B Stator Temn 16 9-4-2 2-2 RWCU Cleanup Discharge Press 2 2 High/ Low 17 9-4-2 2-3 MG SET MG Set A Drive flotor 4 3 A DRIVE Lockout MOTOR 18 9-4-2 2-4 RRMG MG Set Bearing 011 8 3 Temperature High (A or B) O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
l MULTI-IrlPUT ALARMS PANEL 9-4 (continued) ITEM ALARf1 # OF
# -PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 19 9-4-2 5-1 SERVICE Liquid Process High 2. 1 WATER OR Radiation REC 20 9-4-2 5-4 RECIRC A Recirc A Fluid Drive 2 3 Low Oil Pressure ,
21 9-4-2 6-1 SW OR Liquid Process
- 4 2 REC Downscale/Inop 22 9-4-2 6-3 MG DRIVE MG Drive Motor Breaker 10 3 MOTOR A (1CN) Trip BREAKER 23 9-4-2 7-3 MG-A MG Drive Motor Breaker 10 3 DRIVE A (ICS) Trip \
MOTOR BREAKER O 24 9-4-2 7-4 aEClaC PUMP Rec 4rc eumn A or B Motor High Temp 12 3 MOTORS 25 9-4-2 8-2 RWCU C/V Influent High Flow 3 2 or High Space Temp 26 9-4-2 9-1 RX BLDG Reactor Building Vent 2 1 VENT High-High Radiation 27 9-4-2 9-2 RECIRC Recire A Trip High 2 2 PUMP A Press / Low Level 28 9-4-3 2-1 RECIRC A Recire A Pump Seal STG 2 3 PUMP Flow Hi/ Low SEAL O Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-IflPUT ALARMS PANEL 9-4 (continued) ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 29 9-4-3 2-2 RECIRC Recirc. Gen. B Lockout 6 3 GENERATOR B
30 9 a-3 3-2 MG SET B MG Set B Drive Motor' 4 3 DP.IVE Lockout MOTOR 31 9-4-3 4-3 RECIRC Recirc B Fluid Drive ~ 2 3 B Low Oil Pressure Low 32 9-4-3 5-4 RECIRC Recirc "B" Trip Hi 2 3 PUMP B Press /Lo Level 33 9-4-3 7-2 MG-B MG B fiator Breaker 10 3 DRIVE (1Df!) Trip MOTOR BREAKER 9-4-3 7-3 RECIR B Recirc B Pump Motor 2 3 q 34 'v PUMP MOTOR Oil High/ Low 35 9-4-3 8-2 MG-B MG B Motor Breaker 10 3 MOTOR (IDS) Trip BREAKER 36 9 a-3 9-3 RECIRC B Recirc B Pump Seal 2 3 PUMP SEAL Stg. Flow Hi/ Low Level 37 9-4-2 9-4 RECIRC A Recirc A Pump Motor 2 3 MOTOR Oil High/ Low Level 38 9-4-2 7-2 RWCU Cleanup Influent Low 2 3 Press 39 9-4-2 8-1 Rx Bldg Reactor Bldg Vent 2 3 Vent Downscale 40 9 a-2 7-1 Rx Bldg Reactor Bldg Vent 2 3 Vent High Radiation 41 9-4-2 4-1 Mn Steam Main Steam Line 4 3 Line Downscale Radition O 42 9-4-1 3-3 reei Pool ree1 ecoi cooiins Alarm 7 3
- Subject to verification against number of senscrs and trip setpoints in each of the alarm circuits.
n V MULTI-INPUT ALARMS PANEL 9-5 ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE -
INPUTS
- PRIORITY 1 9-5-1 1-4 CONTROL A/B Sequence Rods Not 137 3 RODS Full Out 2 9-5-1 2-2 CRD CRD Pump B (3-16B) 2 3 Breaker Trip 3 9-5-1 2-4 SEQUENCE A Sequence Rods --
3 A RODS Bypassed , 4 9-5-1 2-5 SEQUENCE B Sequence Rods -- 3 B RODS Bypassed 5 9-5-1 3-1 CRD Rod Drift 137 2 6 9-5-1 3-3 REACTOR Reactor Level High/ Low 2 2 LEVEL 7 9-5-1 3-4 R00 SEQ Rod Seq. Cont. -- 3 CONTROL Malfunction 8 9-5-1 4-1 CRD CRD Htd Temp High 137 2 9 9-5-1 7-4 RBM RBM Upscale /Inap 2 3 10 9-5-1 7-5 APRM APRM A, C and E 6 2 Upscale Trip /Inop 11 9-5-1 7-6 APRM APRM B, D, and F 6 2 Upscale Trip /Inop 12 9-5-1 8-1 CRD PUMP CPD Pp A (3-16A) 2 3 A BPEAKER Breaker Trip 13 9-5-1 8-5 APRM APRM Downscale 6 3 14 9-5-1 8-6 APRM APRM Upscale Alarm 6 3 15 9-5-1 9-4 RECIRC Flow Ref. Off Normal 2 3 16 9-5-1 9-5 LPRM LPRM Dcwnscale 124 3 l 8 17 9-5-1 9-6 LPRM LPRM Upscale 124 3 O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
I
- o. MULTI-INPUT ALARMS PANEL 9-5 (continued)
U ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 18 9-5-2 4-1 CRD CRD Accumulator Low 274 2 Press /Hi Level 19 9-5-2 6-1 SCRAM Scram Valve Pilot 2 2 SYS Air High/ Low 20 9-5-2 6-2 DRYWELL Drywell High/ Low 2 2 Pressure ,
21 9-5-2 6-6 SHEER TIP Sheer Viv 3 3 VLV Fired / Trouble 22 9-5-2 7-5 IRM IRM A Upscale 8 2 Trip /Inop 23 9-5-2 7-6 IRM IRM B Upscale 8 2 Trip /Inop 23 9-5-2 8-3 SLC Tank Level High/ Low 2 3 25 9-5-2 8-4 SRM SRM Upscale Alarm or
- 8 3 Inop 26 8-5-2 8-5 IRM IPJ4 Downscale 8 3 27 8-5-2 8-6 IRM IRM Upscale Alarm 8 3 i 28 9-5-2 9-2 SLC Standby Liquid 2 2 High/ Low Temp 29 9-5-2 9a SRM SRM Downscale 4 3 5-3 Feedwater Control a 3 30 9-5-1 RFP Signal Failure i
I O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
rS MULTI-INFUT. ALARMS YBD-A V ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE IllPUTS* PRIORITY 1 VBD-A-1 1-1 RFP RFP Turbine 1A Trip 9 3 TURBINE -Monitor 2 VBD-A-1 1-3 RFP RFP Turbine Drain 2 3 TURBINE Tank High/ Low Level 3 VBD-A-1 1-4 RFP RFP Turbine IB Trip 9 3 j
TURBINE Monitor , 4 VBD-A-1 7-2 RFP RFP Turbine 1A Trip 9 3 TURBINE 5 VBD-A-1 7-5 RFP RFP Turbine IB Trip 9 3
!~ TURBINE 6 VBD-A-1 8-3 DEMIN Demineralized Water 2 3 WATER System Low Pressure 7 VBD-A-1 9-1 WATER Water Treatment. System 5 3 O TREATMENT Trouble 8 VBD-A-2 7-1 HEATER Heater 1A1, 1A2 FW 4 3 Al Bypass 9 VBD-A-2 7-2 HEATER Heater 181,182 FW 4 3 B1 Bypass 10 VBD-A-2 7-3 HEATER Heater 1A3,1A4 FW 5 3 A3 Bypass 4
P ( i 1
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-INPUT ALARMS VBD-A (continued) ITEM ALARM e OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIDRITY 11 VBD-A-2 7-4 HEATER Heater 183, IBa FW 5 3 B3 Bypass 12 VBD-A-2 7-5 STM DUMP Ext. Stm Dump Bypass 8 3 Valves Not In Auto j Position 13 VBD-A-2 8-4 HEATER Heater 1-A-5 FW Bypass
- 4 3 A-5 14 VBD-A-2 8-5 HEATER Heater 1-B-5 FW Bypass 4 3 B-5 15 VBD-A-3 1-5 FILTER Cond. Filter --
3 DEMIN Demineralizer Trouble 16 VBD-A-2 9-3 Traveling Traveling Screen Auto. 23 3 i Screens Trip O 17 v80-A-3 2-5 CST Condensete Store 9e Tenk Level High 2 3 18 VBD-A-3 3-5 CST Contensate Storage Tank 2 3 Level Law 19 VBD-A-3 3-1 CONDENSATE Cond. Booster Pump s1A 4 3 B0OSTER 1A Trip i 20 VBD-A-3 3-2 CONDENSATE Cond. Booster Pump #1B 4 3 B0OSTER 1B Trip 21 VBD-A-3 3-3 CONDENSATE Cond. Booster Pump #1C 4 3 Trip BOOSTER 1C t - l 23 VBD-A-3 5-4 SERVICE Station Service Water 2 3
- WATER 1A Pump 1A Trip 24 VBD-A-3 5-5 SERVICE Station Service Water 2 3 WATER IC Pump 1C Trip i
l O l
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-IrlPUT ALARMS VBD-A (continued) ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 25 VBD-A-3 8-2 SCREEN Screen Wash Pump #1A 3 3 WASH 1A Trip 26 VBD-A-3 8-3 SCREEN Screen Wash Pump #1B 3 3 WASH IB Trip
,27 VBD-A-3 9-4 CST Condensate Storage 3 3 Tank Heaters On ,
28 VBD-A-3 9-5 PRIMARY Water Box Priming Sys 2 3 SYSTEM Vac Tank Hi Wtr Lvl or Vac Low 29 VBD-A-4 1-1 CIRC Cire. Water Pump #1A 6 3 WATER 1A Trip 30 VBD-A-4 1-2 CIRC Cire. Water Pump #18 6 3 WATER 18 Trip O 31 v80-A-4 1-3 CIRC WATER 1C Cire. Weter eumP #1C Trip e 3 32 VBD-A-4 1-4 CIRC Circ. Water Pump #10 6 3 WATER 10 Trip 33 VBD-A-4 1-5 STATION Station Air Compressor 5 3 AIR 1A 1A Trip 34 VBD-A-4 2-5 STATION Station Air Compressor 5 3 AIR 18 18 Trip 35 VBD-A-4 3-5 STATION Station Air Compressor 5 2-AIR IC 1C Trip 36 VBD-A-4 4-5 AIR Air Receiver 1A or 1B 2 2 RECEIVER Press. Low 37 VBD-A-4 8-3 SERVICE Air Dyrer Pre or Post 4 2
& INSTR Filter Diff. Press. - AIR High 38 VBD-A-4 9-1 CONDENSER Condenser Backwash 6 3 BACKWASH Trouble O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-INPUT ALARMS 'lBD-B ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE - INFUTS* PRIORITY 1 VBD-B-1 1-1 T/G Main Turbine Generator 24 3 Auto Stop Trip Solenoid Energized 2 VBD-B-1 4-5 T/G Turb Gen Energ Bear 2 3-Oil Pump Ovid /CS Locked Out
~
3 VBD-B-1 9-1 T/G Main Turbine Generator 2 3 Rotor Expansion Governor End 4 VBD-B-1 9-2 T/G Main Turbine Generator 2 3 Rotor Expansion Governor End 5 VBD-B-1 9-5 LUB CIRC- Lube Oil Conditioner 2 3 ULATING Level High PUMP 6 VBD-B-2 6-2 RRMG AUTO Automatic Recirc Not 3 3 CIRCULATION Permitted 7 VBD-B-2 6-4 AUX BOILER Auxiliary Boiler #1 12 3
#1 Trouble 8 VBD-B-2 6-5 AUX BOILER Auxiliary Boiler #2 12 3
#2 Trouble 9 VBD-B-2 7-1 SCREEN Screen Wash Pumps 2 3 WASH PUMP IC and 10 Gland Wtr Flow Low 10 VBD-B-2 7-2 T/G EH Main Turbine Generator 3 3 EH System Lockcut Circuit Supervision 11 VBD-B-2 8-5 SCREEN Screen Wash Pumps 1C 2 3 WASH and 10 Strainers PUMP Differential Pressure High
'12 VBD-B-3 1-3 SERVICE Station Svc Wtr 2 3 WATER Strainers A & C Diff.
O Pressure High
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
, MULTI-INPUTALARMSVBD-B(continued)
ITEM ALARM # OF
# PANEL. ID SYSTEM ALARM TITLE INPUTS
- PRIORITY l
' 13 VBD-B-3 1-4 TURBINE Turbine Bidg. Corridor a 3 BLDG 903' High Temp 14 VBD-B-3 1-5 BATTERY Battery Room Exhaust 2 3 RM FANS Fan Failure to Run 15 VBD-B-3 1-1 SERVICE Station Svc Wtr Pump 2 3 WATER 18 IB Trip ,
16 VBD-B-3 1-2 SERVICE Station Svc Wtr Pump 2 3 - WATER 10 10 Trip = 17 VBD-B-3 2-5 SCREEN Screen Wash Pumps 1A & 2 3 WASH PUMPS 1B Gland Wtr Flow Low 18 VBD-B-3 4-1 SCREEN Screen Wash Pump 2' 3 WASH PUMP #1C Ovid & Ground 1C O 19 vBD-B-1 2-2 t/G seia rurbiae Geaerator Turning Gear Failure 3 3 20 VBD-B-3 4-4 SERVICE No Standby Station 4 3 STATION Service Water Pump WATER 21 VBD-B-3 6-1 SCREEN Screen Wash Pumps 1C 2 3 WASH PUMPS and 10 Low Disch Press 22 VBD-B-3 6-4 SW-1A SW Gland Water Supply -- 3 System 1A Trouble 23 VBD-B-3 6-5 TORUS Torus Vacuum Relief 12 2 Open O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
p MULTI-INPUT ALARMS VBD-B (continued)
\_/
ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 24 VBD-B-3 7-1 ELECTRODE Electrode Boiler -- 3 BOILER ASB-B-1C Trouble 25 VBD-B-3 7-2 ELECTRODE Electrode Boiler -- 3 BOILER ASB-B-10 Trouble 26 VBD-B-3 7-4 SW-1B SW Gland Water Supply -- 3 System 18 Trouble ,
27 VBD-B-3 8-4 RHR RHR Gland Water Supply -- 3 System 1A Trouble 2B VBD-B-3 8-5 A0G Augmented Off Gas -- 3 Trouble 29 VBD-B-3 9-4 RHR-B RHR Gland Water Supply -- 3 System 1B Trouble 30 VBD-B-3 9-5 ARW Augmented Radwaste 2 3 O Troubie 31 VBD-B-3 2-4 SW Pumps RHR SW Pumps 1A & IC 2 3 Inlet Strainer Hi DP 32 VBD-B-3 5-1 Screen Screen Wash Pump 1C 2 3 Wash Trip 33 VBD-B-3 5-2 Screen Screen Wash Pump 1D 2 3 Wash Trip I I l l i O { l Subject to verification against number of sensors and trip setpoints in l each of the alarm circuits. l t
n MULTI-INPUT ALARMS VBD-R () ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE It! PUTS
- PRIORITY 1 VBD-R-1 1-1 TURB BLDG Turb. Bldg. Unit 2 3 HVAC 1-HV-T-1A Failure to Run 2 VBD-R-1 1-2 TURB BLDG Turb. Bldg. Unit 2 3 HVAC 1-HV-T-1B Failure to Run 3 VBD-R-1 1-3 TURB BLDG Turb. Bldg. Unit 2 3 HVAC 1-HV-T-1C Failure to Run 4 VBD-R-1 1-4 TURB BLDG Turb. Bldg Diff Press 2 3 ATMOS DP High/ Low 5 VBD-R-1 2-2 TURB BLDG Turb Bldg Unit 2 3 HVAC 1-HV-T-1B or 1-AC-T-1A Freeze Stat 6 VBD-R-1 3-3 TURS BLDG H&V Unit 1-HV-T-1C Air 2 3 AIR Washer DP Hi Air WASHER Washer Pump Discharge Flow Low 7 VBD-R-1 4-4 TURB BLDG H&V Unit 1-HV-T-1A Air 2 3 AIR Washer DP Hi Air WASHER Washer Pump Discharge Flow Low 8 VBD-R-1 5-1 Control Bldg Unit 2 3 1-HV-C-1A Failure to Run 9 VBD-R-1 5-3 Control Room Unit 2 3
, 1-AC-C-1A Failure to Run 10 VBD-R-1 5-5 Computer Room Unit 2 3 1-AC-C-1B Failure to Run 11 VBD-R-1 6-5 COMPUTER Computer Room 2 3 ROOM Ventilation Trouble O veritt'Attor<
Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
(3 MULTI-INPUT ALARMS VBD-R (continued) tj ITEM ALARM # OF
# PANEL ID SYSTEM AL.sRM TITLE INPUTS
- PRIORITY 12 VBD-R-2 1-1 RX BLDG Rx. Bldg Unit 2 3 HVAC 1-HV-R-1A Failure to Run 13 VBD-R-2 1-2 RX BLDG Rx Bldg Booster Fans 2 3 BCOSTER 1-BF-R-1A or 1-BF-R-1B FANS Failure to Run 14 VBD-R-2 2-2 RX BLDG Rx Bldg Exh. Fans 2 3 HVAC 1-BF-R-1A or 1-BF-R-1B Failure to Run 15 VBD-R-2 2-5 DG #1 DG #1 H&V Trouble 4 3 16 VBD-R-2 3-1 RX BLDG H&V Unit 1-HV-R-1A Air 2 3 HVAC Washer DP High Air Wash Pump Discharge Flow Low (O> 17 VBD-R-2 3-2 MG HVAC MG Sets Exh. Fans 2 3 1-EF-R-1C or 1-EF-4-1D Failure to Run 18 VBD-R-2 3-4 RX BLDG Rx. Bldg. Pump Rooms 5 1 VENTIL Temperature High 19 VBD-R-2 3-5 DG #2 D.G. #2 H&V Trouble 4 3 20 VBD-R-2 4-2 MG HVAC f!G Sets Outlet No Air 2 3 Flow 21 VBD-R-2 4-3 INTAKE Intake Structure 2 3 STRUCTURE HV-IS-1A & B Freeze Status 22 VBD-R-2 4-4 RX BLDG Rx Bldg Differential 2 1 Press Too High/ Low 23 VBD-R-2 4-5 CHAflGE Change Area H & V 8 3 AREA Trcuble 2a VBD-R-1 6-4 MACHINE Machine Shop H&V 3 3 SHOP Trouble Subject to verification against nurrber of sensors and trip setpoints in each of the alarm circuits.
gs) MULTI-INPUT ALARMS VBD-J v ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 1 VBD-J-1 1-1 SUPPR Rx Bldg Supp Chamber 16 1 CHAMBER Hater Hi Temp 2 VBD-J-1 2-5 TORUS Rx Bldg Torus Door 2 3 000R Open 3 VBD-J-1 4-2 T/G Turbine Generator 2 3 Control Corridor Heater Bay Doors Open -
4 VBD-J-1 5-3 T/G Turbine Generator Bldg 2 3 NE Stair Doors Open 5 VBD-J-1 5-5 RX BLDC- Px Bldg CCW Pump 1A 2 2 CCW PUMP Discharge Hi/Lo Press 1A 6 VBD-J-1 6-2 RX BLDG Rx Bldg CCW Pump 1B 2 2 3 CCW PUMP Discharge Hi/Lo Press u,) 1B 7 VBD-J-1 6-3 RX BLDG Rx Bldg CCW Pump 1C 2 2 CCW PUMP Discharge Hi/Lo Press 1C 8 VBD-J-1 6-5 RX BLDG Rx Bldg CCW Pump 10 2 2 CCW PUMP Discharge Hi/Lo Press ID 1
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
I MULTI-INPUT ALARMS VBD-S : 2
. ITEM ALARM # OF j # PANEL ID SYSTEM ALARM TITLE IllPUTS* PRIORITY l
i 1 VBD-S-1 6-2 ARW-HVAC Trouble ARW-HVAC -- 3 i i i l i 1 i } . I 4 t 1 . f ! f O ; ! t i l l 1 i i l l r ! l P t i O i
.t t
~
i
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits. L
--_ ~ . _ _ -- . _ _. - - - - , - -
r^'s MULTI-INPUT ALARMS V80-Q V ITEM ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY I VBD-Q-1 1-6 ARW Aug. Radwaste Vent 3 1 Activity High 2 VBD-0-1 2-6 ARW Aug. Radwaste Vent 3 2 Monitor Failure 3 VBD-Q-1 5-5 ERP ERP Discharge Activity 3 1 High ,
4 VBD-Q-1 6-5 ERP EPP Discharge Monitor 4 2 failure 10 V O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
() MULTI-INPUT ALARMS VBD-H ITEM ALARfi # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 1 VBD-H-1 2-4 SUPPR Supp Chamber Vacuum 4 2 CHAMBER Relief Viv 243AV Open 2 VBD-H-1 3-4 SUPPR Supp Chamber Vacuum 2 2 CHAMBER Relief Viv 244AV Open I
O V Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
.. - - - . - __- - -_. = _ . _ . -.. . -_-. .- _ . - -
3 1 ,i Q MULTI-INPUT ALARPS VBD-K ! ITEM ALARii # OF
# PAtlEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY
)
- 1 V6D-K-1 5-2 SGT Standby Gas Treatment 3 3 4
System Unit Low Flow 2 VBD-K-1 6-3 A0G Augmented Off Gas Auto 2 3
- Isolation i'
1 i 1 t lO i i' 1 1 J i i i i i l ( i 4 i l . l i : i !,O l 1
- Subject to verification against number of sensors and trip setpoints in i each of the alarm circuits.
_ _ _ - - . _ , _ _ - _ . _ ~ . , _ . . _ _ _ . . . _ . _ . . _ _ _ _ _ _ . _ _ _ _ _ , , _ _ . _ .._.~. __ _ _ ,_-
MULTI-INPUT ALARMS VBD-M (VD ITEM ALARM 4 0F
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 1 VBD-M-1 2-1 RHR SW RHR Service Water Pump 2 3 1A 1A Trip 2 VBD-M-1 2-2 RHR SW RHR Service Water Pump 2 3 IB IB Trip 3 VBD-M-1 2-3 RHR SW RHR Service Water Pump 2 3 1C 1C Trip 4 VBD-M-1 2-4 RHR SW RHR Service Water Pump ' 2 3 1D 10 Trip 5 VBD-M-1 5-1 RHR SW RHR Pump 1A Cooling 2 3 1A Water Trouble 6 VBD-M-1 5-2 RHR SW RHR Pump 1B Cooling 2 3 IB Water Trouble 7 VBD-M-1 5-3 RHR SW RHR Pump 1C Cooling 2 3 IC Water Trouble
(~] v 8 VBD-M-1 5-4 RHR SW RHR Pump 10 Cooling 2 3 1D Water Trouble 9 VBD-M-2 2-1 RHR SWB RHR Service Water 2 2 (9-3) Booster Pumps 1A&lC Suction Pressure Low 10 VBD-M-2 2-2 RHR SWB RHR Service Water 2 2 (9-3) Booster Pumps 18&lD Suction Pressure Low 11 VBD-M-2 3-1 RHR RHR Service Water 2 2 (9-3) Ecoster Pumps 1A&lC Discharge Pressure Lcw 12 VBD-M-2 3-2 RHR RHR Service Water 2 2 (9-3) Booster Pumps IB&lD Discharge Pressure Low 13 VBD-M-2 5-1 CR0 PUMP CRD Hyd. Pump 1A 2 2 1A Cooling Water Temp Hi 14 VBD-M-2 5-2 CRD PUMP CR0 Hyd. Pump 1B 2 2 18 Cooling Water Temp Hi 15 VBD-M-2 6-1 REC PUMPS REC Standby 4 3
- Subject to verificaticn against number of sensors and trip setpoints in each of the alarm circuits.
O MULTI-INPUT ALARMS VBD-C G ITEM ALARM # OF
# PANEL- ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 1 VBD-C-1 1-1 DG#1 Diesel Generator #1 9 2 Breaker EGI Trip 2 VBD-C-1 1-2 4160V 4160V Switchgear IF 4 3 SUITCHGEAR Main Breaker IFA Trip IF 3 VBD-C-1 1-3 4160V 4160V Switchgear IF '
3 3 SWITCHGEAR Main Breaker 1FS Trip 1F 4 VBD-C-1 14 4160V 4160V Switchgear 1A 2 3 SWITCHGEAR Main Breaker 1AN Trip 1A 5 VBD-C-1 1-5 4160V 4160V Switchgear 1A 5 3 SWITCHGEAR Main Breaker 1AS Trip 1A O e v80-C-1 2-1 DG 1 RELAY Dieseei Generetor #1 Relay 86 Lockout 5 2 7 VBD-C-1 3-4 4160V 4160V Switchgear 1A 6 3 > FEEDER Feeder Breaker IAE Trip 8 VBD-C-1 3-5 4160V 4160V Switchgear 1A 6 3 FEEDER Feeder Breaker IAF Trip 9 VBD-C-1 4-2 4160V 4160V Switchgear IF 5 3 i FEEDER Feeder Breaker 1FE Trip Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-INPUT ALARMS VBD-C (continued) O-ITEM ALARM # OF
# PANEL ID SYSTEM ALARf1 TITLE INPUTS
- PRIORITY 10 VBD-C-1 6-1 DG#1 Diesel #1 Day Tank 2 3 Level High-Low
( 11 VBD-C-2 3-1 MAIN Main Transformer Phase 6 3 TRANSFORMER A Trouble 12 VBD-C-2 3-2 MAIN Main Transformer Phase 6 3 TRANSFORMER 8 Trouble 13 VBD-C-2 3-3 MAIN Main Transformer Phase 6 3 TRANSFORMER C Trouble Main Transformer Spare
- 14 VBD-C-2 3-4 MAIN 6 3 TRANSFORMER Trouble SPARE 15 VBD-C-2 3-5 MAIN Main Generator Voltage 4 3 GENERATOR Regulator Trouble VOLTAGE
() REGULATOR 16 VBD-C-2 4-1 MAIN Main Generator Bus 2 3 GENERATOR Duct High Temp 17 VBD-C-2 5-1 STATION Normal Station Service 2 3 SERVICE Transformer Zone TRANSFORMER Protective Relays 18 VBD-C-2 5-3 125V DC 125V DC Swgr. Bus 1A 7 2 1A Breaker Trip 19 VBD-C-2 5-4 SERVICE Station Service 2 3 TRANSF Trnsformer 1A Trouble 1A O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
MULTI-INPUT ALARMS VBD-C (continued) ITEM ALARM 7 0F
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 20 VBD-C-2 6-1 STATION Normal Station Service 6 3 SERVICE Transformer Trouble TRANSFORiiER 21 VBD-C-2 6-2 STARTUP Startup Station 6 1 SERVICE Service Transformer TRANSFORMER Trouble 22 VBD-C-2 6-3 EMERG Emergency Station 6 1 g SERVICE Service Transformer -
\
TRANSFORf1ER Trouble 23 VBD-C-2 6-4 SERVICE Station Service 2 3 TRANSF Transformer 1B Trouble IB 24 VBD-C-2 7-4 SERVICE Station Service 2 3 TRANSF Trar.former 1E Trouble ~ 1E O 25 v80-C-2 8-4 scavtct TRANSF stat 4oa service Transformer IF Trouble 2 3 IF 26 VBD-C-2 9-4 SERVICE Station Service 2 3 TRANSF Transformer 1G Trouble 1G 27 VBD-C-3 1-4 250VDC 250V DC Swgr. IA or 18 12 2 Breaker Trip 28 VBD-C-3 1-5 125VDC 125V DC Swgr. Bus 1B 7 2 IB Breaker Trip 29 VBD-C-3 2-4 250VDC 250V DC System 2 2 Transfer 30 VBD-C-3 3-4 250VDC 250 V DC Battery 3 2 1A Charger 1A Trouble 31 VBD-C-3 4-4 250VDC 250V DC Battery 3 2 IB Charger 1B Trouble 32 VBD-C-3 5-2 24VDC 24V DC Battery Charger 3 2 Al A1 Trouble O
- Subject to verification against number of sensors and trip setpoints in each of the alarm circuits.
n p MULTI-It!PUT ALARMS VBD-C (continued) U ITEM ALARM # OF
# PAtlEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 33 VBD-C-3 6-2 24VDC 24V DC Battery Charger 3 3 A2 A2 Trouble 34 VBD-C-3 64 125VDC 125 VDC System 5 3 Transfer 35 VBD-C-3 6-5 MG-1A Rx. Protection MG Set 2 3 1A Motor Disconnected ,
36 VBD-C-3 7-2 24VDC 24V DC Battery Charger 3 3 81 B1 Trcuble 37 VBD-C-3 7-4 125VDC 125V DC Battery 3 2 1A Charger 1A Trouble 38 VBD-C-3 7-5 MG-1B Rx, Protection MG Set 2 3 1B Motor Disconnected q 39 VBD-C-3 8-2 24VDC 24V DC Battery Charger 3 2 V B2 B2 Trouble 40 VBD-C-3 8-4 125VDC 125V DC Battery 3 2 18 Charger 1B Trouble 41 VBD-C 4 1-1 4160V 4160V Swgr. 18 Main 2 3 SWGR Breaker IBfl Trip 42 VBD-C-4 1-2 4160V 4160V Swgr. 1B Main 6 3 SWGR Breaker 185 Trip 43 VBD-C-4 1-3 4160V 4160V Swgr. 1G Main 7 3 SWGR Breaker 1GB Trip 44 VBD-C-4 1-4 4160V 4160V Swgr. 1G Main 5 3 SWGR Breaker 1GS Trip 45 VBD-C-4 1-5 DGd2 Diesel Gen. #2 Breaker 9 2 EG-2 Trip 46 VBD-C-4 2-5 DGd2 Diesel Gen. #2 Relay 5 2 RELAY 86 Lockout 47 VBD-C-4 3-1 4160V 4160V Swgr. 1B Feeder 6 3 FEEDER Bkr. IBE Trip O
- Subject to verification against number of senscrs and trip setpoints in each of the alarm circuits.
I MULTI-INPUT ALARMS VBD-C (continued) l ITEM ALARM # OF
# PANEL ID . SYSTEM ALARM TITLE INPUTS
- PRIORITY 48 VBD-C-4 3-2 4160V 4160V Swgr. IB Feeder 6 3 Ekr. IBG. Trip FEEDER 49 VBD-C-4 4-3 4160V 4160V Swgr. 1G Feeder 6 3 j FEEDER Bkr. 1GE Trip 50 VBD-C-4 6-5 DG#2 Diesel #2 Day Tank 2 3 Level Hi-Low ,
1 51 VBD-C-5 1-5 DG#1 DG-1 C07 System 6 - 3 AbnormaT 4 52 VBD-C-6 1-5 DG#2 DG #2 CO System 6 3 2 j Abnormal J 53 VBD-C-7 1-2 ACB-3302 ACB-3302 Trouble 5 3 1, 54 VBD-C-7 1-3 ACB-3304 ACB-3304 Trouble 5 3 i )O 55 vBD-C-7 1-4 ACB-3306 ACB-3306 Troubie 5 3 56 VBD-C-7 1-5 ACB-3308 ACB-3308 Trouble 5 3
! l ! 57 VBD-C-7 3-4 ACB-3306 ACB-3306 Trip 2 3 Ponitoring i
1 58 VBD-C-8 1-1 ACB-3310 ACB-3310 Trouble 5 3 l 59 VBD-C-8 1-2 ACB-3312 ACB-3312 Trouble 5 3 ! i i 60 VBD-C-8 1-5 345KV 345 KV Swyd Trouble -- 3 l SWYD 61 VBD-C-8 2-4 345KV 345 KV Bkr Sync Sw On -- 3 j BKR ( 62 VBD-C-8 3-1 ACB-3310 ACB-3310 Trip 4 3 ! ! Monitoring I' 63 VBD-C-8 3-2 ACB-3312 ACB-3312 Trip 4 3 I Penitoring , l 64 VBD-C-8 3-4 AUTO Auto Trans Trouble 12 3 TRANSFER { I t i
- Subject to verification against nurber of sensors and trip setpoints in I cach of the alarm circuits.
4 !
