ML19322A256
| ML19322A256 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/28/1979 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GQL-0186, GQL-186, NUDOCS 7903050325 | |
| Download: ML19322A256 (10) | |
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/ METROPOLITAN EDISON COMPANY 2 smim,u cazm m. ac um m,- ; cont. s. r e.
f POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 February 2$ 1979 TELEPHONE 215 - 929-3601 GQL 0186 Director of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 Steam Generator Operating History No. 2 Enclosed please find our second completed questionaire concerning steam generator operating history. Should you have any questions concerning this response, please contact R. O. Barley at Three Mile Island Nuclear Station.
incere ',
.i J.
. Herbein Vice President-Generation
(
JGH:DGM:Jdp Enclosure p
1 6
\\g 7903050 3a5 P
~
.1 ENCLOSURE 1 STEAM GENERATOR OPEPATING e
HISTORY QUESTIONNAIRE no. 2 l
fi i'
NOTE:
All percentages should be reported to four significant figures.
I.
BASIC PLANT INFORMATION Plant:
T,hree Mile Island - Unit 1 Startup Date:
2 September 1974 i
e U '.i1i ty:
Metropolitan Edison company Plant Location:
Middletown, Pennsylvania Thermal Power Level:
2535 MWT j
Babcock & Wilcox
}
Nuclear Steam Supply System (NSSS) Supplier:
i Number of Loops:
2 e
Steam Generator Supplier, Model No. and Type:
3&w,.gfA,0730 J
Number of Tubes Per Generator:
15, 531 g
0.625" o.D./o.03h" vall e
}
Tube Size and Material:
56' 2 3/8" Ingonel i
II.
STEAM GENERATOR OPERATING CONDITIONS f
l r
Normal Operation Prim.
Sec.
,1 l
Temperature:
602.8 F/570 F Flow Rate: 65.6 x 106 g /5.3x106 MAllowable Leakage Rate: 1 gpm / 2 Steam Generator)
HR HR Primary Pres 3bre: 22uo psia
)
Secondary Pressure: 925 psia l
Accidents Design Base LOCA Max. Delta-P:
925 psia l
tiain Steam Line Break (MSLB) Max. Delta-P: 2200 psia q
l III.
STEAM GENERATOR SUPPORT PLATE INFORMATION i
e atedal:
Carbon Steel Design Type:
Broached opening SA-212-B Design Code:
i i
Dimensions:
118 3/8" Diameter h
Flow Rate:
5.3 x lo Tube Hole Dimensions: =0.320 in. min. radius / tube
[
Flow Hole Dimensions: =0.135 sq. in./ tube
{.
i i
l
.:. IV.
STEAM GENERATOR BLOWDOWN INFORMATION Frequency of Blowdown:
Not Required Normal Blowdown Rate:
NA Blowdown Rate w/ Condenser Leakage:
NA Chemical Analysis Results:
NA Results Parameter Control Limits NA NA V.
WATER CHEMISTRY INFORMA$ ION Secondary Water Type of Treatment and Effective Full Power (EFP) Months of Operation:
Ammonia and Hydrazine added to feedvater - Powdex polishing 32 EFPM Typical Chemistry or Impurity Limits:
Ammonia 2-20 ppm Hydrazine
>50 ppm Catalyzed Hydrazine
>25 ppm pH @77 F 9 5-10.5 i
Cation Conductivity
<10 pmho Na
<1.0 ppm Cl-
<l.0 ppm Feedwatof Typical Chemistry or Impurity Limits 1 pH @77 F 9.3-9 5 Max Solids
<50 ppb Cation Conductivity
<5 pmho bhx 0 7
ppb 2
Max Si 0 20 ppb 2
Max. Fe 10 ppb Max. Cu 2
ppb Condenser Cooling Water Typical Chemistry or Impurity Limits:
- 1. Concentration controlled to.2-3x river water solids concentration by blowdown
- 2. Maintain 0-0.5 L' Angelier Index by adding sulfuric acid
- 3. Chlorination 0.4 ppm free Cl-by adding for the 15 minute periods per day during warm months only Demineralizers - Type: None Cooling Tower (open cycle, closed cycle or none):
Closed Cycle
)
l j
l VI. TURBINE STOP VALVE TESTIf;G (applicable to Babcock & Wilcox (B&W) 5.G. only) l t
Frequency of Testing Actual:
1 pet. month Manufacturer Recomendation:
1 per day t
Power Level At Which Testing Is Conducted Actual:
50%
Manufacturer Recomendation:
Not specified Testing Procedures (Stroke length, stroke rate, etc:)
~
Actual:
100% stroke 6 <1 min. full open to mil close Manufacturer Fecomendation:
Not specified VII.
