ML20197C704
| ML20197C704 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/25/1986 |
| From: | William Ford SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20197C690 | List: |
| References | |
| 1008L, TAC-61631, NUDOCS 8611060363 | |
| Download: ML20197C704 (55) | |
Text
_ _ _ _ _ _ _ _ _ _
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DETERMINISTIC FAILURE CONSEQUENCES ANALYSIS (DFC)
FOR NON-NUCLEAR INSTRUMENTATION (NNI)
AND INTEGRATED CONTROL SYSTEM (ICS)
POWER SUPPLY FAILURES .
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Supplement 1 f
c-Loss of NNI X or Y/ICS ac power -
(Auto-Bus Transfer-ABI-Failure) *
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Prepared by:
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DURDOSY OF THE RfVIEW ' # ~ ~
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^ The effect due to loss of ac and dc power supplies to NNI/ICS instrumentation and. process control senemes were evaluated, cocumented and discussed in the original DFC report _ of July 25, 1986.
~
Nuclear Engineering management recuested a further review on the loss of a <
single auto-bus transf er ( ABT) for NNI X or Y and ICS ac power. .
This review focuses upon the effects on instrumentation and process controls as a result of an ABT failing to successfully transfer its at loacs from the normal 120 Vac source to the back up source.
SUMMARY
OF RESULTS
- 1. ICS (Loss of ac power)
As shown in electrical schematics N-21.01-65 and 66, ac power is provided by Vital Invertor 1C and backed up by Reactor Plant Bus 1J via an ABT. This ac power is rcuted to fuse panels for distribution to various .ICS loads. In addition, four hand controllers are powered directly (f used at the controller) . Blown fuse indication is provided for each fuse except those within the hand controllers.
1 ICS ac power is utilized to drive a series of steam and feedwater control valves in addition to modest number of process instruments.
None of these process instrumen'ts. are~ necessary for achieving hot er ,
cold shutdown conditions. The ' steam (TBV's & ADV's) and f eedwater (SU &
Main) are used to achieve het and colli shutcown wnen ICS ac power is available.
Loss of ac power to two of the four hand controllers can result in a plant trip.
Attachment 1 of this supplement provides the data sneets for loss of ICS ac power. Each device is identified with tne system or component it controls. Instruments ef fected are icentified as are f ailures tnat can lead directly to a plant trip.
Should de power be lost simultaneously with ac power there will De additional plant trip initations as oetailed in :ne original report.
Only a major change to the entire ICS control scheme will alter the ICS failure modes shown in Attachment 1. A series of modest control modifications have been initiated as a result of the original report.
These modifications coupled wfth EFIC will provide alternate controls for steam and feedwater, independent of ICS power.
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.8 Page 1 of 4 1008L
i 1
- 2. ICS (loss of NNI X or Y ac power)
The NNI provides 23 process inputs to the ICS. Each has failure modes l based on loss of ac and or dc power. In a numoer of cases this results in multiple failure modes. Details of these failure modes are shown in Attachment 2 Loss of X ac power and Attachment 3, Loss of Y ac power.
Of the 23 NNI process . inputs to the-ICS,11 can result in a plant trip on loss of NNI X or Y ac power.
The installation of EFIC will remove ICS control from AFW and ADV's. ,
This will eliminate the potential dry OTSG's events discussed in the original DFC report. EFIC wil1 also eliminate the auto start of AFW on each reactor trip as discussed in the-original report.
- 3. NNI (loss of X or Y ac power)
As shown in electrical schematics N15.07-57, 58, 59, and 60, X & Y ac power is provided by Vital Invertor 10 and backed up by Reactor Plant '
Bus 1J via an ABT. This ac power is routed to fuse panels for distribution to various loads. Blown fuse indication is provided for each fuse. Detail.s of failure modes associated with each fuse are shown in Attachments 2 and 3. ..
NNI ac power is utilized to driver a series of process systems sensing transmitters, indicators, recorsers and control valves. These devises
(( allow the operator to control and monitor such systems as RCS letdown and make up, RCP seal flows, pr,imary and secondary levels, pressures, temperatures and flows. .. -
') . -
The NNI provides 13 process inputs .to the SPDS that are directly impacted by loss of NNI X or Y ac power. Nine of these 13 are selet*able by the operator. All are subject to failures of NNI X or Y cc power failures as well. A modification is Deing developed to remove these SPDS inputs from NNI or ensure each monitored point is redunoant.
A series of SFAS indicators fail on loss of NNI X or Y ac power. These include HPI Flows, CFT levels and pressures, DHS flows and temperatures and NCW flows to reactor building cooling. In addition, a great many of the SFAS annunciators either are failed 21 or oefeated. The coerators ability to verify specific safegaurd act1ons can be inhibited by these failures.
Loss of NNI X ac power results in 49 process indicators and 11 trend recorders failing. Loss of NNI Y ac power results in 17 process indicators and three trend recorders failing. Valve positioners driven by these power sources may continue to operate but they will respond slowly to control signals. "
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. Page 2 of 4 1008L !
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Other than ICS, there are only three processe's directly controlled by NNI. These are:
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- P=r level (make up flow)
Loss of Xac - Pzr level driven to 160" Loss of Yac - Pzr level driven to 200" indicated,
- 270" actual .
-. *RCP seal supply -
Loss of Xac - Flow stablizes at 40 gom Loss of Yac - no effect
- Letdown Bypass Control Loss of Xac - no effect Loss of Yac - Fails to 50% open The failure modes themselves' are not that dramatic, particularly wnen compared with the impact on ICS driven processes. However, they do add to the operator challenge. The real problem lies in the operators .
in-ability to monitor the process systems with failed instruments (and to determine which instruments are good or bad).
METHODOLOGY The materials and support documenti developed for the original DFC report have been put on a computer in a mr~nner that permits a sort for a variety of failures or equipment identificatio,n, A sort was made for loss on NNI X, .Y and ICS ac power. A review of the '
individual NNI and ICS drawings was perfdrmed using each sort item 4
individually and all sort items collectively.
I The failure modes identified as a result of this review did not reveal any new information. It does leave the reviewer with ne coinion that plant
' response on loss of any one instrument or control ac bus is bounced by loss of any one de bus. The difference in the plant trauma will not likely be
- cetected by the operator.
RECOMMENDATIONS As stated in the original a report, loss of NNI or ICS ac power (ABT's fail to transfer) does inhibit plant operation, impact process instrumentation and will likely result in a plant trip.
Planned modifications to.the invertor complex that provides ac power to NNI/ICS will improve the reliability of these input power sources.
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There are no planned modifications to improve ABT reliability. The track
<n record at this station indicates current ABT reliability is cuite V satisfactory. The possibility of a ground fault downstream of the ABT but upstream of the fuse distribution panels could lead to f ailure of both ac power inputs to NNI X or Y or ICS. In this case, Oc power would also be lost and the previous report recomme'ndations address these failures. A modification is -being developed to trip the ICS de power on loss of NNI X or
- Y ac or dc. This will drive the plant to a known safe condition.
One of the problems identified in the original report will.be resolved by the installation of EFIC. This is problem #1, provide OTSG auto-level control independent of ICS power.
The remainder of the problems 2-17 address ac and de failures and encompass y loss of. X, Y or ICS ac power (see Attachment 4).