( MULTI-INPUT ALARMS VBD-C (continued) ITEri ALARM # OF
# PANEL ID SYSTEM ALARM TITLE INPUTS
- PRIORITY 65 VBD-C-8 3-5 DCB-1604 DCB-1604 & 1606 Trip 2 3
& 1606 Monitoring 66 VBD-C-2 1-1 Main Main Generator Station 13 3 Generator Lockout Relays Tripped 67 VBD-C-2 4-3 Main Main Generator Potential 2 3 Generator Transformer Failure ,
68 VBD-C-2 4-5 Main Main Generator Ground 2 3 Generator Detection Monitor 69 VBD-C-2 5-2 Startup Startup Service 2 3 Trans- Transformer Zcne former Protective Relays 70 VBD-C-2 7-5 480V IE Station Service 5 3 Bus Transformer IE Ground O O 71 VBD-C-2 8-5 480V 1F Bus Station Service Transformer IF Ground 11 3 72 VBD-C-2 9-5 480V 1G Station Service 11 3 Bus Transformer 1G Ground 73 VBD-C-3 3-2 Board F Board F Lockout Relay 17 3 Lockout Monitoring Relay 74 VBD-C-3 5-3 Inverter No Break System 2 3 1A Inverter 1A Voltage Failure O V Subject to verificatior against number of sensors and trip setpoints in each of the alarm circuits.
m_u-4.A2-h- us e hu a u.4 m A SL hm --- -- S Mh' " " - ACmh-u*4*w---&- - 6Ah.Ah2 *.-..Ah w --J Jhau. -MhM-E-- -- 4-_m .Jm-.*uu*-eh u4- --mer_w--_ 1 e e i i 1 i 4 9 . I e k i t i i i a 1 l J l 1 ! APPENDIX D f DCDR VALIDATION CilECKLIST 1 i 1 i J l i l i , I l l i I t i f I l I i f r h I [ k O i i
P.1 of 10 APPENDIX D
, O DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date:
Reviewers:
,, ; Enhancements /Modifigations Item Compliance Remarks
- 1. Relocation or Addition of Components is in Accordance with Components' Modification List for this Panel. l O
l. l 1
- 2. Removal of Components Is As Specified In Panel Design Change Document i
.i lO I l i i
P. 2 of 10 b DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications Item Ccmpliance Remarks
- 3. Panel Layout ,.
3.1 Functional Demarcation 0 LINE WICTHs 73 MAJen DivisicNs ( ) - 3/8"
- SuspANE'. - 1/4"
- WITHIn SuaPANEL
- 1/8" LABEL EXTENsiCN LINES - 1/16*
- ANNUNCIATC8/
CP!TicAL C:sta:Ls - 3/8" O CCL30 08 DE"ARCA?!CN LINES
- N 0
- v A L ', Y BLUE ANNUNCIATO*
CONim0'. G80uP:NG - cRANGE CP: tcAL CcNTRets/IN0!C-ATICNs
- Rf O Ccantas
- N0 ara;,Lv Hitat:
ANNUNCIA7CS/ Cn!!! CAL C:Niac.s - s:vAnt: !3 U .
P. 3 of 10 DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: .. Review Date: Reviewers: Enhancements / Modifications - Item Compliance Remarks
- 3. Panel Layout (cont'd) 3.2 Mimic Arrangements 0 LINE W!CTH$
PRIMARY Flow (D 'J_ PATH $ (To REACicP): 3/16" LINES WITH 1/8" DASHED LINE SUPERIMPOSE' CN THE 3/15' LINE OTHER Flew PATH $ - 3/15" LINES
- MINIMUM Flew BYP AS$ - 1/8" LINE o Flew DIRE T! 4 -
ARRCwHEAD$ $ PACE TC C'. E ARLY REVE AL FL w DIPECT!c4 o STAN ARD $YP30',$ U$t3 (EXAMP'.!$: HFCI Tues!NE, HPC: PUMP, RHR HX) O MIM!C CRIGIN At:* TESM!NAL PolNTS 10ENT!FIE A
./
P. I4 of 10 DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawino ID: Review Date: Reviewers: Enhancements / Modifications . Item Ccmpliance Remarks 3.2 Mimic Arranaements (cont'd) o COLOR C:stNG CONVENT!CN! FOR MIMICS STEAM LINES - RED PRrwAnv Ftew f~') PATH = LIGHT BLUE WITH THIN BLUE DASHE3 LINES TEST l!NE5 - LIGHT BLUE MINIMUM. Flow BYPASS l!NES - LIGHT BLUE (1/8) NITROGEN LINES
- YELLCW AIR LINES -
LIGHT BRCW"! j RHR S:C M::E cF OPERATICfl = DARK BRC'*4 a l RHR Pc0L CCOLING - LIGwT BLUE
- RHR TcRus t DW SPRAYS - PU8PLE I - RHR SERVICE WATER - ARK GREEN ,em, ._/
l
P. 5 of 10 C) U DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST . Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications Item Compliance Remarks I 1 l I4, Controls o CONTROL CODING YELLOW BAND CR COLLAR FOR PUMPS CR FANS Cs - OVAL FLUTED KNOB FCP THROTTLE VALVES o CcNTROL VISIBILITY l P0tnTER I CONTRCL LABEL CCnTRCL OPTienS o GUARD CRITICAL CONTacLS RE3 LABELS /0EMARCATICM PHYSICAL GUAR 01 FCE VULNERAELE COMTRC.' S l o ConTRet MovErEni DIRECTION
- NcRMALLY RIGHT, CLCCKWISE. UP. CP IN FCR INCREASE C#
ACTIVATICN O
P. 6 of 10 DCRDR PANEL ENHANCElENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications - Item Compliance Remarks
- 5. Meters and Chart Recorders-Corrections are in Accordance with Displays' Enhancement Document:
() 'd 0 SCALE BANDING AND ENTRY TO EMERGENCY MARKS 0 SCALE MARKINGS NINE MARKINGS BETWEEN NUMERALS OR LESS DISTINGUISHABLE MAJCR, MINCR & INTERMEDIATE MARKINGS 0 SCALE PROGRESSION: 1,2, 5 OR DECIMAL MULTIPLES 0 REG. GUIDE 1.97 NOTATIONS CN CRITICAL INDICATIONS 0 SCALE UNITS SHChN O Pointer extends to S cIleSt grcduct!Cn marks, parallcx cv01ded. O Scale directienclity -up or left for increOSe
P. 7 of 10
'r -(V DCRDR PANEL ENHANCE'iENTS 8 MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date:
Reviewers: Enhancements / Modifications Item Compliance Remarks
- 6. Indicator Lights a Negative indications-avoided o Two-lamp redundancy
""*r*
O o
' " d*d Color Coding-
- Red: Active state, flow, running
- Green: Deactivated,
- no-flow, off
- Amber: Onset of abnormal events or states; operator alert
- Blue: Bypasses
- White: Normally -
Illuminated O
P. 8 of 10 V DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications . Item Ccmoliance Remarks
- 7. Labeling 0 Camponent Reicbeling IS in ACCordonCe with Lcbel Chcnge Document 0 LABEL PLACEMENT
SUMMARY
LABELS ABOVE COMPONENT GROUPINGS
SUMMARY
LABELS NORMALLY WITHIN DEMARCATION LINES CcMPONENT LABELS ABOVE CONTRCLS AND BELOW DISPLAYS O LETTER AND 3ACKGROUND COLOR I ELACX-ON-WHITE IS MADE STANDARD, j NORMALLY l - RED-CN-WHITE LABELING FCR HIGHLIGHTING CRITICAL CCHTRCLS O LABEL SIZES MAJcR PANEL ID - 1" LETTERS SYSTEM LABEL - 1/2" SUBSYSTEM - 1/4" (' - CCMPCNENT - 3/16" ( - ANNUNCIATOR CONTRCLS - 1/4" CRITICAL CCNTROLS - 3/16" POWER SUPPLIES - 1/C"
P. 9 of 10 0 DCRDR PANEL ENHANCEMENTS & MODIFICATIONS VALIDATION CHECKLIST Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications Item Cmpliance Remarks
- 7. Labelina (cont'd) 0 INFORMATION, CAUTION AfC WARNING LABELS l gm. -
BLACK-ON-WHITE FOR ' (_j) INFORMATION LABELS BLACK-ON-AMBER FOR CAUTION LABELS WHITE-ON-RED FOR WARNING LABELS l 0 -Informal Lcbeling I ReplcCed 1 I l l l l r\ b
P. 10 of 10 O DCRDR PANEL ENHANCEMENTS 8 MODIFICATIONS VALIDATT.ON CHECKLIST Panel ID: Drawing ID: Review Date: Reviewers: Enhancements / Modifications ' Itein Compliance Remarks
- 8. Annunciators o STANDARDIZATICN OF ANNUNCIATCR RESPONSE CONTROLS - TRIANGULAR ARRANGEMENT o FUNCTIONAL DEMARCAT!CM CF l ANNUNCIATOR CONTROL GROUP!NG - CRANGE LINE!
0F DEMARCATION O LABELING 0F ANNUNC!ATCR MATRIX CCCRDINATES NUMERIC - NUMERIC l CCDING o COLOR CCDING OF AlanM TILES I WHITE: GENERAL ALARMS 8 A0V!$ CRY INFORMATICN RED: RPS TRIP ALARMS AND ENTRY TO E0Ps AMBER: ALARMS THAT REcV!RE CPERATOR
, ATTENTION TO PREVENT i
ONSET OF A RED ALARM, OR TO PREVENT p ECUIPMENT FAILURE 0 0 Elimination of multi-incut clarms where acerator confusion or delcy mcy result
- = - - _ _ _ _ _
O
! i APPENDIX E
, E.1 DCRDR OPERATING TRAINING LESSON PLAN (p. I to 56) l E.2 PARTICIPANTS HANDOUT (p. I to 119) O l l
APPENDIX! E E.1 DCRDR OPERATING TRAINING LESSON FLAN TABLE OF CONTENTS [] x-Item Page I. LESSON PLAN (Pages 1 to 56) o Program Duty Area, Subject 1 o References Training Material 2 Objective 3 o o Human Factors Engineering - History and 4 Technical Backgrcund o NPPD DCRDR Effort 9 CNS. Human Factors Engineering Standards 17 o
- Panel Layout 17 Controls 24
- Meter and Chart Recorders 25
- Labeling 27
- Annunciators 32 o Panel Changes Scheduled for Implementation in the 1986 Refueling Outage:
- Panel 9-3 Enhancements & Modifications 35 Panel 9-4 Enhancements & Modifications 38
- Panel 9-5 Enhancements & Modifications 42
- VBD-S Enhancements & Modifications 44
- j. 3 VBD-J Enhancements & Modifications 47 U -
- VBD-R Enhancements & Modifications 49 o Description of Participants' Handout 53 Reference Material 53 Checklists 54 II PARTICIPANT HAND 0UT (Pages 1 to 119) j 1. Reference Material 6 Panel 9-3 7 A.
l - Description of Enhancements & Modifications
- Upgraded Panel Drawing
- List of Affected Components
- Label Changes B. Panel 9-4 37 C. Panel 9-5 58 D. VBD-S 78 l E. VBD-J 88 F. VBD-4 96
- 2. Checklist 112 2.1 Description 112 2.2 Checklist Sheets 114 O
NEBRASKA PUBLIC POWER DISTRICT R0P8SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 1 0F 56 REVISION 0 LESSON PLAN (]) PROGRAM: REACTOR OPERATOR, SENIOR REACTOR OPERATOR AND SHIFT TECHNICAL ADVISOR SYSTEM / DUTY AREA: CONTROL ROOM TASK /
SUBJECT:
DCRDR, HUMAN FACTORS ENGINEERING AND CONTROL ROOM PANEL CHANGES DEVELOPED: M. M. ABUROMIA l0/24/1986 DEVELOPER DATE APPROVED: SUPERVISOR DATE RECORD OF REVISIONS REV. NO, PREPARED BY/DATE APPROVED BY/DATE 01 02 03-04 05 f I
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 2 0F 56 REVISION O PROGRAM: REACTOR OPERATOR AND SHIFT TECHNICAL ADVISOR /~w) (_ SYSTEM DUTY AREA: CONTROL ROOM TASK /
SUBJECT:
DCRDR, HUMAN FACTORS ENGINEERING AND CONTROL ROOM PANEL CHANGE PRESENTATION TIME: FOUR (4) HOURS
REFERENCES:
- 1. REQUIREMENTS FOR EMERGENCY RESPONSE CAPABILITY, NUREG-0737, SUPPLEMENT 1, DECEMBER 17, 1982.
- 2. GUIDELINES FOR CONTROL ROOM DESIGN REVIEWS, NUREG-0700, SEPTEMBER, 1981
- 3. CNS CONTROL ROOM HUMAN FACTORS ENGINEERING STANDARDS AND IMPLEMENTATION GUIDELINES, GENERAL ELECTRIC COMPANY, MDE-142-0585, AUGUST 1984.
- 4. CNS DETAILED CONTPOL ROOM DESIGN REVIEW
SUMMARY
REPORT, FEBRUARY 1983.
- 5. CNS DETAILED CONTROL ROOM DESIGN REVIEW SUPPLEMENT TO THE
SUMMARY
REPORT, FEBRUARY 1985 O(~s (TP-1) TRAINING MATERIALS / EQUIPMENT LOCATION
- 1. TRANSPARENCIES TP-1 THROUGH LESSON PLAN PACKAGE TP-43
- 2. OVERHEAD PROJECTOR CLASSROOM
- 3. STUDENT HANDOUT H0-1 TRAINING MATERIALS STORAGE AREA
- 4. DETAILED DESIGN DRAWINGS CLASSROOM OF THE UPGRADED PANELS:
PNL 9-3, 9-4, 9-5, VBD-S, VBD-J, AND VBD-R PREREQUISITES NONE ,, O
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 3 0F 56 REVISION 0 LESSON OBJECllVES ([) INSTRUCIOR GUIDE OBJ. (TP-2) OBJECTIVE GIVEN THE FOLLOWING INFORMATION: 1.A THE HISTORY AND TECHNICAL BACKGROUND OF HUMAN FACTORS ENGINEERING AS IT APPLIES TO THE NUCLEAR POWER INDUSTRY. 1.B NPPD DCRDR EFFORT TO COMPLY WITH NRC REQUIREMENTS. 1.C GENERIC HUMAN FACTORS ENGINEERING STANDARDS APPLICABLE TO CNS. 1.D PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE. AND THE PARTICIPANTS HAND 0UT OF:
, 2.A DESCRIPTION OF PANEL ENHANCEMENTS AND (J MODIFICATIONS.
2.B PANEL UPGRADE DRAWINGS 2.C LISTINGS OF ALL COMPONENTS THAT WERE ADDED, OR RELOCATED. 2.D LISTINGS OF LABEL CHANGES. PARTICIPANTS WILL BE ABLE TO COMPLETE A PANEL WALK-THROUGH CHECKLIST IDENTIFYING ALL ENHANCEMENTS AND MODIFICATIONS, AND RELOCATING ALL SWITCHES AND INDICATIONS. l v
NEBRASKA PUBLIC POWER' DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 4 0F 56 REVISION 0 (]) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.A HUMAN FACTORS ENGINEERING (HFE) DEFINITION, GENERAL PURPOSE TP-3 1.A-1 THE HUMAN FACTORS (HF) DISCIPLINE O A DISCIPLINE CONCERNED WITH THE SYSTEMATIC APPLICATION CF WHAT IS KNOWN ABOUT HUMAN BEHAVIOR DURING THE DEVELOPMENT OF A PRODUCT OR SYSTEM 0 HF DATA BASE DERIVED FROM SCIENTIFIC DISCIPLINES OF PSYCHOLOGY, PHYSIOLOGY, SOCIOLOGY, PERSONNEL-SELECTION, AND EDUCATION O PRIMARY PURPOSE OF APPLYING HF PRINCIPLES IN THE DEVELOPMdNT OF ENGINEER!f4G SYSTEMS IS TO REDUCE POTENTIALS FOR HUMAN ERROR THAT COULD AFFECT SYSTEM SAFETY AND/OR PRODUCTIVITY. l i
' ~^ ~ ~
NEBRASKA PUBLIC PbsER DISTRICT ROP &SRUSSf61TCh'-Jh-00f COOPER NUCLEAR STATION PAGE 5 0F 56 REVISION 0 - LESSON MATERIALS n INSTRUCTOR GUIDE U ILLUSTRATION OF MAN-MACHINE TP 14 j
- FIG.1, SCHEMATIC REPRESENTATION OF MAN-MACHINE i INTERFACE AND THE NEED FOR APPLYING HUMAN I
FACTORS IN THE DESIGN OF DISPLAYS & C0tlTP.0LS i 1 i worn envronment [
- o 4- ==
5~ r. m ,..m., s _e a... xg6 i .
*
- g.
\
Disc:oys - ..,...s l
.c ,
i bow' ' N oj,,, e lO i l l
NEBRASKA PUBLIC POWER DISTRICT R0P&SR08STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 6 0F 56 REVISION 0 ([) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.A-2 ORIGIN AND APPLICATIONS OF HF TO ORIGIN & ENGINEERING SYSTEMS APPLICATIONS TP-5 0 THE NEED FOR APPLICATION OF HUMAN BEHAVIOR IN SYSTEM DEVELOPMENT WAS RECOGNIZED DURING WORLD WAR.II, TO REDUCE HUMAN ERROR IN COMPLEX MILITARY SYSTEMS O FOR MANY YEARS, HF EXPERTISE WAS ALMOST EXCLUSIVELY APPLIED TO MILITARY SYSTEM DEVELOPMENTS, AND LATER TO SPACE APPLICATIONS WHERE HIGH SYSTEM RELIABILITY IS A REQUIREMENT. 0 OvER THE PAST DECADE, HF KNOWLEDGE HAS BEEN EXTENDED TO INFORMATION SYSTEMS, ARCHITECTURE, SIMULATOR SYSTEMS, CONSUMER PRODUCTS, AND MEDICAL FACILITIES.
NEBRASKA PUBLIC POWER DISTRICT R0PgSR08STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 7 0F 56 REVISION O ([) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.A-3 RELEVANCY OF HFE TO NUCLEAR NEED TO IMPROVE POWER PLANT SAFETY HFE IN CONTROL ROOMS 0 TRACED TO WASH-1400, NUCLEAR TP-6 REACTOR SAFETY STUDY - NRC, 1975, THAT DOCUMENTED:
" INCREASED RISK. POTENTIALS ATTRIBUTABLE TO DISCREPANCIES IN THE DESIGN OF CONTROL ROOM, PANELS, AND DISPLAY / CONTROL INSTRUMENTS."
O EPRI-SPONSORED REVIEW OF FIVE REPRESENTATIVE PLANTS, THAT
) DOCUMENTED:
"A LACK OF SYSTEMATIC APPLICATION OF HUMAN FACTORS PRINCIPLES AND CRITERIA IN OPERATIONAL PLANTS."
O NUREG-0585, TMI LESSONS LEARNED TASK FORCE,
".. 0NE OF THE MOST IMPORTANT LESSONS LEARNED FROM THE THREE MILE ISLAND ACCIDENT IS THAT THERE IS A NEED TO RAPIDLY IMPROVE THE HUMAN FACTORS ENGINEERING IN THE DESIGN AND LAYOUT OF EXISTING AND FUTURE CONTROL ROOMS."
O
NEBRASKA-PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 8 0F 56 REVISION 0 i ($) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.A-4 NRC REQUIREMENTS FOR DCRDR AND REQUIREMENTS INCLUSION OF HFE FOR DCRDR TP-7 0 NUREG-0660, ACTION PLAN FOR IMPLEMENTING RECOMMENDATIONS OF THE PRESIDENT COMMISSION AND OTHER STUDIES OF THE TMI-2 ACCIDENT, "THESE ACTIONS INCLUDE STEPS TO IMPROVE EXISTING AND FUTURE CONTROL ROOM DESIGNS, TO DEVELOP STANDARDS AND REGULATORY GUIDES RELATED T0 (-) CONTROL ROOM DESIGN AND HUMAN FACTORS ENGINEERING" O NUREG-0737, EMERGENCY RESPONSE CAPABILITY, TASK I.D,1, DETAILED CONTROL ROOM DESIGN ' REVIEW REQUIREMENTS, CONDUCT CONTROL ROOM
- DESIGN REVIEW TO IDENTIFY HUMAN ENGINEERING DISCREPANCIES (HEDS)
ASSESS THE SIGNIFICANCE OF HEDS AND SELECT DESIGN IMPROVEMENTS THAT CORRECT THOSE DISCREPANCIES, {}
NEBRASKA PUBLIC POWER DISTRICT R0P&SRO&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 9 0F 56 REVISION 0 ([) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.B NPPD DCRDR EFFORT THE DCRDR TEAM
& OPERATOR 1.B-1 SETTING-UP A REVIEW TEAM INVOLVEMENT TP-8 0 TEAM MEMBERS CONSISTED OF:
- LICENSED OPERATORS &
SENIOR OPERATORS, R0, SRO, (CNS)
- SYSTEM ENGINEER (GE)
- HF SPECIALIST (GE)
- igg SPECIALISTS (CNS &
NPPD) 0 TEAM FUNCTIONS UNDER DIRECTION OF:
- CNS OPERATIONS MANAGER
- CNS TECHNICAL MANAGER 8
- NPPD DCRDR PROGRAM MANAGER t
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 10 0F 56 REVISION 0 LESSON MATERIALS (]) INSTRUCTOR GUIDE ITEM #1 1.B-2 CONDUCTING THE REVIEW PROCESS DESCRIPTION OF PROCESS USED IN REVIEW TASKS CONSISTED OF: CONTROL IDENTIFYING ROOM SURVEY, FUNCTION & DISCREPANCIES TASK ANALYSIS, AND OPERATING TP-9 EXPERIENCE REVIEW - SEE FIG. 2 0 CONTROL ROOM SURVEY. AREAS SURVEYED:
- PANEL LAYOUT AND DESIGN
- INSTRUMENTATION AND HARDWARE
() - ANNUNCIATORS
- COMPUTERS
- PROCEDURES
- CONTROL ROOM ENVIRONMENT 8 COMMUNICATION O FUNCTIONS AND TASK ANALYSIS:
ANALYSIS PERFORMED TO VERIFY THE AVAILABILITY AND SUITABILITY OF THE INSTRUMENTS
- TO MEET THE STEPS IDENTIFIED IN THE EMERGENCY OPERATING PROCEDURES.
l (])
. . . =. . ... . -. . - .
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 11 0F 56 REVISION 0 0 INSTRUCTOR GUIDE LESSON MATERIALS DESCRIPTION OF DCRDR PROCESS TP-10 FIG.2 CNS CONTROL ROOM DESIGN REVIEW PROCESS
- REviYw DATA SOURCES **ECxt$sY dYvfis SUPPLEMENT I
HUMAN ENOR. c'55g','o"' .
~'
Q HED IDENTIFICATION l HUMAN EN0iNEERING OISCREPENCIES 'HEDe* l I l DELETES l l O.U'U .e. ASSESSMONT I l CORRECTION SY CORRECTION SY E,',,'
*,'".'",'T'"
; ti..ii . '""*"c'"*"' """'"
' l CATEcoRr
,,,,,,,,,,,,,,, C4TE,0oRr ,
g,g,ya~.. = nx ogg.N 0;";.R TE#a"
- m,7..r... .=....'
.e _, . ,
ses,edule F., eisT M*d'g ,, 1ST,2NO.3RO.4TH lapiematosten Rtrutun0 oEsica uoo. REFUELING O
NEBRASKA PUBLIC' POWER DISTRICT R0P8SR08STA-DCR-DR-001 l COOPER NUCLEAR STATION PAGE 12 0F 56 REVISION 0 0 INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.B-2 CONDUCTING THE REVIEW PROCESS OPERATING (CONTINUED) EXPERIENCE 8 OPERATOR INPUT 0 PLANT OPERATING EXPERIENCE USED IN REVIEW IDENTIFYING DISCREPANCIES - LERS AND SCRAM REPORTS, . TP-11 IN THE PERIOD FROM APRIL 1981 TO APRIL 1984 WERE REVIEWED, TO IDENTIFY HFE CONSIDERATIONS THAT MAY CONTRIBUTE TO OPEPATOR ERROR. O - OPERATOR INTERVIEWS WERE CONDUCTED TO OBTAltl DIRECT CONTROL ROOM INFORMATION FROM THE USER'S POPULATION. WRITTEri QUESTIONNAIRES WERE COMPLETED BY 21 OPERATORS. O hecimum muum ll m _ _ _ _
NEBRASKA PUBLIC POWER DISTRICT R0P8SRbahTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 13 0F 56 REVISION 0 (~') INSTRUCTOR GUIDE LESSON MATERIALS v ITEM #1 IB-3 IDENTIFICATION OF HUMAN ENGINEERING NOTING SOME DISCREPANCIES (HEDS) 0F THE DISCREPANCIES 0 FOLLOWING THE CONTROL ROOM FOUND IN CNS REVIEW, DEVIATIONS FROM HF ROOM CONTROL STANDARDS WERE ASSESSED TP-12 BY THE DCRDR TEA.M, AND THOSE NOTED FOR SIGNIFICANCE WERE IDENTIFIED AS HEDS, REFER TO FIG. 2 (DCRDR REVIEW PROCESS) FOR HED ASSESSMENT. Q . T l i Oe 'l jO
NEBRASKA PUBLIC POWER DISTRICT R0PgSR0aSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 14 0F 56 REVISION O INSTRUCTOR GUIDE LESSON MATERIALS -(]) ITEM #1 SELECTED HEDS FIG.3 EXAMPLES OF HEDS FOR ONE BACK FOR (VBD-S) PANEL (VBD-S) TP-13 HED DESCRIPTION 110S NO PHYSICAL DISTINCTION BETWEEN HANDLES. CODING BY SIZE, SHAPE OR COLOR IS NOT BEING USED. 164S ANNUNCIATOR RESPONSE CONTROLS NOT CODED FOR EASE OF RECOGNITION O 63T SECONDARY CONTAINMENT (SC) SUMPS' WATER LEVEL INDICATIONS NOT AVAILABLE. 64T ALARM FOR SECONDARY CONTAINMENT TOP,US AREA LEVEL, AS AN ALERT TO EMERGENCY, NOT AVAILABLE. 177SS INDICATORS NOT MARKED TO SHOW NORMAL RANGES OF OPERATION. 181SS ANNUNCIATOR ALARMS NOT PRIORITIZED FOR REQUIRED RESPONSE LEVEL BY LEGEND PLATE C0VER, 174SS- RELATED GROUPS OF CONT 0LS OR DISPLAYS NOT SET OFF BY DEMARCATION LINES. 89SS EXTENSIVE TEMPORARY LABELS BEING USED
NEBRASKA PUBLIc POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 15 0F 56 REVISION 0 () INSTRUCTOR GUIDE , LESSON MATERIALS ITEM #1 SELECTED HEDs FIG. 4, EXAMPLES OF HEDS FOR ONE FRONT PANEL FOR PANEL 9-3 (PNL 9-3) (c0NTINUED) TP-14 HED DESCRIPTION 13SS INSTRUMENTS ARE NOT SCALED IN PROCESS UNITS RELATING TO SYSTEM OPERATION. 15I LACK OF DIRECT ACCIDENT WATER LEVEL INDICATION, ISS LACK 0F MIMICS INTEGRATING SYSTEM COMPONENTS, 39T SP LEVEL ALARM UTILIZES COMMON ANNUNCIATOR (]) FOR BOTH HIGH AND LOW LEVELS., 9SS INDICATING CONTROLLER DOES NOT FOLLOW CONVENTIONAL PATTERN, 35T RHR SERVICE WATER PUMP CONTROLS a INDICATIONS - LOCATED ON BACK PANELS RATHER THAN PANEL 9-3, 19T WIDE RANGE TORUS PRESSURE RECORDER NOT AVAILABLE, 88S RECORDER SCALES NOT MARKED TO SHOW NORMAL / ABNORMAL RANGES OF OPERATION, ISS GROUPINGS OF CONTROLS AND DISPLAYS OF SIMILAR FUNCTIONS NOT APPARENT,
NEBRASKA PUBLIC POWER DISTRICT R0P&SRO&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 16 0F 56 REVISION O LESSON MATERIALS (]) INSTRUCTOR GUIDE ITEM #1 1.B-4 SELECTION AND IMPLEMENTATION OF INTRODUCTION TO DESIGN CORRECTIONS THE 1986 PANEL CORRECTIONS 0 GENERIC HFE GUIDELINES TP-15 DEVELOPED AND MADE STANDARD FOR CNS CONTROL ROOM O ENHANCEMENTS AND DESIGN CORRECTIONS OF SIX PANELS WERE , DEVELOPED AND WILL BE IMPLEMENTED DURING THE 1986 REFUELING OUTAGE. THE UPGRADED PANELS ARE: PANEL 9-3, REACTOR & ($) - CONTAINMENT COOLING
- PANEL 9-4, RCIC, PC, RW, RWCU, REACTOR RECIRC
- PANEL 9-5, REACTOR CONTROL & FEEDWATER CONTROL
' - VBD-S, SUMP PUMPS
- VBD-J, SUPPRESSION POOL &
! TORUS PRESSURE RELIEF l - VBD-R, HEATING & 4 VENTILATION CONTROL 0 MOST OF THE REMAINING j CORRECTIONS WILL BE l IMPLEMENTED IN 2ND AND 3RD REFUELING OUTAGES. I O
NEBRASKA PUBLIC POWER DISTRICT R0P8SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 17 0F 56 REVISION 0 O INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.C CNS HUMAN FACTORS ENGINEERING DESCRIPTION OF STANDARDS GENERIC STANDARDS APPLICABLE TO CNS 1.C-1 PANEL LAYOUT TP-16 A. FUNCTIONAL DEMARCATION (REFER TO F.IG. 5) 0 LINE WIDTHS MAJOR DIVISIONS
- 3/8" SUBPANEL - 1/4" WITHIN SUBPANEL
- 1/8" O -
label ExTEnSi0n LINES - 1/16" ANNUNCIATOR / CRITICAL l CONTROLS - 3/8" l O COLOR OF DEMARCATION LINES I NORMALLY BLUE
- ANNUNCIATOP, CONTROL GROUPING -
ORANGE l I - CP,!TICAL CONTROLS /INDIC-ATIONS - RED O
NEBRASKA PUBLIC POWER' DISTRICT R0P& srb 8STA-DCR-DRbO1 COOPER NUCLEAR STATION PAGE 18 0F 56 REVISION O lQ INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.C CNS HUMAN FACTORS ENGINEERING DESCRIPTION OF STANDARDS (CONTINUED) GENERIC STANDARDS APPLICABLE To CNS 0 CORNERS TP-16 - NORMALLY MITRED
- ANNUNCIATOR /
CRIT,ICAL CONTROLS - SOUARED O . 1 4 l l I 'O l
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y --. -,_ ,,,, . . _ . - ,n,._-..-,,,,-,,,_,----_,-_n--------------,.--n.------,--,--------
NEBRASKA PUBLIC POWER DISTRICT R0P&SRO&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 19 0F 56 REVISION 0 LESSON MATERIALS p .a INSTRUCTOR GUIDE ITEM #1 FUNCTIONAL DEMARCATION FIG. 5 FUNCTIONAL DEMARCATION OF PANEL TP-17 SYSTEMS & SUBSYSTEMS
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NEBRASKA-PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 ' COOPER NUCLEAR STATI0rf PAGE 20 0F 56 REVISION 0 INSTRUCTOR GUIDE LESSON MATERIALS (])
- ITEM #1 1.C CNS HUMAN FACTORS ENGINEERING MIMICS, LINE STANDARDS WIDTHS AND COLOR CODING; 1.C-1 PANEL LAYOUT (CONTINUED)
TP-18 B. MIMIC ARRANGEMENTS (REFER TO FIG. 6) 0 LINE WIDTHS P^RIMARY FLOW PATHS (TO REACTOR): 3/16" LINES WITH 1/8" DASHED LINE s SUPERIMPOSED ON THE 3/16" LINE O - OTHER FLOW PATHS - 3/16" LINES MINIMUM FLOW
,~
BYPASS - 1/8"
~
LINE s O FLOW DIRECTION - ARROWHEADS SPACED TO CLEARLY REVEAL FLOW DIRECTION O STANDARD SYMBOLS USED (EXAMPLES: HPCI TURBINE, HPCI PUMP, RHR HX) O MIMIC ORIGIN AND TERMINAL POINTS O iDENTiPiED F
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NEBRASKA PUBLIC POWER DISTRICT RUP&SROSSTA-DCR-DRM01 COOPER NUCLEAR STATION PAGE 21 0F 56 REVISION 0 'A INSTRUCTOR GUIDE LESSON MATERIALS
.O ITEM #1 1.C-1 PANEL LAYOUT (CONTINUED)
MIMIC, LINE B. MIMIC ARRANGEMENTS WIDTHS AND COLOR (CONTINUED) CODING 0 COLOR CODING TP-18 CONVENTIONS FOR MIMICS STEAM LINES - R"ED PRIMARY FLOW PATH - LIGHT BLUE WITH THIfl BLUE DASHED LINES TEST LINES - O - TIGHT BtVE MINIMUM FLOW , BYPASS LINES - LIGHT BLUE (1/8) NITROGEN LINES
- YELLOW AIR LINES -
LIGHT BROWN RHR SDC MODE OF l, OPERATI0fl - DARK BROWN RHR POOL
-- COOLING - LIGHT BLUE l
' O) L
~e,- ~ ,, . - - - + -
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 22 0F 56 - REVISION 0
- O INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.C-1 PANEL LAYOUT (CONTINUED)
- MIMICS, LINE B. MIMIC ARRANGEMENTS
- WIDTHS AND COLOR (CONTINUED)
CODING TP-18 - RHR TORUS & DW SPRAYS - PURPLE RHR SERVICE WATER - DARK GREEN O I
~ . _ . . _ , . - . . . ~ , - _ . . _ _ - . . . _ _ . _ , , _ _ , _ . . _ , _ _ - . _ _ _ _ _ . , , _ _ . _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ , _ . _ _ , , . _ . _ _ _ _ _ _ _ , , , , .
NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 23 0F 56 REVISION 0
,n INSTRUCTOR GUIDE LESSON MATERIALS 4
v ITEM #1 ILLUSTRATION OF FIG. 6 MIMIC CONVENTIONS & COLOR CODING mimic CONVENTIONS TP-19 i; g er-- e o
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NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 24 0F 56 REVISION 0 INSTRUCTOR GUIDE LESSON MATERIALS (]) ITEM #1 1.C-2 CONTROLS STANDARDIZATION OF CONTROLS 0 CONTROL CODING
- TP-20 YELLOW BAND OR COLLAR FOR PUMPS OR' FANS OVAL FLUTED KNOB FOR THROTTLE VALVES u
! O CONTROL VISIBILITY POINTER CONTROL LABEL I () - CONTROL OPTIONS i l 0 GUARD CRITICAL CONTROLS RED l LABELS / DEMARCATION PHYSICAL GUARDS FOR VULNERABLE CONTROLS 1 3 0 ' CONTROL MOVEMENT ! DIRECTION 4
- NORMALLY RIGHT,
- CLOCKWISE, UP, OR IN FOR INCREASE OR I ACTIVATION l0 f
I
NEBRASKA PUBLIC POWER DISTRICT R0PgSRUSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 25 0F 56 REVISION 0 INSTRUCTOR GUIDE LESSON MATERIALS (]) ITEM #1 1.C-3 METERS AND CHART RECORDERS STANDARDIZATION (REFER TO FIG. 7) OF METERS 0 SCALE BANDING AND ENTRY TP-21 TO EMERGENCY MARKS 0 SCALE MARKINGS NINE MARKINGS BETWEEN NUMERALS OR LESS DISTINGUISHABLE MAJOR, MINOR & INTERMEDIATE MARKINGS O O SCALE PROGRESSION: 1,2, 5 OR DECIMAL MULTIPLES 0 REG. GUIDE 1.97 NOTATIONS ON CRITICAL INDICATIONS O SCALE UNITS SHOWN 1
~ ~ ~ ~ ~
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-D'CR-DR-001 COOPER NUCLEAR STATION PAGE 26 0F 56 REVISION 0-INSTRUCTOR sulDE LESSON MATERIALS O ITEM #1 COLOR BANDING OF METER SCALE & FIG. 7 COLOR BANDING CONVENTION FOR METER IDENTIFICATION OF AND CHART RECORDER SCALES ENTRY TO EMERGENCY TP-22 I i TM I h50
=
~ 4 :
O =.
=_ RED ARROWS - ENTRY
@ TO E0Ps W h5
- 20 5- A
^
- to TRANSPARENT GREEN b
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NEBRASKA PUBLIC POWER DISTRICT R0P8SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 27 0F 56 REVISION 0 ; l LESSON MATERIALS f[]) INSTRUCTOR GUIDE ITEM #1 1.C-5 LABELING (REFER TO FIG. 8) STANDARDIZATION OF LABELS 0 HIERARCHICAL LABELING - TP-23 PROVIDED TO COMPLIMENT EXISTING LABELING 0 LABEL PLACE. MENT
SUMMARY
LABELS ABOVE COMPONENT GROUPINGS
SUMMARY
LABELS NORMALLY WITHIN DEMARCATION LINES COMPONENT LABELS () ABOVE CONTROLS AND BELOW DISPLAYS v O
NEBRASKA PUBLIC POWER DISTRICT R0PaSR0gSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 28 0F 56 REVISION 0 n v INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 FIG 8 HIERARCHICAL LABELING AND LABEL PLACEMENT HIERARCHICAL LABELING IP-24 i .i L 'i
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! m.W Label Designation Location
- 1. System / workstation Centered near top .
label edge of panel 1
- 2. Stsysten/ functional Centered near top 1.itel of subsection ,
- 3. Component label Above control and below display
- 4. Control position Near control indicator O
NEBRASKA PUBLIC POWER DISTRICT P.bh& srb 8STA-DCR-Dk-001 COOPER NUCLEAR STATION PAGE 29 0F 56
! REVISION 0 LESSON MATERIALS
(]) INSTRUCTOR GUIDE 4 ITEM #1 1.C-5 LABELING (CONTINUED) -REFER TO FIG.9 LABELS' READABILITY 0 LETTER AND BACKGROUND TP-25 COLOR BLACK-ON-WHITE IS MADE STANDARD, NORMALLY RED-ON-WHITE LABELING FOR HIGHLIGHTING CRITICAL CONTROLS O LABEL SIZES MAJOR PANEL ID - 1" LETTERS SYSTEM LABEL - 1/2" SUBSYSTEM - 1/4" ([) - COMPONENT - 3/16" ANNUNCIATOR CONTROLS - 3/16" i - CRITICAL CONTROLS - 3/16" POWER SUPPLIES - 1/8" l l l i (S)
NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATI0tt PAGE 30 0F 56 REVISION O INSTRUCTOR GUIDE LESSON MATERIALS O ITEM #1 1.C-5 LABELING (CONTINUED) LABELS READABILITY TP-25 0 INFORMATION, CAUTION AND WARNING LABELS BLACK-ON-WHITE FOR INFORMATI0ft LABELS BLACK-ON-AMBER FOR CAUTION LABELS WHITE-ON-RED FOR WARNING LABELS O 1 1 1 e I I O 1
NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 31 0F 56 REVISION 0 () INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 STANDARDIZATION FIG 9 LABELING DIMENSIONS AND COLOR OF LABELING - CODING DIMENSIONS AND COLOR CODING TP-26 I u a PANEL VBD-S _o . 7..u T , y_ - !- ma ' 1/4" 7" ' . WW WW WW WR 3' 5" WW WW WW R4 a w . =: e g g. g g. RJ. RJ. RJ. RJ
.W W WV W W. W.
Ae R. R. NNN CC e NJ. TW WW -
!!: W..
. =
{ , . , . . . . . .. .- pm-4 7
COOPER NUCLEAR. STATION PAGE 32 0F 56 REVISION 0 INSTRUCTOR GUIDE LESSON MATERIALS (v~'t ITEM #1 1.C-6 ANNUNCIATORS (REFER TO FIG. STANDARDIZATION 10,1 AND 10.2 0F ANNUNCIATORS TP-27 0 STANDARDIZATION OF ANNUNCIATOR RESPONSE CONTROLS - TRIANGULAR ARRANGEMENT, O FUNCTIONAL DEMARCATION OF ANNUNCIATOR CONTROL GROUPING - ORANGE LINES OF DEMARCATION O LABELING OF ANNUNCIATOR MATRIX COORDINATES NUMERIC - NUMERIC CODING 0 COLOR CODING OF ALARM TILES WHITE: GENERAL ALARMS 8 ADVISORY INFORMATI0tl l j RED: RPS TRIP : ALARMS AND ENTRY TO l I E0PS f i l -. .-- -_- -_-- - . . - _ - _ - . - . _ - - _ - _ . - ---
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 35 0F 56 REVISION 0 LESSON MATERIALS (]) INSTRUCTOR GUIDE ITEM #1 1.C-6 ANNUNCIATORS (CONTINUED) STANDARDIZATION OF ANNUNCIATORS 0 COLOR CODING OF TP-27 ALARM TILES (CONTINUED) AMBER:, ALARMS THAT REQUIRE OPERATOR ATTENTION TO PREVENT ONSET OF A RED ALARM, OR TO PREVENT EQUIPMENT FAILURE O I l l(:) 1 I
liEBRA3KA PUBLIC POWER DlWRICT RUPISROX5:n-btn-un-uul 1 COOPER NUCLEAR STATION PAGE 34 CF 56 REVI5!0N O O INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 STANDARDIZATION OF ANNUNCIATORS T-28 FIG. 10.1 LABELING OF ANNUNCIATOR MATRIX COORDINATES t *2 ~3 4 .
.s ., .s l
, = -
- c. -
l z T -r -=. == 9:: .=s:. s 3 Y :-E =.- .5?. %:? :.=5 m i i 4 ?= 9 9 = . - E E F5. 55. lO se g= = =:= = .n .=, =s s == *
%.= :.: ~5 >:.: === =.= w FIG. 10.2 ANNUNCIATOR CONTROL ARRANGEMENT AND FUNCTIONAL DEMARCATION 40
- 40. ANNUNCIATOR NAMEPLATE .f
- 41. ANNUNCIATOR ACKNOWLEDGE l I qj L
p l 42 42 . ANNUNCIATOR RESET L l 82 . ANNUNCIATOR TEST iO
NEBRASKA PUBLIC POWER DISTRICT R0P&SR08STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 35 0F 56 REVISION O r^N INSTRUCTOR GUIDE LESSON MATERIALS V ITEM #1 1.D -PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTION OF SCHEDULED FOR IMPl.EMENTATION IN THE 1986 PANEL 9-3 REFUELING OUTAGE ENHANCEMEtlTS TP-29 1.D-1 PANEL 9-3, (REFER TO THE 1/4 SCALE COLOR DRAWINGS IN THE CLASSROOM)
~
A. ENHAf1 CEMENTS , O MIMIC ARRANGEMENTS SHOWIrlG FLOW PATHS FOR RHR, CS, AND HPCI WITH DISTINCTIVE COLOR CODING IDEllTIFYING VARIOUS MODES OF SYSTEM OPERATION 0 FUNCTIONAL DEMARCATION AND (]) LABELING OF VARIOUS DISPLAYS'/ CONTROLS' SUBGROUPINGS:
- PC, NBI, SW, A0G STM SUPPLY, ON 9-3L (LEFT SECTION OF THE PANEL)
- HPCI PUMP, HPCI TURBINE, A0G STM SUPPLY, ON 9-3C (CErlTER SECTI0tl 0F THE PANEL)
- PC, NBI, SW, RHR STM LINES, A0G STM LINES, MN STM ISOL VALVES, ON 9-3R (RIGHT SECTI0li 0F THE PANEL)
. O IDENTIFICATION OF ALARM TILES l
0F ANNUllCIATOR MATRICES, 9-3-1, 9-3-2, 9-3-3, AND 9-3-4 i () .
NEBRASKA PUBLIC POWER DISTRICT ROPESR0gSTA-DCR-DR-001
-COOPER NUCLEAR STATION PAGE 36 0F 56 REVISION 0 LESSON MATERIALS
(]) INSTRUCTOR GUIDE OBJECT #1 1.D-1 PANEL 9-3, (REFER TO THE 1/4 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) PANEL 9-3 (CONTINUED) ENHANCEMENTS TP-29 A. ENHANCEMENTS (CONTINUED) O CLARIFICATION OF, AMBIGUOUS LABELS, (REFER TO PNL 9-3 LABEL CHANGE DOCUMENT) 0 SCALE BANDING OF METERS AND CHART RECORDERS, AND MARKING. ENTRY TO EMERGENCIES () 0 DISTINCTION OF PUMP AND VALVE SWITCHES THROUGH CONTROL CODING OF PUMPS BY YELLOW BANDS
- RHR A8B PUMPS
- CS A&B PUMPS
- HPCI GLAND SEAL CNDSR BLOWER i
AND CONDENSATE PUMP AND
- AUXILIARY OIL PUMP i
i f l
NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 37 0F 56 REVISION 0 (]) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-1 PANEL 9-3, (REFER TO THE 1/4 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) PANEL 9-3 (CONTINUED) MODIFICATIONS 1P-30 B. MODIFICATIONS 0 RELOCATION OF RHR, CS AND HPCI CONTROLS NOTED ON PANEL 9-3 DRAWINGS IN THE CLASSROOM,
- SEE TABLE 1, LIST OF RELOCATED COMPONENTS ON 9-3L (STUDENT HANDOUT)
- SEE TABLE 2, LIST OF RELOCATED COMP 0NEflTS ON
($) 9-3C (STUDENT HANDOUT)
- SEE TABLE 3, LIST OF RELOCATED COMPONENTS ON 9-3R (STUDENT HANDOUT) 0 INCORPORATION OF RG 1.97 INSTRUMENTATION " TORUS PRESSURE RECORDER" O STANDARDIZATI0fl 0F ALARM RESPONSE CONTROLS 0 REMOVAL OF REACTOR HEAD SPRAY FLOW CONTROLLER FIC-142 0 REMOVAL OF REACTOR HEAD SPRAY VALVES M0-32 & 33 0 FUflCTIONAL SEPARATION OF PRIMARY CONTAINMENT DISPLAYS FROM REACTOR PRESSURE DISPLAY
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 38 0F 56 REVISION 0 , INSTRUCTOR GUIDE LESSON MATERIALS (]) __ ITEM #1 1.D PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTIOff 0F SCHEDULED FOR IMPLEMENTATION IN THE 1986 PANEL 9-4 REFUELING OUTAGE ENHANCEMENTS TP-31 1.D-2 PANEL 9-4, (REFER TO THE 1/4 SCALE COLOR DRAWINGS IN THE CLASSROOM) A. ENHANCEMENTS i 0 MIMIC ARRANGEMEilTS SHOWING FLOW PATHS FOR RCIC AND RWCU 0 FUNCTIONAL DEMARCATION AND LABELING OF VARIOUS DISPLAYS' () AND CONTROLS' SUBGROUPINGS:
- RCIC TURBINE, RCIC PUMP, MN ST LINE DRAINS, RX WTR CLEANUP, FLANGE LEAK 0FF Oil 9-4L
- RX BLDG SUMP, DW EQUIP DR SUMP, DW SUMPS, POST ACCIDENT SAMPLING SYSTEM, DEMIN. CONDUCTIVITY, Oil 9-4C.
i - NBI, PC, COMPUTER TREND, RRMG OIL PUMP-A, RRMG OIL PUMP-B, SC00PTUBE A&B ON 9-4R 0 MATRIX IDENTIFICATION OF ANNUNCIATORS THROUGH LABELIflG OF THE ANilVNCIATOR AXES FOR () 9-4-1, 9-4-2, AND 9-4-3
NEBRASKA PUBLIC POWER DISTRICT R0PgSR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 39 0F 56 REVISION 0 LESSON MATERIALS (]) INSTRUCTOR GUIDE OBJECT #1 1.D-2 PANEL 9-4, (REFER TO THE 1/4 SCALE DESCRIPTION COLOR DRAWINGS IN THE CLASSROOM) 0F PANEL 9-4 (CONTINUED) ENHANCEMENTS TP-31 A. ENHANCEMENTS (CONTINUED) 0 SCALE BANDING OF, METERS AND CHART RECORDERS AND MARKING ENTRY TO EMERGENCIES. O CONTROL CODING OF PUMPS BY YELLOW BANDS OR COLLARS, () - RCIC GLAND SEAL VACUUM AND CONDENSATE PUMPS ON 9-4L
- DW SUMP PUMPS, AND RWCU PUMPS ON PANEL 9-4C
- RRMG A & RRMG B OIL PUMPS ON 9-4R O
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 40 0F 56 REVISION 0 0 INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-2 PANEL 9-4, (REFER TO THE 1/4 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) PANEL 9-4 (CONTINUED) MODIFICATIONS TP-32 B. MODIFICATION O RELOCATION OF RCIC AND RWCU CONTROLS NOTED 011 PANEL 9-4 DRAWINGS IN THE CLASSROOM.
- SEE TABLE 7, LIST OF AFFECTED COMPONENTS Oft 9-4L (STUDENT HANDOUT)
- SEE TABLE 8, LIST OF AFFECTED COMP 0flENTS ON 9-4C (STUDEflT HANDOUT) 0 INCORPORATION OF RG 1.97 IflSTRUMEllTATION " TORUS PRESSURE RECORDER" ON 9-4R 0 STAflDARDIZIflG THE ARRANGEMENT OF ALARM RESP 0flSE CONTROLS, Oft 9-4C 0 FUNCT!0flAL SEPARATION OF HPCI TURBillE AND HPCI PUMP DISPLAYS Oft 9-4L
! O FUNCTIONAL SEPARAT10M OF PRIMARY C0flTAINMENT DISPLAYS f FROM REACTOR PRESSURE DISPLAY i Off 9-4R
~
I 'O t
NEBRASKA PUBLIC POWER DISTRICT R0PaSR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 41 0F 56 REVISION O LESSON MATERIALS ([) INSTRUCTOR GUIDE ITEM #1 1.D-2 PANEL 9-4, (REFER TO THE 1/4 SCALE DESCRIPTION COLOR DRAWINGS IN THE CLASSROOM) 0F PANEL 9-4 (CONTINUED) MODIFICATIONS IP-32 B. MODIFICATION (CONTINUED) O SWAPPING THE LOCATIONS OF COMPUTER TREND RECORDER AND SUCTION FEEDWATER TEMPERATURE RECORDER ON 9-4L (SEE TABLE 9, STUDENT HANDOUT) O . O . 1
NEBRASKA PUBLIC POWER DISTRICT R0PaSR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 42 0F 56 REVISION 0 INSTRUCTOR GUIDE LESSON MATERIALS (]) ITEM #1 1.D PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTION OF SCHEDULED FOR IMPLEMENTATION IN THE 1986 PANEL 9-4 REFUELING OUTAGE ENHANCEMEtlTS TP-33 1.D-3 PANEL 9-5, (REFER TO THE 1/4 SCALE COLOR DRAWINGS IN THE CLASSROOM) A. ENHANCEMENTS , O FUtlCTIOflAL DEMARCATION AND LABELING OF VARIOUS DISPLAYS AND CONTROLS' SUBGROUP!NGS:
- SRM MONITORS, NM BYPASS, GROUP ISOLATION INDICATIONS Off 9-4L
- IRM/APRM MONITORS, R0D O SEQUENCE CONTROL Oft 9-4C
- SCRAM INDICATIONS, RPV WATER LEVEL, RFW FLOW, RPV PRESS, FW FLOW CONTROLLERS, WATER LEVEL TRIP RESET Off 9-4R 0 IDErlTIFICATIOff 0F ALARM TILES OF ANNUtlCIATOR MATRICES Ofl 9-5-1 AND 9-5-2 0 MATRIX IDEflTIFICAT10fl 0F THE CONTROL ROD POSIT 10flS Off THE FULL CORE DISPLAY 0 SCALE BAflDING OF , METERS AND CHART RECORDERS, AND MARKlflG ENTRY TO EMERGENCIES 0 CONTROL CODING OF PUMPS BY YELLOW BANDS FOR CRD PUMPS A AND B AND SLC PUMP
NEBRASKA PUBLIC POWER DISTRICT R0P&SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 43 0F 56 REVISION 0 O rNSTRuCTOR GulDE LESSON MATERMLS
![
.: i i
ITEM #1 1.D-3 PANEL 9-5, (REFER TO THE 1/'t SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM)
- PANEL 9-5 (CONTINUED)
ENHANCEMENTS j TP-34 c. MODIFICATION $. 0 RELOCAT 0N OF GROUF 1 1 INDICATING LIGHTS ON 9-5L AND 2 ADDIT 10ft OF GROUPS 2,3,4,5,6,7 .
! INDICATING LIGHTS ON 9-5L 1 (LIGHTS WILL BE INSTALLED BUT fl0T FUNCTIONAL IN THIS OUTAGE) e O REPLACEMENT OF LPRM METER l I SCALES ON 9-5C O RELOCATION OF REACTOR FECD AtlD STARTUP FLOW CONTROLLERS ON '
9-5R (SEE TABLE 15 STUDEf4T HANDOUT) . O RELOCATION OF NARROW RANGE i 1 LEVEL INDICATIONS ON 9-5R l i 0 RELOCATION OF SELECTOR 3 l SWITCHES FOR STM FLOW, RX WTR LVL, AND 1 OR 3 ELEMENT, ON 9-5R ! O RELOCAT!0fl 0F HIGH WTR l I LVL/ TRIP LOGIC B Afl0 C RESET SWITCHES, Ofi 9-5R. [ I b 5 i i !O i l i , l 1 F
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 44 0F 56 REVISION 0 () INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTION OF SCHEDULED FOR IMPLEMENTATION IN THE 1986 VBD-S REFUELING OUTAGE ENHANCEMENTS TP-35 1.D-4 PANEL VBD-S, (REFER TO THE 1/2 SCALE COLOR DRAWINGS IN THE CLASSROOM) A, ENHANCEMENTS 0 FUNCTIONAL DEMARCATION AND LABELING OF SUMP CONTROLS IN TURBINE BLDG, RX BLDG, YARD AND CONTROL BLDG O 0 FUNCTIONAL DEMARCATION AND LABELING OF CONTROLS' AND DISPLAYS' SUBGROUPINGS WITHIN THE TURBINE AND REACTOR BUILDINGS
- RAD AREA EQUIP DRAINS, RAD FLOOR DRAINS NONRAD FLOOR DRAINS, IN TURBINE BUILDING
- AREA NW, AREA NE, AREA SW, AREA SE, TORUS AREA IN REACTOR BUILDING 0 ELIMINATION OF TEMPORARY LABELS THROUGH INCLUSION OF
- NEEDED INFORMATION ON THE NEW LABELS 0 RELABELING OF PANEL COMPONENTS IN A HIERARCHICAL SCHEME
(]}
NEBRASKA PUBLIC POWER DISTRICT R0P8SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 45 0F 56 REVISION 0 0 INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-4 PANEL VBD-S REFER TO THE 1/2 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) VBD-S (CONTINUED) ENHANCEMENTS TP-35 A. ENHANCEMENTS (CONTINUED) O SCALE BANDING OF AREA LEVEL INDICATIONS AND MARKING ENTRY TO EMERGENCIES. O DISTINCTION OF PUMP AND VALVE SWITCHES THROUGH CONTROL CODING OF PUMPS BY YELLOW BANDS 0 FUNCTIONAL DEMARCATION OF ANNUNCIATOR CONTROLS O
NEBRASKA PUBLIC POWER DISTRICT R0P8SR08STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 46 0F 56 REVISION 0 ([) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-4 PANEL VBD-S, (REFER _TO THE 1/2 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) VBD-S (CONTINUED) MODIFICATIONS TP-36 B. MODIFICATIONS 0 INCORPORATION OF,NEW REACTOR BUILDING SUMP 8 AREA LEVEL INDICATIONS O RELOCATIOfj OF ERP PUMP COUNTERS AND RUN TIME DISPLAYS TO IMPROVE VlSIBILITY (3 (> 0 RELOCATION 4ND SUBGROUP!NG OF YARD SUMP PUMPS 0 STANDARDlZATION OF ALARM RESPONSE CONTROLS
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 47 0F 56 REVISION 0
- 1) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTION OF SCHEDULED FOR IMPLEMENTATION IN THE 1986 VBD-J REFUELING OUTAGE ENHANCEMENTS TP-37 1.D-5 PAtlEL VBD-J, (REFER TO THE 1/2 SCALE COLOR DRAWINGS Ifl THE CLASSROOM)
A. ENHANCEMENTS 0 FUNCTIONAL DEMARCATION AND LABELING OF SUPPRESS 10ft POOL DISPLAYS, TORUS AIR SPACE CONTROLS / DISPLAYS, D00R AIR <3 \- LOCK STATUS, AND THE VACUUM RELIEF VALVE C0f4TROLS 0 RELABELING OF PANEL COMPONENTS Af4D VARIOUS SUBGROUPS If1 A HIERARCHICAL SCHEME O FUNCTIONAL DEMARCATION OF THE VACUUM RELIEF VALVE MASTER C0flTROLLER SWITCH BY RED Lit!ES OF DEMARCATION RESERVED FOR CRITICAL C0flTROLS 0 SCALE BAflDING OF CHART RECORDERS AND MARKiflG EflTRY TO EMERGENCIES 0 FUNCTIONAL DEMARCATION OF ANNUNCIATOR C0flTROLS IN A MANNER SIMILAR TO OTHER (~) L ,! A N fl u fl C I A T O R C 0 fl T R O L S
JNEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE.48 0F 56 . REVISION 0 m
.l) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-5 PANEL VBD-J, (REFER TO THE 1/2 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) 7 MODIFICATIONS
> TP-38 B. MODIFICATIONS
- 1 L 0 RELOCATION OF TORUS i 2 '
TEMPERATURE AND. PRESSURE g RECORDERS PC-TR-21, PC-PR-20 AND PC-TR-23 s 0 INCORPORATION OF A NEW SUPPRESSION POOL TEMPERATURE , RECORDER PC-TR-25 (COMPONENT-
- 40) TO SEPARATE DIV I AND DIV l 11 TEMPERATURE SENSORS O PROVISION OF DUAL IL'S (OPEN/ CLOSED) FOR:
i ! w - DW AIR LOCK D'00R STATUS l l - l - RR AIR LOCK OUTER DOOR
, STATUS
- RR AIR LOCK INNER DOOR STATUS O
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 49 0F 56 REVISION 0 ($) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D PANEL ENHANCEMENTS AND MODIFICATIONS DESCRIPTION OF SCHEDULED FOR IMPLEMENTATION IN THE 1986 VBD-R REFUELING OUTAGE ENHANCEMENTS TP-39 1.D-6 PANEL VBD-R, (REFER TO THE 1/4 SCALE COLOR DRAWINGS IN THE CLASSROOM) A. ENHANCEMENTS 0 FUNCTIONAL DEMARCATION OF REACTOR BUILDING, CONTROL BUILDING AND TURBINE BUILDING VENTILATION SYSTEM 0 SUBGROUPING OF SUPPLY AIR, EXHAUST AIR, AND MG
-)> VENTILATION COMPONENTS IN THE REACTOR BUILDING SUBSECTION OF THE PANEL AND DEVELOPMENT OF MIMICS THAT CONNECT RELATED COMPONENTS 0 SUBGROUPING OF THE CONTROL ROOM AND COMPUTER ROOM FANS IN THE CONTROL BUILDING SUBSECTION OF THE PANEL 0 LABELING OF THE CONTROLS AND DISPLAYS SUBGROUPINGS WITHIN THE TURBINE BUILDING, CONTROL BUILDING AND THE RX BUILDING 0 SCALE BANDING OF METERS AND MARKING ENTRY TO EMERGENCIES 0 FUNCTIONAL DEMARCATION OF ANNUNCIATOR CONTROLS
{} l
NEBRASKA PUBLic POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 50 0F 56 REVISION 0 ($)- INSTRUCTOR GUIDE LESSON MATERIALS - ITEM #1 1.D-6 PANEL VBD-R, (REFER TO THE 1/4 SCALE DESCRIPTION OF C_QLOR DRAWINGS IN THE CLASSROOM) VBD-R (CONTINUED) ENHANCEMENTS TP-39 A. ENHANCEMENTS (CONTINUED) O MATRIX IDENTIFICATION OF ANNUNCIATORS THROUGH LABELING < OF THE AXES FOR ANNUNCIATOR BOXES R-1 AND R-2 0 CONTROL CODING OF FANS BY YELLOW BANDS OR COLLARS O l
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 51 0F 56 REVISION 0
's - INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-6 PANEL VBD-R, (REFER TO THE 1/4 SCALE DESCRIPTION OF COLOR DRAWINGS Ifl THE CLASSROOM)
VBD-R (CONT! FLUED) MODIFICATIONS TP-40 B. MODIFICATIONS 0 RELOCATION OF SUPPLY AIR, EXHAUST AIR, MG VENTILATION C0f1TROLS, AND FILTER EXHAUST B0OSTER FANS Ill THE REACTOR BLDG SUBSECTION OF THE PANEL
. (SEE VBD-R DRAWING Irl THE CLASSROOM Af1D TABLE 25 FOR LIST OF AFFECTED COMPONENTS Off (S
VBD-R IN STUDENT HANDOUT)
O RELOCATION OF CONTROL ROOM AND l COMPUTER ROOM FAff CONTROLS Ill l THE C0flTROL BLDG SUBSECTION OF THE PANEL (SSEE TABLE 23 FOR LIST OF AFFECTED COMPONEf!TS) 0 RELOCATION OF BATTERY FANS, RECIRC FANS AND MAIN SUPPLY FAN CONTROLS IN THE CONTROL BLDG SUBSECTION OF THE PAf1EL I ,. l
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0aSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 52 0F 56 REVISION 0 () INSTRUCTOR GUIDE LESSON MATERIALS ITEM #1 1.D-6 PANEL VBD-R, (REFER TO THE 1/4 SCALE DESCRIPTION OF COLOR DRAWINGS IN THE CLASSROOM) VBD-R (CONTINUED) 4 MODIFICATIONS IP-40 B. MODIFICATIONS (CONTINUED) O LOWERING THE POSITIONS OF DIFFERENTIAL PRESSURE CONTROLLERS AND RECORDERS ON THE PANEL TO MEET NUREG-0700 ANTHROP 0 METRIC LIMITS. O MOVEMENT dF Rx BLDG DIFFER-ENTIAL PRESS. CONTROLLER HV-DPIC-835B'FROM CONTROL BLDG 3'
' SUBSECTION OF THE PANEL TO Rx BUILDING SUBSECTION OF THE PANEL 0 RELOCATION OF PRIMARY CONTAINMENT VENTING VALVE CONTROL IN THE Rx BUILDING SUBSECTION OF THE PANEL 0 REMOVAL OF FILTER DRIVE SWITCHES THAT ARE NOT OPERABLE FROM THE CONTROL ROOM.
O
NEBRASKA PUBLIC POWER DISTRICT R0P&SRO&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 53 0F 56 REVISION 0
' ( .) INSTRUCTOR GUIDE LESSON MATERIALS ITEM #2 2. REFERENCE MATERIAL GO-0VER THE (INCLUDED IN PARTICIPANTS HANDOUT)
PARTICIPANTS HANDOUT FOR EACH OF THE SIX PANELS SCHEDULED FOR TP-41 UPGRADE IN THE 1986 REFUELING OUTAGE, THE REFERENCE MATERIAL INCLUDES: . DESCRIPTI0fl 0F PANEL ENHANCEMENTS AtlD MODIFICATIONS UPGRADED PANEL DRAWINGS SHOWING POSITIONS OF ADDED OR RELOCATED COMPONENTS
,()
LIST OF AFFECTED COMPONENTS ON THE PANEL, IDENTIFYING THE TYPE OF CHANGE LIST OF
SUMMARY
LABELS & HED LABEL CHANGES THIS MATERIAL IS TO BE USED BY THE PARTICIPANTS IN ACQUAINT!flG THEliSELVES WITH THE CHANGES ON THE PANEL, AND IN COMPLETING
- THE CHECKLISTS INCLUDED IN THE HANDOUT.
I
. . . = -_- . _ _ ., _ ,. . , , . - _ - . - - - - - - - - - - . _ - - - - - - . - - - - . - - - . , _ _ - - _
NEBRASKA PUBLIC POWER DISTRICT R0P8SROSSTA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 54 0F 56 REVISION 0 g v INSTRUCTOR GUIDE LESSON MATERIALS ITEM #3 3. CHECKLIST GO-OvER THE (INCLUDED IN PARTICIPANTS HANDOUT) CHECKLIST TP-42 3.1 PURPOSE . TO ASSIST THE PARTICIPANT IN SYSTEMATICALLY RECOGNIZING ALL THE CHANGES ON THE PANELS. 3.2 CHECKLIST ITEMS (REFER TO FIG ll) k) - PANEL ENHANCEMENTS: MIMICS, FUNCTIONAL DEMARCATION, RELABELING, CONTROL CODING AND METER BANDING PANEL MODIFICATIONS: RELOCATED COMPONENTS, ADDED AND REMOVED COMPONENTS LIST OF RELATED SYSTEMS' PROCEDURES ASSOCIATED WITH THE PANEL CHANGES O
NEBRASKA PUBLIC POWER DISTRICT R0P&SR0&STA-DCR-DR-001 COOPER NUCLEAR STATION PAGE 55 0F 56 REVISION 0 (_/ INSTRUCTOR GUIDE LESSON MATERIALS ITEM #3 3.3 PROCEDURE FOR COMPLETING THE CHECKLIST GO-0VER THE CHECKLIST - GO TO EACH OF THE PANELS. OBSERVE TP-42 NEW PANEL LAYOUT, NEW POSITIONS OF RELOCATED CONTROLS AND ADDED COMPONENTS. DOCUMENT.YOUR OBSERVATIONS AND COMMENTS. OBTAIN COPIES OF THE REFERENCED SYSTEMS' PROCEDURES. WALK-THROUGH OPERATOR STEPS THAT RELATE TO PANEL CHANGES. DOCUMENT AND INCLUDE COMMENTS. HAND IN THE COMPLETED CHECKLIST TO THE SHIFT SUPERVISOR. e O
avr a s. ~ a Tn - . n w ;. ... NEBRASKA PUBLI'C' POWER UI'STRICf COOPER NUCLEAR STATION PAGE 56 0F 56 REVISION 0 LESSON MATERIALS () INSTRUCTOR GUIDE OBJ. FIG.11 PANEL WALK-THROUGH CHECKLIST IN THE CONTROL ROOM (VBD-S) COMPLETION 0F CHECKLIST TP-43 ITEM OBSERVED COMMENTS
- 1. PANEL ENHANCEMENTS MIMICS, FUNCTIONAL .
