ML20212M905
| ML20212M905 | |
| Person / Time | |
|---|---|
| Site: | Vogtle |
| Issue date: | 08/22/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| 0682V, 682V, GN-1055, NUDOCS 8608280001 | |
| Download: ML20212M905 (14) | |
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Georgia Power Company Post Offics Box 282 Waynesborn Georgia 30830 Telephone 404 554-9961 404 724 4114 Southern Company Services, Inc.
Fbst Office Box 2625 Birmingham, Alabama 35202 Teleohone 205 870-6011 VOgtle Project August 22, 1986 Director of Nuclear Reactor degulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GN-1055 PWR Project Directorate #4 Division of PWR, Licensing A
' U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF:
(1) MILLER TO CONWAY, DATED 8/6/86 (2) BAILEY TO DENTON, DATED 8/14'/86 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEt4 17: TRAINING PROGRAM
Dear Mr. Denton:
Attached is the additional information requested by your staff in a telephone conversation on August 22, 1986.
If your staff requires any additional information, please do not hesitate to contact me, Sincerely, J. A. Bailey '
Project Licensing Manager JAB /caa.
Attachment xc:
R. E. Conway (w/o att.)
NRC Regional Administrator R. A. Thomas (w/o att.)
NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey (w/o att.)
M. A. Miller L. T. Gucwa (w/o att.)
B. Jones, Esquire Vogtle Project File G. Bockhold, Jr. (w/o att.)
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REASON FOR REVISION:
MAJOR REVISION DUE TO ERRORS OR OMISSIONS.
REVISION DUE TO CHANGES IN EQUIPMENT.
y REVISION DUE TO CHANGE 3 IN PROC DURES/0PERATING INSTRUCTIONS OR POLICY.
DESIRE ADDITIONAL GRAPHICS / HANDOUTS FOR THIS TRAINING MATERIAL OTHER COMMITTMENIS: TES X NO DRAFIING ret;UEST FILLED OUT. TES NOJ DATE SUBMITTED EOR SUPERVISOR'S REVIEW Y2 L.
REVI2.W SAT / UNSAT APPROVAL SIGNA M
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DATE NIEDED BY SUFIRTISOE REVI Ws TTFING SAT UNSAT DRAFTING SAT UNSAT
' REWORK: WHYT DATE NEED E BY
' SUPERVISOR SIGNATURE DATE LIBRARIAN RECEIFT FOR INCLUSION /OUT3ATINC OF' FILES. DATE l
FILE WORK DONE DATE 4
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VOGTLE ELECTFilC GENERATING P J
TRAINING LESSON PLAN l
oc e - izc -LP - t s TITLE: $1c_9.1 VITAL INSTRUMENTATION NUMBER:
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PROGRAM:
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REVISION:
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RICHARD D. BRIGDON DATE:
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REFERENCES:
1.
NUREG 0737, ITEM II.B.4
- 2..
MCD TRAINING, VEGP-FSAR, CHAPTER 13; ITEM 13.2.1.1.6 S.
" VITAL INSTRUMENTATION," MITIGATING REACTOR CORE DAMAGE, GENERAL PHYSICS CORPORATION 9,
" VITAL INSTRUMENTATION," MITIGATING CORE DAMAGE, WESTINGHOUSE ELECTRIC CORPORATION INSTRUCTOR GUIDELINES:
Lo -Ho -wo y -oo v - oo t HANDOUT: " VITAL INSTRUMENTATION,"-GF,-20 000 TRANSPARENCIES:
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SA-EIL-083-4 oot ENTHALPY VS PP. ESSURE / TEMPERATURE S0--r 000-2 0o3 PRESSUR1ZER PRESSURE / LEVEL INSTRUMENT ARRANGEMENT 4
Sa-38-483-GooM PRESSURIZER SYSTEM 0^ "'" 000-hoc-LOOP NR TEMPERATURE MANIFOLD f
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PURPOSE STATEMENT:
THIS LESSON UILL PROVIDE THE STUDENT WITH AN UNDERSTANDING OF THE RESPONSE OF THE ?LANT'S VITAL PROCKSS INSTRUMENTATION DURING AND AFTER A MAJOR PLANT ACCIDENT, INCLUDING FAILURE TIMES AND FAILUP.E METHODS. THE STUDENT WILL ALSO LEARN ALTERNATIVE MEANS OF MEASURING LOST PARAMETERS.
11.
LIST OF OBJECT,lVES:
Ta--in:1 Obj ectise At th: :nd cf thic lessen-the s;-d.us will hav. eu uudescending af the-response of u
tha-plant vi e =1 instrumentatin-to-a-aa}cr plant =ce4 dent-ir.Heras-of hou rha instruments are.expeerad_to failr-f actst; affecting indiestien r=14 =hilityrend-alternative _maans.of_
paranator-seasurement._
"--Elin;'Obje;;i.ea:
1.
List and describe'four environmental factors that affect the reliability and potential failure of instrumentation associated with critical plant parameters.
2.
State the probable failure modes of critical instrumentation when exposed to the adverse condition defined in the previous objective.
3.
Describe what is meant by adverse containment conditions.
4.
Deacribe at least one alternative means for measuring the following primary parameters:
- RCS locp ten.peratures
- PZR pressure
- PZR level
- RCS flow rate
- Letdown flow rate 5.
Describe the problems associated with the PZR pressure control system and PORV's at TMI-2 and relate how these have been corrected at VECP.
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LESSON OUTLINE:
NOTES I.
INTRODUCTION A.
TMI-2 accident 1.
During first day - all instrumentation with w.re-Wic4
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exception of thermocouples worked satisfactorily.
y,' g 2.
