ML19326D103
| ML19326D103 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/17/1975 |
| From: | Bauman R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8006060627 | |
| Download: ML19326D103 (28) | |
Text
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FROM:
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R.C. Bauman 12-17-75 12-19-75 XXX TO:
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Additional information regarding., imp.le-
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7 mentation.of Regulatory Guides' for tbc THIS D'0CUMENT CONTAINS. l Midlcnd Plant......
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General Offices: 212 West Micnigen Avenue dacxson, Micnigan 49201 e Area Code S17 788-0550
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07' 73l December 17, 1975
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Director of Nuclear Reaction Regulatic(Q, 7,.m '[f 7 Lu Attention:
Mr. Roger Boyd, Acting Dire
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4.il jgg U. S. Nuclear Regulatory Commission
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Washington, D. C. 2055
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4 /Is DOCKET NUMBERS 50-329, 50-330 REGULATORY GUIDE bEETINGS FILE: 0505 SERIAL:
2013 The enclosed information responds to Mr. A. Schwencer's November 19, 1975 letter requesting additional infor=ation regarding imple=entation of Regulatory Guides for the Midland Plant. These guides deal with Materials Engineering and were discussed with your staff on October 20, 1975 R. C. B au=an Project Engineer RCB/fy 14087
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r 121.1 Reg. Guide 1.2 With regard to Regulatory Guide 1.2, " Thermal Shock to Reactor Pressure Vessels" (11/2/72), the staff does not consider the material presented to be an exception to this guide.
Please confirm your full conformance with Regulatory Guide 1.2.
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Response
As stated in the Regulatory Guide position presented at the October 20, 1975 NRC/CPCo/B&W conference, B&W complies with this Guide.
At this conference, the Staff considered the position presented to indicate full compliance with this Regula, tory Guide.
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121.2 Reg. Guide 1.14 With regard to Regulatory Guide 1.14, " Reactor Coolant Pump f
Flywheel Integrity" (10/27/71), please confirm that the design j'
of the reactor coolant pump and flywheel assembly provides access to enable 1007. ultrasonic volumetri~c examination of the flywheels.
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Response
1 By removal of covers and some motor hardware, the upper surface and rim of each pump motor flywheel will be accessibic for ultrasonic testing. This exposure will allow sufficient ultrasonic testing to assure safety.
Removal of the flywheel from the motor shaft will not be done.
The flywheels have already been procured.
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122.1 Reg. Guide 1.31 l
Regarding Regulatory Guide 1.31, " Control of Stainless Steel
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Welding," the degree of compliance with the April 11, 1974, Interim Position of the Guide (i.e., Branch Technical Position MTEB 5-1) is incomplete for the equipment Within the B&W scope of supply, for the balance of plant components, and for installation f
of the NSSS and BOP components. Describe the status of the procurement of the NSSS and BOP austenitic stainless components and the status of the welding installation of the austenitic stainless steel components of the NSSS and the. BOP.
Response
I.
The status of procurement of ASME Section III balance of plant austenitic stainless steel components and of welding installation of these components is as follows-l
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Procurement Stat:us of Balance of Plant Components Procurement
% Manufacturing Component Date Complete Comments M-104A 5-20-74 2%
8 Spools j
Shop Fabricated installed Suspended Piping for Nuclear Ser-vice M-105 5-3-73 100%
all spools shipped Shop Fabricated Embedded and Buried S.S. Piping M-115 3-11-74 100%
all spools shipped Reactor Building Spray Header Pip-ing i
M-123A 5-24-74 5%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" and Larger M-123B 10-25-74 0%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" and Larger M-123C 10-25-74 10%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" and Larger Z J-255AC
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7-1-74 25%
Nuclear Service Butterfly Control Valves J-256 Not Placed Nuclear Service Solenoid Valves l
J-258 7-28-75 0%
Nuclear Control.
Valves M-125A 6-14-75 5%
Nuclear, S.S.
Valves, 150#
through 400# rat-ing, 2 1/2"'and
122.1 Cont'd
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Prreuren nt Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments M-146 6-5-75 0%
Centrifugal Water Chillers M-125B 6-14-74 25%
Nuclear, S.S.