DEMARCATIONS, CONTROL CODING, METER BANDING, AND RELABELING __
- 2. PANEL MODIFICATION i LIST OF RELOCATED COMPONENTS OR ADDED
(]) COMPONENTS (TABLE 19 0F HANDOUT) ___ ' COMPLETED COMMENTS ITEM
- 3. WALK-THROUGH RELATED SYSTEMS PROCEDURE
-EOUIPMENT, FLOOR AND CHEMICAL DRAIN SYSTEM, S0P REF 2.2.27 __
- () COMPLETED BY
DATE
_ _ _ _ _ _ _ . _ . _ _ _ _ . . - ..m. _ . __ _ . . _ . Nebraska Public Power District- R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 1 of 119 Revision 0 O ATTACHMENT E E.2 PARTICIPANT HANDOUT H0-1 PROGRAM: Reactor Operator, Senior Reactor Operator and Shift Technical Advisor . SYSTEM / DUTY AREA: Control Room i TASK /SU3 JECT: DCRDR, Human Factors Engineering and Control Room Panel Changes i i e O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 2 of 119 Revision 0 NOTES- TRAINING MATERIAL { PROGRAM: Reactor Operator, Senior Reactor Operator and Shift Technical Advisor SYSTEM DUTY AREA: Control Room TASK /
SUBJECT:
DCRDR, Human Factors Engineering and Control Room Panel Change REFERENCES
- 1. Requirements For Emergenev Response Capability, NUREG-0737, Supplement 1, December 17,.1982
- 2. Guidelines for Control Room Design Reviews, NUREG-0700, September 1981
- 3. CNS Control Room Human Factors Engineering Standards and Implementation Guidelines, General Electric Company, MDE-142-0685, August 1984
- 4. CNS Detailed Control Room Design Review Summary Report, February 1985.
(~h
\m) 5. CNS Detailed Control Room Design Review Supplement to the Summary Report, February 1986 OBJECTIVE This material is to be used by the participant in acquainting i himself with the changes on the panels, and in completing the checklists for Panels 9-3, 9-4 and 9-5, and VBD-S, J and R, included in this handout, t
a
Nebraske Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 3 of 119 Revision 0 (~). ( NOTES TRAINING MATERIAL CONTENTS ITEM PAGE
- 1. REFERENCE MATERIAL 6 A. PANEL 9-3 7 A.1 Description of Enhancements 8 and Modifications A.2 Upgraded Panel Drawing 11 A.3 List of Affected Components 14 A.4 Label Changes -
25 B. PANEL 9-4 37 B.1 Description of Enhancements 38 and Modifications
.B.2 Upgraded Panel Drawing 42
'B.3 List of Affected Components 45 B.4 Label Changes 49 C. -PANEL 9-5 58
("% k- C.1 Description of Enhancements 59 and Modifications C.2 Upgraded Panel Drawing 62 C.2 List of Affected Components 65 C.4 Label Changes 71 D. VBD-S 78 D.1 Description of Enhancements 79 and Modifications D.2 Upgraded Panel Drawing 82 D3 List of Affected Components 83 D.4 Label Changes 85 E. VBD-J 88 E.1 Description of Enhancements 89 and Modifications E.2 Upgraded Panel Drawing 91 E.3 List of Affected Components 92 E.4 Label Changes 94
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 4 of 119 Revision 0 NOTES TRAINING MATERIAL CONTENTS (continued) L ITEM PAGE F. VBD-R 96 F.! Description of Enhancements 97 and Modifications F.2 Upgraded Panel Drawing 101 F.3 List of Affected Components 102 F.4 Label Changes 107
- 2. CHECKLIST 112 2.1 Description 112 2.2 Checklist Sheets 114 :
i A. PANEL 9-3 114 !' B. PANEL 9-4 115 i C. PANEL 9-5 116 D. VBD-S 117 E. VBD-J 118 [ F. VBD-R 119 O 4 I l O
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Coopor Nuclear Stetion Paga 5 of 119 Revision 0 () NOTES TRAINING MATERIAL DCRDR Acronyms BWROC Boiling Water Reactor Owners Group CRS Control Room Survey CRDR Control Room Design Review DCRDR Detailed Control Room Design Review ENHANC Enhancements - F&TA Function And Task Analysis l HED Human Engineering Discrepancy HE0 Human Engineering Observation HF Human Factors HFE Human Factors Engineering (- LER License Event Report MOD Modifications V&V Verification And Validation 4 J l i C) l 1
.= . ._ . = . ._ . _ - _ - - - -. -
Nebraska Public Power District ROP &SRO&STA-DCR-DE-00-1 Cooper Nuclear Station Page 6 of 119 Revision 0 (} NOTES TRAINING MATERIAL
- 1. REFERENCE MATERIAL For each of the six panels scheduled for upgrade in the 1986 refueling outage, the reference material includes:
4 Description of Panel. Enhancements and i Modifications Upgraded Panel Drawings Showing Positions of Added or Relocated Components List of Affected Components on the Panel, Identifying the Type of Change List of Summary Labels & HED Label Changes 4, f
- - - . . . ,n. - _ ,,-.-,n. - . - , , - - -, , . . , - - , _ , , . . . _ . - . _ , - - - - , - - - - - , . - - - - - - - .
---.e -
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 7 of 119 Revision 0 NOTES TRAINING MATERIAL A. PANEL 9-3 . O e r lO
Nobraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 8 of 119 Revision 0 p)s (. . NOTES TRAINING MATERIAL PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE Panel 9-3
- a. Enhancements o Mimic arrangements showing flow paths for RHR, CS, and HPCI with distinctive color coding identifying various modes of system operation o Functional demarcation and
. labeling of various displays'/
- controls' subgroupings:
- PC, NBI, SW, A0G STM SUPPLY, on 9-3L (left section of the panel)
- HPCI PUMP, HPCI TURBINE, A0G STM SUPPLY, on 9-3C (center section of the panel)
- PC, NBI, SW, RHR STM LINES, A0G STM LINES, MN STM ISOL VALVES, on 9-3R (right section of the panel) o Identification of alarm tiles of annunciator matrices, 9-3-1, 9-3-2, 9-3-3, and 9-3-4
'I O
Nebraska Public Power District ROP &SROSSTA-DCR-DR-00-1 Cooper Nuclear Station Page 9 of 119 Revision 0 (~'t NOTES TRAINING MATERIAL s/
- a. Enhancements (continued) o Clarification of ambiguous labels, (Refer to Pnl 9-3 Label Change Document) o Scale banding of meters and chart recorders, and marking entry to emergencies o Distinction of pump and valve switches through control coding of pumps by yellow bands
- RHR A&B Pumps CS A&B Pumps HPCI Gland Seal Cndsr Blower and Condensate Pump and Auxiliary 011 Pump j
4 O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 10 of 119 Revision 0 O TRAINING MATERIAL i_) s NOTES
- b. Modifications o Relocation of RHR, CS and HPCI controls noted on Panel 9-3 drawings in the classroom.
See Table 1, List of relocated components on 9-3L (Student Handout)
- See Table 2, List of relocated components on 9-3C (Student Handout)
- Table 3, List of relocated components on 9-3R (Student Handout) o Incorporation of RG 1.97 instrumentation " Torus Pressure Recorder" o Standardization of alarm
' response controls l o Removal of reactor head spray j flow controller FIC-142 ( o Removal of reactor head spray valves M0-32 & 33 o Functional separation of primary containment displays from reactor pressure display ( I [
Nobrasko Public Pcwcr District ROP &SRO&STA-DCR-DR-00-1 Cooper Nucloor Station Pago 11 of 119 Revision 0 i-
'O NOTES TRAINING MATERIAL a
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Nobrooke Public Power Diotrict ROP &SRO&STA-DCR-DR-00-1 Cocpor Nuclocr Station Pcgo 12 of 119 Revision 0 7. NOTES TRAINING MATERIAL a _ _n . se -.- _- -- .
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Nobraska Public Power Dietrict R0P&SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Page 14 of 119 Revision 0 (m (_) NOTES TRAINING MATERIAL J l TABLE 1 - AFFECTED COMPONENTS ON PANEL 9-3 (9-3 LEFT) Component # Dwg. Component ID Associated Type of (SKE-EE-115) & Description System Change 35 NBI-PR-2A, NBI o Component Relocated Reactor Pressure on 9-3L 37 PC-LR-1A, Prim PC o Component Relocated Containment Level on 9-3L Recorder O
- FIC-10-142, RHR RHR-B o Component Removed Head Spray Flow Controller 81 Drywell Spray RHR-A o Component Relocated Outboard Throttle on 9-3L Valve 26A o Label Changed 84 Torus Spray RHR-A o Component Relocated Throttle Valve on 9-3L 39A o Label Changed 90 Containment Spray RHR-A o Component Relocated
, Valve Control on 9-3L
*Not Showr. on Revised D,rawings for Panel 9-3 Left
.. . . - . _ _ - _ _ - - = . . _ . ~ . _ = - _ _ . - __. _
Nobrosko Public Powar District ROP &SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Page 15 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 1 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 LEFT) , Component # Dwg. Component ID Associated Type of (SKE-EE-115) & Description System Change 91 Heat Exchanger A RHR-A o Component Relocated Drain Valve 36A on 9-3L i 92 Drywell Spray Valve RHR-A o Component Relocated 31A Control on 9-3L 4 o Label Changed l() 93 Press. Reducing RHR-A o Component Relocated i Valve 69A & 70A on 9-3L Control 4 94 Loop A Minimum Flow RHR-A o Component Relocated Bypass Valve 16A on 9'-3L Control i 96 Inboard Injection RHR-A o Component Relocated Valve 25A Control on 9-3L 97 Suppression Pool RHR-A o Component Relocated Cooling Valve 34A on 9-3L j Control o Label Changed i O
Nobrooks Public Power District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuclear Stetion Pogo 16 of 119 Revision 0 r () NOTES TRAINING MATERIAL TABLE 1 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 LEFT) [ Component # Dwg. Component ID Associated Type of (SKE-EE-115) & Description System Change 99 Heat Exchanger A RHR-A o Component Relocated 2 Drain Valve 21A on 9-3L Control 100 Heat Exchanger A RHR-A o Component Relocated Vent Valve 166A on 9-3L Control
- Mode Selector RHR-A & o Component Removed Switch for Pressure B from 9-3L and Relocated Ind. Controller to RHR-B on 9-3R 105 Torus Spray Valve RHR-A o Component Relocated I 38A Control on 9-3L o Label Changed 1
l l 108 Outboard Injection RHR-A o Component Relocated
- Valve 27A Control on 9-3L I
- 131,121,122, Bypass 15A Test CS-A o Components Relocated i 125,126,127, Check 13A Control on 9-3L j
129,130 & Associated IL's l i
- q 'Not Shown on Revised D'r awing for Panel 9-3 Left l %d
. . . . - _ , , , , - _ _ _ - _ - _ _ _ , _ , . _ _ , . _ _ _ , - _ _ . _ _ _ _ , ___.------_.r,, . _ - . _ . - . . , , _ _ _ - - _ _ _ , _ , - - _ . _ _ . . . , . _ _ . - .
Nobrcska Public Powar District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuclear Station Pega 17 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 1 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 LEFT) Component # Dwg. Component ID Associated Type of (SKE-EE-115) & Description System Change 132 Pump A Control CS-A o Component Relocated ., on 9-3L 1 133 Suction Valve 7A CS-A o Component Relocated Keylock on 9-3L l 134,135 Inboard Injection CS-A o Component Relocated Throttle Valve 12A on 9-3L Control & Signal
~
Sealed-In Indicator Lamp i 136 Outboard Injection CS-A o_ Component Relocated Valve 11A Control on 9-3L 137 Minimum Flow Bypass CS-A o Component Relocated Valve SA Control on 9-3L 138 Test Bypass Valve CS-A o Component Relocated 26A Control on 9-3L I O
3 Nobrosko Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Pego 18 of 119 Revioion 0 _ () NOTES TRAINING MATERIAL TABLE 1 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 LEFT) Component # Dwg. Component ID Associated Type of (SKE-EE-115) & Description System Change 123 Stop Signal CS-A o Component Relocated Sealed-In 14A on 9-3L Status Lights 155 SW Booster SW o Component Moved To Pump-A Control 9-3L From VBD-M i 156 SW Booster SW o Component Moved To Pump-C Control 9-3L From VBD-M 171 SWBP-A Amp. SW o Component Moved To ! Indication 9-3L From VBD-M l 172 SWBP-C Amp. SW o Component Moved To l Indication 9-3L.Fr'om VBD-M l 173 Torus Wide Range PC o New Component Added Press. Recorder to 9-3L I i O _w - , . - , _ -- - - - , , - - . - , - -
Nobrcska Public Power District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuclear Station Page 19 of 119 Revision 0 (} NOTES TRAINING MATERIAL TABLE 2 - AFFECTED COMPONENTS ON PANEL 9-3 (9-3 CENTER) Component # Dwg. Component ID Associated Type of (SKE-EE-117) & Description System Change 5 PI-112, HPCI HPCI o Component Relocated Turbine Exhaust on 9-3C Pressure 7 PI-109, HPCI Pump HPCI o Component Relocated Discharge Pressure on 9-3C O 9 PI-111, HPCI HPCI o Component Relocated Turbine Steam on 9-3C Pressure 70,71,72 Annunciator Annunciator o Components Relocated Acknowledge Response on 9-3C Reset, and Test i O
Nobrcoko Public Power District , R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 20 of 119 3 Revision 0 NOTES , TRAINING MATERIAL
, Y TABLE 3 - AFFECTED COMPONENTS ON PANEL 9-3 (9-3 RIGHT) s Component #.
pwg. Component ID
's
' Associated Type of (SKE-EE-119) & Description -
System Change 53 Drywell Spray RHR-B o Component Relocated joutboard Throttle on 9-3R Valve 26B ' o Label Changed 61 Torus Spray RHR-B o Component Relocated Throttle Valve on 9-3R 39B o Label Changed O 69 Containment Spray RHR-B o Component Relocated Valve Control on 9-3R 70 Heat Exchanger B RHR-B o Component Relocated Drain Valve 36B on 9'-3R 71 Drywell Spray Valve RHR-B o Component Relocated s 31B Control on 9-3R l o Label Changed 72 ' Iress. Reducing ) RHR-B o Component Relocated Valve 69B & 70B on 9-3R i Contro,1 1 i ( O
~ ' '
R0P&SR06STA-DCR-DR-002 1'
~
4 Nebraska Public Power District Cooper-Nuclecr Station Page 21 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 3 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 RIGHT) Component # Dwg. Component ID Associated Type of (SKE-EE-119) & Description System Change i 75 Loop B Minimum Flow RHR-B o Cobponent Relocated Bypass Valve 16B on 9-3R Control 76 Inboard Injection RHR-B o Component Relocated Valve 25B Control on 9-3R j 77 Suppression Pool RHR-B o Component Relocated l Cooling Valve 34B on 9-3R 1 l Control o Label Changed l 79 Heat Exchanger B RHR-B o Component Relocated Drain Valve 21B on 9-3R Control 80 Heat Exchanger B RHR-B o Component Relocated Vent Valve 166B on 9-3R Control 179 Mode Selector RHR-A & o Component Moved Switch for Pressure B to RHR-B From Ind. Controller RHR-A 1 m - , . - _ , . , , . -
Nabroska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 22 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 3 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 RIGHT) Component # Dwg. Component ID Associated Type of (SKE-EE-119) & Description System Change 84 Torus Spray Valve RHR-B o Component Relocated
~
38B Control on 9-3R o Label Changed 87 Outboard Injection RHR-B o Component Relocated Valve 27B Control on 9-3R 103,93,94, Bypass 15B Test CS-B o Componerts Relocated check 13B Control on 9-3R {}97,99,100, 101,102 & Associated IL's 104 Pump B Control CS-B o Component Relocated on 9-3R 105 Suction Valve 7B CS-B o Component Relocated Keylock on 9-3R 107,106 Inboard Injection CS-B o Component Relocated l Throttle Valve 12B on 9-3R Control & Signal Sealed-In Indicator Lamp 108 Outboard Injection CS-P o Component Relocated Valve llB Control on 9-3R O
Nabrcoka Public Powar District R0P&SRO&STA-DCR-DR-00-1 Coopsr Nucisar Station Pego 23 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 3 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 RIGHT) Component # Dwg. Component ID Associated Type of (SKE-EE-119) & Description System Change 109 Minimum Flow Bypass CS-B o Cosponent Relocated Valve SB Control on 9-3R 110 Test Bypass Valve CS-B o Component Relocated 26B Control on 9-3R 95 Stop Signal CS-B o Component Relocated Sealed-In 14B on 9-3R (J~h Status Lights 89 PI-483, Core Spray CS-B o Component Relocated Pump Pressure on 9-3R 91 FI-50B, Core Spray CS-B o Component Relocated Pump Flow on 9-3R 147 SW Booster SW o Component Moved To Pump-B Control 9-3R From VBD-M 146 SW Booster SW o Component Moved To Pump-D Control 9-3R From VBD-M I O
' ~~~ ~
^
Nebraska'Public Power District
~
R0P&SRO&@2A'@s@-@s-@6-A Cooper Nuclear Station Page 24 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 3 - AFFECTED COMPONENTS ON PANEL 9-3 (continued) (9-3 RIGHT) Component # Dwg. Component ID Associated Type of (SKE-EE-119) & Description System Change 160 SWBP-B Amp. SW o Component Moved To Indication 9-3R From VBD-M 4 162 SWBP-D Amp. SW o Component Moved To Indication 9-3R From VBD-M
- MO 32&33 RHR o Components Removed l
Head Spray
- Valves
*Not Shown on Revised Drawing for Panel 9-3 Right i
I l l l
+ - - - - -
,------,--,yr.-- y.._ , _ _ , _ _ _ _ , _ _ _, _ __
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 25 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 4-DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3L Related Associated Component System Label Contents I 22 Alarm Box 9-3-4 23 Alarm Box 9-3-1 , 1 ADS ADS Alarm Tile Alarm Boxes 1,2,3------ ,9 ID (Vertical Numerals Alarm Tile Alarm Boxes -1,-2,-3,-4 ID (Horizon Numerals 24 RHR RHR-A 110 CS CS-A O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 26 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 4-DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3L (continued) Related Associated Component System Label Contents 158 NBI NBI I ! 159 PC PC i 160 NBI " NBI i 161 SW SW i ! 166 NBI NBI 111 PC PC 114 NBI NBI r 163 A0G ' A0G Steam Supply 8 157 SRV/ ADS Low-Low Set i 145 RHR-A TO RHR SYS I
Nobracks Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 27 of 119 Revision 0 NOTES TRAINING MATERIAL 8 TABLE 4 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3L (continued) Related Associated Component System Label Contents 144 RHR-A FM SDC VLV 17 153 RHR-A FM TORUS 154 RHR-A FM TORUS 164 RHR-A/SW FM SW PUMPS 165 RHR-A/SW FM SW PUMPS 73 RHR-A FM SW PUMPS 128 RHR-A TO TORUS 148 RHR-A TORUS $ PRAY 147 RHR-A TO TORUS 176 RHR-A TO RX O
Nebraska Public Powor District R0P&SRO&STA-DCR-DR-00-1 L Coopor Nuclear Station Page 28 of 119 Revision 0 () NOTES TRAINING MATERIAL l TABLE 4 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3L (continued) Related Associated Component System Label Contents 150 CS-A FM TORUS 151 CS-A TO TORUS ! 152 CS-A TO TORUS
- - 149 CS-A TO RX l 81 RHR-A DW Spray Outbd
, Throttle Valve 26A ! 84 RHR-A Supp Pool Cooling / Torus Spray Outbd Valve 39A ( I i 90 RHR-A Contmt Cooling 2/3 Core Valve Control Permissive I 82 RHR-A Contmt Cooling Valve l Control Permissive O 9
' - - - - - , - - . -.s ,,yp_.,_ . . - y , , , . _ . , , , _ . - - , - . , . , _ . , , , - _ , - . - - _ , , - , _ - _ _ . . _ . ,.,_m m_,, , _ , , , , .-,,.-,.r. .. ,.. ,...-.y,,
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 29 of 119 Revision 0 () NOTES TRAINING MATERIAL 4 TABLE 4 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes I Panel 9-3L (continued) I Related Associated , Component System Label Contents 97 RHR-A Supp Pool Cooling Inbd Throttle Valve 34A ! 92 RHR-A DW Spray Inbd Valves 31A O 105 RHR-A Torus Spray Inbd i Throttle Valve 38A i 177 RHR-A N/A l (RHR-HX Symbol) t I i s l l
.. ~ _ _ _ . _ _ _ _ . , . _ _ . . . _ . . _ _ _ _ _ - _ . . . . _ , _ , . _ . , _ _ , _ _ . _ _ _ _ . _ _ . _ , , . _ _ _ , . _ _ . . _ . . _ _ _ _ _ _ . . _ _ . , _ _ . _ . . .
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nucloer Station Pago 30 of 119 Revision 0 TRAINING MATERIAL () NOTES Table 5- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3C Related Associated Component System Label Contents l l 1 Alarm Box 9-3-2 , Alarm Tile Alarm Box 1,2,3 ------ ,9 ID (Vertical Numerals) Alarm Tile Alarm Box -1,-2,-3.-4 ID (Horizon Numerals) i 1 ! 2 HPCI HPCI l l l 77 8 HPCI HPCI Pump 78 HPCI HPCI Turbine 88 A0G A0G Stm Supply 0
Nobraska Public Power District ROP &SRO&STA-DCR-DR-00-1 l Cooper Nuclear Station Page 31 of 119 l Revision 0 i NOTES TRAINING MATERIAL t TABLE 5 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3C (continued) Related Associated Component System Label Contents 79 HPCI FM ECST 80 HPCI TO ECST 1 81 HPCI TO TORUS 83 HPCI TO RX 84 HPCI FM RX 86 HPCI FM TORUS 1 I l
- o
Nebraska Public Power Dietrict R0P&SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Page 32 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 6 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3R Related Associated Component System Label Contents 1 Alarm Box 9-3-3 2 RHR RHR-B Alarm Tile Alarm Box 1,2,3,------ ,9 ID (Vertical Numerals) Alarm Tile Alarm Box -1,-2,-3,-4 ID (Horizon Numerals) t 168 NBI NBI 3 PC PC 177 SW SW f O I I
Nobraska Public Powor-District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuclear Station Page 33 of 119 Revision 0 I
) NOTES TRAINING MATERIAL 4
TABLE 6- DCRDR HED CORRECTIONS ! Summary Labels & HED Label Changes Panel 9-3R (continued) Related Associated Component System Label Contents 169 NBI NBI 178 RHR-B TO RX 4 J 155 RHR-B TO RHR SYS () 159 RHR-B FM SDC VLV 17
- 157 RHR-B FM TORUS 158 RHR-B FM TORUS i
- 153 RHR-B FM SW PUMPS 154 RHR-B FM SW PUMPS 151 RHR-B FM RHR PUMPS l
l l 145 RHR-B TO TORUS l O
Nobrooka Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 34 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 6 - DCRDR HED CORRECTIONS j Summary Labels & HED Label Changes Panel 9-3R (continued) Related Associated Component System Label Centents 180 RHR-B TORUS SPRAY 4 181 RHR-B DW SPRAY 148 RER-B TO VLVS 15A&l5C i () 149 RHR-B TO VLVS 15B&l5D 150 RHR-B RM RX I l 182 RHR-B N/A (RHR-HX Symbol) 164 CS-B TO RX 165 CS-B TO TORUS 166 CS-B TO TORUS
Nobrcska Public Power District ROP &SRO&STA-DCR-DR-00-1. Cooper Nucloor Station Page 35 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 6- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3R (continued) Related Associated Component System Label Contents I 167 CS-B FM TORUS 88 CS-B CS-B 53 RHR-B DV Spray Outbd Throttle Valve 26B
- 61 RHR-B Supp Pool Cooling / -
Torus Spray Outbd Valve 39B 69 RHR-B Cntmt Cooling Valve Control Permissive 54 RHR-B Cntmt Cooling 2/3 Core Valve Control Permissive i 77 RHR-B Supp Pool Cooling Inbd Throttle Valve 34B i d? y-s-w.s,- m%-- 3- w_m_.9_mp,.,se_m. ._ ,-we--mwt"N -a we wTT 'em* *wm'h*--O-M'----Wrw-f'N*F=--'W-" *"'r-- *w-9 me-vNe-- -N-'F****=U= '7'~--
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 36 of 119 Revision 0 () NOTES TRAINING MATERIAL TABLE 6- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-3R (continued) Related Associated Component System Label Contents 71 RHR-B DW Spray Inbd Valve 31B 84 RHR-B Torus Spray Inbd Throttle Valve 38B 111 MS MS 170 RHR RHR Stm Lines i O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1
< Cooper Nuclear Station Page 37 of 119 ! Revision 0 NOTES TRAINING MATERIAL 4
i e l r i i i ' B. PANEL 9-4 4 i i k f 4 i l i l l s O
Nobrcoko Public Powcr District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuclear Station Pago 38 of 119 Revision 0 l () NOTES TRAINING MATERIAL PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE i Panel 9-4 J
- a. Enhancements -
o Mimic arrangements showing flow paths for RCIC and RWCU o Functional demarcation and labeling of various displays' and controls' subgroupings:
- RCIC TURBINE, RCIC PUMP, MN ST LINE DRAINS, RX WTR CLEANUP, FLANGE LEAKOFF on 9-4L
! - RX BLDG SUMP, DW EQUIP DR i SUMP, DW SUMPS, POST ACCIDENT SAMPLING SYSTEM, 4 DEMIN. CONDUCTIVITY, on 9-4C.
- NBI, PC, COMPUTER TREND, l RRMC OIL PUMP-A, RRMC OIL PUMP-B, SCOOPTUBE A&B on 9-4R o Matrix identification of annunciators through labeling of the annunciator axes for 9-4-1, 9-4-2, and 9-4-3 '
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Nobrcsko Public Powor Dictrict ROP &SRO&STA-DCR-DR-00-1 Coopor Nuciocr Station Pogo 39 of 119 Rovision 0 () NOTES TRAINING MATERIAL Panel 9-4
- a. Enhancements (continued) o Scale banding of meters and chart recorders and marking entry to emergancies, o Control coding of pumps by yellow bands or collars.
- RCIC Gland Seal Vacuum and Condensate Pumps on 9-4-L
- DW sump pumps, and RWCU pumps on panel 9-4C
- RRMG A and RRMG B oil pumps on 9-4R l
4 O
Nabraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Coopor Nucicar Station Pago 40 of 119 Revision 0 () NOTES TRAINING MATERIAL Panel 9-4
- b. Modification o Relocation of RCIC and RWCU controls noted on Panel 9-4 drawings in the classroom.
See Table 7. List of affected components on 9-4L (Student Handout)
- See Table 8. List of affected components on 9-4C (Student Handout) o Incorporation of RG 1.97
() instrumentation " Torus Pressure Recorder" on 9-4R o Standardizing the arrangement of alarm response controls, on 9-4C o Functional separation of HPCI turbine and HPCI pump displays on 9-4L o Functional separation of primary containment displays from reactor pressure display on 9-4R O
._ -. .. . . _ - _ __- __. - _ _ - -- - .. . _. .. - - - _ -~
3 Nebrocka Public Power District R0P&SRO&STA-DCR-DR-00-1 3 Cooper Nuclear Station Page 41 of 119 i Revision 0 NOTES TRAINING MATERIAL Panel 9-4
- b. Modification (continued)
- o Swapping the locations of computer trend recorder and suction feedwater temperature recorder on 9-4L (See Table 9 Student Handout) 1 4
4 O - 1 i e i 1 i 4 1 i O l
Nobrcoko Public Pcwor District R0P&SRO&STA-DCR-DR-00-1 Coop 3r Nucloor Station Pogo 42 of 119 Rovision 0 NOTES TRAINING MATERIAL (v)
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Nobrocko Public Pocor District ROP &SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Pogo 43 of 119 Rovision 0 NOTES TRAINING MATERIAL
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Nobrcsko Pchlic Pecor Dictrict ROP &SRO&STA-DCR-DR-00-1 Ccapar Nucicor Station Pogo 44 of 119 Rovision 0 A NOTES TRAINING MATERIAL U
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Nebraska Public Powar District ROP &SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Pego 45 of 119 Revision 0 (( ) NOTES TRAINING MATERIAL TABLE 7 - AFFECTED COMPONENTS ON PANEL 9-4 (9-4 LEFT) Component # Dvg. Component ID Associated Type of (SKE-EE-168) & Description System . Change 55 Pump Sunction From RCIC o Component Torus 41 Control Relocated on 9-4L 48 Min Flow Byp. Viv RCIC o Component 27 Control Relocated on 9-4L o Label Changed 57 Turbine Cooling Wtr RCIC o Component Supply 132 Control Relocated on 9-4L 4 Pump Disch Press. RCIC o Component Indicator Relocated on 9-4L 6 Turbine Sem Press. RCIC o Component Indicator Relocated on 9-4L 8 Turbine Exhaust RCIC o Component Press. Indicator Relocated on 9-4L 10 Pump Suction Press. RCIC o Component Indicator Relocated on 9-4L O
_ . _ = - - _ _ . __ Nobrcoka Public Powar District ROP &SRO&STA-DCR-DR-00-1 Coopor Nuc102r Station Pcge 46 of 119 Revision 0 f' i \ NOTES TRAINING MATERIAL TABLE 8 - AFFECTED COMPONENTS ON PANEL 9-4 i (9-4 CENTER) Camponent # Dwg. Component ID Associated Type of (SKE-EE-169) & Description System Change 59 Blowdown Orifice RWCU o Component Bypass 53 Control Relocated on 9-4 60 Recire Pump A RWCU o Component Control Relocated on 9-4 4 p 61 Drain to RW Coll. RWCU o Component j d Tank 57 Control Relocated on 9-4 62 Recire Pump B RWCU o Component Control Relocated on 9-4 i 63 Blowdown to Main RWCU o Component , Condenser 56 Control Relocated on 9-4 i 4 64 Return Line to RWCU o Component j Reactor 68 Control Relocated on 9-4 i 65 Demin Suction Bypass RWCU o Component 74 Control Relocated on 9-4 iO 1 l l
. _ . _ . . - - . . - . . _ . _ _ - - _ . _. -- .-= _
Nobroska Public Power Diotrict ROP &SRO&STA-DCR-DR-00-1 Coopor Nucloor Station Page 47 of 119 Revision 0 4 () NOTES TRAINING MATERIAL TABLE 8 - AFFECTED COMPONENTS ON PANEL 9-4 (9-4 CENTER) Component # Dvg. Component ID Associated Type of (SKE-EE- 16 9) & Description System Change 4 j 66 Radwaste/ Normal RWCU o Component Moved Bypass (Alarm) Switch to 9-4C from 9-4L 33,34,35 Annunciator Annunciator o Component Acknowledge, Response Relocated on 9-3C Reset, and Test O v .l I i J d l l
i Hobraske Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Pego 48 of 119 Revision O' NOTES TRAINING MATERIAL TABLE 9 - AFFECTED COMPONENTS ON PANEL 9-4 (9-4 RIGHT) Component # Dwg. Component ID Associated Tvoe of (SKE-EE-170) & Descriotion System Change 62 NBI-PR-2B, NBI o Component Reactor Pressure Relocated on 9-3 64 PC-LR-1B PC o Component Relocated on 9-3
- 119 Torus /DW Pressure PC o New Component Recorder Added to 9-3R 54 Computer Trend . N/A o Component Recorder Relocated on 9-3 52 Suction A Feedwater Feedwater o Component Temp Recorder Relocated on 9-3 I
I O l e a..-. -- - , - . - - .-
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 i Cooper Nuclear Station Page 49 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 10 - DCRDR.HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4L Related Associated Component System Label Contents 1 Alarm Box 9-4-1 Alarm Tile Alarm Box 1,2,3.------ ,9 ID (Vertical Numerals)
,O l
Alarm Tile Alarm Box -1,-2,-3.-4 ID (Horizon Numerals) 2 RCIC RCIC 64 PC PC 82 RCIC RCIC Pump I 83 RCIC RCIC Turbine l O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 50 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 10 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4L (continued) Related Associated Component System Label Contents 66 MS Main Steam Lines Drains 67 RWCU Reactor Water Cleanup t 68 RX Flange Leakoff 77 RX Vessel Head Vents 87 RCIC FM RX 85 RCIC FM ECST 86 RCIC FM TORUS 84 RCIC TO RX 88 RCIC TO TORUS O
_ _ _ . _ _ m .. _ _ Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 51 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 10 - DCRDR HED CORRECTIONS Summary Labels & HED Lab'el Changes l Panel 9-4L (continued) Related Associated Component System Label Contents 4 89 RCIC TO ECST 90 RWCU TO RWCU PUMPS 91 RWCU FM RX O . 1 I l l0 l 1 1 I
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 52 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 11 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4C Related Associated Component System Label Contents 2 Alarm Box 9-4-2 Alarm Tile Alarm Box 1,2,3,4,----- ,9 ID (Vertical Numerals)
)
Alarm Tile Alarm Box -1,-2.-3 -4 ID (Horizon Numerals) 3 RW RW l l 36 RWCU RWCU 73 RW RX Bldg Sump 1 l- 74 RW Drywell Sump l O
Nebrcska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 53 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 14 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4C (continued) Related Associated Component System Label Contents 75 RWCU Demineralizer Conductivity 41 RWCU CRS-132 RWCU INLET CONDUCTIVITY O 53 RWCU CRS-135 RWCU OUTLET CONDUCTIVITY 10 RW Drywell Sumps 72 RW Sump Pumps 31 RW Post Accident Sampling O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper _ Nuclear Station Page 54 of 119 Revision 0
/v^\ TRAINING MATERIAL NOTES TABLE 11 -
DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4C (continued) Related Associated Component System Label Contents 27 RW Equip Sump Inbd Isol Viv A0-94 28 RW Equip Sump Outbd ' Isol Viv A0-95 29 RW Sump Recirc/Disch Byp Vlv A0-92/93 30 RW Equip Sump Isol Vlv A0-1002 67 RWCU From Inbd/Outbd Isol Valves 69 RWCU To MN Condser i 70 RWCU TO RW 71 RWCU TO RX lO
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 55 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 11 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4C (continued) Related Associated Component System Label Contents 76 RWCU If Either RWCU-M015 (CAUTION or M018 Should Close, TAG) Immediately Open RWCU-M074 Until Pump Seal Purge is Isolated (m d 77 RWCU N/A, Filter Demin Symbol Q l
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 56 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 12 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes o Panel 9-4R Related Associated Component System Label Contents 58 Alarm Box 9-4-3 1 RRMG RRMG-A , 59 RRMG RRMG-B Alarm Tile Alarm Box 1,2,3.----- ,9 ID (Vertical Numerals) Alarm Tile Alarm Box -1,-2,-3 -4 ID (Horizon Numerals) 127 All Computer Trend , 128 PC PC O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 57 of 119 Revision 0 0 NOTES TRAINING MATERIAL TABLE 12 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-4R (continued) Related Associated Component System Label Contents 129 NBI NBI 123 RRMG RRMG-A 011 Pumps 124 RRMG RRMG-B Oil Pumps 125 Scoop Tube Scoop Tube-A 126 Scoop Tube Scoop Tube-B 81 NBI SCALE VESSEL HEIGHTS 0": 516.75" INST ZERO & 165" ABOVE TAF 112": 628" BOTTOM 208": 722.75" VESSEL FLANGE , 400": 194" ABOVE FLANGE OR 66" ABOVE DOME O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 58 of 119 Revision 0 O NOTES TRAINING MATERIAL 4 C. PANEL 9-5 i O i i ) l l \
- O l
l l
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 59 of 119 Revision 0
,9 NOTES TRAINING MATERIAL PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE Panel 9-5
- a. Enhancements -
o Functional demarcation and labeling of various displays and controls' subgroupings:
- SRM MONITORS, NM BYPASS, GROUP ISOLATION INDICATIONS on 9-4L
- IRM/APRM MONITORS, ROD g-(~/ SEQUENCE CONTROL on 9-4C
- SCRAM INDICATIONS, RPV WATER LEVEL, RFW FLOW, RPV PRESS, FW FLOW CONTROLLERS, WATER LEVEL TRIP RESET on 9-4R o Identification of alarm tiles of annunciator matrices on 9-5-1 and 9-5-2
, o Matrix identification of the control rod positions on the full core display o Scale banding of meters and chart recorders, and marking entry to emergencies l
l o Control coding of pumps by yellow bands, for CRD pumps A and B and SLC pump i l 1
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 60 of 119 Revision 0 0 NOTES TRAINING MATERIAL Panel 9-5
- b. Modifications o Relocation of Group 1 indicating lights on 9-SL and addition of Groups 2,3,4,5,6,7 indicating lights on 9-5L (Lights will be installed but not functional in this outage) o Replacement of LPRM meter scales on 9-5C o Relocation of reactor feed and startup flow controllers on O 9-5R (See Table 15 Student Handout) o Relocation of narrow range level indications, on 9-5R o Relocation of selector switches for STM FLOW, RX WTR LVL, and 1 or 3 element, on 9-5R I
O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 61 of 119 Revision 0 O NOTES TRAINING MATERIAL Panel 9-5
- b. Modifications (continued) o Relocation of HIGH WTR LVL/ TRIP LOGIC B and C reset switches, on 9.- 5 R .
