IR 05000206/1993020
| ML13329A274 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/14/1993 |
| From: | Wong H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13329A273 | List: |
| References | |
| 50-206-93-20-MM, 50-361-93-20, 50-362-93-20, NUDOCS 9307260040 | |
| Download: ML13329A274 (51) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No /93-20, 50-361/93-20, and 50-362/93-20 Docket No, 50-361, 50-362 License No DPR-13, NPF-10, NPF-15 Licensee:
Southern California Edison Company Irvine Operations Center 23 Parker Street Drive Irvine, California 92718 Facility Name:
San Onofre Units 1, 2, and 3 Meeting at:
Region V Office Walnut Creek, California Prepared by:
B. J. Olson, Project Inspector Approved by:
_________________
H. Wong, Chief Date Signe Reactor ProjectsSection II Summary:
A meeting was held on July 1, 1993, to discuss the ongoing Unit 3 steam generator primary to secondary leak and plans for Unit 2 steam generator eddy current inspg'ctions. A copy of the slides used in the licensee's presentation is enclose '
PDR ADOCK 05000206 G
DETAILS Meeting Attendees Southern California Edison Company (SCE)
D. Rosenblum, Vice President, Engineering & Technical Services R. Waldo, Manager, Operations M. Short, Manager, Site Technical Services J. Clark, Manager, Chemistry G. Gibson, Supervisor, Generic Licensing J. Mundas, Senior Engineer, Nuclear Engineering Nuclear Regulatory Commission K. Perkins, Director, Division of Reactor Safety and Projects C. Serpan, Acting Deputy Director, Division of Reactor Safety and Projects C. VanDenburgh, Chief, Reactor Projects Branch H. Wong, Chief, Reactor ProjectsSection II W. Ang, Chief, Engineering Section J. Reese, Chief, Facilities Radiological Protection Branch M. Fields, Project Manager, NRR E. Murphy, Materials & Chemical Engineering Branch, NRR J. Winton, Materials & Chemical Engineering Branch, NRR C. Myers, Reactor Inspector B. Olson, Project Inspector Details Mr. Perkins provided opening remarks and indicated that the NRC was interested in SCE's assessment of the ongoing primary to secondary leak in San Onofre Unit 3 and the eddy current inspection program that would be conducted during the current Unit 2 refueling outage. Mr. Rosenblum provided opening remarks for SCE and indicated that, in general, SCE considered the steam generators at San Onofre to be less vulnerable to the tube flaws that have been recently observed at Palo Verde. He also listed the topics that would be presented: (1) Unit 3 steam generator primary-to secondary leakage, (2) Unit 2 steam generator eddy current inspection plans, and (3) a comparison of San Onofre and Palo Verde secondary characteristic Unit 3 Steam Generator Primary to Secondary Leakage Mr. Waldo reviewed the history of an ongoing Unit 3 steam generator primary to secondary leak. The leak was first observed on May 11, 1993, and initially stabilized at approximately five gallons per day (gpd).
The leak had slowly increased to approximately 15 gpd in the month and one-half period since developing. San Onofre's Technical Specifications require that primary to secondary leakage from one steam generator be limited to less than 720 gp Mr. Waldo explained that the most likely source of the leak was through a Westinghouse steam generator tube plug known as a plug-in-plug. This
design, of which there are 178 installed in the Unit 3 steam generators, incorporates a separate, internal plug and has developed leaks at other facilities. Westinghouse analysis indicated that the potential leakage past this type of plug is limited to approximately 15 gp Mr. Waldo provided an overview of the methods used to monitor the leakrate and the actions that would be taken if the leakrate increase He indicated that San Onofre uses activity measurements of the main condenser air ejector exhaust as the primary method for determining the leakrate. He also indicated that operating crews would perform a rapid plant shutdown if the leakrate increased by