ML17299A774
| ML17299A774 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/27/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-34121-EEVB, TAC-56656, NUDOCS 8512020328 | |
| Download: ML17299A774 (24) | |
Text
~
)
REGUL'ATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR",8512020328 DOC ~ DATE: 85/11/27 NOTARIZED+
NO DOCKET-'
FACIL:STN 50 528'a,lo Verde Nuc,lear Stationg Unit iq Arizona Publi.
05000528'TN"50 S29 Palo Verde Nuclear Stationr Unit 2g Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station~
Unit 3i A'rizona Publi 05000530 AUTH ~ NAME.
AUTHOR. AFF ILtIATION VAN BRUNT~K'.E,'r izopat iVuc>>lear Power Project (formerly, Arizona Publ,ic Ser v RECIP-,NAME RECIPIENT AFFILIATION KNIGHTON~G ~ W ~,
PAR Pt oject Director ate
-7
SUBJECT:
Forwards human engineering observation disposition cri ter iai index for. human 'engineering discrepancies 8 proposed corrective actionsiper 850830 commitment re DCRDR.
DISTRIBUTION CODE'e A0030 COPIES RECEIVED;L!TR KNCL SIZE:
TITLE; OR/L'ice'nsing Submitta'1:
- Suppl, 1 to NUREG 0737(Generic>> Ltr"82 33)
NOTES;Standardized plant',
OL'; 12/31/80 Standardized
- plant, Standardized'lant".
05000528 05000529 05000530 RECIPIENT ID'QDK/NAMEI PWR~B PD7 PD LICITRAtE INTERNAL:: ADM/LFMB NRR PAULSONtW NRR PWR A
ADTS NRR/DHFT/HFIB D:IR REG F
ES EXTERNAl.: 2QX NRC PDR COPIES LffTR ENCI 7
7 1
1 1
0 1
1 1
1 5
5 1
1 1
1 1.
1 1
1 RECIPIENT.
ID COOK'/NAMEi PWR~B'O7 I.'A IE/OEPER/EPB NRR PWR-ADTS NRR PWR~B. ADTS NRR/DHFT/MTB NRR/ORAS RGNS LPDR NSIC COPIES'TTR ENCL 1.
1 1
1,.
1 TOTAL NUMBER OF COPIES REQUIRED'TTR 32, ENCL" 31
N I
'h
~
Nh
'h N
~
~
'Nt P
V h h
N.
hh Pl I
I'NN- 'h,
Arizona Nuclear Power Project P.O. BOX 52034 4
PHOENIX, ARIZONA85072-2034 November 27, '1985 ANPP 34121 EEVB/JKO Director of Nuclear Reactor Regulation Attention:
Mr. George W. Knighton, Project Director PWR Project Directorate 717 Division of Pressurized Water Reactor Licensing B U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos.
STN-50-528 (License No. NPF-41)/529/530 Results of the Detailed Control Room Design Review (DCRDR)
File:
85-05626.
G.1.01.10
Reference:
Letter to G.
W. Knighton,
- NRC, from E.
E."
Van Brunt, Jr.,
- ANPP, dated August 30, 1985 (ANPP-33302);
Subject:
Detailed Control Room Design Rev1ew
Dear Mr. Kn1ghton:
In the referenced letter Appendix BB, Section 3.0, Arizona Public Service Company (APS) committed to evaluate the observations which resulted from the PVNGS DCRDR task analysis and control room inventory.
All the observat1ons have been reviewed and categorized as either safety, reliability, reliability-enhancement,
- minor, or non&iscrepancies.
Attachment 1 indicates the Human Eng1neering Observation Disposition Criteria used
'to categorize the observations.
Some observations were not considered discrepancies because these observations have a resolution already implemented.
Attachment 2 provides an index of the observations identified by the above referenced letter to the HED corrective actions identified in Attachment 3 to this letter.
Attachment 3 lists only those observations that we categorized as Human Engineer1ng Discrepancies (HED's)
A, B or C
and their respective proposed corrective actions.
Category D
HED's and non-discrepancy observations are not discussed in this letter but have been dispositioned by the results review committee.
The implementation schedules of the Category A and B
HED's are to have the resolutions implemented prior to startup from the respective Unit's first refueling outage.
The category C HED's vill be evaluated as plant betterment items.
g f,27 boa 85~~ ~
OCW P~
pOR
'3~ 8 00528 F
py3 a /
0
/
t f'
Mr. George W. Knighton Results of the Detailed Control Room Design Review (DCRDR)
ANPP-34121 Page Two If you have any further questions, please contact Mr. W. F. inn of my staff.
