BVY-94-110, Transmits Addl Info Concerning Fracture Mechanics Evaluations Performed to Support Alternative Insp Interval Re Feedwater Nozzle
| ML20078G855 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/08/1994 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-94-110, NUDOCS 9411160212 | |
| Download: ML20078G855 (45) | |
Text
' V$RMONT YANKEE NUCLEAR POWER CORPORATION
.vp Ferry Road, Brattleboro, VT 05301-7002 mm h ( ./
ENGINEERING OFFICE 500 MAIN STRET BOLTON MA 01740 (508) 779-6711 November 8,1994 BVY 94-110 United States Nuclear Regulatory Commission ATI'N: Document Control Desk Washington, DC 20555
References:
- a. License No. DPR-28 (Docket No. 50-271)
Subject:
Feedwater Nozzle Inspection Relief Request Vermont Yankee is currently required to perform a liquid penetrant examination of the feedwater nozzle inner radius during the 1995 Refueling Outage. A relief request was submitted to the USNRC pro)osing an altemative inspection technique (Reference (b)]. On August 30,1994 a meeting was he d with USNRC staff to discuss the relief request. At that meeting we were requested to clarify cenain aspects of the inspection and qualification plan. In addition we were requested to provide additional information conceming the fracture mechanics evaluations performed to support the attemative inspection interval. The purpose of this letter is to transmit the requested information.
Vermont Yankee will conduct a blind qualification test of the automated ID inspection technique using a nozzle mockup. The nozzle will be manufactured from similar material and have similar geometry to the Vermont Yankee reactor vessel feedwater nozzle (same nozzle bare ID and same inner radius geometry). Four axial fatigue cracks with crack depths enveloping the range of depths for qualification sizmg will be implanted into the mockup and then clad with stainless steel to reflect the actual condition in the reactor vessel. This will hide the implanted flaws from the qualification inspectors.
Following the blind qualification test the flaws will be ground to simulate the grindouts in the actual feedwater nozzles. Because of the depth of the implanted flaws some remnant flaws will remain. He automated ID inspection technique will again be demonstrated for detection and sizing capability.
He manual ultrasonic inspection technique from the OD of the nozzle to cover the area of the bore under the nozzle boss, taper and safe-end attachment region will be demonstrated on the existing feedwater nozzle mockup. This mockup contains axial notches in the nozzle boss and taper regions. Qualification of this technique will be based on industry accepted techniques for relating notches and actual flaws. This mockup and the inspection technique have been reviewed by USNRC Region I personnel in past ISI inspections.
De goal of the qualification testing is to be able to detect flaws that are one eighth inch or greater into the base metal. The goal of the sizing demonstration is to be able to size flaws covering the range of one-eighth inch to one-half inch into the base metal. Early technique development has confirmed these parameters.
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9411160212 941108 PDR ADOCK0500g1 f 8
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.wr VLRMONT YANKLL NUCLEAR POWER CORPORATION United States Nuclear Regulatory Commission November 8,1994 Page 2 The results of the demonstrations will be r: ported to the USNRC no later than December 31, 1994. We will inform the NRC of the dates for the qualification demonstrations to allow witnessing if desired. The Electric Power Research Institute (EPRI) hDE Center will act as a thini party proctor for the qualifications to maintain sample integrity and to confirm NDE technique adequacy.
Enclosure 1 to this letter shows the inspection volumes of the ID and OD inspection techniques, demonstrating the coverage required by NUREG-0619. We were also requested to provide documentation supporting our determination that a four cycle inspection interval is appropriate. The four cycle interval was established by conservatively estimating the number of expected transient cycles during the interval and calculating the flaw growth rate for a missed flaw one half inch deep into the base metal. The flaw growth during the four cycle interval was less than that required to reach the ASME Section XI maximum permissible flaw depth of one tenth the section thickness of the feedwater nozzle. The details of the evaluation are contained in Enclosure 2 to this letter.
We trust that this additional information proves sufficient for your staff to complete their review of our feedwater nozzle inspection plans, resulting in approval of our relief request. Since Vermont Yankee plans to apply this inspection technique during our planned Spring,1995 refueling outage, we request that NRC assign a high priority to completion of this relief request.
Should your staff require any additional information, please contact this office.
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION W .C . M '
e.
