ML19317G947
| ML19317G947 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/16/1977 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020605 | |
| Download: ML19317G947 (10) | |
Text
m g
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-312 REC: GOLLER K R ORG: MATTIMOE J J DOCDATE: 02/16/78 NRC SACRAMENTO MUN UTILITY DISTRIC DATE RCVD: 02/24/78 DOCTYPE. LETTER NOTARIZED: NO
SUBJECT:
COPIES RECEIVED LTR 1 ENCL 1 FORWARDING APPLICANT"S COMPLETED QUESTIONNAIRE RE STEAM GENERATOR OPERATING HISTORY.
PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:
- 'f*************** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
RESPONSES TO STEAN GENERATOR QUESTIONNARE (DISTRIBUTION CODE A023)
FOR ACTION:
BRANrH rHI _r
/7 ENCL INTERNAL:
EG FILE **
NRC PDR**W/ ENCL 1 a t m b.entL OELD**W/ ENCL HANAUER**W/ ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL J COLLINS **W/ ENCL EXTERNAL:
LPDR'S SACRAMENTO, CA**W/ ENCL REGION V**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL RON GAMBLE **W/6 ENCL KEN HERRING **W/6 ENCL ACRS CAT B**W/16 ENCL
@ISTRIBUTION:
LTR 51 ENt:L 5I SIZE: 9P CONTROL NBR: - 't,
...hkf7 L'i cococco****************************
THE END
- 0I 8 0 04 920 @ S~
/
n w w
',T~ 5.
~.,c.ad.
aw. ~..
$SMUD SACRAMENTO MUNICIPAL UYlLITY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califcmia 95813; (916) 452-3211 February 16, 1977 Director of Nuclear Reactor Regulation ATTN:
Karl R. Goller
~,
Q2/
Assistant Director for Operating Reactors
-4 Division of Operating Reactors
^
N/
U. S. Nuclear Regulatory Commission y
Washington, D. C. 20555 Re:
Docket No. 50-312 Steam Generator Operating History Questionnaire, Dated December 9, 1977 Rancho Seco Nuclear Generating Station Unit Number 1 Gentlemen:
Please find attached the completed questionnaire regarding steam generator operating history.
If we can provide any additional information, please feel free to contact us.
Respectfully submitted, L
&n
/.'J. Mattimoe i
J Assistant General Manager and Chief Engineer i
JJM:DA:sc Attachment O
9 f
.m--
.A 1
l l
AN ELECTRIC SYSTEM S E R VIN G MORE THAN 600,000 IN THE HEART OF C ALIF0 R NI A
V 8
r
~
)
/
l I
ENCLOSURE 1 STEA'l GEliERATOR OPEPfTING l
HISTORY QUESTIONNAIRE NOTE: All percentages should be reported to four significant figures.
I.
BASIC PLANT INFOP.'ATION Plant: ' Rancho Seco Unit I St'artup Date:
April 18,1975' Utility: Sacramento Mu'n'icipal' Utility District P.lant Location:
Herald, California Thermal Power Level,- 2772 nre Nu'elear Steam Supply System (NSSS) Supplier:
B6W Number of Loops:
2 Steam Generator Supplier, Model No. and Type: B6W
~Nu'mb'er of Tubes Per Generator: 15,457 T'ube Size.and I:aterial:
56 ft. long, 0.625 in. 0.D., 0.b34 in. 'dall '
thickness, Inconel.
II. STEAM GENERATOR OPERATING CONDITIONS Normal Operation Temperature: 582* F Average (Primary)
Elow Rate: 68.95x106 Lb/Hr (Primary) Allowable Leakage Rate: 1 GPM, Tota,1 for all Steam t h ators Primary Pressure:
2155 psig Secondary Pressure:
900 psia Accidents Design Base LOCA Max. Delta-P:
- Less than 1285 psi
.' We hava used Delta-P
!!ain Steam Line Break (t:SLB) ; ax. Delta-P:
to mean the difference III. STER: GENERATOR SUPPORT PLATE INFORMATION
,,between primary and l
secondary system Material:
Carbon Steel ASFE-SA-515 GR70 pressu e.
Design Type:
Broached Plate - with Tri-lobed holes Design Code:
ASFE III - 1967 Class A Vessel Dimensions:
115 in.
diameter x 1 1/2" thick 6
Flo.1 Rate:
3.06x10.Lb/Hr Tube Hole Dimensions:
Tubes are 0.625 0.D.
Flow Hole Dimensions:
Lobed hole shell side flow area is approximately 0.12 in2 per hole.
=- ' -
e ')
g-s IV.
STEAM GENERATOR BLOWDOWN IhTORMATION Frequency of Blowdown:
With Once Through Steam Generators, the only time that blowdown is initiated is when the plant is operating below 15% power.