t l t 't 1 I l t l l l l
Nobroska Public Pcwor District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclocr Section Page 62 of 119 Revision 0 O V NOTES TRAINING MATERIAL
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Nebrcske Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclect Station Page 64 of 119 Revision 0 NOTES TRAINING MATERIAL
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Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 65 of 119 Revision 0
,rq V NOTES TRAINING MATERIAL TABLE 13 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 LEFT)
Component # Dwg. Component ID Associated Type of (SKE-EE-172) & Description System Change 44,45 Indicating Lights Isol. Gr. o Components Moved for Isolation 1 to 9-5L From 9-5R Group 1 47,48 Indicating Lights Isol. Gr. o New Components Added for Isolation 2 to 9-5L _ Group 2 50,51 Indicating Lights Isol. Gr. o New Components Added for Isolation 3 to 9-5L Group 3 t 53,54 Indicating Lights Isol. Gr. o New Components Added for Isolation 4 to 9-5L Group 4 l 56,57 Indicating Lights Isc1. Gr. o New Components Added for Isolation 5 to 9-5L l Group 5 l
Nobraska Public Power District- R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 66 of 119 Revision 0 0 NOTES TRAINING MATERIAL 4 TABLE 13 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 LEFT) (continued) Component # Dwg. Component ID Associated Type of (SKE-EE-172) & Description System Change 59,60 Indicating Lights Isol. Gr. o New Components Added for Isolation 6 to 9-SL Group 6 62,63 Indicating Lights Isol. Gr. o New Components Added i for Isolation 7 to 9-5L l Group 7 l i l l \ l l l O r _ _ _ _ _ _ _ _
Nebraska Public Power District R0P&SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 67 of 119 Revision 0
.G V TRAINING MATERIAL NOTES TABLE 14 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 CENTER)
Component # Component ID Associated Type of h (SKE-EE-174) & Description System Change 22-37 LPRM Meter Scales NMS o Replacement of Meter Scales 76.77,78 Annunciator Annunciator o Components Relocated Acknowledge, Response on 9-SC
' Reset, and Test i
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Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 68 of 119 Revision 0 0 NOTES TRAINING MATERIAL TABLE 15 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 RIGHT) Component # Dwg. Component ID Associated Type of (SKE-EE-176) & Description System Change 68 Pump SLC o Components Modified Isol. Valve to Allow For Two-Pump Operation (Prelim'inary Locations Shown) 71 Reactor Feed Reactor Feed o Component Relocated Controller on 9-5R _ RFC-MA-84A 72 Reactor Feed Reactor Feed o Component Relocated Controller on 9-5R RFC-MA-84B 69 Master Flow Reactor Feed o Compenent Relocated Controller on 9-5R RFC-LC-83 91 Startup Flow Reactor Feed o Component Moved to Controller 9-5R From 9-5C RFC-MA-131A l [ l () l
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 69 of 119 Revision 0 G
', V NOTES TRAINING MATERIAL TABLE 15 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 RIGHT) (continued)
Component # Dwg. Component ID Associated Type of (SKE-EE-176) & Description System Change 92 Startup Flow Reactor Feed o Component Moved to Controller 9-5R From 9-SC RFC-MA-131B 93 Startup Flow Reactor Feed o Component Moved to controller 9-5R From 9-5C RFC-LC-130 36 Narrow Range Reactor Feed o Component Relocated Level Ind, on 9-5R RFC-LI-94B 38 Narrow Range Reactor Feed o Component Relocated Level Ind. on 9-5R RFC-LI-94C l I 35 Selector Switch Reactor Feed o Component Relocated for Sem Flow / on 9-5R Shutdown Level 37 Selector Switch Reactor Feed o Component Relocated for RX Wtr/Lvl on 9-5R O l l
Nebranks Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 70 of 119 Revision 0
~s NOTES TRAINING MATERIAL TABLE 15 - AFFECTED COMPONENTS ON PANEL 9-5 (9-5 RIGHT) (continued)
Component # Dwg. Component ID Associated Type of (SKE-EE-176) & Description System Change 49 Selector Switch Reactor Feed o Component Relocated for 1 or 3 on 9-5R Element /Lvl Cont 50 High Wtr Lvl/ Trip Reactor Feed o Component Relocated Logic B Reset on 9-5R
, O
( 51 High Wtr Lvl/ Trip Reactor Feed o Component Relocated Logic C Reset on 9-5R 50 High Wtr Lvl/ Trip Reactor Feed o Component Relocated Logic B Reset on 9-5R 51 High Wtr Lvl/ Trip Reactor Feed o Component Relocated Logic C Reset on 9-5R l l l l O l l
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 71 of 119 Revision 0 0 NOTES TRAINING MATERIAL TABLE 16 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5L Related A ss o c ia t e d Component System Label Contents 1 Alarm Box 9-5-1 Alarm Tile Alarm Box 1,2,3,4-------9 ID (Vertical
- Numerals)
Alarm Tile Alarm Box -1,-2,-3,-4,'5,-6 ID (Horizon Numerals) l 42 PCIS Group Isolation Indications 43 PCIS TRIP SYS A/GR1/ TRIP SYS B 1 l 46 PCIS TRIP SYS A/GR2/ TRIP SYS B l 49 PCIS TRIP SYS A/GR3/ TRIP SYS B l O I I l - - . _ _ _ _ _ , ,-_ ___. _ __ _ _. _ . . . _ _ _ _.
Nebrasko Public. Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 72 of 119 Revision 0 0 NOTES TRAINING MATERIAL TABLE 16 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5L (continued) Related Associated Component System Label Contents 52 PCIS TRIP SYS A/GR4/ TRIP SYS B 55 PCIS TRIP SYS A/GRS/ TRIP SYS B 58 PCIS TRIP SYS A/GR6/ TRIP SYS B
) 61 PCIS TRIP SYS A/GR7/ TRIP SYS B ~
44,45,47 PCIS DUAL IND 48,50,41, (14 Tags) i 53,54,56,67 59,60,62,63 l 64 NM SRM Monitors l 66 RWM Rodworth Minimizer 8 RWM Rodworth Minimizer Bypass 20 PCIS Group Isol Reset O
I l Nobraska Public Power District ROP &SRO&STA-DCR-DR-00-1 , Cooper Nuclear Station Page 73 of 119 ! Revision 0 NOTES TRAINING MATERIAL TABLE 16 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5L (continued) Related Associated Component System Label Contents 23 CRD Scram Discharge Volume 1 65 NM Neutron Monitor i Bypass l. l I l l I t O
_ ._. ._ m __ Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 74 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 17 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5C Related Associated Component System Label Contents 99 Reactor Reactor Control Control (Panel 9-5) 100 Control Rods Control Rod Dispicy 96 IRM/APRM IRM/APRM Monitors 104 IRM/APRM IRM/APRM Monitors 74 Control Rods Rod Sequence Control 101 Control Rods Control Rod Select
- O I
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Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 75 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 18 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5R Related Associated Component System Label Contents 98 Alarm Box 9-5-2 Alarm Tile Alarm Box 1,2,3,4-------9 1D (Vertical Numerals Alarm Tile Alarm Box -1,-2.-3,-4,-5,-6 ID (Horizon Numerals) 1 RPS Group A 1 2 3 4 83 RPS Scram Indications 3 RPS Group A l 1 2 3 4 i O
3 1:obraska Public Power District ROP &SRO&STA-DCR-DR-00-1
,Coopor Nuclear Station Page 76 of 119
, Revision 0 O NOTES TRAINING MATERIAL r
\
TABLE 18-DCRDR HED CORRECTIONS Summary Labels &cHED Label Changes Panel 9-5R (continued) Related Associated Component System Label Contents 87 RF Reactor Feedwater Control i 13 NBI Reactor Water Level 16 RF Reactor Feedwater Flow 17 NBI Reactor Pressure 88 NBI Water Level Trip t Reset ! 39 CRD CRD Hydraulic l 45 SBLC Standby ',16, *. *. d Conten: l l t r
?
Nebraska Public Power District ROP &SRO&STA-DCR-DR-00-1 Cooper Nuclear Station Page 77 of 119 Revision 0 TRAINING MATERIAL () NOTES TABLE 18 -DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel 9-5R (continued) Related Associated Component System Label Contents 70 RF Feedwater Flow Controller 90 RF Feedwater Startup Flow Controllers O
i Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 . E Cooper Nuclear Station Page 78 of 119 Revision 0 I-NOTES TRAINING MATERIAL i i t I k e a g 6 4
! D. VBD-S 1
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Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 79 of 119 Revision 0 (i ' ' ~ TRAINING MATERIAL NOTES PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTALL Panel VBD-S
- a. Enhancements o Functional demarcation and labeling of sump controls in Turbine Bldg, RX Bldg. Yard and Control Bldg o Functional demarcation and labeling of controls' and displays' subgroupings within the Turbine and Reactor Buildings
- RAD AREA EQUIP DRAINS, RAD FLOOR DRAINS NONRAD FLOOR DRAINS, in Turbine Building
- AREA NW, AREA NE, AREA SW, AREA SE, TORUS AREA in
() o Reactor Building Elimination of temporary labels through inclusion of needed information on the new labels o Relabeling of panel components in a hierarchical scheme
4 5 Nebraska Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 80 of 119 Revision 0 NOTES TRAINING MATERIAL Panel VBD-S
- a. Enhancements (continued) o Scale banding of area level indications and marking entry to emergencies.
s ' o Distinction of pump and valve i switches through control coding of pumps by yellow bands o Functional demarcation of annunciator controls i
- O F
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Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 81 of 119 Revision 0 O NOTES TRAINING MATERIAL Panel VBD-S
- b. Modifications o Incorporation of new reactor
' building sump & area level indications o Relocation of ERP pump COUNTERS and RUN TIME DISPLAYS TO IMPROVE VISIBILITY o Relocation and subgrouping of Yard Sump Pumps O
i. l l t l l l l l O i 1
Nabracko Public Pcwor Dictrict POP &SRO&STA-DCR-DR-001 Cospor Nucloor Station Pago 82 of 119 Revision 0 h,o NOTES TRAINING MATERIAL e u G W
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Nebraska Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 83 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 19 - AFFECTED COMPONENTS ON VBD-S Component # Dwg. Component ID Associated Type of
& Description System Change iSKE-EE-621 38 Electric Manhole Yard Sumps . Components Relocated Sump Pump W in VBD-S 39 Electric Manhole Yard Sumps Components Relocated Sump Pump Y in VBD-S 52 Pump Starts ERP Components Relocated Z-1 in VBD-S 54 Pump Run ERP Components Relocated' Z-1 in VBD-S 53 Pump Starts ERP Components Relocated Z-2 in VBD-S 55 Pump Run ERP Components Relocated Z-2 in VBD-S 65 Sump A Level RX Bldg New Component Added Indication Sumps to VBD-S NW Quad
Nebraska-Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 84 of 119 Revision 0 . bon NOTES TRAINING MATERIAL TABLE 19 - AFFECTED COMPONENTS ON VBD-S (continued) Component # Dwg. Component ID Associated Type of (SKE-EE-62) & Description System Change 66 Sump B Level RX Bldg New Component Added Indication Sumps to VBD-S NE Quad 67 Sump C Level RX Bldg New Component Added Indication Sumps to VBD-S SW Quad 68 Sump D Level RX Bldg New Component Added Indication Sumps to VBD-S SE Quad O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 85 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 20- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-S Related Associated Component System Label Contents 83- Alarm Box S-1 Alarm Tile Alarm Box 1,2,3,4,5,6 ID (Vertical i Numerals) l Alarm Tile Alarm Box -1,-2,-3,-4 l ID (Horizon Numerals) { f 1 T/G Bldg Turbine Generator Bldg Sumps 69 T/G Bldg Rad Area Equip Drain 51 T/C Bldg Radioactive Area Floor Drains l i i
Nobraska.Public Power' District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 86 of 119 Revision 0 [D
%)
NOTES TRAINING MATERIAL TABLE 20- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-S (continued) Related Associated Component System Label Contents 71 T/G Bldg Non Radioactive Area Floor Drains 18 Reactor Bldg Reactor Bldg Sumps 72 Reactor Bldg Floor drain - Area NW 73 Reactor Bldg Floor drain - Area NE 73 Reactor Bldg Floor drain - Area SW i ! 75 Reactor Bldg Floor drain - Area SE 83 Reactor Bldg Equip drain - Area SE l 34 Misc Sumps Misc Sumps 61 Control Bldg Control Bldg 62 ERP Elevated Release Point [ I Torus Area
- 43 Torus i
Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 87 of.119 Revision 0 O NOTES TRAINING MATERIAL TABLE 20- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-S (continued) Related Associated
^
Component System Label Contents 63 Yard Yard 81 Annunciator Annunciator Proced-ures S-1 i i a I O
- - . _ . -.. . -... ... . _ -._ .._.~_. . --.- - . . . . _ _ . .. . - . _ - - .__
L Nebraska Public Power District ROP &SRO&STA-DCR-DR-001
- ' Cooper Nuclear Station Page 88 of 119 Revision 0 NOTES TRAINING MATERIAL I ;
I i i t i f-t e i i J E. VBD-J l 1 l 4 i t i i l' I 4 i I I i i i j 1 , ? l i e i i i i I
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Nobraska-Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 89 of 119 Revision 0 NOTES TRAINING MATERIAL PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE Panel VBD-J
- a. Enhancements o Functional demarcation and labeling of Suppression Pool Displays. Torus Air Space Controls & Displays, Door Air Lock Status, and the Vacuum Relief Valve Controls o Relabeling of panel components and various subgroups in a hierarchical scheme o Functional demarcation of the vacuum relief valve master controller switch by red lines of demarcation reserved for critical controls o Scale banding of chart recorders and marking entry to emergencies o Functional demarcation of annunciator controls in a manner similar to other annunciator controls O
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 90 of 119 Revision 0 I A) (_ NOTES TRAINING MATERIAL i Panel VBD-J
- b. Modifications o Relocation of torus temperature and* pressure recorders PC-TR-21, PC-PR-20 and PC-TR-23
- o Incorporation of a new suppression pool temperature i
recorder PC-TR-25 (component
- 40) to separate Div I and Div II temperature sensors I
o Provision of dual IL's (OPEN/ CLOSED) for: - - DW Air Lock Door Status RR Air Lock Outer Door Status l i RR Air Lock Inner Door Status i i o Standardization of alarm response controls. i l
Nobrooko Public Power District ROP &SRO&STA-DCR-DR-001 Coopor Nucloor Station Pogo 91 of 119 Revision 0 O(,/ NOTES TRAINING MATERIAL
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r Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 92 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 21 - AFFECTED COMPONENTS ON VBD-J Component # Dwg. Component ID Associated Type of (SKE-EE-113) & Description System Change 5 Supp Chamber Torus o Component Temp Recorder Relocated on PC-TR-21 VBD-J o Label Change 7 Supp Chamber Torus o Component Temp Recorder Air Relocated on
'- PC-PR-20 Space VBD-J o Label Change 11 Nameplate Supp Pool o Component Torus Temp Relocated on Sensing Pts VBD-J o Label Change 15 DW Air Lock Air Lock o Component
! Door Status ILs Relocated on l VBD-J ! o OPEN/ CLOSED 1 Its Added i
Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 93.of 119 Revision 0 /O %/ NOTES TRAINING MATERIAL TABLE 21 - AFFECTED COMPONENTS ON VBD-J (continued) Component # Dwg. Component ID Associated Type of (SKE-EE-113) & Description System Change 16 RR Air Lock Air Lock o Component Outer Door Relocated on Status ILs VBD-J o OPEN/ CLOSED ILs Added 17 RR Air Lock Air Lock o Component gg Inner Door Relocated on \- Status Its VBD-J o OPEN/ CLOSED ILs Added 31 Torus Air Temp Torus Air o Component Recorder Space Relocated on PC-TR-23 VBD-J 40 Supp Pool Temp Supp Pool o New Component Recorder Added to PC-TR-25 VBD-J O
Nebracks Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 94 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 22 - DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-J Related Associated Component System Label Contents 1 Suppression Chamber / Pressure Relief Panel (VBD-J) 2 Alarm Box J-1 O Alarm Tile Alarm Box 1,2,3, - - - 6 ID (Vertical J-1 Numerals Alarm Tile Alarm Box -1,-2,-3,-4,-5 (Horizontal) J-1 Numerals 3 PC Suppression Pool 13 PC Air Lock 42 PC Torus Air Space O
Nebrooka Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 95 of 119 ' , Revision 0 I-
; NOTES TRAINING MATERIAL !
I 1 TABLE 22- DCRDR HED CORRECTIONS
; Summary Labels & HED Label Changes l 1
Panel VBD-J I, Related Associated 1
! Component System Label Contents
~
1 J l 45 PC Torus Temp Trend ] 14 PC Vacuum Relief Valves l' 43 PC Pressure Monitor i 44 PC Temperature Monitor
- 1 1
i j l i 1 i i i i I i
! i j
!O 1 i l 1
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 96 of 119 Revision 0 0 NOTES TRAINING MATERIAL O F. HD-R O O
Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 97 of 119 Revision 0 NOTES TRAINING MATERIAL PANEL ENHANCEMENTS AND MODIFICATIONS SCHEDULED FOR IMPLEMENTATION IN THE 1986 REFUELING OUTAGE Panel VBD-R
- a. Enhancements o Functional demarcation of reactor building, control building and turbine building ventilation system o Subgrouping of supply air, exhaust air, and MG
~ ventilation components in the reactor building subsection of the panel and development of r mimics that connect related components o Subgrouping of the control room and computer room fans in I the control building subsection of the panel i o Labeling of the controls and displays subgroupings within 1 the turbine building, control building and the RX building o Scale banding of meters and marking entry to emergencies 4
o Functional demarcation of annunciator controls
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 98 of 119 Revision 0 0 NOTES TRAINING MATERIAL Panel VBD-R
- a. Enhancements (continued) o Matrix identification of annunciators through labeling of the axes, annunciator boxes R-1 and R-2 o Control coding of fans by yellow bands or collars O
O
Nobrocko Public Powcr District ROP &SRO&STA-DCR-DR-001 Coopor Nuclost Station Page 99 of 119 Revision 0 ,O
'~
NOTES TRAINING MATERIAL i Panel VBD-R
- b. Modifications o Relocation of supply air, exhaust air MG ventilation controls, and filter exhaust booster fans in the reactor b1dg subsection of the panel (See VBD-R drawing in the classroom and Table 23 for list of affected components on VBD-R in Student Handout)
O(_j o Relocation of control room and computer room fan controls in the control b1dg subsection of the panel (Ssee Table 23 for list of affected components) o Relocation of battery fans, rectre fans and main supply i fan controls in the control bidg subsection of the panel O
Nobracke Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 100 of 119 Revision 0 ' O, NOTES TRAINING MATERIAL Panel VBD-R
- b. Modifications (continued) o Lowering the positions of differential pressure controllers and* recorders on the panel to meet NUREG-0700 anthropometric limits.
o Movement of Rx Bldg differ-ential press. controller HV-dPIC-835B from control bids subsection of the panel to Rx building subsection of the panel o Relocation of primary containment venting valve control in the Rx building subsection of the panel o Standardizing the arrangement of alarm response controls o Removal of filter drive switches that are not operable from the control room. O
Nobrocks Public Pcwor District R0P&'SRO&STA-DCR-DR-001 Coopor Nuciocr Station Pago 101 of 119 Rovision 0
'im \
I U NOTES TRAINING MATERIAL
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NGbracka Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 102 of 119 Revision 0 nJ NOTES TRAINING MATERIAL TABLE 23 - AFFECTED' COMPONENTS ON VBD-R Component # . Dwg. Component ID Associated Tvge of (SKE-EE-216) & Description System Change 40 Battery Room Battery Rm Component Relocated Exhaust Fan H&V on VBD-R 41 Emergency Control Component Relocated Filter Fan Room H&V on VBD-R 46 Light: Control Control Component Relocated Room Compressor Room H&V on VBD-R 81 Recirculation Controi Component Relocated Fan Bldg H&V on'VBD-R 82 Recirculation Control Component Relocated Fan Bldg H&V on VBD-R 94 Battery Room Battery Rm Component Relocated Exhaust Fan H&V on VBD-R 95 Fan Coil Unit Control Component Relocated Bldg H&V on VBD-R O
Nebrsoka Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 103 of 119 Revision 0 NOTES TRAIN " MATERIAL TABLE 23 - AFFECTED COMPONENTS ON VBD-R (continued) Component # Dwg. Component ID Associated Type of (SKE-EE-216) & Description System Change 56 Filter Room Filter Rm . Component Relocated Exhaust Booster H&V on VBD-R Fan 69 Filter Room Rx Bldg Component Relocated Exhaust Booster H&V on'VBD-R Fan
) 86 Exhaust Fans Rx Bldg Component Relocated H&V on VBD-R 85 Exhaust Fans Rx Bldg Component Relocated H&V on VBD-R 97 MC Set 1-A M/G H&V Component Relocated Exhaust Fans on VBD-R 98 MG Set 1-B M/G H&V Component Relocated Exhaust Fans on VBD-R 37 H&V Unit Rx Bldg Component Relocated Discharge H&V on VBD-R Isolation Valve
Nebracke Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclect Station Page 104 of 119 Revision 0
~'
NOTES TRAINING MATERIAL
. TABLE 23 - AFFECTED COMPONENTS ON VBD-R (continued)
Component # , s M. Component ID Associated gpe of ,2 (SKE-EE-216) & Description System Change 43 H&V Unit Rx Bldg, ,
. Component Relocated Discharge H&V on VBD-R Isolation Valve .
'T 44 Exhaust Fans Rx Bldg Component Relocated Discharge H&V on VBD-R Isolation Valve , I 45 Exhaust Fans Rx Bldg Component Relocated Discharge H&V [ on VBD-R Isolation Valve 59 MG Set 1B M/G H&V Component Relocated Ventilating on VBD-R Inlet Isolation Valhe 61 MG Set IB M/G H&V Component Relocated j, Ventilating on VBD ,R' l Outlet Isolation e Valve t l l l 4
R0P&SRO&STA-DCR-DR-001 Nebraska Public Power. District Page 105 of 119 Cooper Nuclear Station Revision 0 m f NOTES TRAINING MATERIAL TABLE 23 - AFFECTED COMPONENTS ON VBD-R (continued) Component # Component ID Associated Type of D3 Change Description System (SKE-EE-216)_ &
-MG Set 1A M/G H&V . Component Relocated 71 Ventilating on VBD-R Inlet Isolation Valve i
MG Set 1A M/G H&V Component Relocated 73 Ventilating on VBD-R J I Outlet Isolation q V Valve l Exhaust Fans Rx Bldg Component Relocated
! 39 Discharge H&V on VBD-R Isolation Valve 1
f Exhaust Fans Rx Bldg Component Relocated 38 Discharge H&V on VBD-R Isolation Valve i TG Bldg / ATMOS T/G Bldg Component Relocated 5 DP Recorder H&V on the same sub-section of the panel l O l I
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 107 of 119 Revision 0 0 NOTES TRAINING MATERIAL , TABLE 24- DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-R Related Associated Component System Label Contents 1 VBD-R Heating & Ventil-ation Control 150 Alarm Box R-1 151 Alarm Box R-2 Alarm Tile Alarm Box 1,2,3, ---6 ID (Vertical) R-1 Numerals e Alarm Tile Alarm Box -1,-2,-3.-4,-5
- ID (Horizon) R-1 I Numerals i
Alarm Tile Alarm Box 1,2,3 - - - 6 ID (Vertical) R-2 Numerals Alarm Tile Alarm Box -1,-2,-3,-4,-5 ID (Horizon) R-2 Numerals l
Nebraska Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 108 of 119 Revision 0 O NOTES TRAINING MATERIAL TABLE 24 DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-R (continued) Related Associated Component System Label Contents 108 HV Turbine Bldg 109 HV Control Bldg l 110 HV Reactor Bldg 111 HV Turb Bldg / Atmos P 112 HV Supply Fans ! 113 HV Exhaust Fans f 114 HV Recire Fans l 115 HV P Controller 116 HV Battery Fens 117 HV Recire Fans
--_ ~ - . .- _ . _ . _ . __ - . . . .
l Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 109 of 119 Revision 0 0 NOTES TRAINING MATERIAL TABLE 24 DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-R (continued) Related Associated Component System Lab'el Contents 1 i 118 HV MN Supply Fans 119 HV Control Room i 121 HV Computer Room 128 HV RX Bldg / Atmos DP 130 HV Supply Air P N iO
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 110 of 119 Revision 0 NOTES TRAINING MATERIAL TABLE 24 DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-R (continued) Related Associated Component System Label Contents 132 HV Exhaust Air 131 HV To Bldg r~ 133 HV To Atmos v Q)g i l 134 HV Quad Temperatures 135 HV Quad Fans 136 HV Stm Tunnel Fans 138 HV Fitr Exh Bstr Fans 139 HV MG Ventilation I i 140 HV Exhaust Fans 141 HV PC Venting l () I L
Nebraska Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 111 of 119 Revision'0 NOTES TRAINING MATERIAL TABLE 24 DCRDR HED CORRECTIONS Summary Labels & HED Label Changes Panel VBD-R (continued) Related Associated Component System Label Contents 144 HV Isolation Valves 142 HV To Atmos 146 HV Fm Atmos O' 145 HV MG-1A 147 HV MG-1B 143 HV Fan Room 148 HV Alarm Procedures R-1 149 HV Alarm Procedures R-2 O
Nebrooko Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 112 of 119 Revision 0 ()- NOTES TRAINING MATERIAL
- 2. CHECKLIST 2.1 Description 2.1.1 Purpose To assist the participant in systematically recognizing all the changes on the panels.
2.1.2 Checklist Items Panel Enhancements: Mimics, Functional Demarcation, Relabeling, Control Coding and Meter Banding Panel Modifications: Relocated Components, Added and Removed Components List of Related Systems' Procedures Associated with the Panel Changes () ' 2.1.3 Procedure for Completing the Checklist Go to each of the panels. Observe new panel layout, new positions of relocated controls and added components. Document your observations-and comments. i l l t
. Nebraska Public Power District R0P&SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 113 of 119 Revision 0
r (d NOTES TRAINING MATERIAL i
1
- 2. CHECKLIST (continued) i l' 2.1.3 Procedure for Completing the Checklist (continued)
- Obtain copies of the referenced systems' procedures. Walk-through operator steps that relate to panel changes. Document and include
- comments.
- Hand in the completed checklist to the shift supervisor.
O . - \_) i i l' l l l l O i
i Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 I Cooper Nuclear Station Page 114 of 119 Revision 0 l (~s !
%.) NOTES TRAINING MATERIAL )
2.2 Checklist Sheets A. PANEL 9-3 WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
- 1. Panel Enhancements
- Mimics, Functional .
Demarcations, Control Coding, Meter Banding, and Relabeling
- 2. Panel Modification List of Relocated Components or Added ___
Components O ITEM COMPLETED COMMENTS
- 3. Walk-through Related Systems Procedure
- PC. SOP REF. 4.9
- SW,50P REF. 2.2.70 ___
- RHR, SOP REF. 2.2.69
- CS, SOP REF. 2.2.9 l
- HPCI, SOP REF. 2.2.33
- MSIV, SOP REF. 2.2.56 ___
- ADS,50P REF. 2.2.1 Completed by: Date l
[ l l
1 Nebracks Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 115 of 119 Revision 0 CE) NOTES TRAINING MATERIAL , 2.2 Checklist Sheets (continued) B. PANEL 9-4 WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
- 1. Panel Enhancements Mimics, Functional Demarcations, Control -
Coding, Meter Banding, and Relabeling
- 2. Panel Modification List of Relocated Components or Added Components O ITEM COMPLETED COMMENTS
- 3. Walk-through Related Systems Procedures Radwaste Procedures (SOP Ref. 2.2.62)
RCIC Procedures (SOP Ref. 2.2.67) ___ i RWCU Procedures (SOP Ref. 2.2.66) RRMG Procedures (SOP Ref. 2.2.28) Completed by: Date O
Nebracke Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 116 of 119 Revision 0 O NOTES TRAINING MATERIAL 2.2 Checklist Sheets (continued) C. PANEL 9-$ WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
- 1. Panel Enhancements Mimics, Functional Demarcations, Control _
Coding, Meter Banding, . and Relabeling ___
- 2. Panel Modification List of Relocated Components or Added Components ___
ITEM COMPLETED COMMENTS O 3. Walk-through Related Systems Procedures
- NM Procedures (SOP Ref .4.1)
- CRD Procedures (SOP Ref. 2.2.8) ___
SLC Procedures (SOP Ref. 2.2.74)
- RF/RFC Procedures (SOP Ref. 2.2.28)
Completed by: Date _____ O
Nobraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclect Station Page 117 of 119 Revision 0 NOTES TRAINING MATERIAL 2.2 Checklist Sheets (continued) D. VBD-S WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
- 1. Panel Enhancements Mimics, Functional Demarcations, Control Coding, Meter Banding,
- and Relabeling
- 2. Panel Modification List of Relocated Components or Added Components _
() ITEM COMPLETED COMMENTS
- 3. Walk-through Related Systems Procedures
- Equipment, Floor and Chemical Drain System.