Leonard A. Tremblay, Jr., P.E. \4 Senior Licensing Engineer Enclosures I and 2 cc: USNRC Region I Administrator USNRC Resident inspector- VYNPS USNRC Project Manager- VYNPS
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ENCI OSliRF 2 1
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Supplemental Informatiott for Relief from NUREG-0619 Inspection Requirements Vermont Yankee Feedwater Nozzle Linear Elastic Fracture Mechanics Evaluation i
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VY UT Exam NUREG-0619 Table of Contents List of Sections:
I. Vermont Yankee Feedwater Nozzle Operating Cycles II. Design Transient Stress Information III. Fatigue Crack Growth Evaluation IV. Additional Fatigue Crack Growth Evaluations List of Tables:
Table 1. Feedwater Nozzle Fatigue Cycle Summary; Operating Cycles XIV, XV, XVI, XVII.
List of Figures:
- 1. Startup/ Shutdown Cycle Design Transient
- 5. Details of FEM - Blend Radius Region List of Attachments:
- 1. Detailed Feedwater Nozzle Fatigue Cycle Summary; Operating Cycles XIV, XV, XVI, XVII.
- 2. Transient Stress Informatien at the Blend and Bore Regions for the Startup/ Shutdown Cycle Design Transient.
Reference:
Letter James Pelletier to USNRC, " Request for Relief from NUREG-0619 Inspection Requirements", BVY 94-07, February ll, 1994.
Supplemental LEFM Information Page 2
VY UT. Exam NUREG-0619 1 I
vermont Yankee Feedwater Nozzle Operating Cycles Table 1 summarizes Vermont Yankee feedwater nozzle cyclic data over the past four operating cycles; XIV, XV, XVI, and XVII. This includes plant experience from September 1987 through August 1993.
This summary was compiled by Engineering with the assistance of senior Vermont Yankee Operations Department personnel. Plant operating logs, scram reports, as well as RPV pressure, reactor level, recirc temperature, feedwater flow, and feedwater :
temperature records were reviewed to quantify feedwater nozzle j startup/ shutdown cycling over the last four operating cycles.
Attachment 1 includes a more detailed summary by date and event.
Over the last four operating cycles there were 26 total startup ,
events. Feedwater flow remained on for all startup events. While j some of these events include full pressurization and heatup many of ,
these startups were from almost full pressure and temperature. The design startup transient (Figure 1), which assumes the reactor was -
hot during initiation of cold feedwater flow in conjunction with a full pressurization cycle, is a conservative envelope of Vermont Yankee operational startup transients over the last four operating '
cycles. Based on this recent experience, we have conservatively assumed there will be 35 startup/ shutdown cycles over the next four ;
operating cycles.
For the 26 shutdown events, 12 were normal shutdowns and 14 were scram related. Six (6) of the shutdowns were from low power where feedwater heating was never established. The design transient (Figure 1) which assumes a step reduction in feedwater temperature and flow conservatively envelopes the normal Vermont Yankee operational shutdown transients.
Following shutdown, during hot standby or during cooldown, the l operational data was reviewed to identify any feedwater flow off/on cycling. A total of 21 off/on feedwater flow changes was i identified over the four operating cycles for the A train. The B feedwater train had 30 off/on flow changes. The most common off/on flow events included:
i feedwater pump trip on high level following a scram, and
- RCIC injection tests after shutdown at low feedwater flow.
Other off/on flow events included:
- loss of feed flow due to loss of offsite power followed by HPCI and RCIC on/off injection.
The design transient (Figure 1) depicts five 0% to 25% off/on step flow changes per shutdown. 26 Startup/ shutdown design cycles I
Supplemental LEFM Information Page 3 l
VY UT Exam NUREG-0619 therefore include 130 additional on/off feedwater flow cycles. The Vermont Yankee operating data indicates that over 26 startup/
shutdown cycles Vermont Yankee axperienced only 30 additional feedwater cycles.
Based on our review of the feedwater transient data over the past four operating cycles, the Figure 1 startup/ shutdown design transient which includes 5 off/on flow changes per shutdown is a conservative representation of typical startup/ shutdown fatigue cycle loading.
Vermont Yankee will maintain a cumulative record of feedwater nozzle startup/ shutdown transient data between UT exams. We will evaluate the data against the design' transient to assess whether the thermal duty is enveloped by the design. transient. We will keep a cumulative count of startup/ shutdown and on/off flow cycles.
Supplemental LEFM Information Page 4
VY UT Exam NUREG-0619 II Design Transient Stress Information The NRC requested that Vermont Yankee supply transient stress information at the blend and bore regions for the design transient shown in Figure 1. The transient data depicts through wall stress distribution at the sections shown in the detailed section of the finite element model shown in Figure 5. Stress data for both low and high bypass leak cases are included. The stress data is presented in Attachment 2. Computer files are also included.