Normal Blowdown Rate:
During operation below 15% power and on startup, a blowdown of approximately 30 gpm from each OTSG is established.
Blowdown Rate w/ Condenser Leakage:
None, if there is condenser leakage, it is repaired.
Chemical Analysis Results Parameter Control Limits (Last time at (15% power)
Cat Cond 0.21 umho/cm 10.0 pmhos/cm Sodium 7 ppb 2.0 ppm Silica 15 ppb 2.0 ppm Chloride
<25 ppb 1.0 ppm V.
WATER CHEMISThY INFORMATION Secondarv Water 5
Type of Treatment - Use 9 polishing demineralizers with Hydrazine addition for oxygen control and ammonia addition for pH control.
E.F.P. months approximately 16.
Typical Chemistry or Impurity Limits:
None.
Specifications on Feedwater and Steam Only.
Feedwater Typical Chemistry or Impurity Limits:
pH 9.3 to 9.5 Cation Conductivity 0.3 umhos/cm Total Solids 40 ppb Dissolved Oxygen 7 ppb Hydrazine 20-100 ppb l
Ammonia 0.5 to 1.5 ppm Silica 10 ppb Copper 2 ppb Chloride 3 ppb Conductivi,ty 5.7 to 8.4 pmhos/cm Sodium 3 ppb Iron 10 ppb Lead 1 ppb l
(~~)
p
- h.
- w*ATER CHD!ISTRY INF00fATION (Continued)
Condenser Cooling Water Typical Chemistry or Impurity Limits pH 7.4 to 7.8 Conductivity 1050 pahos/cm max.
Silica 150 ppm max.
TDS 800 ppm max.
Tocci Chlorine 0.2 ppm max No demineralizers are used in the condenser cooling water system, which is an open cycle recirculating system.
1 i
p, 3_
F
'VI.
TURBINE STOP VALVE TESTING (applicable to Babcock & Wilcox (B&W) S.G. only)
Frequency of Testing Actual:
Fonthly Manufacturer Recommendation: Weekly (Westinghouse)
Power level at Which Testing is Conducted Actual:
< 65% power Manufacturer Recommendation:
B&W recommends < 65%, Westinghouse allows up to 100% power.
Testing Procedures (Stroke length, stroke rate, etc.)
Actual:
15.4 inches - Full stroke 20 sec. to close (12-19 to open' Manufacturer Recommendation: B&W:
(15-20 sec)
Wes tinghouse:
Full stroke VII. STEAM GENERATOR TUBE DEGRADATION HISTORY (The following is to be repeated for each scheduled ISI)
Inservice Inspection (ISI) Date:
Sept. 1977 Number of EFP Days of Operation Since Last Inspection:
460.1 Steam Generator Number: E-205A S/N Unit 1 620-0011-55 Percentage of Tubes Inspected at This ISI:
9.000% (1391 tubes inspected)
Percentage of Tubes Inspected at This ISI That Had Been Inspected At The Previous Scheduled ISI: N/A (1st Inspection)
Percentage of Tubes Plugged Prior to This ISI: N/A Percentage of Tubes Plugged At This ISI:
.0518% (8 Tubes)
Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:
.0259% (4 tubeG Percentage of Tubes Plugged As A Result of Exceedance of Degradation Limits:
.0259% (4 tubes)
Sludge Layer Material Chemical Analysis Results:
Spectographic analysis identified iron as the major elemental constituent.
Other contaminants present were nickel (2.8%-4.2%), chromium (0.5%-1.9%), molybdenum (0.03%-0.1%),
manganese (0.3%-0.4%), ein (0.06%-0.1%), and a trace of zinc.
Sludge Lancing (date): N/A Ave. Height of Sludge Before Lancing: Tight Oxide coating on tubes Ave. Height of Sludge Af ter Lancing: N/A Replacement, Retubing or Other Remedial Action Considered:
(Briefly Specify Details):
None Support Plate Hourglassing: None
l(];
/~'
o'
-4 VII.
STEAM GENERATOR TUBE DEGRADATION HISTORf (Continued)
E-205A Support Plate Islanding:
None Tube Metalurgical Exam Results:
No specimens were removed.
VII.