Valves, 150#
through 400# rat-ing, 2 1/2" and Larger M-132 11-27-74 0%
Nuclear Butter-fly Valves M-149 not placed Air Handling Units M-125C 6-21-74 15%
Nuclear, S.S Valves, 150#
'through 400# rat-ing, 2 1/2 and Larger M-129A 9-16-74 0%
Nuclear, S.S.
Valves 2" and' Smaller M-129B 9-16-74 0%
Nuclear, S.S.
Valves 2" and Smaller M-112 not placed Expansion Bellows for R.B. Penetra-tion M-204 not placed 2" and Smaller Nuclear Carbon Steel and Austen-itic Stainless Steel Pipe, Flanges and Fittings M-134 not placed Nuclear Plug Valves n
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122.1 Cont'd Procurement Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments M-18 Not Placed Auxiliaries Emergency Diesel Generator M-61 11-13-74 0%
Makeup System Filters M-54 2-12-74 20%
Reactor Building Spray Pumps M-55 10-25-74 0%
Fuel Pool Cool-ing Heat Ex-changers M-56 1-14-75 0%
Fuel Pool Cool-
- ing and Safeguards Chilled Water Pumps M-64 3-29-74 5%
Miscellaneous Nuclear Tanks M-90 not placed Incore Instru-ment Tanks ~
M-180
'not placed Service Water Self Cleaning Strainers M-182 not placed WYE Strainer and Traps I
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- ^3 122.1 c:nt'd Procurement Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments C-18 10-6-75 0%
Field Irected Storage Tank 5 J-255 7-1-74 25%
Nuclear Control Valves J-256 Not Placed Nuclear Service Solenoid Valves J-258 7-28-75 0%
Nuclear Service Butterfly Control Valves 1
J-260 Not Placed Instrument Valves and Bypass Manifolds for Nuclear Service w-e o
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g^3 122.1 Cont'd It is the applicant's position that the checking of production welds is not necessary when the procurement of the stainless steel weld filler materials is correctly controlled.
The weld filler materials are purchased with the minimum ferrite con-tent higher than the minimum ferrite content recuired by the Regulatory Guide.
The Regulatory Guide requires 3% minimum ferrite as measured while Bechtel requires 8% minimum as determined from chemical analysis.
This 5% margin is suffi-cient to take into account any differences in the method of determining ferrite. As was stated in the Septembdr 11, 1975 submittal to the NRC. this position will be verified on three other projects through production testing of welds.
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II.
The procurement status of austenitic stainless steel components in the NSSS, supplied by B&W, is as follows:
Procurement Status for B&W Supplied Equipment i
Date of Component Shipped s
Component Procurement Unit 2 Unit I l
1.
Pressurizer 6-24-70 Yes Yes 2.
Pressurizer spray nozzle 6-24-70 Yes Yes valves 3.
Pressurizer spray control 7-13-70 Yes Yes valve i
4.
Pressurizer, safety valve 4-26-70 No No l
S.
Pressurizer, electrically 10-28-70 Ne No actuated relief valve 6.
Vent valves, reactor internals 5-22-69 Yes Yes 7.
Letdown cooler (tubeside) 11-6-73 No No 8.
Control rod drive assemblies 12-28-70 Yes No (pressure retaining portion) 9.
R.C. Pump castings and 1-27-69 Partial No internals
- 10. Reactor coolant piping 5-8-69 Yes Partial
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- 11. Reactor vessel 8-12-70 Yes Yes l
- 12. Closure assembly flanges for 6-26-75 No No incore detector
- 13. Purification system makeup 3-30-72 No No pump
- 14. Purification system storage 12-27-73 Yes Yes tank
- 15. Decay heat removal pumps 10-9-70 Partial No
- 16. Reactor internals, upper 7-23-70 Yes No j
plenum assembly, core support i
sub-assembly, core support I
shield assembly m
'17. Core flooding tank 8-4-69 Yes No 1
- 18. Nozzles, R.B. spray system 10-15-74 Yes Yes
- 19. Pressurizer heater bundle 6-24-70 Yes Yes
- 20. Closure head, reactor vessel 8-12-70 Yes Yes No installation welding of the NSS has been started.
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(a 122.3 Reg. Guide 1.36 Regarding Regulatory Guide 1.36, " Nonmetallic Thermal Insul-ation for Austenitic Stainless Steel," the degree of compli-ance with the Guide is satisfactory for the entire Midland project except for assurance that all of the provisions of Regulatory Position I will be complied with.