The computer codes used to generate the linear elastic fracture mechanics stress intensity values were modified to capture the requested stress information. Documentation and verification of the modified code was also performed.
Supplemental LEFM Information Page 5
.- -VY UT Exam NUREG-0619 ;
l 1
i III i Fatigue Crack Growth Evaluation )!
Upon review of Vermont Yankee feedwater nozzle transient data the l Figure 1 transient was selected as a suitable enveloping-transient -
for normal startup/ shutdown cycle counting as demonstrated above in Section I. :
1 Fatigue crack growth curves for this transient assuming an initial 3 1/2 inch flaw are presented in Figure 2. These curves were developed using the ASME XI crack growth law and the following linear elastic fracture mechanics stress intensity relation:
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K,(t) = [xa' [0.706 Co(t) + 0.537 (2a/x) C (t) + 3 i
2 3 0.448(a /2) C 2(t) + 0.393 (4a /3n) C 3(r)]
where:
a is the crack depth Co, C 3, C 2, C are 3 time dependent stress coefficients ;
The time dependent stress coefficients where developed with the following third order polynomial function to represent through wall hoop stress distribution at the bore and blend sections:
o(x, t) = Co (r) + C (r) x + C2 (r) x2 + Ca (') I*
3 Both x and crack depth are measured from the inside surface.
In this relief request, we have proposed performing a more detailed .
evaluation of transients and performing additional crack growth !
evaluations if the number of startup/ shutdown cycles exceeds 35 cycles. As demonstrated in Section I, the Figure 1 transient is a -
conservative representation of typical startup/ shutdown fatigue ;
cycle loading. As shown in Figure 2, in 35 startup/ shutdown design cycles a 0.50 inch initial flaw would grow to less than 0.56 inches, much less than the 0.823 inch ASME XI allowable flaw size.
An alternate fracture mechanics evaluation was run using a startup/ shutdown transient which included, 30 hot standby off/on. i feedwater injections assuming a 3350 F RPV/feedwater temperature differential and 10 cooldown off/on feedwater injections assuming a 2000 F RPV/feedwater temperature differential.
Supplemental LEFM Information Page 6
VY UT Exam NUREG-0619 This transient is not easily applied to cycle counting. There are far too many assumed hot standby and cooldown cycles to apply this transient to each plant startup/ shutdown event.
On 8/30/94 this crack growth curve was pres,ented as a conservative crack growth curve for the Figure 1 design transient. Upon further evaluation, the 8/30/94 curve was found to b9 an overly conservative representation. The Figure 2 curve was specifically developed from the Figure 1 design transient and should be used as the representative curve for comparison when performing evaluations.
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Supplemental LEFM Information Page 7
VY UT Exam NUREG-0619 IV Additional Fatigue Crack Growth Evaluations A more detailed evaluation of transients and additional crack growth evaluation will be performed in the following cases:
Startup/ shutdown cycles are projected to exceed 35 cycles prior to the next scheduled UT exam.
Additional feedwater on/off cycles are projected to exceed 175 cycles (5 x 35) prior to the next scheduled UT exam.
The Figure 1 design transient cannot be used as a conservative representation of an operating transient.
In the event that conservative crack growth projections based on conservative estimates of pre-existing flaw size and fatigue loading could approach the ASME Section XI (by analysis) allowable flaw size within the four cycle inspection interval, the inspection frequency will be adjusted accordingly.
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Supplemental LEFM Information Page 8 )
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VY UT Exam NUREG-0619 ,
Table 1 (Page 1 of 2) . .
Feedwater Nozzle Fatigue Cycle Summnry; Operating Cycles XIV, XV, XVI, XVII.
SUMMARY
RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS SCRAM SCRAM, HTG HTG FLOW FLOW FLOW. FLO_W PERIOD DATE SU SD SD ON OFF ON OFF ON OFF CYCLE XIV 10/87 TO 2/89 8 3 5 6 6 6 6 7 7 CYCLE XV 4/89 TO 8/90 4 2 2 3 3 3 3 4 4 CYCLE XVI 10/90 TO 3/92 12 5 7 10 10 10 10 16 16 CYCLE XVII 4/92 TO 8/93 2 2 0 3 3 2 2 3 3 TOTALS 10/87 TO 8/93 26 12 14 22 22 21 21 30 30 l
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VY UT Exam NUREG-0619 Table 1 (Page 2 of 2) .