Following accident several indicators f ailed due to:
Bei'ng overranged (Temp instruments) a.
b.
Flooding of containment floor.
3.
Failure prompted use of alternative means of measuring key parameters.
B.
Scope of Lesson l
o gytcrwt 3
1.
Problems' associated with Pressurizer level control and PORV's at TMI.
2.
Factors affaccing vital instrumentation operability.
3.
Alternative means of measuring key plant parameters II.
PROBLEMS ASSOCIATED WITH PRESSURIZER LEVEL AND PORV'S AT TMI Misunderstandingofishthalpicprocesses.
A.
1.
Isenthalpic processes censarve energy (h) 6 n c-va;-i 1-r-oo 2.
As pressure drops via throttling process the steam
-82'* ^33-3 expands distributing the energy over a larger Tp_oo,
area. Therefore the temperature dropa.
i 2.
Isenthalpic processes not common knowledge prior l
to TMI-2.
Now is,rege0N G part of training.
Misunderstandis @{)(( p Y Valve Position Indication G
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B.
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FJEF WI at%@@ was demanded position, not actual 1.
pagities.
l 2.
Therefore, when conttol switch wa:s placed in shut position, it indicated shut when it was really still open.
C.
PORV Leaked Prior to Accident 1.
Related to isenthalpic throttling procesi.
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LESSON OUTLINE:
NOTES 2.
Tailpipe temperatures were prematurely high prior to the accident. Therefore, when the relief valve remained open it was not readily apparent.
D.
Industry misunderstanding of pressurizer level response during a steam space LOCA.
1.
Pressurizer level thought to decrer.se as pressure decreases during all LOCA events.
2.
During steam space LOCA, however, level rises as pressure decreases.
a.
Bubble moves to head area (hottest part of system) b.
~
As head bubble expands, it displaces water into the pressurizer.
III. ENVIRONMENTAL EFFECTS ON INSTRUMENTATION A.
Radiation o c,3tm u L.* l 1.
Adverse containment conditions
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5 are rad levels in excess of 10 R/hr.
2.
No adverse effects on prea'sure, temperature, d/p instruments.
- DW D ' '.I B.
Temperature cm w.s sE< n. -)
1.
Describe basic icop temperatura instrumentation
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Adverse effects a.
RTD's - less than 2% arror i
b.
Pressura - no significant effect d;;
l c.
4/p cellsh(level) - level decreases (5 to
' '.10% error at 300*F) 1 ad C.
Cont M Pres
.n 1.
Adverse containment pressure greater than or equal to 4 psig 2.
Adverse effects a.
RTD's - no significant effect b.
1ressure - changes reference for gauge presst res 4
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111.
LESSON OUTLINE:
NOTES d/p,(level)
'no significant effect c.
D.
Humidity / Flooding 1.
Affects instrument reliability by:
a.
Increasing cerrosion on terminal blocks b.
Shorting out instruments 2.
Adverse effects a.
RTD's - fail low /high b.
Pressure - fail low c.
d/p cells - fail low IV.
ALTERNATIVE MEANS OF MEASURING VITAL PARAMETERS
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Pressurizer Level
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1.
Measure d/p between liquid and vapor space sample caps (large errors) 2.
Compare actual pressurigst heatup rate to pre-calculated heatup rata curves based on level vs.
HUR with different curves for different combinations of pressurizer heaters.
B.
Pressurizer Pressure En " ^*2 2
1.
Measure pressura at liquid or vapor space sample line 2.
Use alternate wide range loop pressure instruments on hot legs 1 and 4.
i l
C.
RCS Flowrace y Ljik 1.
NC - Delta'T.between hot and cold leg vide range tempetasures.
D.
Letdova FlowrAtee p" '
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1.
Heat balance acrces letdown heat exchanger 2.
Flow balance across VCT.
i E.
Loop NR Temperatures en ynn i_z l
Tf'- c o S 1.
Use Wide Range temperatures.
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2.
Use core exiti t herwcouples l
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LESSON OUTLINE:
NOTES 3._
Re-calibrate overranged instruments to indicate on range.
V.
SUMMARY
A.
Existence of reliable instrumentation vital to safe operation of plant.
B.
TMI shcwed danger of zeroing in on one indication, no matter how reliable it may be, or is thought to be.
C.
Alternative indications may be used to replace faulty instrumentation or act as backup indication for verificatien of actual plant or component conditions.
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MAJOR REVISION DUE TO ERRORS OR OMISSIONS.
REVISION DUE TO CHANGES IN EQUIPMENT.
X REVISION DUE TO CHANGES IN PROCEDURES /0PERATING INSTRUCTIONS OR POLICT.
DESIR: ADDITIONAL GRAPHICS / HANDOUTS FOR THIS TEAINING MATERIAL OTHER COMMITTHENTS: TES X NO DRAFTING REQUEST FILLE OUT. TES NO X,
i DATE SUBMITTED FOR SUPERVISOR'S REVIEW ~7/tt REVIEW SAT UNSAT APPROVAL SIGNA DATE f/
- DATE NEDE FOR EW FROM ING
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LIBRART CLERK: %
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DATE FROM TTFING DATE FROM DRAFTING A/r!M i
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DATE INSTRUCTOR RETIEW: TTFING SAT UNSAT DRAFTING SAT UNSAT REWORK: WETT l
T. M..
-DATE NES S BT SUPERTISOR RETIEW TTFDG SAT UNSAT DRAFTING SAT UNSAT 1
'REWORKt WET 7 DATE NED E BT SUPERVISOR SIGNATURE DATE LIBRARIAN RECEIFT FOR INCLUSION /0UTDATING OF FILES. DATE FILE WORK DONE DATE l
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REFERENCES:
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