A review of the priorities established for correcting the identified problems is recommended.
ANALYSIS -
The following is a list of the supporting documents with a brief cescription of the content in each attachment.
l 1
Attachment 1 - Loss of ICS ac Poweg,I Provides a itsting by fuse pane'l and fuse number of each ac load on the ICS ABT. .
Briefly descfibes the failure mode for each device, .
identifies the.effe,;ted process and sunnarizes the l likelyhood of a plaht trip wnen applicaole. 1 Attachment 2 - Loss of X ac Power Provides a listing by fuse panels and fuse numoer of each at load on NNI X ABT.
Briefly describes the failure mode for each device, identifies tne effected process and summarized the likelyhood of a plant trip wnen a:plicatie.
Attachment 3 - Loss of Y at Power' Provides a listing by fuse panel and fuse numoer of each at load on NNI Y ABT.
Briefly describes the failure modes for each device, identifies the effected process and summarizes the likelyhood of a plant trip when applicable.
Attachment 4 - A copy of the recommendations from the original report.
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Page 4 of 4 1008L p **--e'--w-m
Plant Control and Indication NNI/ICS COMPUTER DISPLAYS CONTROL ROOM l l HlSS HlCO PARAMETER INDICATION SPD3 IDADS BAILEY 855 H4BS H2SD EPIC RECORDER OTSG A LEVEL NNI X XENNI NNI X EPIC X X OTSG B LEVEL NNI X XENNI NNI X EFIC X X OTSG A PRESS NNI NNI NNI NNI X EFIC X X OTSG B PRESS NNI NNI NNI NNI X EFIC X X AFW A FLOW X' AFW B FLOW X AFW PUMP P-318 X PRESSURE ,
AFW PUMP P-318 X PRESSURE ,
Tc LOOP A NNI X X&NNI NNI X X X Tc LOOP B NNI X X&NNI NNI X X X Th LOOP A NNI X X&NNI NNI X X X l
Th LOOP B NNI X X&NNI NNI X X X CPT A LEVEL NNI X XENNI NNI CFT B LEVEL NNI X X&NNI NNI CFT A PRESS NNI CFT B PRESS NNI MU TANK LEVEL NNI X (ENNI NNI X X X MU FLOW NNI X X LETDOWN FLOW NNI X XENNI NNI X HPI A FLOW X HPI B FLOW X DHS A FLOW NNI X X DHS B FLOW NNI X- X PZR. LEVEL NNI X X&NNI NNI X X X RCS A PRESS NNI X X X RCS B PRESS NNI X X X SOURCE RNG A X X SOURCE RNG B X X O
d X = Parameter is displayed in that system independent of NNI/ICS ICS or NNI = Parameter is displayed in that system subject to NNI or ICS failure Attachment 1.1j-1 Page 1 of 3 ATTilJ1(C)
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Plant Control and Indication
[ NNI/ICS COMPUTER DISPLAYS CONTROL ROOM l HISS HlCO l
PARAMETER INDICATION SPDS IDADS BAILEY 855 H4BS H2SD EFIC RECORDER PZR TEMP. NNI NNI NNI :
RCS A FLOW NNI RCS B FLOW NNI RCS A dT NNI NNI NNI RCS B dT NNI NNI NNI ,
UNIT Tave NNI LOOP A Tave NNI LOOP B Tave NNI RCS PRESSURE NNI NNI l
l (LOW RANGE)
RCP SEAL NNI NNI NNI PRESSURE MU TANK NNI PRESSURE ,
MU PRESSURE NNI LETDOWN TEMP ~ NNI DH A TEMP NNI .
DH B TEMP NNI FW VLV A dP NNI NNI NNI FW VLV B dP NNI NNI NNI MFW A FLOW NNI/ICS NNI NNI NNI MFW B FLOW NNI/ICS NNI NNI NNI SUFW A FLOW NNI NNI NNI SUFW B FLOW NNI NNI NNI PRT TEMP NNI PRT PRESS NNI NEUTRON ERROR ICS GENERATOR FREQ ICS X X INCORE T/C RCP SEAL FLOW X X MU FILTER dP NNI X SEC STM TEMP A NNI NNI NNI X -
SEC STM TEMP B NNI NNI NNI X X = Parameter is displayed in that system independent of NNI/ICS ICS Or NNI = Parameter is displayed in that system subject to NNI or ICS failure Attachment 1.14-1 Page 2 of 3 g v- , ,9 .r - -- = ----.wT - - - _ p at-
i Plant Control and Indication f.-
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NNI/ICS ALTERNATE CONTROLLED CONTROL ROOM CONTROL ROOM l PARAMETER CONTROL H2SD CONTROL AFW LOOP A EPIC EFIC AFW LOOP B EPIC EFIC ADV LOOP A EFIC EFIC ADV LOOP B EFIC EFIC PZR HEATERS X RCP SEAL INJECT X LETDOWN FLOW X PZR SPRAY X PORV X MU FLOW X TBV LOOP A X , X X TBV LOOP B X X X
[ MW LTP A X MFW LOOP B X SUFW LOOP A X SUFW LOOP B X FW PUMP TURBINE A 3 FW PUMP TURBINE B X AUX. STM REDUCING X GENERATOR PULSER X ROD CONTROL X a
1 er X = Parameter is displayed in that system independent of NNI/ICS ICS or NNI = Parameter is displayed in that system subject to NNI or ICS failure ATTilJ1(C)
Attachment 1.1j-1 Page 3 of 3 i
l
SACRAMENTO MUNICIPAL UTILITY DISTRICT
/' OFFICE MEMORANDUM 1
h -
To. L. Conklin DATE: October 13, 1896 FRou: S. Carmichael 1 0
SUBJECT:
PARALLEL POWER SUPPLY MONITORS l
In January 1986 three Bailey 820 Power Supply Monitor (PSM) modules were set up in the test stand located in the I&C Maintenance Shop. Each PSM module was calibrated using the Bailey Instruction Manual E92-81 prior to installation of all three PSM's. The modules were adjusted such that the setpoints were within about five millivolts of each other. When installed in the test stand the PSM's were connected in parallel to the same power supplies (+24 VDC & -24 VOC). Each power supply was then varied to test either the Pos bus o~ Neg bus setpoints ( 22.5 VDC). When the voltage level was reduced to just above the setpoint for the bus trip, a PSM tripped as indicated by a DVM set to measure resistance across the trip relay contacts. Decreasing ,
l the voltage further (still above the setpoint) a second PSM tripped and the
.first PSM reset. Contincing to reduce the voltage the first and third PSM tripped and the second PSM reset. When the setpoint voltage was
. finally reached the second PSM tripped and the other two PSM's did not reset.
