TXX-4687, Forwards Response to Remaining SER Open Items for SPDS & Rev 2 to SAR for Spds.... Encl Will Enable NRC to Complete Review of Outstanding Issue 35 Re SPDS & Parameter Analysis (TMI Action Plan Item I.D.2)
| ML20137T260 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/07/1986 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Noonan V NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM) |
| Shared Package | |
| ML20137T263 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-TM TXX-4687, NUDOCS 8602180294 | |
| Download: ML20137T260 (6) | |
Text
Log # TXX-4687 File # 10010 919 TEXAS UTILITIES GENERATING COMPAhT SKYWAY TOWER e 400 NORTH OLIVE STREET. L.B. El e IDAll.AM, TEXAS 75208 February 7, 1986 52EUa'EY.10%
Director of Nuclear Reactor Regulation Attention:
Mr. Vince S. Noonan, Director Comanche Peak Project Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 TMI ACTION ITEM I.D.2 SAFETY PARAMETER DISPLAY SYSTEM Ref:
- 1) CPSES Supplemental Safety Evaluation Report No. 12 dateu October 1985.
- 2) Letter from J. W. Beck (TUGCO) to the Director of Nuclear Reactor Regulation with attachment, " Safety Parameter Display System for Comanche Peak Steam Electric Station Units 1 and 2 Emergency Response Facility Computer".
Dear Mr. Noonan:
Reference (1) provides an update to the staff's safety evaluation report relative to the Safety Parameter Display System (SPDS) at CPSES. contains the CPSES response to the three remaining open items for the SPDS. is the revision to the Safety Analysis Report for the SPDS, which was originally submitted per reference (2).
The enclosed attachments will enable the staff to complete its review of Outstanding Issue (35), " Safety parameter display system and parameter analysis (TMI Action Plan Item I.D.2)".
Very truly yours, 2100 h
p W. G. Counsil JCH/ arm Attachments c - Original + 40 copies gl Annette Vietti-Cook J/
I; n q
,,,- -,~nerax,,,m
-,cn,,,~r
P ATTACHMENT 1 1.
The staff finds the applicant's response to the NRC recommendation to add containment isolation valve status unacceptable - the applicant should add an indication of isolation valve status that allows a rapid assessment of containment integrity vis-a-vis isolation valve response (e.g., " Containment Isolation Phase A/B Complete / Incomplete").
The staff also recommends the addition of lower level, detailed information such as containment mimic showing isolation valves and their status (Supplement 1 to NUREG-0737, Sections 4.1.a, b, and f:
" concise display" and " continuous display" of critical plant variables suf-ficient to rapidly and reliably assess the safety status of the plant regarding " containment conditions" and " radioactivity control").
The present methods are not concise, continuous indications and are not displayed on the SPDS.
(Reference (1), p. 22-17)
Response
Texas Utilities will add to the SPDS top-level display message area, messages that will indicate to a system user the status (complete / incomplete) of Phase A Containment Isolation, Phase B Containment Isolation, and Containment Ventilation Isolation events.
These messages will be formatted as shown in Figure 1.
The event message area will be blank until isolation signals are received. Upon receipt of each isolation signal, the name of the signal will appear in the message area, along with the time and date of signal receipt, and an event marker number.
The marker number will be positioned near the top of each SPDS trend graph, "
time that corresponds to the time of signal receipt. The status of each isolation event will be indicated by an appropriate word that will appear immediately below the signal name.
If all of the valves associated with the signal are in their correct positions, the word will be " COMPLETE"; otherwise, the word will be " INCOMPLETE". This event status word will be updated every other second.
In addition, the system will include a !?wer-level display associated with each of these signals.
Upon requen, each of these displays will list relevant information about each valve that is not in its correct position.
This information will be formatted as shown in Figure 2.
This addition is scheduled to be implemented by July, 1986.
2.
The staff has found that the applicant appears to have deviated from a commitment to include main stack radiation as an SPDS parameter (Supplement i to NUREG-0737, Sections 4.1.a, b, and f).
This should be explained or corrected.
(Reference (1), p. 22-17)
Response
Texas Utilities will add main stack radiation indication to one of the SPDS trend graphs.
