ML20064C473
| ML20064C473 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1982 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20064C452 | List: |
| References | |
| 2338W-1, NUDOCS 8301040407 | |
| Download: ML20064C473 (171) | |
Text
{{#Wiki_filter:_ Response to Human Factors Engineering Control Room Design Review / Audit 4 - For LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO. 3 DECEMBER 1982 - REV.1 000*S$S$Eo!S$S$52 A PDR
l OUISIANA 342 OctAnoNoe Srneer P O W E R & L i G H T! P O BOX 6008
- NEW ORLEANS. LOUISIANA 70174
+ (504) 366-2345 Eu?I's ESSE L. V. MAURIN Vice President Nuclear Op rations Decarber 22, 1982 W3T82-0491 , Mr. T.M. Novak l U.S. Nuclear Regulatory Commission Washington, D.C. 20555 g
SUBJECT:
Waterford 3 SES Unit 3 Control Rocm Design Review
REFERENCE:
W3T82-0407 dated October 20, 1982
Dear Mr. Novak:
[ The referenced letter transmitted a report docunenting LP&L's disposition of Human Engineering Discrepancy identified to date at Waterford 3. On November 4, 1982, we had the benefit of detailed discussions with w mh=rs
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of the NRC's Human Factors' Branch and Consultants. As agreed to at the neeting, we are transmitting Revision 1 of this report which documents agreements reached at the November 4,1982, neeting. The major area of con rn expressed to us by the Human Factors Branch at the meeting was the rate of progress being made on the inplenentation , of Human Factors Enhancenents and design changes in the wulwl room. Another concern was that corrective action for a very large numer of HEDs would take place just prior to licensing which oculd result in sone negative transfer of learning to our operators as well as burden our on site resident inspector with a large anount of items to review in this short period of tine. 'Iherefore, as requested, you will find attached a graph shawing the approximate nunber of HEDs that have been inplenented and that will be inplenunted each nonth between now and our anticipated fuel load date (May 12, 1983). J Also note that it is one of our objectives tc have all changes and V enhancements to the main control boards inplemented by hot functionals. At this tine, the critical path item for the enhancement of the main boards is noter labeling. 'Ihe first phase of higher hierarchical and demarcation has been cmpleted on the main boards. Critical path items through fuel load include enhancement of the renote shutdown panel, meter scale changes and control switch coding enhancenents. The attached report also docununts the dates that various studies such as the lighting survey and color coding report will be subnitted to NRC.
Mr. T.M. NovaK W3T82-0491 ( Page 2 LP&L wishes to thank NRC for what we feel has been a very beneficial review in the area of Human Factors and we want to assure you that we are making our best efforts to inplenent corrective actions in a timely manner and that we will be continuing our program as described in Reference 1 after the date of licensing. Should you have any questions, please contact Dr. Z.A. Sabri at (504) 464-3136. Very truly yours, 0
/7?G L.V. Maurin LVM/pb Attachment cc: D. Tondi, A. Raney Smith, R. Rantirez, E. Blake, M.L. Stevenson, S. Black l
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l Response to Human Factors Engineering Control Room Design Review / Audit For LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO. 3 l
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i DECEMBER 1982 - REV.1
2338W-1 RESPONSE TO HUMAN FACTORS ENGINEERING (DNTROL ROOM DESIGN REVIEW / AUDIT CONTENTS Section Title Page 1.0 1NTRODUCTIO N 1.0-1 1.1 OVERVIEW OF TIIE WATERFORD-3 CONTROL ROOM 1.1-1 1.2 OVERALL ST ATUS AND SCHEDULE FOR HUS!AN FACTORS ENHANCEME NTS 1,2-1 1.3 CROSS REFERENCE OF NRC FINDINGS TO REPORT SECTIONS 1.3-1 2.0 MAIN CONTROL BOARDS 2.1-1
> 2.1 REACTOR (DNTROL PANEL (CP-2) 2.1-1 2.2 PLANT PRCTTECTION CONTROL PANEL (CP-7) 2.2-1 2.3 CllD11 CAL AND VOLUME (DNTROL PANEL (CP-4) 2.3-1 2.4 POWER C0tNERSION AND DISTRIBUTION PANEL (CP-1) 2.4-1 2.5 Tl'RBINE STARTUP RUPF.PV TSORY PANET. (CP-13) 2.5-1 2.6 Pd(TTECTIVE RELAYS PANEL (CP-15) 2.6-1 2.7 ELECTRICAL MONITORING PANEL (CP-17) 2.7-1 2.8 ESFAS TEST AND RESET COOLING TOWERS AND CO NTAIR!E N'T 2.8-1 HYDROGEN MONITOR AND RECDM BINER WNTROL PANEL (CP-33) 2.9 ENGINEERED SAFEGU ARDS PANEL (CP-8) 2.9-1 2.10 HVAC PANEL (C P-18) 2.10-1 2.11 THE ODNTROL ROOM ANNUNCIATOR SYSTD1S 2.11-1
[ L 2.12 !! ASTER FIRE PROTECTION CONTROL PANEL (MCRP) AND 2.12-1 LOCAL FIRE DETECTION (DNTROL PAhTL 2.13 PLANT MONITORING WMNTER DISPLAY PANELS 2. 13-1 (CP-3, 3 5, 36) 2.14 RD10TE SilUTDOWN - TRANSFER AND CONTROL 2.14-1 l 2.15 GENERIC PANEL FINDINGS 2.15-1 3.0 COSE!UNICATIONS 3.1-1 4.0 PLANT MONITORING WMPUTER 4.1-1 1 5.0 EINIRORIENTAL FACTORS 5.1-1 5.1 LIGllTING 5.1-1 5.2 ACW:Et0DATIONS 5.2-1 6.0 SUM.1ARY AND CDNCLUSION 6.1-1 i Rev. No. 1, (12/82) L_______ ____ _ _ _ _ __ _ _ _ _ _ _
I i 2351W-1 LIST OF FIGURES Figure No. Title 1.1-1 GENERAL ARRANGEMENT OF CONTROL ROOM 1.1-2 DDiENSIONS OF OPERATOR WORKSPACE (UPDATE) 2.1-1 CP-2 ENHANCEMENT l 2.1-2 BEFORE ENHANCEMENT 2.1-3 AFTER ENHANCEMENT 2.1-4 ROD MIMIC DIAGRAM 2.2-1 CP-7 ENHANCEMENT r 2.2-2 BEFORE ENHANCEMENT 2.2-3 AFTER ENHANCEMENT 2.3-1 CP-4 ENilANCEMENT 2.3-2 BEFORE ENilANCEd1ENT ( 2.3-3 AFTER ENHANCEMENT l 2,4-1 CP-1 ENilANCEMENT I 2.5-1 CP-13 ENHANCEMENT l 2.5-2 AFTER ENilANCE:1ENT 2.6-1 CP-15 ENilANCEMENT 2.6-2 BEFORE ENllANCEMENT 2.6-3 AFTER ENHANCEMENT 2.7-1 CP-17 ENHANCEMENT f 2.7-2 BEFORE ENilANCEMENT 2.7-3 AFTER ENHANCEMENT 2.8-1 CP-33 ENilANCEMENT 2.8-2 BEFORE ENHANCE 1ENT 2.E-3 AFTER ENiiANCEME.;T 2.9-1 CP-S ENHANCEMEN1 ii
l 2351W-2 LIS f 0F FIGURES (Cont 'd) Figure No. Title 2.10-1 CP-18 ENHANCEMENI 2.Il-1 ANNUNCIAIOR ZONES 2.11-2 ANNUNCIAIOR PAdEL ( ALPHA-NUMERIC) 2.12-1 MASTER PANEL FIRE PROTECTION SYSTEM - A 2.12-2 MASTER PANEL FIRE PROIECTI0d SYSIEM - B 2.12-3 FPE-3 & 3A 2.13-1 COMPUIER INTERFACE BOARD 2.14-1 LCP-43 PRELIMINARY DRAFI ENHANCEMENT f 2.15-1 MICRO-SWITCH CODING 2.15-2 ANThKOP0 METRICS (Ptt0f0 0F OPERATORS) 3.1-1 SOUND POWERED PHONE iii Rev. No. 1, (12/82)
1.0 INTRODUCTION
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I 2337W-1 l
1.0 INTRODUCTION
This report documents LP&L's disposition of the human engineering discrepancies (HEDs) identified to date as part of our Control Room Design I Review Program (TML Task 1.D.1) . .ipproximately 130 HEDs resulted from our review program as conducted by Lockheed Missile and Space Co., and an additional 95 HEDs resulted from the NRC audit of May 1982. The organization of this report is basically by topic. Individual Control Room panels are discussed first in order of the original enhancement schedule. Next, sections covering remote shutdown, computer displays, generic findings, communications, lighting and accommodations are provided. For convenience a cross reference between NRC findings and report sections is contained in Section 1.3. l It should be noted that if a finding is against two panels (e.g. display-control integration), then the response is repeated in both subsections. However, generic panel findings which may potentially impact several or all panels are discussed in Section 2.15. Each panel section contains a brief introductory write up, and a copy of the human f ac tors enhancement drawing. for those panels which have undergone the first phase of human factors enhancement (approximately 8 panels) copies of pre enhancement and post enhancement photographs are provided. Other drawings or photographs are provided to augment and clarify some of the responses to the NRC findings. I I I i 1.0-1
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2344W 1 f 1.1 OVERVlFM OF THEjATERFORD-3 CONTROL ROOM The general arrangement of the Control Room and its adjacent facilities is shown on Figure 1.1-1. The operators' workspace around the main control board and the key dimensions of this space are shown on Figure 1,1-2.
\ The Contrel Room area measures roughly 65 feet vide by 87 f eet long in its two e * -tongest dim'ensions.' , Ine area containing the contrcl panels measures about 36 feet wide by 31-feet / des,p and contains the supervisor's office and the desk consoles. ine main control' board is arranged as a nonsymmetrical wing shape and is appt.oximately 50' 4" long measured on the vertical panel surf ace. )1 (CP-16-to,CP-8). The side panel is 33' long (CP-13 to CP-52).
Ihe operator's consolN ir set within this area with an aisle of 6 to 7-1/2 i feet wide between it and the main control console. This console is 13-1/2 f er,t i.ong at its front edge. The operator at this console will be seated 12 to 13 feet from tne closest main panel areas. The supervisor's office is a "0" snaied enclosure. Tne supervitor'will be seated approximately 30 feet from the center of CP-2
, 4 Ine loc 4tio'n of the supervisor's office in the Control Room permits a diroet e ' visual# monitoring of the operating area and the quick access to the operator's wo r n s p/* c e , whenever need/d.' The half-octagonal shape provides access clearance to tne Control'Koom from the main entrance. Tnere is a clearance of dbout- 6 feet ,f rom the edge of the of fice to tne corner of the fire alarm panel
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, ' 4 r,oilet und kitchen facility arellocated on the periphery of the Control Room for the operators use. These are behind CP-13 and CP-33.
l < < s. Ihe Cont, cal Room has direct access to the Computer Room. This arrangement facilitat,ev'the cooperation which is expected between operators and compivar
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'f Across the;corriJpr from the main entrance to tne Control Room is located tne onsite Ircuni~ cal dopport ,Lenter Conference Room. Beyond the opposite wall of the Conttel koom are located the emergency living quarters wnien is part of 1 the techhic9l support center witn indirect access from the Control Room
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L 1 J 1.2 OVERALL STATUS OF HUMAN FACTORS ENHANCEMENT PROGRAM 4 1
I s s 2337d-3 n 1.2 OVERALL SIATUS AND SCHEDULE FOR HUMAN FACTORS ENdANCEMENTS in 1974 LP&L elected to dedicate substantial resources to the Waterford-3 man machine interface. An advanced plant monitoring computer was decided on i in late 1975 and a plant operational review program was initiated. Following the accident at Tdi-2 and re. view of subsequent government and industry studies, LP&L decided to commit even more resources to insure a highly reliable man-machine interface. As part of this effort a Control Room design review and a systems operability review were initiated in November 1980. duman Factors experts from Lockheed Missile and Space Co., participated in a multidiscipline review / evaluation. A preliminary planning review was conducted in December 1980 (ref W3P81-1102), a half scale mockup was constructed in late 1981, interface meetings were held in 1981, enhancement drawing review with the plant staff toon place in late 1981, RED committee meetings began in early 1982, production of final enhancement drawings began in May 1982 and implementation of enhancements began in August 1982. LP&L's goal is to complete human factors enhancements of the Main Control Room panels by not functional testing, in order to give the operators time to y become familiar witn already enhanced panels. Hot Functional Testing is scheduled to begin January 18, 1983. In general, other Control Room improvements committed to in the following sections of this report such as additional meters and recorders, lighting improvements, etc. are planned to be completed prior to Licensing (presently equal to fuel loading wnich is y seneduled for May 5, 1983). Some items which are presently under review and which may require corrective action will be implemented by first refueling. LP&L believes that all significant HEDs are being properly addressed. S Presently, tne first phase of interim enhancements has been completed for 9 of l1 the 12 panels slated for enhancement. A revision of the enhancement drawings is underway to incorporate additional ennancements such as control switch coding and to resolve discrepancies found during application of enhancements. LP&L will issue a manual for enhancement tnat will include tne approved glossary of terms and abbreviations, and approved color code and controls for ensuring tnat ennancements are updated with changes to the control panels, s (I 1.2-1 Rev. No. 1, (12/82)
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r I 1.3 CROSS-REFERENCE OF NRC FINDINGS TO REPORT SECTIONS l 4
2343W - 1 1.3 CROSS REFERENCE OF NRC FINDINGS TO REPORT SECTIONS NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page B-1 1 1 Transfer 2.14.2 2.14-9 B-1 2 1 Transfer 2.14.2 2.14-9 B-1 3 2 CP-2 2.1 2.1-1 B-1 4 2 CP-2 2.1 2.1-1 B-1 5 1 CP-33 2.8 2.8-1 B-1 6 1 Transfer 2.14.2 2.14-9 B-1 7 1 Environ 5.2 5.2-1 B-1 8 1 Generic 2.15.5 2.15-19 B-1 9 2 Etiviron 5.2 5.2-2 B-1 10 2 Environ 5.2 5.2-2 B-1 11 2 Environ 5.2 5.2-2 B-1 12 1 LCP-43 2.14.1 2.14-1 B-1 13 1 LCP-43 2.14.1 2.14-1 B-1 14 3 Generic 2.15.5 2.15-19 B-1 15 3 Generic 2.15.5 2.15-19 B-1 16 2 CP-4 2.3 2.3-1 B-1 17 3 Environ 5.2 5.2-1 B-1 18 1 Environ 5.2 5.2-3 B-1 19 3 Environ 5.2 5.2-1 B-1 20 1 Environ 5.1 5.1-1 B-1 21 1 Environ 5.1 5.1-1 B-1 22 1 CP-7 2.2 2.2-1 (; B-1 23 1 Environ 5.1 5.1-2 j B-1 24 1 Environ 5.1 5.1-2 B-1 25 1 Communication 3.0 3.1-1 B-1 26 3 Environ 5.2 5.2-3 B-2 1 1 Communication 3.0 3.1-2 B-2 2 1 Communication 3.0 3.1-2 B-2 3 1 Communication LCP-41 3.0/2.14 3.1-2/2.14-10 B-2 4 1 Communication 3.0 3.1-2 B-2 5 3 Comunication 3.0 3.1-2 B-2 6 1 Communication 3.0 3.1-3 1.3-1
2 34 3W - 2 NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page ( B-2 7 3 Communication 3.0 3.1- 3 B-2 8 1 Communication 3.0 3.1- 3 B-2 9 1 Communication 3.L 3.1- 3 B-2 10 1 Communication 3.0 3.1-3 B-2 11 3 Communication 3.0 3.1-4 B-3 1 3 Fi re 2.12 2.12-1 B-3 2 3 Annunciator 2.11 2.11-2 B-3 3 2 Annunciator 2.11 2.11-2 B-3 4 Annunciator 2.11 2.11-2 B-3 5 Annunciator 2.11 2.11-2 b-3 6 Annunciator 2.11 2.11-3 B-3 7 2 CP-8/ Annunciator 2.9/2.11 2.9-2/2.11-3 B-3 8 2 Annunciator 2.11 2.11-3 B-3 9 Annunciator 2.11 2.11-4 I B-3 10 3 Ac 9ur.c i d e. .' r 2.11 2.11-4 B-3 11 2 * : no.ic i a t ar ?.11 2.11-4 B-3 12 1 Anne clator 2.11 2.11-4 I B-3 13 3 Annun iator 2.11 2.11-4 B-3 14 1 Annunciator 2.11 2.11-5 B-3 15 3 Annunciator 2.11 2.11-5 B-3 16 1 Annunciator 2.11 2.11-5 B-3 17 1 Generic 2.15.1 2.15-1 B-3 18 1 Ge neri c 2.15.1 2.15-1 B-3 19 2 13/33 2.5/2.8 2. 5- 1/2. 8- 1 B-3 20 1 Fire 2-12 2.12-2 B-3 21 2 Annunciator 2.11 2.11-6 B-3 22 2 Annunciator 2.11 2.11-6 B-3 23 1 Annunciator 2.11 2.11-6 s B-4 1 1 LCP-43 2.14.1 2.14-2 B-4 2 1 CP-33 2.8 2.8-2 B-4 3 1 CP-7 2.2 2.2-2 B-4 4 1 CP-8 2.9 2.9-2 B-4 5 1 Generic 2.15.2 2.15-6 1.3-2
1 2343W - 3 NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page f r B-4 6 3 CP-4 2.3 2.3-2 B-4 7 2 Generic 2.15.2 2.15-8 B-4 8 1 CP-1 2.4 2.4-2 B-4 9 1 Generic 2.15.2 2.15-10 B-4 10 1 Generic 2.15.2 2.15-10 B-4 11 2 Fire 2.12 2.12-2 B-4 12 1 Generic 2.15.2 2.15-7 B-4 13 3 Generic 2.15.2 2.15-7 B-4 14 1 LCP-43 2.14.1 2.14-2
/ B-4 15 2 CP-4 2.3 2.3-2 B-4 16 1 Generic 2.15.2 2.15-8 b
y B-4 17 1 CP-2 2.1 2.1-2 s B-4 18 2 CP-2 2.1 2.1-2 B-4 19 1 Communication 3.0 3.1-4 B-4 20 3 Generic 2.15.2 2.15-7 B-4 21 3 CP-33 2.8 2.8-2 B-5 1 1 CP-2 2.1 2.1-2 i B-5 2 3 CP-33 2.8 2 . 8- 2 B-5 3 1 CP-8 2.9 2. 9- 2 B-5 4 1 CP-8 2.9 2.9-3 B-5 5 1 CP-8 2.9 2.9-3 B-5 6 1 CP-8 2.9 2.9-3 B-5 7 1 CP-8 2.9 2.9-3 B-5 8 1 Generic 2.15.2 2.15-8 B-5 9 1 Generic 2.15.3 2.15-14
. B-5 10 3 Generic 2.15.3 2.15-15 B-5 11 1 Generic 2.15 .3 2.15-12 B-5 12 1 Generic 2.15.3 2.15-13 B-5 13 1 CP-1 2.4 2.4-2 B-5 14 3 Generic 2.15.3 2.15-15 B-5 15 1 CP-1 2.4 2.4-2 i B-5 16 1 Generic 2.15.3 2.15-12 B-5 17 1 LCP-43 2.14 .1 2.14-3 1
B-5 18 3 CP-13 2.5 2. 5- 2 1.3-3
1 2 343W - 4 1 NRC Report Finding NRC !anel or Report Section Number Priority Topic Section Page F' B-5 19 3 Generic 2.15.4 2.15-17 i 7 B-5 20 1 CP-2 2.1 2.1-2 i B-5 21 3 Generic 2.15.3 2.15-13
, B-5 22 1 Generic 2.15.3 2.15-13 B-5 23 1 Generic 2.15.3 2.15-13 B-5 24 1 CP-2 2.1 2.1-3
- B-5 25 3 CP-7 2.2 2.2-2 B-5 26 1 CP-7 2.2 2.2-3 B-5 27 1 LCP-43 2.14 .1 2.14-3 B-5 28 1 CP-4 2.3 2.3-2 B-5 29 1 Generic 2.15.1 2.15-4 8-5 30 2 LCP-4 3 2.14 .1 2.14-3 B-5 31 1 LCP-43 2.14 .1 2.14-3 B-5 32 1 CP-8 2.9 2.9-4 1
B-5 33 3 Generic 2.15 .3 2.15-15 i B-5 34 3 Generic 2.15.3 2.15-15 B-5 35 1 Generic 2.15.2 2.15-9 B-5 36 1 Generic 2.15.2 2.15-10 B-5 37 1 Generic 2.15.2 2.15-9 B-5 38 1 CP-2 2.1 2 .1- 3 B-5 39 1 Generic 2.15.4 2.15-18 B-5 40 3 Generic 2.15.4 2.15-18 B-5 41 3 Generic 2.15.4 2.15-16 B-5 42 3 Generic 2.15.4 2.15-16 B-5 43 3 1 Generic 2.15.4 2.15-17 B-5 44 1 Generic 2.15.4 2.15-16
- B-5 45 1 CP-33 2.8 2.8-3 B-6 1 1 Generic 2.15.2 2.13-6 B-6 2 1 CP-4 2.3 2.3-2 B-o 3 1 CP-4 2.3 2.3-3 B-6 4 1 Transfer 2.14 .2 2.14-10 B-6 5 1 CP-1 2.6 2.4-3 B-6 6 1 Finding
) Withdrawn
2343W - 5 NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page f f B-6 7 3 Fire 2.12 2.12-2 5 '; 6 8 1 CP-1 2.4 2.4-3 l B-6 9 1 Generic 2.15.1 2.15-2 B-6 10 1 Transfer 2.14.2 2.14-10 B-6 1.1 1 LCP-43 2.14.1 2.14-4 i B-6 12 1 CP-1/ 2 2.1/2.4 2.1-3 /2. 4- 3 B-6 13 1 LCP-43 2.14.1 2.14-4 B-6 14 1 LCP-43 2.14.1 2.14-4 B-6 15 1 LCP-43 '2.14.1 2.14-5 B-6 16 1 LCP-43 2.14.1 2.14-5 B-6 17 1 Generic 2.15.1 2.15-2 B-6 18 1 CP-7 2.2 2.2-3 B-6 19 1 Generic 2.15.1 2. 5- 2 B-6 20 1 Generic 2.15.3 2.15-14 B-6 21 1 LCP-43 2.14.1 2.14-5 B-6 22 3 Communication 3.0 3.1-4 1 B-6 23 3 Generic 2.15.1 2.15-3 B-6 24 2 Generic 2.15.2 2.15-7 i B-6 25 1 Generic 2.15.3 2.15-12 B. 26 1 CP-4 2.3 2.3-3 B-6 27 3 Fire 2.12 2.12-3 B-6 28 3 Fire 2.12 2.12-3 B-6 29 3 Fire 2.12 2.12-3 B-6 30 1 Transfer 2.14.2 2.14-1 B-6 31 1 LCP-43 2.14.1 2.14-5 B-6 32 1 Generic 2.15.1 2.15-3 s B-6 33 1 CP-4 2.3 2.3-3 B-6 34 1 Generic 2.15.2 2.15-6 B-6 35 1 CP-4 2.3 2.3-4 B-6 36 ? Fire 2.12 2.12-4 Bo 37 1 Generic 2.15.1 2.15-1 I B-6 38 1 Generic 2.15.1 2.15-2 B-6 39 1 CP-13 2.5 2.5-2
\ B-6 40 1 LCP-43 2.14.1 2.14-5 B-6 41 3 1.3-5 Generic 2.15.1 2.15-3
2343W - 6 NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page B-6 42 1 Generic 2.15.1 2.15-5 f B-6 43 1 Communication 3.0 3.1-4 B-6 44 1 Generic 2. 15 .3 2.15-12 B-6 45 1 Generic 2.15.1 2.15-3 B-6 46 1 CP-33/ Generic 2.8/2.15.1 2.8-3/2.15-3 B-6 47 3 Generic 2.15.2 2.15-6 B-6 48 1 CP-1 2.4 2,4- 3 B-7 1 3 Computer 2.13 2.13-1 B-7 2 1 Computer 2.13 2.13-1
/ B-7 3 1 CP-2 2.1 2.1-3 B-7 4 1 Computer 2 .13 2.13-2 B-7 5 1 Computer 2.13 2.13-2 B-8 1 1 CP-1 2.4 2.4-3 B-8 2 2 CP-8 2.9 2.9-4 B-8 3 1 CP-4 2.3 2.3-4 B-8 4 2 CP-8 2.9 2.9-4 B-8 5 3 CP-13/33 2.5/2.8 2. 5-2 /2. 8- 3 B-8 6 1 LCP-43 2.14.1 2.14-6 B-8 7 1 CP-1 2.4 2.4-4 B-8 8 1 CP-1 2.4 2.4-4 B-8 9 1 LCP-4 3 2.14.1 2.14-6 B-8 10 1 C P-3 3 2.8 2.8-3 B-8 11 2 CP-13 2.5 2.5-2 B-8 12 3 Annunciator 2.11 2.11-6 i B-8 13 1 Generic 2.15.3 2.15-14 B-8 14 1 LCP-43 2.14.1 2.14-6 B-8 15 3 Fire 2.12 2.12-4 )
B-8 16 1 Generic 2.15.1 2.15-4 B-8 17 1 CP-2/4 2 .1/ 2. 3 2.1-4/2.3-4
' B-8 18 1 CP-2 2.1 2 .1- 4 B-8 19 1 CP-8 2.9 2.9-4 B-8 20 1 CP-8/ Generic 2.9/2.15.1 2.9-5/2.15-4 B-8 21 3 LCP-4 3 2.14.1 2.14-7 1.3-6
l 2 343W - 7 NRC Report Finding NRC Panel or Report Section Number Priority Topic Section Page B-8 22 1 LCP-43 2.14.1 2.14-7 B-8 23 2 CP-8 2.9 2.9- 5 B-8 24 1 LCP-43 2.14.1 2.14-7 B-8 25 1 CP-4 2.3 2 . 3- 4 B-8 26 2 CP-8 2.9 2.9-5 B-8 27 3 CP-2 2.1 2.1-4 B-8 28 2 CP-4 2.3 2. 3- 5
/ B-8 29 3 CP-2 2.1 2.1- 5 B-8 30 2 CP-13 2.5 2 . 5- 3 B-8 31 3 Fire 2.12 2.12-4 B-8 32 3 CP-33 2.8 2.8-4 B-8 33 1 CP-4 2.3 1. 3- 5 B-8 34 1 CP-7 2.2 2.2-3 B-8 35 1 CP-1/8 2.4/2.9 2.4-5/2.9-5 B-9 1 1 CP-33 2.8 2 . 8- 4 B-9 2 1 CP-2 2.1 2 .1- 5 B-9 3 1 CP-2 2.1 2 .1- 5 B-9 4 2 CP-2 2.1 2 .1- 6 B-9 5 1 CP-2/4 2.1/2.3 2.1- 6/2. 3- 5 B-9 6 1 CP-4 2.3 2. 3- 5 B-9 7 2 CP-2 2.1 2 .1- 6 B-9 8 2 CP-8 2.9 2.9-6 B -9 9 2 CP-1 2.4 2.4-5 B-9 10 3 LCP-43 2.14.1 2 . 4- 8 B-9 11 1 CP-1 2.4 2.4-5 ,
1.3-7 , 1
i 1 2.0 MAIN CONTROL BOARDS 2.1 REACTOR CONTROL PANEL (CP-2) f
2314W - 1 2.0 HAIN 00NIROL BOARDS l 2.1 REACf0R C0!TIROL PANEL - CP-2 CP-2 contains the indicators and the controls for the following systems constituting or directly related to the reactor: a) Control Rods position indicators (CRT, bottom-out mimic, digital indicators for selected group and selected CEA) and controls (CEA Drive Mechanism Control). b) Reactor Coolant System - indicators (pressurizer level, pressure and temperature; hot and cold leg temperatures, Coolant Pumps monitoring instrumentation) and controls (Pressurizer Heater Controls, Spray ~ Controls, Coolant Pump Controls). c) Reactor Regulating System - Power monitoring and control (Reactor power and rate of change indicators, Neutron Flux Monitors, Core AP and COLSS indicators, Boronometer, RRS System Selector). d) Megawatt Demand Setter - insert witn corresponding indicators and controls. e) Reactor Power Cutback - indicators and controls. f) Reactor Trip pushbuttons CP-2 also contains tne Safety System Status Indication insert and a limited number or otner distinct controls (Fuel Pool Pumps, Quencn Tank Valves, Annunciator Cont rols, etc). Figure 2.1-1 is the human factors enhancement drawing for CP-2. Figures 2.1-2 and 2.1-3 snow photograpns of the panel before and af ter ennancement. Twenty findings or Human Engineering discrepancies were reported against CP-2. Inese findings and tneir disposition are discussed below: B-1, Finding 3, Priority 2 "A wide range hot leg temperature (fn ) recoruer is not provided on CP-2."