Repeating this test resulted in the same results but with different variation of tripping and resetting. When a small series resistance was introduced between the PSM modules and the Power Supplies the same interaction betwe'en the PSM on decreasing voltage occurred. The only difference was that th'e interaction started at a higher voltage level with all PSM tripping finally above the setpoint. With approximately three ohms of resistance the PSM interaction would start about a half volt ( 23.5 VDC) below the normal bus voltage ( 24 VDC), and would end anywhere between that level and the setpoint level ( 22.5 VEC). No consistency was noted in which PSM tripped first o-last, nor was any set interaction between PSM's except random.
cc: J. Irwin -
L. Fossum .
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Page No. 2 09/27/B6
' ICS INSTRUMENTATION OR CONTROL WHICH IS FUNCT!DNAL ON LDSS OF ICS AC POWER DNLY l INSTRUMENT LOCATION DESCRIPTION FAILURE MODE REACTOR TRIP DRAWIN6 NO. EFFECT NUMBER REEEEEEEEEEEE EEEEEEEEEE EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE BEEEEEEEEEEEEEEE d
$ SP-F LOOP A MFW FLOW FAILS TO 501 LOW PRESSURE TRIP LIKELY N21.01-77 E
@ SP-6 LOOP B MFW FLOW FAILS TO 501 LOW PRESSURE TRIP LIKELY N21.01-77 e
.~ SP-H. LOOP A SU FLOW NO EFFECT PRE OR POST TRIP ACCEPTABLE FAILURE MODE N21.01-77 Y
~SP-J LOOP B SU FLOW , NO EFFECT PRE OR POST TRIP ACCEPABLE FAILURE MODE N21.01-77 i
SP-R LOOP A FW VALVE DELTA P FAILS TO 501 H16H PRESSURE TRIP LIKELY N21.01-B1 SP-S LOOP B FW VALVE DELTA P FAILS TO 501 HIGH PRESSURE TRIP LIKELY N21.01-B1 SP-D LOOP A FW TEMP FAILS TO 50% HIGH PRESSURE TRIP LIKELY (BTU) N21.01-77 SP-E LOOP B FW TEMP FAILS TO 501 HIGH PRESSURE TRIP LIKELY (BTU) N21.01-77 l
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i Attachment 1.3-4
e -u i
IDADS consists of a central conputer system located in the Co p er Room. It has various types of input nultiplexing equipt, display- 1 terminals and hardeepy equipment in the Control room, TSC, and EOF, '
c and display ecuipt at the assently points. Plant inputs enter the
( system f rom the follcaing sources: the Bailey Multiplexer, the MODCOE Riltiplexer, and the Anatec Remote Multiplexer (REMUX) system.
W e following general features are to be provided:
A. Data Acquisition B. Man-Machine Interface C. Alarm Annunciation D. Radioactive Release Monitoring E. Reactivity Calculations -
F. On-Line Trending G. Data Link to EOF
. A data link with the GA Technologies' DFS Conputer so that .
radiation data will be available on IDADS.
. A long term history storage and retrieval option for later interrogation of data.
. Calculated values using predefined equations which can be alarmed or trended.
C. DRMS -
We District contracted with GA 'DK:hnologies (GA) to design and deliver a Digital Radiation Monitoring System (DPS) to meet the appropriate requirements of NUREG 0737. We DRMS provides on-line information concerning radiation levels of selected radioisotopic concentrations within the plant processes and dose rate information for various areas within the plant facility. Process measurements provide diagnostic or status information for a particular portion of the plant operation, and monitor releases of radioactive material from the plant environment.
DRMS consists of subsystem elements. including:
. RM-ll central control and display system
. Gaseous process monitors
. . Liquid process monitors
. Wide range gas monitor (WRGM) control cabinet
. Strip chart recorders .
. RM-23 portable control and display units
. High range In Containment area monitors
. Main steam line radiation monitors Attachment 6.la-1 Page 1 of 2 -
_ . _ . _ . ~ . . . - _ _ . _ . _ _ - _ - - _ _ _ . . . _ _ . . _ _-
% RM-ll coup:ter commicates with all the conitors using thrre loops of redundant commications lines. Com:nications between each nonitor and the RM-23 : nodule are accomplished over a single dedicated
, f.- line separate from the RM-ll loops.
':he DBMS design incorporates the following features:
. Distributed data processing.
. Expansion capability
. Centralization of control and display -
. Redundancy and reliability
. Independence of safety related nonitors
- . n ending I
w Attach:: tent 6.la-1
- Page 2 of 2
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- sta se* 52* 520 INADEQUATE CORE COOLING (ICC) DISPLAY
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RIR 35-573 Cacameer 30, 1985 . j 1
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DIRECTOR. OF NUCLEAR REAcr0R REGULATION , ,,
ATTM HUGH L THCMPSC.4 JR ,
DIVISION OF LICENSING '
U S NUCLEAR REGULATORY CCmI53ICM l WASHINGTON OC 20555 -
1
-l OCCXET 50-311 RANCHO SECO NUCLEAR GENERATING STATION UNIT NQ. L 1 NUREG 0737 LTE!T II.F.1 INADECUATE CORE COOLING (ICC) 1
,p Ey letter datatt April 15, 1983, the District proposed. ICC instrumentation to i satisfy your order For Modification af License for Rancho Seca Nuclear .
- Generatirq Station, datsii Decanhar.10,1981. On June 28, 1984, the District
. respornieci ter your Request for Additionalttformation, datati August 14, 1981.
rrr these submittals, the Utstrict bientified a. heatest junctiort ther9accouple systear (HITC3) as the preferreci method For reactor vessel coolant inventarf-tesruiinct. A- differential pressure (DP) systear was identified as an option.
Due to the recent availability of qualified higher accuracy transmittars and procursment difficulties uitfr the H2TCE, the District has reevaluated the '
options anci decided ts pursue the DP systeare The attachment to thir letter provides a design descriptiert for the proposed reactor coolant inventarf trackirs systes (RITS). This information supersedes the reactor vesset level seasurement systes description provided by the District'r. April .t5,198I anti June 2E,1984 submittals. The previous descriptions of the balance of the ICC instrumentation, including hot . leg level, are still valid.
i ArrACEMENI 6.id-Z Y
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Page L of 6
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. _ , - - - . - - -.-- - ~-----.--.-.,- - . - .-.-. -- _-....--. .
g'_g,gg ,3 3 Attrchment 6.id-2 Hugh L. Thomcson. Jr. 0: camber 30, 1985 1,5%
.' tu Oistrict . 2., sins car.:nittaci to install the balanca of ths 25 instrumentation ' curing tne Cycle 8 refueling outage, as releeracec in our lattar of Sectambar 30, 1985.
I? you have any questions concerning. the above, please contact Robert Little at (916) 731-602I..
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-\~n, R . I. R RIGUEk ~
ASSISTANT GENERAL MANAGER, NUCLEAR Attachmene bc: D. K. K. Lowe R. I. Rodriguer R. F. Cubra' . L. It'. Keilmart R. A. Dietarich V. C Lawis (2)
G. 4. Cbwarti 2. E Ct Iceba (2)
'< L. G. Schwieger- (2) G.,CT,.4T.ini. (MS 39)
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Syd: Miner- (NatC, Bethesda) I. Eckhartit (NRC, Itanch)
F. G. Delazonski. Fourtle Floor- Files Eng. Filas-Plaza 50 , Licensinq 711es (MS 32)
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V ATTACHMENT 6.ld-2 l
Page 2 of 6 f .