Provide infor-mation regarding chloride control during field installation of nonmetallic thermal insulation.
Response
The nonmetallic thermal insulation for austenitic stainless steel will be procured under a subcontract.
This subcontract will cover both insulation design and installation.
Compli-ance with the requirements of Regulatory Guide 1.36 will be part of this subcontract.
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122.4 Reg. Guide 1.43 Regarding Regulatory Guide 1.43, " Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components," the degree of compliance with the Guide is incomplete for the B&W scope of supply and for the Midland Construction of BOP components.
and installation of the NSSS.
Describe the status of the pro-curement and construction of Midland Units 1 and 2 involving stainless steel weld cladding of low-alloy steel components.
Position C.I.b of the Regulatory Guide should be complied with for " low-heat-input" as well as "high-heat-input" weld cladding procedures.
Response
I.
The status of procurement and construction of ASME Section III balance of plant Midland Unit 1 and 2 components involving stainless steel weld cladding of low-alloy steel components is as follows:
Procurement
% Manufacturing Component Date Complete Comments M-55 10-25-74 0%
. Fuel Pool Cooling Heat Exchangers The subject guide was written because very small cracks were found in SA-508 Class 2 material when it was weld overlay clad. The cracks were only found when the cladding was performed using weld processes with extremely high heat inputs (strip and 6-wire submerged are).
Underclad cracks have not been found in SA-508' Class 2 type
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materials when they were clad with low heat input weld pro-cesses such as SMAW or GMAW.
Production testing and laboratory studies have confirmed this position.
There is no justification to control low heat input cladding processes in the same manner as high heat input processes.
For the work performed directly by Bechtel, no cladding will be done on SA-508 Class 2 type of materials and no high heat input processes will be utilized.
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122.4 cont'd II.
The procurement status of NSSS components involving stainless steel weld cladding of low-alloy steel components is as follows:
Procurement Status for B&W Supplied Equipment Date of Component Shipped Component Procurement Unit 2 Unit 1 1.
Pressurizer 6-24-70 Yes Yes 2.
Reactor vessel' 8-12-70 Yes Yes 3.
Closure head, reactor vessel 8-12-70 Yes Yes 4.
Steam generator (tubeside) 7-69 Yes No No ins 6411ation welding of the NSS has started.
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s 122.5 Reg. Guide 1.44 Regarding Regulatory Guide 1.44. " Control of the Use of Sensi-tized Stainless Steel." the degree of compliance with the Guide is satisfactory for the equipment within the B&W scope -
of supply. except for lack of compliance with Regulatory Guide Position C.3; and is satisfactory for the BOP eauipment and for field fabrication and installation, except for lack of compliance with Regulatory Guide Positions C.3 and C.6.
Describe the status of the procurement and welding installa-tion of austenitic stainless steel components in Midland 1 and 2.
Response
I.
The status of the procurement and welding installation of ASME Section III austenitic stainless steel components in Midland Units 1 and 2 is as follows:
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122.5 cont'd Prreurr nt Status of Balenen of Pirnt Components Procurement
% Manufacturing Component Date Complete Comments M-104A 5-20-74 2%
8 Spools Shop Fabricated installed Suspended Piping for Nuclear Ser-vice M-105 5-3-73 100%
all spools shipped Shop Fabricated Embedded and Buried S.S. Piping M-115 3-11-74 100%
all spools shipped Reactor Building Spray Header Pip-ing M-123A 5-24-74 5%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" i
and Larger M-1233 10-25-74 0%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" and Larger M-123C 10-25-74 10%
Nuclear S.S.
Valves 600# Rating and Higher 2 1/2" and Larger J-255AC 7-1-74 25%
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Nuclear Service Butterfly Control Valves J-256 Not Placed Nuclear Service Solenoid Valves J-258 7-28-75 0%
Nuclear Control Valves M-125A 6-14-75 5%
l Nuclear, S.S.
Valves, 150#
through 4000 rat-ing, 2 1/2" and Larger
122.5 c nt'd i~
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Procurement Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments M-146 '
6-5-75 0%
Centrifugal Water Chillers M-125B 6-14-74 25%
Nuclear, S.S.