Response
A dual scale wide range temperature recorder is being provided (DCN-IC-1085). Tne range or this recorder is 50-750of for born hot legs. It will be located on the far rignt vertical panel surface between tne existing RCS average and ceterence temperature and cold leg temperature recorders. Tne recorder will be installed prior to Licensing. 1 B-1, finding 4, Priority 2 "A sub cooling monitor is not provided on CP-2." 1 1 2.1-1 Rev. No. 1, (12/82) l
2314d - 2 1 l
Response
In accordance with TMI action Item II.F.2 a saturation margin temperature indicator is provided in the upper left vertical panel section of CP-2 next to the reactor power rate of change indication (ref DCN-IC-837). This indicator htd not been installed at the time of the NRC Human Factor Audit. B-4, Finding 17, Priority 1 "On CP-2, the legends for the audible count rate meter Audio Range Switch and Audio Channel Selector switch are unclear, i.e., the Audio Range Selector Switch label does not indicate range scale; the Audio Channel Switch has no position label for the 2 position toggle."
Response
Clear labels are now provided for the channel selector switch as can be seen on Figure 2.1-1. A scale will be provided for the Audio count rate selector switch by Hot Functional Testing. This scale will show the audio count rate ly multipliers (e.g. x 1, x 10, x 10 2 , x 10 3 , x 10 4 ) B-4, Finding 18, Priority 2 "On panel CP-2 and CP-4 Hagan Flow Controllers, the skirt diameter is less I than 2" (1.25) and the finger stop is less than 1.25" (1.0")."
Response
Several LP&L operators have successfully manipulated the subject Hagan Flow ,y Controllers. No operational problems are anticipated . I B-5, Finding 1, Priority 1
" Motor amperage is not displayed and is considered necessary by operators.
NUREG-0700, para 6.5.1.lb requires that necessary information be presented."
Response
Motor amperage is generally displayed via the plant monitoring computer. However, at the operators request, ammeters for the four reactor coolant pump motors are being provided on the middle right vertical section of CP-2 y (DCN-lC-837). ( Ammeters for 14 other pumps are also being- evaluated. These safety-related pumps are HPSI, LPSI, Cont. Spray, Emer. F.W., CCW on_CP-8 and ACCW pumps on CP-33. If LP&L feels ammeters are necessary for these pumps, then they will be provided prior to Licensing.) 2.1-2 Rev. No. 1, (12/82)
23144 - 3 8-5, Finding 20, Priority 1 "The log scale (on the startup neutron flux level meter) appears inverted - possibly an assemoly error. Major divisions are correct; intermediate and minor (divisions) are not." R>sponse Tne meter scale nas been corrected (refer to Figure 2.1-3). 3-5, Finding 24, Priority 1 "On CP-2, one PZR LVL meter scale states DC volts; the other PZR LVL scale states % but units are not indicated." desponse LP6L will correct tne scales to indicate the proper units (% level) prior to fuel load. B-5, Findin d 8,_Pr,iority,,1,
" Numbered rod bottom-out indicator lamp caps are not keyed to prevent installation in improper location or improper orientation."
Response
in order to avoid improper installation, rod numoers will be added on the panel benind the cover door as shown on Figure 2.1-* prior to not Functional 1 Testing. B-6, Finding 12, Priority 1 "On the mimic on CP-1 and on CP-2 enere are sets of indicator ligets that are either not labeled or not inscribed." desponse LP&L will provide Laoels aoove or on the indicating lignts wnicnever is y appropriate as part of tne ennancement effort by dot Functionals. I B-7, Finding 3, Priority 1 "CRf Displaying CEA positions scaled tapes are applied to the face of the CRI, at borders." Scales delineate tne order or CEA sub groups labeling tor part lengtn groups, and tne individual CEA nu.nbers. I 2.1-3 Rev. No. 1, (12/82)
2314W - 4
- 1. Tape scales do not correspond witn ene sub group order, labeling for part length groups, or CEA number sequence used on the CEDMCS Module.
- 2. The upper scale is about 78" above tne floor, on the convex surface of the CRI face and about 32" viewing distance (excessive) for the 95th percentile operator height. Viewing angle and distance are excessive for readability /use.
- 3. Registration (lateral alignment) of the 91 CEA vertical (rod) bars with tne tape scales will vary with the viewing angle, and registration reliability of the CRI."
Response
Ine scaled tapes will be removed since tne display software now provides coordinates for the CRT. Incorporating coordinates in the CRT display will help the readaoility. Tne hign density of this display is acceptable considering the intended function (i.e., gross display of group positions). Indicating modules above the selector switen are being revised to be consi.itent with selector switen positions. The need to have the same CEA order used on CRI and tne CdD1CS module has been l1 reviewed and evaluated to oe of very little consequence to trained operator. Refer to Section 2.15.5, B-1, Findings 14 and 15 for a generic discussion of anthropometric/ readability issues. B-8, Finding 17, Priority 1 "Ene letdown valve selector, controller, and indicator are not on the same panel; e.g., Selector is on CP-4, Controller is on CP-2, Indicator is on CP-4. Ine distance between CP-2 and CP-4 is about 10 feet."
Response
fne letdown valve controller has been transferred from CP-2 to CP-4 as indicated on the enhancement drawings and photos (2.1-1, 2, 3 and 2.3-1, 2, 3). All controls and indicators for the letdown valves are now located on CP-4. (DCNs-1C-d37 and 1011) 6-3, Finding 18, Priority 1
" Reactivity is controlled during startup at CP-2, wnile indicators (count rate steps) is provided on panel CP-7 approximately 10 feet away. Ine indicator, when viewed from CP-2, nas 2 cands of glare near mid-scale."
Response
Two, redundant Rate of Power Change indicators will be added to CP-2 prior to 1 tio t Functional Testing. Tnese indicators are duplicates of the same ones mounted on CP-7. (DCa-1C-o37) j 2.1-4 Rev. No. 1, (12/82)
g 23144 - 5 B-8, Finding 27, Priority 3 .
"On CP-2, the left-to-right order of tne Quench Tank meters does not match the top-to-bottom order of the corresponding annunciator tiles; e.g. Meters: QT i Temp, QT Level, QT Press. Annunciators: QT Level, QT Press, QI Temp."
Response
Inis finding does not present any problem to tne operator; therefore, no
; corrective action is warranted. The human factors engineer also concurs.
l B-8, Finding 29, Priority 3 r
"On CP-2, the Quenen Tank vent and drain valve controls are not directly below their corresponding meters."
Response
The Quench Tank Vent and drain valves are located four feet to tne right of tne Quench TanA pressare and level indicators. These valves are open-close ratner than modulating valves. Tnerefore, the operators will not have a significant readsoility problem for this infrequent operation. ) B-9, Finding 2, Priority 1 "PZR Setpoint-SdC displays on CP-7 are separate from tne associated controls l on CP-2. Tne pressurizer pressure display on CP-2 only goes to 1600 psig."
Response
The four pressurizer pressure (0-1609 psig) displays on CP-2 nave been replaced oy two wide range (0-3000 psia) displays and two narrow range (100-750 psia) displays. Tne operator will control RCS pressure from CP-2 and will observe tne pressure from these displays. For example, during the shutdown the operator will initially use tne 0-3000 psia display and then use tne 100-750 psia displays when going to cold shutdown. The four safety channels of pressurizer pressure on CP-7 are each provided witn a setpoint indicator (normally at approximately 1600 psia). Tnese are associated witn tne reactor protection system. During shutdown, as RCS pressure is gradually reduced, the operator will manually lower the individual setpoints. If system pressure comes too close to the setpoint before the operator has lowered tne setpoint, tnen an alarm will be sounded. During startup the setpoint is elevated automatically. In view of the enanges to tne pressurizer pressure displays on CP-2, there will be no human factors problems with tne control-display integration. 2.1-5 Rev. No. 1, (12/82)
23144 - 6 8-9, Finding 3, Priority 1 "Four startups rate-of-change power meters on CP-7 are used in conjunction witn tne rod insert witndraw joy stick on CP-2, about eight feet away."
Response
Two rate of power change indications will be installed on CP-2 to tne left of lI 1 the CRT by dot Functional Testing. B-9, Finding 4, Priority 2 "On CP-2, the RRS Panel / Local Panel Status indicator is not located near associated controls and displays. It is not clear where the control is for switching of local / remote."
Response
Tne suoject display indicates where the value of control signal (i.e., setpoint) for pressurizer level control system is established. This area of CP-2 nas been modified. Ine pressurizer le' vel controller will be located directly below tne status indicator. Tne indicator has been relabeled to provide immediate display recognition. Operations has concurred witn the enhancement / modification and these changes will be completed by dot Functional Testing. Switening from the Reactor Regulating System to RIGB taxes place at CP-31. Witn RRS selected, the "RRS" section of tne indicator light will be lit and tne pressurizer level will be controlled by tne Reactor Regulating System 1 or 2. Tne position of tne RRS system selector switen (also on CP-2) determines whicn suosystem is controlling the pressurizer level. Witn RTGd selected, the "RTGB" section of the indicator light will be lit and prescurizer level will be controlled by the M/A station directly below the indicating lignt on CP-2. l
\
- 6-9, Finding 5, Priority 1 l " Operator states tnat letdown flow is controlled on CP-2 (Item 1) and indicated on CP-4 (Item 2). Letdown bacK pressure is indicated on meter at l' left of pack pressure controller on CP-4 (ltem 3). During manual operation, either control will affect both indicators. Operation will be a difficult two-man job."
NRC Review ream Com.nent : Controller and display are approximately 8 feet away j trom tne valve A, 8 and ootn selectors. desponse l Ine letdown flow controller nas been moved from CP-2 to CP-4 (DCNs-IC-837 and
; 1011). Inerefore, ootn tne controls and indicators are now on CP-4 Also,
- refer to B-3, finding 17.
4
! 2.1-6 Rev. No. 1, (12/82) i I _ , _ _ , _ _ . _ _ _ _ _ _ __ _ ___ _ .,__ _ _ _ ___ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _
l i j 23144 - 7 , i B-9, Finding 7, Priority 2 "On CP-2, RCP Oil Lift Pump Controls (IA, 18, 2A, 28) and RCPs controls and l corresponding instrumentation are nicely arranged vertically, dowever, the associated annunciator tiles are on an adjacent panel not directly above the ! pump controls."
Response
l J
! Althougn the associated annunciator tiles are not directly above the controls, l tney are still above CP-2 on ene left-nand side. This is within an acceptaole viewing distance as far as control is concerned.
! B-4, Finding 4, Priority 1
" Reactor trip pushbuttons on CP-2 and CP-8 do not have protective housings as l described in NUAEG-0700; pg. 6.4-4, Exhibit 6.4-1. Turbine trip pushbuttons on CP-1 do nave tnese housings."
Response
1 Guards will be provided on tne reactor trip pushouttons by dot Functional Testing (DCN-LC-1009). Tne identical type pusnbuttons presently used for turbine trip including tne protective housing will be used. 1 i i i l l r t t I l 1 i 2.1-7 Rev. No. 1, (12/82)
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FIGURE 2.1-4 89 70 71 81 61 57 62 82 69 49 37 38 50 72 80 44 29 21 30 45 83 48 24 13 14 25 51 l f 9 31 63 60 28 8 5 l 36 12 2 15 39 73 68 4 6 22 58 90 88 56 20 1 43 19 16 40 74 79 67 35 11 7 10 32 64 55 27 18 17 26 52 47 34 23 33 46 84 87 78 54 42 41 53 75 86 66 59 65 85 77 76 91 NUMBERS ASSOCIATED WITH INDICATING LIGHTS ARE TO BE ON THE INSIDE F ACEPLATE ABOVE INDICATORS LOCKHEED MISSILES & SPACE COMPANY, INC. DATE [/Ap/f_2., A SUDSID! ARY OF LOCKHEED AIRCR AFT CORPORAT
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2.2 PLANT PROTECTION CONTROL PANEL (CP-7) l l
23164-1 2.2 PLANT PROTECTION CONTROL PANEL - CP-7 CP-7 contains the indicators and the controls for the Plant Protection System (PPS) and the Engineered Safety Features Actuation System (ESFAS). The control panel is organized in four measurement enannels monitoring protective , NSSS and containment parameters. Besides the four measurement channels, CP-7 includes a set of manual controls for actuating ESFAS equipment to limit the consequences of an accident. Eacn measurement charmel includes indicating instrumentation for reactor parameters (neutron f lux, rate of power change, local power density, DNBR margin) RCS parametets (Pressurizer pressure, Bot leg and Cold leg temperatures), containment pressure and R4SP level. Each channel also includes recorders for key reactor and RCS parameters. Distinctive inserts are provided for each channel.
- A Plant Protection System Remoce Control Module indicating the reactor trip, pre-trip and the bypassed status lights for each monitored process parameters, and providing controls for the reset (adjustment) of the " Low Pzr. Press" and " Low SG Press" setpoints.
l1 the bypass of the " Low Pzr. Press" and " Low SG Press" setpoints, tne bypass of tne "dign Log. Pwr." and the calibration of tne "Excore Linear Power" secpoints.
- A CEAC/CPC Control Module, permitting monitoring of specific inputs and calculated values provided by the corresponding calculators.
Figure 2.2-1 snows the human factors enhancement drawing for CP-7. Figures 2.2-2 and 2.2-3 are pnotographs of this panel before and after enhancement. Six findings or dEDs were reported against CP-7. The disposition of these l findings are discussed below: B-1, Finding 22, Priority 1:
- 1. " Labels are excessively redundant. Abbreviations easily confused.
Font size appears small for a control witn this level of importance. EFAS selector SWs are labeled below S4 wnile all others are labeled above. 8FAS laoels for the same control are different from CP-7 to CP-8."
- 2. "Laoels are engraved on polished (silver) metal. Glare and poor contrast maxe readaoility poor."
Response
Hierarenical labeling has been provided. To tne extent possible words ratner tnan abbreviations nave oeen used. In addition the engraved silver plates nave been replaced by direct lettering on the panel. l1 2.2-1 Rev. No. 1, (12/82)
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i ,,,y j 2316W-2 y f 3j , p . / V -y, B-4, Finding 3, Priority 1: , hfv ['T "The Containment Spray Activation System pushbuttons near the front oQthe ! CP-7 benchboard are vulnerable to inadvertent actuation. The pushbuttons ar'J not guarded." $ # 7 7 i ... s .i n - / p
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! Guards will be provided for all ESFAS pusnbuttons by Hot Functional"7$ sting. l1' 1 The containnent spray buttons have been moved one position ug<away f/om the '.
4 front edge of the benchboard (DCN-IC-1009). Tne bottom buttons are spares and g"f v '; j y' 1 will be removed if not needed prior to Licensing. 9
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r B-5, Finding 25, Priority 3: - .,, c e-
- 1. "These critical meters'use multipliers (reading X100) in l'ieu off /
showing entire actual value on the scale. Other pres'sure meter [ ihow # , j-actual values, (e.g., 0-30 psia for Containment). '(Uther meters iAf d 4 control room show value X10.)" ,-
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" Wide range Adjacent narrow and rangesetpoint meters meter displays 20 ps display
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in,ia graduatio35.i40 (F ;j NtAEG ' > psia gra'd
- 0700, 6.5.1.5d). Cross reference can be e,onfusing. tW%13;er9ti6i4~j p pressure ot 2250 psia is at same-vertical point on the scales, aiding" u normal operation; but increases potential for confusion / error, readini,/ g 'e otner values." /,*
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The use of multipliers on meter scales 'is a standard ryaetice in~g' generally it s i represents only a minor nuisance to the-operators. 11 taken Alef.e t'aese might A' not be a significant discrepancy. However, the use of ,variout / silli' pliers /' , #kJ wnen space would permit actual values is one of seveisl factortishich can '~ I combine with others to result in poor meter scr.le' disp,l'ays.'pl'c these -
.i meters on CP-7 are felt to be acceptable all reters are presergly being .
reviewed, and any unduly confusing scales will be eninged prihr to Liceuing. l1 ~ yW j (Refer to Section 2.15, Generic Panel findings.).. , ";', .
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l Regarding the different scale graduations between wj,Le and hard rangP
- pressurizer pressure, the consequences of misreading valu p are consid; red to" be very slight since tne PPS is fully automatic and tne ope;ator would q,)9 r f ,
normally control pressurizer pressure from CP-2'. Ine dual e,cales provide some / l benefit as a way of checking the channel, reading.>
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" Containment wide range pressure measures from 0-40 psi. Narrow range I measures from 0-30 psi. Mixed scales on same meter make easy interpolation / reading difficult".
Response ,' . Tne subject containment pressure in .qators i are not for the monitoring of narrow and wide ranges. They are pr.;t'of',two independent loops; one for cantainment isolation (CIAS); And the geher-for containment spray (CSAS). As
shfv.n on ene enhancement drawing' (Fig'ure 2.2-1), labels to clarify this point will be prosided. No comparison of cne subject scales will be required. ly
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- 1. " Labels aI'c! elcessissly redundant. Abbreviations easily confused.
Font sizp appears ,small for a control witn this level of importance. I-{g EFAS safecypr SW's/are labeled below SW while all others are labeled above. EFAS, labels.for the same control are different from CP-7 to
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' :J Ref er to B-1, Fi;iding 22, auove.
