ML20024C575
| ML20024C575 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Crystal River, Rancho Seco, Midland, Crane  |
| Issue date: | 05/05/1978 |
| From: | Ohanlon J METROPOLITAN EDISON CO. |
| To: | METROPOLITAN EDISON CO. |
| References | |
| TASK-*, TASK-03, TASK-3, TASK-GB GPU-2030, NUDOCS 8307120827 | |
| Download: ML20024C575 (7) | |
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jf METROPOl.lTAN EDISON COMPANY s-., a w. um. e B&W USERS G't0UP MEETING 9 MAY 1978 TMI Nuclear Station g
Lassdes Middletown. Pa.
Det.
May 5. 1978 r.
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OTSG TUBE PROGRAM - (Don Montcomery) 1.
Most Likely causes:
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a.
Metal fatigue di.e to flow unduced vibration
'b.
Mechanical wear c.
Liquid impingement erosion I-6M d.
Corrosion pitting l,
h.fl8 2.
Contributino Factors:
a.
Generator Feature 1.
Aux FW nozzles 2.
Inspection lane: Path for moisture to get to upper part of GT3G.
leads to chemical deposits 3.
Shroud bypass b.
System Oesian 1.
FW line length: Langth of line not cleaned up on startup 2.
Staan line configuration: Possible influence on pressure esci11ation 3.
FW heating capability and oxygen control: Affect capability of hydrazine to reavenge oxygen (Oconee problem) c.
Plant Operation 1.
Turbine stop valve tasting: Power level and frequency of tasting 2.
Bypass of condensata domineralizer: Minimiza 3.
Auxiliary FW syster operation 4.
Water hassner 5.
Steam generator layup
, 3.
88W OTSG Procram a.
Sita inspect 1on b.
Sita tasting c.
Review of operations d.
Sastple evaluation e.
Manufacuring review f.
Laboratory review g
INTER-OFFICE MEMORANDUM
.. _ ~
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Bal/ Users Group Meeting.'
9 May 1978 Page 2
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g.
Analytical programs.
h.
Chemical cleaning studies Nota: B&W has completed their study of the TMI-1 OTSG orifica plate measurements. B&W is satisfied that the orifica plata could have been closed. B&W will forward study results to Met-Ed. (Barley) 4.
Site Insoections a.
Eddy Current Inspection b.
Profilameter Inspection c.
Visual Examination d.
Deposit Analysis e.
FW Analysis 5.
Results of Oconee 2 a.
Max vibration amplitude was.050" b.
thK5 tress was 5000 psit well within fatique limit c.
No significant tube displacement duiing turbine stop valve tasting d.
Approximatley 71 incr in steam flow during turbing stop valve testing e.
External accelerometer quiet except for water hammer on startup ~
~~
- 6. TMI-II Procram a.' $2 million project 7.
Review of coerations a.
Operating history b.
Procedure review c.
Site comparison studies d.
Procedura modifications t
8.
Possible Mechanical Fixes a.
UT3E tube stiffeners, some being tasted b.
Fix to block the lane at 15th TSP (looking at some other levels also) 8.
SECONDARY SIDE WATER CHEMISTRY - (Merl Bell)_
1.
Hot Functional Testino c
a.
0f38 feedwater pH 9.3-g.5 for carbon-steel FW Systes
~
8.5-5.3 for non-carbon-steel FW System i
Cation Conductivity 0.5 umho/cm max
{t Hydrazine 20-100 ppb max e
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B&W Users Group Meeting, 9 May 1978 Page 3 i
Total Iron as Fe 100 ppb max Dissolved Oxygen as 02 7 ppb max Total Copper as Cu 2 ppb max Silica as 5102 20 ppb. max b.
0758 Water
. Cation Conductivity 10 sho/cm max Sodium as Na 2 ppu max Chlorida as C1 1.0 ppe max 2.
Normai power coerations
- a. Of5G FW Soecs Total Solids 50 ppb max Cation Cond
.5 Dissolved 02 7 ppb max..
N2H4 20-100 ppb max 5102 20 ppb max Fe 10 ppb max C1 2 ppb max pH 9 77F 9.3-9.5 Pb
__ 1 ppb max l
b.
Start Un (Prior to feedino OTSG's)
Total Fe 100 ppb max l
Cation Cond 1.0 umho/cm max l
Dissolved 02 100 ppb max General Comnent: Chemistry control for B&W plants in 1977 was poorer taan in previous years. B&W service manager will contact the plant superintendent with specific connants (O'Hanlon) ~
- 3. m Of5E Water pH 9.5 to 10.5 NH3 10 ppe nominal 2 to 20 ppe N2Hf 200 ppe initial 50 ppa sin Sodium 1.0 ppe max Cation Cond 10 unho/cm max 9
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S&W Users Group Meeting.