Valves, 150#
through 400# rat-ing, 2 1/2" and Larger M-132 11-27-74 0%
Nuclear Butter-fly Valves M-149 not placed Air Handling Units M-125C 6-21-74 15%
Nuclear, S.S Valves, 150#
through 400# rat-ing, 2 1/2 and Larger M-129A 9-16-74 0%
Nuclear, S.S.
Valves T' and Smaller M-129B 9-16-74 0%
Nuclear, S.S.
Valves 2" and Smaller
' M-112 not placed Expansion' Bellows for R.B. Penetra-tion M-204 Not Placed 2" and Smaller Nuclear Carbon Steel and Austen-itic Stainless Steel Pipe, Flanges and Fittings M-134 not placed Nuclear Plug Valves
122.5 cr t'd Procurement Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments M-18 Not Placed Auxiliaries Emergency Diesel Generator M-61 11-13-74 0%
Makeup System Filters M-54 2-12-74 20%
Reactor Building Spray Pumps M-55 10-25-74 0%
Fuel Pool Cool-ing Heat Ex-changers M-56 1-14-75 0%
Fuel Pool Cool-
- ing and Safeguards Chilled Water Pumps M:-64 3-29-74 5%
Miscellaneous Nuclear Tanks M 90 not placed Incore Instru-ment Tanks M-180 not placed Service Water Self Cleaning Strainers M-182 not placed WYE Strainer and Traps O
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Procurement Status of Balance of Plant Components (continued)
Procurement
% Manufacturing Component Date Complete Comments C-18 10-6-75 0%
Field Erected Storage Tanks J-255 7-1-74 25%
Nuclear Control Valves J-256 Not Placed Nuclear Service Solenoid Valves J-258 7-28-75 0%
Nuclear Service Butterfly Control Valves J-260 Not Placed Instrument Valves and Bypass Manifolds for Nuclear Service
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122.,5 c:nt'd rS r~s Position C3 states that all solution heat treatment of austen-itic stainless steel should be qualifieu 'or each heat of material and/or heat treatment practice.
The qualification to con-sist of meeting the requirements of ASTM A-262 practice A or E.
All austenitic stainless steels are furnished in the solution heat treated condition in accordance with the material specifi-cation. For material s.olution heat treated by the material manufacturer, testing to determine susceptibility to intergran-
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ular corrosion is performed only wh'en required by the material specification.
During fabrication and installation austenitic stainless steels are not permitted to be exposed to temperatures in the range of 8009F to 1500 F, except for velding and hot forming. Welding practices are controlled to avoid severe sensitization, and solution heat treatment is required follow-ing hot forming in the temperature range 800 F to 1500 F.
Position C6 states that welding procedures should be qualified to verify that it will not sensitize the base material heat affected zone. The qualification should consist of meeting the requirements of ASTM-A262 practice A or E.
Welding practices are controlled to avo1d severe sensitization in the heat affected zone of unstabilized austenitic stainless steel. The controls include procedural control of welding heat input, limiting interpass temperature and limiting weaving.
Bechtel controls weld heat input during field installation by using shielded metal-arc welding'(SMAW) and ga tungsten-arc welding (GTAW) processes only, and limiting the size of elec-trodes for each process to 5/32-inch and 1/8-inch diameter maximum, respectively.
The interpass temperature is controlled so as not to exceed 350PF.
Intergranular corrosion testing is not performed on a routine
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basis. Performing intergranular cdrrosion tests for each weld-ing procedure serves no useful purpose when welding practices are controlled as discussed above.
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122.5 c nt'd
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II.
The procurement status of austenitic stainless steel components for the NSSS, supplied by B&W, is as follows:
Procurement Status for NSSS B&W Supplied Equipment Date of Componenc Shipped Component Procurement Unit 2 Unit 1 1.
Pressurizer 6-24-70 Yes Yes 2.
Pressurizer spray nozzle 6-24-70 Yes Yes 3.
Pressurizer spray control 7-13-70 Yes Yes valve 4.
Pressurizer safety valve 4-26-70 No No 5.
Pressurizer electrically 10-28-70 No No actuated relief valve 6.
Vent valves, reactor 5-22-69 Yes Yes internals 7.
Letdown cooler, (tubeside) 11-6-73 No No 8.
R.C. pump castings and 1-27-69 Partial No internals 9.
