ML20134K891
| ML20134K891 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/27/1985 |
| From: | Thompson O Office of Nuclear Reactor Regulation |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8508300494 | |
| Download: ML20134K891 (44) | |
Text
-
August 270 1985 hh MEMORANDUM FOR: John F. Stolz, Branch Chief, ORB #4, DL FROM: Owen Thompson, Project Manager, ORB #4, DL
SUBJECT:
THREE MILE ISLAND, UNIT 1 (TMI-1), SPDS AUDIT On August 12-14, 1985, the NRR staff performed an audit of the Three Mile Island, Unit 1 (TMI-1) Safety Parameter Display System (SPDS). The audit team consisted of Leo Beltracchi and tiichard Shaker from Human Factors Engineering Branch (HFEB), and Joseph Joyce from Instrument and Control Systems Branch (ICSB). I was present on the first and last days of the audit.
The licensee provided a two-hour briefing of the overall SPDS system. Copies of the slides used are enclosed. The staff then audited the licensee's documents and observed the SPDS system in operation. The audit. programs outlined in letters to the licensee dated April 5 and July 9,1985 were basically followed.
i At the exit briefing on Wednesday, August 14 the staff informed tne licensee that the TMI-1 SPDS system is generally a good system which reflects the value resulting from Human Engineering input throughout development. The staff will be requesting the licensee to provide a copy of the validation test program report. Also, additional information will be requested to confirm the adequacy of certain isolation devices that protect the Class 1-E electrical circuits. The staff also indicated that the Procedures and Systems Review Branch (PSRB) review of the selection of critical parameters was not covered during the audit.
04531 R*J 59 ,
Owen Thompson, Project Manager Operating Reactors Branch #4, DL
Enclosure:
As Stated
~
cc w/ enclosure:
G. Lainas W. Regan L. Beltracchi R. Shaker F. Rosa J. Joyce D. Ziemann DISTRIBUTION F. Orr Docket File J. Thoma ORB #4 Rdg l 0. Thompson Memo File i PDR L PDR l
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'TO'T[
ORB 4:D HF p IC ORB #4:DLST ORP#4:9L l 0 Thompson;cr G $h- JStolz LBel racchi JJoyce 8/v /85 8/3)/85 85l/85 8g /85 8/3?/85 l
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TMI-l SPDS OVERVIEW NRC AUDIT AUGUST 12,13, AND 14,1985 J
H. C CRAWFORD
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n INTRODUCTION o EVOLUTION OF THE SPDS IDEA SLIDE 1 o DESCRIPTION OF PT PLOT SLIDE 2 CONCEPT OF SPDS o FLOW CHART (PAGE 1) SLIDE 3 o USERS SS/STA 0 CSFs SLIDE 4 o SELECTED PARAMETERS UNIQUELY DEFINE CSFs NUREG 0737 SUPPLEMENT 1 REQUIREMENTS o SAFETY ANALYSIS SUBilTTED 4/30/84 o B11-1 SPDS DEFINITION SLIDE 5 o TMI-1 SPDS PURPOSE SLIDE 6 o USED FOR OVERVIEW PURPOSES NOT TO CONTROL THE PLANT o B11-1 SPDS HAS BEEN PROMPTLY IMPLEMENTED
~
o N0 TECH SPEC CHANGES OR UNREVIEWED SAFETY QUESTIONS o HUMAN FACTORS DESIGN PHILOSOPHY o USER TRAINING WITH & WITHOUT SPDS
DISPLAY DESIGN o FLOW CHART (PAGE 1) SLIDE 7 o USE EXISTING PLANT COMPUTER SYSTEM SLIDE 8 RELIABLE OPERATING EXPERIENCE (5-10 YRS)
ENHANCE USEFULNESS OF SPDS (F#ilLIARITY, CONFIDENCE, LOCATION)
V&V ONLY ITEMS ADDED TO SYSTEM BY SPDS SPDS IMPLEMENTATION o FLOW CHART (PAGE 2) SLIDE 9 o DISPLAY HIERARCHY SLIDE 10 o ALARM CRT .