more than 60 gpd in one hou Unit 2 Steam Generator Eddy Current Inspection Plans Mr. Mundas described the steam generator eddy current inspection plan which will be implemented during the current Unit 2 refueling outag He indicated that 20% of the steam generator tubes will be inspected using an eddy current bobbin coi This sampling percentage follows recommendations from the Electric Power Research Institute and exceeds the Technical Specification minimum inspection requirements. In addition, about 500 tubes per steam generator will be inspected just above the hot leg side of the tubesheet using an eddy current motorized rotating pancake coil (MRPC). Mr. Mundas stated that San Onofre had previously only used the more sensitive MRPC to perform inspections of areas where anomalies had been observed in bobbin coil signal Mr. Mundas described the actions being taken as a result of axial indications that have been recently observed in Palo Verde Unit 2 steam generators. He indicated that Combustion Engineering developed a thermal-hydraulic model of the San Onofre steam generators, and the model was used to determine areas where deposits may form on steam generator tubes. The model was developed after Palo Verde observed axial indications associated with tube deposits. Based on an evaluation of the deposit parameters from the San Onofre model, additional tubes would be inspected using the MRPC. Mr. Mundas said that approximately 400 additional tubes in each steam generator would be partially inspected using the MRPC, although the final evaluation was not complete. In addition to changes in the scope of inspection activities as a result of the Palo Verde findings, Mr. Mundas stated that the training program for the eddy current analysts had been modified to use actual data from indications observed at Palo Verd Mr. Murphy stated that the bobbin coil could inspect long tube sections faster than the MRPC and commented that SCE might want to consider using the bobbin coil to inspect more full length tube sections and use the MRPC to inspect more tubes at the top of the tubesheet. Mr. Mundas indicated that SCE was confident that any existing flaws would be found by inspecting 20% of the tubes with the bobbin coil and that the MRPC would be capable of finding flaws in the early stages of developmen He added that the inspection plan would be evaluated if any flaws were found. Mr. Rosenblum said that SCE wanted a balanced perspective in
developing the inspection plan; to have reasonable assurance of finding an existing flaw using the bobbin coil and to find early indications of flaw development using the MRP Comparison of San Onofre and Palo Verde Mr. Clark provided a comparison of San Onofre and Palo Verde secondary operating characteristics. He described differences in steam generator and balance of plant designs. He also described San Onofre design features which contribute to maintaining low concentrations of impurities in the steam generator Closing Remarks Mr. Perkins thanked the SCE personnel and indicated that the presentations were very informative. He reiterated Mr. Murphy's comment that SCE might want to consider additional eddy current MRPC inspections in the steam generator tubesheet area. Mr. Rosenblum said that SCE was very sensitive to steam generator tube issues and would want to deal with any potential problems early. He added that Mr. Murphy's comment would be considere EFFLUENT WARRANTY VALUES (Continued)
1.3 Moderate Condenser Leakage (200 ppb Cl Influent)
Sodium 0.1 ppb (max)
Chloride 0.2 ppb (max)
Sulfate 0.5 ppb (max)
Copper 2.0 ppb (max)
Silica 5.0 ppb (max)
Cation conductivity @ 250C 0.10 PS/cm Straight conductivity @ 250C 0.10 PS/cm Total Suspended Solids 10.00 ppb (max)
Total Iron 10.00 ppb (max)
pH @ 250.5 to Run length 60 hr (mi)
1.4 Severe Condenser Inleakage (500 ppb Cl Influent)
Sodium 0.2 ppb (max)
Chloride 0.5 ppb (max)
Sulfate 1.0 pbb (max)
Copper 2.0 ppb (max)
Silica Cation conductivity @ 25*C.