CHECK SHEET Attachment 6.id-2 Lat:er No: k b ~ b 7(E Final Agency Due Date: e #-
%sconsibie 7 Date Submitted to / l 4 .%
dcividual: k
- b ITbC . Ucansing/NCRC: /E /8Y equiatorv Agency: N'D NN
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Summary: YM h I f"/2.tc T Ff 8 Al%4.Wt t NG TNiE NIU__ THAT- IT
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Commitments in tnis letter: MO MEtc t C8MW MM EM m
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Commitment Assigned to: Due Cate:
L Commitment Numcer:
Pfnal1.atter Concurrence with Dates: tJoensingtNORC Reconi Summary:
r2 [Io[87 Cisociine Suoervisor- -
/ TMf' MR.C. CW.tlAA 4
sPrincipal Project Engineer: /- - - -=
iNf/r IT II h"1lL To Dir.$stbapuT 4 [ly/g Operations: 47 /T/f7/ I ' R Q.C.' 7 AT. & [M [a?
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UsensingsNORC C . ;1_ .:: Claseeut S_ ...._. 7 J',orrosoondence Signed By: d IN th Date: I- 90 riginal & CC Olstnbuted By: I E D Date: ME '
SCC Oletributed: bfN Date: / N
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6.1d-2
! mues m / Page 3 of 6
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At-acnment Attachment 6.1d-2 REACTOR COCLA,77 D;VOTORY T9ENDING SYSTEM
~
j
,. .. .. l brha reactor coolane invencory cracxing system (RITS) is designed to prcvido unambiguous indication of reactor coolant inventory trending. The RITS wtil with the reactor coolant pumps (RCFs) provide inventory either running or tripoec. trencing indicationTha system is being designed to meet the intant of NUREG 0737 Item II.F.2.
The RITS measures three parameters for reactor coolant inventory trending determination: :
. differential pressura (DP) across the vertical,run of the. hot legs (hot ..
lag level);
. - OP across the upper region reactor vessel (RV level); arxi
. RCP motor power.
Hot Lee Level Measurement The hot Iag Iavel portion of the RITS is described in the Dist-ict's submittals of April 15, 1983' arxi June- 28', 1984 RV Level Measurement ;
The W 1evel measurement provides an indication of reactor coolant inventory
. trending wherr the.RCPs are not operating.- \
7-
' h RV Ievel measurement ranges from the top of the reactor vessel (RV) head to the center of the coM leg. The desigw includes the removal of the central i control drive mechanism to: provide a F . 6-O-ion in the RV head for locatiorr .
of the top RV pressure tap The existing.. tan ort the Loop A cold Iag .
(discharge of RCP F-2108) will be used as a lower pressure tag. Use of the cxisting ccM leg tan provides the following benefits:
- eliminatierr of single failure concerns relative- to use of the tap on decay heat drop line common with the hot leg DP transmitters; and ,
I
- lower personnel exposure over installing a new hot Ieg tag.
1 Wo OP transmitters (one per channel) will be usei to provide redundancy.
Eactr transmitter will be powerai independently by- Class L instrumentatiort l power. The DP transmitters will be located- inside containment and will be qualifici to withstand the normal, abnormal, and post accident conditions, in accordance wittr the District's environmental qualification progree. The DP .
transmitters will be qualified to. withstand the overpressure conditions '
imposed on the diaphrage of the transmitters when the RCPs are running and will be fully recoverable when the RCPs are stopped. The transmitters will be
~ installai in an insulated enclosure to protect them frosit temperature
~
transients during design basis events and to improve their performance.
. ATTACEMENT 6.1d-2
'O '
Page 4 of 6
.h - -
Attachment 6.Id-2 Tha design includes density comosnsacion for- level measurements due to tamparatum effaces on process liquid density. Density compensation cn the ference legs (vertical runs) is not required because the sensing lines will
' insulatsc with 1" thick insulation to maintain the temperature of the
.aference legs mlatively constant. The maximum temoe'rature rise of the l rafaranca lags is anticipatad to ha 10*F .abcVe normal containmene abnospneric temperature (120*F) when subjected to the temperature transients cur:..g a design basis event.
Th3 output of the transmitters will be connected to the Class 1 tultiplexer i system for the level indications on the safety parameter display systam (SPOS) and the interim data acquisition and display system (ICA05) CRTs. Isolation e
for IDA05 is provided in the multiplexers. IDA05 is the primarf display 4
system for ICC and has trend recording capability showing the level-time . .
historf of representative RV level readings.
j Primary (IDADS) and ' backup (SPDS) display channels are electrically-
' independent. IDA05 is pcwared from battsrf backed Class I got er source and SPOS will be powered from a Clasr L power source. SPOE modifications will be implemented per the Living Schedula arxi in accordanca with Reg. Guide 1.97 and ,
CROR reccmmendations.
a sketch of the RV level portiert of the RITS. is shown in Figure L. ,
RCP Motor Power RCP motor power and pump inlet temperature measurements'will be used by the GE to trend the reactor coolant void: fractiort wherr one, or more, of the RCPT h RCP *9*tl5I' _ _ -l power seasurement requires the.. usa of 3rphase Watt-transducers (Class I),
j one for each RCP, te provide arr analog signal proportionaf to RCP actor power. Watt-transducers will use existing Class I current and potential transformer signals and will be self prn.M. The transducers will be high quality commercial grade components armi will be installed in the same-environment as the existing S.9kV switchgear supplying power to RCPs.
The output from the transducers will be Fed inta Class I multiplexers located irr the same switchgear room. The Watt-transducars.' signals will be processed i in IDA05 (Primary display) to provide percent void indication for each pump via CRT orr demarxi. IDA05 alsa has trend capability armi recording capability on. demarxi. Since IDADE tr powered Fros a. battery backed Class I power sourca and the RCP' motort are poweredi from a Clast I power source, the percent void indicatiort will be available on IDA03 CRT whenever the RCPs are running. ,
ATTACHMENT 6.1d-Z I
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ATTACENENT 6.1d-2 FIGURE I
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Page 6'of 6
/ . __ _ _ . _ _ - _ _ _
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ACTION ITEM CLOSURE REPORT
~
Action List Item' Number 3.f.7 Action List' Description evaluate ICS trouble annunciator and NNI Quarantined Equipment List Item Number N/A Responsibility of v. Lewis ,
Prepared By M. Ross Date 3-11-86 .
A. Description of Issue / Concern:
During the review of the 12/26/85 trip sequence, a concern wa raised regarding the possibility that the combination of ICS power failure and cabinet fan failure in one annunciator window could mislead the operator or extend the time taken to respond Hence r an evaluation of ICS trouble-annunciation was requested. Due to the- similaritT of ICS and NNI, the request foe evaluation was_ broadened to include the NNI annunciation.
B. Investigations Done:
A review of the annunciator windows identified the following 6 windows are associated with ICS and. NNI powerr 13 m2,SA 5
- n2 5.
mv ,.
Window 651 NNI I ,
hiindots $23 ICS or NNI PWR Failure 12G volt Power Transfer Window $63 NNI oc Fan Window F34 ICS I PWR ruse Failure Failure Windoe $64 NNI/ Fan Window 964 ICS or r PWR Fan Power Failure Failure In addition to the windows the following drawings were reviewed to determine the actuating devices of the above window and the annunciator procedures were reviewed for operator response.