SLIDE 11 -
0 CRT CONSOLE SLIDE 12 o SPDS MENU SLIDE 13 SPDS FINAL DISPLAYS POWER OPERATION l 0 REACT / POWER DIST & PRIM SIDE HEAT REMOVAL l
LOW POWER 3 RC PUMPS SLIDE 14 POWER > 20% 4 RC PUMPS SLIDE 15 POWER > 55% 4 RC PUMPS SLIDE 16 LEVEL 2 DISPLAY SLIDE 17 o RCS INTEGRITY SLIDES 17 AND 18 o RADIATION CONTROL SLIDES 19 AND 20 o CONTAINMENT CONDITIONS SLIDES 21 AND 22 l .
l
POST TRIP o REACTIVITY / POWER DISTRIBUTION SLIDES 23 AND 24 o PRIMARY SIDE HEAT REMOVAL FORCED FLOW SLIDE 25 o RCS INTEGRITY FORCED FLOW SLIDES 26 AND 27 o PRIMARY SIDE HEAT REMOVAL SLIDES 28 AND 29 NATURAL CIRCULATION o RCS INTEGRITY NATURAL CIRCULATION SLIDES 30 AND 31 4
O e
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r Evolution of the SPDS Idea TMI-2 Lessons Learned 5
Vendor Abnormal Pressure Transient Temperature Operating Plot Guidelines (PT Plot)
(ATOG)
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Symptom Safety Oriented - - - - - ---- Parameter Emergency -
Display Procedures - - - --- - - -
System (EOPS) (SPDS) ,
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-- - - - - - -- - - - - - , _ - , - - , - , . , , . ,n,e,r ..- ,. .._ ,, . . - , ,.- -- - , - . .---------,-..--,w, , , . , , , _ --,-- -..-.----_...n
SPDS Definition The Safety Parameter Display System (SPDS) will aid the control room personnel in determining the overall plant safety status and determining if the actions taken by the operators have brought the plant to a stable and safe condition.
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SPDS Purpose
- 1. Provide organized information at one location.
- 2. Continuously monitor information. P'w c~v'lo -
- 3. Primary use for off normal events.
- 4. Secondary use during normal evolutions.
- 5. Critical safety function approach.]
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DESIGNING AND IMPLEMEf4 TING AN SPDS
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,h DOCUMENT SOFTWARE 1 REv'EW DE SGN ,2 i gpg . ogefg DE$lGN REPORT TI a%a ENGR RESJLTS UNSAI DEFINE TE ST $At METNOOOLOGY TEST a I PLAN DE FINE '"
ADOfTCNAL DS TESTING C TEST Py YES i
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SPOS DISPLAY HIERARCHY POWFR OPERATION L 2776 = 3 and SPDS M N RCS Tergerature 1 525'r
- 1. Reactivity / Power Dastribution 2 Primary Side Ileat Removal -
3 Reactor Coolant System Integrity 4 Radiation Control '
- 5. Containment Conditions Select I or 2 Select Then Execute Ji Then Execute p- --- ---- - .. ._ .
