ML19220B237
| ML19220B237 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/30/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| GQL-1138, NUDOCS 7904250529 | |
| Download: ML19220B237 (11) | |
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METROPOLITAN EDISON COMPANY :vesicuar cr as. vent pueucuriuriesconpaurica,!
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POST OFFICE BOX 542 READING, PENNSYLV ANI A 1%C3 TE LEPHONE 215 - 9c9-3601 June 30, 1973 GO,L 1133 Director of Nuclear Reactor Regulatica Attn:
S. A. Vargs Light 'iater Reacters 3 ranch No. L U.S. :Iuclear Regulatory Cennissica
'4as hin gten, D. C. 20555
Dear Sir:
2:ree Mile Island Nuclea-Statica Unit 2 (CC-2)
Cperating License No. DPR-73 Occhet No. 50-320 Stean Generator Questiennaire Attached for your info -a+'~ and use is a cenpleted ccpy of the Stees Generater Operating Histcrf Questiennaire which was enciesed with ycur letter lated April 21, 1973.
"'his questiennaire has been answered -dth respect to the OC-2 (3FJ) Once "'hrcugh Steen Generators.
Sincerely, i
J.
a.
Herbein Vice President-Generation JGE:JES:cjg Attac'-
- helesure 1; Steam Generater Operating History Questiennaire 7904250521 g, w,. u i.,g'd 0 1 N. [e}soo92 s
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3 ENCLOSURE 1 STENi GENERATOR OPERATING I8 HISTORY QUESTIONNAIRE
- jrA h1 1
NOTE: All percentages should be reported to four significant figures.
6 I.
BASIC PLANT INFORMATICN
' Plant m --a '411e Island - Unit 2 Startup Date: Ju17 19T8 (Ho* "~~' ~al Testins)
Utility: Metropolitan Edisen Co-Plant Locatient Middleto-m, PA Thermal Power Level: 2772 My Nuclear Steam Supply System (NSSS) Supplier:
3&'4 Number of Loops: 2
)
Steam Generator Supplier, Model No. and Type:
~&'4 OTSG Number of Tubes Per Generator: 15,531 Tube Size and Material: 0.625" cc, 0.03k" # 11, 56' 2 3/8" isth, Incenel II. STEMI GENERATOR OPERATING CONDITIONS Normal Operation Ten.oerature: g;.nar/, c:0 ? 21*t
- a.u C SC! - 570 F Flow Rate:
Pri.arr - 63.ghx;o Mllowable Leakage Rate:
1 G3'4 Total 524-c.12 X 10 1/hr Priatry Pressure:
2155 ?sig Seco1dary Pressure: 925 ?sig (m
1 Accidents M
. ')
Design Base LOCA Max. Delta-P: 925 ?sig g
Main Steam Line Break (MSLB) Max. Delta-P: 2200 Psis
.1~
III. STEAM GENERATOR SUPPORT PLATE INFORMATION
/22'I Material:
Carben steel Design Type: 3reec'ned W ening Design Code:
,,4; p c q~
Dimensicns:
1:.3 3/8" Dia.
Flow Rate:
5 3 I 10 I3/hr-Tube Hole Dimensicas:
=0.320 in. =in. radius /tute Finw Hole nimensions-c.135 in.2/ tube
gs g
IV. STEM 1 GENERATOR BLCWCOWN INFORMATION
~, i
~
frequency of Bicwdown: Centinucus s 45%FF; C ! >15% FF j
d Normal Blowdown Rate: 5 GF'4 0
Blowdcwn Rate w/ Condenser Leakage: I;/A i@
Q Chemical Analysis Results y
i Results Parameter Control Limits Caticn COnd - 1 umho
< 10 t=ho
- Ta - 0.05 pp:
< 1 pp:
C1 - 3.05 pp:
< 1 pp:
V.
WATER CHEMISTRY INF0Fd'.ATION Q-Secondarv Water s
Type of Treatment and Effective Full Power (Effy. Months of Operation:
ayd' azine /Acronis CAU"'
O 2,t r Typical Chemistry?