I N15.07-57 & -58: Schematic Diagram - NNI E 118 VAC Power Distribution i N15.07-59 & -40: Schematic Diagram - NNI Y Power Distribution N15.07-81: Schematic
- Diagram - NNI I Power Distribution Schematic Diagram - ICS Power Distribution N21.01-45 & -46:
Annunciator Procedures: 52PSA Rev 14 l
- 52PSB Rev 13 & 14 a }
/
l Pege 1 of 4 jb/
' ATTACHMENT 6.2a-I f
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_. _ _ _ _ - _ _ _ _ _ _ , _ . . _ _ _ - --.__ _ ___ _ ___..__..__,__-___~m, _ , _ . . . , _ . . . _ , _ . _ . . . . _ . _ _ _ - , _ , - , . ._. _
i C. Conclusions / Explanation (should include Root Cause): -
The purpose of the annunciator system is to alert the operator of abnormal conditions. This annunciation should be consistent not only with the .
consequences of the alarm condition but also with the necessary operator response.
ICS:
The review of the drawings and windows confirmed the windows which combine power failure and fan failure will. alarm should any associated cabinet fan fail or should the power monitor sense powee failure.
Annunciator window E2PSB-34 will be redefined as "ICS TROUBLE
- and will alarm on any of the following conditions:
- 1. Any fuse blown in. the ICS system
- 2. Any cabinet fan failure in the ICS system .
- 3. Any power supply failure within the ICS system ,
Annunciator window E2PSB-64 will be redefined as 'ICS SYSTEM FAILURE *.
mis window- will alars orr the loss, of the +- or - 24. VDC power busses only. Morefore on a total loss of ICS DC power, the control roo.m will have a definitive alarm alerting the operator to the condition. On a less severe condition, such as fan failure oc blown fuse, the ICS trouble window will alert.the operator. Im addition, indic'a ting lights will be installed on the ICS cabinets that:will indicate a loss of any ICS power
- j supply. ~
AC faults withirt the ICS systes arer annunciated as follows:
- 1. Foe a fault downstrear of a' fuse,. the 'ICS Ttouble* alarm will actuate on the blown fuse.
- 2. Foe a fault between the ABT and the fuses, the normal supplT breaker IC07 will tripe the ABT will transfee to the alternate supply and breakee IJ04. will also trip causing a total loss of power to the ICS system. The E2PSB-34 'ICS Trouble *, E2PSB-64 'ICS SYSTEN FAILURE *,
E2PSB-23 *ICS OR NNI 120 VOLT POWER TRANSFER *, 52ES-49 ' VITAL PWR BUS LC TROUBLR* and H2ES-83 "NON-VITAL PWR BUS lE/lF/lJ TROUBLE
- will all alatz on this conditiorr.
- 3. For a fault upstream of the AST on the normal supply, breakee 1C07 will trip and the ABT will transfer to the alternate supply. Se j E2PSB-34 'ICS T200BLR*, 52PSB-23 "ICS or NNI 120 VOLT POWER TRANSFER
- will all alarm on this condition. For a fault upstream of the ABT on the alternate supply, breaker lJ04 will trip. The E2PSB-34 "ICS TROUBLE
- and H2ES-83
'NON-VITE PWR BUS lE/1F/lJ'. TROUBLE
- will alarm on this condition.
Page I of 4 S. ATIACHMENT 6.2a -l s ;
o ny w , .
l
i f NNI:
N Since NNI is similar to ICS but with three (3) distinct DC power
> distribution systems three (3) annunciator windows will be used to alarm a loss of a + or - 24 VDC power bus: .
- 1. E2PSA-52 "NNI I FAILURE
- alarms on a loss of -Z 24 VDC power bus -
- 2. 52PSA-63 "NNI X FAILURE
- alarms on a loss of +1 or -124 7DC power busses
- 3. 52PSA-64 "NNI Y FAILURE
- alarms on a loss of +Y or -Y 24 VDC power busses .
Annunciator window E2PSA-32 will be established as 'NNI TROUBLE
- and will ~
alarm on any of the following conditionar j l. Any fuse blown in the NNI system .
- 2. Any cabinet fan failure in the NNI system
- 3. Any' power supply failure within the NNI system Therefore on the loss of any NNI DC power distribution system, the control room will have a definitive alarm alerting the operatoe as to which system l
is lost so that the appropriate action can be taken. On a'less severe
{
condition, such as fan failure or blown fuse, the NNI trouble window will I alect the operator.
! AC faults within the NEI system are annnneinted as followse
. n; *
- 1. fee a fault downstream of anyCfuse withis the NNI system, the E2PSE-32 "WNI TROUBLE
- ala'rur wiLL actuate om a blown fuse.
- 2. Foe a fault between the Arrand the fuses within the I power distribution system, the normal supply breakee 1D07 will trip, the ABT will transfer to the alternate supply and breaker lJ08 will also l
l trip, causing a total loss of I powee to the NNI system. The j
E2PSA-Il *NNI TROUBLE *, E2PSA-61 "NNI I FAILURE *, H2PSB-23 *ICS OR NNI 120 VOLT POWER TRANSFER *, H2ES-66 *7 ITAL POWER SUS 1D TROUBLE
- will all alarm on -
, this condition.
- 3. Foe a fault between the ABT and the fuses within the r and I' power distribution systems, the normal supply breaker ID01 will trip, the Aar will transfee ta the alternate supply and breaker IJ06 will also l
trip causing a total loss of I and I powee to the NNI system. The E2PSA-31 *NNI TROUBLE *, 52PSA-64 *NMI T FAILURE *, 52PSA-52 *NNI 1 PAILURE*r 52PSB-13 *ICS OR NNI 120 VOLT POWER TRANSFER *, 52ES-66 I " VITAL POWER BUS 1D. TROUBLE
- will all alarm on this condition.
- 4. For a fault upstream of the ABT in the z power distribution on the normal supply, breaker 1D07 will trip and the ABT will transfer to the alternate supply. The E2PSA-31 *NNI TROUBLE *, B2PSB-23 *ICS OR NNI 120 VOLT POWER TRANSFER
- and 52ES-46 " VITAL ' POWER 8051D TROUBLE"
- e. will alarm on this condition. For.a fault on the alternate supply, breaker 1J08 will trip. The 32PSA-31 "NNI TROUBLE
- will alarm.
ATTACHMENT 6.2a -I Page 3 of 4 i ll ._
l ---
- 5. For a fault upstream of the ABT in the Y and Z power distribution on i the nocmal supply, breaker 1D01 will trip and the AST will transfer to the alternate supply. The H2PSA-31 "NNI TROUBLE", H2PSB-23 "ICS OR NNI 120 VOLT POWER TRANSFER" and H2ES-66 " VITAL POWER BUS 1D TROUBLE
- will alarm on thir coridition. For a fault on the alternate supply, breaker 1J06 will trip. The 82PSA-32 "NNI TROUBLE" and .
H2ES-83 'NON-VITAL PWR SUS lE/IP/lJ TROUBLE
- will alarm.
D. Shoct-teen Followup Required / Recommendations:
- 1. Befoce stactup insure annunciator procedures for the above windows ,
provide correct operator direction. .
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- 2. Issue ECN R-0517 and R-0580 to incorporate the above changes.
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- 3. A determination of the scope of inconsistencies in annunciator 4 procedure should be completed prior to startup (refer to F). The Annunciator Study has accumulated data. which may aid in this determination.
E. Long-term Recommendationer For ther long tocar the annunciator study (Pre-mod 8522) .is reviewing the ,
i entire annunciator system.