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J6 8 ' PAGE A and B < 55% $
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3 P q p q p l THEN EXfrUTE THl'N EXtr PTE TifEN E(ECUTE I l g DISPLAY l DISPLAY 2 DISPLAY 3 DISPLAY 5 DISPIAY (o DIS? LAY 7 g
- PRf'VIOUS OR PT PIBr PT PIEF PT PIUT TABULAR' - TAPULAR .Nd:bT o e e TABUIAR I FLUX /FIDW/IMB FLUX /FIDW/IMB FLUX /FIDW/IMB l INFORMATION INf'ORMATION INFORf 4ATIOff I fw FIDW/POWP:R FW FIDW/ POWER FM FLOW / POWER 4
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I SPDS DISPEAY HIERARCHY TOST TRIP FORCED FtDW PUMPS # 0 and 12776
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- 3. REACTtAt COOLAN' SYSTEM INTtERITY 4 RACIATION CONTROL W776 mm &
g g g 7 5 CYWTAINMINT CullulTIONS l MiD PUMPS # 0 SELECT 1 j g THEN ExtrUTE I J k
, PAGE BACK LEVEL 1 1 SELECT 1 SELECT 2 SFLECT 3 SELECT 4 STLECT S htN EXECUTE THFN EXECUTE 1 F THIN EXtrVTE . *THEN EXtrtJT1 THEN EXECUTE DISPLAY 8 DISPLAY 9 OtSPLAY 10
.. TABULAR DISPLAY 6 PRfNIOUS OR PT PIDr DISPLAY 7 INFORMATION TABULAR NTXT TAIMJLAR INFORMATION *** * * ** TAl9UI.AR INFORMATION ea a INFORMATION i_ w LEVEL 2
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- SPDS DISPLAY HIFRARCtfY POST TRIP NATURAL CIpcutAfgry4 PUMPS . O ar,3 g,; , y,, ,,
/ or PT PIDT RUTTm ON CRT 4 PUMPS = 0 and RCS T12? :.RATU.< R < 52 % ,
Cm SOLE IS DEPRESSED AND 7
PUMPS
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- 1. REACTIVITY /MMER DISTRIBUTION
- 2. PRIMARY SIDE HEAT REMOVAL L2776 CHANGES STATE m
- 3. REACTUR COOLANT SYSTfN INTEGRITY rpm I to O AND - 4. RADIATIm CMTROL pumps . o 3. CONTAINMfMT CONDITIONS Sf: LECT J g TIf1N EXtrUTE d b PAGE ItACK Lf'VII 1 SELECT I SELfr7 2 THEN EXECUTt; St1ECT 3 SELFCT 4 THl.N EXECUTE.q p THEN EXECUTE
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- 6-Mt;LT::ttxtas
- CRTS(2) 1 ANALOG REMort { oisc cent TRENO ANALOG l MEMORY MEMOAY "ECC" IR SNPut , 32K tiORDS ,
OPf4ATORS N CONSOLE caj,$tga DISPLAY LaCAL
- ""' 1/INDOI?
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- PROGRAM TYPER CUh5CLE l
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I ,
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I HUX I Switch FCA - PROGRA!!MERS AREA FUNCTIONAI.
I FCB - DATA ACQUISITION Cott:'trl CRS FCC - HUMAN CO:OfUNICATION5 0-100 2N I ~
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LOCAL FCC 100 - +100 2;V FCE M1ALOC/ FCE - EALANCE OF PLANT CALCULATION l
4-29 ITA DICITAL , __
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g APID CPID CRF t
LN: VAL - Read Bailey SDF, convert value, and I DISC store in data base.
g DA:EXC - Data Acquisition Executive l
l \ l BAILEY 855 DATA BASE i \ l I'
BF - BULK POINT FILE I APID - ANALOC POINT ID FILE CPID - CONTACT POINT ID FILE CRF - CROSS REFERENCE FILE SDF - SYSTDI DATA FILE FIELD BAILEY 855 COMPUTER MODCOMP CLASSIC COMPUTER .
< > Data Flow Lines (Bi-Directional)
FICURE 2 NORMAL OPERATION '
DATA FIIM FROff FIELD TO DATA BASES
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FUNCTIONAL FCB - DATA ACQUISITIO:J 0-100 HV '^ FCC - HUMAN C0!!MUNICATIONS g,p 7 FE FCD - NUCLEAR CALCULATIONS
-10G - +1t?O .':V ANatoc/ FCE - BALANCE OF PLANT CALCULATIONS 4-20 ftA DIGITAL ~ --
/4 Others !!UI.TI- g I
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I -" > DATA Digita l #
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g LN: VAL (X)RE l DA:EXC HEI:0RY l
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l l ,
DA:EXC - Data Acquisition Executive g
N N BAILEY 855 Data Base j .
I BPF - DUU' POINT FII.E I
APID - ANALOG POINT ID FII.E .
