ML20196D021
| ML20196D021 | |
| Person / Time | |
|---|---|
| Issue date: | 11/18/1988 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8812080186 | |
| Download: ML20196D021 (30) | |
Text
-__
November 18, 1988 mi a
g APPLICANT:
BABC0CK AND WILCOX OWNERS GROUP FACILITY:
ASSOCIATED FACILITIES
SUBJECT:
MEETING
SUMMARY
- THERMAL STRATIFICATION IN THE PRESSURIZER SURGE LINE - SEPTEMBER 29, 1988 TheBabcockandWilcoxOwnersGroup(B&WOG)wasrequestedtobriefthestaff on the status and direction of their efforts related to pressurizer surge line movement associated with significant thermal stratification in the surge line. This phenomenon had been observed et several Westinghouse NSSS designed facilities as well as a Babcock and Wilcox NSSS designed facility.
The meeting opened with remarks by the staff describing the background of this issue, the staff'? concerns associated with the observed temperature stratification, its significance, and the need for prompt resolution. The B&WOG then opened their presentation. The B&WOG presentation slides are attached as Enclosure 1; specific areas of discussion are identified in.
The discussion focused primarily on the data obtained by the instrumented surge line on the Muelheim - Kaerlich reactor.
The staff informed the B&WOG that the NRC was issuing a Bulletin related to this phenomenon, and solicited corrments as ta how the Bulletin's requirements might complement the B&WOG efforts. The 86WOG suggetted that requiring innediate actions by licensees may not be entirely productive if the issue could be resolved on a more "generic" basis and requested the NRC to confider deferring the issuance of the Bulletin until the B&WOG obtained and evaluated the additional data needed to quantify the impact on operation. They anticipated that this effort would be corrpleted around October of 1989.
A list of attendees is provided in Enclosure 3.
original signed by Terence Chan Terence L. Chan, Senior Project Manger l
Project Directorate V Division of Reactor Projects - !!!,
IV, Y and Special Projects
Enclosures:
DISTRIBUTION As stated Docket Fue
~
EJordan HPastis NRC & Local PDRs BGrimes HSilver cc:
See next page PD5 Reading NRC Participants ADeAgazio GKnighton ACRS (10)
TLChan MJohnson(RegionV)
.q
_ y y' OGC g
DRSP/PD5 DR h.P05
- ) ' %
TLChan:dr G
C ghton 11/n/88 11/ys8 m298ADSQ Mo3 ih
y W so n%
e e
UNITED STATES 8" 3 P
NUCLEAR REGULATORY COMMISSION 4
g
,.E WASHING TON, D. C. 20555 e
e
\\..... #'
November 18, IQ88 i
LICENSEE:
BABC0CK AND WILC0X OWNERS GROV.D FACILITY:
ASSOCIATED FACILITIES
SUBJECT:
MEETING
SUMMARY
- THERMAL STRATIFICATION IN THE PRESSURIZER SURGE LIhE - SEPTEMBER 29, 1988 i
The Babcock and Wilcox Owners Group (B&WOG) was requested to brief the staff on the status and direction of their of forts related to pressurizer surge line movement associated with significant thtrmal stratification in the surge line. This phenomenon had been observed at several Westinghouse NSSS designed facilities as well as a Babcock and Wilcox NSSS designed facility.
The meeting opened with remarks by the staff describing the background of this issue, the staff's concerns associated with the observed temperature stratification, its significance, ano the need for prompt resolution. The B&WOG then opened their presentation. The B&WOG presentation slides are attached as Enclosure 1; specific areas of discussion are identifieo in.
The discussion focused primarily on the data obtained by the instrumenteo surge line on the Muelheim - Kaerlich reactor.
The staff informed the B&WOG that the NRC was issuing a Bulletin related to this phenomenon, and solicited coments as to how the Bulletin's requirements might complement the B&WOG efforts. The B&WOG suggested that requiring imediate actions by licensees may not be entirely productive if the issue could be resolved cn a more "generic" basis and requested the NRC to consider deferring the issuance of the Bulletin until the B&WOG obtainoa and evaluatte the accitional data needed to quantify the impact on operation.