Control rod drive assemblies, 12-28-70 Yes No pressure retaining portion
- 10. Reactant coolant piping 5-8-69 Yes Partial
- 11. Reactor vessel 8-12-70 Yes Yes
- 12. Closure head, reactor 8-12-70 Yes Yes vessel
- 13. Closure assembly flanges 6-26-75 No No for incore detector
- 14. Purification system makeup 3-30-72 No No pump
- 15. Purification system storage 12-27-73 Yes Yes tank
- 16. Decay heat removal pumps 10-9-70 Partially No
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- 17. Reactor internals, upper 7-23-70 Yes No plenum assembly, core support sub-assembly, core support shield assembly
- 18. Core flooding tank 8-4-69 Yes No
- 19. Nozzles, R.B. spray system 10-15-74 Yes Yes
- 20. Pressurizer heater bundle 6-24-70 Yes Yes 9
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122.6 Reg. Guide 1.50 Regarding Regulatory Guide 1.50, " Control of Preheat Temperature for Welding of Low-Alloy Steel," the degree of compliance with the Guide is satisfactory for the equipment within the B&W scope of supply and is satisfactory for the construction of BOP equipment and the installation of the NSSS, except for lack of compliance with Regulatory Guide Position 1.a.
Describe the status of the construction of the BOP equipment and the installation of the NSSS.
Response
The status of procurement and manufacture of ASME Sectica III balance of plant low-alloy steel components (low alloy as given in ASME Section III, Division 1-Subsection NA Table 1-10.1) is as follows:
Procurement Status of Balance of Plant Low-Alloy Components Procurement
% Manufacturing Component Date Complete Comments M-14 Auxiliary Feedwater Not Placed Pumps M-52 5-13-74 20%
Component Cooling Water Pumps M-55 10-25-74 0%
Fuel Pool Cooling
- Heat Exchangers M-64 3-29-74 5%
Miscellaneous
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Nuclear Tanks M Not Placed Service Water Pumps M-ll7 3-15-74 60%
600# Carbon Steel Nuclear Valves 2 1/2" and Larger M-204 6-13-74 0%
2" and Smaller Nuclear Carbon Steel and Austenitic SS Pipe, Flanges and Fittings
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Procurement Status of Balance of Plant Low-Alloy Components (continued)
Procurement
% Manufacturing Component Date Complete Comments M-104A 5-20-74 2%
8 Spools Installed.
Shop Fabricated Suspended Piping for Nuclear Service M-117 3-15-74 60%
Nuclear Carbon Steel Valves, 600# Rating and higher, 2 1/2" and larger M-118A 5-16-74 40%
Nucicar C.S. Valves, 600# Rating and Higher, Impact Tested Material, 2 1/2" and Larger M-118B 5-9-74 0%
. Nuclear C.S. Valves, 600# Rating and Higher. Impact Tested Material. 2 1/2" and Larner M-120 7-16-74 20%
Nuclear. C.S. Valves.
150 through 400#
Rating. 2 1/2" and Larger M-127A-9-16-74 0%
Nuclear C.S. Valves, 2" and Smaller M-127B 9-16-74 50%
Nuclear C.S. Valves.
2" and Smaller M-127C 9-16-74 20%
Nuclear C.S. Valves.-
2" and Smaller
,m 122.'6 cont'd 9
Procurement Status of Balance of Plant Low-Alloy Components (continued)
Procurement
% Manufacturing Compenent Date Complete Comments M-132 11-27-74 0%
Nuclear Butterfly Valves J-253 6-7-74 0%
Atmosphe~ric Steam Dump Valves C-50B 6-5-69 20%
Containment Personnel Lock and Equipment Hatches The applicants response to position C.l.a for balance of plant components is that when impact testing is required, the welding procedure controls both the preheat and interpess temperature. However, if impact testing is not required, the welding procedure only controls the minimum required preheat.
Welding procedure for impact tested materials control the maximum interpass temperature because it is considered good practice for the impact properties. ' The purpose of Regulatory Guide 1.50 is to control preheat with the intention of prevent.ing hydrogen delayed cracking.
The significant parameter for the control of hydrogen cracking is the minimum preheat which is in compliance with the Regulatory Guide.
Further assurance that cracking has not occurred is obtained through preoperational ultrasonic examinations in accordance with ASME Section XI.
These examinations are in general more sensitive than radiograph proformed during manufacturing.