CPID - CO: TRACT POINT ID FII.E 4
CRF - CROSS REFERENCE FILE SDF - SYSTDI DATA FILE FIELD BAILEY 855 COMPUTER MODCOMP CLASSIC COMPUTER ,
( , > Data Flow Lines (Bi-Directional)
FICURE 3 i: ,
BAILEY 855 OUT OF SERVICE DATA FIDi FROM FIELD TO MODCOMP DATA RASE
h HUMAN FACTORS AT GPU NUCLEAR sla/sc Staff:
Manager, 2 full time HF Engineers, Co-Op student (grad)
Location: Corporate HQ, Parsippany, NJ Organization:
Computer Appl./ Human Engineering Dept, Systems Engineering, Technical Functions Division, GPU Nuclear Involvement in Projects:
Reviews all new modifications to plant, reviews existing control stations. Reviews all op/maint. mods.
INVOLVEMENT BEGINS AS EARLY AS POSSIBLE IN EACH DESIGN DEGREE OF INVOLVEMENT SELF-DETERMINED (DEPENDS ON NATU One HF Engineer Assigned to Each Project HF GROUP WILL INITIATE NEW PROJECTS TO CORRECT Human Engineering Deficiencies WHICH ARE FOUND IN THE PLANT.
HF will review and aid in preperation of applicable documents *,
drawings, hardware sele'etion, etc. and follows through to project installation.
Other areas of HF involvement:
Ambient Environment surveys Assigns Control Room hardware / alarm locations y p Formats all CRT displays All plant labels ordered through HF All wording (labels, alarms, etc) chosen by HF Reviews / Formats plant procedures on request, Formats all E0Ps Attendance: HF attends all applicable PEDR and OMCR meetings
SUMMARY
- COMPREHENSIVE, FULLY INLOVED HF PROGRAM .
llI -
y .if '7 -
- fliF G.25tew ef 'l IHF Riview sf T HUMA3 FACTORS PROCESS ,
SPDS goals / Generic HF g, SPDS DEVELOPMENT reeutrements Documents W CE EPRI NRC- T NUTAC SPOS Gutde L NUREG 0835 J HF books E s (DISPLAY g k GPU Doctaments ) DESIGN g
(
V %. . HF/SAPC F Definition of ] Functional' 'j / Existing.
Computer Displar l
Plant-Specific is Analysis by I g Task SA/PC Review.
Safety Analysis (SA/PC) Red ews/
Y SPOS Goals and Needs
) Analysts E- >
Background Work by SA/PC C(Objectives-Users),
by SA/PC J W.
LPARAMETERSELECTIDN.[h I
t r
/____ _
3 F 3 r
3 r m r- 3 F Secondary Task Analysts Walkthrough #1 Training. 2nd HF Review of Walk-Displays: Color, by SPDS Comuntttee; with all users Session-for A. through with-Format Scales. Units Relation of SPOS to CR (STAS. SR0s) l Consistency .
) Crew Roles / workstations Q done with proper h SPDS / CRT Displays display options by _U1crs . _
i HF/SAPC Coinnent 1 0 l Resolution l l Mit 4 ** /h.>
j J L j k I
~J L ,
,, y} p~ *t ! <* . t* t< > s . 1/
l AJ! /I L * / t'PWQ f
/*t. wit # *'I-- SPDS Comittee 4 evaluation of- (
j,f[,, y- conenents - final e SPDS '.
Display Scrutiny f i l
J l
.- tw ra o i so l
[/MM .
jyjGW * /5AJt'l.-
Z>sp4**fS ll6ke2> /Ei>: 2beu,w nAs be, w f" _
N.
- ekspr V8V TEAM MEMBERS o BRUCE OLAF -
SOFTWARE DEVELOPER 0 JIM P. Hell -
0.A. ENGINEER 0 TAE Y. BYOUN -
NUCLEAR ENGINEER Zh- .
e
. SPDS V8V SCOPE 1
INDEPENDENT REVIEW & EVALUATION OF THE SPDS SOFT (5 CSF'S & 9 DISPLAY PROGRAMS), '--
2.
REVIEW AND COMMENTS ON SYSTEM REQUIREMENTS DOCUM AND DESIGN DOCUMENTS PER V8V PROCEDURE.