They anticipated that this effort would be completed around October cf 1989.
A list of attencess is provided in Enclos 3.
AG n c
T rence L. Chan, Senior Project Manger Project Directorate Y Division of Reactor Projects - !!!,
IV, Y and Special Projects
Enclosures:
As stated cc:
See next pagt
E
.c B&WOG PRESSURIZER SURGE LINE PRESENTATION TO NRC i
l SEPTEl!BER 29, 1988 1
1 1
1 I
l
[
e AGENDA NRC OPENING COMMENTS MEETING OBJECTIVES SURGE LINE HISTORY B&WOG PROGRAM M-K EVALUATION B&WOG PHASE 1 j
i B&WOG PHASE 2 OBJECTIVES B&WOG PHASE 3 ACTIVITIES
SUMMARY
COMMENTS
i MEETING OBJECTIVE _S_
TO ACQUIRE INFORMATION ABOUT THE NRC's CONCERN REGARDING PRESSURIZER SURGELINE THERMAL STRATIFICATION TO INFORM THE HRC ABOUT THE B&WOG SURGELINE PROGRAM TO DETERMINE IF THE NRC CONCERN IS ENVELOPED BY THE B&WOG PROGRAM l
I
PRESSURIZER SURGELINE HISTORY 12/84-USNRC INFORliATION NOTICE 84-87 "PIPING THERMAL DEFLECTION INDUCED BY STRATIFIED FLOW" 10/85-B&W WAS ADVISED OF THERMAL DATA RETRIEVED AT M-K 3/86-B&WOG STEERING COMMITTEE IS ADVISE OF M-K CONDITION 3/86-B&W0G MATERIALS COMMITTEE ADVISED OF M-K l
CONDITION 6/86-B&WOG MATERIALS COMMITTEE REQUESTS AN INVESTIGATION 12/86-PROGRAM WORKSCOPE DEFINED IN RESPONSE TO B&WOG MATERIALS COMMITTEE REQUEST 4/87-DRAFT INPO SER ISSUED TO B&W, CE, W, FRAMATOME AND VBG IN GERMANY 9/87-INP0 SER 25-87 ISSUED 7/88-B&W0G PRESSURIZER SURGELINE REPORT ISSUED DETAILING REVIEW 0F M-K DATA AND RECOMMENDING INSTRUMENTATION OF A B&W 177FA SURGELINE i
I i
SURGE LINE THERMAL STRATIFICATION FINAL RESOLUTION FLOW CHART
[ valuate iWR D.ala Tr.h - 1 Assess IUJ 177 rre Tossible 5:=sIar tses g
Tr.h - 2 1P enaa rw
!seum Nm otuttort 3 r Tek - 3
)N 1V Instrwt a DW 1/1 Srge Law ninSE 2 1r
[ valuate Data and trate report i
P qg lili IECIPIIIRE DEEl5!04 PCINI 1P is data artrottle 1P or not attepthle7 Isu e resel,,g Perfor=9 & tailed W tlosed A
an41 535 to 7
& terms w resolution
+
Develop retWitinn br.ed on analyses 9P we te returt Isvr rewived g
.vuf3_Im ed
DH-Ausgleichsloi'ing (DN 400) v PER-SuRee une
/
/v Hof LEG TEMP IgAfa101&
Wondst5rken:
- Gerodes Rohr : 45,72 mm I*.
Rohrbogen
- 51:"5mm BC O b1 2.03'"
Werksteff-X10 CrNETi its (1.4541)
H ATEf L%
9 v
2's"
/,$
ELavAn00
\\
4
$a
\\ #
a uu-a d
6,
<'N 10 YP 10 T 001 N
s s,
8,'~.