Feedwater. Nozzle Fatigue Cycle Summary; Operating Cycles XIV, XV, XVI, XVII. ,
I Definitions ,
(Also applicable'to Attachment 1 detail cycle summary) !
- 1. SU: Startup cycles include startup events ranging from startup from cold shutdown through heatup and power ascension i to startup from hot standby and power ascension.
- 2. Non Scram SD: Non scram shutdown cycles include operator controlled power reductions to hot standby or to cold shutdown.
i
During heatup and at low power feedwater is at approximately ,
condenser temperature. At approximately 15 to 20% power extraction steam'is routed to the feedwater heaters and l feedwater heating is established. Table 1 and Attachment 1 :
indicate for each startup event whether feedwater heating was established and whether feedwater heating was on when each shutdown event was initiated.
- 5. A/B-Train Nozls On/Off Cycles: Feedwater train on/off flow l cycles. Normally feedwater flow is continuous during heatup, normal operation, and cooldown. Table 1 and Attachment 1 indicate events during heatup, hot standby, or cooldown when feedwater flow was interrupted and reinstated.
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. VY UT Exam NUREG-0619 Figure 1 (Pg 1 of 2) . Startup/ Shutdown Cycle Design Transient Reactor Pressure 1600-1400-1200-1025
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VY UT Exam NUREG-0619 l
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NUREG-0619 VY UT Exam ,
Figure 2. Feedwater Nozzle Crack Growth; Startup/ Shutdown Cycle Design Transient FEEDWATER NOZZLE CRACK GROWTH DESIGN CONDITIOt4 (fig 1) 0.7 0.69 p
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l Supplemental LEFM Information Page 13
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VY UT Exam NUREG-0619 Figure 3. Vermont Yankee Feedwater Nozzle Geometry l
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-VY UT' Exam. NUREG-0619
' Figure 4. Finite Element Model(FEM) for. Vermont Yankee Feedwater Nozzle E
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-VY UT Exam NUREG-0619 j Figure 5. Details of FEM - Blend Radius Region l
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2 12 ction Used for Bore Region l NP Maximum Blend Radius Section Supplemental LEFM Information Page 16 i
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s VY.UT Exam NUREG-0619 Attachment 1.
-Detailed Feedwater Nozzle Fatigue Cycle Summary; operating Cycles XIV,'XV, XVI, XVII.
Supplemental LEFM Information
FW HEATING RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR l SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON- OFF ON OFF LEV 10-2-87 HEATUP/STARTUP 1 12%
10-3-87 SCRAM 1 1 1 12% l 1 1 10-3-87 COOLDOWN 10-3-87 HEATUP/STARTUP 1 1 46%
10-6-87 RECRC PMP TRIP 10-7-87 RECRC EMP TRIP MANUAL
FW HEATING RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION 4
i FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW Ph%
, DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
__________ _____________________ _______ _______ _______ _______ __ _ - _ _ _______ _______ - =__ ______ _______
i, i 11-8 c7 REACTOR SCRAM 1 1 1 1 87%
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1-30-88 RECRC PMP TRIP MANUAL 50%
4-30-88 RECRC PMP TRIP MANUAL 52%
i FW HEATING <
RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION a ____--- _____-- -__________--- ______- -----__ --
FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV 6-18-88 SCRAM 1 1 1 1 100%
1 1 6-19-88 heatup startup 1 1 100%
'i-24-88 SCRAM 1 1 1 1 100%
1 1 6 .'5-88 COOLDOW w e --
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FW HEATING RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES ~
SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE SvMiARY NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFE ON OFF ON OFF LEV l
7-2-88 HEATUP/STARTUP 1 1 55%
7-3-88 SHUTDOWN FROM 55% TO 1 1 55%
7-3-88 SCRAM AT LOW PWR 1 1 1 1%
1 1 1
7-8-88 STARTUP 1 1 98%
8-24-88 SHUTDOWN /COOLDOWN 1 1 100%
8-26-88 HEATUP/STARTUP 1 7%
l FW HEATING RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES f SHUTDOWN CYCLES CYCLES DURING OPERATION .