3.
REVIEW AND COMMENTS ON TEST PROCEDURES AND TES PRIOR TO AND AFTER THE TESTING COMPLETION.
4 MONITOR AND EVALUATE THE TESTING PROCESS.
- 5. NOT INCLUDED ARE:
, O '
4 HdRIDWARE CONFIGURATI0N DESIGN REVIEW '
PLANT PROCESS COMPUTER HARDWARE AND SOFTWARE WAS INSTALLED PRIOR TO AND INDEPENDENT OF THE SPDS DE THERE IS NO SPDS HARDWARE.
O HUMAN FACTOR REVIEWS HUMAN FACTORS CONSIDERATIONS HAVE BEEN INCLUDED IN THE SPDS AS AN INTEGRAL PART OF DESIGN PROCESS. THE HUMAN FACTORS EVALUATIONS HAVE BEEN PERFORMED SEPARAT AND DOCUMENTED.
O SPDS OBJECTIVES AND REGULATORY REQUIREMENTS -
4
s P.'I.E 7 Or 21 TIREEMILEIILANDUNITI IAFETYPARAMETERDIIPLAYSTITEM REQUIREMENT! TRACEAPILITY MATRIX (RTM II) l GPLW l l l l l l RTM l REQUIREMENT l I ITEMi DEICRIPTION IREQUIREMENTIDEIIGN/CODEITEITMAN. 1TEITPROC.I REFERENCE (!)lREFERENCE(IllREFERENCE(!)l REFERENCE REMARKS l u n m l u n n u n n u n n u u l n(A)nP.163 i 13.36 i Radiation Control Priority 2 CIF flowchart. m Iu(A)nP.f44, m In u n n u n n li e n n mi i l l i VER-M5I l -l l (A) P.350 l 145 I I lVER-60$J
--l-c I -1 -l-l 13.35 l Radiation Control Priority i CIF floschart. 1 (A) P.163 l (A) P.143, I l l I I j... ..l ......... l l
......ll..(A) P.356 1 144 l l l13.46IContainmentConditionearningCIFfloschart. ...__...l.c----------1------------I----------1-------.-...-.-.1 l(A)P.164 l(A)P.133-l I I l l 1 I l- I(A)P.351 1157 l l l . 1 1 -1.c -l- -l- -g-i 13.45 i Contai nent Condition alare CIF floschart. -j I I 1(A)P.164 l(A)P.136-l l 1 1 I(A)P.351 1152 l I I I lumulminununununununununnmumninununniecununnlimimnulunnunniumun i 14. M l 3PDI paraseters organized into 5 I(A)P.12 I(A)P.7,191 l l critical safety (sactions (CIF). l 1 I l l l l l l l aum i mmunu m u n mmmam**mmman l 15.H l Reactivity /Pomer listribution CIF l 1- lmmunn i nunann i nnmum l umun
-l lParaseters. 'l t .
- l. I I l- .l.. . ___ _ _ .. . .__ . . ..
_l __ _ ____ll. ll__ . . .l._
l 15.65 i Paraseters for CIFs, Table 3.1.
1(B)P.28 l(A)P.26, I l ......ll.. . ..
.ll l 1 l lVER-M4N l 1
1 I116-118 I I l I l
-l- l-c I I i 15.16 l Reactivity / Power listribstion paraseter names. I I l
1(B)P.30 l(A)P.27,271 1 I l 1 1 -l-c -l- 1 -l
- i 15.15 i Reactivity / Power distrib: tion critical safety I(A)P.39 I(A)P.26,271 l I I function parameters, point niebers (Table 6.1). I I i i I
j .
l.. ... . . .... ...
.l.g l l l l l 15.26 l R/PD & PSHR poser operation level i display.... _ _l_
l... l.... l _ .. -
-l l l coopster points - PT Plot. l(A)P.354 l(A)P.27 l l l l l l l l- I-- l l l
! -l l-c -1 I
! 15.25 i R/PD & P!HR power operation level i display I l I l computer points - Fler Flos 1 (A) P.355 l (A) P.26 l 1 l l
I l l l g .___. l _
...___..............Isb a la nce Pl o t...........