5.0 ppb m
Straight'conductivity @ 250C 0.10 PS/cm Total Suspended Solids 10.0 ppb (max)
Total Iron 10.0ppb (max)
pH @ 250.5 to Run length 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (mx)
Steam Generator Inspection San Onofre Units 2 and 3
- Southern California Edison
SIGNIFICANT SONGS DESIGN FEATURES Steam Generator BlowdownlFeedwater Feedwater fed at the top of the shrou gpm/SG continuous and optimally located Seawater Typical Chemistry Chloride (ppm)
19,000 Calcium (ppm as calcium carbonate)
400 Sulfate (ppm)
2,650 Silica (ppm)
ad
FFCPD F-H
_W-4 I-I - 21-2-F3:2P-3 FL : 3 M 4-M -P-5---3, M26
6-2 I-_l-
-
il -
-M l-
- 4D
'-
S -L M 7 IF 6-MIIP i-M-i 3-a-4-(7-8 W--210~
-- N QN-N
-N
3-VP
4 W 4 2-(3-M 4~-M J
5-6N1P 621k1 -B-3& -I 4-MM-1 Paitial LIP05 I 2-4T 3-4 MU36
~
'uII 1J04 P0PH EG3
)TVhI _________f---
-
1O4998
SIGNIFICANT SONGS DESIGN FEATURES Full Flow Condensate Polishing Demineralizer (FFCPD)
Resin Fines Filters 5 u fines filters down stream of resin beds. No resin leakag *
Six lead CPs, removes all ammonia and sodium in condensat High sodium remova SECONDARY CHEMISTRY HISTORY
Steam Generator Hideout Data Unit 2 Unit 3 Cycle 4 Cycle 5 Cycle 4 Cycle 5 Sodium (gm)
66
80 Sulfate (gm)
210
106 Chloride (gm)
52
12 These values are within Industry averag *
Steam Generator Molar Ratios Unit 2 Unit 3 Cycle 4 Cycle 5 Present Cycle 4 Cycle 5 Present.9 0.74.3 1.23
Steam Generator Resin Intrusions Non SECONDARY CHEMISTRY HISTORY Typical Steady State Secondary Chemistry
Steam Generator SONGS EPRI RATIOS 199211989-1991 GUIDELINES GLISONGS Cation (uSicm)
0.0810.08
< Chloride (ppb)
0.31 <20 66.7/6 Sulfate (ppb)
0.11 < 20 20016 Sodium (ppb)
0.11 <20 20016 *
Condensate Demineralizer Effluent Chloride (ppb)
0.002 NA Sulfate (ppb)
0.010 NA Sodium (ppb)
0.003
<3 1000 Cation (uSlcm)
0.057
<.5
Condenser Leaks Leak detection @ 0.2 uS cat.con No significant leaks,corrective action taken immediately FFCPD in service to eliminate contaminants ingress to S SONGS SECONDARY SYSTEM CHEMISTRY HISTORY AND DESIGN FEATURES
SAN ONOFRE/PALO VERDE COMPARISON FACTORS AFFECTING SECONDARY IGA/IGSCC
- Operating Temperature (~ 532 deg F)
- Secondary Chemistry (Na ~0.1, CI ~0.3, S04 -0.1)
- Thermal Hydraulic Conditions (Maximum Quality 53%)
- Tube Proximity to Other Tubes (Three partial supports)
- Fabrication Defects/Scars (None identified)
- Tube Vibration (Effect not known)
BALANCE OF PLANT DESIGN DIFFERENCES Palo Verde San Onofre Condensate Polishing Demineralizers Mixed bed Lead cation only bed + mixed bed + resin fines fil Continuous Blowdown Capacity (gpm)
36 -
100 -
150 Cooling Water Processed Seawater
"gray" water +
cooling tower treatment Feedwater Heater Tubing Material Stainless Copper steel Nickel
STEAM GENERATOR DESIGN DIFFERENCES Palo Verde San Onofre Type:
U-tube U-tube Recirc Recirc C-E Model:
System 80 3410 MWt Number of Tubes:
11,012 9,350 Tube Diameter (in.)
0.750 0.750 Tube Wall Thickness (in.)
0.043 0.048 Tube Manufacturer:
Noranda Sawhill (Units 1 & 2)
Sandvick (Unit 3)
Tubing Material:
Alloy 600 Alloy 600 Annealing Temperature (degF):
1810-1850 1875 Tube Support Type:
Lattice Lattice Bar Bar Tube Support Material:
Stainless Carbon Steel *
Steel Number of Partial Tube Supports
3 Special Features (Palo Verde):
o Drilled stainless steel flow distribution plate o Feedwater preheater (economizer) on cold-leg side
-
Affects blowdown flow/concentrations o No handhole access to tubesheet o High capacity blowdown (short term)
Special Features (San Onofre):
o Handhole access to tubesheet
Except for "scallop bars"
SAN ONOFRE UNIT 2 STEAM GENERATOR INSPECTION SAN ONOFRE/PALO VERDE COMPARISON
- Steam Generator Design Differences
- Balance of Plant Design Differences
- Factors Affecting Secondary IGA/IGSCC
- Water Chemistry
SAN ONOFRE UNIT 2 EDDY CURRENT TESTING PLAN EDDY CURRENT TESTING IMPROVEMENTS
- Improved MRPC Probe Signal Amplitude
- Optimized Combinations of Probes/Frequencies
- All MRPC Data to be Plotted on C-Scan
- C-Scan Plots Use Doubled Amplitude
-Steam Outlet Nozzle Steam Dryers Steam Separators Secondary
..-
Manway ett Feedwater ra.Feedwater Spargr
--cNozzle Snubber Lug Tubesheet Primary Inlet Nozzle
.,,Primary Outlet Nozzle FIGURE 1. SCHEMATIC OF SONGS 2/3 STEAM GENERATORS
KEPARATOR DCc-26 FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ
=23 TOP OF U-NENi 3E01IO9
---
(323 TO 338 IN. ABOVE TUBESHEET-HOT SIDE)
7I PARTIAL EOOCAATII
-
MAX. VALUE;.
