ML19274D380
| ML19274D380 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/16/1979 |
| From: | Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| IPN-79-1, NUDOCS 7901230278 | |
| Download: ML19274D380 (14) | |
Text
F L
I POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMaur CIRCLE NEW YORK. N. Y.10019 (212) 397 6200 TR U STEE S GEORGE T. BERRY FREDERICK R. CLARK AND CHIEF ENG NEER LEWIS R. BENNE GEORGE L. ING ALLS MANAGER-GENERAL VICE CHAIRM AN COUNSEL RICH ARD M. FLYNN WILB U R GRONBER ROBERT l. MILLONZI
"*"#"I"""'""'"*
M""Y M' DD
"" TiREC1ofo",
wiLuAM r. LuooY IPN-79-1 Powra cara*Tio"*
THOMAS F CCRANN.JR.
Darrell G.
Eisenhut Assistant Director for Systems & Projects Division of Operating Reactors U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Steam Generator Operating History Questionnaire Indian Point #3 Nuclear Power Plant Docket 286
Dear Mr. Eisenhut:
The enclosed Steam Generator Operating History Question-naire with attached supplementary Information is being submitted to you in response to the February 10, 1978 letter from Karl R.
Goller, Assistant Director for Operating Reactors.
Very tru
- ours, l}f
/LQ
/
Pau e Early Asst Chief E gineer-Projects
/
Enc.
1 0 5
\\
\\
790123CA78 i
ENCLOSURE STEAM GENERATOR OPERATING HISTORY QUESTIONNAIRE NOTE:
All percentages should be reported to four significant figures.
I.
BASIC PLANT INFORMATION Plant:
Indian Point Unit No. 3 Startup Date:
Initial Criticality:
4/6/76 Utility:
Power Authority of the State of New York Plant Location:
Buchanan, New York 10511 Thermal Power Level:
3025 MWth Nuclear Steam Supply System (NSSS) Supplier:
Westinghouse Electric Corp.
Number of Loops: 4 Steam Generator Supplier, Model No. and Type:
West., Series 44, Vertical, U-bend.
1 Number of Tubes per Generator: 3260 Tube Size and Material:
Inconel 600:
0.875" outside diameter 0.050" wall thickness II.
STEAM GENERATOR OPERATING CONDITIONS Normal Operation Temperature:
Primary Secondary 0
0 Thot (SGin)= 600.4 F Feedwaterin = 427.2 F 0
513.8 F T
(S out) =542.6 F Steam
=
cold out Tavg = 571.5 F Primary Flow Rate:
34.05x106 lb/hr per S.G.
Allowable Leakage Rate:
1 gpm (total primary to secondary).
500 gpd max, for any single S.G.
Primary Pressure: 2235 psig Secondary Pressure:
755 to 780 psig Accidents:
Design Base LOCA Max.
Delta-P:
1600 psi (sec.to pri.)
Main Steam Line Break (MSLB)
Max. Delta-P:
1600 psi (pri. to sec.)
III.
STEAM GENERATOR SUPPORT PLATE INFORMATION Material:
SA-285, Grade C.
Design Type:
Drilled Plate Design Code:
ASME Section III Dimensions:
9'8" diameter; 0.750" thickness.
Secondary Flow 6
Rate:
3.315x10 lb/hr per S.G.
Tube Hole Dimensions:
29/32" Flow Hole Dimensions:
11/16" IV.
STEAM GENERATOR BLOWDOWN INFORMATION Frequency of Blowdown:
Continuous Normal Blowdown Rate:
10 gpm per S.G.
Blowdown Rate w/ Condenser Leakage:
Up to 30 gpm per S.G.
depending on water chemistry.
