ML19259C418
| ML19259C418 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/18/1979 |
| From: | Haynes J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13333A375 | List: |
| References | |
| NUDOCS 7906200345 | |
| Download: ML19259C418 (12) | |
Text
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bb Southern California Edison Company P. o. Box 800 2244 WALNUT oRQvE AVENUE RoSEME AD. C ALIFoRNI A 91770 June 18, 1979 Director, Office of Nuclear Reactor Regulation Attention:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206, Provisional Operating License No. DPR-13 Information Requested on Feedwater Lines San Onofre Nuclear Generating Station, Unit 1 By letter dated May 25, 1979, you requested that we submit the infor-mation identified in the enclosure to that letter concerning the feedwater lines at San Onofre Unit 1.
You indicated that this request for information was being made in accordance with 10CFR550.54(f) of the Commission's regulations and should be submitted within 20 days of receipt of your letter.
Accordingly, submitted herewith as Enclosure 1 is the information requested by your May 25, 1979 letter. The information contained in Enclosure 1 represents a complete response; therefore, a subsequent submittal of any remaining information within the 60 days identified in the enclosure to your letter is not required.
Subscribed on th.is 18th day of June
, 1979.
Subscribed and sworn to before me this Respectfully submitted 18th day of June, 1979.
SOUTHERN CALIFORNIA EDISON COMPANY Y t/
By d4/n.24 J
Notary Public in and for the County of J. G. Haynes [
Los Angeles, State of California Chief of Nuclear Engineering
.9 My Commission Expires b N7 #Q.
2285 130 i
---o Enclosure AGNES CRASTREE I l
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ENCIDSURE 1 INECINATICN REQUESTED CN IHR FEcIHATER LINES SAN CNOFRE NIX 1 EAR GENERATING STATICN UNIT 1 INMINATICN REQUESTED Design 1.
Provide as-built piping or isonetric drawings of the feedwater line to steam generator sparger (feedwater ring) within containment. Show details of the design such as dimensions, pipe schedule, support type and locations, pipe restraints, and valve (s).
2.
Provide the results of any stress fatigue analyses which was performed for this system.
Responses 1.
As-built isaretric drawing nos. 334539, 334538 and 334537 are provided as Figures 1, 2 ard 3 showing steam generators A, B and C, respectively. All pipe is schedule 60.
Support typ is delineated in Table 1.
2.
Structural and fatigue analyses have been performed on the SCE feedwater line configuration inside containment.
'Ihe results of the analyses are contained in the report entitled " Interim Begrt, San Onofre Unit 1 Steam Generator Nozzle to Piping Inspction and Corrective Action, June 13, 1979," a copy of which is attached. W is report was subnitted to the NBC by letter dated June 15, 1979. Results are provided for only the maximum thermal, deadweight and pressure stresses which occur at the nozzle to reducer junction. 'Ihese stresses are well below code allowable values and stresses alcng the remainder of the pipe are less than those presented.
2285 131
INMEMATICN REQUESTED Fabrication Histcry 1.
Supply a list of the materials for the steam generator sparger (feedwater ring), steam generator feedwater nozzles and feedwater piping within contain-ment.
i 2.
Provide the details of the welding process (es) used to make the nozzle-t W pe, pipe to feedwater ring and piping welds.
Include details of welding such as preheat, joint configuraticn (include with or without backing ring), and post weld treatment, if any.
3.
Provide the NDE performed during and after fabrication of the weld joints requested in question 2.
4.
Provide the code edition to which the feedwater piping system was fabricated.
5.
State the fracture toughness requirements, if any, for the feedwater piping system.
Responses 1.
Se following list of materials for the steam generator feedwater system is provided:
a.
Feedwater ring is SA-106, Gr. B b.
Feedwater nozzle is ASIM - A105 Class 2 c.
Feedwater reducer is ASIM - A234 WPB d.
Feedwater piping is ASIM - A106 Gr. B 2.
Se welding procedures for the original as-built mnfiguration and for the newly installed 10" x 14" reducers are described in the attached aforemen-tiened report.
3.
A randcm 10 per nt of all weld joints were originally radiographed.
In addition, a hydrostatic test was performed on the feedwater systen. He NDE performed on the newly installed 10" x 14" reducers are described in the attached aforementioned report.
4.
%e feedwater piping system was fabricated to the 1962 edition of the ASME Boiler and Pressure Vessel Code,Section I.
5.
mere were no stated fracture toughness requirements for the feedwater piping system.
2285 132
INEGMATICN RECUESTED Preservice/ Inservice Inspection and Operating History 1.
State whether the feedwater system welds received a preservice inspection in accordance with ASME B&W Code,Section XI.
2.
Provide the extent of inservice inspection performed cn the feedwater pipe to steam generator nozzle welds.
Include the results of the examinations, any corrective actions taken and causes of any failures.
3.
