ML17206A528
| ML17206A528 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/08/1978 |
| From: | Erickson P Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811280073 | |
| Download: ML17206A528 (15) | |
Text
NO/ 08 1978 Docket Ho. 50-335 LICENSEE:
FLORIDA POWER AHD LIGHT COHPANY {FPSLQ FACILITY:
ST. LUCIE UNIT NO.
1 HIHUTES OF MEETING WITH FP&L ON STEAN GENERATOR CLEANING The subject meeting was held in Bethesda, Maryland on October 26, 19?8, to discuss FP&L steam generator cleaning program for St. Lucie Unit Ho. 1.
FP&L presented their plans for SG cleaning.
The fo'1lowfng was included in discussions:
Doe Chemical has been selected as the contractor to accomplish the SG cleaning.
2)
Testing programs are noi underway to assure that the cleaning process will remove the deposits in the SG but will not adversely effect steam generators.
3)
The -cleaning system efll have provisions for external heating of solution or using reactor coo'tant pumps for heating.
4)
Decision on s~hether to proceed with cleaning and modifications to support plates vill be based on the November 19?8 steam generator inspection resu1ts.
No leakage has occurred fn any SG tubes at St. Lucie Unit Ho. l.
5)
FP&L <rill develop by late November their position on whether SG cleaning is an unrevfewed safety question.
HRC representatives provided guidance on vihat information >vas needed by the NRC.
A copy (Enclosure 2) of comments given to consolidated OFCICC~
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I'dison for a similar SG cleaning operation at Indian Point Unit 2 was given to FPKt..
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Enclosures:
'ist of Attendees 2.
Comments on SG cleaning at IP<<2 Peter B. Erickson, Project t3anager Operating Reactors Branch 94 Division of Operating Reactors
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MEETING
SUMMARY
DISTRIBUTION ORB¹4 Florida Power
& Light Company Advanced Systems
& Technology Dr. Robert E. Uhrig Vice President P. 0.
Box 529100 Miami, Florida 33152 Mocket File NRC PDR L PDR ORB;,4 Rdg.
NPR Rdg H.
Denton E. 6.
Case Y. Stell.o 8.
Grimes T. Carter D. Eisenhut A. Schwencer D. Ziemann T. Ippolito R. Reid V. Noonan P.
Check G. Lainas G. Knighton Project Manager OELD OI&E(3)
R.
Ingram R. Fraley, ACRS(16)
TERA J.
Buchanan Meeting Summary File Program Support Branch NRC..Participants B. D. Liaw E. H., Webster D. C. DiIanni G. Lear R. B. Samworth P. O'onnor C. J.
De Bevec F. Almeter
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Q UNITEDSTATES NUCLEAR REGULATORYCOMMISSION 1NASHINGTON, D. C. 20555 November 8, 1978 Docket No. 50-335 LICENSEE:
FLORIDA POWER AND LIGHT COMPANY (FP&L}
FACILITY:
ST. LUCIE UNIT NO.
1 MINUTES OF MEETING WITH FP&L ON STEAM GENERATOR CLEANING The subject meeting was held in Bethesda, Maryland on October 26,
- 1978, to discuss FP&L steam generator cleaning program for St. Lucie Unit No. l.
FP&L presented their plans for SG cleaning.
The following was included in discussions:
1)
Dow Chemical has been selected as the contractor to accomplish the SG cleaning.
2)
Testing programs are now underway to assure that the cleaning process will remove the deposits in the SG but will not adversely effect steam generators.
3)
The cleaning system will have provisions for external heating of solution or using reactor coolant pumps for heating.
4)
Decision on whether to proceed with cleaning and modifications to support plates will be based on the November 1978 steam generator inspection results.
No leakage has occurred in any SG tubes at St. Lucie Unit No. l.
5)
FP&L will develop by late November their position on whether SG cleaning is an unreviewed safety question.
NRC representatives provided guidance on what information was needed by the NRC.
A copy (Enclosure
- 2) of comments given to consolidated
Edison for a similar SG cleaning operation at Indian Point Unit 2 was given to FPSL.
Enclosures:
1.
List of Attendees 2.
Comments on SG cleaning at IP-2 Pe er B.
ric son, Project Manager Operating Reactors Branch ¹4 Division of Operating Reactors
MEETING OCTOBER 26, 1978 ST.
LUCIE STEAM GENERATOR CLEANING
'Enclosure 1
PARTICIPANTS Peter B. Erickson B. D. Liaw E.
H. Webster D. C. DiIanni R.
W. Reid George Lear Robert B. Samworth Paul
'W. O'onnor C. J.
De Bevec Frank Almeter Charles A. Moore George E. Liebler Larry L. Leskovjan Alan L. Gould Robert M. Hartranft Charles B. Brinkman Martin L. Marugg Francis P. Frauson, Jr.
Raymond W. Boyle ORGANIZATION NRC ORB - 4 NRC DOR EB NRC IE SLS - Proj. Insp.
NRC DOR ORB - 4 NRC DOR ORB - 4 NRC DSE ESB NRC - Env. Spec.
Br.
NRC DOR - 2 NRC IE DROI NRC EB DOR FPSL SGCC - Proj. Mgr.
FPSL GO - Staff Supv.
FP8(L FP8L GO - Staff-Technical CE - Pro.
Mgr.
CE CE Dow Chemical - Proj. Mgr.
Dow Chemical -
RSD
Enclosure 2
Comments on Con Edison's Safet Anal sis Outline Corrosion Considerations 1.
Describe the cleaning processes that will be used for cleaning the IP-2 steam generators.
Include chemical compositions of all
- solvents, concentrations, makeup rates, pH, temperature, velocities, time, etc.