Very truly yours, E. E.
Van Brunt, Jr.
Executive Vice President Project Director EEVB/WFg/JKO/dim cc:
E. Licitra M. Ley R. Ramirez R. P.
Zimmerman A. C. Gehr (All w/a)
0 y
~
4 II
ATTACHMENT 1 HUMAN ENGINEERING OBSERVATION DISPOSITION'RITERIA
~(ate or Non Discrepancy Safety Reliability (90X Availability Criterion)
Reliabili,ty (Enhancement)
Minor Non Discrepancy Im lementation Criteria Mandatory Mandatory Non-Mandatory Nonmandatory Non-HED Implementation Complete Note:
Category C will be reviewed as plant betterment items.
E I
Y
)3 "g y c>f l' h
A J
M 4
ATTACHMENT 2 INDEX FOR HED's
He are starting a 200 series for HED numbering.
HED NUMBER 200 201 8/30/85 SUBMITTAL REFERENCE Appendix H 1.1.10 '0p 1 1 10'0 '
10' 1 ~ 20 ' '
Appendix H 4.5.35.5.10.10, 4.5.35.10.10.10, 4.5.35.5.10.35, 4.5.35.10.10.35 202 203 Appendix H 5 1 75 0 0 45, 5 1 75 0 0 50, 5 1 75 0 0 55, 5 1 75 0 0 60, 5 1 75 0 0 65, 5 1 75 0 0 70, 5 1 75 0 0 75, 5 1 75 0 0 80, 5 1 75 0 0 85, 5 1 75 0 0 90, 5 1 75 0 0 95, 5 1 75 0 0 100 Appendix H 13 20 25 5 10 0, 13 20 25 5 15 0, 13 20 25 5 20 01 13 20 25 5 25 0, 13 20 25 5 30 0 204 205 206 207 208 209 210 211 212 213 214 215 216 217 218 219 Table 3-2 Table 3-1 CB Item 177 Table 3-1 CB Item'158 Table 3-1 CB Item 81 and 79 I
Table 3-1 CB Item 157 Table 3-1 CB,Item 126 Table 3-1 CB Item 55 Table 3-1 CB Item 156 Table 3-1 CB Item 33 Table 3-1 CB Item 152 Table 3-1 CB Item NA Non-Discrepancy Non-Discrepancy Non-Discrepancy Appendix I 1.3.40.30.20.25, 1.3.40.30.5.25 Appendix J 3.5.60.5.0.10
e l
E.
tl C
a'b i
~
a
~
220 221 222 223 224 New Event/Task 6.2.10.15.0.0 Appendix I 11.3.20.15.40.10, 11.3.20.15.35.15, 11.3.20.15.40.30, 11.3.20.15.35.20 Table 3-3 Item 4 Non-Discrepancy Appendix I 4.2.30.5.10.15, 4.2.30.10.0.20 Some Non-Discrepancies were inadvertently assigned numbers
kl C
~
o
ATTACHMENT 3 Human Engineering Discrepancies and their Proposed Corrective Actions
Human En ineerin Discre anc Summa (Safet 'andator Im lementation)
HED No.
Discre anc Corrective Action The Reactor Vessel Head and Plenum Level dual pen Recorder (SHA-TR-5) does not have engineering units.
Revise recorder to indicate engineering units that match the QSPDS engineering units.
Also provide indication of Reactor Vessel Level on top half of recorder and Plenum Level on bottom half of recorder.
Incorrect label for handswitch SIA-HS-673.
Correct labels per design drawings.
220 While maintaining the Containment Temperature and Pressure critical safety function using the Containment Spray System, the operator task requires to monitor containment temperature to make sure it is constant or decreasing.
Device RMW-UJR-5 monitors containment temperature but is not labeled as such.
The scale of the device is from 0-100 with no engineering units.
Provide adequate scale and engineering units on recorder.
The adequate range for containment temperature will also be provided.
~
I c<
4
Human En ineerin Discre anc Summar (Reliabilit 90X Availabilit Criterion:'andato Im lementat'ion)
HED No.
Corrective Action 205 13.8KV Bus 1-E-NAN-S01 (NAN-EI-S01A) Supply voltmeter Nameplate is incorrect.
Provide correct device nameplate per design documents.
206 SG2 Downcomer Feedwater Control Valve Position Indicator (SGN-ZI-1123) nameplate is missing.
Provide correct device nameplate per design document.
207 Nameplates for devices.
SGA-HS-204, SGA-HS-211, SGB-HS-219 and SGB-HS-228 are incorrect.
Provide correct device nameplate per design document.