B-d, Finding 34, Priority 1: - J.:
- , . s' "On CP-7 Containment Pressurce9$he Ab wide range meter is on right; on Pressurizer Pressutt' meters, dido Eange is on left.",
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Response -- -- { ,*' -p Refer to Pf$$ Findng 26. InemGhfrs for containment pressure had been i mislabeled. Inis will be corrected. Tne scales are separately provided for ly monitoring of- tne containment isolation actuation signal and the containment spray actuatton signal. .; I < i '/ G <
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l 2.3 CHEMICAL AND VOLUME CONTROL PANEL (CP 14)
2315W - 1 2.3 CHEMICAL AND VOLUME CONTROL SYSTEM (CP-4) CP-4 groups together tne indicators, recorders and controls for the chemical and volume control system (CVCS) and ties to the Boron Management System (BMS). The upper left side of the control panel includes the indicators for the key parameters of the letdown loop (temperatures and flow), Volume Control Tank leemperature, pressure and level) and charging loop (temperature and flow). The same row of indicators includes wide range and narrow range Pressurizer pressure instruments. A second row of instruments for the CVCS includes a pair of level indicators for tne boric acid makeup tanks, a pressure indicator for the RCP bleedoff header, and a set of recorders monitoring the process radioactivity, the boron concentration and the flows of primary water (for dilution) and boric acid (for boration). The next row (on tne inclined section of the panel) groups the valve control swi ches and the process control stations by loops (Letdown, Makeup, RCP Bleedoff) and equipment (Volume Control Tank). The benen section of the CP-4 includes a set of control switches for the Charging and Pressurizer Spray loops, flankea on both ' sides by groups of switenes controlling various related valves and tne Boric Acid Makeup pumps. The right side of the CP-4 (with the exception of the bench section) is dedicated to Boron Management System (BMS) related equipment. 1 The top row of indicators monitors the level and pressure of various tanks (Reactor drain, equipment drain, flash, holdup tanks). Three counters and three recorders on the same vertical section monitor the flow and tne radiation level of the boric acid condensate, liquid waste and gaseous waste. The inclined sectioc includes all control switches and control stations for tne various pumps, valves and tanks. A set o f two double-t race trend recorders are located on the vertical section between tne CVCS and the BMS sets of recorders. These recorders are driven by the plant monitoring computer and are able to record any key parameter of these two systems. Figure 2.3-1 is the CP-4 ennancement drawing; Figures 2.3-2 and 3 are pnoto's showing this panel before and after enhancement respectively. Sixteen findings or ilED's were reported against CP-4. The disposition of 1 these findings are discussed below. B-1, Finding 16, Priority 2:
- 1. "The panel meters that are located on One upper portion of the panel are placed too nigh. They are located beyond the optirum visual distance for good human engineering practices."
2.3-1 Rev. No. 1, (12/82)
2315W - 2
- 2. " Parallax in discrimination of the major / minor scales of the meter may result from the present location of many of the meters. Lighting reflections may increase the reading problem, especially for shorter operators."
Re sponse The control boards do not accommodate the 5th percentile female. However, the control boards are designed so that all the major controls and indicators are generally accessible and readable. If during startup testing and procedure validation a readability problem is discovered, then the individual component I will be evaluated and modified if necessary prior to Licensing. Light ing l changes will reduce reflective glare and ameliorate reading difficulties for the short er operators. Also refer to Section 2.15.5, Findings 14 and 15. B-4, Finding 6, Priority 3:
"Some key switches on CP-4 and CP-8 have a black ring, some do not. There is no functional consistency for the use of black and silver switches".
Response
This does not conflict with any color code convention utilized in the Main Control Room. Black is a neutral color; therefore no corrective action is warranted. B-4, Findi ng 15, Priority 2:
"On CP-4, some key switches have different key orientation from the key teeth down convention used in the Control Room".
Response
The key switch orientation has been reviewed and will be made consistent prior 1 to LJcensing. B-5, Finding 28, Priority 1:
"The two recorders adjacent to D-5 recorder waste flow in blue ink as per its window labels. D-5 rccorder charts waste flow in red ink which is not consistent with the other."
Response
The ink color markers will be corrected to red f or waste and green for radiation. < B-6, Finding 2, Priori ty 1 "ILese (valves) status indicators do not have labels to indicate status, i.e., valve position close-open." 2.3-2 Rev. No. 1, (12/82)
i 2315W - 3 NRC Review Team Comment: Refers to CP-4 Charging Pumps Reader discharge valve and PZR Aux Spray valve.
Response
l All controls have "open" or "close" position labels, associated with the 1 corresponding red or green colors. Indicators do not have labels, but use the red and green colors to provide status. These colors follow the uniform color convention for this purpose and are not seen as a problem to the operator. No confusion is expected. Associated controls are labeled according to the position selection. B-6 Finding 3, Priority 1:
" Refueling dater to Charging Pump This switen is not labeled."
Response
Labeling is now provided for tnis switch as can be seen in tne lower center bench board section of the enhancement drawing (Figure 2.3-1). B-6, Finding 26, Priority 1:
" Meter C-12 "(Equipment Drain Tank) is not adequately labeled to show parameter being measured."
i NRC Review Team Comment: One meter is labeled PSIG and another is labeled only %. This discrepancy also applies to tne Holdup Tank and the Reactor Drain Tank."
Response
Tne meters have been labeled to designate tne appropriate parameters as can be seen in the upper right portion of Figures 2.3-1 and 2.3-3. 3-6, Finding 33, Priority 1: The combination and sequential arrangement of the (charging) pump selector sets as now exist and displayed on the face plate of the charging pumps is difficult to follow. Tnere is no clear relationsnip between this switch selection arrangement and tne pump switches it refers to above it." i
Response
Tne meaning of the switen was misunderstood, it is now labeled correctly to indicate tnat it is a " backup pump" selector switch. Each position lists two pumps; the order of listing implies the sequence in whicn they will initiate as backups to the selected or primary pump. Labeling will reflect correct sequencing by dat Functional Testing. Refer to Figure 2.3-1. 1 1 2.3-3 Rev. No. 1, (12/82) l --,
r 2315W - 4 B-6, Finding 35, Priority 1:
"This vertical meter ic mislabeled. It is now labeled (Hold Up Tank D). It should be labeled (Hold Up Tanks Vent Header Pressure)" by Hot Functional Te s ting . >
Re sponse As shown on Figure 2.3-1 (upper right corner) this meter will be labeled, 1
" Hold Up Tanks, Vent Header Pressure" by Hot Functional Testing.
B-8, Finding 3, Priority 1 On CP-4, CVCS, there are duplications of controls; e.g. ,
- 1) Lutdown Containment Isolation VA IN
- 2) Charging Loop 1A Shutoff VA
- 3) Charging Loop 2A Shutof f VA
Response
There is no duplicatic., of controls on CP-4. Specifically, letdown Containment 1 solation Va, Charging Loop 1A Shut-of f Va, and Charging Loop 2A Shut-of f Va , have each an individual control switch with individual indication 1 lights. Labels have been provided to show inside and outside containment. B-8, Finding 17, Priority 1: The Letdown Valve selector, controller, and indicator are not on the same panel: e.g., Selector is on CP-4 Controller is on CP-2 Indicator is on CP-4 The distance between CP-2 and CP-4 is about 10'. Re spons e The controller has been transf erred from CP-2 to CP-4 as indicated on Figures 2.1-3 and 2.3-1. All controls and indicators for the letdown valves are now 1 located on CP-4. (DCN No's IC-837 and 1011) . B-8, Finding 25, Priority 1: The order in which A73 and A7 7 (Boric Acid Gravity Feed Valves) are arranged, Valve B to the lef t of Valve A is poor. This arrangement breaks control board conventions and human expectations".
Response
As can be seen on Figure 2.3-1 (bench board section, middle right), these valve control switchet, will be repositioned 3 ito the proper lef t to right sequence by Hot Funct ional Te sting ( DCN-IC-413) . Ide switch f or valve A is on 1 the lef t and the switch for valve B is on the right. 2.3-4 Rev. No. 1, (12/82)
i i 2315W - 5 B-8, Finding 28, Priority 2:
"On CP-4 there is an inconsistent lef t to right, top to bottom numbering convention; i.e. ,
- 1. Boric Acid Tank B and A Gravity Feed Valve
- 2. Charging Loop 2A and 1A valve controls."
)
Response l
- 1. Refer to B-8 Finding 25, above. !
l l
- 2. Charging loop 1A valve switch will be moved to the lef t and charging 1 I loop 2A valve switch to the right on CP-4 by Hot Functional Testing.
B-8, Finding 33, Priority 1: The placement of C-ll and C-12 (Equipment Drain Tank) does not follow pattern set by the adjacent meters, that is (psig) TK vent, followed by (level) DRB TK."
Response
The subject meters have been interchanged (DCN-IC-1011) as can be seen in the upper right section of Figure 2.3-1. B-9, Finding 5, Priority 1:
" Operator states that letdown flow is controlled on CP-2 (ltem 1) and indicated on CF-4 (Item 2). Letdown back pressure is indicated on meter at lef t of back pressure controller on CP-4 (Item 3) . During manual operation, either control will af fect both indicators. Operation will be a difficult t wo-m a n j o b. "
NRC Review Team Comment: Centro 11er and display are approximately 8 feet away from the Valve A, B, and both selectors."
Response
Refer to Section 2.1, Reactor Control Panel Findings B-8; 17 and B-9; 5. Letdown flow control has been transferred to CP-4, therefore, both controls 1 and indicators are on the same panel. B-9, Finding 6 Priority 1:
" On C P-4, the association between the gross coolant activity recorder and the pushbuttons/ indicators above it is not clear."
Response
The indicators show the operator the selected range on the process radiation recorder. Enhancements have been provided to show this relationship. 2.3-5 Rev. No. 1, (12/82)
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2.4 POWER CONVERSION AND DISTRIBUTION PANEL (CP-1)
2329W - 1 2.4 POWER CONVERSION AND DISTRIBUTION PANEL (CP-1) CP-1 includes the indicators and controls of the Main Turbine Generator, the Emergency Diesel Generators, their electrical distribution network and their related systems and subsystems. The eq-sipment grouped on CP-1 corresponds to the continuous operational needs for ruaning these systems and subsystems, while the equipment required only for status recording, occasional supervision, or for operation in infre(uent, non emergency situations (like start up) is located on separate control panels (e.g., CP-13 for the main turbine and related subsystems or the lecal control panels for the Emergency Diesel Generators) . Da the left side of the vertical section of CP-1 are located the key parameter indicators of the Main Generator (including the exciter), the synchroscope and the Main Generator Lockout Trip pushbuttons. On both sides of this cluster are located the indicators, synchroscopes and Trip Pushbuttons of the Emergency Diesel Generators (EDG's), as well as light indicators showing the transfer of controls between the Main Control Board (MCB) and the EDG Local Control Panels. On the lowest row of the vertical section are located the control switches for testing the under voltage relays of buses A, B and AB, as well as the control switches for testing the sequencers A and B, with corresponding light indicators showing the sequential loading of the diesels. On the inclined and bench sections on the left side of CP-1 is located the Mimic of the station power distribution network, with lights indicating the main breakers status, switches for operating the breakers, for starting and for adjusting the speed of the EDG's, and for adjusting the voltage of all three generators. On the right side of the vertical section of CP-1 are located the indicators for key par' meters of the Main Turbine, Conde nsa te , Blowdown, Steam Generators, Feedwater Pumps, FPT and Auxiliary Steam. Below the Main Turbine indicators are mounted the Turbine Trip pushbuttons, the indicating lights showing the trip coil status and the Condenser Vacuum Breaker control switch. Farther below on the vertical section and on the inclined and bench sections a re located the DEH Control System inserts and switches controlling the Turbine Oil Pumps and the E-H Fluid Pumpe. On the right side of CP-1 are also located the following clusters of instruments: Indicators and switches for the control of the Turbine Ge ne ra tor Temperature Control Valves, Moisture Separator Reheater Valves, Blowdown Valves, Turbine Drains and Extraction Valves.
- Control btations, switches and indicators for the Steam Bypass, Feedwater, Condensate and Blowdown loops.
2.4-1
i 2329W - 2 Control switches and status indicators for the Heater Drain Pumps, Circulating Water and Screen Wash Pumps, River Water Pump, Air Evacuation Pump, Primary Wa ter Pumps and Condensate Vacuum Pumps. A set of pushbuttons for the annunciator control completes the CP-1 equipment. The enhancements for CP-1 are shown on Figure 2.4-1. Thirteen findings or Human Engineering discrepancies were reported against CP-1. These findings and their disposition are discussed below: B-4, Finding 8, Priority 1 "On CP-1 there are intenmixed status lights and pushbutton controls which are the same size and appearance with no differentiation between those that are indicators and those that are controls." Re spons e LP6L will ensure that the enhancement effort adequately differentiates status lights and pushbutton controls located on CP-1 that are of the same size and a p pearanc e. This is a surf ace ennancement process and the changes will be 1 completed by Hot Punctional Testing. B-5, Fi nding 13, 'ri cri ty 1 l
"Re ference meters are dual pointer units. Content of upper and lower meters are the same in each case: LP TURB ( A, B or C) STM INLET."
i Response I' 1
- Labeling will be corrected prior to Hot Functional Testing.
I B-5, Finding 15, Priority 1 "Both meters display 0-33 ( AC volts x 1000) . On C20, umeric values are present at intervals of 10. On C23, numeric values are yreient at intervals of 5." I NRC Review Team Comment: One meter is Running Bus; other is AC GEN VOLTS.
Response
Indicator C20 is used only during synchronization of the main generator. Indicator C23 is a permanent display of generator voltage. Scales will be changed to be consistent by Hot Functional Testing. 1 1 I 2,4-2 Rev. No. 1, (12/82)
; 2329W - 3 B-6, Finding 5, Priority 1 I
" Association of dual action controls and association of "think" button and applicable controls are not shown."
Response
As part of the surf ace enhancement, lines were added to show the relationship of these switches. i B-6, Finding 8, Priority 1
" Circuit breaker indicators (not micro-switches) are not labeled. Bus l sections are labeled."
Re sponse Corrections / completion of the mimic on CP-1 will be provided by Hot Functional 1 Te s ting . Enhancement will include the labeling of the circuit breaker status indicating lights. l I B-6, Finding 12, Priority 1 "On the mimic on CP-1 and CP-2, there are sets of indicator lights that are either not labeled or not inscribed." Re sponse LP&L will provide labels or inscriptions, whichever is appropriate, as part of 1 the enhancement ef f ort by llot Functional Testing. B-6, Finding 48, Priority 1
" Mimic of diagram of power flow to transformers supply power to plant equipment is incomplete and inaccurate."
Re sponse Correction / completion of the mimic on CP . will be provided as part of the 1 enhancement ef f art , prior to liot Functio .a1 Testing. B-8, Finding 1, Priority 1 Panel review by lluuan Engineering personnel and Waterf ord-3 operators indicates that existing arrangement of panel elements does not re flect f unctional relationships as understood by operators in all cases. 2.4-3 Rev. No. 1, (12/82)
i 2329W - 4 NRC Review Team Comment: Examples:
- 1. River water pump control is separated from circulating water system i con trol s.
- 2. Condensate vacuum pump system controls are located at the lower lef t bottom sloping panel and the Condenser Exhaust Selector control is located 1 at the lower right of bottom sloping panel.
- 3. COND to MAKEUP TIE (TK) VALVE located in middle of the right lower sloping panel.
4 Cond Vac. Brkr, Cond. B Vac. recorder are located on the upper lef t vertical panel below annunciators, i Respons e
- 1. River Wa ter Pump is used during the plant shutdown to provide make-up water to. f.he Prima ry Water System via circulating water system pipes.
2 This is an appropriate location for the condenser exhaust selector control switch. Euhancement effort will address functional relationship problems by Hot Functional Testing.
- 3. The control switch f or condensate to make up tie valve has been removed.
4 Condenser vacuum breakers control switch and condenser vacuum recorder are located on the vertical section of the control panel. This is an appropriate location f or this equipment . B-8, Finding 7, Priority 1 "On CP-1, steam generator pressure is shown only as combined value on indicator SBCS master controller. Individual Steam Generator pressures are shown only on CP-8. Operator desires individual Steam Generator pressures on CP-1, at least to help localize a tube rupture. Isolation valve controls are o n C P-1. " NRC Review Team Comment: Isolation valve controls are on CP-8. Re sponse Individual steam generacor pressure indicators are being added to CP-1 ( DCN-IC-1014) . B-8, Finding 8, Priority 1 "Re ferenced switch controls river water supply. It is located between feedwater and blowdown areas of the panei. It is minimally related to either of those groups." 2.4-4 Rev No. i, (12/82)
2329W - 5 Re sponse
, River Water Pump is operated only during complete shutdown of the plant to provide the make-up water to the Primary Water System. Functionally, the River Water Pump is not related to any other equipment on the control panel except that it belongs to the balance of the plant.
B-8, Finding 35, Priority 1 "On CP-1 and CP-8 there are groups of 10 meters in a row, instead of the recommended maximum of five in a row."
Response
1 There is one group of 10 meters in a row on panel CP-1. All meters in that group are monitoring main turbine parameters. There are two groups of 10 meters in a row on panel CP-8. All meters in one group are monitoring parameters of the Safety Injection System in Safety Channel A, the other group for Safety Channel B. In addition, lines of demarcation clarifying the 1 association of the meters will be provided by Hot Functional Testing. t B-9, Finding 9, Priority 2 "The f our raferenced elements (Cooling Water Temp and Press Controls) ate located in a vertical column, the two meters above the two switches. The i upper meter and upper switch are associated, and the lower meter and lower switch are associated. Thus, associated meters and switches are not adjacent." i Response Whenever the operator adjusts this system he has to move both valves. Since indicators are adjacent to each other LP&L feels that it is highly unlikely that he will not see the proper valve movement indication. Furthe rmore , labels showing temperature and pressure association have been provided. B-9, Finding 11, Priority 1 l " Operators repot, that Turbine Generator Temperature Control Valves will be difficult to operate with desired or necessary precision. Possible violation o f NUREG-0 700, Pa ra. 6.9.3.2.a." NRC heview Team Conment: Operators agree that the indication on valve position is adequate (0-100%) , bu t there may be a question concerning valve travel rate (%/sec) . Re sponse No di f ficulty is anticipated with the modulating control valves. Va lve position indication is provided over the full range and the temperature is also indicated. No problem with the valve travel rate is anticipated based on experience at other operating plants. The adequacy of the valve travel rate will be confirmed during startup testing and documented prior to startup 7 3 following the first re f ueli ng . l 2.4-5 Rev. No. 1, (12/82)
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i l 2.5 TURBINE STARTUP/ SUPERVISORY PANEL (CP-13) l l
2323W-1 2.5 TURBINE STARTUP/ SUPERVISORY PANEL (CP-13) CP-13 includes all recorders, but only part of the indicators and controls pertinent to the Main Turbine and its related equipment (Feedwater Pump Turbines, Heaters, Drain Loops). While the equipment required by the continuous operational needs concerning the Main Turbine is located on CP-1, the instrumentation required for status recording, supervision and operation in infrequent, non-emergency situations (like start up) is mounted on CP-13. / The top-center section of control panel is occupied by the annunciator cabinet A (including all alarms related to the Heaters, Moisture Separator - Reheater and Water detected in the steam lines). Left of the annunciator cabinet is located a cluster of indicators for the following Turbine parameters: speed, acceleration, rotor eccentricity phase angle and rotor vibration phase angle. On the right side, the annunciator is flanked by the Feedwater Pump Turbines A and B recorders. A second row of recorders monitor the turbine bearing temperature 2 (bearing oil and bearing metal), the turbine metal and steam temperatures, the rotor vibration and eccentricity, the casing expansion and the differential expansion, the rotor speed and rotor position. Below the recorders, the following clusters of instruments are mounted in'a horizontal row: Indicators and switches for the control of drain valves. Indicators and switches for the control of heater valves.
- Control switches for the operation of Nitrogen Supply and Vent Valves.
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- Control switches for the operation of FWPT steam line drain valves,
- condenser air exhausters, gland seal leakof f pump, heater bypass valves and L P heaters isolation valves.
The lower seccion of the CP-13 is occupied by the Feedwater Pumps Turbine Monitor Drawers (eccentricity, vibration and thrust bearing wear) and the Main Turbine Monitor Drawers (eccentricity, vibration, rotor position, casing expansion, differential expansion, speed and additive valve position). A set of pushbuttons controlling the annunciator and a vibration detectors i reset pushbutton (for the large motors) are also located on CP-13. The enhancements for CP-13 are shown on Figure 2.5-1. A post enhancement l I photograph is provided as Figure 2.5-2. Six findings or Human Engineering discrepancies were reported against CP-13. These findings and their disposition are discussed below: B-3, Finding 19, Priority 2 "The annunciator controls for annunciator panel B on CP-33 are located on CP-13." 2.5-1 Rev. No. 1, (12/82)
2323 W-2
Response
The annunciator control pushbuttons for CP-33 and CP-13 are located on CP-13. Since these panels are adjacent no significant operational problems or confusion is anticipated. The operators will be trained to absorb the annunciated message before acknowledging from the pushbutton station. There~ 1 is no need for the operator to be in front of the pushbutton while reading the annunciator. Moving the pushbutton station to the right side of CP-13 was considered, however internal wiring and structural supports precluded this move. B-5, Finding 18, Priority 3 1
' "There is extraneous infonnation on meter faces 1scated on CP-13 (e.g.,
circular meters indicating phase angle, vibration, and speed) ."
Response
- The label will be removed from the meter scale as per EDN-EC-447 and y hierarchical labeling will be added prior to Licensing.
B-6, Finding 39, Priority 1 "There is inconsistent labeling on CP-13 ; e.g. , on " Heater" subpanel,1 & 2 indicates HP, 3 & 4 indicates IP, 5 & 6 indicates LP. On " Heater bypass" sub-panel, HP indicates HP, IP indicates IP, LP indicates LP.
Response
t Labeling has been corrected as part of the enhancement ef fort. B-8, Finding 5, Priority 3 "The vibration reset pushbutton for the cooling tower f ans is presently I located on CP-13. There are no other cooling tower related controls or displays nearby. It should be placed near cooling tower fan controls on CP-33." i
Response
The vibration reset pushbutton is for all large motors, not just cooling tower fans. Tnerefore, the proper corrective action shall be to relocate the annunciator from CP-33 to CP-13 (DCN-IC-987) and labels will be corrected by Hot Functiona l Tes ting. B-8, Finding 11, Priority 2 1
- "On CP-13 displays and controls related to turbine / generator shaf t vibration l are separated by a group of controls and displays associated with secondary side s team extraction and drains. Panel demarcation and associated labeling is not clear and does not compensate for the poor layout. .There are two
< unassociated controls on the panel, i.e. , a reset pushbutton for annunciators on CP-33 and a CR Potable Water switch." i 2.5-2 Rev. No. 1, (12/82) I
2 323W-3 j Re spons e The location of recorders in the upper part of the panel is appropriate. The location of the power drawers that process field signals for display indicators, recorders, and alarms are also appropriate in the lower part of i the panel since they have no direct relation to the rest of equipment on that panel and could have been located, as a group, outside of that panel with no effect on operational procedure. The layout of the control stations on panel CP-13 is functionally correct and is in proper sequence to provide a clear supervision of equipment operation to the operator. The annunciator pushbuttons located on panel CP-13 are associated with annunciator display cabinets located on panels CP-13 and CP-33. The Control Room potable water control switch is provided to enable the operator to quickly isolate potable water to Control Room in case ;,f potable water pipe break within the confines of the Control Room, thus preventing flooding of essential control circuits. This is a regulatory requirement and control switch is located at extreme lef t of all controls in the Control Room to assist in quick location of the control switch in case of need. B-8, Finding 30, Priority 2 r
"On CP-13 the Extraction Steam Heaters controls / displays are layed out in a dog leg arrangement."