, F. Programmatic Implications: ,
J
$ In review of the annunciator procedures, inconsistencies were found,
- Those related to these specifici windows should be corrected prior to startup pec U.l. Determination.of othee problemar outside the areas
< addressed, by this closure repoet 'should-be completed. prior to startup per
- D.3.
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i Reviewed and Accepted Date Action List Coordinator - SMUD i
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ATTACBMENT 6.2a -l Page 4 of 4 i
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SACRAMENTO MUNICIPAI. UTII.ITY DISTRIC oftRCE MEMORANOUM
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cATE: 7 9bruary 7, 1986 To: Distribution NOM 86-92 -
mou: Dan Whitney ,
0ECEMBER 26, 1985 TRANSIENT CLOSURE REPnar, rToe 1.o -t SUSJact Attached is a copy of SPOS vs. Stric Char- for GTSG Ocerate Level for your information, reference, and imolementation.
Distribution: .l,, ;
J. Fleid F. Turner J. McColiigan B. Ford M. WomeTdorf ,. 3, gg7p-
- 5. Redeker ,fs, g R. Cctiombo G. Simmons 3 R. Wichert
- 8. Spencer I . b R. Dieteric!t N. Brock G. Pagtzurr if. Heckert
- I hi S Crunk J. Jonesr .
V. Lawfs M. Frice -
F. KeTTie Control Room Trip Report #7E T. Huntar J. Jewet: J. Shetler S. Luke F. Thompsort l
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At N'W m T 6.2d-l Page L of 13 i d
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. I SACRAMENTO MUNICIPAL UTILITY DISTRICT s) opmcE MEMORANDUM g
DATn: Feoruary 7, 1986 To: ?!oC 7.esicent. Inscec:ce NOM S6-91 FROM: Uan " Whitney susaac1! - TRANSMITTAL GF REQUESTED ITEGRMATICN, ACTION. LIST ITEM 1.o _
The attacned Decemoer 26, 1985 avent related Closure Repari on SPOS vs. Stria Chart for OTSG Ocerate Lvi., Action List Item i.o , is provicea as requestec.
It is our understanding :nat you f!! "cr. arc :nts cateria! -
ta the NRC IIT Team for their information ana use. Should yca have questions regarcing :Mir material, do not hesitate
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- c:ntact us.
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Attachment:
NRC (3 copies) .* 1, ..
9
- cc: G. A. Coward w/o attachments .
l (h/,{' \
I 5. Redeker w/o attachments (* * ;
J Y. McCoTifgan w/o attachments 'N J. Delezenskt w/o attachments.- i f,u,t g
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ArrACEMENT 6.2d-1 -
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Page 2 Of 13 I -
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LCT!O!! :TCit OLOS"RE REPORT
, _ ACTION LIST :T;: ::L*:'2E2 '
ACTION LIST DESCRIPTION SPOS vs STRfD CHART FOR OTSG OPERATE t.EVEL QUARANTINED EQUIPMENT LIST ITEM NUMBER N/A RESPONSIBILITY OF J. FTELO uv i PREPARED BY Tim t.ovett GATE: 1-28-86 .
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A. '0ESCRIPTION OF ISSUE / CONCERN: ,
The STA and several Contro1 Room Operators during the 12-26-85 transient reported that SPOS OTSG operate levels were not observed to increase >97% on A and. >93% on S. The Control Room strip. chart recorder indicated that OTSG operate range Tevel was off-scale higtr for a. period of 30 to 40 minutes. The IDA05 points which monitor OT'*G start-un range level and Full range levei indicate that actual steam generator level was high enouqtr such that all '
operate range level instruments shonid have read *off scale hign.*
- 5. INVESTIGATIONS 00NE:
T. Review of oorsonnel statements and interviews.
O L
( The personnel statements included in . Trip Report #75 were reviewed for references to a discrepancy between the QTSE operate range level as
(' indicated by SPOS versus the level indicated. by the Control Room level recorder. The STA stated that he 'never saw SPOS OTSG operate levels increase >97% on A and >93% on- 8.* The Control Room Operator stated that "Throughout the' transient, SPOS was ver/ helpfui...," and the Senior Control Rocar Operator stated that *0TSGs. indicated full on SPOS....* In later interviews the Shift Supervisor and several Oprators. noted that the maximum level of GTSGs indicated on SPOS had been Jess than 100%. .
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XETACBMDrf 6.2d-l Page 3 of 13
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INVESTIGATIONS 00NE (Continued)
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- 2. System Oescriotion i Each steam generator i: acut;i; sed aith esc 0;;arsta range level instruments. The A-0TSG 1evel is measured by LT-20503A and LT-205038.
l The signal from LT-20503A goes to IDA03 and 3705 as an uncompensated
' level indication, and also to a 9aiT9y temeerature compensation device, LY-20503A, which also receives a temperature proportional signal from TY-20503A. The uncompensated signal is monitored and logged by IDA05 as computer point L9803. The signal to the SPOS is internally compensated ;
l by the SPOS, and the temoerature compensated operate range level is displayed. The signal from LT-205038 goes to IDADS(uncompensated level,. ~~~
l
.- L1804) and to another temoerature compensation de.vhe, LY-205033, but-not to SPOS. The two signals wnich have been compensated by the Bailey devices go to hand switch MS-20503A, in the Control; Room. When tne hand switch is in position 1, as it probably was during the 12-26-85 transient, the compensated signal from LT-20503A goes to the ICS and the Control Roost level recorder,. LR-20503. The other compensated signal, froar LT-205038, goes to the Bailey computer, where it is logged as point,. nummer LO37. This means that if the hand switch is. in position 1, the signar to the Control Rooar level recorder LA-20503 and the signal to the SP05. Tevel indication both originated in the same level transsitter, LT-20503A. The only difforence in the final 11gnal, iF the hand switch is in position 1, is the temperature compensation, whictr in the case of the level recorder is accomplished in TY-20503A, and in the ~~
J case of the SPOS is accompi.tshed internally by the SPOS. If the hand switchr is in position Z, thei signat displayed by the Control Room levei
! recorder wiiT be the signaT-which originatad in LT-205038, and was compensated by LY-205038. LThe SEDS' input would not be changed.
The arrangement on. the B' QTSE is. simi'lar, with the exception of the hand l
switelt position, which must be in position Z in order for the same level l
transmitter (LT-20504 8) to supply the signal to the Control Room level i recorder and the SP05.
i The twa control rocar hand switches. H5-20503A and H5-20504A, are ,
! generally selected tar the number 1 position. During the Weekly Instrumentation Surveillance, SP 200.03, both transmitters are read and recorded, but there is no record of the initial or final hand switch l
position. The operators generally take a reading with hand switch position at number T, then switc!* ta number Z position and take a l
reading., thent 'switett back to number T position,. but this is not
! controlled.
A schematic diagram of GTSG operate range level instruments is included -
l I as an attachment.