Chemical Analysis Results Control Results Chemistry Parameter Limits 8.8 pH @ 25 C 8.5 - 9.01 0.15 Free Hydroxide as ppm CACO 3 2.0 Total Conductivity umhos/cm
( 4. 0
@ 250C
.05
(.05 Chloride, ppm
<.1 Sodium, ppm NH3, Ppm N/A Dissolved Oxygen, ppb N/A 2, Ppm N/A SiO N/A Suspended Solids, ppm 1 To be maintained with hydrazine at sea and brackish water s i te s,
e Not tested for per IP3 Tech Specs.
V.
WATER CHEMISTRY INFORMATION Secondary Water Type of Treatment:
AVT (All Volatile Treatment)
Effective Full Power (EFP)
Days of Operation:
504.9 EFD (as of June 16, 1978)
Typical Chemistry or Impurity Limits:
Same as blowdown Feedwater Impurity Limits:
AVT - Normal Power pH 8.8 - 9.2 Total Conductivity (4
umhos/cm e 250c Ammonia 4 0.5 ppm Hydrazine 02
+
.005 ppm 02
<5 ppb.
Condenser Cooling Water Typical Chemistry or 7
Impurity Limits:
Saline Estuary Demineralizers - Type:
Do not have condensate polishing.
Cooling Tower (open cycle, closed cycle or none):
None VI.
TURBINE STOP VALVE TESTING (applicable to Babcock & Wilcox (B&W)
S.G.
only)
Not applicable.
VII.
STEAM GENERATOR TUBE DEGFADATION HISTORY (The following is to be repeated for each scheduled ISI)
Inservice Inspection (ISI) Date:
June 16, 1978 Number of EFP Days of Operation Since Last Inspection:
504.9 FPD This was first ISI since commence-ment of commercial operation.
(The following is to be repeated for each steam generator)
Steam Generator Number:
31 32 33 34 Percentage of Tubes Inspected at this ISI:
0.450%
0%
8.957%
8.957%
Percentage of Tubes Inspected at this ISI That Had Been Inspected at the Previous Scheduled ISI:
- NONE, FIRST ISI Percentage of Tubes Plugged Prior to this ISI:
NONE Percentage of Tubes Plugged at this ISI: 0.092%
0%
0%
0%
Percentage of Tubesl Plugged That Did Not Exceed Degradation 4
Limits:
SEE ATTACHED LETTER Percentage of Tubes Plugged as a Result of Exceedance of
' Degradation Limits:
NONE, SEE ATTACHED LETTER Sludge Layer Material Chemical Analysis Results:
Sludge Lancing (date):
June 12, 1978 Ave. Height of
)
Sludge Before
)
Eddy current examination was performed Lancing:
)
after sludge lancing.
See Table I
)
for volumetric analysis.
Ave. Height of
)
Sludge After
)
Lancing:
)
Replacement, Re-tubing or other Remedial Action Considered:
(Briefly Specify None necessary.
Details)
Support Plate Hourglassing:
None Support Plate Islanding:
None Tube Metallurgical Exam Results:
None, done.
TABLE I TUBESHEET CLEANING
SUMMARY
SHEET Plant:
Indian Point Unit #3 Outage Dates:
6/12 - 6/20/78 Prelance Post Lance
~
PEEEent~
S/G Sludge Volume Sludge Volume Removal Comments 31 24.8 Gal.
O Gal.
100%
Return Water from 518 lbs.
O lbs.
S/G Visually Clear.
32 24.8 Gal.
2.1 Gal.
92%
Return Water from 518 lbs.
43.2 lbs.
S/G Visually Clear.
33 33.1 Gal.
2.1 Gal.
94%
Return Water from 692 lbs.
43.2 lbs.
S/G Visually Clear.
34 35.2 Gal.
6.3 Gal.
82%
Return Water fron 734 lbs.
130 lbs.
S/G Visually Clear.
/
7.
1 l.
's.
i Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF 11/;16/78 s
Percentage of Tubes Plugged Other Preventive Measures i
See accompanying letter.
I,
' Hastage/ Cavitation Erosion AS OF.6/16/78 l
t Hot: Leg:
(Repeat this inforeation for the cold leg on Combustion Engineering (C.E.)andWestinghouse(W)EG.)
a b
c d
e Area of Tube Bundle (1)
% of Tubes Affected by 1
Wastage / Cavitation Erosion n.