2 FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW Ph"A DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
__________ _____________________ _______ _______ _______ _______ _______ _______ _______ _______ _ _ _ =__ _______
i
'i 8-27-88 SHUTDOWN /COOLDOWN 1 7%
i 8-28-88 HEATUP/STARTUP 1 1 100%
i 10-29-88 RECRC PMP TRIP MANUAL 50%
2-11-89 SHUTDWN/RCIC/COOLDWN 1 1 100%
1 2
-O EW HEATING v RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW ELOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
_. --------.------------ ------- _------ - - - - - -----_- ------- ------- --- =- -
1 2 TOTALS CYCLE XIV 8 3 5 6 6 6 6 7 7 l
i i
1 i
I I >
I l
l l
FW HEATING '
RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION
-----------------_- ------- ------- ------- - --- ------- ------ - - - . =_ - = _ -------
FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TFAIN NOZLS -APPR ,
SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV f
f i
4-L-89 HEATUP/STARTUP 1 1 100%
r L
?
t 3-16-90 SHUTDOWN /COOLDOWN 1 1 100%
1 1 1 1 3-19-90 HEATUP/STARTUP 1 8%
Lm._________2. - - _ _ - - ____e__ + _ _ _ _ _ _ _ m ---nw w --4a*-r n* hm+-4--i w- w - .+-was , -+- -4 *. .-_-_ _ '-__s -
m_ __r___
e FW HEATING $
RPV/FEEDWATER STARTUP- CN/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW Ph%
DATE EVENT SU SD SD OII OFF ON OFF ON OFF LEV 3-21-90 SCRAM 1 8%
3-25-90 HEATUP/STARTUP 1 1 100%
6-1-90 SCRAM / HOT STANDBYe 1 1 1 1 100%
1 1 6-2-90 STARTUP 1 1 100%
8-31-90 SHUTDOWN /RCIC/CLDWN 1 1 100%
1 2 1 2
FW HEATING RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PhR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV TOTALS CYCLE XV 4 2 2 3 3 3 3 4 4 4
9
. . ~ , - . .. .-
-. . - .. . - , . . c _
o FW HEATING -
RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES' SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV 10-15-90 HEATUP/STARTUP 1 1 100%
4 11-4-90 SCRAM 1 1 1 1 94%
1 1 11-5-90 HEATUP/STARTUP 1 1 100%
+
3-13-91 SCRAM /COOLDOWN 1 1 2 2 100%
2 2 i
3-17-91 HEATUP/STARTUP 1 LOW l
3-17-91 SHUTDOWN /COOLDOWN 1
FW HEATING '
RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES
- SHUTDOWN CYCLES CYCLES DURING OPERATION i __________ _____________________ . - - - - - - - - _______ _______ _______ _______ -- ---- _______ _______ _______ _______
FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS D-TRAIN NOZLS APPR j SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR t
DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
_______ _______ _ __ i.
i-i 3-18-91 HEATUP/STARTUP 1 1 100%
! i i
4-23-91 SCRAM /RECIRC TRIP 1 100%
1 1 1 1
1 1 ,
4 1
1
t 4.
FW HEATING s-RPV/FEEDWATER STARTUP- -ON/OFF' -ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR T
SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV s
b i
t a
1 -l 1
f-1 1
c 1
4 r
1 i ,
1 ,
L i
i E
i
FW HEATING
- RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
JON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
__________ _____________________ _______ _______ _._____ _______ _______ _______ _.._____ _______ __ _=
1 1 t
4-30-91 HEATUP/STARTUP 1 1 100%
6-15-91 SCRAM 1 1 1 1 100%
l 1 1 '
l i
I t
_ _ _ _.- _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ - e _ - - 4 _.___m i------_______________ _____.____
, a _a m a ., ,,, - , -_ . - - - - - - - - - - - - - - - , - - , - - - - - - - - - - , - - - - - - - - - - - -
FW HEATING RPV/FEEDWATER STARTUP- CN/OFF ADDITIONAL FEEDWATER CYCLES l l
SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PWR DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV 6-21-91 HEATUP/STARTUP 1 1 100%
7 I
I 9-8-91 SHUTDOWN /COOLDOWN 1 1 100%
9-15-91 HEATUP/STARTUP 1 1 100%
1-16-92 SHUTDOWN / STANDBY 1 1 5%
1 1-16-92 STANDBY /STARTUP 1 1 100%
s
FW HEATING RPV/FEEDWATER STARTUP- CN/OFF ADDITIONAL FEEDWATER' CYCLES SHUTDOWN CYCLES CYCLES DURING OPERATION
- - - - _ . ------- -- = _ = - - ----- - _ - _ - - - - -----
FEEDWATER NOZZLE SL'MMARY NON FW FW A-TRAIN NOZLS- B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLON FLOW FLOW PWR SU SD SD ON OFF ON OFF ON OFF LEV DATE EVENT
- - - = - - - _. ------- . - - ------- ------- _ _ - - - ,
3-6-92 SHUTDOWN /COOLDOWN 1 5%
1 1 2 1 2 l
l t
e
.____m
_ _mm_.-..m_ _ _ _ _ _ _ , _ , m._ _.m._ m__ _ _ _ _ _ _ _ __ .m_____
FW HEATING .