SOP Ref. 2.2.27 T Completed by: Date l l l l l - - - - -- _,
Nebriska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Pego 118 of 119 Revision 0
) NOTES
~~ ~~~
TRAINING MATERIAL 7 . :: Checklist _ Sheets (continued) E. VBD-J WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
- 1. Panel Enhancements Mimics, Functional Demarcations, Control Coding, Meter Banding, ,
and Relabeling i
- 2. Panel Modification List of Relocated Components or Added Components ___
() 1 TEM COMPLETED
- 3. Walk-through Related Systems Procedures
- RHR, SOP REF. 2.2.69 ___
Completed by: Date i 4
- - ,- --. - - . . -- ,,. . , , , ,-_.a-,- -- --,,----,--,o,, --.
Nebraska Public Power District ROP &SRO&STA-DCR-DR-001 Cooper Nuclear Station Page 119 of 119 Revision 0 ( TRAINING MATERIAL NOTES 2.2 Checklist Sheets (continued) F. VBD-R WALK-THROUGH CHECKLIST IN THE CONTROL ROOM ITEM OBSERVED COMMENTS
, 1. Panel Enhancements Mimics, Functional Demarcations, Control
- Coding, Meter Banding.
and Relabeling
- 2. Panel Modification List of Relocated
- Components or Added Components
- O ITEM COMPLETED COMMENTS 6
- 3. Walk-through Related Systems Procedures
- HVAC Reactor Bldg SOP REF. 2.2.47
- HVAC Control Bldg i SOP REF. 2.2.3A i
- HVAC Turbine Bldg SOP REF. 2.2.49 Completed by: Date l
i i O
- m 6 a. -m m. . _ .)
3r a.2 s--a-%---- -- u4 4 e+e--,-=Am _ Al .u u. a. 4_.# , _a 4 u4 l 4
.O-l' 4
l ! I J APPENDIX F IMPLEMENTED CORRECTIONS BY END OF O 1986 REFUELING OUTAGE F.1 VBD-S HED CORRECTIONS (p. 1-3) F.2 VBD-J HED CORRECTIONS (p. 4-5) < F.3 PNL 9-3 HED CORRECTIONS (p.6-11) (p. 12-15) I F.4 PNL 9-4 HED CORRECTIONS F.5 PNL 9-5 HED CORRECTIONS (c. 16-18) i (p. 19-23) i F.6 VBD-R HED CORRECTIONS l r e !O ' i l l 4
,. w , -,. ,,,--#,--,# ,, w...,c-w.w.em,_.,..-,m,, -.-w ...,--. . ,,,- m m -,- w w - w. ..-me,, m,, ..m-, , ,. w,,..-,v,.--
Dce e5-1s0 F.1 V80-S HED CORRECTIONS PANEL / BOARD VBD-S Verification / Validation Sign-Off Sheet (* (v) CORE TEAM ~ e RE50WTION SIGN OFF 5EW HED CDMMENTS , DESCRIPTION COMMENTS I HED# WRIF. VALID. Y/N Controls and displays located The ERP sunp meters are outside recommended zones. being elevated and the new sump meters coreply. 17355 See SKE-EE-61 & SKE-EE-6 Related groups of controls or System and ossystem displays not set off by demar- groups are identified and 17455 cation lines. will be enclosed with
- lines of demarcation.
See SKE-EE-62, Step A108 Extensive temporary labels are Temporary labels will be i being used. eliminated. Formal labels will include necessary information. . , 3933 See SKE-EE-62 and Label ( Change Table. l Control switch position not Replace switch position l P k 18555 permanently marked. escutcheon. See Page 29, Step A115. i i No plant standards exist for Color code standards are 215 color coding for all panels. specified in the CNS HF Guidelines and are imple mented for this panel. l Annunciator response Functional ContrO1S are not Coded demarcation for ease of recognition provided. See SKE-EE-113 Annunciator alarms are not Present system uses provided with alphanumeric code nuneric/nuneric code. 1495 for prompt response. Labels will be used to identify. See SKE-EE-62. l O l
F.1 VBD-S HED CORRECTIONS (continued) ERIfICATION/ VALIDATION SIGN-OFF 94EET DCf 85-150 PANEL / BOARD VBO-S CCRE TEAM RESOLUTION SIGN 7F NEW CGeENTS HED CINMENTS HEDd E SCRIPTI0ri VARIF. VALID. Y/N Inconsistent use of acronyme A list of acronyms and and abbreviations. abbreviations has been generated in the CNS HF 1765S guidelines; new labels
- shall be made then appli-cable to comply with guidelines. See Label Change Table.
Indicators not marked to show The indicators for the normal ranges of operation. sump levels and Torus Area show green band for 17755 normal operation ed red arrow for entry to emer. gency. See SKE-EE-213. Ntaber of graduations betseen Replace RW-L1-900 scale numbered markinga on scales and human factor new l l
~
17855 exceed the maximum of nine. aceles for the sump level meters. O See SKE-EE-213. Association of feedback The ERP sump metera are
- related controle not apparent being relocated above l 18355 through labeling mimics, and related controls, and demarcation lines. lines of demarc. identify l
related equipment. See SKE-EE-62. No piysical distinction between The 2 Type OR2940 handles, coding by size, shape, switches shall be color or color to identify switch by coded. A yellow ring l 1105 type or function, signifies a pump mid a f black ring signifies valves sid miscellaneous. See SKE-EE-62 and Step A116. Annunciators not grouped above Relocate AROHVAC Trouble related controle and displays. to Annunciator R1. Add 138S , Torus Area High Level to Annuneistor St. ! See SKE-EE-59 & 60. Also see Step A102, page 27.
- O i
1
F.1 VBD-S HED CORRECTI0fl5 (continued) DCf G-150 ERIFICATION/ VALIDATION SIGN-0FF 94EET PANEL /80ARD VBD-S ( CORE TEAM SIGN OFF NEW RESOLUTION HED CC M NTS CESCRIPTION C0994ENTS HEDf VALID. Y/N ERIF. Annunciator response controls The annunciator response are not coded for esse of controls are demarcated 1645 recognition. by 3/8" orange box around. See SKE-EE-62 and Ste; A108 on page 29. Secondary containment sump Level transmitters shall be added to each RX 81dg. , water level indication is not Floor drain sunp with 63T available. indication on panel 20-5 and PMIS. See SKE-EE-62. Alare for secondary containment Adding Torus Area Hi Torus Area Level not available. Level Alarm to Amuncia-64T tor S-1. See SKE-EE-60 l and Step A105 on page 28. Direct indication of secondary With the addition of sump containment sump pump discharge level instrunents the l 65T not available. operation of the pumps can be determined. Existing labels are not clear New labels are being with respect to function or installed on this panel to correct this HED. t 175S5 intent, f See Label Change Table I end Step A107 on page 28. O
F.2 VBD-J HED CORRECTIONS WRIFICATION/VALICATION SIGN OFF B EET OC# 35-15 l PA.TL/50HW V80-J f CORE TEAN RESCLUT!CN SICN &F Por l (D OIENTS i HED# K SCRIPTION ComENTS HED VERIF. VAL 10. Y/N l Switches for mergency or Enc 1ceed switch PC.5W-l ebnormal me not consistently CSYS with red lines of i 1165 merked. demarcation idiich signi. fios emergency use. See SKE-E-113. l l l l i O . l l Association of feedback to Instelling new labels and' related controle not apperant linee of desercetion to 349SS through labeling, mielce or identify related equip-desercation lines. eent. See SKE-CE-113 and l Label Change Table. Annunciatar alarme era not Amee of annunciater provided wiW alphenweric metrices will be labeled. I 1495 code for prompt respones. See SKE.(E-113. 1 i
~ - - - - - - - - . - - , - - , - _ __ 7,,,_ _ , ,,,,,_ __ _
1 F.2 VBD-J HED CORRECTIONS (continued) WRIFICATICN/ VALIDATION SIth-7F SHEET QCf 85-1 PAPEL/BCAS V80-J CWtf TEAN MSOLUTION $1GN 7F EW HEDf (ESCRIPTION COMENT5 HED CDeCNTS
%ERIF. VALID. V/N Inconsistent use of acronyme Generated list of abbre- '
and abbreviatione. vietione and acronyme in 18955 CNS W th:1delines ed implemented with new labeling. See Label Dienge Table. thidentifiable process mite. Place label identifying process mite on recorder 72SS cover PC-PR-20. See Label Change Table and SNE-EE.113. haber of graduations betwen Replaced meter scales nuntered markings on scale with new HF ocales. 191$$ escoed the maximus of nine. PC-TR-24 ! PC-TR-25 See CC 54-108. l l Pointer covere recorder scale Elevate recorder scale l merkings. elightly for PC-TR-23. 17255 See Step 35, pg.15. Alere pointe not identified on Zone marked scales for recordere. PC-TR-21, PC-TR-23, PC-84S TR.24, PC-TR-25, PC-PR-20 to show normal rege and mergency conditione. See SNE 4E-205. PC-TR-24
& 25 per DC 86-108.
Recortine scales ret marked to Zone oarked staise for show normal or abnormel reges PC.TR-21, PC TR.23, PC-948 of operation. TR-24, PC.TR-25, PC-PR. 20 to show norwel range and mergency conditione. See 5kE4E-205. PC-TR-24
& 25 per DC 85-108.
Displaye located below Elevated recorder PC-TR-recensended heights. 23. O 1015 See SNE-EE-113.
F.3 Pill 9-3 HED CORRECTIOfJS Oc #85-15r ERIr1 CATION / VALIDATION SIGN-Wf SiEET p h PANEL / BOARD 9-3 CORE TEAM S!CN Off NEW RESOLUTION HED Cate1ENTS CDP 9fENTS HED# ESCRIPTION VALID. Y/N VER!r. Enhancements are being Related groups of controls or displays not set off by implemented. See drawings 65 demarcation lines. (HPCI peps and turbine instru- SKE-EE-115 m entation; tel & PC instrumen- SKE-EE-117 SKE-CE-119 tation.) Lack of mimics integrating Mimics are being imple- , mented. See drawings: system components, SKE-EE-115 ISS (RHR nodes of operation, HPCI SKE-EE-117 turbine and po ps, CS p op SKE-EE-119 switches.) Devices are being reloca-Subgroups within system are not properly laid-out so that flow tsd to permit orderly 115 paths can be easily constructed flow. See drawings: l SKE-EE-115, SKE-EE-117, ' (RHR modes of operation, HPCI turbine and pumps, CS switches) SXE-EE-119 < O ADS Reller Valve Controls out of consistent sequencing. Labels for valve opening sequence will be placed on switch covers per 355 (Valves Switches 71A, B, C, E Panel 9-3 Label Diange Table, Attachment H G, H) Croupings of controls and Devices are being reloca-displays of similar fections ted mid demarcation lines ' not apparent. are being added. 155 (RNR switches for various modes See drawings: of operations.) ^ SKE-EE-115 SKE-EE-119 Labels and demarcation ( line . Enhancements are l Strings and matrices of l 185 components of sis 11er rections being implemented. See not differentiated by demarce- drawings tion of hierarchical labeling. SKE-EE-115 ! SkE EE-117 (HPCI pump and turbine instru. l SKC-EE-119 l labeling PC & 21 labels.) Association of related controls Devices are being re-not apparent through labeling, located to achieve < mimics, demarcation lines, etc. proximity of relater' i controls. See drawings: (1) Control. Switches 529 A and SkE EE-115 for Components l 485 S40A for HX Parallel Vent 69 & 100 - v Valves 166A and 167A are too s far apart for A RHR 2) same se SHE-EE-119 for Component
- 1) for B-RHR. 68 & 80 l
F.3 PNL 9-3 HED CORRECTIONS (continued) ERIFICATION/ VALIDATION SICN-Off SiEET DC# 85-15F PANEL / BOARD 9-3 O. CORE TEAM RESOLUTION SIGN T F NEW ESCRIPTION COMMENTS HED *CDmENTS HED# VERIF. VALID. Y/N No plant standard exists for CNS Hunan Factors color color coding. coding standards have 215 been developed and (Color coding standards.) implemented. Use of colors not consistently CNS Human Factors color applied on panel. coding standards have ' 225 , been developed and (Components labeling, caution implemented. labels.) Lack of labels for identifying New labels are being made component function and power per Panel 9-3 Label supply to instruments. Change Table, (1) Meter and recorder Attachment H 255 indications missing power swply ident. 2) Turbine vibration meter for HPCI lacks label ID. 3) RHR Flow Recorder FR-143 has no label identifying component function.) Inconsistent use of acronyms CNS Hunan Factors stand-and abbreviations. - ords include a list of 655 (Integrate with HED 21s for abbreviations. Relebel-development of hunan factor ing of the boards will plant standards, that include utilize this standard labeling and list of standard list. Label Change abbreviations.)' lable, Attachment H Existing labels are not clear Panel 9-3 Label Change with respect to fmetion or Table clarifies previous-intent. ly confusing labels. 855 (1) No distinction between DW See Attachment H. andSPSdrayValves31Aand 388. 2) Label for RHR level permissive manual override switch not succinctly worded.) Indicators > not marked to show Color banding of indica-normal ranges of operation. tors will be implemented 575 (Primary containment pressure per Attachment B. and level meters and recorders. PC-PR-1 A & IA, PC.LI-13, PC-PI-512, PC-LI-12.)
F.3 PNL 9-3 HED CORRECTIONS (continued) VERIFICATION / VALIDATION SI(N-OFF SHEET DCf 85-15F PANEL / BOARD 9-3 - n . U
\
CDRE TEAM POf RESOLUTION- SIGN OFF HED COMENTS HED# DESCRIPTION COMENTS Y/N VERIF. VALID. Instruments are not scaled in Process mits will be process mits relating to implemented per system operation. Attachment B. . (1) Unidentifiable process 1355 units for HPCI Pump PI-116, should be PSIC. 2) DW Pressure Heter and Recorder PC-PI-5128
& PC-PR-512A, process units ,
should be PSIG other than PSIA. Indicator design does not The indicator is being follow conventional pattern. inverted and new scale is 1C35 (HPCI Turbine Speed Indication oeing installed with 0 51-2792, pointer moves downward at bottom. See installa-to indicate increase in speed.) tion Step B259. Nunber of, graduations between Heter scales are being numbered markings on scales enhanced per Attachment-O exceed the maximum of nine. B. (1) RHR-FI-133A & B, 24 1455 graduations. 2) HPCI-PI-109 & 1'1, 1 14 graduations.
~
- 3) PC-LI-13,19 graduations.
- 4) RHR-FR-1433,19 graduations.)
Alarm points not identified on Scale banding will be recorders. implemented per 775 Attachment B. (PC-PR-1A and PC-PR-2A) Recorder scales not merked to Scale banding will be show normal or abnormal ranges implemented per 885 of operations. Attachment B. (PC-PR-1A,PC-PR-6A) Indicating lights do not Positive indications in indicate positive state or the form of amber lights 1555 positive response. Extin- will be provided. guished light means valve is actuated. (S/RV blue bu'Ibs) 1
F.3 PNL 9-3 HED CORRECTIONS (continued) DC# 85-15 WRIFICATION/ VALIDATION SICN OFF SiECT PANEL /BOARO 9-3 , CORE TEAM RESOLUTION SICN TF NEW HED COMMENT 5 DESCRIPTION COP 94ENTS HEDf VERIF. VALID. Y/N Indicating controller does not Device will be follow conventional pattern. eliminated. (Valve Position Indicating 955 Controller FIC-142, " closed" position indicated on the r igh t. Conventional pattern is
" closed" on the left.)
No physical distinction between Color Coding is being ' handles. Coding by size, provided in accordance shape, or color is not being with CNS HFE Standards. 1655 used to identify switch by type See drawings of function. (1) RHR Punp Controls 3A, 38, SKE-EE-115 3C, 30. 2) HPCI Pump 522. 3) CS SKE-EE-117 Pumps 1A and 18.) SKE-EE-119 , Process mits information not Process u11ts will be visible through recorder visible. Scales arv being modified per p 755 windows.
\ (1) DW Press. Recorder PC-PR-1A Attachment B.
(2) Primary Containment Level Recorder PC-LR-1A.) Lack of Himics Intet; rating ' Mimics are being System Components. implemented. 155 See drawings: SKE-EE-115 I SKE-CE-117 SKE-CE-119 Alarma not provided with Axes of Annunciator alphanumeric code for prompt matrices will be labeled 1495 response. per Panel 9-3 Label f Change Table Attach. H l (Labeling of exes.) See Step 8260 and dags. Alarm response system not Standardized arrangement consistent among panels. of ANN Controls is being 2355 implemented. c (Linear accangement of See drawing l annunciator controls.) SKE-EE-117 i lO
F.3 PNL 9-3 HED CORRECTIONS (continued)
~ tes 83-153 WRIFICAT10N/ VALIDATION SIGN-OFF 34EET PAML/80 AID 9-3 CORE TEAM ESOLUTION SICM CFF EW HED CtHEENTS E SCRIPT 10N COMMENTS HEDd VALID. Y/N WRIT.
l Front panele primary contein. Heter banding is being sent pressure recordere ,need to implemented per JT identify normal /off normal Attacteent 8. range of operation. (Presours Recordere PC.PR.1A & PC-PR.18.) j Indication le being Wide range torus preneurs f installed. See Item #173 indication not available. * + i 177 on 5KE-CE-115. ( l SRV label identification out Labels for valve opening of sequence. esquence will be pieced on switch covere per 207 (Valve Switches 71 A, 8, C, E, Penel 9-3 Label Change 0, H, D, F.) Table, Attachment H Functional esperation between Improved labeling plue j ADS and LLS valves not evident. extension lines provide the necessary 21T (Desercation betw en A05 and sepa ratione. See Label LLS valves.) Change Table, Attechment H. r, Ice t.c pump controle Devices are being RHR end indicatione are located on relocated. back penels rather than SkE-CE-115 Penel 9-3. SKE.EE.117 35T (Service eter pg control and Related alarme will eleo AMP retors on WD-M, locp flow be relocated by kned.1 controle on Penel 9 3.) of this DC. Incorrect demarcation of eleca Meter Banding vill be setpoints on SP level implemented per 40T indication. Atteersnent 8. . I 1 lO l l
l F.3 PNL 9-3 HE_Q_CQRRECTIONS_ (continued) OC# e5-15r VERIFICATION / VALIDATION SIGN-OFF SHEET PANEL / BOARD 9-3 . CORE TEAM , RESOLUTION SIGN OFF NEW HED COMTNTS DESCRIPTION C0894CNTS HED# VERIF. VALID. Y/N Label differentiation between Label Differentiation SP and DW system sprays needed. will be accomplished per Panel 9-3 Label Change 46T Table, Attachment H l (Label for Valves 31 A and 38A -
- i. and 318 and 388.)
1 Action levels on SP temperature Enhecements are being and level and, RX level and implemented per 55T pressure need to be marked. Attachment B. . (PC-PR-1 A & 2A, PC-LI-13, CP-PI-512, PC-LI-12.) RHR 2/3 core height level Relabeling of Valves permissive manual override 18A & 188 is being 111 switch label confusing. implemented per (RHR (2/3) Logic Override Panel 9-3 Label Change Switches S18A labels.) Table, Attachment H I , iO I I 1 i lO~ I I ' l
F.4 PNL 9-4 HED CORRECTIONS I VERIFICATION /VALIDATICN C10N.0t1* OtCCT OCf asy PATL/SCARD f4 O CCRE TEAM RCSCLUTION $1CN FF - WW C04HENTS NED C30CNT$ l NEDf E SCRIPTION _ WRIF. VALID. Y/N Use of colors not consistently Label colore have been applied on the penei. etandardized. 235 See sxt 4t-168. 169, 170 (PCI5, RWCU, RR, & RCIC and Label Change Table Control.) Iridicotore are not marked to Color bending of indice-show normal ranges of tore will be enhanced 585 operation. with color bande imple-sented per and arrows se - directed by Attactinent 8
& E of DCROR CCRE TEAM DIRECTIE this Design Change Docunent.
Alarm pointe are not identified Scale bending will be on the recorder scales. 1splemented per Attach-785 ment 8 & E of this Design Change Document. Switches fbr energency or Red demarcation ed white i ebnormal use ere not protected on-red labeling are med l 1148 from inadvertent operation. for seergency controle por CNS W E etenderde. h MfsFre16R wid LWiel { t Change Table. The displays thich reflect only " Demand Signal" labels demand signal are not labeled will be placed on bezele 122$ occordingly. of contro11ere. (PC15 RWCV, RR, & RCIC 5ee Label Change Table. Control.). Alerne not provided with Ames of annunciator will alphanumeric code for pecenpt be labeled. 1495 response. See Penel 9-4 Label Change and $xC4C-168, (Lebeling of exes.) 169, and 170. Front panele primary contain- Recorder banding will be sent press. Recordere need to implemented per Attach. sent 8 & C of this Design ST identify nomeal/off norsel range of operation. Change Docunent. l (Prese. Rec a. PC-PR-1A & PC-PR-tO a> l l
F.4 PNL 9-4 HED CORRECTI0ftS (continued) s-VERIFICATION / VALIDATION $1CN-FF SMET DC# 85-1! PAEL/SOARD 9-4 O (2lRE TEAM ESOLUTICN SIGN Fr NEW HEDd ESCRIPTION C3HENTS HED C:FENTS E RIF. %ALIO. Y/N Wide range torus pressure New Indicator will be indication not evellable. instelled - 197 See SKE4E-170, Component 119, Step 13C, [ pp V11-33. l I Action levels on $P temperature Enhancements are being and level sid, RX level ed implemented por Attach-557 preseues need to be marised. eent B & E of thie Design (PC PR-1 A&2A, PC.LI-13, Q'-P.!- Change. . 512.) Alere Response System not Devicoe are being consistent among panels. relocated. 2355 (Lineer erregement of See SWE-EE-169. annuncistor controls.) 52grosse within system are ret Devicae are being reloca-
~
preserly laid-out es that flow ted to permit orderly pathe een be emelly construct- flow pathe. See drawings O 2&SS ed. - SKE4E-168, SKE-EE-149 and SWE4E-170. Controle and displays not Devices are being grouped in rectional or relocated and rection- . 25SS sequential relationehlp. elly demercated. See Drawinge SKE-EE-168,169 and 170.
- Controle located outside Redweste Norme1/5ypees I recommended zones. 5 witch is being relocat-2755 ed for easy reach. See
, Drawing SWE-EE-169, Componet 64.
See Step 89, pp VII-24. Labels and legend plates, not 01ecropency will be uniformly positioned for corrected by recorder - , 2855 rectionei clarity. . relocation, Component #54 ' see SKE-CE-170. See Step 131, pp VII-33. l O
- l l
l
F.4 PflL 9-4 HED CORRECTIO!15 (continued) e OCf 85 1! VERIFICATION /VALIQ471CN SIGN-ofF SHEET PATL/8 CARD 9A O- RC50WTION CORE TEAM SION FF WW NED COMENTS NtOf DESCRIPTION C09thTS VERIF. VALIO. Y/N Number of graduations between New scales are being nebered esekings on a:eles added. 2955 escoed the meni: sus of nine. See Attactuente 5 & C. Turbine speed indiestor does Turbine Speed Indiestor not follow conventional corrected per Atteetwent 3055 pattern. 8 & E.
- See Step 25, pp VII-13.
No pysical distinction between Control Coding will be
- handles. Coding by size, provided in accordance 315$ shape, or color is not being with CNS hTE etenderde.
used to identify switch by type See Drawinge SWE-CE.165, of function. 149 sid 170. See 5tv, 139, pp V11 3A. Inconsistent use of seronyme CNS Human Factore Stand-ords include e list of > end abbreviations. 3255 embreviations. Relebel-ing of the boerde will utilire this etendard list. See Label Dienge Table. Indicatore not scaled with us. New scelse are being divisions in decimal multiples added. 3353 of1,2 ors. See attactumt 8 & E. Process mite information not Procese u11te will be easily road, made available on instru-u I 3455 mente. See Attachiente 8 & E and Label Change Table. Pointer covers recorder scale Scelse will be elevated merking elightly to itsprove 3555 visibility. See Step 140, pp VII.34 O l
)
i i F.4 Pill 9-4 HED CORRECTIONS (continued) S , DC# 851 ' )ER1r1 CAT 10N/WALIDATICN SIGN.0FT 5HEET PA8(L/ BOARD 94
~
l CGtt TEAM j RCSCLUTION SIGN (FF 4W i HED C39ENTS DESCRIPTION CD4CNTS _ HCD# WRIF. VALID. Y/N f Association of feedback to i Functional Desercation related controle not apparent Enhancements are being throgh leeling, mimics, added. See Drawings 395$ demarcation lines. SKC-CC.168 ' SKE-CC-169 Set-CE-170 O l l O f
l DCf 5-1 M F.5 PNL 9-5 HED CORRECTIONS - PAE L/ BOARD 9-5 ERIFICATION/VALICATION SIGN-OFF SET b CORE TEAM RESOLUTIDN SIGN 7 F ,
,E W COMENTS HED CD1E NTS HED# E SCRIPTION VERIF. VALID. YAi Labels ed legend plates, not labels Legend Plates, and consistently positioned above Demarcation Lines are 4555 or below devices. being re-done to comply with new standard.
SE-EE-176 Labels are not size coded in a New standards for label hierarchical system. sizes are being followed. 4655 SKE-EE-172 SKE-EE-174 .
- SE-CE-176 Lack of labels for identifying System Demarcation lines systes designation. are being added.
4755 SKE-EE-172 SKE-EE-174 SKE-EE-176 Number of graduations between New scales are being nebered merkings on scales added. 4855 exceed the maxims of nine. l l Indicators not scaled with stb- New scales are being divisions in decimal multiples added. 455 of 1, 2 or 5. ( Reacts: N de Switch rasquires i excessive force to operate. ! 5455 l Indicator information not New scales are being easily read. added. 55SS l Pointer covers recorder scale New scales are being merking. added. 5655 O ( i i l i i L
DC8 65- W F.5 PNL 9-5 HED CORRECTIONS (continued) PANEL /BOAfD 9-5 VERIFICATION /VALICATION $1CN-CFF 94EET CORE TEAM RESOLUTION SIGN T F - EW HED CIHiENTS DESCRIPTION CDMMENTS HED# Y/N VERIT. VALID. Control Rod Drive Water Delta New scales are being Pressure Cage has non-standard installed. 91 increments. (Press. Ind. CRD-PDI-303.) Lack of panel function identi- Labels are being added. fication label. 1755 , Alarm response system ret Devices are being consistent among panels. relocated. 2355 SKE-CE-174
^
Controls and di, plays not Devices are being grouped in functional or relocated. l l 4055 sequential relationship. ! SKE-EE-174 SE-EE-176 Use of colors not consistently Labels and Demarcation l lines are being standard-spplied on panel. l 4155 ized. SE-EE-172, SKE.rt-174, SKE-EE-176 Related groups of controls or Demarcation lines are displays not set off by being installed. l ! 42SS demarcation lines. SKE-EE-172 l SKE-EE-174 l SKE-EE-176 Controls located outside Devices are being recommended zones. relocated. I 43SS SKE-EE-176 , Existing 1 Eels are not clear New labels are being with respect to function or installed. 4455 intent. l 0 l l t
r DC# c_1m F.5 PNL 9-5 HED CORRECTIONS (continued) PAEL/ BOARD 9-5 ERIFICATION/ VALIDATION SICN-OFF SEET D b CORE TEAM RESOLUTION SIGN OFF . EW HED C04MENTS CCNMENTS HEDf DESCRIPTIGi Y/N VERIF. VALID. Indicators are not marked to Meter banding will be ' show normal reges of opere- done. 595 tion. See Step 3 In Acceptance Test Alarm points ar2 not identified Meter bending will be on the recorder scales. done. 195 - See Step 3 In Acceptance Test The displays sich reflect only " Demand Signal" demand signal are ret labeled Labels will be placed on 1235 accordingly. betels of controle. Intermediate range monitor Switch Enhancements are switches need color marking being M ded. improvements. See drawings: 10T SKE-EE-172, SE-EE-174, SKE-EE-176 Enhancements are being An APRM value of 2.55 at ths low end of the recorder scels added. 13T is difficult to read. The label merking of Group 1 Labels and Demarcation isolation reset switches needs are being added. 27T improvement. Sea SKE-EE-172 i The rod sequence control switch Labels and Domercation j are being udded. l label needs improvement. 28T See SKE-EE-174 Standby Liquid Control Tank An anber arrow is being Level indication la difficult p1rsed at 15 on indica-tor. 29T to read at the 15 level. O-
F.6 VBD-R HED CORRECTIONS WRIFICATION/ VALIDATION SIGN-OFF SiEET DC# 85-15L PANEL / BOARD R CORE TEAM l RESOLUTION SIGN 7 F - NEW DESCRIPTION CGKNTS HED CDMMENTS HED# VER IF. VALIO. Y/N No Plant Standard for Color CNS Human Factors Color 215 Coding. Coding has been developed and implemented. 4 Controllers requiring manuel Controllers are being operation not easily reached. relocated lower on panel. 555 Controller switches located 12" above max. limits. See drawing SNE-EE-216. (d/P Controllers: HV-DPIC-840,
- HV-OPIC-8158, HV-OPIC-835A.)
Indicators not marked to show Color Bending of indice-normal ranges of operatien. tors will be implemented 645 (1. RX Bldg./ ATMOS Delta P Re- per Attactment B. corder, 2. QJed Temperature Meters for RHR Rooms, Core Sprey lboma ord HPCI Room.) Alors pointe not identified on Color Bandirq of indice-recorders. Lors will be implemented 1 855 rer Attachment B. (RX Bldg./ATHOS. Delte P Re-corder DPRC-835.) Recorder roles not marked to Color Bending of indice-show normel or abnormal ranges tors will be implemented
> of operations. per Attactment B.
955 .(1. RX Building / ATMOS Delte P Recorder DPRC-835. 2. Quad l Area Temperature >bters for ! RHR, CS and HPCI Systems.) l No physical distinctica between Control Coding will be l j handles. Coding by size, provided in accordance shape, or color is not being with CNS HFE Stenderde. 1135 used to identify switch by type of function. See SNE-EE-216. ( All fan switch handles on this panel should be phyelcelly dis-l' tinct from velve handles. Displays reflecting ely desenf See Label Change Table, signal not leeled accordingly. Attactwent. 1275 f OP Controllers OPIC-845, OPIC-835A&B, DPIC-940. O
- l. . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _
F.6 VBD-R HED CORRECTIONS (continued) OCf 85-15L
%ERIFICATION/VALICATION SIGN-OFF S4EET PANEL / BOARD R V
CDRE TEAM ESOLUTION SIGN OFF EW HED (EMMENTS DESCRIPTION C04MENTS HE0f V/N VERIF. VALID. Recorder reading at low-end of Nameplate misplaced, will scale not visible through be lowered. Scales will be cleaned, and recorder 1325 recorder window. (RX Building /ATM05 Delte P Re. will be lowered. corder OPR-835.) See drawing SKE-EE-216. Alarme not provided with Labeling will be rpplied alphanuneric code for prompt to Annmciator Penel 1495 response. Axis. . (Labeling of Axes.) Alarm response system not Standardized arrangement consistent among panels. of annmelator controls 1545 has been provided. ( Annunciator Response Buttons.) See SKE-EE-216. SC HVAC controls ed displays Enhancements are being f(' 667 not set off by demarcation lines.
.added.
See Drawing SKE-CE-216. Range (50-170F) of eres temp- Scales are being extended eroture indications for CS, and loops are being 67T RHR's and HPCI do not extend to recelibrated. emergency limits ( Alert signal 200F). Alare response system ret Standardized arrangement consistent among panels. ,of enn melator controls 2355 has been provided. ' See SKE-EE-216. Labels are not visually dis- See Label Change Table, l tinctive - red letters on black Attachment. 13355 b ackground. (SBGT Flow Controller Label, OPEC-8350.) Controller's height causes Controllers are being , difficulty in identifying mode relocated lower on panel.' 13555 positions. (d/P Controllers: HV-OPIC-840, See Drawing SkE-EE-216. HV-OPIC-8350, HV-0PIC-835A.) l ._'- . .- -_- -- .. . _ _ _ _ _ _ . - . _ _- . . . _ _ _ _
F.6 VBD-R HED CORRECT 10f15 (continued) ERIFICATION/ VALIDATION SIGN-OFF 94EET CC# 85-15L
. ' PANEL /80ARD R CDRE TEAM RESOLWION SIGN OFF MW HED# ESCRIPTION CD4K NTS HED CDMMENTS VERIF. VALID. Y/N Denareetion linea or mimice not Enhancemonta ere being used to enclose related dis. added.
pl ay s. (1. Quad fan switches and their See Drawing SKE-EE-216. feedback taperature indica-l 14855 tions - Reactor building not demarc ated. 2. No mimic for supply and exhaust fans ed , their asociated isolation
- valves.)
Related groups of controls or Visual chancements are
- . displays not set off by demar- being added to panel.
- cation lines.
149S5 See drawing SIC-EE-216. (1. Supply and exhaust fans,
. 2. Quad fans.)
I Analog controllers located : Controllers are being l above maximum limits. ' low red on ganel. 15055 (1. Analog Controllers HV-OPIC. 840, 2. Analog Controllers HV- See drawing SKE-EE-216. OPIC-8358, 3. Analog Controller i HV-OPIC-835A.) - Existing labels are not clear See Label Change Table. I with respect to (metion or 15155 intent. (Lebeling for Exhaust Fans:
- 1. F-R-1A, 1-EF-R-18, 2. F -T.