STEAM GENERATOR IUSE DEGRADATION HISTO...
(The following is t'o be repeated for each scheduled ISI) l 4
Inservice Inspection (ISI) Date:
3/T8 i
Number of EFP Days of Operation Since Last Inspection:
28T
]
(The following is to be repeated for each steam gene.ator)
-r A
B s
Steam Generator Number:
f 12% 9%
Percentage of Tubes Inspected At This ISI:
i Percentage of Tubes Inspected At This 151 That Had Been Inspected At The Previous Scheduled ISI:
3% 3%
4 9
Number of Tubes Plugged Prior to This ISI:
1 1
of Tubes Plugged At This 151:
g g g,,
0 100%
Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:
Percentage of Tubes Plugged As A Result of Exceedance of Degradation 1oog og Limits:
g l
Sludge Layer Material Chemical Analysis Results:
Not applicable
.(
l Sludge Lancing (date):
ng Ave. Height of Sludge Before Lancing:
NA j
Ave. Height of Sludge After Lancing:
NA (Briefly Replacement, Retubing or Other Remedial Action Considered:
NA Specify Details)
NA Support Plate Hourglassing:
NA Support Plate Islanding:
N/
Tube Metalurgical Exam Results:
Y Mn
,b ogg9 BW.D q
l; i
to I
. k 2
a Fretting or Vibration in U-Bend, Area (not applicable to B&W S.G.) AS OF (4)
Percentage of Tubes Plugged Other Preventive Measures
{
t NA i:
E 4
Wastage / Cavitation Erosion AS OF (4) 5 Hot Leg:
(Repeat this information for the cold leg on Combustion Engineering 4
(C.E.) and Westinghouse (W) 5.G.)
l b I c'I d l
Area of Tube Bundle (l')
a
!e
'NA
% of Tubes Affected by Wastage / Cavitation Erosion N05 APPI ICABI B
+
Ei
% of Tubes Plugged Due to Exceedance of Allowable
(
Limit (2)
V f
t
% of Tubes Plugged That
~
~
e Did not Exceed Degradation y
Limit r.[
Location Above Tube 5.
Sheet (3)
[
i Max. Wastage / Cavitation Erosion y
Rate for Any Single Tube (i
(Tube Circum. Ave) (Mills / Month)
[f Max. Wastage / Cavitation Erosion fi in Any Single Unplugged Tube K
(Tube Circum. Ave) (Mills) ji H.
z.
Li Crackin9 AS OF M ylI Caustic Stress Corrosion Induced in C.E. and W S.G.
L' Flow Induced Vibration Caused in B&W S.G.
Ei y,
V 1A
.w-r.
b
1 l
i
! 4:
Cracking (Con't)
Hot Leg:
(nepeat this information for the cold leg on C.E. and E S.G.)
II) j Area of Tube Bundle a
b c
d e
i
% of Tubes Affected NO ' APPI ICABLE By Cracking j
g
% of Tubes Plugged Due to s
Cracking i
5
% of Tubes Plugged That Did
.f tiot Exceed Degradation Limit a
2 Location Above (3) -
Tube Sheet i
Rate of Leakage From Leaking Cracks (gpm)
Denting (fiot applicable to B&W S.G.) AS OF (d)
Hot Leg:
(Repeat this information for,the cold leg en C.E. and H S.G.)