.. (
~,
/-i\\, :
V
- > p p 01 0 L 4 N:,s j
i s/,,,,,
.o tai
\\10 YP 30t006
,i TH e m e oce v r t,c, spTc
,/
kl,l,t 5
"'*"as
INSTRUMENTED S.RRGELINE PROGRAM AT MUELHEIM-KAERLICH 0
THERM 0 COUPLES INSTALLED ON PRESSURIZER SURGELINE PRIOR TO STARTUP TESTING 0
STRATIFICATION OCCURRED IN HORIZONTAL PIPE RUN BELOW PRESSURIZER SURGE N0ZZLE AT LOW FLOW CONDITIONS PRIOR TO REACTOR I
COOLANT HEATUP (PRESSURIZER TEMPERATURE = 450F, PRESSURE = 435 PSIG) t 0
TEMPERATURE SWINGS OF UP TO 3250F WERE MEASURED IN UP'PER PORTION OF SURGELINE DURING MINOR PLANT EVOLUTIONS 1
O STRATIFICATION HOT COVERED IN DESIGN l
SPECIFICATION 0
RESULTS OF MEASUREMENT PROGRAM i
NECESSITATED ADDITIONAL STRUCTURAL ANALYSIS OF SURGELINE AND PRESSURIZER SURGE N0ZZLE TO ACCOURT FOR ADDITIONAL LOADS DUE TO STRATIFICATION (E.G.,
CIRCUMFERENTIAL TEMPERATURE GRADIENT IN PIPE, ADDITIONAL PIPING MOMENT DUE TO TEMPERATURE DIFFERENCE OVER HEIGHT OF PIPE)
CONCLUSIONS RESULTING FROM M!LFJJiEIM-KAERLICH MEASUREMENT PRQGRAM 0
EVALUATION OF THE THERMOCOUPLE DATA AND FATIGUE ANALYSES OF THE SURGELINE AND PRESSURIZER SURGE N0ZZLE REVEALED THAT OHlY COLD STARTUPS OF THE PLANT LINKED WITH THE RELEVANT COOLANT FLUCTUATIONS VIA THE SURGEl.INE CONTRIBUTE SIGNIFICANTLY TO THE FATIGUE USAGE FACTORS 0
THE CUMULATIVE USAGE FACTORS FOR THE SPECIFIED NUMBER OF DESIGN TRANSIENTS ARE ACCEPTABLE (U < 0.5 < 1,0 ALLOWABLE)
e l
e B&WOG PRESSURIZER SURGELINE PHASE 1
a Thennal Stratification Mechanism T
4 Primary Side
[~
~
n f
h, * -
flot enoimk egow llot Water reed flot Water riow N Cold W. iter Iteu to a<',+,ce
,s pp py solid fronc
~v a
-[
7 Y (-
(
llorizontal rtix, C
/
=-
~~ v.
- T-
.~.
/
~
M
\\
T T
T 7
il S
L
REVIEW 0F BBR DATA 0
EVALUATION OF THERMAL HYDRAULICS TEMPERATURE FLUCTUATION IN SURGE LINE IS DIRECTLY RELATED TO PRESSURIZER LEVEL CHANGCS (I.E., SURGE LINE FLOW).
T6 ALWAYS LEADS IN THE TEMPERATURE CHANGES.
THUS, FLUID MOTION OCCURS PREFERENTIALLY IN THE UPPER HALF 0F THE SURGE LINE.
l T6 > T7 > T8 IS ALWAYS TRUE.
THEREFORE, THE THERMAL STRATIFICATION APPEARS STABLE.
ROUGH CALCULATIONS SHOW THAT TYPICAL SURGE LINE VELOCITIES ARE IN THE RANGE OF 1/3 -
2/3 FT/S.
THIS VELOCITY IS T00 SMALL TO
, QUICKLY ELIMINATE STRATIFICATION.
l l
t
4 177 FA PLANT SURGE LINE CCNFIGURATION f
\\
Spray Line Pressuizer v :I-Q Heaters
%'8" m
\\
)
I e
A N/
f E
13' 5
6'7" b
>,3c l' 3" O
33' 6"
=
z
,[
{
w e
N t.
-s.
O 1.