! 1A, 18, 1C, 10.) i Labels not consistently Label positione are being positioned above or below installed in scordance labels. with CNS HFE standards. (1. Primary Contairment Vent 15255 Switch 55/AD-R-1 A&18 2. Name- See drawing SKE-EE-216. ! plates for RX Bldg., Turbine . Generator 81dg., and Control Bldg. are located below their esacciated . switches.) e e
- O-3
' - . - . . - - . - , - . , - _ . - _ _ - - . - . , . , - . - - . _ . . _ _ _ - . ~ . _ _
F.6 VBD-R HED CORRECTIONS (continued) WRIFICATION/ VALIDATION SIGN-OFF SHEET DCf 85-15L PAEL/ BOARD R CDRE TEAM ESOLUTION SIGN OFF EW C09 TENTS HED COMMENTS HED# DESCRIPTION VERIF. VALID. Y/N Number of graduations betmeen New scales are installed. numbered merkings on scales exceed the maximun of nine. (Temperature Meters for 1. SE - Core Spray Pump Room, 2. T l 15355 Core Spray Pump Room, 3. SW R4R ' Ptap Room, 4. FM RtR Pump Room,
- 5. HPCI Pump Rom - Number of .
graduatioits between numerals is
- 15. )
Control switch positiori not New switch escutcheon clearly marked with permanent plates are being added. 1545S labeling. (Discharge Isolation Valvest 272MV, 258MV, 260MV.) Lack of labels for identifying See Label Change Table. system designation. O 1795S (Labels for Fan Switches for
- 1. 1 -EF-T-1 A , 2. 1EF-T-18, 3.1-EF-T-1C, 4.1EF-T-10 Do not identify switch function.
Inconsistent type style ed ; Filter Drive Controls are application of type size. being removed. (Nemeplates ed Lettering of 1845S Filter Drives fort H&V thits See SNE-EE-216. 1-HV-T-1 A, H&V Units 1-Hv T-18, H&V thits 1-HV-T-1C, H&V Units 1-HV-C-1 A. ) Controllers are being Controls located outside recommended zones. relocated lower on panel, (1. Indicating Controllers for temperature indicators I f 194SS RX Building, Control Building to remain in same and Turbine Building Delte P's position. located above Anthropometric I Limits 2. Quod Temperature See drawing SE-EE-216. Indiestors above Anthropometric Limits.) . k 'O l
-a s-- - - a -,. an n _ .s _ ,+
F.6 VBD-R HED CORRECTIONS (continued) ERIFICATION/ VALIDATION SIGN-OFF StEET DC# 8515L
, PAPEL/BOARO R CORE TEAM ..
K50LUTION SICN OFF EW CIMMENTS HED CD*ENTS HED# DESCRIPTION VERIF. VALID. Y/N Association of reisted controls Device is being relocat-not apparent through labeling, ed to achieve proximity mimics, demarcation lines. of related controle. 19555 (1. OPIC 8356 Controller should - be located cm RX Bldg. es- See SKE-EE-215 & 216 - esction of the Penel rather Component 10. than Control Bldg. Subsection.) Indicatore not scaled with sub- New indicator roles are divisions in decimal multiples being installed. of 1, 2 or 5. 19655 (Quod Temperature Meters for CS, RiR and HPCI Room, Scale ' Progreselon 50, 80. 110, 140,.) Labels are not size coded in a See Label Change Table, Hierarchical system Attac!went. i 34755 ' ' (Lebeling of H&V Fans and l Velv es.) , l l l l
.6 O
LO-APPENDIX G HED CORRECTIONS & SCHEDULE MASTER LIST (p. 1-110)
- 1. PANELS
- 2. PROCEDURES (p.111-113)
- 3. ENVIRONMENT & C0!EUNICATIONS (p.114-116)
- 4. MAINTENANCE & S*JRVEILLANCE (p.117)
AND TRAINING & MANNING O
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O O . O Page No. 16 01/22/87 ATTACHMENT 6 CNS DCRDR HED CORKCT10NS & SCEDULE RASTER LIST I. PAELS RECORD CATEGORY IMPLEMEN-ENHANCEMENT CECK- NURES- TATION NO. / LIST 0700 E5 PANEL / SCEDULE RESOLUTION / NOTES PRIORIif ACTION
- 10. ID. ROO!FICAT10N ITER SECil0N El MSCRIPi!0N FII 1998 REFUELING FAIRICATE E N AN W NCIATOR LE6ENO ENHMC. I C2.5 6.3.3.4 2155 9-3 ilLES MD ENSURE CONFORMMCE 287 A WUNCIATOR LEGEND TILE e N!!H SYSTEN M Sl6 NATION &
TERalNGLQ61 IS NOT CONSISTENT CONTROLS LAKLING. NITN THE INPUI SIGNR FUNCTION. SPLli HIGH-PRIORITY pulil-INPUT 9-3 M SIGN N00. !! FII 1988 REFUELIN6 C2.7 6.3.3.4 2255 RMMS 10 SINGLE-INPUT RARMS OR 298 NULilPLE CH0!CE INDICATIONS e PROVIE REFLASHIN6 CAPAgilliY IN USES ON RARM TILES. ACCORDMCE NITH THE RULil-INPUT EMR STURY FOR CNS CONTROL R00R. I CORRECTION 1986 REFUELIN6 *COMBIE WITH ED 575 FOR N/A 6.5.2.3 31 9-3 L 9-4 ENHMC. PC-PR-IA, MD HED 2655 FOR 179 FRONT PANELS PRinMY RADE CONTAINnENT P E SS. RECORDERS PC-PR-il. NEED 10 I E NTIFT NORn R/0FF NORMAL BAN 6E OF OPERATION. FII 1998 REFUELIN6 INSTEL HPCI MI RCIC SYSTEN M SIGN N08. 11 N/A 6.5.1.1 15T 9-3 & 9-4 STMT EMRS IN THE EMMS BOIES 191 HPCI MO KIC SYSTEN STMi e AIOVE HPCI ANB RCIC SUBSYSTEN R ARMS E EM D. EMR UNii COULO K A00E0 TO { EITHER OF THE EllSTING SYSTER 4 FLON LOOP OR TURBINE SPEED LO 10 PERFORM SUCH FUNCTION. 1 INSTEL 1988 REFUELIN6 INTEGRATE NiiH R6 1.97 NATER 9-3 & 9-4 M IEN MOD. I 194 RPV NIE RANGE NATER LEVEL N/A 6.5.I.! Igi RECORER EEVEL INSTRUNENTATION. RECORK f K SI6N RED'15: RANGE -150 TO + j TEEND !!ECORDING NOT AVAILABLE. 60 IN, ACC. 6.51. OPERAIlltif l RED'TS: R6 1.97 INSTRUMENTAT10N CATE60RY 1. M S!6N IS TO MEET CNS HF EN61EERING STDS FOR l VISU R DISPLAYS. l
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V O O Page No. 21 01/21/87 AllACHMENT 6 CNS DCRDR HED CORRECTIONS & SCE DULE MASTER LIST
- l. PANELS RECORD ENHANCEMENT CATE60Rf IMPLEMEN-NO. CHECK- NUREG-LIST 0700 HED PANEL / / TATION PODIFICAll0N PRIORiff E1102 SCEDULE ESOLUTION/NTES HES MSCRIPi!DN 11EM SEC110N 10. 10.
3 CORREtil0N 1986 REFUELING REPL EE SC E E IN ECORDANCE UllH 299 INDICATORS NOT SCRED NITH B2.13 6.5.1.5 3355 9-4 ENHANC MDE ENS NF STANDARDS AND NUREE 0700 l SUSDIVISIONS IN DECIME EUIMLIES. i MULTIPLES OF I, 2 DR 5. A CORRECTION 1986 REFUELING EIMIE RECORKR AND MIERMINE B2.4, 6.5.4.1, 3455 9-4 ENHMCEMENT 300 PROCESS UNilS INFORMAT10N N01 COMPLIANCE OF RECORM R DISPLAYEB MADE EASILY READ 582.1 6.5.4.2, INFORMAT10N N!iH CNS HF (SEE STMDARDS MD NURES 0700. COMENTS PROCESS UNIIS MY K PLEED ON 1 FACE OF RECORE R. CORRECTION 1986 REFUELING REPL EE POINTER OR MODIFT SCALE W POINTER COVERS RECORDER SCEE B3.1 6.5.2.2, 3555 9-4 EMAE A MADE MARKING 6.5.4.1, SEE COMMENTS 11 FII 1988 REFUELING SPLli HIGH-PRIORiiY MULTI-INPUT C2.7 6.3.3.4, 3655 9-4 DESIGN MOD.
*302 MUL11PLE CHOICE INDICA 110NS EARMS TO SINGLE-INPUT RARMS OR USED DN ALARM ilLES. SEE PROVIDE REFLASHING CAPAB!llif, COMENTS IN ECORDANCE NiiH THE MULil-INPUT R ARM STUDY FOR CNS CONTROL ROOM.
CORRECTION 1986 REFUELING REPLEE CHART PAPER 303 COMBINED LINEAR AND NONLINEAR SBl.2 6.5.1.5, 375S 9-4 ENHANC I MADE SCALES ARE USED ON THE SAME SEE RECORER PAPER. COMENTS FII 1988 REFUELING INTE6 RATE UlTH HED 2755 IN Cl.1 6.3.3.3 3BSS 9-4 KSI6N M00. 11 304 ANNUNCIATORS N01 GROUPED RELOCAllNG ALARM MO ALARM NiiHIN A MUNCIATOR 801 BY (SEE BYPASS SELECTOR SNITCH 10 THE N SPECIFIC SYSTEM. MISCICOM SUBSECTION OF THE PANEL. MENTSI
O O O Page No. 22 01/21/87 ATIACHMENT E CMS DCRDR HEB CORRECTIONS & SCE DULE RASTER LIST
- 1. PANELS RECORD ENHANCFRENT CATE60RY IMPLEMEN-NO. CHECK- NURE6-LIST 0700 HED PAEL / / TATION F310RiiY Atil0N SCHE'JULE RESOLuil0NIN0iES El MSCRIPil04 11ER SECTION 10. lir. MODIFICATION CORREti!DN 1996 REFUELING INTEGRATE NITH HEB 24SS n 25S5.
305 ASSOCIAT10N OF FEEDBACK 10 A3.7, 6.4.2.2, 39SS 1-4 DESI6N M00. 11 MOE RELOCATE CONTROLS & INDICAll0NS RELATED CONTROLS NOT APPARENT SA3 6.5.1.6, TO PROVIK E CESSARY THROUGH LABELIN6, RIMICS, 6.6.6.44 M MRTICATION OF SUBJOUPS. E MARCAi!ON LINES. C2.2 6.3.3.4, 1905S 9-4 ENHANC. A FII Mf'85 THE ANNUNCIATOR TILE IN OUESTION 455 ALARM NINDON TILES ARE SHOULI BE ENHANCED TO CORRECT INCONSISTENT IN TYPE S!!E 6.3.3.5, K FICIENCIES IN AGREEMENT MliH SEE SPECIFIC CNS STA110N STANDARDS COMMENTS AND NURES-0700 SU! KLINES. 182 FRONT PANEL METER INDICATION N/A 6.5.1.1 61 9-4/SPDS OTHER M00. II ABO 10 1988 REFUELING METER IN0! Call 0NS AYAILABLE ON PMIS/SPDS BACK PANELS 9-10 % 9-02. FOR MAIN STEAR RADIATION NOT AVAILABLE. PLACE ON 1988 REFUELING PLACE ALL E0Ps TNO-DIMENSIONAL 227 THE '2D' PC LinliS OF HEAT N/A 6.5.1.1, Sti 9-4/SPDS "THER MOD. 11 SPOS PC LIMITS ON SPDS CAPACITY TEMP. LIMIT VERSUS SEE SP NL REQUIRES PERFORRING COMMENTS CALCULA1[0NS. INCICATIONS FOR INPUT PARAMETERS NOT IN CLOSE PR0llRITY.
O O O Page No. 23 01/21/81 ATTEHMENT S CNS DERDR HED CORRECTIONS & SCEDULE MASTER LIST
- 1. PAELS 4
CATEGORY IMPLEEN-RECORD ENHANCEMENT CECK- NUES- / TAT 10N NO. ED PANEL / ESoluil0NINOTES LiSi 0700 PRIOR!if ACTION SCHEDULE ID. ID. MODIFICATION ITEM SECTION HE8 DESCRIPT!DN CORRECil0N 1986 REFUELING NORMAL RAN6ES OF OPERAi!ON M0 ENHAE. I 82.1 6.5.2.3 595 9-5 ENTRY CONBli10NS TO EERGEEIES, 59 INCICAIDRS NOT MARKED TO SHON MDE (SEE AS SPFCIFIED BY CNS EDP'S, WILL NOR ML RAN6ES OF OPERATION. MISC /CDM K MAM E9 ON PRIMARY INDICA 10RS. MENTS) I LORRECT10N 1986 REFUELING INTEGRATE WITH E9 595. 795 9-5 ENHAE. 83.3 6.5.2.3 MDE IN NTIFY NORMAL RA85CS OF 79 ALARM PolNIS NOT IDENTIFIED ON OPERAIl0N & ENTRY 10 EMER6EKY RECORKRS. ON RECORKR. VERIFY THAT ALARM , PolNTS ARE KLON OR AT THE EER6EEY MARKING. CORRECil0E 1986 KFUELING LASEL SC Eid OR CONTA0LLIA filft ENHMC. A 581.3 6.5.1.1, 1235 1-5 TO HISHLIGHT M M ND INDICAll0NS. 123 OISPLAYS REFLECTING ONLY MADE 6.6.3.1 DERMD SIGNAL NOT LABELED ACCORDINGLY. NO Eil0N NONE A MINOR DISCREPAEY. KARM GTER M00. til Cl.! 6.3.3.3 1355 9-5 BOIES ARE A0J EENT. l 135 ANNUNCIATORS NOT SROUPED (SEE i WITHIN ANNUNCIA10R BOI BY MISC /COM SPECIFIC SYSTEM. MENTS)
- BISCREPMCY COULB NOT K 6.3.3.3 13T5 1-5 01 ER M00. !!! NO Eil0N NONE VERIFIEO. THE INFORMATION i Cl.3 131 NARNING AND DIA6MOSilt R ARMS ALARMS ON TH15 PAE L ARE ALSO NOT SE6RESATED FROM CONSI ERED WARNING ANO INFORMATION AND ADVISORY DIA6NOSTIC KARMS.
l ALARMS. FAIR!CATE E N AMUNCIATOR LE E E ! 9-5 ENHANC. I Fl! 1988 REFUELIN6 C2.5 6.3.3.4 1405 TILES AND ENSURE CONFORMMCE 140 ANNUNCIATOR LE6END I!LE (SEE WITH SYSTEM MSI6NAll0N & TERMIN0LD6Y 15 NOT CONSISTENT MISC /CDM CONTROLS LABELING. WITH THE INPUT Sl6NAL ENTSI FUNCTION.
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O O O r Page No. 27 Dl/21/8T , AllACHMENT 6 CNS DCRDR HED CORREC110NS & SCHEDULE MASTER LIST
- 1. PANELS RECORD ENHANCEMENT CATEGORY IMPLEMEN-NO. CHECK- NURES-LIST 0700 HED PANEL / / TATION PRIORiiY ACTION SCHEDULE RESOLuil0NIN0TES HER M SCRIPil0N ITEM SECTION ID. ID. MODIFICAi!DN CORRECTION 1986 REFUELING INTE6AATE NiiH HED 215 FOR 30T USE OF COLORS NOT CONSISTENTLY A4.1, 6.5.1.6, 4155 9-5 ENHMC. B MADE EVELOPMENT OF HUMM FACTOR APPLIED ON PANEL. A4.2 6.5.2.3, PLMT SIDS FOR THE CONTROL ROOM.
6.6.6 e PERFORM ENHANCEMENT TECHW120ES IN FORMS OF DEMARCATION MIMICS, IGNE MARKING OF DISPLAYS, & FUNCTIONAL CDDING OF CONTROLS & DISPLAYS Ulill!!N6 SPEC COLCR CODING. A CORRECTION 1986 REFUELING PROVIDE FUNCTIONAL DEMARCAi!ON 308 RELATED SROUPS OF CONTROLS OR A2.3, 6.6.6.1, 42S5 9-5 ENHANC. MADE 10 SET OFF FUNC110NALLY RELATED DISPLAYS NOT SET OFF BY SA3 6.6.6.2, SROUPS OF CONTROLS AND DISPLAYS. KRARCAi!0N LINES. 6.8.1.3 e CORRECTIM 1986 REFUELINS INTEGRATE NITH HED 405S. < 309 CONTROLS LOCATED OUTSIDE Al.1, 6.1.2 435S 9-5 K S16N M00. 11 MADE RELOCATE STARTUP FEEDNATER RECOMMENDED ZONES. Bl.1 CONTROLLERS IN ACCORDANCE NITH NURE6 0700 ANTHROP 0 METRIC LIMITS 20FSRECOMMENDATIONSFORPANEL
. MODIFICAT10NS.
CORRECTION 1986 REFUELING FABRICATE EN LAKLS CONSISTENT 310 EllSI!N6 LABELS ARE NOT CLEAR A5.10 6.6.2.1, 4455 1-5 ,ENHANC. A l MADE N/LA ELING THROU6HOUT THE CTRL N!!H RESPECT TO FUNCil0N OR 6.6.3.1 l SEE RM. i INTENT. COMENT6 CORRECTION 1986 REFUELINS PLACE LABELS ACCORDING TO CNS HF 311 LA ELS AND LESEND PLATES, NOT A5.ll 6.6.2.1 4555 9-5 ENHMC. A MADE SIMDARDS - UllLi!E HIERARCHICAL CONSISTENTLY POSlil0NED ABOVE LABELING SCHEME TO DISi!NSUISH DR WLON DEVICES. BEINEEN COMPONENT AND SUBSYSTEM LAMLING.
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O O O Page No. 29 01/26/87 ATTACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS RECORD ENHANCEMENT CATE60RY IMPLEMEN-ND. CHECK- NUREG-LIST 0700 HED PANEL / / tai!ON PRIORITY ACTION SCHEDULE RESOLUT!0N/ NOTES HED DESCRIPTION ITER SECTION 10. 10. MODIFICATIDN 318 ANNUNCIATOR NOMENCLATURE, C2.1 6.3.3.4 51SS 9-5 ENHANC. A FII 1988 REFUCLING FABRICATE NEW ANNUNCIATOR LE6END
- i!LES WHERE APPLICABLE IN ACRONYMS, OR ABBREVIAi!ONS ARE (SEE ACCORDANCE N/ STATION HUMAN NOT STANDARD!!ED. COMENTS FACIDR STDS & NURE6 0700 1
6UIDELINES. ENSURE THE UPDATE OF APPROPRIATE DW65 AND PROCEDURES. ENSURE OPERATOR AWARENESS OF ANY CHANSES IN TERMINOLO6Y USED. 319 ANNUNCIATORS WITH Muli!PLE C2.6 6.3.1.2 52SS 9-5 GTHER MOD !!! NO ACTION NONE PLACEMENT OF SETPOINTS ON WINDOWS IS NOT NECESSARY. THEY TRIP LEVELS NOT PROVIDED WITH ARE EASILY FOUND IN ALARM PARAMETER SETPOINTS. PROCEDURES LOCATED AT PANELS. FII 1988 REFUELING SPLli HI6H-PRIORITY MULTI-INPUT 320 MULilPLE CHOICE INDICATICNS C2.7 6.3.3.4, 53SS 9-5 DESI6N M00. 11 ALARMS TO SINGLE-!NPUT ALARMS OR USED ON ALARM TILES. SEE PROVIDE REFLASHING CAPABILITY IN COMENTS ACCORDANCE WITH THE MULil-INPUT ALARM STUDY FOR CNS CONTROL ROOM. B5.5, 6.4.4. 5455 9-5 DESIGN MOD !! Fl! 1989 EFUELING FOLLOW UP WITH THE bur OWNER'S
- 321 REACTOR MODE SWITCH REQUIRES SROUP COMliTEE THAT IS EIEESSIVE FORCE TO OPERATE. 87.6 ADDRESSING REACTOR MODE SWITCH DESI6N. IMPLEMENT DESI6N CHAN6ES WHEN AVAILABLE.
CORRECTION 1986 REFUELING PROVIDE MATRl! IDENilFICAil0N 322 INDICATOR INFORMATION NOT B2.4 6.5.1.1, 5555 9-5 ENHANC. A MADE LABELS AND All6NMENT CUES TO EASILY READ. 6.5.2.2, FACILITATE PROPER IDENTIFICATION SEE OF INDICATIN6 Ll6 HTS. COMENTS
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O. U , V Page No. 33 01/221BT ATTACHMENT S CNS KRDR HED CORRECT 10NS 6 SCHEDULE MASTER LIST
!. PMELS CATE60RY IMPLEMEN-RECORD ENHAKEENT CHECK- NUREG- TATION NO. PMEL / /
LIST - 0100 HED PRIORITY ACTION SCHEDULE RESOLUTIONINOTES ID. ID. MODIFICAT10N ITEM SECTION HER DESCRIPil0N CORRECTION 1986 REFUEllN6 EIMINE RECORKR MD KTERMINE ENHANC. A 582.1 6.5.4.1, 132S VBD-R MADE THE CAUSE OF OBSTRUCTION.
- 132 RECORE R READING AT LON-END OF 6.5.4.2, PERFORM NECESSARY CORRECTIONS l
SCALE NOT VISIBLE THROUGH (SEE ENSURE SCALE VALUES ME VIStBLE RECORDER WINDON. COMMENTS THROUGH RECOR E R NINDON. I Fl! 1988 REFUELINE STMDMDlIE RMM ESPONSE DESIGN M00. 11 6.3.4.2 1545 VBD-R SYSTEMS AMONG EL PMELS TO THE C5.5 154 ALARM RESPONSE SYSTEM NOT TRIAN6ULM ARRAN6EMENT OF CONSISTENT AMONG PMELS. CONTROLS USEl DN BOP PANELS.
'ACKNONLEDGE' MD 'ESEi* P8'S ON TOP RON, AND 'iES1* DN B0iiOM RON. SEE CNS HF STAN0MDS.
elNTEGRATE NIIH HED 14855. I CORRECTION 1986 K FUELING VBD-R ENHANC. N/A 6.6.6.2 66T MADE VID-R SHOULD K E MANCED IN 242 SC HVAC CONTROLS AND DISPLAYS TERMS OF KMRCATION LINES NOT SET OFF BY DEMRCAllDN IM NilF11N6 FUNCTIONR LY RELAT LIES. CONTROLS AND DISPLAYS. CHANGE SHOULD K PERFORMEB IN AGREE
. NiiH SPECIFlc CNS STAi!ON STMDMDS MD NUKE 0100 60!KLINES.
REVIEW E!!$ TING HARDWARE TO I CDRRECTION 1986 REFUELING 6.5.1.1, VBD-R DESIGN M00. N/A 67T RADE DETERMINE li IS CAPABLE OF BEIN 243 RANGE 150-170F) DF AREA 6.5.1.2, CALIBRATED 10 M W DATA (200F + TEMPERATURE INDICA 110NS FOR SEE 2011. IF THIS IS TRUE ONLY CS, RHR's, AND HPCI DO NOT j COMMENTS METER SCALES WILL BE REPLACEI. EliEND 10 EMERGENCY LIMITS ' IF NOT, .EN A COMPLETE DESIM (ALERT $16hAL 200FI CHAN6E WILL K REQUIRED. 9
~
O O O Page No. 34 D1/22/87 AliACHRENT 6 CNS DCRDR HED CORRECT!0NS & SCHEDULE RASTER LIST
- 1. PANELS RECORD IMPLEMEN-ENHANCEMENT CATE60RY NO.
CHECK- NURE6-LIST 0700 ED PANEL / / TATION ACT10N SCEDULE RESOLUT10NIN0TES ID. 10. MODIFICATION PR10R11Y HED DESCRIPTION ITER SECil0N NONE INBlVIDUAL FAN FLOW NOT NEEDED, OTHER MOD. Ill NO AC110N 244 DIRECT INDICAll0N OF SC HVAC N/A 6.5.1.1 68T VBD-R AS TOIAL FANS ElHAUST FLOW IS FAN FLOW NOT AVAILABLE. INDICATED ON FR-4003 AND VBD-E. B CORREtilDN 1986 REFUELING REPLACE EllSilNG LABEL WITH A A5.8 6.6.4.1 13355 VBD-R EMANC. 399 LAM LS ARE NOT VISUALLY MADE E W LAE L THAT IS CONSISTENT DISTINCTIVE - RED LETTERS ON W/ LABELING THROU6HOUT THE CTRL BLACK BACK6ROUND. R00R. INTEGRATE NITH HED 55SS IN Bl.3 6.1.2.2 135SS VBD-R DESIGN MOD !! CORRECTION 1986 REFUELING 401 CONTROLLER'S HEIGHT CAUSES MADE RELDCATING THE CONTROLLERS. DIFFICULIV IN I E NTIFYIN6 RODE 1 POSil10NS. i A CORRECT 10N 1986 REFUELIN6 PROVIDE RIMICS THAT COMECT 414 DEMARCAll0N LINES OR MIMICS A2.2 6.6.6.1, 148S5 VBD-R ENHANC. RELATED 6ROUPS, IN ACCORDANCE l 6.6.6.2, MADE NOT USED TO ENCLOSE RELATED WITH CNS HF SIMDARDS. DISPLAYS. 6.8.1.3 e . B CORRECTION 1986 REFUELING INTE6 RATE NITH HED 14955. 415 RELATED EROUPS OF CONTROLS OR A2.3 6.6.6.1, 1495S VBD-R ENHANC. MADE PROVIDE FUNCTIONAL DEMARCATION DISPLAYS NOT SET OFF BY 6.6.6.2, TO SET OFF FUNCTIONALLY RELATED DEMARCAT10N LINES. 6.8.1.3 6ROUPS OF CONTROLS AND DISPLAYS. 8 , i
!! CORRECTION 1986 REFUELING INTE6 RATE WITH E D 555.
416 ANALOG CONTROLLERS LOCATED A3.6 6.1.2 1505S VBD-R DESIGN MOD. MADE RELOCATE CONTROL AND ASSOCIATED AB0VE MAI!nUR LIMITS. DISPLAYS IN ACCDRDANCE WITH NURE6-0700 MTHROP0 METRIC LintiS. A CORRECTION 1986 REFUELIN6 FABRICATE NEW LABELS CONSISTENT 417 EIISilN6 LAELS ARE NOT CLEAR A5.10 6.6.2.1, 151SS VBD-R ENHANC. MADE W/ LABELING THROUGHOUT THE CTRL N!IH RESPECT TO FUNCT10N OR 6.6.3.1 Rn. CAUTION RUST BE EIERCISED SEE INTENT. TO ENSURE NO BISCREPANCIES ARE COMMENTS 6ENERATEB,
p fy --- O- O O Page No. 35 01/22/B7 ATTACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS I l
RECORD ENHANCEMENT CATE60RY IMPLEMEN-NO. CHECK- NURES-LIST 0700 HED PANEL / / tai!0N ACil0N SCHEDULE RESOLUT10NIN0TES
- 10. ID. MODIFICATION PRIORiiY ITEM SECT 10N HED DESCRIPT!0N 3 00RRECT10N 1986 REFUELING RELOCATE EIISTING LABELS IN 418 LABELS NOT CONSISTENTLY A5.Il 6.6.2.1, 152S5 VBD-R ENHANC.
MADE COMPLIANCE WITH SPECIFIC STATION 1 SEE POSITIONED ABOVE OR BELON STMDARDS. l LABELS. COMMENTS S CORRECil0N 1986 REFUELING REPL EE SCALES PER CNS 419 NUMBER OF GRADUAi!ONS BEINEEN B2.12 6.5.2.5 15355 VBD-R ENHANC. MADE SIMDARDS. NUME RED MARKINGS ON SCALES (SEE MISC /COM EXCEED THE MAIIMUM OF NINE. MENTSI A CORRECT 10N 1986 REFUELING FABRICATE NEW LE6END LABELS 95.2 6.6.3.8 1545S VBD-R ENHANC. 420 CONTROL SNliCH POSil10N NOT MADE WHICH REFLECT CONTROL POSITION. CLEARLY MARKED WITH PERMANENT THE NEW LABELS SHOULD BE LABELING. CONSISTENT WITH EllSilN6 LABELS IN TERMS OF COLOR, LETTER S!!E, TERMINGLOGY, SilE AND LOCAil0N. EL LABELS SHOULD BE PERMMENTLY ATTACHED. C2.1 6.3.3.4 15555 VBD-R ENHANC. A Fl! 1988 REFUELING FAIRICATE NEW ANNUNCIATOR LE6END 421 ANNUNCIATOR NOMENCLATURE, ilLES NHERE APPLICABLE IN ACRONYMS, OR ABBREVIATIONS ARE ISEE ACCORDANCE MISTATION HUMAN N0i STANDARDilEB. COMMENTS
. FACTOR STDS & NURES 0700 I
SUIDELINES. ENSURE THE UPDATE OF APPROPRIATE DN6S AND PROCEDURES. ENSURE OPERATOR ANARENESS OF MY CHANGES IN TERMIN0 LOGY USED. II Fl! 1988 REFUELING SPLli H16H-PR10RITV MULTI-!NPUT C2.7 6.3.3.4, 156SS VBB-R DESIGN N00. 422 HULTIPLE CHalCE INDICATIONS R ARMS TO SIN 6LE-INPUT R ARMS OR SEE USED ON ALARM IILES. PROVIDE REFLASHING CAPABILITY, COMMENTS IN ACCORDMCE NITH THE MULil-INPUT R ARM STUDY FOR CNS CONTROL ROOM.
O O . O Page No. 36 0!!22181 ATTACHMENT 6 CNS DCRDR HED CORREtil0NS & SCHEDULE MASTER LIST
- 1. PANELS RECORD CATEGORY IMPLEMEN-ENHANCEMENT CHECK- NURE6-NO.
HED PAKL / / Tail 0N LIST 0700 SCHEDULE RESOLUTION / NOTES PRIORiff AC110N
- 10. 10. MODIFICA110N ITEN SECT 10N HER ESCRIPil0N ALARM SETPOINTS ARE INNilFIEB 6.3.1.2, 15755 VBB-R OTHER MOD III NO ACT10N NONE ON ALARM PROCEDUE S, L K ATED ON C2.6 423 MNUNCIATORS NiiH MULTIPLE SEE PANELS.
TRIP LEVELS NOT PROVIM D WITH
- COMMENTS PARAMETER SEIPOINTS.
i INTE6 RATE NITH HED 555. 6.1.2 19455 VID-R DESISN N00. Il CORRECTION 1986 REFUELIN6 A1.1 MK. RELOCATE CONTROLS AND ASSOCIATE 439 CONTROLS LOCATED DUTSIDE l BISPLAiS IN ECOR9MCE WITH REConNENDED IONES NURE6 0700 PNTHROP0NETRIC LintiS. INTE6 RATE WITH HED 19455 FOR 6.4.2.2, 1955S VBD-R DESIGN M00. Il CORRECTION 1996 REFUELINS A3.7, RELOCATING DPIC 8358 CONTROLLER 440 ASSOCIAll0N OF FEEtthCK 10 - MADE 6.5.1.6, ON Rt ELD 6 SUBSECTION OF FANEL. RELATED CONTROLS NOT APPARENT SA3 THROU6H LABELING, MIMICS, 6.6.6.4 PROVIDE KCESSARY ASSOCIATION O i CONTROLS MD FEEDSACK. DEMARCAT10N LINES. CORREti10N 1986 REFUELINS FABRICATE E N LAKLS I N NilFYINS ENHANC. A A5.3 6.6.1.1, 179S5 VBD-R SYSTEM DESI6 MTION. CORRECT 445 LACK OF LA E LS FOR I N NilFVING RADE 6.6.3.1, LAELS IKullFICAi!0N. ETSTER DES 16 MAT 10N. SEE ConRENTS ! CORRECTION 1986 REFUEllNS STMDARDITE PAKL LAKLINS IN ENME. A AS.6 6.6.4.1, 19455 VBD-R KCORDAEE NiiH CNS HF STMDARD 450 IKONSISTENT TYPE STYLE AND EDE l SEE MD NURE6 0700 SUlKLINES. APPLICAi!ON OF TYPE SIZE. CDMMENTS CORRECTION 1996 REFUELINGREPLACE SCALE IN Act0RDANCE WI ENHANC. I B2.!! 6.5.1.5 1965S VBB-R CNS HF STANDARDS MD NURES 0700 45B INDICATORS NOT SLALED N!iH MADE SUIDIVISIONS IN DECIMAL SUlKLINES. MILT!PLES OF 1, 2 DR 5. ENHANC. 3 CORRECTION 1986 REFIELING INTE6 RATE WITH E D 555. B2.4 6.5.1.1, B2SS VBD-R LONERING THE CONTROLLERS NILL 460 INDICATOR INFORMATION NOT MADE 6.5.2.2, RESOLVE THIS HED. EASILY READ - POINTER COVERS SEE SCALE NUMERALS. COMENil
O o O Page No. 37 01/22/B7 ATTACHMENT 6 CNS BCROR HED CORRECTIONS & SCHEDULE MSTER LIST
- 1. PANELS RECORD CATEGORY IMPLEMEN-ENHANCEMENT CHECK- NRES-
- NO.