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'ATTACEMEttr 6.2d-1 l
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INVESTIGATIONS 00NE (continuec)
V 3. Check of Adequaev of Temaerature Comoensation Algorithm Internal to SPOS A review of tne values Of unc mpensated OTSG operate range levels for the period of time following the Reactor Trip on 12-26-85, when OTSG operate range levels were correctly indicated as 100% by the contro; room Tevel recorders, shows good agreement between the two trsnsmiMers on each OTSG. The uncompensated output from LT-20503A and LT-205038, tne two transmitters on A GTSG, which are recorded as computer ooints L9803 and LT804 respectively, never differ by more than 1.51 and typically by .
about 15.- The two transmitters on B OTSG, LT-20504A and LT-205048.
recorded as computer points L1803 and L9804 respec.tively, typically *,
differ by about 0.7" In the worst case, with HS-20503A salacted ts position 2 this difference- in transmitter output could.. explain no more than 1.5% or, one half of the reportaa difference between ene A-0TSG .
Tevel recorder and the A-0TSG SPOS display. The transmitter outputs on the E QTSG are too close to exnlain any significant portion of the '
reported 7% difference between the level recorder and. the SPOS display, regardiess- of hand switch HS-20504A cosition. The Temperature -
Compensatiorr System was seen as a: possible cause of the difference, since the signal supplied. to the level recorder and the SPOS display was essentially- the same prior en temperature compensation.
Page 4 of Appendix 1, of the SMUE Safety Parameter 01 splay functional l descrtation (attached) states that "ali displays that use OTSG operating Tevei shall be density compensated... where:
.7 Output. = C* INPUT = Compensated GTSE Tevet in 5 Input is in counts (819-4095) foc QTSE level C = AT+A2*(OTSG PRES)
- A3*(OTSE PRES)2
+A4(GTSE PRES)3
- AS*(OTSG PRES)'
+A6*(GTSE PRES)i AT = T.039529Z l AZ = Z.3131582E-04 .
. A3' = -T.5208028E-07 A4 = 6.9245419E-11 A5 = -1.5142765E-14 A6 = T.2623188E-18
- l QTSG Tevel is in 5, QTSE PRES is in psig. ;
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ArrACHMENT 6.2d-l Page 5 of 13
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I INVESTIGATIONS 00NE (Contiaued)
As a means of evaluating the adequacy of t' sis compensation algorithm, an l
exercise was performed in which an actual liouid level was assumed to
/ exist in the downcomer ano tne tuce ouno ee. at an elevation of 277.4 inches above the lower tap. Ws wmsponds to 95% of the 292 inch range. The pressure exerted' by a column of saturated water, 277.4 inches high, was calculated For a range of temperature and pressure 4
' combinations. That oressure was comoared to the pressure exerted by the 292* reference leg filled witn saturated water at 105'F. This aP was entered into the calibration table for the transmitter, and an 3
uncompensated transmitter output in 5 obtained. The compensation i algorithm from the SPOS was then aoplied to the uncompensated level ;
' values. A perfect compensation routine would yield 951 for each of the uncompensated level values, even thouqft the uncompensated level values ,
vary due to the change in water density at different temperatures.
l The first result of this exercise was the discovery tha't since the correction factor C is always a number very close to unity, it is impossible for INPUT, i.e. uncompensated level, to be in counts, and l
OUTPUT, t.e. compensated Tevel, to be in percent. It appeared that. IF INPUT was irt counts,. OUTPUT would be in counts, and.if INPUT was in l '
percent,. OUTPUT would be irr percent. Based on this conjecture,. the exercise was completed. The taale of values is attached as Table 1.
i The compensation algoritner wnee appiled. to the uncompensated level l I
l veTues,. rather than producing a unifor1e value of 955, produced values ranging front 835 ta 905. As, a means of checking this, actual values for L9804,, (uncompensated leveLand input to SPOS, 8 GT5G) and P9300 (5 GT5G.
j pressure) were retrieved for TZ-19-8Ev when t'1e plant was at 1005
! power. The compensation aTgoritfus appiled to anr uncompensated level of 6T.31% at a pressure of 904,psiguyields a compensated value of 7T.855.*
However, the $POSL level ind:fcation for the S. OTSG. was observed to be t reading: 885 on 12-19-85, and, the Tevel recorder was observed ta be-reading.905. This suggested that the compensation algorithet described le the SPOS manual was not the algorithm that was actually being
! performed by the SPOS.
1 Conversations, with Said yielded a. revised algorithm claimed to be the '
f routine that SPOS was actually applying. This was later shown to be so'.
i
) OUTPUT = C* INPUT
' where INPUT = uncompensated Tevel in E and: C = correctiort factor,. using pressure i
- le counts 'G psig, = G counts and.
l 1203 psig = 4096 counts. AIT coefficients used is the calculation of the correction factor C are unchanged. i 1
Table 2 was generated using this revised algorithm. Compensated level l was seen to very only front 94,895 to 95.41% for pressures ranging frois 20% to 1050 psig. The values for uncompensated level and pressure from.
12-19-45 were input to this revised algorithm and a compensated level of
' 88.85 was produced. This compares very well with the $POS level of 885 l
observed on 12-19-85. Therefore, the revised algorithm appears to be a
_c- good compensation for density variations. .
J ATTAC19ENT 6.2d-l ,
-Page 6 of 13
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!?iVESTIGATIONS 00NE (Continued)
Cate:Tation of S?OS Level indicatien Ouring 12-26-95 Trantient. U:in;
, IDADS Values for uncomoensateo Level and Pressure. ano The Reviseo l
)
l Temnerature Comnensation Algorithm;
' IDA05 values for L1804, L3803, L1803, L9804, P9301 and P9300 were retrieved for 12-26-85, from 0400 to 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />. This includes a period of about 30 to 45 minutes when OTSE Operate ran9e levels as indicated by the control room level recorders, LA-20503 and LR-20504, were 100%. .
Calculation of compensated level, using the revised algorithm, yielded values from 981 tai 99% for both steam generators. - ,, ,
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- 5. Simulated Inout Sionals for Uncomoensated Level and iteam Generator Pressure. and Observed SPOS Outout; i
1 Three different values of uncompensated level were input to the S?OS as l' duany signals. This was. done at each of three different pressures, also input as dummy signals. The results are shown in the following charts. )
i A-GM ..
! Unenseensated Level. L9807 OTSE 15n 50 5 851 PRESSURE
! P930T SPOS CALCULATER SPOS CALCULATER SPOS CALCULATED I
k [NOICATED INDICATED INDICATED
/ 300 99.65
! PSIG 17% T7. 62 58% 58.85 995 j'
~~
600 l T8.75 62.55 106E I- 106% ,
PSIG 185 .62%
l 900 l 195 T9'.8% 66 1 65.02 112% 112%
PSIG ,
i l
. I t-0TSE )
Uncompensated f.evel. l9804 )
i GTSG ISS 50% 85%
PRESSURE .
P9300 SPOS CALCULATED' SPOS CALCUI.ATED SPOS CALCULATED 4
{
IN0fCATED IMOICATED IMOICATED i 300 j PSIG 17% T7.65 585 58.8E 991 99.6%
600 PSIG T85 18.7% 62% 62.55 1065 - 1061 7 900 l t PSIG , 19% 19.85 - 655 66.01 1125 1T25 (Calculated levels are compensated with the revised algorithm.)
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- ATIACHENT 6.2d-l 1
Page 7 of 13 1
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. INVESTIGATIONS 00NE (Continued)
(
It is c'f interest to note that the values for unc:mpensstad la/el of 35*. I and pressure of 300 psig, which caused an SP03 output of 99% are very .
l close to values which occurred during the transient. At 05:00:00, 8 31sa pressure was 301.0 psig, and S-0TSG uncompensated level' .as .