Response
Feedwater heaters consist of two groups; high and low pressure. High pressure heaters are grouped on the lef t and low pressure heaters are grouped on the ri gh t . There fore , the board components are properly arranged within each group of heater s. Enhancements will be provided by Hot Functional Testing to y better clarify the arrangement. Re fer to Figure 2.5-1. 2.5-3 Rev. No. 1, (12/82)
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i ;' , s, , / . . , V ' CP-13 includes the protective relays fer the followfng equipclent: #
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The enhancements for CP-15 are shown on fig'u;ry; 2.6-1. Before and after ennancement photographe are providea as Figt.6'e= 2.c 2 and 3, res;sectively. J,1 :
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.a ? g There were no specific findings against CP-15, however, any af' the generic i findings (Section 2.15) applicable to CP-15 Feve 'been aJdressed us described-in Section 2.15.
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i 2.7 ELECTRICAL MONITORING PANEL (CP-17)
2323W-5 2.7 ELECTRICAL MONITORING PANEL (CP-17) CP-17 includes on its front panel the following instruments: I Three recorders monitoring the Main Generator frequency (Hz), the Main Generator power (NW) and the Grid Voltage (V). Three energy (KWil) meters totalizing the Generator gross power, the power transmitted to the 4kV switchgear and the power transmitted to the 7kV switchgear. The Automatic Synchronizer. The enhancements for CP-17 are shown on Figure 2.7-1. Before and after enhancement photographs are provided as Figures 2.7-2 and 3, respectively. Findings There were no specific findings against CP-17, however, any of the generic findings (Section 2.15) applicable to CP-17 have been addressed as described in Section 2.15. 2.7-1
FIGURE 2.7-1 1 CP-17 ELECTRICAL MONITORING AUTOMATIC SYNCHRONIZER GENERATOR FREQUENCY r_ - _ GENERATOR NET POWER SWITCHGEAR
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2,8 ESFAS TEST AND COOLING TOWERS AND CONTAINMENT HYDROGEN MONITOR AND RECOMBINER C0iiTROL PANEL (CP-33)
'l 2323W-6 2.8 ESFAS TEST AND COOLING TOWERS AND CONIAINMENT HYDROGEN MONITOR AND RECOMBINER CONTROL PANEL (CP-33)
The top-center section of the CP-33 is occupied by the annunciator cabinet B, including alarms related to HVAC systems, various sumps, the Hydrogen Analyzer, the CCW/ Auxiliary CCW loops and their cooling towers. Lef t and right of the annunciator cabinet are located clusters of indicators corresponding respectively to the loops A and B of the CCW (temp) auxiliary CCW (flow), wet tower basin (temp) and Hydrogen Recombiner (temp and power). Below these indicators are located tne Hydrogen Analyzer recorders for the corresponding A and B systems, together with their sample selectors. Further down on tne lateral sections of CP-33 are located the selector switches for the corresponding Hydrogen Analyzer and Recombiner Systems. On the central section of CP-33, below the annunciator cabinet B, are mounted the ESFAS Test Modules A and B and ESFAS Reset Pushbuttons. Below these modules are located two clusters (A and B) of selector switches for the control of cooling tower fans, valves, and Auxiliary CCW Pumps. Two control stations, for the auxiliary CCW A and B temperature control valves, are also mounted on CP-33. Tne enhancements for CP-33 are shown on Figure 2.8-1. Before and after enhancement pnotographs are provided as Figures 2.8-2 and 3, respectively. Eleven findings or Human Engineering discrepancies were reported against CP-33. 1hese findings and their dispositions are discussed below: B-1, Finding 5, Priority 1 "To reser reactor safety injection, tne operator must go to a back panel in the Control Room for the master reset and down to the next elevation below the Control Room tor the slave reset."
Response
A duplicate of the slave reset will be provided on CP-33 in the Control Room prior to fuel load. B-3, Finding 19, Priority 2 "The annunciator controls for annunciator panel B on CP-33 are located on CP-13."
Response
The annunciator control pushouttons for CP-33 and CP-13 are located on CP-13. Since these panels are adjacent no significant operational problems or confusion is anticipated. Tne operators will be trained to absorb the 2.8-1 Rev. No. 1, (12/82)
2323W-7 annunciated message before acknowledging fram the pushbutton station. There is no need for the operator to be in front of the pushbutton station while reading the annunciator. Moving the pushbutton station to the right side of CP-13 was considered, however internal wiring and structural supports precluded this move. B-4, Finding 2, Priority 1
" Dry Cooling Tower Fans - Micro-switches
- 1. In order to turn the 4 position micro-switch from AUTO to 0FF, it must be switched through the MANUAL FAST and through the MANUAL SLOW positions.
- 2. It was reported that the CWD's indicated push to activate 4 position micro-switches. If this is true, the hardware in the Control Room differs from that indicated by the CWD's.
- 3. These same 30 DRY COOLING TOWER FAN micro switch controls are repeated on LCP-43, the Emergency Shutdown Panel. On LCP-43 the controls are 3 position (there is no AUTO mode) PUSH TO ACTIVATE. The controls should be identical at the two locations."
NRC Review Team Com=cnt: Items 2 and 3 are not discrepancies.
Response
l The problem indicated by paragraph I has been corrected per DCN-IC-885. Now j the switch can go directly from auto to off. B-4, Finding 21, Priority 3 "On CP-33 when the Containment Hydrogen Detection lower rocker switch is pushed to the ON position, the lower rocker is flush with the panel surface, making it difficult to depress the switch to the OFF position."
Response
. LP&L has reviewed this llED; after having the rocker switch operated repeatedly to ON and 0FF positions by various operators, no problem with this operation could be found.
B-5. Finding 2, Priority 3 "Of the 15 dry cooling tower fans on the A side and 15 on the B side, 9 of the A and 9 of the B fans are missile shielded and 6A and bB are not. Operators indicated this would be useful information and it is not presently indicated on the control panel."
Response
This item has been corrected as part of the surf ace enhancement effort. 2.8-2 Rev No. 1, (12/82)
3323W-8 B-5, Finding 45, Priority 1
" Hydrogen Analyzer
- 1. The scale is from 0-100 with numerals in units of 10. The area of interest when monitoring hydrogen concentration is from 0-30%.
- 2. Hazardous levels (caution and danger) should be coded on scale (below 30%). Physical breadth on recorder paper is very narrow for quickly discerning trend and/or actual concentration level. Available width is
, wasted."
Response
This scale will be corrected by Hot Functional Testing to show 0-10% (vol) I which is what the analyzer actually measures. This range is required by TPE , task Tssk II.F.1. The lower flammability limit of hydrogen in a steam-air i atmosphere is approximately 4% (vol). Hazardous levels need not be coded f since an alarm is provided on CP-33 when concentrations approach 3% (vol). 1 The correct scale will make the concentration trend more obvious. I ( FCR-IC-E-18 7) . l1 B-6, Finding 46, Priority 1 "There is incomplete use of demarcation in the Control Room r.nd remote shutdown pane l; e.g. , LCP-4 3, CP-1, CP-2, CP-18, CP-3 3." 4
Response
Surf ace enhancement effort will correct this deficiency on the main boards by 1 Hot Functional Testing. LCP-43 will be enhanced prior to Licensing. B-8, Finding 5, Priority 3 Pu shbutton CP-33 "The vibration reset pushbutton for the cooling tower f ans is presently located on CP-13. There are no other cooling tower related controls or displays nearby. It should be placed near cooling tower f an controls on CP-33."
Response
The vibration reset pushbutton is for all large motors, not just cooling tower fans. Therefore, the proper corrective action shall be to relocate the annunciator from CP-33 to CP-13 (DCN-IC-987) and labels will be corrected by 1 Hot Functional Testing. B-8, Finding 10, Priority 1 i 1 Dry Cooling Tower Fans - Labels The dry cooling tower f an number sequence on CP-33 in the Control Room does not c orrespond wi th tha t on the CWD 's. This discrepancy was reported by operators and was verified by looking at tne cable wiring schemes. 2.8-3 Rev. No. 1, (12/82)
2323W-9 a
Response
DCN-lC-885 has been issued to correct this problem. Re fer to Figure 2.8-1. - B-8, Finding 32, Priority 3 1 On CP-33 partial mirror imaging exists, e.g., H2 Analyzers and H2 Rec ombiner s.
Response
Two redundant Hydrogen Analyzers and Recombiners are located one at extreme lef t and one at extreme right of the control panel for channel separation i purposes. No mirror imaging exists in this case. B-9, Finding 1, Priority ) i Wet Cooling Towers - Meters Controls for wet cooling tower equalizing valves A and B are located on CP-33. The two meters displaying water level in the Wet Cooling Tower Basins A and B are on CP-8, Engineered Safeguards Panel. i NRC Review Team Con =ent: Panela CP-8 and CP-33 arc acreas the room from each other.
Response
i The tena " equalizing valves" is a misnomer and project documents will be l1 ! corrected by Hot Functional Testing to refer to Valves 3CC-F285A and 286B as i "cro s s-t ie valves" . It would be an error for the operators to try to maintain the same level in both wet cooling tower basins using the cross-tie. The two wet cooling towers are independent. The cross-tie between the wet tower ! basins was provided because NRC Reg. Guide 1.27 stipulates that a single l mechanistic f ailure of a man-made structure be postulated in the case of the ultimate heat sink. In the unlikely event that the cross-tie is ever needed, e.g. , as a backup source of makeup water post tornado, there is more than adequate time for the operators to walk from CP-8 to CP-33. Separating the cross-tie function from the basin level indication is a good design; however, this finding will be b rough t to the attention of the operators by the training program prior to Licensing in order to eliminate any confusion caused by previous reference to 1
" equalizing valves".
2.8-4 Rev. No. 1, (12/82)
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2.9 ENGINEERED SAFEGUARDS ^ PANEL (CP-8) i I l t l l
7 2333W-1 2.9 ENGINEERED SAFEGUARDS PANEL (CP-8) CP-8 includes indicators, recorders, control switches and control stations for a variety of systems and subsystems, most of which are part of, or related to the Engineered Safety Features Actuation Systems (ESFAS). CP-8 includes also a pair of Reactor and ESFAS Trip pushbuttons and a set of annunciator control pushbuttons. The top row of indicators provides the key parameters for the two Safety Injection System loops, the levels of the condensate storage pool, refueling water storage pool, wet cooling tower basin, the level of the steam generators and the pressure at the discharge of the Emergency Feedwater Pump. The middle section of the second and third rows of indicators includes four measurement channels (SMA, SMB, SMC, SMD) for the pressure and level of the steam generators, together with two recorders for the same parameters. Indicators for the CCW system status (loops A and B) are located left and right of the steam generator instrument clusters and the shutdown cooling loops A and B. Below these indicators, on the lateral zones of the vertical section, are located the following: Control switches for the Main Steam and Main Feedwater isolation valves test. Light indicators for the personnel airlock interior and exterior doors status. Indicators for the key parameters of the Containment Spray System. - Recorders for the key parameters of the containment and the Shutdown Heat Exchangers. The central zone of the vertical section of the CP-8 includes two clusters (channels A and B) of pushbuttons and switches for the manual initiation of the Engineered Sa fety Features. At their right are located the Reactor Trip pushbuttons (channels B and C) . The central zone of the inclined section includes indicators for key parameters of the turbine-driven EFW pump AB, light indicators for the EFW pump turbine governor and stop valves position, light indicators for the bus AB status ( fed from bus A or from bus B), selector switches for the 11 PSI pumps A or B selection and for the CCW pumps A or B selection, control switches for the EFW pump turbine stop valves, for the HPSI pump AB and for the CCW pump AB. Left and right of this " AB" zone, the inclined section of CP-8 includes the " A" and "B" clusters of control switches and control switches related to the main steam and main feedwater isolation, containment isolation, containment spray , emergency feedwater loops, RCS vent valves, atmospheric steam dump, steam generator blowdown, etc . The cent ral zone of the benen section includes the LPSI flow control stations, the control switches and indicating lights. The Annunciator control pushbuttons are located in the same central zone. , 2.9-1
2333W-2 Lef t and right of the central zone, the bench section of CP-8 includes control switches, light indicators and analog position indicators f or the valves of the following loops:
- Low Pressure Safety Injection - liigh Pressure Safety Injection - Saf ety Injection Tanks nitrogen filling, venting and isolation - Containment Isolation - Sampling The enhancements f or CP-8 are shown on Figure 2.9-1. Sixteen findings or liuman Engineering discrepencies were reported against CP-8. These findings and their dispositions are discussed below.
l B-3, Findi ng 7, Priority 1 "The SI tank (meter) displays on the lef t side of CP-8 (under annunciator panel H) have their corresponding annunciator on panel N - located on the right side of panel. The SI meters on the right have their annunciator on the left."
Response
The subject alarms and associated indicators on CP-8 will be rearranged prior 1 to lio t Punctional Testing. ( DCN-IC-1010) B-4, Finding 4, Priority 1
" Reactor trip pushbuttons on CP-2 and CP-8 do not have protective housing as described in NUREG-0700, page 6.4-4, Exhibit 6.4-1. Turbin'e trip pushbuttons c n CP-1 do have these housings."
Re sponse Guard s will be provided on reactor trip pushbuttons (DCN-IC-1009) . The identical type pushbuttons presently used for turbine trip including the 1 protective housing will be provided by llot Functional Testing. B-5, Finding 3, Priority 1 "Saf ety Injection Tank Display The two meters appear to be measuring the same parameters. Why the duplicate instrumentation? If the globe valve (s) stuck, what assurance would the operator have that both instruments would remain accurate?" 2.9-2 Rev. No. 1, (12/82)
2333W-3
Response
Refer to B-5, Finding 7 below. B-5, Finding 4, Priority 1 " Safety injection Tank Pressure Duplicate instrument (C-52 measurement of C-53). Both transducers operate f rom the same side of the globe valve, adding no additional reliability to the reading / comparison. Determine why two meters display the same parameter. Determine if the meters are redundant." NRC Review Team Comment: Also see B-5.3, B-5.5
Response
Re f er to B-5, Finding 7 below. b-5, Finding 5, Priority 1 " Safety injection Tank Pressure Meters seem to be duplicate. See HED Number 12. The two meters appear to be measuring the same parameters. Why the duplicate instrumentation? If the globe valve (s) stuck, what assurance would the operator have that both instrumente. would remain accurate?" NRC Review Team Comment: Also see B-5.3, B-5.4
Response
Refer to B-5, Finding 7 below. B-5, Finding 6, Priority 1 "Saf ety injection Tank Pressure Duplicate instrument C-42 repeats measurement of C-43. Both transducers op2 rate from the same side of the valve. Additional reliability to the reading / comparison is questionable." NRC Review Team Coument: This and B-5.7 are repeats of B-5.4, B-5.5.
Response
Refer to B-5, Finding 7 below. B-5, Finding 7, Priority 1 " Safety injection Tank Pressure Repeetts meascrements of C-42. Since both transducers operate from the same side of the valve additional reliability to the reading / comparison is questionable.' 2.9-3
l 1 2333W-4 4 NRC Review and Team Comment: This and B-5.6 are repeats of B-5.4 and B-5.5. Re spons e a
! The narrow range of Saf ety Injection Tank's level and pressure is measured and j displayed on the main control panel with two independent loops of j
instrumentation. The two independent loops of instrumentation are provided for each parameter to ensure the means of quick verification of one meter display by comparison with display of another identical and redundant meter. ' B-5, Finding 32, Priority 1 i "The pressurizer pressure and setpoint dual meter is loosely mounted on CP-7. l1 I This condition could allow vibration of the meter which in turn could cause erroneous readings." t Re sponse i The pressurizer pressure and setpoint dual meter is secured. All meters in the Ibin Control Room have been verified for proper installation. B-8, Finding 2, Priori ty 2 I i " Current (Steam Generator and CCW Controls) arrangement can be improved upon to af ford a better grouping of related controls." l
Response
Ref er to B-8, Finding 4 below. , B-8, Finding 4, Priority 2 f 2
" Current (Steam Generator and CCW Controls) arrangement can be improved upon to present a more accurate relationship between controls."
- Response
; Steam generators and CCW system controls will be rearranged by Hot Functional 1 i
Testing f or better grouping per DCN-IC-1010. l l B-8, Finding 19, Pri ori ty 1 i l " Identical side-by-side vertical meters that provide exactly the same information from redundant sensot s located at the same spot are found at f several places in the Control Room (e.g. , CP-8) . The rationale for the ' a rrangemen t is tha t i t provides a check on the sensor (s)/ wiring / meter (s) involved. These duplicated meters are buried in the middle of a longer bank j i of similar meterr- nnd are not readily distinguishable from other meters in the l s t ri ng . That arrangement makes f ast, accurate perf ormance of the desired comparison difficult." i l l 2.9-4 Rev. No. 1, (12/82)
2333W-5 Re sponLa The indicators displaying redundant parameters will be located side by side on 1 CP-8 by Hot Functional Testing to provide means of a quick check on accuracy and perf ormance of redundant instrumentation loops by visual comparison of their displays. Enhancement efforts will help operator to compare data fast and accurately. B-8, Finding 20, Priority 1 "On CP-8 enhancement techniques, such as spacing, demarcation, and color shading, are not used for setting apart groups of controls and displays." Re sponse The association between controls and displays, as well as, functional groupings, wherever found to be unsatisfactory, have been corrected by DCNs. 1 Demarcation and enhancement techniques such as hierarchical labeling will also be provided by Hot Functional Testing. B-8, Finding 23, Priority 2 On CP-8 displays which are observed in a specified sequence are not grouped together. Example: S1 TANK PRESS S1 TANK LEVEL i
Response
Displays on CP-8 will be relocated by Hot Functional Testing per DCN-IC-1010 1 B-8, Finding 26, Priority, 2 "EFW Pump Ibrbine - AB Stop Valve Switch is not located within the appropriate group of controls. A functionally more appropriate location should be found giving the criticality of the control." Re sponse The EFW Pump Turbine Stop Valve is not used for control of the turbine. The valve is used to provide overspeed protection to the turbine and is appropriately located on CP-8 within the safety channel AB area. Im proved y hierarchical labeling by Hot Functional Testing will facilitate the location of the switch by operator. B-8, Finding 3 5, Priority 1 "On CP-1 and CP-8 there are groups of 10 meters in a row, instead of the recommended maximum of five in a row." 2.9-5 Rev No. 1, (12/82)
a j 2333W-6 t
! Re spons e There is one group of 10 meters in a row on panel CP-1. All meters in that group are monitoring main turbine parameters. 'Ihere are two groups of 10 meters in a row on panel CP-8. All meters in one group are monitoring i parameters of the Safety Injection System in Safety Channel A, the other group g i f or Saf ety Channel B. In addition, lines of demarcation will clarify the association of the meters by 'bt I Functional Testing.
B-9, Finding 8, Priority 2
- 01 CP-8, multiple controls and displays related to the same function are not grouped tonether, (e.g. , SI TANK VENT VA) ."
Response
a Controls and displays are being rearranged on CP-8 per DCN-IC-1010 and y i enhancements will further improve the control display relationship by Hot
! Func tional Testing.
t i 1 il l l I, i l l l l t i I 2.9-6 Rev. No. 1, (12/82)
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I - 2.11 THE CONTROL ROOM ANNUNCIATOR SYSTEMS
2335W-1 2.11 THE CONTROL ROOM ANNUNCIATOR SYSTEMS The Control Room is provided with two distinct Annunciator Systems:
- 1. The safety-related annunciator system composed of two cabinets (SA and SB) is seismic Category 1, Class IE; located at the top of CP-18,
- 2. The non safety annunciator system composed of 12 cabinets ( A through N) is located as shown on Figure 2.11-1.
Annunciator cabinets SA and SB are identical, each one having a capacity of 5 columns x 9 rows = 45 alarm windows. Both cabinets are of integral design and include their own separate power supplies, logic circuits and their own horns. The bench section of CP-18 includes two distinct and separate sets of pushbuttons (" Test", " Clear" and " Acknowledge") for the independent control of the two annunciator cabinets. Two white lights connected in parallel are used for each window. The " Test" operation simulates an alarm condition, with all windows fast flashing in synchronism. Release of the " Test" pushbutton simulates return to normal condition, with all windows which are not in alarm mode slow-flashing in synchronism. Operating the " Clear" pushbutton brings to Normal all windows which are not in alarm mode anymore. The points that are in alarm mode are not a f fected by test. The horn actuation is included in the test sequence. Annunciator cabinets A through N are identical among themselves, with a single exception: Cabinet E is separated in two lialves, located respectively on top of cabinets D and F, on CP-1. 1 In contrast with cabinets SA and SB, these non-safety cabinets are not of integral design; they are plain " lamp boxes" driven by separate logic circuits and power supplies located in CP-19. As initially designed, these cabinets were provided with two distinct " horn zones"; however, a design change to four zones is being planned as follows:
- Cabinets A & B will operate in conjunction with a horn located in CP-13.
l
- Cabinets C through F will operate in conjunction with a horn located in l
CP-1,
- Cabinets G through H will operate in conjunction with a horn located in CP-2.
- Cabinets L through N will operate in conjunction with a horn located in CP-8.
I Panels CP-13, CP-1, CP-2 and CP-8 each includes a set o f pushbut tons (" Test" ,
- " Clear" and " Acknowledge") for the independent control of the above four I
"c ontrol zones":
The operating sequence of the alarm cycle of cabinets A through N is identical with the sequence of cabinets SA and SB. Also identical is the construction of the light windows (with two white lights connected in parallel; and the operation of the annunciator control pushbuttons. Figure 2.11-2 is a typical annunciator display cabinet. 2.11-1
l, 23356-2 While the horns of the SA, SB cabinets are of the electronic (static) type, with adjustable tone and warbling, the horns for the cabinets A through N are electromechanical, quite dif ferent in tone from the static ones. Nineteen findings or Human Engineering discrepancies were reported against the Control Room Annunciator System. These findiags and their disposition are discussed below. Fire Panel alarms findings are discussed in Section 2.12 B-3, Finding 2, Priority 3 "Many auxiliary system annunciators require Control Room operator to direct auxiliary operator to given plant location to obtain specific information."
Response
The auxiliary systems annunciators are located on auxiliary systems control panels that are located in the vicinity of the equipment that they are associated with and do not require continuous supervision by operators. The alarms generated on local annunciator units are reproduced as a general alarm for that unit in the Main Control Room so that the Control Room operator is aware of the local conditions in the plant. Bringing all detail alarmc in the Control Room would clutter the Control Room annunciators in an unacceptable measure, without providing much help to the operator. Most of the local alarms (provided by the auxiliary systems annunciators) are available to the operator, whenever required, through the computer displays. I B-3, Finding 3, Priority 2 "A separate first out panel is not provided for the Reactor System."
Response
I LP&L feels that a fit- is not required in this case. The Reactor System provides equivale c.uts to the Plant Computer for monitoring the sequence of events (SOE program) . Hence, the first out trip input is available to the operators through the computer terminals. B-3, Finding 4, Priority 2
" A separa te first out panel is not provided for the turbine / generator system."