1.000 ECOS
________7 FULL fOOCRA7ECIC0-C0
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FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ = 22 TOP OFU-IEWO EOIO4-
-
(308 TO 323 I ABOVE TUBESHEET-HOT SIDE)
PARTIAL lOaCRAIII MAX. VALUE:
0.888 nc$,
FULL EGOCRA____E___EC
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REPAATOE DICK
FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ = 21 TOP OF O-IfIXO NE81O-.K-(297 TO 308 IN. ABOVE TUBESHEET -HOTSIE PARTIAL EOOCRATIS It MA VALUL;.
0.878 EC17
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FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ
=20 TOP OF U-11EMO OEIM (287 TO 297 IN. ABOVE TUBESHEET -HOT SIDE)
PARTIAL 190CRATIO
[Cos
________I MA VALUIE:
0.887 EO
______________
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BEPAATOR DECK I
FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ =19 TOP OF U-winO 11010-"
(277 TO 287 IN. ABOVE TUBESHEET -HOT SIDE)
24___ __
tell______
IF________
PARTIAL [OOCIAISI
- Is ECU 17_______
MAX. VALI5E:
0.991 E-
___
___
FULL ZOOCRAYEI -
IE______
________
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______________
-
DowNCOuMtER EIO
I!
0. 2
............. BOPARAICK DECO
FIGURE
SONGS 2/3 SG DEPOSIT PARAMETER AT IZ = 6 TOP OF 11-1010 REGIOK-i--
(63 TO 81 IN. ABOVE TUBESHEET-HOT SIDE)___
PARTIAL EOOCRATfS(R512 ice?_________
MA VALUE.:
0.883 ECOS
_______
It ECOI Dowlicamck~-
bSilo-- _________
0.__
0.2I 0.3S
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SEPARATOR HOT SIDE COLD SIDE DECK
7
5
4
TOP OF2G
U-BEND
REGION
25Ir EC10 V
ECO8
~1 ECO7
ECO6~
144 EC05 ECO4
.
ECO3 ECO2E EC01
0.0~
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Mi
012 FIUR
1 D OE OE 0 3/3 S
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DEPOSIT PRR T I>
41 ECIY
FIUR 7 DOWNOMEROPENNGLE0 SONG 2/3SG -OEPOIT P~nN.AT I
0.51
SEPARATOR HOT SIDE COLD SIDE DECK
7
8
3 274
TOP OF
3
U-BEND25 IX 2
REGION
DO5WXN
24
23
1 2 3 4 56 7 8 9
1
20
EC08
07 5
ECO7
77 0.20 ECO61404
2
2 FIGURE 6 ECO4
1z OWNCOMER OPENING 3I IONGS 2/3 SGI
-
fEPOSIT PARFI AIT IX<
'1 FINf 11
SEPARATOR HOT SIDE COLD SIDE DECK-28
27
10 TOP OF
3
U-BEND 2X 2X12
REGION
1
78
Mi21 EC9
18
iE C ECO3 224
13
.
11 0.76
Lul 0. L 2004
7
5
3
DOWNCDMER OPENING 21I FIGURE
SON[S 2/3 SG -
DEPOSIT PARFIM. AIT IX<
A AND
SEPARATOR HOT SIDE COLD SIDE DECK28
27
10 TOP OF
/
U-9END 25 IX 2
REGIONr
13
14
1 2 3 4 6 7 8 9 E9
IY
20
ECO81
O
ECO7
0. 2
0. 3 0. 1 ECO
Ol.I4
O.5
Eon~
ECOS
0. 7 ECO4 0. 9 101 EC
.....
9 ECO3
ECO25
EC0 1
2 FIGURE
DOWNCOMER OPENING 1 IZ SONGS 2/3 SG
-
DEPOSIT PARAM. AT IX<
2 AND 13
S!PARATOR HOT SIDE COLD SIDE
.DEC2K
t
'**
TOP OF
.U-9END REGIO I
EC1 O91
......