-:: = A 105'o. c'00nd. = 0.3 USno < 02 <30 50 ?"3 o
- 3 o, --
^
Feedsater Incurity Limits Fe < 100 ::b Pb=0:b 00 7 7 hib E7dra: inh ='> C 1 pp:
S.Ilyes <RO_ ppb Cation Ocnd.- < 0.5 ucho/cm pn s.3 - y.a s
Ccndenser Cooling 'a'ater Typical Chemistry.or Impurity Limits: :ro specific limits
[0, n
Ccrineralizers - Type: :Icte 3
C;aling Tower (open cycle, closed cycle or none): Closed Cycle i
e as kg
.g
~
O O
3-VI. TURBINE STCP VALVE TESTIriG (applicable to Babcock & Wilcox (B&W) S.G. only) e Frecuency of Testing 0
Ca Actual: : ret ye: perec eed h
Manufacturer Reco=endation:
Weekly 2
fi Pcwer Level At Which Testing Is Conducted q
i:
Actual: ::ct yet perre=ea Manuf acturer Recc.mendation:
0 to 225 or So to icc5 Testing Procedures (Stroke length, stroke rate, etc.)
Actual:
Fun s: te, appr x.13 see. run cycle Manufacturer Reccmmendation: ru n stroke, apprax. 13 sec. fun eyele VII. STE/41 GENERATOR TU5E DEGRADATION HISTORY (See attached sheet, Page 10)
(The following is to be repeated for each scheduled ISI)
Inservice Inspection (ISI) Date:
- TA Number of EFP Cays of Operation Since Last Inspection:
O (The following is to be repeated for each steam generator)
Steam Generator Number:
Percentage of Tubes Inspected At This ISI:
Percentage of Tubes Inspected At This 15I That Had Been Inspected At The Previous Scheduled ISI:
i/A Percentage of Tubes Plugged Prior to This ISI:
Percentage of Tubes Plugged At This ISI:
Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:
Percentage of Tubes Plugged As A Result of Exce'edance of Cegradation Limits:
fj Sludge Layer flaterial Chemical Analysis Results: :r/A
(
Sludge Lancing (date):
- i/A i
Ava. Height of Sludge Before Lancing: :r/A Ave. Height of Sludge After Lancing: :I/A g
U Replacement. Retubing or Other Remedial Actica Considered: (Briefly Specify Details) :rene
)
Support Plate Hourglassing: :rene Suo; ort Plate Islanding:
- Icne iube Metalurgical Exam Results:
9' G
r -
Fretting or Vibraticn in U-Bend Area (not applicabla to B&W S.G.) AS OF (4)
'[
Percentage of Tubes Plugged Other Preventive Measures t.
Wastage / Cavitation Erosion AS OF (a)
Hot Lec:
(Repect this infor::aticn for the cold leg on Conibustion Engine ring (C.E.) and t!estinghouse (W) 5.G.)
Area of Tube Bundle (i) la b
c d
ie
% of Tubes Affected by i
Wastage / Cavitation Erosion i
O
% of Tubes Plugged Due to I
Exceedance of Allewable Limit (2)
I'
% of Tubes Plugged That Did not Exceed Degradation Limit Location Above Tube Sheet (3) l Hax. Wastage / Cavitation Erosion
}
Rate for Any Single Tube
]g j
(Tube Circum. Ave) (Mills /Mcnth)
Max. Wastage / Cavitation Erosion in Any Single Unplueged Tubc 3
(Tube Circum. Ave) { Mills)
- r. m
~3
?
Cracking AS OF (4)
Caustic Stress Corrosion Induced in C.E. and W S.G.
Ficw Induced Vibration Caused in 85W S.G.
,.;4_.pco l
L..
s I
S A
J Crackin9 (Con't)
- a (nepeat this infomation for the cold leg on C.E. and E S.G.)
rot Leg:
Y a
b c
d le'
)
AreaofTubeBundle(I)
- 1 4
'4
% of Tubes Affected L
By Cracking
% of Tubes Plugged Due to Cracking
% of Tubes Plugged That Did Not Exceed Degradation Limit Location Above (3)
Tube Sheet l
Rate of Leakage From Leaking Cracks (gpm)
Denting (Not applicable to B&W S.G.) AS OF (4)
Hot Leg:
(Repeat this information for the cold leg on C.E. and E S.G.)
Area of Tube Eundle (1) a b
c d
e
% of Tubes Affected by Denting
% of Tubes Plugged Due to Exceedance of Allowable Limit (2)
W'i;
% of Tubes Plugged That
.:j Did Not Exceed Degradation jd Limit E. 2 P. ate of leakage Frca Leaking Dents (gpm) j!
L Max. Denting Rate for Any Single Tube (Tube
~
Circum. Ave) (Mills / Month)
.c e q.