\\
Reacter g
Vessel
SURGELINE-DATA MUELHEIM-KAERLICH:
STRAIGHT PIPE: OD = 19.3" T=
1.8" ELBOWS: OD = 19.8" T=
2.0" MATERIAL: X10 CR HI TI 189 (1.4541)
(STAINLESS STEEL)
B&W 177FA PLANTS:
STRAIGHT PIPE: OD = 10.75" T=
1.0" ELBOWS: OD = 10.75" T=
1.0" MATERIAL: SA-376 TYPE 316 S.S.
. _=
COMPARISON OF SURGE LINE CONDITIONS PLANT PIPE DENSITY PLANT CONDITION DIAM.
LB/FT3 UPSET HEATUP BYPASS M-K 15.7" 37.0 FL6W (La/s) 2000 10 0.12 VEL. (Fr/s) 40 0.2 0.002 RE. #
1.12 E9 5.6 E6 7.0 E4 177FA 10" 37.0 FLOW (La/s) 2000 10 0.121 VEL.
(FT/s) 99 0.5 0.006 RE. #
1.85 E9 9.2 E6 1.1 E5 i
i i
i
)
1 i
i 1
i i
tiOST RECENT 177FA PLANT CONFIGURATI0B STRESSES AND CUMULATIVE USAGE FACTORS l
o RESULTS FOR RECENT (1982) SURGELINE ANYALSIS o
ANALYSIS BASED ON ASME SECTION III, SUMMER
{
1979 ADDENDA i
o STRATIFICATION NOT CONSIDERED o
CUMULATIVE USAGE FACTORS BASED ON 360 HU/CD I
CYCLES (40 YEARS) o MAXIMUM PRIMARY & SECONDARY STRESS RANGES:
110DE 68: S = 30 KSI (STRAIGHT) j N0DE 105: S = 57* KSI (ELB0W)
NODE 148: S = 37 KSI (ELBOW)
ALLOWABLE
= 3SM = 50 KSI
- SIMPLIFIED ELASTIC-PLASTIC ANALYSIS PERFORMED o
HAXIMUM CUMULATIVE USAGE FACTORS:
NODE 68: U = 0.53 NODE 105: U = 0.55 ALLOWABLE = 1.0 N0DE 148: U = 0.16 N0DE 149: U = 0.57 SEE FOLLOWING FIGURE FOR LOCATION OF NODES
m------_
e q
28 p
I a
b$gh{
S g\\ L -.,
g f
~
\\
1 s
,N f
L% S'Mb
\\
=
I l
%j j
5 q
v m
E I
5 5
- 4 f
E e
f
?
/
~
a z
o e
o 2
i
)
o t
O
(
- u 5
\\
E
\\
\\@E o
9
=O J
46
/
12h
/
e
_ j aE
?1 t
- b-u xe, Y
e
IMPACT ON CURRENT OPERATION 0
IF STRATIFICATION EXISTS, IT WILL OCCUR IN HORIZONTAL PIPE RUN 0
SINCE POINTS OF MAXIMUM FATIGUE USAGE (AT N0ZZLE CONNECTIONS) ARE LOCATED IN OR NEAR VERTICAL RUNS, NO ADDITIONAL STRESSES WILL BE INDUCED AT THESE LOCATIONS DUE TO CIRCUMFERENTIAL TEMPERATURE GRADIENTS 0
ADDITIONAL BENDING MOMENTS AT N0ZZLES DUE TO STRATIFICATION IN HORIZONTAL PIPE RUN WOULD HAVE TO BE CONSIDERED, BUT MARGIN EXISTS TO ACCOMMODATE THESE l
)
O MAXIMUM USAGE FACTORS CALCULATED BASED ON 360 HEATUP/C00LDOWN CYCLES O
NO B&W 177FA PLANT HAS UNDERGONE MORE THAN ~
120 HU/CD CYCLES S0 THAT ACTUAL FATIGUE USAGE IS LOW t
I 0
MORE DATA IS NEEDED T0 QUANITFY THE IMPACT ON f
OPERATION l
l r
i
B844 PH AS E 1_
SUMMARY
0 THERMAL STRATIFICATION FOR THE B&W PLANTS IS POSSIBLE.
0 THERMAL CYCLES ARE MORE FREQUENT THAN IN ORIGINAL DESIGN.
O THERMAL CYCLES IN SURGE LINE ARE DIRECTLY REl.ATED TO PRESSURIZER LEVEL CHANGES.