STEAM CENERATOR TUBE DEGRADATION HISTORY E-205B Steam Generator Nember:
E-205 3, S/N Unit 2 620-0011-55 Percentage of Tubes Inspected At This ISI:
3.345% (517 tubes)
Percentage of Tubes Inspected At This ISI That Had Been Inspected At The Previous Scheduled ISI:
N/A (1st Inspection)
Percentage of Tubes Plugged Prior To This ISI: N/A Percentage of Tubes Plugged At This ISI: 0.000%
Percentage of Tubes Plugged That Did Not Exceed Degradation Lir5 ts:
0.000%
Percentage of Tubea Plugged As A Rusult of Exceedance of Degradation Limits:
0.000%
Sludge Layer Material' Chemical Analysis Results:
Spectrographic analysis identified iron as the major elemental constituent. Other contaminants present were nickel (2.7%-4.5%), chromium (0.7%-3.8%), molybdenum (0 1%-0.4%).
and manganese (0.4%-0.5%)
Sludge Lancing (date): N/A Ave. Height of Sludge Before Lancing: Tight oxide coating on tubes.
Ave. Height of Sludge Af ter Lancing:
N/A Replacement, Retubing or Other Remedial Action Considered:
(Briefly Epecify Details)
None Support Plate Hourglassing: None Support Plate Islanding:
None Tube Metalurgical Exam Results:
No specimens were removeu.
t^,
"A"
'OTSG Wastage / Cavitation Erosion AS OF Sept. 1977.
(No specimens were removed and therefore the type of defect could not be positively identified. However, the indications were thought to be caused by wear.
Hot Leg:
(Repeat this information for the cold leg on Combustion Engineering (C.E.) and Westinghouse (W) S.G.)
Area of Tube, Bundle (1) a b
c d
e
% of Tubes Affected by Wastage / Cavitation ' Erosion
.0518%
.0518%
~
~
~
% of Tubes Plugged Due to Exceedance of Allowable
~
.0259%
~
~
.0259%
Limit (2)
% of Tubes Plugged That Did Not Exceed Degradation
.0259%
.0259%
Limit Location Above Tube U.T.S.
U.T.S.
Sheet (3)
(15th)
(15th)
Max. Wastage / Cavitation Erosion i
Rate for Any Single Tube
.7 mil /mo
.7 (Tube Circum. Ave)
(Mills / Month) mil /mo Max. Wastage / Cavitation Erosion in any Single Unplugged Tube
< 7 mil
~
~
~
~
(Tube Circum. Ave)
(Mills)
(<20%)
Cracking AS OF Sept. 1977 Flaw Induced Vibration Caused in B&W S.G.
Defects found were not of type associated with cracks.
i i
i l
4 e
,,)
g-s
- ** "B" OTSG Wastage / Cavitation Erosion AS OF Sept. 1977 (No specimens were removed and therefore the type of defect could not be positively identified.
One indication was found and it was reported as a pit, but it was not plugged because it was less than 40% thru wall).
Hot Leg:
(Repeat this information for the cold leg on Combustion Engineering (C.E.) and Westinghouse (]d) S.G.)*
Area of Tube Bundle (1) a b
c o
e
% of Tubes Affected by 0.0 0 Wastage / Cavitation Erosion
)
% of Tubes Plugged Due to Exceedance of Allowable
~
~
~
Limit (2)
~
% of Tubes Plugged That Did Not Exceed Degradation
~
~
~
~
Limit
~
Location Above Tube Sheet (3)
U.T.S.
(15th)
Max. Wastage / Cavitation Erosion 4
Rate for Any Single Tube
,gy),*
(Tube Circum. Ave)
(Mills / Month)
Max. Wastage / Cavitation Erosion in Any Single Unplugged Tube
.4 l
(Tube Circum. Ave) (Mills)
~
~
~
~
mil Cracking AS OF Sept.,1977 Flow Induced Vibration Caused in B&W S.G.
Defect found was not of type associated with cracks.
^
n o
a
.- Denting N/A VIII.
SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS None IX.
CONDENSER INFORMATION Condenser Tube Leakage Detectable Detection Tube Limit Method Material Date Rate (gpm)
Stainless 3/25/77
<.5 gpm 0.1 gpm Cation Steel Conductance A249 Type 304 X. RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Dosage (Man-Rem)
Repair Dosage (Man-Rem)
Comments i
i i
Sept, 1977 16 50 Includes all 1
associated activities, 1.e., erection od tents, cleaning !
- studs, sampling,closurd etc.
XI.
DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR WHICH THE RESULTS OF TWO OR MORE ISI'S ARE AVAILABLE Only one ISI has been done
C; o
TABLE KEY NOTE: All percentages refer to the percent of the tubes within a given area of the tube bundle.
(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) c.
Missing Tube Lane (B&W only)
(w1/5 rows) c.
Flow Slot Areas (C.E. and W only)
(wi/10 rows) d.
Wedge Regions (C.E. and W only)
(wi/8 rows) e.
Interior of Bundle (remainder of tubes)
(2)
Allowable Limit for Wastage / Cavitation Erosion:
Allowable Limit for Denting:
(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:
Cracking:
(4)
Specify the date of the inspection for which results have been tabulated.
\\