1 2 3 45 6 7 8 ECO1 ECO7
,.
12ECO2
10
14Z ECOG 0.91
.
ECO
DOWN OMER OPENING 1I
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DEPOSIT PRAM EC23
16
12 DOW~rnMER PENIN I11 ONGS '-./3 S
OEPSITPAR ATIX 1ANO10
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SEA4TO DECSID 2_
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1_
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Ix________
SPLAERAT Et-21 ECID 223_______
PARTIALA ECOCRATETI20 FIOUE 2 ATHS I MODL C THESAMOMOFE 9EAM EMEA is
SAN ONOFRE UNIT 2 EDDY CURRENT TESTING PLAN EDDY CURRENT TESTING IGAlIGSCC PROGRAM GOALS
- Use Best Available Eddy Current Test Techniques
- Indentify Mid-Span /Tube Support IGA/IGSCC
- Quantify/Maximize Signal/Noise Ratio
- Identify Detectable Deposits
.
Establish Baseline for Future Inspections
..SAN ONOFRE UNIT 2 EDDY CURRENT TESTING PLAN FACTORS AFFECTING SECONDARY IGA/IGSCC Operating Temperature
- Secondary Chemistry Thermal-Hydraulic Conditions
- Tube Proximity to Other Tubes S4'
- Fabrication Defects/Scars
- Tube Vibration
,6/93, SOUTHERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 2 STEAM GENE ATOR: 88 DATE: 06/29/93 PROC: SO23..XXVII-2 TIME:
18:24:18 MRPC EXPAt4 ION NUMBER I CRITERIA: iUBES TO BE EXAMINED IN GROUP (S) 13, 14, 15, 16. 17. 18. 19. 20 STAYS
- .
PLUGGED
1288
DBH-VG'
4 101-VHl
- CPH
?
.
~INLET VE
13 0 101
50
'10'
20
40
60
f0
100 110 120 130 1 40
!50 tO 170 CONAM NUCLEA IN OW
-6/93, SOUTHERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 2 STEAM GENEFVATOR: 88 DATE: 06/29/93 PROC: 5023.XXVII-2 TIME:
11:56:51 CRITERIA: *T'UBES TO BE EXAMINED IN GROUP(S) 1,2.3.4, STAYS A
MULTIPLE 319 t:X 140
£10
LA 0 G
Y 2G
.30 410 bO0 s
7k0
/0 D
90 c3-10)
120 130 14LC
C)
iG Ic
.*sCONAM NUCLEA IN W
06/93, SOUTHERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 2 STEAM GENE ATOR: 88 DATE: 06/30/93 PROC:
S023- (XVII-23. 1 TIME:
13:18:06 CRITERIA:.*1BES TO BE EXAMINED IN GROUP(S) 11, 12 STAYS PLUGGED 261;.*
Groupti 260 +
MULTIPLE O**
INLET VIEW NOZZLE 140 -140 130
_130 110------
-
-
120 90 -90
-80 70 -
-
--
60
-
-60
--
40
30-30
20 10-
.
20
40
50
so
100 11o 120 130 140 150 iso 170 CONAH NUCLEAR IN W
06/93, SOUTHERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 2 STEAM GENE TOR: 88 DATE: 06/30/93 PROC: SO23 (XVII-2 TIME:
13:14:37 CRITERIA: TU8ES TO BE EXAMINED IN GROUP (S) 1, 2. 3. 4. 5, 6 STAYS A
PLUGGED 269 4 Groupi 424
V GrouP3 705 *
Group4 337 *
GroupS 20 +
GroupS
- NULTIPLE
.)K INLET VIEW NOZZLE 1 40 -
-
-
--
-
.-
-
-
-
-
-
1 4O 130
-
---
130 120 110 --
100 --
-
-
90-9-
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70 -
--
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60 ---
50
40 --
30-30 20 --
10
--
is
20
40
s0
80
too 1o 120 130 1o40 i50 io 170 CONAM NUCLEA INC. E3W
SAN ONOFRE UNIT 2 EDDY CURRENT TESTING PLAN BASES FOR EDDY CURRENT TESTING PROGRAM
- T chnical Specifications-3%
+ prior > 20% indications
- EPRI Recommendation-20%
- T, p of Hot Leg Tubesheet (MRPC)
- 500 tubes/SG c PWSCC Secondary IGA/IGSCC
- P.lrofilometry
- 100 tubes/SG
- Mid-Span/Tube Support IGA/IGSCC
-
under development 1*,
Steam Generator Status (con't)
S02 S03 Tubes Plugged 614 555 Improper Annealing
24 Batwing Wear 460 459 Vertical Strap Wear
9 Loose Part Wear
15 Tie-Rod Denting
6 Pre-Service
35 Other Causes
7
- *
team Generator Status S02 S03 Tubes Installed 18,700 18,700 Tubes Plugged 614 555 Tubes In Service 18,086 18,145
F E :
SIDE VIEW OF SONGS, UNITS 2 AND 3 FIGURE 1:
SISTEAM GENERATORS S team D Cc steam Dryers moisture Separators (TYpical)
.-
.