4 RPV/FEEDWATER STARTUP- ON/OFF ADDITIONAL FEEDWATER CYCLES t SHUTDOWN CYCLES CYCLES DURING OPERATION FEEDWATER NOZZLE
SUMMARY
NON FW FW A-TRAIN NOZLS B-TRAIN NOZLS APPR SCRAM SCRAM HTG HTG FLOW FLOW FLOW FLOW PhR ;
4 DATE EVENT SU SD SD ON OFF ON OFF ON OFF LEV
, 4-19-92 HEATUP/STARTUP 1 100%
1 1
1 4-7-93 SHUTDWN/RCIC/COOLDWN 100%
1 1 1 2 1 2 4-16-93 HEATUP/STARTUP 1 1 100%
8-27-93 SHUTDWN/RCIC/COOLDWN 1 1 100%
RCIC TEST, TOOK 3 MIN 1 1 l
1 1 1
l CYCLE XVIT. 2 2 0 3 3. 2 2 ~3 3 TOTAL
VY UT Exam NUREG-0619 Attachment 2.
Transient Stress Information at the Blend and Bore Regions for the Startup/ Shutdown Cycle Design Transient.
The following pages include stress coefficient plots. Digitized data is included on the attached 3.5" floppy disk. Hard copy of the digitized data will be forwarded upon requested.
SUBDIRECTORY FILE NOZZLE LOCATION BYPASS LEAKAGE STRESSCO BOREHL.PRN BORE 15 GPM STRESSCO BLENDHL.PRN BLEND 15 GPM STRESSCO BORELL.PRN BORE O GPM STRESSCO BLENDLL.PRN BLEND 0 GPM I
l l
1 1
Supplemental LEFM Information
., VY UT Exam NUREG-0619 Bore.(Hegh Leakoge) 100 -
90 -
f ( ( f f 70 -
60 -
50 -
k.
, 40 -
I 30 -
f 20
- 'LLL*
3 o y h-i- _
Ahhhh WO FWh /
y ~10 -
V g -20 -
-30 -
l
-40 -
l l ff f
-50 -
5
~60 . . . . . . .
0 l 2 l 4 l 0 l 8 l 10 l 12 l 14 l 1 3 5 7 9 11 13 15 (Thousands)
Time (sec)
CO C1 C2 C3 !
i I
Blend (High Leokoge) 100 t 90 -
~
f f f f f 70 - , i 60 -
50 -
, 40 -
30 -
L u w L,,, wu _ ___
,Y 20 -
g 1, '
10 b
O o
['\ I\ $\ $\ }h, s a s -NN/\-r% j
$ -10 -
5 -20 -
-30 (" '
-40 -
f ( l ( f
-50 -
-60 r ,
O l 2 3
4 l 6 l 8 l 10 l 12 l 14 l 1 5 7 9 11 13 15 (Thousands)
Time (sec)
- co ct c:
c3 Supplemental LEEM Information
g*a VY UT Exam NUREG-0619 Bore (Low Leakage)
,; 60 50 -
\
K 7 r r i '
40 -
x 30 -
FY 20 -
gQv [
E 5 10 -
Iu O -b- U\r-O'6'A'r I\ I\ I\ I\
j
~
. -10 -
$ /
-20 --
/ j j j f
-30 -
-40 . r- , . -
0 l 2 l 4 l 6 l 8 l 1C l 12 l 14 l 1 3 $ 7 9 11 13 15 (Thousands)
Time (set)
CO C1 C2 i
C3 Blend (Low Leakoge) 60 50 -
c f 7
.- 40 -
, 30 -
e w L. L L_ t 20 -
G i
(o 10 .-
O
( (( ( L
^ '
\
i /
.E
- -to .-
V
-20 -
l f l l
-30 , , , , ,
12 l O l 2 ! 4 l 6 f 8 l 10 l 14 l 1 3 $ 7 9 11 13 15 (Thousonds)
Time (sec) cc ci c2 C3 Supplemental LEFM Information
, . - . - . . . _ - . - . - - - . _ _ - - . . . . _ - - . _ _ _ _ _ - _ ____ ____