0 FLUID MOTION OCCURS PREFERENTIALLY IN THE UPPER HALF 0F THE SURGE LINE.
O SURGE LINE FLUID WILL RESTRATIFY AFTER A LARGE SURGE.
0 THERMAL CYCLING MINIMIZED BY:
AUTOMATIC STEAM PRESSURE CONTROL CLOSE PRESSURIZER LEVEL CONTROL j
SEQUENCE OF EVENTS DURING HU/CD i
1 i
,n-~_
i l
OBJECTIVES OF PHASE 2 INSTRUMENTATIOP l
DETERMINE THE MAGNITUDE AND EXTENT OF POSSIBLE STRATIFICATION BY INSTRUMENTING THE OCONEE-1 PRESSURIZEK SURGELINE 1
RELATE HEATUP/C00LDOWN EVENTS TO PRESSURIZER N0ZZLE i
USAGE FACTOR COMPARE RESULTS TO THE REACTOR COOLANT SYSTEM (RCS)
FUNCTIONAL SPECIFICATION DETERMINE THE NEED FOR ADDITIONAL STRESS AND FATIGUE ANALYSIS, IF NECESSARY DETERMINE THE NEED FOR MODIFICATION OF OPERATIONAL l
PROCEDURES DETERMINE IF MODIFICATIONS TO THE TRANSIENT CYCLE LOGGING PROGRAM ARE NECESSARY
PflASE 2
- SU9tCE LINE INSTRUNENTAT*ON SC?tEDUIE FOR OCONEE 1
/98 9/es 10/Ra 11/94---------------------- /AR S
12 1/89 2/89 3
/99 4/89 5/_29 6/n? 7/89 8/89 9/89_---------------------------
/h9 12/89 10/89 11 1.0 rretent.
preparation 2.0 in itication en 3.0 Pretest setup 4.0 Data acepsinition 5.0 Evaluation 6.0 Final report 1
j
SP?.W L!NE v
l PRESSURizET:
eme X
(_M'R5 I
/
4' 2
e e
Z l
=
c 5
i ! 3" l
i._
~
/
\\
E W vg
. w
/
ue e
/
+'g,' 4 0
g i
FTE u!
,17 GENERATOR
/
Z NH
'.k o>..
'y le
(,
i hs 4.
fN w
y}s x
3
- 5 k
?c
/
.s.
e j'
! 3'
,r
[
2 f
e
~.
?
5 e
x 6
N 5
4
'n'.
67~
Y g
~.
N
\\ v,,
i s
II
\\
e s
z i
5,
\\
Il \\
10'4" X
.'4 REACTOR j
VISSEL je Thermocouple = #
Chosen from Tyr es E..'.K s r.4 i Total: 20 locations.