The parameter that will be trended is the sum of the wide-range gaseous monitor signals from the north and south plant vent stacks.
The format of this trend graph is shown in Figure 3, with the new parameter shown on the left.
In addition, the status of this parameter will be monitored through the " RAD MON" target on the Operation top-level display; if this parameter reaches its alarm limit, or if any of the other parameters monitored through the target reach their limits, the target color will change from green to yellow, to indicate an " alert" condition. This addition is sche-duled to be implemented by July, 1986. i
ATTACHMENT 1 3.
The applicant has not fully reviewed the implemented system against the functional requirements and design specifications and has not performed final dynamic validation testing to ensure that the system (person / machine) performs as specified and is usable under a wide range of events.
Response
Final site verification and validation (V & V) tests are currently scheduled to be performed in July of 1986, by a V & V contractor.
Texas Utilities will develop a dynamic testing program to address both the validation of the parameter set and human factors consideration.
This program will include validation methods similar to those used in the validation of the generic Safety Assessment System, and will be implemented during operator training on the CPSES simulator, before the first refueling outage.
' Figure 1.
New Event Message Area Format CSFM SUBCRITICALITY E CORE COOLING G
'i HEAT SINK
.i INTEGRITY
[]
i>
CONTAINMENT Q
N INVENTCRY o
I m
POlJER 5.0X105 CPS z
-i RUCT HI Tave 386 F SR SUR DPM
~
cvre s Y s i
p a u >< Tw P g.e ggo A Li;4E" CVf*HYSNTHTuS Event 4
- E E' 'Yc ' EIAIEEA" Message
- !" h?'
A24134E*
j Area
- VT.CA20teve
%N!Paa 2
i
- 57PeoMCLro A!LENA '
,5 r eHosc a ssou gggggo i
6 m s enanncvEm ranLunc I
COrtPU T CH THOuptg Cor1N TER ROOH t aAnti 26 SEP 85 17:04:39 CPES E i
E HERTUP/COOLDOlJN th!T E-
Figure 2.
Format of Isolacion Event Verification Displays (Phase A Containment Isolation Verification Display Shown)
PHRSE A CHTMT ISOLATIONIS TIME OF REQUEST: 29 flVG 85 08:33:34 ISOLRTION TIME OF SIGNAL: 29 flVG 85 07:55:23 INC0WLETE VERIFICATION i
DESCRIPTION POINT ID Tr'5 H0.
PROPER STflTUS ClRRENT STATUS l
i CNTNT INSTR RIR ISOL VLY Y97980 HY-3487 CLOSED OPEN HL 1 SMPL ISOL VLY Y9472D HV-4168 CLOSED UHKHOWN ACCUM 4 SMPL ISOL VLV Y94570 HV-4174 CLOSED OPEN 3
4R E
i 9
~
i i
l t
i i
1 i
3 POINTS 29 RUG 85 08:34:22 UIS
.'Cl HERTUP/COOLD0!JH udi E
1N 0
Figure 3.
Revised " RAD MON" Trend Graph (with " STACK" parameter trend)
CSFM SUBCRITICALITl l'
CORE COOLING HEAT SIHK INTEGRITY d
CCHTAINMENT c
9 INVENTORY i
M POWER 5.0X185 CPS i
AUCT HI Tave 386 F SR SUR DPM j
~
EVCHTS 1 RM TRIP 4
OG a SI eg sintu le SLDs es!GsCET HEL EVENTS /STRTUS g
-*r'
-'r'
-'d
=c,9j.O._.goggg;;3 gl
j
=
I';'.1*T'-
1241341*
.4
_ ire
...e 5"wc E*cTc EMM" 2'
E?*hoAE"c~Tc A2EE*EE'
[,,,
n
.r
-ira
- i.i
. _. 1=;,.
P -..
l a
seos n.=ancyc= rais.u-c
-ir+
-ir
-i COMPUTEN THOUDt.C coe9PUTCH ErOOrt hanRM l
26 T.P 8517:04:39 cpgs m 1b185 5 610Y 5 618-2 5 k132 CE EATUP/COOLDOWN LMT g gCVs gCVal gCVal pCVal TIME OF DAY o
-