9 May 1978 Pa'ge 4 4.
On shutdowa return moisture separator drains to the hotwell in order to prevent buildup of contaminants in the OTSG. Contaminants come from the wet steam. washing the pipes and turbine.
+
8
- 5. TMI-l's practice of returning two moisture separator drains to the hotwell approximatley 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> each day is good., Keeps contaminant levels low.
6.
Nedd to look at sulfate in Powdex effluent. (FrederickcallM. Bell)
C.
OTSG LEVEL CONTROL DURING HEAT Up - (Al Cobb)
~
1.
Probles a.
88W operating procedures require FW nozzles to be flooded during 4
startup. (388") for seal welded FW nozzled.
1 b.
Standard TS specify 0738 level (348" Max)
- c. TMI-1. TMI-2. 08-1. Midland i
JNo: David Besse perfomed a reanalysis which showed that they
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could startup with flooded FW nozzles.
I 2.
Possible Consequence J
a.
N nozzle lifetime may be shortened.
Condition Nozzle Excected Lifetime i:
1850F Nozzle Flooded 40 Yrs.
i 1850F Nozzle Not Flooded Approx. 40 Yrs.
900F Nozzle Flooded 40 Yrs.
N 900F Nozzle No,t Flooded Not Analyzed 1
1 Os REFUELING EXPERIENCE - (Jim Phinney) o 1.
81W Refuelinos Units 13 i
.j Avg Work Activities 2.000 s
Avg Manhours 150,000 I
AvgExposure(ManRam) 234
.},
Avg Manpower 200 above norisal station staff' i
Avg Cost
$4.5 Million i
a 1
1 a..; m.x-k:u a -L = - 1.
- 3. _- :. m -
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I B&W Users Group Meeting.
9 May 1978 Page 5 2.
Refuelino Outace lengths AMO-I 55 TMI-1 46 Oconee II 94 Oconee I 72 Rancho Seco 78 Oconee III 44 3.
ANO Eddy Current Insoection: A-215. B-95 E.' BPRA - (Jim Phinney) 1.
Chronolooy 2/17/78 - Constant LPM alans from B-0TSG. Secured 1 RCP
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2/18/78 - Noise data taking. Confirmed loose parts in 8 075G 2/19/78 - Decided to continue operation for approximatley 2 weeks 3/3/78 - Unit shutdown 2.
Soider Assently a.
Comon to both 8PRA; and ORA's b.
Ball lock assently c.
Balls were through top of female coupling F.
CRYSTAL RIVER 3 - (Guy Beatty)
'1.
Core Support AssembTy to be installed 5/8/78.
2.
Reload without BPRA's, replace all SPRA's except 8 with ORA's, other 8.
nothing 1
3.
Dumped deep beds in lieu of regenerating I
4.
Initial repairs to be completed and startup by July 4th 5.
Follow on repairs during a subsequent outage 6.
Initial detection difficult because:
5 Initial power level was 701 FP because of condensate pump problems a.
b.
Plant was in transient condition Indications of a core tilt; then 8ailey 855 went out of service for c.
j a while i
d.
Frequent indications and alarms of noise on loose parts monitor (frem
.j probe on RV head CR0 guide tube). Operator believed alarms were due to electrical noise due to system sensitivity.
j RCP Bentley-Nevada indications thoughf. to be electrical noise; j
e.
alanns discounted e
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'84W Users Group Meeting.
~
9 May 1978 Page 6 f.
Replaced MU filters frequently, thought resin was causing the high filter dp.
Revizw of RCS r'diochemistry showed a long tem buildup of g.
a zire activity.
gfa,, Hindsight shows that items c through g above told CR that something was wrong. What would TMI operators have done?
~
1.
CRD ratchet trip fii* failed last' week.
'2.
Replacingall'snubbersinRC(except4RCPsnubbers)with mechanical snubbers.
3.
RB polar crane drips oil and grease.
H.
OCONEE - (J. Ed Smith 1
- 1. ' Unit 3 - three RCP operation; tilt is reappearing
~
2.
Better prepare for primary to secondary leaks a.
Line from air ejectcr to. unit -vent monitor b.
Resin /Powdex disposal various secondary plant leaks - pumps.
valves flanges c.
FPC will send out a itst of items they have done d.
Call Oconee to get list of items they have done (Kunder) e.
3 gpa leak: Took 3 months to determine which 075G; not able to detect which tube 3.
CRD Problems a.
4 stator failures in 6 months b.
fuse failures r
t 4.
Low RCP oil alams on Oconee 3; cause unknown 5.*
Plagued by high R8 activity; causes a several day delay after shutdown before R8 entry is possible.
6.
Plan to go to 18 month cycle on all three plants.
E d
J.P. O'Hanlon g,
G. Hertain unit 1 Superintendent L.L. Lawyer.
G.P. Miller Department Heads Lead Engineers Superintendents
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