)
Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) -
g-g 7
Centing (Cen't) e Q
Bupport Max. Denting in Any Single
- 7. of Tubes Affected By 6
Plate Tube in Bundle Area Genting in Bundle f
Levels (Tube Ave) (Mills)- (1)
Area a
b c
d e
a b
c d
e L
1 2
l 3
l 4
l l
I 5
l j
I 6
l 7
l 8
i 9
O 10 l
11.
12 i
b c-i E.d
?b
.I U
'24'CS9 f
f
nv
' m TABLE XEY
's NOTE: All percentages refer to the perce'nt of the tubes within a given 1
area of the tube bundle.
g (1)
Area of the Tube Bundle No. of Tubes Within the Area a.
Periphery of Bundle (wi/20 rows for B&W; wi/10 rows for C.E. and W) b.
Patch Plate (wi/4 rows)
Missing Tube Lane (B&W only) c.
(wi/5 rows) 3 c.
Flow Slot Areas (C.E. and W only)
)
wi/10 rows) d.
Wedge Regions (C.E. and W only)
(wi/S rows) e.
Interior of Bundle (remainder of tubes)
(2)
Allowable Limit for Wastage / Cavitation Erosion:
Allcwable Limit For Denting:
(3) y 1.
5;:ecifies area between the tube sheet and the first support plate
.j
'(I;f 2.
Specifies in the folicwing locations: (list the additional locations)
.y Wastage / Cavitation Erosion:
WLl Cracking:
,4
.'[9 (4) 3, Specify the date of the inspection for which results have been tabulated.
-~
O' O
C 8-n
?
C VIII. SIGNIFICANT STEMt GENERATOR ABNCRMAL ORERATIONAL EVENTS da Rk DATE SUP14ARY L
(Include event description; unscheduled ISI results, if performed; and subsequent remedial actions) h-23-73
?.apid pressure transient due to improper MS Safety 7alve operstica IX. CCNDENSER INFORMATION Ccndenser Tube Leakage Detectable Detection Material Date Rate (gpm)
Limit Method (htes)
SS_As2.!
O Cation COnd.
A2L9
- Ta+
?/pe 30k X.
RADIATION EXF05URE HISTORY WITH RESPECT TO STEAM GENERATORS t
Date ExamDosage(Man-Rem)
Repair Desage (Man-Rem)
Con =ents IICne
{.]n$
b
,4 6.,
- 4 bU
q, e
C b
B XI. CEGRADATION HISTCRY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN
[j]
REPRESENTATIVE, UNPLUGGED TUBES FOR kHICH THE RESULTS OF TWO OR MORE ISI'5 ARE AVAILABLE
- UA A
If the results for ten tubes a~re not available, specify this infor-S mation for all those tubes for which results are available.
'E (repeat the follcwing information for each tube and degradation type)
Steam Generator No:
Tube Identification:
Type of Degradation:
(s;:ecify denting, wastage, cavitation erosion, caustic stress corrosion cracking, or flow induced vibration cracking)
(repeat the following information chronologically for each ISI for which re:,ults are available) m ISI Date:
s AT.0unt of Degradation:
(specify amount and units)
EFP Months of Operation Since Last ISI for Which Results are Given:
me t.m 94 102 E.
J
@..a..
.,, 4 - 4.- _.a.4--
..... <... e...__., v e... -,.
...>e,e.
a a.4..,
- 4 -. -. /.
a
....a v.-
s.
documents the result of the presertice exa=inatien. An IS!
has nct yet been conducted.
Dreser rice Inspection Date: December 1977; EFF Days of Cperaticn is not applicable.
V. et1 ::
e.-
V.c-aa rt s
Percentage cf tubes inspected at PSI:
1005 1C05 Fercentage of tubes plugged prior to this PS!:
" + cvn unkncvn Percentage of tubes plugged at this
. 8 h ",
. 5 *, ",
S. SI -.
^
Percentage of tubes plugged that did not exceed degradation ~dts:
23.075 12.55 Percentage of tubes pluggad as a result of exct.edance of degradaticn limits :
Tc.k25 37.55
"'abe Meta 12=gical Exa= ?.esults
- ene
- A tube with an eddy current indicaticn of a 555 C.D. defect was re=cved.
Metallurgical ex' # ation revealed a scab or lap presu= ably f'c= tubing
=anufacture with a depth of about 50".
f
.k J
- 4
.