ML19261B221

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Discusses Three Programs That Evaluate Results of Chemical Cleaning:Component Insp Program,Metal Surveillance Program & Radiation Level Determination
ML19261B221
Person / Time
Site: Dresden Constellation icon.png
Issue date: 11/28/1978
From: Stephenson B
COMMONWEALTH EDISON CO.
To:
Shared Package
ML19261B218 List:
References
78-1550, NUDOCS 7902140253
Download: ML19261B221 (20)
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Text

{{#Wiki_filter:.. BBS LTR #78-1550 November 28, 1978 TO: J.L. White

SUBJECT:

Surveillance Programs Required for Chemical Cleaning Attached you will find the programs required by the NRC in their letter of conditional approval of the chemical cleaning of _ Dresden 1, December 9, 1975 These programs are approved by the station for use in conjunction with the chemical cleaning project, and should be submitted to the NRC for their approval as required. j B.B. Stephensen Station Superintendent Dresden Nuclear Power Station BBS/JH:krk Attachment cc: G.L. Redman D.L. Farrar S. Lange S. Hunsader J. Harrison E. Budzichowski File Copy / Chemical Cleaning / Q t

The Chemical Cleaning of Dresden I has three programs that are required to evaluate the results. Those programs are: 1. Component inspection Program 11. Metal Surveillance Program Ill. Radiation Level Determination 1. Component inspection Program The chemical c.eaning licensing submittal committed Commonwealth Edison to a component inspection program. "A Component inspection program will be implemented specifically for the Dresden I chemical cleaning. This inspection program will include a baseline inspection (of selected com-ponents) before the cleaning with post cleaning inspections immediately after cleaning before (reactor) operations and at (the) two subsequent (refueling) outages. This component inspection program will be to insure that the chemical cleaning has caused no degradation (of the reactor system) and will be separate from the normal Dresden 1 inservice inspec-tion Program. The component inspection Program will be based on the requirements of the ASME Boiler and Pressure vessel code, Section XI, but will only include those categories that are relevant to the chemical cleaning process. The acceptance criteria and component selection will remain onstant, and will be based on the code in effect at the time of the first inspection." The conditional approval from the NRC dated December 9, 1975, for the Chemical Cleaning requi red that: "A pre-service inspection program for the primary coolant boundary will be formulated and submitted for our review and approval prior to returning the reactor to service." This inspection program is to be distinct from the required ASME Section XI in-service inspection program, however, components that are common to both programs will be included. The program is divided into four time periods: 1. Pre-Cleaning 2. Immediate Post Cleaning (be fo re returning the reactor to service) 3 The First Refueling Outage 4. The Second Refueling Outage The following is a list of components to be inspected, and Table I will define the components to be inspected in each time period. LIST OF COMPONENTS (UT - Ultrasonic Testing / PT - Penetrant Testing / V - Visual) ASME CATEGORY INSPECTION METHOD COMPONENT 1. B-B UT Meridonal Head Weld, at 7 Loc., 1 Ft. UT Ci rcumferent ial Head Weld, From 186 to 2060, 1 Ft. LIST OF COMPONENTS (Continued) A. (Continued) ASME CATEGORY INSPECTION HETHOD COMPONENT 2. B-C UT Vessel-To-Flange Weld, From Bolt #18 To Bolt Hole #24, 3.5 Ft. dead-To-Flc.1ge Weld, From Bolt Hole #18 To Bolt Hole #24, 3.5 Ft. 3 B-F UT, PT System Line/ System Weld # Weld Tyn;c Unload-1901-10" 11 P-V ing 1906-10" 16 P-V System 4. B-l-1 V 6" X 6" Patch of Vessel Cladding Near Riser Nozzle N2L (3440) 5 B-J UT System Line/ System Weld # Weld Type (P Pe Welds) I Recirc. 0124-22" 33 Tee-P Suction 0126-22" 8 P-V Recirc. 0132-18" 16 P-E Return 0136-18" 24 P-E Risers 0117-16" 17 P-E 0118-16" 17 P-E Down-0104-16" 18 P-E Comers 0107-16" 18 P-E Unioad-0404-10" 379S P-E ing 0405-6" FW9652-2 P-E System Recirc. 0324-6" CLI P3 Bypass Loop Down-0137-6" 3E P-E Comer Cross-Tie Clean-Up 0301-4" 8E P-E Supply Clean-Up 0306-4" FW9652-3 P-E Re t u rri Vessel 0504-4" 207 P-E Drain 0504-4" 212 P-E Poison 0407-3" 173 P-E System LIST vF COMPONENTS (Continued) A. (Continued) ASME CATEGORY INSPECTION METHOD COMPONENT 6. B-N-1 Visual

1) Top Grid - Inspect Sample of Cross Beam Welds
2) Core Support Plate - Inspect Bolting That Secures it To Bottom Grid
3) Turning Vane Supports - Inspect Bolting and Welds.
4) Bottom Grid - If Possible, Cross Beam Welds Will Be Inspected.