7
% of Tubes Plugged Due to o
Exceedance of Allowable a
Limit (2)
M
'I
% of Tubes Plugged That I
Did not Exceed Degradation 0
Limit n
i Location Above Tube t
0 'I Sheet (3) i A
Max. Wastage / Cavitation Erosion V
Rate for Any Single Tube j
(Tube Circum. Ave) (Mills / Month)
A L
Max. Wastage / Cavitation Erosion A
in Any Single Unplugged Tube B
(Tube Circum. Ave) (Mills)
I E
Crackin9 AS OF 6-/16/78 Caustic Stress Corrosion Induced in C.E. and W S.G.
Flow Induced Vibration Caused in B&W S.G.
I e
o I
j-s i
.7 1
Cracking (Con't)
SEE ACCOMPANYING LETTER.
2
},
ROI Leg:
(Kepeat this information for the cold leg on C.E. and E S.G.)
II)-
f Area of Tube Bundle a
b c
d e
% of Tubes Affected l
By Cracking l
i
% of lubes Plugged Due to l
Cracking l
1
% of Tubes Plugged That Did l
Not Exceed Degradation Limit e
e l
Location Above (3)
Tube Sheet i
Rate of Lest ay F-Leaking tracks (gpm) n 1
~
(Repeat this information for the cold leg on C.E. and E S.G.)
Area of Tube Bundle (1) a b
c d
e 9
% of Tubes Affected by i
Denting I
% of Tubes Plugged Due to I
Exceedance of Allowable Limit (2) i j
% of Tubes Plugged That
,,. g Did Not Exceed Degradation Limit Rate of Leakage From Leaking Dents (gpm)
Max. Denting Rate for Any Single Tube (Tube
' Circum. Ave) (Mills / Month)
Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills)',
o e
'W" ee
. I Denting (Con't)'
j Support Max. Denting in Any Single
% of Tubes Affected By Plate Tube in Bundle Area Denting in Bundle Levels (Tube Ave) (Mills) (1)
Area a
b c
d e
a b
c d
e 1
2 3
l 5
l l
6 j
8 r
9 8
10 11 12 l
I i
i r;(
O 1
]
4 Pr -
- .i.a
'~
.I I
~
C TABLE KEY s
NOTE: All percentages refer to the perce'nt of.the tubes within a given area of the tube bundle.
t (1)
Area of the Tube Bundle No. of Tubes Within the Area i
a.
Periphery of Bundle
~t (wi/20 rows for B&W; wi/10 rows for C.E. and W) l l
SEE ACCOMPANYING b.
Patch Plate LETTER (wi/4 rows) c.
flissing Tube Lane (B&W only) l (wi/5 rows) c.
FlowSlotAreas(C.E.andWonly)
. i/1_0 rows).
w d.
Wedge Regions (C.E. and W only)
(wi/S rows) c.
Interior of Bundle (rcmainder of tubes) 1 l
(2) i Allowable Limit for Wastage / Cavitation Erosion:
i Allowable Limit For Denting:
(3) l.
Specifies area between the tube sheet and the first support plate 2.
Specifies in the following locations: (listtheadditionallocations)
Wastage / Cavitation Erosion:
Cracking:
I O
9 p-
. LO:-
VIII. SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS None DATE SUKMARY (Include event description; unscheduled ISI results, if performed; and subsequent remedial actions)
IX. CONDENSER INFORMATION See attached. letter for details.
Condenser Tube Leakage Detectable Detection Material Date Rate (gpm)
Limit Method Admiralty nominal
'lX10-5 gpm IIelium Mass Brass l
Spectrometry X
, RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Dosage (Man-Rem)
Repair Dosage (Man-Rem)
Comments 6/12/78 19.5 Man-Rem for ISI 2.7 Man-Rem Explosively to 5.7 Man-Rem for plugged 3 tubes 8/9/78 Sludge lancing in #31 S.G.