.l....... ...l
__ ....l.. l l l 15.36 l R/PD & PJHR poser operation level i display
.... . l ..
.....ll___.__ l .__. .__ g l (A) P.355 l (A) P.26,271 l lYER-M4D 1 1 Icospiterpoints-FeedsaterFlosPlot. 1 l
I- 1 --
l I28 I l l VER/DR-666 l
(
-1 -l l I l l 15.33 i Correction to R/PD and PJHR poser operation 1(C) ~l
! l l l l I level 1 display computer lVER-991A l j ... l... .... ............ points.............. I RC i M22 I i !
I
....l....__.. l__..... .. !l
.l......
l 15.35 i R/PD poser operation level 2 display - coepiter I(A)P.361 1(A)P.26
..l........... .. . .l l l Ipoints. I I IVER-M4E I l 1 I I l- I I I
-l I-c I I I I i15.46iReactivity/PowerlistributionposttriplevelI l (A) P.378 I (A) P.26 I l 1 1 display - computer points. l 1 l 1 I l l
! lanmimunnumununnmunmunnumanalunnunnlminnnninnnunnlun l i i
\ ~
s ., , ,
OVERVIEW OF SPDS V8V ACTIVITIES
, > .CtX - S o.4.s / h.,u GPUN &V PLAN , 4*'M/ # "'#N" #
/%k HS_AC 39 -y V&V PROCEDURES '
V8V PROC. (TDR-711) g V&V TEAM (SAIC/GPUN) y SPDS SAFETY ANALYSIS y SYSTEM .,
(TR-18) REQUIREMENT REOUIREMENT TRACEABILITY MATRIX VER. 1 (RTM-Ilg SPDS GUIDELINES #', 7 6 VERIFICAT10N _
RE0tilREMENT VERirICAT10N REPORT L (TDR- g y VSV (SAlG)
> DESIGN RTM-Il SPDS DESIGN DOCUMENTAT10N L (IDR_618) g VERIFICATION -
h
} DESIGN VERifICAT10h REPORT V8V (GPU) y 1
f VAllDATION TLST PLAN (L)
' bYblLM RIM-11I TEST PROCIDURES R TEST MANUAL m VALIDAtl0N g
SPDS PACKAGE VALIDAll0N TEST REPORT g h TEST -
V8V (GPU) A M V8V FINAL FINAL REPORT
@ REPORT V i v8v (GPu) d 4
CosmeMr/bsow7MN 87mDS &EET
- =====u=================================
! REVIEWER'S COMMENT VER-003
==
i======================================I 0F 2 1 PROJECT: TMI-1 SPD SERIAL l DA NO:=============== 1
=
g==u================S V&V=======================TE: 06/27/85 1 V&V TASK: Desi
- =======u=======gn ============================
ISSUED BY: T. Byoun/ Heil 1
Verification =======================i=
l DOCUMENT (S) UNDER REVIEW: TDR-618, Rev 0 ================
I ll===========u=======================================
COMMENT:
1 A. =========================
I RTM 05.30 - TDR does not 1
required if instrument address tha t remova t of points froni scan is l ( RESPONSE ACCEPTABLE 08/08/85) string feeding SPDS computer input is removed.
l 1
B. usedRTMif05.35 - TDR does not address that redundant availible. re to besenso I ( RESPONSE ACCEPTABLE 08/08/85) i C. RTH 09.05 - TDR does not address when more provided for'a parameter, than one computer point l
l against alarm setpoint. use point closest to limit to compare I ( RESPONIE ACCEPTABLE 08/08/85)
D. RTM 09.15 - TDR does not address any i exceeding valid point for parameter 1 (. RESPONSE ACCEPTABLEiimit causes CSF atarm ,or warning.
I 08/08/85) .