Provide the schedule and extent of inservice inspection for the feedwater system for the next inspection interval.
4.
Provide any history of water hamer or vibration in the feedwater system and design changes and/or actions taken to prevent these occurrences.
5.
Provide a description of feedwater chemistry controls and a sumary of dienistry data.
RESKNSES 1.
2e original feedwater system welds did not receive a preservice inspec-tion in accordance with ASME B&W Code,Section XI.
Se preservice inspection was performed in accordance with ASME B&W Code,Section I.
Ibwever, the welds for the newly installed reducers wre inspected in acmrdance with ASME B&W Code,Section XI.
2.
S e non-destructive examinations performed on the newly installed feed-water pipe to steam generator nozzle welds are described in the attached aforementioned report.
In addition, the corrective actions taken and the causes of the failures are also described.
3.
2 e schedule and extent of inservice inspection for the feedwater system for the current inspection interval which began in 1978 are as follows:
Steam Generator A Weld Designation Inspection Intes Mode of Examination 393-3 2002 W1umetric 393-5 1978 393-9 1979, 1980 393-10 1979, 1980 Steam Generator B 392-3 1985 392-7 2005 392-10 1997 392-12 1978 392-13 1979, 1980 392-14 1979, 1980 2285 133
. Steam Generator C Weld Designation Inspection Ihtes Mode of Dcamination 391-5 2000 Valumetric 391-9 1979, 1980 391-10 1979, 1980 4.
Se history of water hamer or vibration in the feedwater systen and design changes and/or actions taken to prevent these occurrences are described in the report entitled " Report Concerning Susceptability to Steam Generator Feedwater Line Water Hmmer Events, San Onofre Nuclear Generating Station, Unit 1, De mber, 1977." he report was submitted to the NRC by letter dated Decerber 27, 1977, a copy of which is attacned.
5.
A description of the feedwater chemistry centrols and a sumary of chemistry data was provided to the NRC by letter dated February 17, 1978 in response to a " Steam Generator Operating History Questionnaire."
he pertinent sections of that response are attached as Table 2.
s 2285 134
TABLE 1 Pipe Support Type 1.
Hydraulic Shock and Sway Suppressors (ITT Grinnell)
Steam Generator A Steam Generator B Steam Generator C 1-S-SW 393-1 1-S-SW-392-1 1-S-SW-391-1 1-S- % 393-2 1-S-SW-392-2 1-S-SW-391-2 1-S- % 393-3 1-S-SW-392-3 1-S-SW-391-3 1-S-SW-393-4 1-S-SW-392-4 1-S-SW-391-4 1-S-Si+-392 5 2.
@ ring Hangers (ITT Grinnell)
Steam Generator A Steam Generator B Steam Generator C 1-S-SH-393-1 1-S-SH-392-1 1-S-SH-391-1 1-S-SH-393-2 1-S-SH-392-2 1-S-SH-391-2 3.
Rigid Hangers (ITF Grinnell)
Steam Generator A Steam Generator B Steam Generator C 1-R-RH-393-1 1-R-RH-391-1 1-R-RH-393-2 1-R-RH-391-2 4.
Rigid Hangers (Field Constructed)
Steam Generator A Steam Generator B Steam Generator C 1-KBG-393-l*
l-K-KB-392-1**
1-KBG-391-1*
l-K-KB-392-2**
l-K-KB-392-3**
l-K-KB-392-4**
1-KBA-392-1***
l-KDG-392-3***
l-KDG-392-1*
l-KDG-392-2*
2285 135
- Knee Brace and Guide
- Knee Brace
- Knee Brace and Anchor
ap.
TAeLE.2.
STEAM GENERATOR OPERATING HISTORY QUESTIONNAIRE NOTE: All percentages should be reported to four significant figures.
I.
BASIC PLANT INFORMATION:
Plant: San Onofre Unit 1 Startup Date:
January 1, 1968 Utility: Southern California Edison Company Plant Location:
San Onofre, California Thennal Power Level:
1347 Mwt Nuclear Steam Supply System (NSSS) Supplier:
Westinghouse Electric Ccrp.
Number of Loops:
3 Steam Generator Supplier, Model No. and Type:
Westinghouse, Series 27 Vertical and U-tube Number of Tubes Per Generator:
3794 Tube Size and Material:
0.750 in 0.D. x 0.055 Avg. Wall of NiCrFe alloy, ASTM-B-163-61T II.
STEAM GENERATOR OPERATING CONDITIONS Normal Operation Steam Temperature:
504.70F Steam Flow Rate:
1.902 x 106 lb/hr per steam generator Allowable Leakage Rate:
0.3 gpm in any steam generator Primary Pressure:' 2050 psig Secondary Pressure:
695 psig Accidents 2285 136 Design Base LOCA Hax. Delta-P:
800 psi Main Steam Line Break (MSLB) Max. Delta-P:
2500 psi
(
e, III.. STEAM GENERATOR SUPPORT PLATE INFORMATION Haterial:
Carbon Steel Design Type:
Baffle with 7588 tube holes, 7574 flow holes, and 6 flow-slots Design Code:
ASME Section VIII, 1962 edition Dimensions:
Diameter 8' 8 1/2" thickness 5/8" Flow Rate:
8.0 x 106 lb/hr Tube Hole Dimensions:
43/64" Flow Hole Dimensions:
33/64" IV.