0700 ED PANEL / / Tall 0N LIST SCHEDULE KSOLull0NINDIES i MODIFICA110N PR10 Riff ACil0N ITER SECTIDW ID. 10. HED K SCRIPTION f FII 1988 REFUELINE THE Am uuCIATOR TILE IN 00ESil0N 1 ENHANC. 8 C2.2 6.3.3.4, 197SS VBO-R SHOULB E ENHANCED TO CORRECT 470 ALARR NINDON TILES ARE 6.3.3.5, KFICIEEIES IN AGREEMENT ulTH i IKMSISTENT IN TVPE SIZE. SEE SPECIFIC CNS STAil0N STANDARDS ConMENTS ANI NUREE-0700 SUIKLIES. CORRECil0N 1986 REFUELINS FABRICATE EN LAELING ENHANC. A ' A5.7 6.6.3.2, 347S5 VBB-R CONSISTENT N/LAK LING THROU6HOUT 471 LAKLS ARE NOT SilE CODED IN A RADE 6.6.3.3, THE CTRL R00R. HIERARCHICAL SYSTER 6.6.3.4 i s i
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- 23
O O O i Page No. 40 01/22187 ATTACHRENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE M STER LIST
- 1. PANELS RECtCD ENHANCEMENT CATEGORY IMPLEMEN-NO. CHECK- NURE6-LIST 0700 ED PANEL / / TATION PRIORiif ACTION SCHEDULE RESOLUT10NINOTES ITER SECTION ID. 10. MODIFICATION HED DESCRIPTION SA3 6.4.2.2, 5tS 9-02 ENHANC. 11 Fl! 1988 REFUELING INTEGRATE NITH ED 3175S IN 51 ASSOCIATION OF FEEDSACK TO RELOCAi!NG RECORERS UliH THEIR RELATED CONTROLS NOT APPARENT 6.5.I.6, ASSOCIATED CONTROLS THROUGH LAE LING, MIMICS, 6.6.6.4 a
MRARCAi!Du LIES. 581.4 6.5.1.4 1295 9-02 ENHANC. I Fl! 1988 REFUELIN6 INNilFY PROCESS UNITS. 129 PROCESS UNiiS AND MULi! PLIERS NOT SPECIFIED. CORRECil0N MAY '85 *RECORM R LA8ELES. 183 RECORM R IDENTIFICA110N LABEL N/A 6.6.1.1, 7T 9-02 ENHANC. B MDEe I MISSING. 6.6.3.1 8 FII 1988 REFUELING IENilFY PROCESS UNITS ON FACE 236 PROCESS UNITS NOT IDENTIFIED N/A 6.5.1.4 60i 9-02 ENHANC. f OF RECORKR. SARE DISCREPANCY ! DN SC AREA RADIAi!ON RECOR E R. NOTED IN CR SURVEY (NED 12951. ACTION MAV'85 6CHARI PAPER Ne5 E PLACED. 237 CHARI PAPER OF SC AREA N/A 6.5.4.1 6ti 9-02 ENHANC. A f COMPLETEDe RADIAT!DN RECORDER DOES NOT I MICH RECORKR SCALE. N/A 6.5.4.1, 62T 1-02 DEBISN M00. 11 Fl! 1988 REFUELING TO ALLEVIATE THIS HED N!LL 234 RECORMRCONTAINSEXCES8IVE PROBABLY REQUIRE REDUCING THE
- PLOTS - NO SINGLE TREND CAN 6.5.4.2, .
N MBER OF INPUTS TO A RECORE R j EASILY BE DISTIN6UISHASLE. DY PROVIDING ADDITIOML ,i RECORDERS. IF SCALE IS A l PROBLER, IT IS POSSilLE TO PURCHASE SPLli SCALE RECORM RS. i ' N/A 6.1.2 70T 9-02 DESIGN M00. 11 Fl! 1988 REFUELING INTE6 RATE WITH ED 317SS FOR 246 0FF-6AS VENT PIPE INDICAi!D11 PERFORRING THE MS16N METERS LOCATED 24' FROR THE .i n0DIFICAil0NS 10 IMPROVE THE 1 FLOOR. LOCATION OF THE RECORKR. p
O O O Page No. 41 01/22/87 ATTACHMENT 6 CNS K RDR HED CORRECil0NS & SCHEDULE MASTER LIST
- 1. PANELS RECORD ENHANCEMENT CATEGORY IMPLEMEN-NO. CHECK- NURE6-LIST 0700 HED PAEL / / TATION PRIORITY ACilDN SCHEDULE RESOLUTIONINOTES ITEM SECT 10N 10. 10. MODIFICAi!DN ED DESCRIPIIDN N/A 6.6.2.1 71T 9-02 ENHANC. I Fl! 1988 REFUELING RELOCATE LAKLS IN ACCORDMCE 247 LOCA110N OF FUNCTIONAL LABCLS NITH CNS HF SIMDARDS.
OF OFF-6AS VENT PIPE INDICATION METERS ARE INCONSISTENT (50MEi!MES ABOVF OR KLON ETERI. , N/A 6.5.2.2 72T 9-02 ENHANC. 8 FII 1988 REFUELING RAISE SCALE OR K PLACE POINTER. 248 0FF-6AS VENT PIPE RECORDER SAME DISCREPANCY INNTIFIEI IN POINTER COVERS READING ON CR SURVEY (E D 318SSI. SCALE. Fl! 1988 REFUELING kEVIEN OF THE EI!SilN6 LA KLS 249 INCONSISTENT FUNCTIONAL N/A 6.6.3.6, 73i 9-02 ENHANC. I SHOULD DE PERFORED TO KTERMINE LABELIN6 K INEEN METER AND 6.6.3.1, NHICH LAK L K ST CONVEYS THE RECOR K R FOR SERVICE NATER INTENKD E MIN 6. CORREC110NS RADIATION MONITOR. SHOULD BE MADE IN A6REEMENT NITH THE CNS CTRL HF STANDARDS MD IRPLEENTAil0N 6UIDELINES. N/A 6.5.2.2 74T 9-02 ENHANC. I Fl! 1988 REFUELING SAME E D IDENilFIED IN CR SURVET 250 SERVICE NATER RADIATION (ED 31855). RECORDER PolNTER COVERS READING ON SCALE. A4.1 6.5.1.6, 15955 9-02 ENHAC. B Fl! 1988 REFUELING INTE6 RATE NITH E D 21S FOR 425 USE OF COLORS NOT CONSISTENTLY KVELOPMENT OF HUMAN FACIOR APPLIED ON PANEL. 6.5.2.3, PL M i STDS FOR THE CONTROL ROOM. 6.6.6 8 PERFORM ENHANCEMENT TECHNIBUES IN FORMS OF DEMARCAi!DN, MIMICS, IDE MARKING OF DISPLAYS, & FUNCTIONAL CODIN6 OF CONTROLS & DISPLAYS UTilillNG SPEC COLOR l CODING.
O O O Page Ms. 42 01/22/87 AllACHMENT 6 CNS DCRDR )
! HED CORRECTIONS & SCHEDULE MASTER LIST
- l. PANELS RECORD ENHANCEMENT CATE60RY IMPLEMEN-NO. CHECK- NUREB-0700 HED PANEL / / tai!0N LIST PRIORITY ACil0N SCHEDULE RESoluil0N/ NOTES ITEM SECil0N 10. 10. MODIFICATION HED DESCRIPil0N 1
6.5.1.6, 160SS 9-02 ENHANC. 9 Fl! 1988 REFUELING INTEGRATE NITH HED 21S FOR 426 USE OF COLORS NOT CONSISTENTLY A4.2 DEVELOPMENT OF HUMAN FACIOR APPLIED ON PANEL. 6.5.2.3, PLANT STDS FOR THE CONTROL ROOM. 6.6.6 e PERFORM ENHANCEMENT TECHNIQUES IN FORMS OF DEMARCATION MIMICS, IONE MARKING 0F DISPLAYS, & FUNCil0NAL CODING OF CONTROLS & DISPLAYS UTILil!NG SPC. COLOR CODINB. Al.1, 6.l.2 3175S 9-02 DESIGN MOD. Il Fl! 1988 REFUELIN6 RELOCATE RMA METERS IN 591 DISPLAYS LOCAIED OUTSIDE ACCORDANCE NITH CNS HF RECOMMENDED 10NES. A3.6 ANTHROP 0 METRIC LIMilS. FII 1988 REFUELING RAISE SCALE OR REPLACE PolNTERS. 6.5.2.2, 318SS 9-02 DESIGN MOD 11 592 POINTERS COVER RECORDER 82.5 SEE SCALES. COMMENTS FII 1988 REFUELING REPLACE SCALE NITH NEN ONES THAT 593 METER SCALES ARE HARD 10 READ. B2.11 6.5.1.2, 31955 9-02 ENHANC 11 DISPLAY INTERMEDIATE MARKINGS. NEED INIEMEDIATE MARKIN6S SEE } . COMMENTS . B FII 1988 REFUELING REPLACE COLOR Of INDICAi!NG j 594 POSSIBLE DUAL MEANING FOR A4.3 6.5.3.2, 320SS 9-02 ENHANC. Ll6HIS IN ACCORDANCE NITH CNS HF COLOR OF INDICAllNG LISHIS. SEE STANDARDS. 1 COMMENTS 8 flI 1988 REFUEllNG FABRICATE A NEN LABEL THAT 595 LACK OF LABELS FOR IDENilFYIN6 A5.1 LABELING 3215S 9-02 ENHANC. DESCRIBES IHE FUNCil0N OF THE COMPONENT FUNCT!DN. INFORMAT EQUIPMENT liEM AND COMPONENT I6N I.D.
O O O Page No. 43 01/22/B7 AllACHMENT 6 CNS DCRDR HED CORREti!0NS 6 SCHEDULE MASTER LIST
- 1. PANELS RECORO ENHANCEMENT CATEGORY IMPLEMEN-CHECK- NURES-NO.
/ / TATION LIST 0700 HED PANEL SCKDULE RESOLUil0N/ NOTES MODIFICAil0N PRIORITY AC110N ITEN SECTION 10. ID.
HE8 DESCRIPil0N Fl! 1988 REFUELING FAMICATE KN LABELS INNilf!NG I A5.3 6.6.1.1, 32255 9-02 LNHANC. SYSTER K SI6 NATION. CORRECT 596 LACK OF LA KLS FOR IDENTIFYING SYSTER DESIGNA110N. 6.6.3.1, LAKLS IKNilFICAil0N. SEE CDMENTS Fl! 1998 REFUEllN6 FABRICATE A NEW LAM L THAT I A5.4 6.6.1.1, 323S5 9-02 ENHANC. KSCRIE S PANEL AND MERGE NiiH 597 LACK OF PANEL FUNCTION IDENTIFICAll0N LABEL. 6.6.3.1 EIISilNG PANEL LAMLING IN A HIERARCHICAL SYSTEM. Fl! 1988 REFUELING FABRICATE KN LAMLIN6 B A5.5 6.6.3.2, 324SS 9-02 ENANNC. CONSISTENT WILABELING THROU6HOUT 59B INCONSISTENT USE OF ACRONYMS AND ABBREVIATIONS 6.6.3.3, THE CTRL RM. CAUTION MUST K 6.6.3.4' EIERCISED 10 ENSURE NO DISCREPENCIES ARE SIMERATED KINEEN NEW LABELS MA K 6 TERMIN0LO6Y FOUNI IN PROCEDURES. Fl! 1988 REFUELIN6 ENHmCEMENT IN AGREEMENT NiiN I A5.6 6.6.4.1, 325SS 9-02 ENHANC. CNS HF STANDARDS AND NURE6 0700 599 LAKLS NOT CONSISTENT IN TYPE SEE GutKLINES. STYLE AND APPLICAi!DN OF TYPE - COMMENTS S!!E. Fl! 1988 REFUEllN6 FABRICATE NEN LA KLS CONSISTENT I A5.10 6.6.2.1, 32655 9-02 ENHANC. NILAKLING THR006HOUT THE CTRL 600 EIISilNG LAK LS ARE NOT CLEAR WITH RESPEtt TO FUNCTION Ok 6.6.3.1 RN. CAUTION MUST BE EIERCISED SEE TD ENSURE NO DISCREPANCIES ARE INTENT. COMMENTS SEhERATED BEINEEN NEW LABELS MADE 6 TERMIN0 LOGY FOUNO IN PROCEDURES. f
O O . O Page No. 44 Oll22/8T AllACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST 1.PAMLS RECDPS CATE60RY IMPLEMEN-ENHANCEENT CHECK- NURES- TATION NO. LIST 0700 HED PAEL / / ACTION SCHEDULE MSOLUTION/ NOTES
- 10. MODIFICAi!ON PRIORITY ITER SECTION 10.
HEI MSCRIPi!DN Fl! 1988 REFUE'ING RELOCATE LABELS MB LEGEND MSI6N MOD 111 601 LAM LS AND LEGEND PLATEi, NOT A3.Il 6.6.2.1, 327S5 9-02 PLATES IN ACCORDMCE WITH CNS HF SEE STANDARDS AND NUREE 0700 UNIFORMLY POSITIONED FOR COMENTS 6UIDELIMS. FUNCil0kt CLARlif. FII 1988 REFUELINE REVIEW SERVICES MING PROVIM S ENHMC, I A6.1 & 6.6.5.2 328SS 9-02 SY USE OF TEMPORARY LAMLS. 602 TEMPORARY LABELS NOT REVIENED PERIODICALLY, RADE PERRANENT A6.7 REPLACE IN ACCORBMCE WliH NUREE OT00 SUIDELINES. OR REMOVED. FII NORMAL RANGES OF OPERAi!ON 2 0 6.5.2.3 3295S 9-02 ENHANC. I 1988 REFUELING ENTRY CONDITIONS TO EMER6E ElES, B2.1 603 INDICATORS NOT RARKED TO SHOW iSEE AS SPEt!FIED BY CNS E0P'S, WILL NORMAL RANGES OF OPERAT10N. MISC /COM M MARKED ON PRlRARY INDICATORS MENTS) FII 1989 REFUEllNE SCALE CHANGES SHOULD M 8 6.5.1.2, 3305S 9-02 ENHANC. 604 INSTRUMENTS ARE NOT SCALED IN 92.3 PERfDRMED BY MINOR DES 16N SEE CHAN6E. ENSURE APPROPRIATE PROCESS UNITS RELAi!NS TO RISC/COM CALIBRATION & SURVEILLAKE STSTEN OPERAi!DN. MENTS PROCEDURES ARE UPDATED. ENSUR I
- APPROPRIATE OPERATCR TRAINih6 N!u. M CONDUCTED.
FII 1988 REFUELING INTEGRATE Wiid HED 3295S. I B3.3 6.5.2.3 331SS 9-02 ENHANC. IDENTIFY NORMAL RAN6ES OF 605 ALARM POINTS NOT IDENilFIED ON RECORDERS. OPERATION & ENTRY 10 EMER6E ET ON RECORDER. VERIFY THAT ALARR POINTS ARE MLON OR AT THE EMER6ENCY MARKING.
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O O O Page No. 48 01/22/87 ATTACHMENT 6 CNS BCRDR HED CORREti!DNS & SCHEDULE MASTER LIST i 1. PAELS 4 RECORD CHECK- NURE6- ENHANCEENT CATE60RY IMPLEMEN-NO. LIST 0700 El PANEL / / TAT 10N ID. 10. MODIFICA110N PR10R11Y ACTION SCHEDULE ESOLui10N/ NOTES HED DESCRIP110N 11ER SEC110N 54 ASSOCIATION OF FEEDBACK 10 $43 6.4.2.2, 54S 9-10 & ENHANC. Il Fl! 1988 REFUELING INTEGRATE WITH EI 53 MI 14S TO 6.5.1.6, 9-11 PROYlDE NECESSARY ASSOCIATION OF RELATER CONTROLS NOT APPAtCNT 6.6.6.4 CONTROLS MD FEEDIACK. THROU6H LABELINS, MIMICS, DEMARCATION LIES. e 56 CONTROLS REDUIRING MANUAL B1.1 6.l.2 565 9-10 & DES 16N M00. 11 FII4ER 1998 REFUELIN6 KLOCATE CONTROLLERS IN 9-11 FEASIB!lli ACCORDMCE UliH TE OPERAT10N NOT EASILY REACHED. Y STDV RECOMMENDAil0NS OF THE CONTROL SMITCES L3CATED 26' RECOM FEAS!BILITY STUDY PERFORMEI DN BELON MIN. LIM!iS AN3 11' PANEL MODIFIC.4 IONS. ABOVE MAI! MUM LIM!iS. 65 INDICATORS NOT MARKED 10 SHOW B2.1 6.5.2.3 65S 9-10 L ENHMC. I Fl! 1998 REFUELIN6 ZDNE MARKINGS SHOULD E USED TO 9-11 SHOW OPERA 110NAL IMPLICATIONS OF NORMAL RANGES OF DPERA110N. ISEE VARICUS M ADIN65, SUCH AS MISC /COM
'0PERAll0NAL RAN6E*, ' UPPER ENTS)
LIMITS', ' LONER LfMITS' MD
' DAN 6ER IONE'. 20NE MMKINGS SHOULD E CONSPIC1005 MB DISilNCilVELY DIFFEENT FOR I!FFERENT IONES.
69 INSTRUMENTS NOT SCALED IN 82.3 6.5.1.2, 69S 9-10 L GTER M00. Il PROVIE 1988 PEFUELING SPBS WILL PROVIDE THE SEE 9-11 ALT. INFORMATION IN OPERATIONAL UNITS PROCESS UNIIS RELATING 10 MISC /COM OF CURIE /HR. SYSIEM GPERA110N. MENTS B5.3 6.l.2 1045 9-10 & DESIGN M00. 11 FII-PER 1988 REFUELING INTEGRATE WITH E D SS. FOR 104 CONTROL SNITCHES ABOVE AND BELON RECOMMENDED HE16HIS. 9-il FEASillLli KLOCAllN6 CONTROLS. CONTROL SNiiCHES LOCATED 26' Y STOY BELON MINIMUM LIMiiS AND 11' RECOM ABOVE MAI. LIMITS.
O O O Page No. 49 01/22/87 AllACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS RECORD CHECK- NURE6- ENHANCEMENT CATE60RY IMPLEMEN-NO.
LIST 0700 HED PANEL / / tai!0N PRIORITY ACTION SCHEDULE RESOLUT!DN/ NOTES HED DESCRIPi!0N ITEM SECT!0ii 10. ID. MODIFICA!!Da 107 MSL RADIATION MONITOR SWITCH B5.6 6.4.1 107S 9-10 L DESIGN MOD. Il Fl! 1988 REFUELIN6 SNITCH SilE NOT THE PROBLEM. 9-11 SWITCH 60ARD COVER IS MAKING li NOT OF ADEQUATE SilE. DIFFICULT 10tiPERATETHESNITCH. REPLACE OR MODIFY THE 6UARD COVER. 120 METERS ARE FAR BELON S!6HT - $31.1 6.1.2 1205 9-10 L DESIGN M00. !! FII-PER 1988 REFUELING INTE6 RATE WITH HED 5S IN 9-11 FEASIBILIT PERFORMIN6 THE DESIGN MAKING li DIFFICULT TO PEAD i Y SIDY MODIFICATION TO RELDCATE METERS SCALE RECOM 6.1.2 9-10 & DESIGN N00. 11 FII-PER 1988 REFUELING INTEGRATE NiiH HED 55. 121 INDICATOR SCALES NOT EASILY SBl.1 121S READ WHEN STATIONED AT THE 9-11 FEASIBILli Y STDY PcNEL. RECOM 130 PROCESS UN!iS AND MULTIPLIERS SBl.4 6.5.1.4 130S 9-10 & ENHANC. B FII 1988 REFUELINE IDENilfY PROCESS UNilS. i NOT SPECIFIED. 9-11 234 SC HVAC EIHAUST RADIATION N/A 6.1.2.5N 58T 9-10 & DESIGN MOD. 11 Fl! 1988 REFUELIN8 SAME DISCREPANCY IDENTIFIED IN IA 9-11 CR SURVEY (NED 55). FII METERS ALB LOCATED 15' FROM . ACCORDING TO FEASIBilliY STUDY THE FLOOR. RECOMMENDATIONS. 235 ALARM SETPolNIS ARE N/A 6.6.5.1 59T 9-10 & ENHANC. I Fl! 1988 REFUELIN6 REPLACE BY PERMANENT LABELS. 9-11 - DISCREPANCY ALSO IDENTIFIED IN
; TEMPORARILY PLACED BELON SC ' CA SUVEY INED 39S)
AREA RADIATION INDICATION METERS. 257 SRM RAMP SuliCH IS 100 SMALL N/A 6.4.4.5, 41 9-10 & DESIGN N00. 11 Fl! 1988 REFUELING THE SRM RAMP SuliCH SHOULD BE 9-11 REPLACED WITH A MORE SUITABLE FOR HOLD FOR 90 SECONDS IN SEE COMMENTS TYPE OF CONTROL SW!iCH. A SURVEILLANCE P031 TION CHANGE OF THIS NATURE WILL NEED AN OPERATOR AfD. REQUIRE A DES 16N CHAN6E. l
"% "\
b > (b (d Page No. 50 01/22/B7 ATTACHRENT 6 CNS BCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS
! RECORD IMPLEMEN-ENHANCEMENT CATE60RY CHECK- NURE6-NO. 0700 HED PMEL / / TATION LIST SCHEDULE ESOLUTIONINOTES MODIFICATION PRIORIIV ACTION ITER SECIl0N 10. 10. HES DESCRIPi10N ENTRY CONDITIONS TO EMER6EE!ES, 605 9-21 EMANC. I Fl! 1988 REFUELING 60 INDICA 10RS NOT RARKED TO SHON 82.1 AS SPECIFIED BY CNS E0P'S, NILL NORMAL RAN6ES OF OPERATION. M NARKER ON PRIMARY INDICATORS. h6 ACil0N, NOME eRECORDERS HAVE MEN REPLKED. 9-21 ES!6N MOD. 11 75 PRINTED VALUES NOT EASILY READ B3.1 6.5.4 75S HED NOT APPLICABLE. l HED RESOLVEDs 4 Fl! 1988 REFUELING INTE6 RATE WITH HED 925. 82S 9-21 ENHMC. I 82 RARR POINIS NOT IDENTIFIED ON B3.3 6.5.2.3 IE NilFY NORNE RANGES OF RECORERS. OPERATION & ENTRY 10 EMER6ENCY l ON RECORDER. VERIFY THAT EMR , POINTS ARE ELON OR AT THE EER6EEf MARKING. Fl! 1988 REFUELIN6 IDENilFY NORRR RM6ES OF 9-21 ENHANC. I 92 RECORDER SCALES NOT RARKED TO B3.15 6.5.2.3 92S OPERA 110N AND ENTRY 10 EMER6E EY (SEE PER E0P'S ON KCORER SCRES. SHON NORRE OR ABNORNE RM6ES MISC /COM OF QPERATIONS. MENTSI INTEGRATE NiiH HED 200S5. 581.1 6.l.2 IlBS 9-21 DES 16N N00. !! Fit-PER 1998 REFUELING lib INDICAIDR SCALES NOT EASILY FEASIBILli l READ NEN STAi!0NED AT THE Y STDY
- PANEL. DNE RETER INDICAT10N RECON l LOCATED 17' AB0VE MAI. LIMITS.
Fl! 1988 REFUELING FABRICATE NEN LAKL. SAME 9-21 ENHANC. 8 I ' 232 NO FUNCTIONE LABEL FOR N/A 6.6.1.1 56T DISCREPANCV I N NilFIED IN CR SECONDARY CONTAINRENT AREA SURVEY (NED 166SSI TEMPERATURE INDICATION METER. Fl! 1988 REFUELING INTE6 RATE WITH HED 158SS IN 9-21 SESIGN M00. 11 233 SC AREA TEMPERATURE INDICATION N/A 6.1.2 57T RELOCAlthii METER INDICATIONS TO METER LOCATED ABOVE LINE OF MET INEMTHROPORETRIC LINITS S!6Hi.
O O O Page No. 51 01/22/87 ATTACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS RECORD CHECK- NUREG- ENHANCEMENT CATE60RY IMPLEMEN-NO.
LIST 0700 HED PAEL / / TATION
- 10. PRIORITY ACil0N SCHEDULE RESOLUTION / NOTES HER DESCRIPTION ITEM SECTION 10. MODIFICATION l
427 LACK OF PANEL FU ETION A5.4 f. 6.1.1, 16155 9-21 ENHANC. B FII 1988 REFUELING FABRICATE A NEW LAEL THAT l 6.6.3.1 DESCRIBES PANEL ANB ER6E WITH IDENTIFICATIONLAEL. EIISilN6 PANEL LAE LIN6 IN A HIERARCHICAL SYSTEN. 432 (ACK OF LABELS FOR IDENTIFYIN6 A5.3 6.6.1.1, 16f.~5 9-21 ENHANC. B FII 1988 REFUELING FABRICATE EN LAELS IENTIFYING SYSTEM DESIGNATION. CORRECT SYSTEM DES!6 Nail 0N. 6.6.3.1, SEE LA ELS I E NTIFICATION. COMMENTS 433 INCONSISTENT USE OF ACRONYMS A5.5 6.6.3.2, 16755 9-21 ENHANC. B Fl! 1988 REFUELING FABRICATE NEW LAELING CONSISTENT N/ LABELING THROU6HOUT AND AB6REV!ATIONS. 6.6.3.3, THE CTRL RM. CAUTION MUST BE 6.6.3.4 e EICERCISED TO ENSURE NO DISCREPENCIES ARE SENERATED KTEEN EN LABELS MADE 6 TERMINOLOGY FOUND IN PROCEDURES. 435 ARM RECORDER DOES NOT HAVE B2.3 6.5.1.4 1695S 9-21 ENHANC. B Fl! 1988 REFUELING IDENTIFY PROCESS UNITS ON SCALE PROCESS UNITS ON SEALE 436 INDICATOR POINTERS DBSCURE B2.5 6.5.2.2, 17055 9-21 ENHANC. B Fl! 1988 REFUELIN6 ENHANCEE NT IN AGREE E NT WITH SEE NURE6 0700 SU!KLIES. SRADUATION MARKS AND SCALE NUMERALS. COMMENTS 437 METER INDICATION ON PANEL B3.14 6.1.2.3 1715S 9-21 ENHANC. B Fl! 1988 REFUELING RELOCATE THE INDICATOR. INTEGRATE WITH HED 200SS EIPERIENCE 6LARE AND REFLECTION 438 ANNUNCIATOR NDMENCLATURE, C2.1 6.3.3.4 17255 9-21 ENHANC. 8 Fl! 1988 REFUELING FABRICATE EN AMUNCIATOR LE6END (SEE TILES NHERE APPLICABLE IN ACRONYMS, OR ABBREVIATIONS ARE ACCORDMCE N/ STATION HUMAN NOT STANDARDl!ED. COMMENTS I FACTOR STDS & NURE6 0700 6UIELIES.
p p p -- - d V V Pqe No. 52 01/22/87 ATTACHMENT 6 CNS DCRDR HED CORRECTIONS & SCHEDULE MASTER LIST
- 1. PANELS RECORD h0. CHECK- NUREG- ENHANCEMENT CATE60RY IhPLEMEN-LIST 0700 HED PANEL / / TATION HED DESCRIPTION ITEM SECTION ID. ID. MODIFICATION PRIORITY ACTION SCHEDULE RESOLUTION / NOTES 554 DISPLAYS LOCATED DUTSIDE Al.1, 6.l.2 280SS 9-21 DESIGN MOD. II FII-PER 1988 REFUELING RELOCATE TEMP INDICATOR IN RECOMMENDED ZONES A3.6 FEASIBILIT ACCORDMCE NiiH THE FS Y STDY RECOMMENDATIONS.
RECOM 555 TEMP. INDICATOR FOR STEAM LEAK A5.1 6.6.1.1, 281SS 9-21 ENHANC. I Fl! 1988 REFUELING FABRICATE NEN LABELS THAT DETECil0N LACKS LABEL 6.6.3.1, KSCRIBE THE FUNCil0N OF INNTIFICATION. SEE EQUIPMENT ITEM MD COMPONENT 10. COMENTS 556 DPERATIONAL LIMITS NOT A5.2 6.6.3.9 28255 9-21 ENHANC. B FII 1988 REFUELING FABRICATE A LE6END PLATE THAT IDENTIFIED THROU6H LABELIN6 IDENTIFIES THE VARIOUS LESEND PLAIES. TEMPERATURE LIMliS IN VARIOUS PLANT MONITORED RE6!0NS ON THIS PANEL. 557 LABELS NOT CONSISTENT IN TYPE A5.6 6.6.3.2, 2835S 9-21 ENHMC. 8 Fl! 1988 REFUELING FABRICATE NEW LABELING STYLE AND APPLICAi!0N OF TYPE 6.6.3.3, CONSISTENT N/LAK LING THROUGHOUT SIIE. 6.6.3.4 THE CTRL RM. CAUT10N MUST BE e EICERCISED TO ENSURE NO DISCREPENCIES ARE 6ENERATED BETWEEN NEW LABELS MADE & TERMIN0LO6Y FOUND IN PROCEDURES. 558 NARE TASS BELCd RECORDERS A5.9 6.6.4.1, 284SS 9-21 ENHANC. B Fl! 1988 REFUELING RELOCATE RECORDER'S NAMETA65 - CANNOT BE READ WHEN STAT 10NED SEE PLACE ON FACE OF RECORDERS. AT THE PANEL. COMMENTS 559 TEMPORARY LASELS ARE NOT A6.1 6.6.5.1, 285SS 9-21 ENHANC. 8 FII 1988 REFUELING REVIEN SERVICES PRESENTLY BEIN6 MINIMllED SEE PROV!K D BY USE OF TEMPORARY COMMENTS LAKLS. DETERMINE THEIR NECESSITY AND REPLACE NITH PERMMENT LABELS IN ACCORDMCE NITH NURES 0700 GulDELINES.
O O O Page No. 53 81/22/B7 ATTACHRENT S CNS KRDR HE8 CORRECTIONS & SCHEDULE MSTER LIST
- l. PANELS KCORI CHECK- NURES- ENHAEEMENT CATEGORY IMPLEMEN-C2.
LIST 0700 NES PANEL / / Tail 0N HER KSCRIPilm - ITEM SECTIM 10. 19. ROBIFICAi!0N PRIORiif Kil0N SCKBULE RESOLuilM/ NOTES 560 TEMPORARY LA ELS NOT E VIENE8 A6.7 6.6.5.2 286SS 9-21 ENHMC. I Fl! 1980 KFUELING luiEGRATE UlTH HED 285SS IN REPLEINS TEMPORARIES NITH PER108!CRLY, MADE PERMNENT PERAMENT LAKLS.' OR K A0VEI. 8 NO ETIM NONE TEMPERATUK INelCATOR CANNOT K 561 TEMPERATURE IM ICATORS NOT B2.1 6.5.2.3 28755 9-21 EMANC. RARKED FOR NORMAL RANSE OR ENTRY RARKEI TO SHOW NORML OR (SEE TO EMERSEEIES SIEE li MS ASNORRE RMSES OF OPERAil0N. RISC/COR SEVERE SEIP0INIS. OPERATIONE NENTS) LIRITS WILL M IK NilFIED ON A LE E NI PLATE. (KFER TO HEI 163SSI 562 TEMPERATURE IN0!CATOR 82.2 6.1.2.2 200SS 9-21 ENNANC. I Fl! 1980 REFUELINS ELOCAil0N OF THE IM ICATOR (MES 200SSI NILL RESOLVE THIS . EIPERIEEES ELARE & DISCREPANCY. KFLECT10N. 590 MULTI-CHMNEL RECORKR B0ES $52.2 6.5.4.2 31656 9-21 DESIM MB. 11 Fit 1990 REFUELING REVIEN SERVICES PROVIMD DV THESE KCOR KRS, IN VIEN TMT NOT DISPLAY CHANNEL K INS BACKUP INDICAil0NS ARE AVAILABLE , PLOTTE8 DURINS ABNORRE _ TO VERIFV RECORDEI VEUE. Couli!0NS. . PLACE ON 1900 REFUELING ANKYSIS OF OPERATOR TASKS IS 201 NO DIRECT hEADOUT OF RI N/A 6.5.1.1, 25i 1-21/SPOS OTHER MS. 111 ' PRIS KCouENKI FOR ESTARISHING COOLDOM RATE AVAILAKE. SEE OPERATOR INFOMAllM ConnENTS ' REQUIRENENTS. VISU E BISPLAVS SHOUll PROVI K R L THE INFORMAil M AIGUT SYSTEM STATUS
& PARAMETER VK UES NEEM B TO NEET TASK REQUIRENENTS IN NORRE AND EMERS. SliUATIONS.
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