2.
Describe in detail the methods for controlling the cleaning process.
To ensure proper control, material samples should be included showing that the actual corrosion during IP-2 is comparable to the results obtained during the development phase.
3.
Based on the development phase give the total corrosion of all materials that will be in contact with the solvents, i.e.,
a total change in material thickness that will result from the complete cleaning process (i.e., sludge removal, crevice cleaning passivation phase, etc.).
4.
Give the effects on corrosion rates due to postulated changes in solvent concentrations, velocities, pH, temperature and time.
State all types of protection that will be employed to prevent off normal conditions.
5.
Provide the effects of galvanic corrosion rate caused by copper or carbon steel'(i.e.,
A285 etc.) to Inconel.
6.
The material corrosion test program should include 405 stainless steel which is support plate material for the advanced steam generator design.
Solvent Tests 1.
Demonstrate that no adverse affects will occur under AVT chemistry following chemical cleaning.
2.
Show that incompatibility of various spent or depleted chemicals will not exist during all phases of the cleaning process, waste handling and disposal.
Vibration Studies Change the last sentence in Item B of the submittal to read as follows:
"These tests are designed to confirm the analysis and will include both straight and U bend tube tests that will show that accelerated tube fatigue, fretting or local wear will not occur under post cleaning conditions."
Pre and Post Cleanin Ins ections Add the following to this section:
"The final rinse solution will be analyzed to determine the concentration.
levels of any acids, Cl P or other corrosive residue from the cleaning process."
Waste Dis osal The safety analysis report should address the following issues for handling and disposing of the radioactive and chemical wastes.
l.
Estimate the total quantity of radioactive effluents expected during chemical cleaning and handling and disposal of spent solutions.
If applicable indicate what treatment systems will be used to minimize radioactive airborne effluents.
2.
Estimate the quantity of radioactive wastes that will be generated during the chemical cleaning of Ip-1
& IP-2.
Identify any abnormal radio-nuclides (e.g.',
Fe-55 and Hi-63) which may be present.
3.
Identify potential sources of radioactive liquid wastes.
Describe the liquid radwaste system's ability to store and process these wastes.
Estimate the quantity and radioactivity of each identified waste component.
Describe the criteria which will be used to determine if the wastes will be processed thru (1) filters, (2) evaporators and/or (3) demineralizers prior to release to the environment.
For each potential source of radioactive liquid evaluate the environmental impact.
Identify the equipment, including both permanently installed or mobile units, available to process the wastes.
Evaluate the possibility of the local contaminated solution(s) having deleterious effect(s) on the equipment employed to process it.
4.
For the entire chemical cleaning process, estimate the total volume and curies in the solid waste matter to be disposed of.
Describe the solidification process.
Describe the solidified properties including liquid content, leachability, stability and biodegrad-ability.
Clearly describe the criteria to be used for disposal of the waste materials including unrestricted release or burial at a licensed burial site.
5.
Describe the form of all chemical waste which will be buried at a low-level waste disposal site.
Your response should include waste chemical constituents and properties, flammability, corrosive
- behavior, expected volumes and expected radioactive concentrations.
Discuss any feature (e.g., solidification and containers) which will minimize the possibility of release of the chemical agents into the burial site.
6.
Provide an estimate man-rem assessment of each of the chemical cleaning based on the experiences from IP-1 program.
Provide a summary of exposure reduction techniques (e.g., shielding and personnel training) which will be implemented to minimize exposures if applicable.
D.
C.
Di Ianni ORB)/4:DOR
Safet Anal sis Outline For S.G.
Secondar Side Chem Cleanin IP82 Demonstration Cleanin Con Edison will provide NRC the following:
Corrosion Rates A.
Technical documents will contain a list of materials (identi-fied 'as to components) which will be exposed to the chemical cleaning solvents during the Unit,No.
2 cleaning job.
B.
Chemicals in the solvents to be used in the Unit No.
2 cleaning job will be listed.
C.
Corrosion rates for metals of construction of the Unit No.
2 steam generators based on the laboratory tests of the two cleaning processes will be documented.
D.
Corrosion rates for metals of construction of the Unit No.
2 steam generators based on the Phase I cleaning will be documented.
Solvent Tests A.
Results of both chemical cleaning processes used during Phase I
of the job will be forwarded for information.
This will include a description of the Phase I cleaning procedure and process system flow diagrams.
B.
A comparison of the results achieved during the Phase I cleaning with,the expected results of Unit No.
2 cleaning job will be forwarded for information.
Cost Cleanin Effects A.
A study of any residuals produced the following the Phase I
cleaning will be performed and documented.
B.
A study of any anticipated effects of the cleaning process residuals on materials of construction of the Unit No.
2 steam generators will be forwarded for information.
Phase II Plans A.
The plans and a detailed description of the svstem modifications and/or system additions for Unit No.
2 cleaning will be trans-
mitted.
B.
Unit No.
2 cleaning procedures and process system flow diagrams will be transmitted.
Vibration Studies A.
An analysis of the effect on tube aging from anticipated patterns of vibration will be documented.
B.
The results of a model test program will be transmitted.
These tests are designed to confirm the analysis and will include both straight and U bend tube tests.
Pre and Post Cleainn Ins ections A.
Eddy current inspection results (performed before and after the Unit No.
2 cleaning) will be transmitted.
B.
Results of visual examinations of the tube support plates (performed before and after the Unit No.
2 cleaning) will be transmitted.
C.
An analysis of the sludge removed from the Indian Point Unit No.
2 steam generators will be transmitted.
Waste Dis osal A.
Plans for the handling and disposing of the radioactive and chemical wastes from the Unit No.
2 cleaning job will be transmitted.