Steam Wrapper Generator rappe
~~Shell Feedwater InlIe t
--
Nozzl Feedring Noz Support Distribution U
/
Box Feedring Secondary Side Primary Side
SAN ONOFRE UNIT 2 STEAM GENERATOR INSPECTION EDDY CURRENT TESTING PLAN
- Steam Generator Characteristics/History
- Bases for Eddy Current Testing Program
- Factors Affecting Secondary IGA/IGSCC
- Preliminary Detailed Inspection Plan
- Eddy Current Testing Improvements
SONGS 2E0s8 TUBE LEAK 3 /1 /88
..
L) ct-z I NMonlh by Days 100 Divsions 5th, 1 0th Accent r-4-I t~ J
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t~
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GRP PAERFrmou_____-P~ok
STEAM GENERATOR T-UBE LEAKS Leakage (GPD)
Air Ej. (CPM)
- 10 0 0 00
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TIME (MINUTES)
-Maine Yankee
+Miarna
- 2 Indian Point 3
RESPONSE TO INDICATION OF TUBE LEAKAGE (SO123 - III - 2.22.23 & S023 - 13 - 14)
M BLOWDOWN is sampled every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Air Ejector is sampled once per wee M Upon indication of tube leakage Chemistry leak rate determinations increase to every 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Upon exceeding 10gpd leakage, Chemistry leak rate determinations increase to dail *
Upon reaching the Air Ejector Alarm Setpoint (30 gpd) Operations begins logging RE-7870 reading M If RE-7870 indicates leakage has increased by more than 60gpd in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, verify the monitor response is real and sustained (by checking blowdown). If valid, then commence a rapid shutdown at 1% to 5% power per minut *
For large leaks we would utilize our EOls. A Mihama
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.type.f tube.rupture. vent.was run last year i generator within 32 minute t*.
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AIR EJECTOR MONITOR 3-7870 ACTIVITY 1. R 8E - Ll 3
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t ST EAM GENERATOR TUBE LEAKAGE MONITORING LOCATION TYPE FREQUENCY LLD (AT Current RCS Activity)
1Air Ejector Monitor Continuous
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1 gpd Air Ejector Alarm Continuous 30 gpd Air Ejector Grab Weekly
~ gpd-3Blowdown Monitor Continuous 5 gpd
.Blowdown Alarm Continuous
"1 000 gpd Blowdown Grab Every 72 Hours
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1 gpd
- Steamline N-16 As needed (new)
1 gpd
- Steamline Monitor Continuous
"3000 gpd
- Feedwater Tritium As needed 0.3 gpd
Upit 3 Tube Leakage - Likely Causes
. W tube plug - 178 PIP's installed in Unit 3 CE tube plug Tie-rod denting Vertical strap or batwing wear
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PRIMARY TOUEODA-v LEAK iAsiTi 30 CPD MAY /JUNE 1993i/c 25....................................................................................
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Q. S/li 5/18 5/25 6/1 6/8 6/15 6/22 6/29 a HC'TWELL F:EC!
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E '_-727l i~ UNIT 3
Vulnerability Assessment Secondary Chemistry less vulnerable Thermo-Hydraulics less vulnerable Tube Support Structure less vulnerable Operating Temperature less vulnerable
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enda Introduction Unit 3 Steam Generator Tube Leakage Leakage Progression Suspected Cause Operational Capabilities Unit 2 Steam Generator Inspection Background Inspection Program Comparison of PVNGS and SONGS Mechanical and Plant Design Chemistry Program Summary