I E. RTM 10.00'-
including TDR does not address that SPDS spurious alarms L2931. may occur during ,
I heatups, and should clear. cooldowns, cold shutdowns, and I (
i RESPONSE UNACCEPTABLE - SEE VER/DR-001 08/08/85) 1 i F. RTh 45.23 - TDR does not address accuracy I I (
chart. for hot leg A/B tevet bar i G.RESPONSE UNACCEPTABLE - SEE VER/DR-002 08/08/85) l l RTM 45.28 - TDR does not l l chart. address accuracy for RV Head level bar I l (
H. RESPONSE UNACCEPTABLE - SEE VER/DR-002 08/08/85) l l i RTM chart.
45.33 - TDR does not address accuracy l
. I ( for Pressurizer level bar I I I. RESPONSE RTH 46.00 - TDR UNACCEPTABLE does not - SEE VER/DR-002 08/08/85) l l
I ment of alarms. address audible alarm or user acknowledge- 1 I ( RESPONSE A j
l = = = = = = = = = = = = = = = =C C E P T A B L E 08/08/85) I i RESPONSE:
l ============================================
i (SEE S.M.CAFRELL1 NEh0 5421-85-0062, 07/18/85) l i I i I I I I I I
l============================================
l RESPONSE BY: (SC)
DATE: 07/1
======================================= = = = = ==================== =========== 1 l
~
, TMl-1 SPDS VEV DOCUMENTATION o
VERIFICATION & VALIDATION PROCEDURES (TDR-711) o VALIDATION TEST PLAN (TDR-710) o ' '
SYSTEM REQUIREMENTS VEAIFICATION RER0RT-(COMPLETED) '
(RTM-1, COMMENTS / RESOLUTIONS, DISCREPANCY REPORTS) o DESIGN VERIFICATION REPORT (DRAFT)
(RTM-II, COMMENTS / RESOLUTION, AND DISCREPANCY REPORTS) ~
o VALIDATION TEST REPORT (RTM-Ill, TEST MONITORING RESULTS, DISCREPANCY REPORTS, AND COMMENTS / RESOLUTIONS) o FINAL V&V REPORT
SPDS SYSTEMS REQUIREMENTS VERiflCATION SPDS SAFETY ANALYSIS y REQUIREMENTS (TR-18) RTM-1 m APPROVE IDENTIFICAT10N " RTM-l L RTM-l 7 SPDS USER GUIDELINES & .
O (TDR-583) V8V (SAIC) GPUN hr RESPOND TO 4 REVIEWER , V8V PROCEDURES COMMENTS i
GPUN FORMAL SYSTEM REQUIREMENT b REQUIREMENTS V}RIFICATIONREPORT g VERIFICATION
@ b
, ,-DISCREPANCY REPORTS a
V&V (SAIC) V&V PROCEDURES h
, RESOLVE 4
DISCREPANCIES T
DESIGN TEAM (GPU)
D
. DESIGN VERIFICATION PROGRAM SOURCES OF DESIGN VERIFICATION o
SPDS COMPUTER DESIGN AND IMPLEMENTATION (TDR-618) o BACKGROUND - SPDS CODE, RESULTS OF REQUIREMENTS VERIFICATIONS AND ANY IDENTIFIED REQUIRB1ENTS UPDATES DESIGN VERIFICATION o
CORRELAT' ION OF DESIGN TO SYSTEM REQUIREMENTS o
REQUIREMENTS TRACEABILITY MATRIX VER. II o
REVIEW & EVALUATION OF DESIGN DOCUMENTATION FOR TECHNICAL CORRECTNESS AND COMPLETENESS o
IMPLICATION ON THE VALIDATION TESTIN3 o
COMMENTS / RESOLUTION AND DISCREPANCY REPORTS
DESIGN VERIFICATION ACTIVITIES (GPUN)
V&V PROCEDURES d
RTM-I g IDENTIFY DESIGN RTM-1I FEATURES AND _, g DESIGN 00C. g ADD RTM-1 f 8V COMMENTS (TDR-618 ) "
f V&V TEAM 4 RESPONSE TO _
V&V COMMENTS V8V PRO'CEDURES 1 r "
1r DESIGN TEAM FORMALDESIGNl
'@j VERIFICATION !