Response
The turbine trip alarms are provided with first out circuitry that allows only the first alarm signal to go through and be displayed on the plant annunciator display panel. B-3, Finding 5, Priority 2 Alarms that have cleared do not initiate an audible signal and activate the alarmed and acknowledged visual tile in some way to provide positive c on fi rma t ion. 2.11-2
233 5W-3
Response
Alarms that have cleared af ter being acknowledged by the operator change the state of annunciator window from a steady light to a slow flash light. Alarms that return to normal before being acknowledged, change the state of the annunciator window from fast flash to slow flash at the moment they are acknowledged by the operator. The annunciator window will remain in the state of slow flash until the operator clears it by depressing the " clear" pushbutton of the annunciator system. This arrangement bas the advantage of requiring the operator to acknowledge an alarm even if it has returned to normal before he had a chance to acknowledge it. At the same time, it does not inconvenience the operator with additional audible signals when urgent action is not required. B-3, Finding 6, Priority 1 "The auditory signals are not reliably discernible above average ambient noise. (10db( A) differential above ambient recommended.)"
Response
The annunciator horns are provided with adjuctabic tone and warble. The horus will be adjusted so that they are readily discernible above average ambient noise. The average ambient noise level can only be determined when normal y Control Room activities begin however, an adjustment will be made prior to Licensing and followup adjustments will be made if necessary. B-3, Finding 7, Priority 1 "Th e Si tank (meter) displays on the lef t side of CP-8 (under annunciator
- panel M) have their corresponding annunciator on panel N - located on the j right side of the panel. The S1 meters on the right have their annunciator on the left."
Response
The subject alarms and associated indicators on CP-8 is being rearranged. 1 ( pcN-IC-1010 ) B-3, Finding 8, Priority 3 "The Diesel Fire Pump Annunciators on CP-4 CVCS panel appear to be poorly located."
Response
While there are no associated fire pump controls on the main panels, it was desirable to place the Diesel Fire Pump Annunciator on a centrally located panel. 2.11-3 Rev. No. 1, (12/82)
2335W-4 . B-3, Finding 9, Priority 3 "Ihe annunciators for Reactor Cooling Pump Seal Water and Component Cooling Mater appear to be inappropriately located on the CP-18 HVAC and Containment 1s olation Panel."
Response
The annunciator panels on CP-18 are Class IE. Loss of Reactor Coolant Pump Seal Water should be responded to promptly. Therefore it is required to locate these alarms on the CP-18 annunciator panels. The seal water is also 1 monitored on each Reactor Coolant Pump individually with alarm windows on CP-2 which is the same control panel where the control switches and indicators to the pumps are located. B-3, Finding 10, Priority 3 1 , "Each annunciator panel is identified by a temporary label placed below the 1 panel." i
Response
The control board enhancement program will resolve this HED by providing y permanent labels by Hot Functional Testing. B-3, Finding 11, Priority 1
" Alarm windows are snap-on onto the frames. These slip out easily and more than one may come out inadvertently when removing one, or when door is handled to replace lamps. Error may occur when replacing windows - in wrong position."
Response
The annunciator panels are being reviewed for loose tiles. l.oose tiles will 1 De secured, and the annunciator administrative procedure will call for a J review and correction of loose tiles. . j l B-3, Finding 12. Priority 1 "The operator aids / tools necessary for lamp replacement are not providad."
Response
All necessary aids / tools will be provided prior to fuel load. 7 r 2.11-4 Rev. No. 1, (12/82) __ _ _ __ _ _ O
233 5W-5 B-3, Finding 13, Priority 3 "No distinctive coding and administrative procedures are currently in place for annunciator tiles tnat must be "0N" for an extended period during normal operations."
Response
LP&L's annunciator system is designed for all lights off (" Black Board") in normal power operation conditions. The administrative procedures will require marking of those tiles which remain "0N" for an extended period due to maintenance, mode of operation or other specific abnormal situations that render the annunciator message moot. Self-s ticking " markers" can be used to identity these annunciator windows. This practice will begin during Hot Functional Testing. B-3, Finding 14, Priority 1
- 1. " Annunciator panels are not labeled for cross-reference to Alarm Procedures and 16C use".
- 2. " Windows are not coded for crose-reference to t.larm Procedures and IGC ue,e."
- 3. " Existing window codes on drawing / diagrams are Numeric-Numeric (X,Y) in a row-column scheme. If operator (or 16C Tech) identifies window by Column-row (i.e. , Y,X) he will locate incorrect Alarm Procedure or I6C d ocumen t/w iring . The X,Y convention fits human stereotypes."
Response
Current method of window identification follows the method of word identification on a printed page (identification of line followed by identification of word position in that line). In order to achieve a viable cross-ref erence to alarm procedure and for 16C use, additional labeling will be provided where required. LP6L will add alpha-numeric annunciator labels prior to fuel load. Refer to Figure 2.11-2. B-3, Finding 15, Priority 3
" Cues f or prompt recognition of annunciators that are out-of-service are not presently availaole."
Response
LP6L will handle this by periodic testing and administrative procedures. Self-sticking " markers" can be used on the corresponding windows. This practice will be tried out during Hot Functional Testing. 2.11-5 Rev. No. 1, (12/82)
233SW-6 B-3, Finding 16, Priority 1 "The Annunciators audible alarm systems do not provide sufficient localization cues to direct the operator to the appropriate alarm source (e.g. , CP-1, CP-2, CP-8) ." Re sponse Two additional horns will be added to the main annunciator system (on panels CP-13 and CP-2, respectively) and the circuits will be modified prior to y Licensing to provide f our alarm zones, each with its own horn and its own set of control pushbuttons. Ref er to Figure 2.11-1. The fire system has its own horn and controls, as do the two safety-related annunciators located on CP-18. B-3, Finding 21, Priority 2
" Alarmed annunciators automatically silence af ter 10 seconds without requiring any operator action."
Re sponse l The present automatic silencing design will be changed to continuous audible l alarm, silenced only by the actuation of the " acknowledge" pushbutton. l ilowever, automatic silencing is an annunciator feature preferred by LP&L in all our fossil-fired units. It has been proven to be preferred by most operators in these units and may well prove in the long run to be a desirable feature f or the Waterf ord-3 annunciator s. LP&L will notif y the NRC if a y change back to automatic silencing will be made. B-3, Finding 22, Priority 2 "There is no separate silence control in the annunciator control groups."
Response
Silencing is part of the " acknowledge" pushbutton f unction. Whenever the pushbutton correspondin;; to a certain " alarm zone" is actuated, it silences the horn of that alarm zone and acknowledges all current alarms in that zone. B-3, Finding 23, Priority 1
" Repetitive groups of annunciator control pushbuttons do not have a consistent arrangement of pushbuttons at each panel location."
2.11-6 Rev. No. 1, (12/82)
4
! 2335W-7 1
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Response
A Design Change Notification (DCN-IC-837) has been implemented. All groups of
! annunciator control pushbuttons are now consistent.
f B-8, Finding 12, Priority 3 "Some annunciators for CP-18 equipment are on tne CP-33 and CP-35 annunciator panels." t
Response
Panel CP-33 is located to the left of panel CP-18 at an angle of 900; panel CP-35 is adjacent to CP-18 on ene right. The annunciator display cabinets located on CP-33 and CP-35 are close enough to the displays on panel CP-18 for Rne operator to perform all required functions. I i. l l 2.11-7 Rev. No. 1, (12/82)
FIGURE 2.11-1 CONTROL ROOM LAYOUT, LOCATING ANNUNCIATORS AND ALARM ZONES I CP-7 CP-36 CP-8 CP-6 I ' ' ' ' ' ' ' L M N HORN CP-2 - NEW HORN i
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2,12 FIRE PROTECTION CONTROL PANEL (MCRP) AND LOCAL FIRE DETECTION CONTROL PANEL
2334W-1 2.12 MASTER REMOTE CONTROL PANEL (MRCP) AND LOCAL FIRE DETECTION CONTROL PANEL The MRCP in the Control Room provides audible and visual fire alarms and reflash capability f or all the zoned detection systems. The MRCP is electrically supervised for continuity, loss of power, short circuits, ground faults, etc. When a malfunction occurs, audible and visual trouble alarms are activated in the Control Room. Electrical power supply to the MRCP is furnished from the 125 volt de system. The operating status of all fire pumps and controllers, automatic sprinkler and water spray systems, heat and smoke detection system, and chemical extinguishing systems are continuously monitored on the MRCP to make sure that all equipment will be available for immediate response to a fire. Local Fire De tection Control Panel (FPE-3 and 3A) is one unit located next to the MRCP in the Control Room and provides audible and visual fire indication f or detection systems in the Reactor Auxiliary Building, Turbine Budlding, Reactor Containment Building, Fuel ihndling Building and the Dry an'd Wet Cooling Tower areas. The fire detection electrical wiring is electrically supervised f or continuity, locs of power, etc. When a malfunction occurs, audible and visual trouble alarms are activated.
" Fire" and "Itouble" signals are transmitted to the MRCP and to the computer displays, which are located in the Control Room.
Figure s 2.12-1 2.12-2 and 2.12-3 show the proposed enhancements of MRCP and FPE-3, 3A. Ten findings were reported against these panels and were discussed below. B-3, Finding 1, Priority 3 "There are two indicator lights directly below label indicating remote panel location. One is labeled ALNU1 and lights red when the remote panel receives signal from a fire detector in that area. The other is labeled TROUBLE and lights amber when a trouble signal is received. The problem is that an audible alarm is sounded when either a fire or trouble signal is received, but the red alarm indicator lights only when a fire signal is received."
Response
There are two audibly distinct alarms in the MRCP. One is a steady tone, the other is a warbling tone. Thu s , the operator can distinguish between trouble and fire without looking at the panel. Also the MRCP will be relabeled, and 1 the word ALARM will be changed to FIRE prior to Licensing. 2.12-1 Rev. No. 1, (12/82)
2334W-2 B-3, Finding 20, Priority 1 " Operators report that alarms are not flashed and then converted to steady when acknowledged (as are the Main Control Room annunciators alarms). The result is that if a second (or third, etc.) alarm occurs, the operator can easily lose track of which was previously acknowledged, i.e. , a "new" alarm is not discriminable from an "old" alarm. This problem has already been realized during testing and maintenance operations with the panel."
Response
Fire panel reflash capability will be provided on the MRCP prior to 1 Licensing. If a fire occurs, then the main fire indicaticn, the individual local panel fire indication, and the individual zone indication, all will flash until acknowledged by the operator. Should a seccnd fire occur the main indicator as well as the individual zone indicator will flash. After acknowledgement the fire zone remains lit in a steady mode until reset. B-4, Finding 11, Priority 2 " Fire Protection panel pushbutton controls will be operated during relamping. Buttons mus t be pressed to re-insert af ter lamp replacement. Pressing causes activation. Halon will be discharged. Panel key switch looks like it disables the panel. It does not. Me thod of actually disabling Halon is dif ficult due to backup power." NRC Review Team Comment: There is no key switch on the panel.
Response
The subject MRCP pushbuttons has been changed. The buttons will no longer be lit; therefore inadvertent actuation during relamping will not be a problem. Separate indicators are also provided. B-6, Finding 7, Priority 3 " Labels do not provide adequate information to the operator to pinpoint the fire area. This differs from HED 121 (B6, 29) because labels are located on indicator lights in 121 and labels are placed between FIRE and TROUBLE." NRC Review Team Comment: This also applies to local panels e.g. , A 88d-M223 in relay room; labels FPM17, FPM18, FPM19.
Response
Re fer to B-6, Finding 28 below. 2.12-2 Rev. No. 1, (12/82)
2334W-3 i B-6, Finding 29, Priority 3 , " Inadequate information displayed on indicator lights. Label reads, for example, RAB 30. This means area 30 in the Reactor Auxiliary Building, but the operator must look at a drawing to locate area 30."
Response
Re fer to B-6, Finding 28 below. B-6, Finding 28, Priority 3 . "La bels are misleading. Lef t hand portion of panel is divided according to 4 location of five local panels. The label "FPE-1 RAB EL.-4" identifies the location of FPE-1 (local panel) as j in the Reactor Auxiliary Building at -4 f t, elevation. This label bnplies that the detectors are located in the RAB -4 Ft. EL. also, but this is not true. FPE-1 local panel covers detectors located at -4 f t. EL. and -35 f t. EL. FPE-2 RAB EL. +21 local panel covers detectors located at +21 and +35 f t. elevation. FPE -3 RAB EL. +46 local panel covers detectors located at +46 f t. EL. (the Main Control Room), the Fuel Handling Bldg. , the Turbine Bldg. , and the RCB. FPE -4 SERVICE / CHILLER BLDG. local panel covers detectors located in these two b1dgs. , plus the Water Treatment Bldg."
Response
In order to help the operators identify the location of a fire, a tabular road m1p will be lettered on the MRCP top hat prior to Licensing. An example of 1 this chart is shown on Table 2.12-1. As can be seen the chart serves as a directory showing the actual fire zone alarmed, as well as the location of the local fire panel. A cross-reference to the fire zone drawings in also provided to further assis t the operators. Other fire panel enhancements, primarily labels, will also provide location information and the plant monitoring computer can also aid in locating a fire. In addition, drawings of the fire zones will be provided in the Control Room / Technical Support Center. B-6, Finding 2 7, Priority 3 "A fire in the plant can af fect cables and therefore instrumentation on the control panels. There is no way at present for the operator to know which , instruments would be af fected by a fire in a particular area." l Re spons e No corrective action is required due to changes already underway in order to comply with Appendix R to 10 CF R5 0. For example , there will always be at least one train of safe shutdown equipment including instrumentation and control available due to various protective measures including sucn measures as re-routing cables, new PAC panels, wrap, sprinklers etc. i 2.12-3 Rev. No. 1, (12/82) l
, . . _ . - . , - _ , _ . _ , , _ - - - . , - . . _ _ . . . , , , . _ , . . , , . - - , , _ . _ , . _ _, ~ .._.-.~._,.# . . . ~ - . _ _ - , , , _ - - -
l 2 334W-4 l 1 B-6, Finding 36, Priority 3 "The word TURBO is used in labeling. Turbo is a prefix and should not be used as a substitute word for turbine." Re sponse i Per the Control Room glossary, turbine will be abbreviated TURB during the enhancement of the fire panels. 1 B-8, Finding 15, Priority 3 Fire Panel - Grouping
" Indicators for Fuel Handling Building Fire and Trouble are located in two columns."
Response
1 The indicators will be rearranged prior to Licensing such that fire zones in the same building are grouped together as shown on Figures 2.12-1 and 2. B-8, Finding 31, Priority 3 Fire Panel - Grouping
" Arrangement of system indicators and pushbuttons at top of each of the panels and bottom of FPE-3 CR local pad is inconsistent. Example, POWER ON is at far right on !! aster Panel, Fire Protection System and f ar lef t on FPE-3 Control Room local panel."
Re sponse The arrangement of indicators and pushbuttons on FPE-3 and on the MRCP is being changed to be as consistent as possible as can be seen on Figure 2.12-1, 1 2 and 3. These changes will be implemented prior to Licensing. I I j 2.12-4 Rev. No. 1, (12/82) i _ ...- ~ __ _ .-- _ _ _ _. . _ - - - - _ _ _, _. _
2334W-5 TABLE 2.12-1
-l l MASTER REMOTE CONTROL PANEL - FIRE DETECTION SYSTEM
, DIRECTORY OF FIRE AREAS , FPE-1 RAB EL. -4 (COL. H-3A) FIRE AREA FIG.NO ELEVATION AREA DESCRIPTION l RAB 30 X-4 EL. -4.0 Administration Area (Health Physics)
- RAB 31 X-4 E L. -4.0 Corridor and Passageways
- RAB 32 X-13 EL. -3 5.0 Wing Area X-13 E L. -4.0 Wing Area
! RAB 3 3 X-3 EL. -3 5.0 Shutdown Cooling Heat Exchangers A&B RAB 34 X-3 EL. -15.0 Valve Operating Enclosure A&B 4 RAB 35 X-3 EL. -3 5.0 Safety Injection Pump B RAB 36 X-3 EL. -3 5.0 Safety Injection Pump A, A/B 1 RAB 3 7 X-3 EL. -3 5.0 Emerg. Feedwater Pump MD A RAB 38 X-3 EL. -3 5.0 Emerg. Feedwater Pump MD B l
- RAB 3 9 X-3 EL. -3 5.0 General Equipment Area
! RAB 40 X-13 EL. -3 5.0 Emerg Diesel Gen Fuel Oil Tank A RAB 41 X-13 EL. -35.0 Emerg Diesel Gen Fuel Oil Tank B
- FIRE AREA II AS MORE THAN ONE 20NC. OEE LOCAL PANEL FPE -1 FPE -2 RAB EL. +21 (COL.K-11A) i FIRE AREA FIG.NO ELEVATION AREA DESCRIPTION
- RAB 8 X-5 E L . +21. 0 Switchgear Room RAB 8D X-5 EL. +21.0 Computer Battery Room RAB 8E X-5 EL. +21.0 CEA Drive MG Sets RAB 8F X-14 EL. +21.0 H&V Fan Room RAB 9 X-5 EL. +21.0 Aux Control Panel LCP43 RAB 11 X-5 EL. +21.0 Battery Room BS RAB 12 X-5 EL. +21.0 Battery Room ABS RAB 13 X-5 EL. +21.0 Battery Room AS RAB 17 X-5 EL. +21.0 CCCW Heat Exchanger 'B' RAB 18 X-5 EL. +21.0 CCCW Heat Exchanger 'A' i RAB 19 X-5 E L. +21.0 CCCW Pump A i RAB 20 X-5 EL. +21.0 CCCW Pump AB I
RAB 21 X-5 E L . +21. 0 CCCW Pump B RAB 22 X-5 EL. +21.0 Drumming Station RAB 23 X-3 E L. +3 5.0 Hold-up Tank Area X-5 EL. +21.0 Corridor & Common Passageways RAB 24 X-14 E L. +21. 0 Decontamination Area & Hot Mach. Shop i 2.12-5
_ . _ = ___ . . _ . . _ . . 2334W-6 l 1 TABLE 2.12-1 (Cont' d) FIRE ARE A FI G.N0 ELEVATION AREA DESCRIPTION RAB 27A X-10 EL. +7.0 FT HVAC Equipment Room RAB 27B X-10 EL. +7.0 FT Electrical Area RAB 27C X-10 EL. +7.0 FT I&C Room RAB 27D X-10 EL. +7.0 FT Communications Equip Room
- FIRE AREA HAS MORE THAN ONE ZONE. SEE LOCAL PANEL FPE-2 i
FPE-3 & 3A RAB EL. +4 6.0 (Col. J-10A) FIRE AREA FIG.NO ELEVATION AREA DESCRIPTION RAB 1A X-6 EL. +4 6.0 FT Control Room RAB 1B X-6 EL. +4 6.0 FT HVAC Equipment Room - Northeast RAB 1C X-6 EL. +4 6.0 FT Emergency Operation Facility
- RAB 2 X-6,15 EL. 4 6.0 FT HVAC Equipment Room - West X-6 EL. +6 9.0 FT HVAC Equipment Room - Northwest
- RAB 3 X-6 EL. +4 6. 0 FT HVAC Equipment Room - Southeast X-21 EL. +3 5.0 FT Corridor RAB 3A X-6 EL. +6 9.0 FT Elevator hachine Room & HV Fan Room
*RAB 7 X-21 E L. +3 5. 0 F T Relay Room *RAB 25 X-14 EL. +21.0 FT Equipment Access Area E L. +3 5. 0 FT Turbine Bldg. X-16 EL. +15.0 FT Switchgear Room 1
- RCB X ' 3,X-14, EL. All Annulus & Elec Penetration Area X-15
- Fuel Handling X-11 EL. All Fuel Handling Building CT1 & CT3 X-2 EL. +21.0 FT Dry Clg. Tower ' A' & We t Clg.
To we r' A' CT2 & CT4 X-4 EL. +21.0 FT Dry Clg . Tower ' B' & Wet Clg. Towe r ' B'
- FIRE ARE A HAS MORE THAN ONE ZONE. SEE LOCAL PANEL FPE 3 & 3A FPE-4 SERVICE / CHILLER BLDG.
FIRE AREA FI C.No ELEVAT IO N AREA DESCRIPTION
*SB X-1 GRADE Service Bldg WT X-1 GRADE Water Treatment Bldg.
! *CB X-1 GRADE Chiller Bldg. l
- FIRE AREA H AS MORE THAN ONE ZONE. SEE LOCAL PANEL FPE 3 & 3A FPE-5 COMPUTER ROOM (COL. G-10A)
FIRE ARE A FIC.NO ELEVATION ARE A DESCRIPTION .
- RAB ID X-6 El +46.0 FT Computer Room
- FIRE AREA HAS MORE THAN ONE ZONE. SEE LOCAL PANEL FPE 5 l 2.12-6 Rev No. 1, (12/82)
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2.13 PLANT fl0NITORING COMPUTER DISPLAY PANELS (CP-3, 35, 36)
2321W-3 2.13 PLANT MONITORING COMPUTER DISPLAY PANELS (CP-3, 35, 36) In the Control Room the operators have three separate stations within the Main Control Board, where they can communicate with the Plant Monitoring Computer (PMC). These stations are located on CP-35, CP-3 and CP-36; each consists of four 19 inch color CRI's and an operator's console which includes a plasma display panel, a functional keyboard and a standard ASCII typewriter keyboa rd . One CRT of each group of four (the top-lef t one) is dedicated for " Computer Alarm" display. A similar CRT dedicated for " Computer Alarm" is also provided on CP-6. This panel will also incorporate the two QSPDS plasma 1 displays, as well as the Plant Radiation Monitoring CRT (CP-51A) . The operator uses the console to display information on the remaining three CRT's available to him at a particular station. In addition to the three ! stations on the Main Control Board, the operators can use the three CRT's and console available on the Operatof s Desk (console) - of which one (at the seated operator's right) is also dedicated f or alarm display - the three keyboards and the plasma display located on the same desk. The Supervisor's office is also equipped with two CRT's and a console for quick access to important plant inf ormation. The five computer stations of the Control Room provide the operations staf f with the computcr gencratcd alarms and with the important plant inf ormation available in the Data Base. For backup to the CRT's and f or recording purposes the Control Room is also equipped with 3 hard copy printers. There is no surf ace enhancement to be shown on the Plant Monitoring Computer Display Panels; among the findings reported, none requires a surface enhancement of the panels. A representative Display Panel is shown in Figure
- 2. 13-1.