Area of Tube Bundle (1) a b
c d
e
% of Tubes Affected by NOM' APPLICAB:.E Denting
% of Tubes Plugged Due to Exceedance of Allowable Limit (2)
% of Tubes Plugged That Did tiot Exceed Degradation I
Limit i
Rate of Leakage From i
Leaking Dents (gpm) f ax. Denting Rate for Any Single Tube (Tube Circum. Ave) -(fiills/flonth) ttax. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (flills)' -
1
di i! I l<
hi fi i {j Denting (Con't)
[
3cpport Max. Denting in Any Single
% of Tubes Affected By Plate Tube-in Bundle Area Denting in Bundle Levels (Tube Ave) (Mills) (1) i Area
.Ir f
a b
c d
e a
b c
d e
1 NOT M PLICM LE l
2 l
3
(
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i 5
l E
l s_
l 7_
l
,,,s 8
0t-9 I
e lo 11 Iie L
Ee b
E b
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a h
e
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r l:
0 d
dl b
,=.
5 e
e D
2
. TABLE KEY NOTE: All percentages refer to the perce'nt of the tubes within a given area of the tube bundle.
(1)
Area of the Tube Bundle No. of Tubes Within the Area
-6870 f
a.
Periphery of Bundle (wi/20rowsforB&W; wi/10 rows for C.Et and W) b.
Patch Plate NA (wi/4 rows)
{
c.
Missing Tube Lane (B&W only) s770 (inclu' ding 200 from part A)
(wi/5 rows) q c.
FlowSlotAreas(C.E.andWonly)
NA wi/10 rows)
[
W d.
Wedge Regions (C.E. and W ortly)
NA (wi/8 rows) e.
Interior of Bundle
%8090 (remainder of tubes) i (2)
]
Allowable Limit for Wastage / Cavitation Erosion: I'0%
3 i
Allowable Limit For Danting:
Not Applicable i
(3) 1.
Specifies area between the tube sheet and the first support plate 2.
Specifies in the following locations: (list the additional locations)
Wastage / Cavitation Erosion:
NA Cracking:
NA (4 )
Specify the date of the inspectior. for which results have been tabulated.
D 3l IA I
D"O
}L h
b.
Wh VIII. SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS DATE
SUMMARY
(Include event description; unsche'duled ~ISI results; -if 5per-formed; and subsequent remedial actions)
Date Event OTSG 1.
HFT*
11 cycles on EF nozzles A&B 2.
12/76 1 hr. @S00 F vith FW <90 F A&B 3
12/76 hr. @ 520 F vith FW <90 F
'A 4.
11/77 6 hr. 8 532 F vith FW <90 F A&B 5
10/77 3.6 pH for about 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (secondary)
A&B 6.
HFT OTSG Level <97% RC>300 F numerous cycles A&B IX.
CONDENSER INFORMATION:
gggr g Le g ge(
)
gggtable Detection Method 30h SS
[FT*
160 gpm 0.1-0.2 gpm Cat. Cond. High 3/9/7 3 0.h-1.5 0.1-0.2 gpm Sodium High Powdex Performance X.
RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Dosage (Man-Rem)
Repair Dosage (Man-Rem)
Comments 76 Data not available NA 77 12.834 Man-Rem 9.467 Man-Rem 78 12 913 Man-Rem 1.085 mrem Tube Plugging
- HPP = Hot Functional Testing Period Y'.
s...,.--
s-
.m
. - ~ -., -,,,_g
, -+-
1
,s i
s f
I l,
1 XI.
DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR ITdICH THE RESULTS OF TWO OR MORE r
ISI'S ARE AVAILABLE r
If the results for ten tubes are not available, specify this infor-rnation for all those tube,s for which results are available.
NA (repeat the following.infomation for eac.h tube and degradation type)
Steam Generator No:
f Tube Identification:
NOT APPLICABLE Y-Type of Degradation:
(specify denting, wastage, cavitation erosion, caustic stress corrosion cracking, or flow induced vibration cracking) i (repeat the following infomation chronologically for each IS'I for which results are available)
ISI Date:
I Amount of Degradation:
(specify amount and units) j EFp Honths of Operation Since Last ISI for Wnich Results are Given:
e I
e e
f.
J