[ph.,3]
E,7
.M e j [s s !k! 5 f jJ.Jdj4 s e IEU z es oz a g,-+ e HO o .o jg g u [ 1'111111.;35 !E .v 3' [
==
i, 2 o PD .Eoj? O E '5 \\ r}/ [g t 2 _ n..__.- r <g e.=- 65 6.f 1 Z-1 H k L I \\ { E 'n Z (j r; N li L.O, % g$E "g,
- 3 e :
g 5 .?*E* r b R ."h g E Y8 34k O }. O DU { He s e n - o.e = I.a (+ J c' N e 8 t '" "4 t v a s 2 e e $viO M U I t'"I 2 2*2l l
- 5 g 3:
E 1 a .E a& 2 y w< c r o H1 (_) "g S., Wz (4 z E 1 s s-s] >8 _O s,, g e --.) $ 'g' c: 's 2 6 5 = Ub A$ 1 05 = 1 E O 3 D a W (U q.. R.- E 5 E o y n [ w 2 U g( 2 al s 0; d i U ~~ ui$t v! q .S' p< w s F N; gg eo e 'n e,R;; e* d :/ i 3 o i r Iu eY m r 1 V yQ v'> Je / m k' i m W E 18 6 O B1? l i o_ I
i ANTICIPATED PHASE 3 ACTIVITIES PERFORM STRESS AND FATIGUE ANALYSIS BASED ON THERM 0 COUPLE DATA UPDATE STRESS ANALYSIS i IF NECESSARY, MODIFY FUNCTIONAL SPECIFICATIONS AND TRANSIENT LOGGING GUIDELINES i IF NECESSARY, RECOMMEND REVISIONS TO PLANT OPERATIONAL PROCEDURES IF NECESSARY, RECOMMEND ENHANCED IST, l I t l i i r l l i i
i
SUMMARY
COMMENTS ? e f o WHEN INFORMED ABOUT THE GERMAN PLANT DATA, i B&WOG INITIATED A PROGRAM. o SOME ROUGH CALCULATIONS HAVE BEEN PERFORMED BASED ON WHAT WAS SEEN AT MK. \\ o MAIN CONCLUSION FROM THE ANALYSES WAS THAT ACTUAL PLANT TEMPERATURE DATA WAS NEEDED. o A DATA COLLECTION PROGRAM WAS OUTLINED. l IMPLEMENTATION IS PLANNED FOR EARLY 1989. o DATA EVALUATION WILL START IN 4/89. o FINAL RESULTS SHOULD BE AVAILABLE ABOUT 9/89. o A FOLLOW ON PHASE HAS BEEN TENTATIVELY DEFINED IF NEEDED. l
DEST /EMEB/EMTB 9/21/88 QUESTIONS FOR OWNER'S GROUPS ON SURGE LINE (1) History of impact or contact of surge line with pipe whip restraint!.. (2) History of surge line support damagt. [ (3) History of 151 (hDE) results of the surge line ano any history of cracking. (4) Surge line material, diaw ter, and well th'ickness. (5) Difference in piping lay out end its effects on thermal stratification. (6) Operational (startup, shutdown, norr41 operation, accidents and transients) i
- delta T" between the hot leg and the pressurizer.
(7) Availability of measured data (temperature, dit, placement, etc.) of the i surge line and whether measurements are sufficient to determine stratifica-tion and thennal striping effects. (8) B&W(GermanPlantData)-Muelheim-KaerlichStation. t (9) Availability of analysis based on measured temperature data. L l - (10) Maximum calculated stress and location. l (11) CUF at end of life with and without accounting for therral stratification and thermal striping. l (12) Sumary of allowable operational cycles in the technical specification. i (13) Sumary of allowable operational tire at r.aximum ' delta T". 1 (14)Operationalchangesthatcouldmitigatetheeffectsofsurgt line strat- [ ification, j (15) Plan of action to adoress surge line stratification causes and effects. f (16) Feasibility of using L6B on plants that have already been granted LES on this surge line. l I ? i t
l [ 9. l l IPC/B8WOG MEETIhG ON THERMAL STRATIFICATICh IN THE PRES $URIZER SURGE LINE j SEPTEMBER 29, 1966 I l l E B&WOG T. Chan D. Sibiga - Combustion Engineering i L. Marsh S. Sharron - SERCH/Bechtel P. Kuo L. Connor - Doc - Search Associates i S. Hou R. Evans - NUMARC l C. Cheng it. 01esnavich - Babcock and Wilcox l K. Wichran J. Shepard - Fabcock arid n'ilcox l J. Richardson J. Taylor - Babcock and Wilcox S. Lee G. Hau - late 11 Corporation D. Terac
- 5. Morgan - Impell Corporation i
K. Er.cleston K. Wilson - Florida Power & Light i G.DeGrassi(ENL) M. Haghi - Duke Power Corpany i P. Jensen D. Whitaker - Cuke Power Corpany C. Liang R. Deese - Duke Power Compa9 N. Kadarbt R. G*adonski - Toledo Edison Company i H. Balukjier. t t i i l i l f ) .}}