Four findings or Human Engineering discrepancies were reported against the Plant Monitoring Computer Display P anels. These findings and their disposition are discussed below: B-7, Finding 1, Priority 3 "Four CRT modules with f our numeric keypads each. CEAC/CPC modules with one keypad each, megawatt demand keypad (1), operator's console, console phone keypad and CRT keyboards." Re spons e Various operator's modules were f urnished f or dif ferent ind unrelated pu rpo se s. If an error occurs in the "keyboarding" the computer will generate a message. Operation of I/O devices will be given special emphasis in training classes. B-7, Finding 2, Priority 1 "A 5 x 7 dot-matrix is used on th2 CRT displays which causes readability pro blem s . " 2.13-1 Rev. No. 1, (12/82)
2321W-4
Response
When LP&L designed and purchased the display system, the 5 x 7 dot matrix was the system being used throughout the indus try. Although, the 7 x 9 dot matrix is pre ferred in NUREG-0700 the 5 x 7 dot matrix is still acceptable throughout the industry. LP&L feels that the 5 x 7 dot matrix characters are adequate for the type of information being provided and the speed at which the operator ia expected to act on this data. The entire display generator system would have to be completely redesigned to accommodate this change. LP&L does not feel that this apparent problem warrants this extensive change. A Human i Factors review of the Computer System man-machine interface will be performed prior to Licensing. 3-7, Finding 4, Priority 1 "The control room printer which will be used to print alarms, critical status information, and trend data does not have a high-speed print capability of at least 300 lines a minute." Re spons e This will be evaluated during testing of the computer. If faster printer is required it will be installed by Licensing. Presently a 600 line per minute i printer is provided in the Computer Room which is adjacent to the Control Room. B-7, Finding 5, Priority 1 "The computer system does not provide capability to obtain a hard copy of any page appearing on the CRT screen at the request of the operator."
Response
A haid copy aevice will be provided in the Control Room prior to Licensing. l1 i 2.13-2 Rev. No. 1, (12/82)
FIGURE 2.131 COMPUTER INTERFACE BOARD CRT CRT pupm M - CRT CRT A LOCATION FOR OPERATOR KEYBOARD AND HERCO D! SPLAY 31 1/7" l V 43" FRONT VIEW CP-3,35 & 36
2 . 1 11 REMOTE SHUTDOWN - TRANSFER AND CONTROL 2340W - 1 2.14 REMOTE SilUTDOUN - TRANSFER AND CONTROL (LCP-43 and Transfer Relay Panels)
- 2. 14. 1 LCP-43 AUXILIARY CONTROL PANEL LCP-43 is located outside the Control Room and contains the instrumentation and controls required to perform, monitor and maintain a safe shutdown of the reactor in the event the Control Room becomes uninhabitable.
This auxiliary panel contains the controls and indicators for the Emergency Feedwater System, the Chemical Volume Control System, the Component Cooling Water System and the Shutdown Cooling System. These instruments are duplicates of those in the Main Control Room. Twenty eight findings were reported against LCP-43. The disposition of these findings is as discussed below: B-1, Finding 12, Priority 1 Emergency Shutdown Panel
" Meters and controls are located far too high on this panel. Recommended upper limit is 72." Problem is compounded by poor layout - lack of good associations."
Response
ln order to improve the anthropometrics of the remote shutdown panel (LCP-43) a permanent metal deck floor (10 inches high) including ramps will be provided on the front side of the panel. The layout of controls and indicators is adequate to perform an orderly hot / cold plant shutdown function. B-1, Finding 13, Priority 1
" The re is a t em pora ry wooden platform 8" high, with metal pipe rails, installed in front of the Remote Shutdown Panel."
Response
The temporary wooden plat form will be replaced by the permanent metal deck floor (10 inches high) including ramps. B-1, Finding 21, Priority 1 "The Remote Snutdown Panel room lighting is harsh and creates a shadowing ef fect on the control panel surfaces. The lower panel is subject to brighter direct lighting while the illumination level of the upper panel portion is noticeably lowe r . "
Response
Re fer to Sec t ion 5.1, " Li gh t i ng" . l [ 2.14-1
2340W - 2 B-1, Finding 24, Priority 1 "To provide emergency AC lights in the Remote Shutdown Panel Room, there is a period of approximately 15 seconds between the time an offsite power loss occurs and the time diesel generator locling begins. DC battery lighting is not provided during this 15 second period."
Response
; Refer to Section 5.1, "Lignting."
B-1, Finding 25, Priority 1 "The PA system speaker for the Remote Shutdown Panel area is too large for the limited / confined area that it covers. The area is approximately 13 1/2 ft square. Tne speaker cone is approximately 20" in diameter."
Response
Re f er to Section 3, " Communications." B-2, Finding 2, Priority 1 "The Remote Shutdown room has no provision for communications, i.e., no telephone; no sound powered phone."
Response
Refer to Section 3, " Communications." i I ' B-2, Finding 10, Priority 1 i j There are no sound powered headsets or storage provisions area for them in the Iransfer Switch room or in the Remote Shutdown Panel area.
Response
Re fer t o Sec tion 3, " Communications." B-4, Finding 1, Priority 1 l l "On the Remote Snutdown panel, there are five controllers missing; i.e., Emergency Feedwater 8 Flow Controls (2), Component Cooling Water (1), Emergency Feedwater A (2)."
Response
All five missing controllers will be installed prior to Licensing. l1 6-4, Finding 14, Priority 1
- "On LCP-43, keylock switenes have 3 positions
- Le f t = Normal, Rignt =
dypass. Middle or straightop position is not labeled." 2.14-2 Rev. No. 1, (12/82)
i 2340W - 3 i
Response
Keylock switches on LCP-43 have 3 positions and two functions (Normal and , Bypass). The third or middle position is used to insert the key into the lock and serves no other function. B-5, Finding 17, Priority 1 "There is a glare problem with the meters (curved vertical) located on the upper part of the Remote Shutdown Panel LCP-43."
Response
New lighting fixtures are being installed (DCN-E-920) to provide a softer quality of light; an additional fixture will reduce the shadowing effect. The results of a Lighting Survey will be provided to NRC 60 days prior to 1 Licensing. B-5, Finding 27, Priority 1 "Two like measured (Cooling Towers) parameters (temperature) with dissimilar scales immediately adjacent to each other. NUREG 0700, Para. 6.5.1.6.d, Exhibit 6.5-6." l NRC Review Team Comment: Dual scale vertical meters Left Scale 50 - 130 ] Degrees F range; Right Scale 30 - 110 degree F range.
Response
These two meters are measuring parameters that are not directly related. The i left scale is for the component cooling water temperature and the right scale is for the wet cooling tower basins. Labels will identify these two unrelated parameters prior to Licensing. B-5, Finding 30, Priority 2 j " Pre-trip indicators (for Steam Generator Pressure) provide a steady red light l indication of impending trip. This is a warning indication but is identical to the normal status indication of micro-switches throughout the plant."
Response
The warning lights are provided as an operator aid to assist him with bringing the plant to cold shutdown without an inadvertent SIAS. The red color choice j is pending on the results of the " Control Room color code study" which will be (An advanced copy of the color 1 ! submitted to NRC 60 days prior to Licensing. study will be sent to NRC in January 1983.) l B-5, Finding 31, Priority 1 I " Letdown Flow and Pressure j lt appears that the control switches have lights (white) indicating valve r selection. It also appears that the white CMC indicators above the switches i l l 2.14-3 Rev. No. 1, (12/82)
2340W - 4 show the same information. The red and green CMC above the switch show valve condition. This would be unnecessarily redundant and confusing."
Response
All controls and indications are required. The letdown flow pressure controls consist of three stations on LCP-43 and two valves in parallel. Station #1 indicates the control mode that was selected in the Main Control Room before the transfer. Operator needs this indication to position selector switch (Station #3) so that the mode of operation remains the same af ter the actuation of control circuit. Station #2 indicates the actual position of each valve. Station #3 is used to select the control mode and to actuate the selected mode of operation NOTE: All indicating lights are activated by a transfer switch. The control circuit is also transferred to LCP-43 with a transfer switch; ho.ever, it is not connected to the control switch (Station #3) until the knob on the control switch is d epre cc ed. When the control circuit is connected to the control switen, the white lights in lower portion of Station #3 and on Station #1 go out. The above functions of indicating lights shall be clarified through 1 enhancement o f LCP-43. l B-6, Finding 11, Priority 1 i ! "The neutron flux indicator on LCP-43 has no label or scale or meter f ace identification. This HED applies to both trains on both sides of the panel."
Response
I Labels will be provided prior to Fuel Load. B-6, Finding 13, Priority 1 l l "There is no permanent panel identification on LCP-43. It is written on with grease pencil."
Response
LP&L will provide the required labels during the ongoing enhancement ef fort , to be completed prior to fuel load. l B-6, Finding 14, Priority 1 l ! "In the Remote Snutdown panel room there is an unlabeled blue pushbutton on the communication pane l."
, 2.14-4 Rev. No. 1, (12/82)
__ = - - d 2340W - 5 Re spons e ] Blue pushbutton will be removed (DCN-E-933) . 3 B-6, Finding 15, Priority 1 l "There is no panel number on the Remote Shutdown Panel communications panel." 2 l Response ! l1 Number will be provided prior to Licensing. ( DCN-E-9 33) I I B-6, Finding 16, Priority 1 "On LCP-43 there are only a limited number of hierarchical labels at inconsistent locations. Character sizes used for panel and system labels are the same size as component label characters." ! Response Adequate labels will be provided and will replace or complete the existing . j ones, prior to Licensing. l1 B-6, Finding 21, Priority 1 l ! Le tdown Flow and Pressure j
" Labeling on switches and status display f aces are inaccurate. Poorly i positioned and confusing."
I L ! Response Inaccurate labels are being replaced and those poorly positioned will be I re-located prior to Licensing. B-6, Finding 31, Priority 1 "On LCP-43 there is inconsistent use of abbreviations, i.e., emer. emerg., CR/ Contr. Rm."
Response
Following the ongoing enhancement ef fort, labeling of LCP-43 will use the same standard glossary that is being used for the Control Room panels. Abbreviations will be consistent throughout all main control panels and LCP-43 1 prior to Licensing. B-6, Finding 40, Priority 1
" Control Room Exhaust Fan Switch Labeling on switch f ace is inaccurately positioned."
2.14-5 Rev. No. 1, (12/82)
2 340W - 6
Response
1 Labeling will be corrected prior to Licensing. l B-8, Finding 6, Priority 1 "No indication is provided in the Emergency Control Room that all transfer switches have been thrown. In the latter case, there is no indication of i which switches have not been thrown (there are approx. 62 switches) ."
Response
No special light is required to indicate that all transfer switches have been operated for the following reasons.
- 1) Unless the transfer switch is operated, there will be no lights on the associated controls that are serviced by that particular transfer switch. The missing lights on the panel will be an indication to the operator that the control circuit related to those lights has not been y transferred. A drawing marked to show the transfer switch associated with LCP 43 indications and controls will be provided in the Remote Shutdown Room.
- 2) The fact that not all transfer switches were operated is not an indication that the safe shutdown of the unit is impaired. The transfer of one safety channel SA or SB in addition to four protective channels is suf ficient to effectuate the safe shutdown of the plant.
i This would require operation of approximately half the number of existing transfer switches. (See also response to B-6, Finding 30) . B-8, Finding 9, Priority 1 i " Th e lack of any annunciator panels in the emergency shutdown area was noted by Lockheed analysts. This lack was also of concern to an LP&L operator who s tated that an operator using this panel would not know the status of many important systems if he has only the existing LCP-43." i j Response . The purpose of an annt.nciator is to call the operators attention to an abnormal situation (important deviation from normal operating conditions) which may be otherwise overlooked (Guidelines for Near-Term Improvements in NPP Control Room Annunciator Systems, Battelle, 1982). LCP-43 is designed to be used in abnormal situations (which require immediate i shutdown while the Control Room is not habitable) and is furnished with all l indicators and displays required for the safe performance of this unique operation (shutdown of the plant). Any additional alarm may only divert operator's attention from his immediate duties governed by the corresponding emergency procedures and by the status indications available on the LCP-43. 2.14-6 Rev. No. 1, (12/82)
2340W - 7 J B-8, Finding 14, Priority 1
" Meters and controls are located f ar too high on this panel. Recommend upper limit 72". Problem is compounded by poor layout, lack of good associations."
Response
A permanent metal deck floor will be provided by LP&L, prior to Fuel Load, to improve accessibility of the high located instrumentation (See response to B-1, Finding 12) . The layout is adequate for hot / cold plant shutdown and enhancements will be provided. A preliminary draf t enhancement drawing is provided in Figure 2.14-1. B-8, Finding 21, Priority 3
" Panel layout employs "mirtor imaging" of groups of panel elements. Layout within each group is generally the same on "A Train" or "B Train" sides; exceptions within groups are elements that are redundant from A to B (example: Boric acid pumps A and B - SA Power, and boric acid tanks A and B gravity feed valves. Groups such as CVCS (B side), emergency feedwater (A & B sides ) shutdown cooling (side BC, RCS/ Pressurizer). Entire upper portion of panel have layouts that do not re flect functional grouping, operator use, anthropometerics, or reasonable control display relationships.
NRC Review Team Comment: On LCP-43 functional group blocks are mirror imaged, while component (control and indicator) locations within each group have a consistent lef t to right and top bottom relationship."
Response
! The layout of components on panel LCP-43 was rearranged so as to maintain lef t to right and top to bottom relationship of components within each group. B-8, Finding 22, Priority 1 l l " Condensate Storage Pool - Me ter Position of meter does not easily permit the functional grouping of the meter with emergency feedwater system."
Response
The position of meters on LCP-43 has been rearranged per DCN-IC-834. B-8, Finding 24, Priority 1 Emergency Feedwater to Steam Generator
" Flow meters are physically separated (approximatly 9") from controllers by two other controllers not directly related to the meters."
Response
Position of meters on LCP-43 has been rearranged per DCN-IC-834. 2.14-7 Rev. No. 1, (12/82) l . - . - . - _ , . - .. , - . - , - - _ , _- _ . .
2340W - 8 , B-9, Finding 10, Priority 3 I "On LCP-43, the Charging Pump A/B control is separated from associated displays by the CCW-PUMP A/B Control and Displays."
Response
i b The charging pump AB Control is located in its associated area of AB safety onannel, and the AB safety channel does not contain displays, since display is , on either A or B. i f I e i 4 4 4 i l I Ii i i l j ,i 4 l i l i I 2.14-8 l U___,______._ _ _. ._. _ . . . _ . . - - . _ . __ . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . . . . . _ _ _ . . _ . _ _ _ _ . _ . _ _ . ,
l 2341W-1 l
- 2. 14 .2 TRANSFER SWITCH PANELS I In order to transfer the controls for safe shutdown from the Control Room to
! the Remote Shutdown Panel, sixty-two transf er switches grouped in six cabinets located on the mezzanine floor (El. + 35) of the RAB have to be operated. l Nine findings were reported against the Transf er Switch Panels and Transfer ! Switch room. These findings and their disposition are discussed below: 1 B-1, Finding 1, Priority 1
" Structural steel projects from room ceiling. Operators heads may s trike these projections. During transfer from Main Control Room to LCP-43, operator may be rushing through the transfer procedure and may not be wearing a hard
- hat. He may be injured or incapacitated by hitting projections from the I ceiling."
l
Response
l. l The lower projections will be raised above dangerous levels where possible. All others will be wrapped. All projections will be pointed out to the operators during remote shutdown walk-thrus, and, to the extent possible, a yellow line from the transfer room door to the various transfer switch cabinats will avoid the projections. The modifications will be made prior to 1 Licensing. i B-1, Finding 2, Priority 1 l 1
" Locks are present on transfer switch, cabinet, doors, panel and on the transfer room door. Immediate access is needed during emergency in transferring control from Control Room to Emergency Shutdown Panel."
I NRC Review Team Comment: No access procedures established. I l
Response
The locks will be removed from the doors of the transfer switch compartments of auxiliary panels. Doors within the transfer room will not require locks; however, outside doors of transfer room must have locks per security i regulations. Access procedures will be incorporated into the remote shutdown wa l k- th rus . These changes will be donc prior to Fuel Load. B;1, Finding 6, Priority 1 "In the Transfer Relay Room, the operator must operate safety transfer l switches and non-safety switches on six separate panels which are widely separated over a distance of approximately 70 feet." i i t i 2.14-9 Rev. No. 1, (1;/82)
2341W-2
Response
Fire protection regulations and Reg. Guide 1.75 dictate the layout of the relay room in which the transfer switches are located. In order to improve on human f actors a 4-inch wide yellow line will be painted on the floor from the door to all the transfer switch cabinets prior to Licensing, in addition, Iy these cabinets will also have a yellow tape border on the outside, as well as the inside of the doors. The time to effect transfer is adequate and will be confirmed during pre-op testing. B-1, Finding 2 3, Priority 1 "The Transfer Switch Room battery operated DC emergency lights appear to be inadequate for an operator to perform emergency functions during the 15 second delay period required for AC em rgency lighting to come on."
Response
Re fer to .Section 5.1, Lighting B-2, Finding 3, Priority 1 "The Transfer Switch room has one telephone near the Train A panel, and none within reach of the Train B panel."
Response
Two additional telephones are being installed prior to Licensing to provide ! complete coverage of the transfer switch panels per DCN-E-922. Refer to Section 3, " Communications." B-2, Finding 10, Priority 1 "There are no sound powered headsets or storage provisions area for them in the Transf er Switch room or in the Remote Shutdown Panel area."
Response
Sound powered headsets and storage space for them will be provided prior to i Licensing in the Transfer Switch room and in the Remote Shutdown Panel room. Re fer to Section 3 " Communications". B-6, Finding 4, Priority 1
" Access doors over transfer switch panels are not dif ferentiated from other f doors. They are scattered among cabinets on 2nd level transfer room."
Re sponse Doors of the compartments have distinctive physical appearance and will have labeling wnich enhances identification. This is to be accomplished prior to Fuel Load (see response to B-1-6) . 2.14-10 Rev. No. 1, (12/82)
4 2341W"3 B-6, Finding 10, Priority 1 "In the remote transfer room, switch position and function labels are not provided for some transfer switches (e.g., Panels SB, SA/B, NA/B)." i Response Labels will be provided prior to Fuel Load, but following the completion of the LCP-43 evaluation, i B-6, Finding 30, Priority 1 "At most transfer switch panels numbering of switches rebegins with 43-1. Hence, switches do not have unique designations. If a switch fails or is forgotten during the transfer operation among 62 switches, there is no unique designator to locate the desired switch."
Response
1 New and unique labeling will be provided as part of enhancement. The Cabinets are also uniquly numbered. Transfer from Control Room to LCP-43 will be perf ormed under administrative procedure. Normally micro-switches are not lit on LCP-43 but they will light when control is transferred to LCP-43. If a switch fails or is forgotten during the transfer operation, it will be noticed and identified from micro-switch indication. A marked-up print will be provided showing which transfer switch is associated with the components on 1 LCP-4 3. These changes will be made prior to Licensing. 1 i 1 4 1 l 2.14-11 Rev. No. 1, (12/82)
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2.15 GENERIC PANEL FINDINGS
2317W-1 2.15 GENERIC PANEL FINDINGS There are 57 findings and HEDs against the Control Room excluding the Annunciator System which are generically applicable to all the main boards. These can be organized into five groups:
- 1. Labels, demarcation and color -
- 2. Controls (i.e. , micro-switches, keylocks, tags, bulbs)
- 3. Meter s
- 4. Recorders
- 5. Physical (i.e. , completeness, directness, layout, dimensions)
Generic studies, analyses etc were commissioned to address these findings. Examples include a Control Room glossary; panel enhancement drawings showing hierarchical labeling and demarcation; a micro-switch coding study; a color code study; meter, keysaitch and recorder reviews. The enhancement drawings referenced in Sections 2.1 through 2.10 are applicable to this section. 2.15 .1 L ABELS, DEMARCATION AND COLOR B-3, Finding 17, Priority 1 " CONT is used as the abbreviation for control on CP-7 and CP-8. However, in the plant abbreviation list " CONT" means Contract, Continuous, Controller, and Co nta inmen t ."
Response
Re fer to B-6, Finding 38 below. B-3, Finding 18, Priority 1 "CNIMT is widely used as the abbreviation for Containment and is not included in the plant abbreviation list provided."
Response
Re fer to B-6, Finding 38 below. B-6, Finding 37, Priority 1 " Abbreviations are sometimes confusing and sometimes inconsistent. NUREG-0700, Para. 6.6.3.3 recommends consistency. Examples include: COND - used for condenser and condensate CONT - used for containment and control VA - consistently used for valve but may be confused with vacuum"
Response
Re fer to B-6, Finding 38 below. 2.15-1 Rev. No. 1, (12/82)
2317W-2 B-6, Finding 38, Priority 1 j "La bels on annunciators and associated controls and displays have inscriptions which are not consistent, e.g., On Panel - MSR DR COL TK 1A i On Annunciator - MSR DCT 1A" l i Response { A glossary of all control board abbreviations' has been prepared. Abbreviations on panels and annunciators are being changed as part of the enhancement effort to be consistent with the glossary. For example, containment will always be abbreviated "CNTMT." The panel changes will be 1 completed by Hot Functional Testing and the annunciators will be completed prior to Licensing. B-6, Finding 9, Priority 1
" Labels are missing from controls and displays throughout the Control Room.
- tbny permanent labels have become detached (e.g. , CP-8) ."
j Response 1 i Permanent labels will he provided by Hot Functional Testing as part of the human factors enhancement effort currently underway. Control labels will be { directly inscribed on the panel surf ace with a protective coating applied. Other information will be provided under the switch lenses. Special "wedgetts" have been developed to permanently af fix meter labels. 1 1 B-6, Finding 17, Priority 1 "No hierarchical labeling. Lack of hierarchical labeling results in the need for redundant labeling, a lack of visual grouping of functionally related j c ompo ne nt s . " i Re sponse l Re f er to B-6, Finding 4 5 below. j B-6, Finding 19, Priority 1
- 1. "La bels are sometimes placed above, but mostly placed below ,
i components. NU REG-070 0, Para. 6.6.2.1 recommends labels be placed y a bove components." i [ 2. " Hierarchical labeling scheme, integrated with graphics, required t labeli ng above."
- 3. " Hand action on a control covers the label, increasing error potential."
1 Re spons e 1 j Re fer t o B-6, Finding 4 5 below. 1 j 2.15-2 Rev. No. 2, (12/82) j I _-_ _ _-_ _
- 2317W-3 l
B-6, Finding 23, Priority 3
" Labels are not placed above the panel elements they describe (e.g. , on CP-8, j CP-13)."
Response
Re fer to B-6, Finding 45 below. i B-6, Finding 32, Priority 1
" Functional labeling is not used in the Control Room and at the Remote Snutdown Panel."
i
Response
Refer to B-6, Finding 45 below. B-6, Finding 41, Priority 3
" Lettering on labels is of ten too small for recommended legibility at 3
applicable viewing , distances." NRC Raview Team Comment: 0.g. , Hagen controllers on CP-18
Response
Re fer to B-6, Finding 45 below. f B-6, Finding 4 5, Priority 1 i "There are many unnecessary temporary labels which should be replaced by l permanent labels in the Control Room and the RSP room." 1
Response
As seen in the enhancement drawings, functional, hierarchical labeling (above
- the components) and demarcation lines are being permanently provided as part I of the human factors enhancement effort. The enhancement effort will be 1 completed f or the main boards by Hot Functional Testing. LCP-43 and the fire
, panel enhancement will be completed prior to Licensing. Adequate sized labels are being provided. It should be noted that many panel and wiring changes
. were needed to clear the way for organized demarcation and labeling. Also project documents are impacted by modifications to control and display l inscriptions.
4 l t f i i i 4 i 2.15-3 Rev. No. 1, (12/82) i i
2 317 W-4 i
, B-6, Finding 46, Priority 1 , "There is incomplete use of demarcation in the Control Room and remote shutdown panel; e.g. , LCP-43, CP-1, CP-2, CP-18, CP-33. Some demarcation is inef fective, inaccurate, or confusing; e.g., CP-13."