34.07%.
1
- 6. tLi storical values for SMS Level Versus Strio Chart Recorder '.ewels ;
Durine Ooeration Were Compared
' Since SPOS level is not recorded.anywhere, the artik. data points 41tch .
exist are several values which were recorded as a par: or a staam generator performance monitoring program which is undeFdevelocment.
Level Computer te' Power SPOS Level Recorder LO37 LO38 I 8 A i 8 A i 8 i A A l 82.5% i 99 *. - 83.95*, 89 . 43P. '
!T2-18-% 100.2 % als 88% 1 !
I l l J
T 7-17-6f 100,95, als 88% i 87.55 90 % l 8a. Als I 90.27%!
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- '. 1 1
C. CONCt & ONS/ EXPT.ANATI0lt a s"
i The revised temperature cosipensatiost algorithe is a good compensation
" for variations ist water density. The actual compensation performed by. ;
the SPOS is. the revised algpcit.ue
- The. SPOS manuai, appendix 1,. page 4,.
paragrapit E.E, it incorrect.
.. Z. The SPOS ope 2 ate range Teni~ indi* cation is generally about 1% to 2% less thast the operate range level indicated by the control room strip chart ,
recordies ano, the plant coecuter. )
! 3. The SPOS. was. probably indicating 981 to 995 during the transient,. when -
' the strip _ charc recorkrs. were indicating 100%. This conclusion appears fnescapable in light af the fact that values for uncompensated level and
, GTSG pressure practically identical to those recorded during the transient were input to the SP05 which produced a compensated level valueif 945 ta 995.
- 3. SHORT TTdM F0fJ.fAHk5 REQttTRED/ REC 0felEN0ATIONS
~
T. sak shoul6 oe aske4 to revise page 4, of appendix 1, of the SPOS manual te correctly desc. ribe the temperature compensation algorithe.
- E. LONG TERM RECOMMEN0ATIONS i
e ,, 1.'
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. ATIAQnGNT 6.2d-l Page 8 of 13 i
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F.
PROGRAMMATIC IMPLICATIONS Continued emohasis must De olaced on training operators to use all available inforwition ario te !P 4ction based on evaluation of multiole ooservations of parsmetars.
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OATE f-7-(6 j REVIEWED AND ACCEPTED' /Zbe / f_ ' ~ s w . '
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Action List Coordinatorf- SMUD ~
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ATTACEtENT 6.2d-l O.M PAGE 9 of 13 i / .
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TABLE I ORIGINAL C; f"EMIATIGH ALGORITH'4 C*, -
Soecific uncomoensaceo Compensated Pressure Temp; Vo Me Lewei i Level %
asia osia 'F Ft3/1bm 200 185 382* .0 839 33.56 90.04 250 235' 401* .01865 82.4 89.5
- 300 285 417' .01890 81 .3 89.2 350 335 432* .01913 80.3 88.6 400 385 445' .0193 '79.6 88.4 450 435 456' .0195 78.8 88.0 500 485 467* .0197 78.0 87.6 560 545 479 * .0200 76.3 86.9 ..
600 585 486' .0201 76.5 86.8 660 645 497* .0204 75.3 86.0 i
'700 685 503* .0205 75.0 85.9
- i 760 745 51 2' .0207 T4.2 85.5 800 785 51 8 * .0209 73.5 85.0 860 845 527* .0211 72.8 84.6 900 885 532* .0212 72.5 84.4 -
960 945 540* .0214 7T.a 84.0' 1000 985 545' .0216 71 .1 "
83.4 1050 1031 551 * .0218- 70.5 83.0 NOTE: ActuaT level assumed tb be 277.4* above'the lower tap, or 95% of the 292* span. The shas been converted to an uncompensated T) 3- Tevel cuput per the'i.nstrument calibration sheet.
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AITACEMENT 6.2d-l .
Page 10 o'f 13
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TABLE 2 O'
REVISED COMPENSA7 ION At.3C2!7hM Soecific , Oneomnansarea Comoensated Pressure Temp. Volu. e - f. eve! ". Loel .5 '
asia osic 'F ft3 /1bm 200 185 382* .01833 83.56 35.27 95.34 250 235 401 * .01865 82.1 300 285 417' .01890 81.3 95.27 350 335 432* .01913 30.3 95.18 400 385 445' .0193 79.6 95.34 450 435 456* .0195 78.8 95.34 .
500 485 467* .0197 78.0 '
95.30
- 56C 54T' 471 * .0h00 75.'. 94.93 -
600 585 486* .0201 76.5 95.30 660 645 497* .0204 75.3 94.89 700 685 503* .0205 75.0 95.23 760 745 51 2* .0207 74. 2 95.27 800 785 518* .0209 73.5 95.06 860 845 527' .021T 72.3 95.15 .
900 885 532* .0212 7Z.5 95.40 960 945 540* .0214 71 . 3 95.41 1000 985 541* .0216 7T.1 -
95.08' 1050 1035 551* .0218 70.5 95.QT
~
le0TE: Actual Tevel assodat to- be 277.4.* as, in Tatrie i, and the same uncompensated levels,usede ' Campensation algoriths revised such O ,
that pressure in counts = PSIG" 4096 T200, ATTACHMENT 6.2d-l Page 11 of 13 .
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THE BABCCCX & WILCCX COMPANY Powet oe4mAricN 04 CUP Om navisions l _m .
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Z.4 All displays that use incore thennoccupies shall be compensated using a polynomial curve fit using the following:
- [ Qutput = AL - AZ
- input
- A3
- InputZ
- A 4 ,,
III .
'il. - Lapu ta - A5
- Lacut* - AS
- Encut: -
127
- i where ,
r f.* Qutput is in counts (0 4095)
!!! Input is in counts. (0-4095) -
i
- I ._ . _ _ _
I
~I AL = -3.085ZS350s -
II AZ = L.00077Z99E l j! A3 = L.L57L65E-5 "
- i A4- = -3.00 L6718E-a l t *' AS = L.0980373E-LL 1i A6 = -L.06Z1160E-L5 '
l l'r
- Z.5 The points being displayed. wf TT be marketi witti a bliniting white i
T) 'plus sign. - 'n 3l h
Alt displays that use OT'SG agerating level shall be density gl. Z.6 2.!.y compensated.
5i l
where iii
$8e Output = C+ I!!PUT = Compensated OTSG Level in ':
"* Input is inr counts (8L9 4095) for- OTSG Level
{ ,
y[h I S 1,I C =* AL
- AZ* PRES)_
.1 4* (OTSG (OTSG* APR{5)"5(OTSG
- PRES A3
- 1+
(OTSG PRE 5)Z
!. e
- A 6 (OTSG PRES)2 n-;
IEl Ag L.0395Z92 A , = Z.313L58E E-04 1l Agg =
= -L.SZO80Z8E-GT -
8d A4 = 6.SZ454L9E-LL 3 L.5L42765E-14
((j gg Ag = 1.Z623188E-18 A5=
Ik
'14 sa
.F.
Lt5 c ATTACHMENT 6.2d-l l / Page 12 of 13 AP9'"dN l A1099 Page 4 S4UD 5afety Parameter display 8/S/82 Functional Description .--
na4044 4.o
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