DESIGN
- VERIFICATION REPORT A F
t .
V&V TEAM.
g DISCREPANCY REPORTS 4 RESOLVE _
. DISCREPANCIES o
I DESIGN TEAM
~
7
~
, l yALIDATION TEST PROGRAM o
OVERVIEW OF VAllDATION TEST ACTIV! TIES 1
PREP. VALIDATION TEST PLAN (GPU V&V TEAM) 2.
PREP. TEST PROCEDURES & TEST MANUAL (GPU 3.
UPDATE TEST PROC. & TEST MANUAL REFERENCE TO ~
RTM-Ill AND TEST PLAN (GPU V&V TEAM) 4
~
PERFORM (GPU DESIGN TEAM) AND MONITOR (GPU VALIDATION TESTING 5.
PREP. VALIDATION TEST EVALUATION REPORT (GPU V&V TEAM) o SOURCE MATERIALS o
COMPLETED SPDS PACKAGE (CODE DESIGN D0C. AND ANY DOCUMENTED DESIGN UPDATES) o RESULTS OF REQUIREMENTS VERIFICATION o
RESULTS OF DESIGN VERIFICATION
, .~
VALIDATION TEST AND ANALYSIS [GPUN) v&v PROCEDURE 4
JDR-618 k -583 g DEVELOP SPDS VALIDATION VALIDATION TEST PLAN
_RTM. PACKAGE y TESI PLAN r y t
V&V PROCEDURES U{A V&V TLAM V V DESIGN DOCUMENT (TDR-61R) i DEVELOP TEST lEST PROCLDURES & TEST MANUAL RIM-I & II g h PROCEDURES AND - V&V PROC. y OTHER SPDS PACKAGE
~
m TEST MANUAL
- 9 -e REVIEW AND RTM-1II DESIGN TEAM EVALUATE p
TEST PROG.
VAllDATION
& TEST MANUAL i fDISCRLPANCY RLPORTS
,/.._
N RESOLVE IEST PLAN ygy TEM j f,,,,
DISCRLPANCIES "N y v 4 MONIIOR 4 DESIGN TEAM %C,
C ----) TESTING lEST RESULT DOCUMENTAT10N d VAllDAT ION TEST EVALUATION REPORT g 4
V&V TEAM (MONITOR) ,ANALYii&
q A DESIGN TEAM (PERF0 01) 7 EVALUATE DISCREPANCY REPORTS k Y
k V&V TEAM RESOLVE DISCREPANCIES ,
< DESiGJ1aM
o CURRENT V8V PROGRAM STATUS e
ITE*4 DESCRIPTIONS STATUS o V&V PROCEDURES o DRAFT BY SAIC (10/22/84) o ISSUED BY GPU (8/8/85) o VALIDATION TEST PLAN o DRAFT BY SAIC (3/29/85) o ISSUED BY GPU (8/8/85) o SYSTEM REQUIREMENTS o COMPLETED BY SAIC (3/29/85)
VERIFICATION o RE0'T VERIFICATION REPORT (3/29/85) o RTM-1 (3/29/85) o 29 V&V COMMENTS ISSUED AND RESPONDED o
2 DI.SCREPANCY. REPORTS.lSSUED o CONCLUSION:
RE0'T DOCUMENTS (TR-18', AND TDR-583)
DEFINE THE SPDS SOFTWARE REQUIREMENTS o DESIGN VERIFICATION o DESIGN VERIFICATION REPORT (DRAFT) o RTM-Il COMPLETED SUBJECT TO RESOLUTION OF DISCREPANCY REPORTS o 36 COMMENTS WERE ISSUED AND RESPONDED o 9 DISCREPANCY REPORTS WERE ISSUED o VALIDATION TEST o TEST PROCEDURES (DRAFT) AND TEST MANUAL (DRAFT) WERE REVIEWED AND COMMENTS WERE ISSUED o
REVISED TEST PROCEDURES BEING REVIEWED & C MMENTED o
16 TESTS HAVE BEEN PERFORMED o RTM-Ill BEING ADDED e