Re spons e Re fer to B-8, Finding 20 below. 1 j B-8, Finding 16, Priority 1 i.
" Association between control and related displays is poor. Association of related panel components is poor. Functional groupings are frequently not apparent. Associated display / controls are frequently scattered on a panel
- section."
Response
Re fer to B-8, Finding 20 below. i ~ B-8, Finding 20, Priority 1 l "On CP-8 enhancement techniques, such as spacing, dematcation, and color j shading, are not used for setting apart groups of controls and displays." a j Response I The association between controls and displays, as well as functional groupings, wherever found to be unsatisfactory, have been corrected by design change notices. As noted in the previous response updated demarcation and i enhancement techniques such as hierarchical labeling are being provided by Hot 1 Functional Testing for main boards and by prior to Licensing for LCP-43. B-5, Finding 29, Priority 1 1
- "There appears to be a primary color code s onvention in the Control Room
Red - flow; Green - no flow; Amber - tripped; White - advisory only. Many exceptions exist, however, as with the use of red lights on controller
- buttons; colors (mixed) on various module push switches; red " TRIP" buttons."
i NRC Review Team Comment: Color code conventions are violated at many locations in the Control Room. I 4 } l [ i r i i 2.15-4 Rev. No. 1, (12/82) i
- _ - - ~ - , - - - . - . - - _ - _ .
2317W-5
Response
A study of control panel component colors is underway and recommendations regarding standardization will be provided. The goal of this study is to minimize, to the extent feasible, unacceptable exceptions to the existing color convention. Several factors are involved. For example, the problems of negative transfer of learning should be avoided; vendor module operating manuals make reference to button colors which, if changed could impact that documentation and training. Many issues must be investigated. Eventually a color code convention will be established which satisfies the primary Human Factors criteria of reducing potential operator error. The present color convention can be outlined as follows: ) Red - in service, open position Green - not in service, inactive, closed position Amber - taken out of service automatically, unavailable , White alarm, test, advisory message An advanced copy of the color code study will be provided to NRC in. January 1983 and the final version of the study will be submitted 60 days before Licensing. Corrective action to the control panels is expected by Fuel Loading. However, feasible corrective actions to vendor modules will not be completed until startups following the first refueling. B-6, Finding 42, Priority 1 1
" Labels using white letters on black, or black letters on silver, do.not have as good a contrast as the recommended black letters on white; e.g., on LCP-43, a
CP-1."
Response
1 The enhancement program will improve color contrast. For example, white letters will be used on micro switches with red or green background. Black ! letters will be used on white or yellow background. Also silver plates are being removed from the panels. These changes will be completed prior to 1 licensing. 4 1 i l i 2.15-5 Rev. No. 1. (12/82) l i - _ .--.
i 2317W-6 1 i 2.15.2 CONTROLS B-4, Finding 5, Priority 1 "No attempt appears to have been made to utilize control coding.
- 1. Pumps, breakers and valves generally are operated by identical appearing micro-switches.
- 2. Proportional valves (less-more) are usually controlled by selector switches (Turbine generator temperature controls); but some (SG
] startup-shutoff valves, aux steam to condenser valves, gland steam { spillover bypass shutof f valves) are controlled by micro-switches." Re sponse I Re fer to B-6, Finding 1 below. B-6, Finding 34, Priority 1 l " Multiple types of micro-switches with little or no visual indication of how they operate or how they differ from each other."
Response
Ref er to B-6, Finding 1 below. B-6, Finding 4 7, Priority 3
" CMC switches are of several types but are not coded for easy recognition of type, e.g.,
i
- 1. spring return to center
- 2. selector type which stop in position selected
- 3. maintain position of f - spring return from start."
Response
i Re fer to B-6, Finding 1 below. B-6, Finding 1, Priority 1 i j "Compo.. at/ Instrument tag numbers are not shown on controls, (e.g., valve ! no.). Cross ref erence to procedures, P& ids, and to Plant Auxiliary operators
- may be more dif ficult and prone to error. Error is more likely because of j inconsistent terms on labels among the plant equipment, documentation, and
- control panels."
Response
I Micro-switch coding will be applied prior to Licensing. Figures 2.15-1 and 2 1 illustrates the symbology to be applied which diff erentiates the associated
- process component; m ore-l e s s , open-close; spring return direction; b reake r j type, and tag numbers from the Dnergency Operating Procedures. 1 l 2.15-6 Rev. No. 1, (12/82)
l 2317W-7 B-4, Finding 20, Priority 3 Micro-switches i "According to operator, some spring-re turn micro-switches which allow partial opening of valves (bezel marked ' bore-les s") must be turned and held for up to 10 seconds. Knob size and torque requirements make this difficult. This is an apparent violation of NUREG-0700, Para. 6.4.4.5.F."
Response
Several operators have manipulated the subject micro-awitches with no operational problems. In addition, LP&L has made a random check on the micro-switch torque throughout the Control Room and has found that the maximum torque measured is within the NUREG-0700 guidelines. B-6, Finding 24, Priority 2 Tagouts are large and obscure adjacent controls and indicators (e.g. , LCP-43) .
Response
LP&L will devise a means of tagging out equipment by Hot Functional Testing so l1 tha t the tag doea not obscure adjacent controls and Indicators. B-4, Finding 12, Priority 1 "Many key switches operated by the same key. Was told there were four keys for all key switches, although there will be several sets of keys." NRC Review Team Comment: It could not be verified that there were four keys f or all key switches. Key control procedures are not in place. i
Response
A key is assigned to each particular key switch. The same type of keys are used to operate key switches of redundant equipment. A tabulation will be prepared to identify each type of a key with its associated key switch prior to Licensing. l1 B-4, Finding 13, Priority 3 "Per NUREG-0700, Paragraph 4.4.3.a key switches are to be used when unauthorized operation must be prevented or to secure against activation by unauthorized personnel. This is not the case in the Control Room." NRC Review Team Comment: Keys are also used in administrative control.
Response
The key switches are used to ensure an administrative control of plant operation and to prevent a breach in pressure boundary through erroneous operations of pressure boundary isolation valve by operators. I 2.15-7 Rev. No. 1, (12/82) ]
,---y
4 2 317 W-8 B-4, Finding 16, Priority 1 "The locked position is not identified for some keylock switches."
Response
The " locked" position of the key switch is the position in which the key can be removed from the key switch by Hot Functional Testing. l1 All key switches operating equipment will be provided with locked position indication on the keyswitch. The exception to this convention are synchronizing switches where indication i of locked position is not considered to be necessary. 1 l B-4, Finding 7, Priority 2 "Pushbuttons do not provide a " click" on operation as required by NUREG-0700, Paragraph 6.4.3.1.b (according to operator reports). " Click" provide s confirmation of intended control action." NRC Review Team Comment: There is no tactile click to denote switch contact when the pushbuttons are depressed. The pushbuttons depress to bottom of travel with constant resistance.
Response
i There are several pushbuttons which have no audible or tactile " click" when operated. These pushbuttons have immediate visual or audible feedback not generated within the button. Good engineering does not rely on locally generated feedback, but feedback from the proces s. A broken wire on the pushbutton would cause the function to f ail even though the operator has been, given tactile feedback. Operating experience in power plants indicates that pushbutton operation for critical tasks is not performed as part of a rapidly developing sequence, but rather as a single function to be verified prior to proceeding. B-5, Finding 8, Priority 1
" Operators report that panel indication of status of solenoid-operated devices are driven by status of the solenoid (i.e. , energized or de-energized) and not the actual status of the actuator service. A f alse indication may result, i therefore, if the device " hangs up." NU REG-0700, Paragraph 6. 5.1.1.e.1 requires that actual as opposed to commanded status be indicated." l1
Response
This HED is incorrect. The position of limit switches on the process valves is what is indicated. The indicating lights on micro-switch control stations indicate the position ! of the valve. The indicating lights are operated through the contacts of i limit switches that are physically mounted on the valve movement. l 2.15-8 Rev. No. 1, (12/82)
2317W-9 i , B-5, Finding 37, Priority 1 i " Operator reports that while a valve is cycling, some micro-switches will show both "open" and " closed" lamps on; others will show both lamps off. Neither method displays the "from and to" status."
Response
When valve is cycling in intermediate position of tne travel span, both red and green lights will be "on" in conformance with valve position indicating criterion, as outlined in B-5, Finding 35, below. This is a normal situation for the control valves that are automatically modulating process flow. The situation where both red and green lights are off when valve is in a modulating mode of control is contrary to the valve position indication criterion. B-5, Finding 35, Priority 1 l " Operator reports that when some valves are actuated, both micro-switch
- indicator lamps go off until the valve cycle is complete. No indication is given of direction of travel. Further, if a breaker trips when the valve is first operated, both indicator lamps will go out, giving false indication that the valve is traveling."
Response
l The criterion for valve position indication is as follows: I l
- 1. Only green light is on, the valve is in the fully closed position.
- 2. Only red light is on, the valve is in the fully open position.
- 3. Both, green and red lights are on, the valve is in intermediate position.
! This criterion for valve position indication is applicable to all process j valves. - In few rare occasions where the valve is a solenoid valve mounted directly on ! the line of small diameter and is normally furnished with position contacts that cannot fully satisfy this criterion an exception is taken for intermediate position of tne valve where both red and green lights will be off. However, the travel of the solenoid valve stem is of extremely short i duration (approximately one second) and, therefore, the above exception in ! position indication cannot cause any operational problem. t Wherever the direction of valve travel or exact valve position indication is required, a valve position meter, with 0 to 100% valve open position scale is provided, if the power sutply breaker trips, the indicating lights will go out for a longer time than one second. This condition is a direct indication of loss of power on any circuit. i i f 2.15-9 Rev. No. 1, (12/82)
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1 I 2317 W-10
! B-5, Finding 36, Priority 1
" Micro-switch Lamps Some micro-switches have No. 755 lamps (6.3 volts); some have No. 756 lamps (14.0 volt s) . Bulbs have identical size and shape; No. 755 has number printed on base. No. 756 has number engraved in base. Wrong lamps may be inserted during relamping. If 755 is is socket for 756, bulb life is under 20 minutes, in our test. If 756 is in socket for 755, brightness will be unacceptably low, indications will be missed. Specifically, No. 756 lamps are used in the electrical mimic CP-1, No. 755 lamps are used in CP-8."
Re spons e i
! The reason for the two dif ferent lamp types is that one is used for the ac circuits, the other is used for the de circuits. The proper replacing of lamps will be controlled through, administrative procedures which will be 1 implemented prior to Licensing. LP&L is also studying different colored bezels.
B-4, Finding 9, Priority 1 "On the CP-1 Turbine Generator and Feedwater panel, the CP-8 Engineering Safeguard System Panel, and the CP-1811VAC and Containment Isolation Panel, the switch / indicator lights are not dual filament or dual bulb and there is no lamp tes t capability."
Response
9 ) Re fer to B-4, Finding 10 below. i j B-4, Finding 10, Priority 1
" Micro-switch Lamps No lamp teet feature is provided. Dual lamp indications are rare. These characteristics violate NUREG-0700, Paragraph 6.4.3.3.c o l. A lamp "off" signal is used throughout panels for positive display infonnation."
- NRC Review Team Comment
- The only lamp tes t provisions are on four Channel Reactor Protection and Engineered Safety Feature panels and on the Fire
; Protection Pane l ( FPE-3) .
Response
3 The general industry practice does not require the test capability f or the indicating lights on control panels nor an across-the-board use of dual filament bulbs. 1 The equipment monitoring lights normally have a dual indication; either a red or green light is on all the time. The case where both red and green lights
- are of f on the same station is a clear indication of abnormality to the operator.
I
- 2.15-10 Rev. No. 1, (12/82)
2317W-11 In the case of single indication, such as amber or white lights, dual bulbs are used to provide a back-up for a burned-out bulb until the bulb is replaced. LP&L experience with existing plants has not identified any operational problems with detection of burned-out bulbs and their replacement. Introduction of an additional, expensive circuitry to the control panels for the purpose of performing tests for indicating lights is considered to be unwarranted on account of its extremely high cost and detrimental effect that i it may have on overall reliability of the control circuits inside the panels. As part of the shift turnover procedure, the operators will conduct a control panel walkdown; any indicators which are not properly lit will be identified and investigated. l i I i 4 4 2.15-11
-- - , - - , - - - , - , - - -. - ----- -.--. ,,-.,. - - r-.n . . - , . , - - - , , . , _ , . . , e--.-n.. ,, , ._ , , - - --.--n,
2317W-12 2.15.3 METERS B-6, Finding 44, Priority 1 "The snap-on labels which attach to the bottom and top of the vertical meters are interchangeable and subject to mix-up. Since there is no " keying" mechanism, any label can be attached to any meter. A mix-up of labels, at some point in time, seems inevitable. The " snap-on" design is poor. Labels j are already falling off, slipping, etc."
Response
The labels will be permanently affixed to the wedgetts as part of the 1 enhancement effort. This action will be implemented prior to Licensing.
, B-5, Finding 11, Priority 1
" Labels attached to the meter bezels do not adequately describe the parameter the meter is measuring. If the meter is indicating level, the word level should be included in the title. If it is pressure, then PRESS, etc. The only parameter the scale should show is the units of measurement."
; Response '
i The meter labels are being enhanced and corrected. This is being accomplished l as part of the enhancement eff ort by Hot Functional Testing. Meter scale 1 changes, as required, will be completed prior to Licensing. B-6, Finding 25, Priority 1 i
; " Meter labels (Wide / Narrow Range Meters) do not include the designators, " wide i
range" or " narrow range" as appropriate. Labels should be accurate."
Response
Labeling will be enhanced to Hot Functional Testing to include " wide range" l1 and/or " narrow range" as appropriate. B-5, Finding 16, Priority 1
" Pressure is displayed on many dif ferent scales: PSI absolute, PS1 4
atmospheric, PSI dif f erence, PS1, inches Hg , inches water. Confusion is most likely if dif ferent pressures must be integrated or compared during operating , evaluation of status of problem diagnosis." F2sponse
! All engineering units on scales of indication are in accordance with accepted engineering practice s. Af ter further review it was concluded that no change is required. Scales are appropriate f or the parameter being measured.
i i 2.15-12 Rev. No. 1, (12/82)
r 2317W-13 B-5, Finding 12, Priority i n
" Questions exist on the scales labeled (%) percent as to the real intent of the unit measurement. Does the percent label refer to the " percent capacity" of the tank (before it overflows) or the " percent full" range established by L engine e ring? "
Response
Initially any indication beyond 100% is out of range and may be considered as overfill in the case of tank level measurement. All meter displays show the
, working range of a tank within the meter band.
All percent scale meters are measuring tap-to-tap on the reference leg. If the fluid level is below the lower tap, then the operators consider the tank If the fluid level is above the upper tap, then the operators consider empty. the tank to be full, which will usually initiate high-level alarm. B-5, Finding 21, Driority 3 "In many cases, despite ample space on a meter scale f or the full valve numeric designations, scale values are shown with multipliers, e.g. , X100 or .3 X10. Operator may err in reading. This is especially likely if he is transitioning between Actual, 410 and X100 or X1000 ut X103, 106, etc, There is no consistent pattern presented across the control panels."
Response
3 HED Committee has concluded that there is only some nuisance f actor with the reading of these multipliers. A review is in progress which will identify 1 those scales which may cause operator conf usion or may be awkward. The identified scales will be replaced or modified in accordance with NUREG-0700 guidelines prior to Licensing. l1 =1 B-5, Finding 2 3, Priority 1 "Many scales, varied ranges and graduation increments. Many are very i confusing and difficult to interpolate. HFE practice and NUREG-0700 recommend graduations in increments of 1, 2, 5 on 10 multiples thereof. Recommended practice also calls f or no more than 9 graduations between numbers. Also, graduation marks should be highlighted at major intervals." l [
Response
Re fer B-5. Finding 22 below. B-5, Finding 2 2, Priority 1 =
"Discriminability of minor and intermediate scale markings is poor. The ir dimensions violate the guideline s o f NU REG-0700, Par a. 6. 5.1.5."
2.15-13 Rev. No. 1, (12/82)
2317W-14
Response
LP&L has evaluated the meter scales and those that are a problem will be corrected prior to licensing. B-6, Finding 20, Priority 1 Meter Labels
" Meters with single scale have pointer on lef t (scale number on right) and are labeled on the bottom. Meters with dual scale are labeled on the bottom for the scale with pointer on the right, i.e., the lef t pointer scale is labeled on the bottom when single; labeled on the top when double. (The latter convention is good, but it conflicts with the poor convention on single scales.)"
Response
Meters will be labeled correctly and consistently by Hot Functional Testing as part of the enhancement ef fort. l1 E-8, finding 13, Priority 1 "There a re tuo types of dual scale meters:
- 1. Displaying two parameters, and
- 2. Displaying one parameter and one setpoint.
Because of their identical appearance, clustered installation, and subtle label dif ferences, the operator could mistake a setpoint scale for a parameter reading - especially under current labeling practices. The reverse interpre tation may also occur."
Response
Re fer B-5, Finding 9 below. B-5, Finding 9, Priority 1 "Many dual scale meters use one side for parameter s tatus, the other side for setpoint. It a p m' .- that the term "setpoin t" is generic and does not differentiato cetween:
- 1. Se tpoint as desired status (from which actual status deviated +).
- 2. Upper limit - representing either a caution alarm or trip point.
- 3. Lower limit - representing either a caution alarm or trip point.
The operator would be aided by dif ferentiating among No. 2 and Ne, 3." 2.15-14 Rev. No. 1, (12/82)
2 317W-15
Response
The setpoint is an indication at which value of a parameter the ESF actuation will take place. To distinguish it from the parameter scale a thin (translucent) blue film will be added at the border of the setpoint scale. B-5, Finding 14, Priority 3
" Single scale meters display preferred f ormat with pointer on one side, and touching tic / graduation marks, with numbers on the opposite. Pointer, therefore, does not cover numbers and reading accuracy is permitted by adjacency of pointer and graduation marks. Dual scale meters break these conventions by repeating numbers on either side. A preferred design would place numbers in the center with graduation marks on either side for adjacency to respective pointers. The natural (and preferred) result of this is that dual scale meters must share common scale index. Mixing scales makes interpolation dif ficult and can lead to clutter and error."
Response
The pointer of the indicator comes close to the graduation marks but does not cover them. Therefore accurate readings can be determined. Corrective action is not required. 1 B-5, Finding 34, Priority 3 "Th e r e is a lack of operating zone markings on meters throughout the Control Room . "
Response
J Re f er to B-5, Finding 33 below. 1 B-5, Finding 33, Priority 3 "No visual aid to tell operator if value is out of tolerance or in tolerance. No meter banding is used (i.e. , green zone , red zone , warning zone) ."
Response
LP6L will provide temporary zone marking on meters f or which it would be y beneficial to have operating . cones indicated, prior to exceeding five percent power. LP&L will provide meter banding in selected cases prior to startup following the first refueling af ter operational experience confirms the proper ranges f or the meter banding. B-5, Finding 10, Priority 3 "Most meters f ail to the bottom of the scale rather than to of f-scale."
Response
This finding applies to meters that are calibrated based on 0-10 volt signals. If a meter suddenly gors to bottom of the scale, then the operator will check redundant or diverse parameters and quickly realize the meter has failed. There are never any zero readings on these meters. l1 2.15-15 Rev. No. 1, (12/82)
1 2318W-1 r 2.15.4 RECO RDERS B-5, Finding 44, Priority 1 " Strip Chart Recorders Scale ranges vary widely among the strip chart recorders, according to measured parameters, e.g., 0-100; 0-200; 0-30000; 465-615; 0-600, etc. At present, one standard paper scale is installed in recorders." , NRC Review Team Comment: All recorders presently have the wrong paper."
Response
The recorders were ordered with a minimum 12 month supply of the proper chart paper. The NRC audit reviewed recorders that had a standard factory test chart loaded. Each recorder will receive its proper chart-prior to Hot i Functional testing. B-5, Finding 42, Priority 3 "9 trip Chart Recorders Many different scales are needed on the various strip chart recorders. Assuming that correctly scaled paper will be installed, the problem arises that during paper replacement, the incorrect roll (with mismatched scale) will be installed. The potential result will lead to reading errors. This error , has been reported at other plants."
Response
Each recorder is provided with a minimum 12 month supply of its proper chart paper. Each style of chart has a unique identification number which will be . . affixed to the mating recorder. This will assist in insuring that the proper replacement chart is installed by Hot Functional Testing, y B-5, Finding 41, Priority 3
" Strip Chart Records Recorders fall to comply with several points of NUREG-0700, para. 6.5.4.1. -
- 1. No provision for tearing off record strip.
- 2. No provision in design or location to facilitate annotation of records.
- 3. No easy selection of paper speeds or fast runout speed are provided.'
x 2.15-16 Rev. No. 1 (12/82)
\
2 318W-2
Response
- 1. There is no tear-of f attachment to the recorder. However, the record strip can be cut of f with the remainder of the roll remaining in the r e cord er.
- 2. The recorder chart platen is designed for easy marking of charts, and prevents distortion of the paper by its design.
- 3. 3/4 inch per hour is the only speed provided for plant historical cota. Fast runout is not provided since 2 hours is all that is I generally needed. The plant computer has sof tware for pre-selected events tha t provides 2 hours of pre-event historical data and 4 hours of on-line s torage post event.
1 B-5, Finding 19, Priority 3
" Strip Chart Recorders Scale labels do not indicate that values must be multiplied by 100 or other factors; i.e., scales are inaccurate. ( Re: 070 0, 6.5.1.4(b) , pg . 6.5-6) ."
Response
A review is in progress which will identify those scales which may cause operator confusion or may be awkward. The identified scales will be replaced or modified in accordance with NUREG-0700 guidelines prior to Licensing. l1 B-5, Finding 43, Priority 3
" Strip Chart Recorders
- 1. As installed, there is a mismatch among scales on recorders between the (hard) parameter scale on right side and on the paper. In many scattered cases, a third scale appears as a decal on the lef t side of the window - representing a second parameter. This results in increased scale conflict.
- 2. In some cases, the decal scale is not aligned with the major line divisions on the installed paper.
N RC Review Te am Comment: ltem 1 recorders are dual pen recorders."
Response
The decal scale is provided as an operator aid, facilitating the recognition i or parameter values. The decal scale is aligned with the required values upon l1 2.15-17 Rev. No. 1, (12/82)
2318W-3 calibration. Tne recorders observed were not calibrated. Where dual recorders witn different scales are required the chart paper will have alternating or superimposed cycles for each scale installed by Hot Functional i Testing. B-5, Finding 40, Priority 3
" Chart Recorders Recorders are used for trending historic information. The window sizes of the recorders being installed on CP-8 do not afford easy visual access to information being tracked."
NRC Review Team Comment:
"The recorders must be pulled out of the vertical panel to read the time history record on the chart."
Response
This " time window" visible f rom the f ront of the recorder is approximately two hours, which is sufficient for most operator needs. With a simple operator action, an additional twelve hours are visible by withdrawing the recorder. This is an infrcqueat action during all uudes of reactor operation. B-5, Finding 39, Priority 1
" Strip Chart Recorders Scales are for recorders that feed left to right. The recorders feed right to left. (Graduation markings are on the side of scale away from paper).