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122.7 Reg. Guide 1.65 Regarding Regulatory Guide 1.65, " Materials and Inspections for Reactor Vessel Closure Studs," the degree of compliance with the Guide is incomplete for the B&W scope of supply.
Provide more specific information on fracture toughness, tensile
~
properties, and inspection. Also, provide degree of com-pliance with Positions C.3 and C.4 of the Guide.
Response
Specific information on fracture toughness, tensile properties, and inspections is found in Topical Report BAW-10046P, " Methods of Cocpliance With Fracture Toughness and Operational Requirements of _G CFR 50, Appendix G."
Guide Position C.3 requires that the studs be protected against corrosion.
The Guide position submitted at the October 20, 1975 conference, stated that the reactor vessel closure studs are coated with a corrosion-resistant film to protect them in the event of exposure to a potentially corrosive media.
In addition, the studs are raised and secured to the closure head, removed and stored with this head within the containment in an area well separated from the refueling canal.
Should the studs be inadvertently exposed to corrosive media (borated water), they will be immediately cleaned.
Guide inspections listed in C.4 will be performed to the extent permitted by the procurement status' of the closure studs:
procured, manufactured and delivered to the site.
The intent of Paragraph C.4.a is satisfied I
through the performanet eC a volumetric examination as required by Section XI, Tables IWB-2500 and 2600.
The removal of the studs to comply with the surface examination can lead to damage to the threads due to galling, mechanical damage, etc.
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122.8 Reg. Guide 1.66 Regarding Regulatory Guide 1.66, " Nondestructive Examination of Tubular Products," the degree of compliance with the Guide is incomplete for the equipment within the B&W scope of supply and for the B0P components.
Tubular products should be examined either in accordance with all of the positions of the Guide or in accordance with the requirements of the ASME Code,Section III, Summer 1974 Addenda.
Describe the status of the procurement of the equipment within the B&W scope of supply and the B0P components.
Response
I.
The status of procurement of balance of plant ASME Section III tubular products which fall under the scope of Regulatory Guide 1.66 is as follows:
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Procurement Status of Balance of Plant Components Procurement
% Manufacturing Component Date Complete Comments M-104A 5-20-74 2%
Shop Fabricated Suspended Piping for Nuclear Ser-vice M-204 6-13-74 0%
2" and Smaller Nuclear Carbon Steel and Austenitic SS Pipe, Flanges and Fittings M-149 Not Placed Air Handling Units M-146 6-5-75 0%
Water Chillers M-163 11-15-74 0%
Reactor Building Coolf.g Units M Not Placed Auxiliaries Emergency Diesel Generators M-55 10-25-74 0%
Fuel Pool Cooling Heat Exchangers
+s M'-51 2-5-74 60%
Component Cooling Water Heat Exchangers J-210 Not Placed 1
Nuclear Sampling System m
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Tubular products have been procured in conformance with the ASME Section III Code Addenda in effect at the date of purchase.
To attempt to retrofit the requirements of the Summer 1974 Addenda on components that were purchased to earlier addenda and are in various stages of completion is not justifiable.
When a tubular product has been inc'orporated into a part, piping subassembly or component; the item is much more difficult to examine than a simple tubular product.
The added
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delays and increased costs caused by the additional non-destructive examinations are not justified.
In addition, the increased amount of detection of defects resulting from meeting the requirements of the Summer 1974 Addenda of ASME Section III when compared to that required by the Code Edition and Addenda _in effect at the time of the purchase order is minimal when compared to the delays, increased
' costs and, in some cases, the physical impossibility of performing the examination.
II.
The procurement status of NSSS equipment containing tubular products and supplied by B&W, is as follows:
Procurement Status of NSSS Components Pate of Component Shipped Component Procurement Unit 2 Unit 1 1.
Pre'ssurizer 11-6-73 No No 6-24-70 Yes Yes 2.
Letdown cooler (tubeside) 3.
Control rod drive suscmblies, 12-28-70 Yes No pressure retaining portion
- 4. ~ Reactor vessel 8-12-70 Yes Yes 5.
Closure head, reactor vessel 8-12-70 Yes Yes 6.
Steam generator, tubeside 7-69 Yes No 7.
Decay heat removal cooler, 11-4-70 Yes Yes tubeside 8.
Pressurizer heater bundle 6-24-70 Yes Yes
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