STEAM GENERATOR BLOWDOWN INFORMATION Frequency of Blowdown:
Continuous /1 hr. each week Normal Blowdown Rate:
5 spm/5 x 104 lbm/hr Blowdown Rate w/ Condenser Leakage:
Blowdown rate arid chemical feed are increased as necessary to maintain steam generator pH and control steam generator conductivity. Maricum allowable blowdown rate is 5 x 104 lbm/hr.
01emical Analysis Results i
Results l
Parameter Control Limits No significant I
change from normal blowdown chemistry prior to shutdown to repair condenser 2285 137 leak
=
V.
' WATER CHEMISTRY INFORMATION Secondary Water Type of Treatment and Effective Full Power (EFP) Months of Operation:
Initial unit operation for 23 EFP months coordinated pH-phosphate control Typical Chemistry or Impurity Limits:
PO4 5 to 10 ppm Conducting 75 /Unhos C1 75 ppm pH 9.1 to 9.97 Silica 5 ppm Total Dissolved Solids 600 ppm Dissolved 02 0.00 ppm Type of Treatment and Effective Full Power (EFP) Months of Operation:
Volatile Treatment 4 EFP months of operation Typical Chemistry or Impurity Limits:
pH 8.8 to 9.2 Conductivity 10pntios Dissolved 02 0.00 ppm C1 25 ppn Silica 5 ppn Type of Treatment and Effective Full Power (EFP) Months of Operation:
Coordinated pH-phosphate control for 10 EFP months Typical Chemistry or Impurity Limits:
2285 138 Same as prior to volatile V.
(Cont'd) Page 2)
Secondary Water Type of Treatment and Effective Full Power (EFP) Months of Operation:
Phosphate 19 EFP months Typical Chemistry or Impurity Limits:
Phosphate, P04 20-80 ppn Na/P04 molar ratio 2.6 (max) pH 8.8 to 10.0 Conductivity 150xmhos Silica, SiO2 5 ppm Chlorides 25 ppm Dissolved 02 0.00 ppm Suspended Solids 5.0 ppn Type of Treatment and Effective Full Power (EFP) Months of Operation:
Phosphate 37 EFP months Typical Chemistry or Impurity Limits:
Phosphate, PO4 5 to 10 ppn Na/P04 molar ratio 2.5 to 2.8 pH 9.2 to 9.9 Conductivity 150 gntios Silica, SiO2 5 ppm Chlorides 25 ppm Dissolved 02 0.000 ppn Suspended Solids 5.0 ppn NOTE: pH range has been changed fran 9.2-9.9 to 9.40-9.90 2285 139.
, Cont'd) Page 3)
(
V.
Feedwater Typical Chemistry or Impurity Limits:
pH 8.8 to 9.4 Conductivity 6.5 gmhos Conductivity, Cation 0.5p.mhos Dissolved 02 7.0 ppb Ammonia, NH3 1.0 ppm Iron, Fe 10 ppb Copper, Cu 10 ppb Chlorides 0.5 ppm Hydrazine, N H24 10-30 ppb at 1st point heater Condenser Cooling Water - Sea Wate-Typical Chemistry:
Element g
Chlorine 18980 Sodim 10561 Magnesim 1272 Sulphur 884 Calcim 400-Potassium 380 Bromine 65 Carbon 28 Strontium 13 Boron 4.6 Silicon 0.02 - 4.0 Fluorine 1.4 Nitrogen (comp) 0.01 - 0.7 Aluminum 0.5 Rubiditrn 0.2 Lithium 0.1 Phosphorus 0.001 - 0.10 Baritan 0.05 Iodine 0.05 Arsenic 0.01 - 0.02 -
Iron 0.002 - 0.02 Manganese 0.001 - 0.01 Copper 0.001 - 0.01 Zinc 0.005 Lead 0.004 Selenium 0.004 Cesium 0.002 2285 140
Uranium 0.0015 tblybdenum 0.0005 Thorium 0.0005 Cerium 0.0004 Silver 0.0003 Vanadium 0.0003 Lathanum 0.0003 Yuttrium 0.0003 Nickel 0.0001 Scandium 0.00004 Mercury 0.00003 Gold 0.000006 10 Radium 0.2 - 3 x to Cadmiun Chromium Cobalt Tin Dimineralizers - Type:
N/A Cooling Tower (open cycle, closed cycle or none):
N/A 2285 10 O
O,