208 Nameplate for device SGN-ZI-122 is incorrect.
Provide correct device nameplate per design document.
209 Scale identification for RCN-TR-lllX is omitted.
Provide correct device scale identifi-cation per design documents.
210 Standby Battery Charger AC Ammeter nameplate is not correct.
Provide correct nameplate per design document.
213 Nameplate is missing on device RCN-ZI-100.
Provide correct nameplate per design document.
214 No description is shown on the nameplates for instruments on the Radiation Monitoring System (RMS) Remote Indication and Control (RIC) Panel.
Provide nameplates to indicate instru-ment description on RIC Panel.
219 While maintaining the Pressure Control Critical Safety Function (CSF) using forced circulation RCP and SG, the operator task requires to verify CST and RMWT status in X units.
The devices available provide tank status in FT.
(Tech Spec's require that the tank levels be monitored in FT.)
Provide meter banding to indicate when tank is full.
222 While maintaining the Reactivity Control Critical Safety Function (CSF) using Chemical and Volume Control System (CVCS), the operator task requires to verify spent fuel pool level.
Provide local spent fuel pool level indication (i.e., marking on side of pool).
r C
t l,
Human En ineerin Discre anc Summa (Reliabilit :
Non-Mandato Im lementation)
HED No.
I Discre anc Corrective Action 200'hile maintaining the Reactivity Control Critical Safety Function (CSF), the operator task requires the opening of Reactor Trip breakers SBA-C03, SBB-C03, SBC-C03 and SBD-C03 or deenergizing CEDM MG SFN-C02A and SFN-C02A by opening circuit breaker NGN-L03C4 and NGN-L10C4, respectively.
These circuit breaker controls were not available to the operator in the control room.
Provide labels on Panel B01 to identify switchgear breakers that deenergize NGN-L03C4 and NGN-L10C4.
201 While maintaining the Heat Removal Critical Safety Function (CSF), the operator task is to verify in control room the train "A" essential cooling water system availability by (1) verifying discharge pressure and (2) surge tank level.
These controls were not available to the operator in the control room.
Provide Surge Tank Level indicator.
202 While performing Containment Isolation, the control room operator task requires the verifying of several manual valves.
These valves do not have controls or valve indication status in the control room.
Evaluate prior to first refueling
- outage, the best method to prevent operators from leaving valve CH-V-584 in open position either through a procedural change or physical indication in control room.
203 While performing the Recovery Actions for a Steam Generator
- Rupture, the operator task requires to monitor or sample.
SG1 and SG2 Cold Leg Blowdown, Hot Leg Blow-down and Downcomer for activity.
Monitoring indications are not available in control room other than on the Radiation Monitoring System (RMS)
CRT.
Demonstrate RMS reliability is suf-ficient, otherwise provide indicators in the control room for SG Blowdown activity.
(These indicators are to be separate from RMS).
204 Several Radiation Monitoring devices used while maintaining the Critical Safety Functions (CSF's) are located on a panel near the main control room.
Evaluate alternatives to improve Radiation Monitoring System (RMS) reliability to provide information to the operator to classify an emergency event in the necessary time-frame.
\\
a
~
C pl I
ll
Human En ineerin Discre anc Summar (Reliabilit :
Non-Mandato Im lementation)
HED No.
Discre anc Corrective Action While maintaining the Reactivity Control Critical Safety Function (CSF) using ECCS, the operator task requires monitoring auxiliary feedwater flow in gpm.
Information in the control room is provided in LB/Hl~
Provide an additional label for down-comer auxiliary feedwater flow in gpm and provide training on application of new scale.
During the Heat Removal Critical Safety Function (CSF) using SG and ECCS, the operator task requires to verify main feedwater pump supplying feedwater.
There are no devices labeled as main feedwater pump flow.
Provide an "ONWFF" indication status for main feedwater pumps on main con-trol board.
224 During the Heat Removal Critical Safety Function CSF using SG Natural Circulation, the operator task requires the monitoring and verification that Loop 2A/2B T-Cold temperature is between 350 F and 565'F.
Instruments RCB-TI-112CB, RCC-TI-112CC, RCD-TI-112CD and RCA-TI-112CA have been provided in the control zoom to monitor Loop 2A/2B T-Cold, but have a range from 465-615'F.
This is insufficient to cover the lower range expected.
Recorder RCA-TR-122 is provided on control boards to display temperatures between 50'F and 750'F.
Additional in-vestigation prior to first refueling outage to determine if "delta T" meters on panel RMN-B04, on gSPDS and panel RMN-B02 in the control room are sufficient for operators to perform re-quired task.
~~~