B. ASME CATEGORY INSPECTION METHOD COMPONENT 1. B-D UT Reactor Inlet Nozzle, NIB (150 ) ~ Reactor Outlet Nozzle, N2A (15 ) V W ids) Steam Drum Riser Nozzle, N11E (Line 0115) Steam Drum Downcomer Nozzle, N12E (Line 0105) 2. B-F UT,PT Sa fe End-To-Nozzle Welds : Reactor Inlet, N1b (150 ) 3) Reactor Outlet, N2A (15 ) Steam Drum Riser, N11E (Line 0115) Steam Drum Downcomer, N12E (Line 0105) C. One reactor coolent recirculation pump will be disassembled and inspected for corrosion and wear. The effects of the chemical cleaning will be determined. D. Two valves will be disassembled and inspected for corrosion ana wear. The effects of the chemical cleaning will be determined. NOTE: Any component in this program may be exchanged for a similar com-ponent due to physical configuration of the weld or component that makes it difficult or impossible to examine. 11. Metal Surveiliance Program The need to know the ef fects of the chemical cleaning on the materials of construction during the cleaning and subsequent reactor operation will be addressed by this program. The conditional approval of the cleaning required that: "A post-cleaning surveillance program which includes additional (metal) sur-veillance samples and a specimen withdrawal and examination schedule will be submitted for review and approval prior to returning the reactor to service." There will be five sets of samples prepared. Each set will be identical except for the 410 samples. Each set consists of: 1. Pressurized Tubes at 100% of 550 F Yield Strength (6 specimens per material) A. 304 stainless steel - furnace sensitizcd - as welded. B. 304L stainless steel - furnace sensitized - as welded C. Inconel 600 - furnace sensitized - as welded. D. Incoloy 800 - furnace sensitized - as welde'd. E. Zircoloy 2 - as welded. 2. Bent Beam (6 specimens) A. 410 stainless steel - tempered to 3/4 hard. 3 Flat - weight loss coupons (3 specimens per material) A. 304 stainless (sensitized at 1200 F for 50 hours). B. 304L stainless (sensitized). C. 316 stainless (sensitized). D. 347 stainless. E. Inconel 600 (sensitized). F. Incoloy 800. G. Zircalloy 2. H. 405 stainless. 1. 410 stainless. J. Monel 400. K. Mastelloy B The five sets will be used as follows: Set 1. Chemical cleaning set - to be removed after cleaning. 410 bent beam sample will be stressed to 1002 550 F yield strength. Set 2. Long term set in reactor pressure vessel. (RPV). In during cleaning and remains in for reactor operation. 410 bent beam sample will be unstressed during cleaning and then stressed to soo Z 5500F Y.S. for reactor operation. Set 3 Long term control set in RPV. Placed in for reactor operations. 410 bent beam sample to be st ressed to ho

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for reactor operations. Set 4. Long term test loop set. Inserted in RPV for cleaning, then transferred to test loop for reactor operation. if test loop does not operate during reactor operation, then set will remain in RPV. 410 bent beam to be unstressed during cleaning, then stressed to % 550 F Y.S. for operations. Set 5 Long term test loop control. Inserted in test loop for rc3ctor operations (or in RPV if test loop not operational). 410 bend beam to be stressed to Z 550 F Y.S. for operations. Table I shows insertion and withdrawal schedule. 111. Rai'at ion Level De terminat ion The working dose rates and amounts of radioactive materal before, after and during subsequent reactor operation are the paraneters by which the success of the chemical cleaning will be measured. The program of measuring these levels are as follows: 1. Gemma ray scanning of 35-40 points with a Ge(li) detector. The following points are included: A. Steam drum compartment (5) 1. North manhole. 2. South Manhole. 3 Steam drum mid-section. 4. Southwest riser. 5. Southwest downcomer. B. Secondary steam generator rooms A-B-C-D point; on primary recirculation lines (4 X 7) 1. Recirc. pump suction. 2. Recirc. pump bowl. 3 Se.ondary steam generator. 4. Secondary steam generator discharge. 5 Elbow on SSG discharge line. 6. Discharge isolation valve. 7 Discharge isolatio.1 valve bypass valve. C. Pipeway 1. Unloading heat exchanger return line. 2. Cleanup return line. 3 Downcomer line.

. 2. C-P points. To be determined at the time of the initial survey to include operation and maintenance work zones. NOTE: Any point on this program may be substituted for or eliminated because of physical problems of the scanning equipment. Table i defines the periods of each inspection.

TABLE I 1. Pre-Cleaning A. Component inspection Program Section A B. Metal Surveillance Sets 1, 2, 4 will be inserted in the turning vane of the reactor vessel. C. Radiation Level Determination. All gamma scan points and C.P. points will be surveyed. 2. Immediate Post Cleaning A. Component inspection Program Section A, B, C, D B. Metal Surveillance Sets 1, 4 will be removed from turning vane. Set 3 will be inserted in turning vane. Sets 4, 5 will be inserted in test vessel "A" of corrosion test loop (if test loop is not operabic, then sets 4, 5 will be in turning vane). C. Radiation Level Determination All gamma scan points and C.P. will be surveyed. 3 First Refueling Outage (end of cycle 12) A. Component inspection Program Section A, B B. Metal Surveillance All sets in turning vane to be inspected and re-inserted. Sets in corrosion test loop to be inspected as required. C. Radiation Level Determination All gamma scan peints and C.P. points to be surveyed. 4. Second Refueling Outage (end of cycle 13) A. Component inspection Program Section A, B, D B. Metal Surveillance All sets in turning vane to be inspected. Sets in corrosion test loop to be inspected as required. All sets removed. C. Radiation Level Determination All points gamma scan point and C.P. points to be surveyed. 5 All programs to be terminated at the conclusion of the second refueling outage unless evaluation requires programs to be extended.

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