33.8 Man-Rem for S.G<
mechanical modi-fications made to secondary i
side 12/12/78 4.5 Man-Rem Explosively plugged 1 tube
~
in #33 S.G.
i
i j
-11 "
SEE ACCOMPANYING LETTER i
XI. DE3RADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR WHICH THE RESULTS OF TWO OR MORE I
ISI'S ARE AVAILABLE If the results for ten tubes are not availabic, specify this infor-mation for all those tubes for which results are available.
(repeat the following information for each tube and degradation type)
Steam Generator No:
Tube Identification:
Type of Degradation:
(specify denting, wastege, cavitation erosion, caustic stress corrosion cracking, or flow induced vibration cracking)
I (repeatthefollowinginformationchronologicallyforeachISIfor
^
which results are available)
.I ISI Date:
Amount of Degradation:
(specify amount and units)
EFP Honths of Operation Since Last ISI for Which Resuits are Given:
e 0
g e
w...
INDIAN POINT 3 UNIT STEAM GENERATOR OPERATING HISTORY SUPPLEMENTAL INFORMATION Tube sheet cleaning was performed on all four steam generators during the period of June 12, 1978 through June 20, 1978.
Based on water balance result, an average of 92% of the sludge was removed on all four generators.
During the period of July 17, 1978 through July 26, 1978 eddy current testing was performed on steam generators 33 and 34 to inspect the tubes as part of the Inservice Inspection Program.
Approximately 292 tubes in each generator were inspected, amounting to approximately 8% of the total amount of tubes in both steam generators.
This was the first Inservice Inspect
>n performed since commencement of commercial operation of the unit.
There were reportable eddy current indications noted in any of the tube no walls.
However, dent " indications" were observed at the tube to support plate intersection in approximately 90% of the tubes in-spected.
The probe used had a frequency of 400 KHZ and the size was 700.
As a result of being able to pass a 700 size probe through
=
all tubes, it was not possible to ascertain whether the " indications" 7
were due to manufacturing / metallurgical flaws or the " denting phenomena" currently being experienced with most Westinghouse steam generators.
the location of the indications suggests the latter as the
- However, more likely mechanism.
A further evaluation of this data is being conducted; however, the results are not available at this point in time.
On August 7, 1978 while installing a tube line blocking device in steam generatcr #31, a welder inadvertently struck an arc across 3 tubes.
Fifteen tubes in the vicinity of the subject tubes were examined by eddy current testing.
All tubes showed denting similar to that noted in steam generators 33 and 34.
One of the subject tubes was found to be leaking, but all others showed no reportable indications.
As a precautionary measure, the three subject tubes were plugged.
Therefore, the three plugged tubes indicated on the history questionnaire were not plugged due to degradation from denting.
An increase in radioactivity was noted while performing the steam generator blowdown analysis for No. 33 steam generator on December 8, 1978.
Based on the activity levels, it was determined that approximately a 0.24 gpm primary to secondary leak existed in The unit was taken out of service and eddy current the generator.
examination performed to determine the location of the leak.
One tube in the generator was found to be leaking.
Its location was Row 44, Column 56 in steam generator No. 33.
Examination confirmed that the defect was located at the second tube support.
This particular tube was examined during the first Inservice Inspection eddy current examination and was found to have a dent indication at this particular location at that time.
The tube was plugged on December 12, 1978 and the unit returned'to service.
No further leakage has been detected to date.
Regarding item IX on the history questionnaire, we have experienced approximately six leaks in the condenser prior to August 10, 1978.
Since August 10, 1978 to date we have, however, experienced substantial leaks (approximately 100) in one particular waterbox.
The cause is unknown at this point in time, but is being analyzed.
Steps are immediately taken to plug any failed tube, even if the leakage is nominal.
It is hoped that this supplemental information is of use to you and aids in understanding the data submitted in the history questionnaire.
D.
a e
t