Momentary (or most current) readings are difficult because of paper roll inset and position of stylus. Ilard scale does not have separate pointer, therefore, operator must refer to paper trace which is poorly associated with hard scale."
Response
The scale markings are placed away from the chart paper so that the pointer does not obscure the scale markings. The stylus is being adjusted to bring the stylus to paper contact into a position which is readily visible to the operator without requiring manipulation. All pens for the Control Room are fitted with arrow indicators which overlap the hard scale. Some recorders viewed during the audit were not yet fully assembled and were still in their shipping configuration. The decal scale also has an arrow indicator which is not adjacent to the decal scale, but which is well associated witt the chart scale and readily visible to the operator. The hard scale and chart scale are properly alid ned as part of the initial calibration of the recorder. 2.15-18 Rev. No. 1, (12/82)
2318W-4 2.15 .5 PHYSICAL ITEMS B-1, Finding 8, Priority 1 "Th e r e is a hole in the Control Room flocr with a protruding pipe that presents a tripping hazard."
Response
i 1 There will not be any holes in the Control Room floor prior to Licensing. I B-1 Finding 14, Priority 3 "The dimensions of the control board (console) are such that readability and access for the shorter potential operators is not accommodated. Based on a review of civilian population anthropometric data, it is estimated that the 5th percentile female will have a functional reach approximately 5 inches above the start of the vertical plane of the control boards. Result: Some important controls may be out of reach, e.g. , Turbine Trip; Lockout relay trip on CP-1; Sa fety Ac tuation on CP-8. Upper ends of many vertical meter scales may be very dif ficult to read."
Response
Re fer to B-1, Finding 15 below. B1, Finding 15, Priority 3 "The Main Control Board layout in general is not designed to accommodate the 5th percentile female. Many displays even exceed the recommended viewing envelope for the 50th percentile male." Re spo ns e Pnotograph 2.15-2 shows that the shortest operator (5 '-2" male) can in f act I1 reach the highest controls on CP-1. Manual operation of these controls is infrequent, deliberate and generally unhurried. Likewise, the most significant displays are felt to be readable especially within all but the mos t extreme upper ranges. Of ten recorders showing the same parameter are located below the meters and the plant computer displays can and will be used during normal operation. During startup testing and emergency procedure validation any significant readability or control problems will be identified. Anthropometric problems will be evaluated based on the increased potential f or operator error, and the criticality of the resulting error. A report will be submitted to NRC 60 days 1 prior to Licensing. As necessary, studies to determine feasible corrective action will be made. Possible fixes might include physical relocation, allocation to the plant computer, a change La larger meter scales with increased letter size to enhance visibility f or very high (70") meters, etc. 2.15-19 Rev. No. 1, (12/82)
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3.0 COMMUNICATIONS L' _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._. ._ __ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
2339W-1 3.0 COMMUNICATIONS The Waterford-3 Plant Communications System has the capability of providing intraplant communication, offsite commercial telephone service and offsite emergency communications. Intraplant communications is accomplished by a Private Automatic Branch Exchange (PABX) Telephone System which is interconnected with South Central Bell, a high level voice paging system, radio communication system and a sound powered phone system. The PABX telephone utilizes modern electronic type switching equipment capable of simultaneously supporting thirty extension stations located strategically througnout the plant. Failures in the PABX are annunciated in the MCR and Remote Shutdown Panel Room. The Paging System consists of four independent channels powered by two preamps and five power amplifiers. To improve reliability, the speaker load is divided evenly into nine zones each covered by two channels. Voice paging announcements, site alarms, and plant evacuation signals are broadcast throughout the site by this system. Plant evacuation signals are in accordance with 10CFR50, Appendix E and fire alarm signals meet appropriate NFPA standards. Three radio communication systems are provided for operation and maintenance (OSM) plant security and offsite communications. The O&M and plant security systems utilize separate FM frequencies. The offsite communications system operates on LP&L's assigned FM frequency and is capable of communicating with Sherif f s and Civil Def ense Of fices. Communications between the MCR and the plant staff working in remote areas of the plant is accomplished using the sound powered phone system. There are 1 eleven independent sound powered phone circuits. In addition to high reliability, this system also serves as backup to the normal PABX system. The sound powered phone system requires no external power source. The MCR and the Remote Shutdown Panel Room are both equipped with PABX dial telephones, paging, radio and sound powered phone facilities. The technical support center is provided with its own dedicated telephone and sound powered phone system. The following findings pertain to the communication system: B-1, Finding 25, Priority 1 )
"The PA system speaker for the Remote Shutdown Panel area is too large for the limited / confined area that it covers. The area is approximately 13 1/2 ft square. The speaker cone is approximately 20" in diameter."
Response
The subject speaker has been removed and has been replaced by a surface mounted cone type speaker (8 inch diameter) with integral volume control. 1 3.1-1 Rev. No. 1, (12/82)
2339W-2 B-2, Finding 1, Priority 1 "Ma provisions have been made in the Control Room for the operators to be able to block incoming calls routed to the Control Room by the Universal Non- Answering system, and the Predetermined Non-Answering system. These calls are presently transferred to the Control Room when the plant telephone operator is of f duty." Re sponse Prior to Licensing LP6L will provide a provision for blocking incoming calls 1 to the Control Room by having all calls routed to security during of f-duty telephone operator hours. B-2, Finding 2, Priority 1 "The Remote Shutdown room has no provision f or communications, i.e. , no telephone; no sound powered phone."
Response
A multi-button key set and sound powered telephone monitor /patchboard panel, y both identical to the Control Room equipment will be provided prior to Liceu. sing ( DCN-E-915) . B-2, Finding 3, Priority 1 "The Transf er Switch room has one telephone near the Train A panel, and none within reach of the Train B panel."
Response
Two additional telephones will be installed prior to Licensing to provide complete coverage of the transf er switch panels. ( DCN-E-92 2 ) B-2, Finding 4, Priority 1 "The vertical handsets on the 11ain Control Board are located at knee level on front of the benchboard. In this location they are easily knocked of f their cradles. No f orm of protection is provided."
Response
Guards will be installed prior to Licensing to minimize the possibility of an 1 operator accidently knocking a handset from the cradle. ( DCN-E-56 9 ) B-2, Finding 5, Priority 3 "The ring level telephones in the Control Room is not adjustable." Re s po ns e The ring level is internally adjustable. The ring level will be established prior to Licensing. 1 3.1-2 Rev. No. 1, (12/82)
23394-3 B-2, Finding 6, Friority 1 "The Control Room does not now have a priority access system for communications, i.e. , PA System Procedures are not established." Re sponse LP&L will have procedures established for the PA system prior to fuel load. B-2, Finding 7, Priority 3
" Sound Powered Phone Module
- 1. Panel location requires operator to kneel f or use.
- 2. Panel is mounted at 15* nnele f orward of vertical and is not easily readable f rom s tanding position."
Re sponse A design change for the sound powered telephone monitor /pa tchboard panels has been issued which will make operator use and readability easier. The circuit selector will now be located above the jack outlets at ( DCN-E-915 ) . Refer to risure 3-1. This change will be made prior to Licensing. l1 B-2, Finding 8, Priority 1
" Th e re is no index which identifies stations / circuits on the sound powered tele phone patch panels on the wall in back of back rack areas behind CP-25 and e nd o f CP-14. "
Re spom.e An index will be provided for each sound powered telephone monitor /patchboard I panel in the Control Roon by llot Punctional Testing. (DCN-E-915) b-2, Finding 9, Priority J
" The re is no provision f or s corage of sound powered telephone headsets in the Control Room. Present storage is in the maintenance area of an adjacent service building."
Re s po ns e Irovisions f or Control Roon storage of headsets will be provided prior to 1 Licensing. _-2, B Fi nding 10, Priori ty 1 "Ihere are no sound powered headsets or storage provisions area f or them in the Transfer Switch room or in the kemote Shutdown Panel area." Kesponse Sound powered headsets and storage provisions f or such will be provided in the relay room and the remote shutdown panel room.
2339W-4 B-2, Finding 11, Priority 3 "The sound powered phones selector in the back panel area has different jack and selector designations than those in the Control Room area. Designations are temporarily stamped on a metal plate. Examples: a) Control Room jacks read 1, 2, 3, etc. b) Back panel jacks read J1, J2, etc."
Response
The design of the sound powered monitor /patchboard panels will be standardized throughout the Control Room prior to Licensing. 1 (DCN-E-915) , B-4, Finding 19, Priority 1 "On the sound powered telephone rotary selector switch, it is difficult to see the position selected. The pointer is obscured by the switch. On the 12 position rotary selection switch, 11 positions are marked as used and the 12th positilon is blank and not used."
Response
Changes will be made to the sound powered telephone monitor /patchboard panels enhance operability and readability prior to Licensing. 1 1 B-6, Finding 22, Priority 3
" Sound Powered Phone Module Poor Labeling - component relationship: vertically oriented and numbered circuit directory above a 3 row, 4 column jack matrix above a rotary circuit selector switch. See NUREG-0700, pg. 6.6-3 to 6.6-8, Para. 6.6.2.1."
Response
Refer to B-6, Finding 43 below. B-6, Finding 43, Priority "On the sound powered phone patch panel stations, there are,
- 1. No identification labels on sound powered patch panel stations.
2 lllegible selector position indicator.
- 3. 111egible plus and selector position labels.
4 Poor accessibility of panel." 3.1-4 Rev No. 1, (12/82) l
l l 2339W-5 t
Response
A new arrangement, labeling and index will be provided for the sound power 1 phone modules prior to Licensing (ref. DCN-E915). Refer to Figure 3-1. In addition to the above communications HEDs dispositions some of the items not available for review at the time of the Control Room audit (refer to Section 18 of the NRC report) have been evaluated and are discussed below along with dates for review and evaluation of procedures and instructions not in place at the time of the audit. 2.0 Items A.1, A.3, and A.4 The Normal Operation Communication Procedure will be prepared and reviewed by February 1983. This procedure will include a description of communication equipment available and instruction for its use. Items A.2 Emergency Planning Communication Procedure (EP2-010) is in place. Control Room priority interrupts for communications system access are as follows: (a) Public Address System Control Room operators have public address system voice priority by operation of the control board telephones in the "page" mode by using the button located on top of the phone. Use of the "page" mode silences all other ongoing public address announcements in the plant and assigns priority to the Control Room operator for broadcasting emergency messages or instructions. Control Room operators have public address system alarm priority by operation of the communications control panel site evacuation or fire alarm pushbuttons. This panel is located in the Shift Supervisor's Office. Operation of either alarm silences ongoing public address announcements in the plant and broadcasts the alarm. Ad d i t ional ly , these alarm signals have priority over the Control Room operator voice signals described in (a) above. An enable / disable switch has been provided on the communications control panel to momentarily return priority to Control Room operator voice signals when necessary. (b) Telephone System Cot?rol Room operators have unrestricted access to the telephone system including all intraplant extensions and offsite central office trunks. Telephones are provided on the control board, at the operator's desk and in the shift supervisor's office. The Sntft Supervisor also has access to WATS lines. 1 3.1-5 Rev. No. 1, (12/82)
2339W-6 I (c) Sound Powered Telephone System Control Room operators have priority access to all circuits (11 provided) in this system from the Sound Powered Telephone Monitor /Patchboard Panels located on the main control board. (d) Radio System Control Room operators have priority access to the Operatiuns and Maintenance Radio System. A remote deskset has been provided in the main Control Room at the operator's desk for this purpose. 2.0 Item B UHF transceivers will be used in the Control Room during startup and pre-operational testing. Digital equipment vendors will be contacted and asked to submit any data concerning their equipment's susceptibility to radio frequency signals both past and present. If it is determined that UHF transceivers will cause a problem, then they will not be permitted in the Control Room after Licensing and radio desksets which are handwired to the UHF 7 transmitter / receiver will be used. 7.0 Tron C A survey of the Public Address System is planned for January 1983. The survey will provide data on the degree of voice and alarm signal coverage and the ability of the voice and alarm signals sound pressure level to overcome the ambient noise level throughout the plant site. 2.0 ltem D A survey of walkie-talkie area coverage throughout toe plant will be conducted 60 days prior to fuel load as part of system checkout. y 3.1-6 Rev. No. 1, (12/82)
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r_.- 4.0 PROCESS C0f1PUTER 4
2352W-1 4.0 PLANT MON 1TORING COMPUTER The Waterf ord-3 Plant Monitoring Computer System's primary purpose is to aid the operators in the safe and reliable operation of the plant. The system meets this goal by providing pertinent plant information for maintenance, operations, engineering and management personnel within the plant as well as provide information for the Emergency Response Facilities established for Waterford-3. The NRC Audit Repo rt expressed concern over the lack of available information to properly evaluate the computer system. Presently, procedures to control access to the data base are written and approved. The Data point indices which identify the points in the system will be produced as these procedures are used. However, operators will normally not i.te books to find information in the computer. The system is a CRT bacad system which provides the operator with the information needed without the use of list or indices. The main purposes for hard copy devices are historical records, maintenance documentation, and engineering functions. At the present time many of the CRT display formats exist. By utilizing CRT's for display and having a sof tware based system, LP&L has the flexibility of making the terminology of ths computer system consistent with other equipment in the Cont rol Room. The only limitation being the number of characters that can physically be displayed on the CRT screen. This extensive use of CRT's virtually eliminates the need for any other means of data display. In extreme cases of multiple equipment malfunctions or when operators desire a hard copy printers are available. It was never the intent o f the system to replace existing hardwired instruments essential for the safe operation of the p: ant. All information nec e ssa ry for the safe operation of the plant is provided independent of the computer. LP&L did however take advantage of the computer system by providing a large amount of information in a very concise and manageable format. Without the use of the computer system it would be very di f ficult if not impossible to provide an equivalent amount of information in the space available. 4.1-i
5.0 ENVIRONf1 ENTAL FACTORS 5.1 LIGHTING
l l 2336W-1 5.0 ENVIRON!iENTAL FACTORS 5.1 LIGHTING B-1, Finding 20, Priority 1 "The present overhead lighting system with fixtures inset into the ceiling in rows and a special row over the length of the main control board produces:
- 1. Uneven illumination and reflections / glare off main control panel meters, chart recorder windows, CRT displays and micro-switch face plates. Readability is difficult at each noted location.
- 2. The light level is too bright at CRTs for comfortable viewing.
- 3. Surrounding surfaces reflect light and add to glare, e.g., main control panel, tiled walls and floors."
Response
The Control Room lighting switching arrangement allows independent control of the lighting within the control board area. Switch controls are provided in the Control Room. The luminous strip over the control board, each fixture immodiately behind the control board and all remaining fixtures within the control board area are to be equipped with 1/2" x 1/2" x 1/2" opea cell black louvers to reduce veiled glare on CRT screens, gauges and switches. Additionally, the luminous strip is equipped with opal matt diffusers to reduce glare on switches located on the horizontal slanted section of the control board and reduce glare bands on meters with bezel covers. The entire Control Room will be lamped with F40 T12 RW/3 regal white lamps to further reduce brightness (DCN-E-915). Following the above changes, a survey for both ac and de lighting will be made and the results submitted to NRC 60 days prior 1 to Licensing. B-1, Finding 21, Priority 1 "The Remote Shutdown Panel room lighting is harsh and creates a shadowing effect on the control panel surfaces. The lower panel is subject to brighter direct lighting while the illumination level of the upper panel portion is noticeably lower."
Response
New lighting fixtures are being installed to provide a softer quality of light and an additional fixture plus a change in the lighting layout will reduce the shadowing effect (DCN-E-920). The Remote Shutdown Panel room lighting will 1 also be included in the lighting survey (see response to B1-1, Finding 20). 5.1-1 Rev. No. 1, (12/82)
2336W-2 B-1 Finding 23, Priority 1 "The Transfer Switch Room battery operated DC emergency lights appear to be inadequate for an operator to perform emergency functions during the 15 second delay period required for AC emergency lighting to come on."
Response
Six additional DC emergency lights are being installed in the relay room to provide sufficient lighting for emergency operation during the 15 second delay period required for AC emergency lighting to come on in the unlikely event that there is a loss of offsite power during a transfer to CP-43. (DCN-E-920) B-1, Finding 24, Priority 1 "To provide emergency AC lights in the Remote Shutdown Panel room, there is a period of approximately 15 seconds between the time an offsite power loss occurs and the time diesel generate- loading begins. DC battery lighting is not provided during this 15 second pet ods."
Response
DC cmc rgency lights are beins lastalled to provide sufficient lignting tor emergency operation at CP-43 during a 15 second blackout. (DCN-E-920) 1 5.1-2 Rev. No. 1, (12/82)
5.2 ACC0liMODATIONS
233 6 W-3 5.2 ACCOMMODATIONS B-1, Finding 19, Priority 3 " Tiled / Linoleum floor poses:
- 1. Potential high noise reverberation.
- 2. High lighting reflection and general glare.
- 3. Probable operator fatigue - from lack of floor cushioning.
- 4. Po tential contamination removal problem. (Porous floor is difficult to was h "clea n") .
- 5. Austere environment throughout the MCR because of prevailing hard surface s."
Response
The Main Control Room Area will be carpeted just prior to Licensing with NFPA 1 Class A material per ASTM E-84 (i.e. , max. flame spread rate of 25) and a Flooring Radiant Panel Test result which exceeds 0.45 Watts /cm2 ), Presently, we are cccking quotations frcs several potentially qualified suppliers. The carpeting will also be selected to provide cushioning, patching capability, low static and to improve the Control Room aesthetics. B-1, Finding 17, Priority 3
" Chairs in the Control Room need to be replaced. At time of last visit, there were two new chairs in the Control Room. The others were mended with electrical tape, had sagging cushions, and were worn out."
Response
New chairs will be provided prior to Licensing. l B-1, Finding 7, Priority 1 "It was pointed out that maintenance personnel walk over to the operators console and use the desk top to fill out their paperwork. There is no space available to them at this time to write and fill out f orm s. From time to time, others with legitimate business will also need a desk area."
Response
During normal operation the maintenance personnel will do the major portion of their paper work outside the Control Room. Generally when inside the primary viewing area clip boards will suf fice. In the back panel area maintenance carts can be used. 5.2-1 Rev. No. 1, (12/82)
2336W-4 B-1, Finding 9, Priority 2 "The console was designed to acconmodate one operator. The second operator is required to stand directly in front of the control panels at all times (an LP6L requirement) . Opinions seem to be that this is an unrealistic requirement and will change once the plant is operational. Desk space should be provided for this second operator at the operator's console. There is very little storage space at the console for paper, pencils, staplers and all the o ther small but necessary items. There is no storage space for books, logs, etc. Presently, books are standing on end on top of the desk, obsc. ing the operator's view of the control panels." Re spons e LP6L is presently re-evaluating the operator's console. The number of operators, required desk and storage space as well as the SPDS displays will y be considered during our review. Results of this review will be submitted to NRC by Hot Functional Testing. B-1, Finding 10, Priority 2
" Th e present set-up with a desk for the supervisor and a table with two large CRTS to monitor radiatica represente an inef ficient and incf fective use of space in the supervisor's of fice. During an emergency, there will be a shif t supervisor, a shift technical advisor and possibly the plant supervisor using this of fice space, which now is designed to accommodate one person.
Response
LP&L will evaluate the Supervisors' of fice as part of a Control Room Livability raview which will also cover items identified in Section A.1 of NRC audit report . Results of this review will be submitted to NRC by Hot 1 Func tiona l Testing. B-1, Finding 11, Priority 2
" Th e r e is limited storage space in the Control Room proper. Presently CWDs, FSARs and system descriptions are stored in the Supervisor's office. A print cabinet to store 40 prints was ordered but no other bookcases or file cabinets are in the Con trol Room. There will be a need for additional storage. A roll cart h is been ordered to keep near the control panels. The plan is to keep procedures on the top table of the roll cart where there is suf ficient room to open the procedures out flat and to keep spare parts and expendables such as printer paper, in k, fuses, bulbs, etc. , on the bot tom shelf of the cart."
Response
The study of Control Room livability (see response to B-1, Finding 10 above ) will also address storage of procedures; drawings, system descriptions, FSAR, files, recorder paper, ink, bulbs, keys, fuses, pens, penc ils, etc. The design of the roll cart will also be reviewed. The results of this study will be provided to NRC by Hot Functional Testing and the recommendations implemented prior to Licensing. 5.2-2 Rev. No. 1, (12/82)
2336W-5 B-1, Finding 18, Priority 1 "There was no protective gear in the Control Room. In the room to be used as the Emergency Operation Facilities, there were packs containing breathing apparatus masks and tanks. These should be in the Control Room. There was no protective clothing available."
Response
Self Contained Breathing Apparatus (SCBA) are presently stored in the 1 Technical Support Center. Prior to Licensing these SCBAs and their spare bottles will te moved into a permanent storage locker in the Main Control Room. These SCBAs are on a monthly preventive maintenance and inventory check. B-1, Finding 26, Priority 3 Habitability "A room is needed where Control Room personnel not on duty can go to study, drink coffee or rest. Have been told that off-duty personnel will spend quite d bit of time studying and reading work related materidls. No provision has been =ade for a place of this type."
Response
The Control Room envelope has been provided with kitchen facilities. The technical support center is also in the Control Room envelop which provides meeting and study areas. 5.2-3 Rev. No. 1, (12/82)
6.0
SUMMARY
AND CONCLUSIONS 6.0
SUMMARY
AND CONCLUSIgi Based on the previous sections of this report and its cover letter it can be concluded that Louisiana Power & Light Company has successfully initiated and is well into the implementation of a control room design review and upgrade that satisfies TMI Task I.D.1. Our control room efforts are part of a broad program which we have undertaken to ensure considerations of human factors in the design and operation of our Waterford-3 nuclear power plant. We believe that all human engineering discrepancies that have been determined to be sig-nificant or are easily correctable are being properly addressed in a timely manner. While most corrective actions include design changes, a number of potential human factors problems are addressed by training, or procedure or computer enhancements, as well as combinations of solutions. Some human engineering discrepancies have been evaluated and determined to be insignificant or not truly discrepancies'from acceptable human factors criteria. We hope to have conveyed that LP&L has a sound appreciation of human factors enginaaring principles in eur efforte to improve the ability of the operators to prevent or mitigate accidents by:
- 1. Improving the information provided to them
- 2. Enhancing and thus making the main control panels more intelligible
- 3. Upgrading the enviornment in the control room
- 4. Correcting significant human engineering discrepancies
- 5. Improving procedures and training
- 6. Making best use of the power and flexibility afforded by the Waterford-3 Plant Monitoring Computer.
LP&L believes that the efforts documented in this report will lead to a sig-nificant risk reduction and enhance the safe operation of the plant. While quantification of the reduction to risk is beyond the scope of this report, it is the unanimous concensus of the engineers who were part of our control room task force that the potential for human error has been reduced and will continue to be reduced by the other related projects which are ongoing or planned, such as, the simulator, the emergency procedure validation effort, SPDS, annunciator response manual, maintainability efforts, nuclear training group efforts, other relevant TMI action items, implementation of Regulatory Guide 1.97, etc. Finally we vish to thank the NRC staf f and consultants for their efforts especially in the identification of additional findings during the Waterford-3 Control Room Audit. 6.1- 1
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