ML20236V072
| ML20236V072 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 10/31/1987 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19302D109 | List: |
| References | |
| NUDOCS 8712040069 | |
| Download: ML20236V072 (18) | |
Text
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4 WESTINGHOUSE CLASS 3 AMENDMENT 2 TO RESAR-SP/90 PDA MODULE 1 PRIMARY SIDE SAFEGUARDS SYSTEM O .
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O B712040069 871123
{DR ADOCK 05000601 PDR O WAPWR-PSSS AMENDMENT 2 7017e:1d OCTOBER, 1987 iri i
- I AMENDMENT 2 TO RESAR-SP/90 PDA MODULE 1 PRIMARY SIDE SAFEGUARDS SYSTEM i
Instruction Sheet Remove current pages 1.8-7 through 1.8-11 and replace with revised pages 1.8-7' through 1.8-11. ,
Remove all of current Section 6.1 (pages 6.1-1 through 6.1-8) and replace with revised Section 6.1 (pages 6.1-1 through 6.1-9).
i Place Amendment 2 (pages 281-1 and 281-2) behind Amendment 1 in Module 1 j Questions / Answers section.
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O WAPWR-PSSS AMENDMENT 2 7017e:Id OCTOBER, 1987
. REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 l
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Module 1 l
(C"A 281.1 Provide the interface requirements of the protective coating (6.1.2) systems (paints) inside the containment building for the balance-of-plant.
RESPONSE
Since the Emergency Water Storage Tank (EWST) recirculation flow paths have been specifically designed to accommodate virtually unlimited quantities of failed protective coating (and other) debris -- without significant sump screen blockage or ingestion into the Integrated Safeguards System (ISS) - protective coatings inside containment are not considered safety class systems (Nuclear Service Level I). Therefore the specifications and quality assurance requirements for all protectivo coatings O' inside containment will be for Nuclear Service Level II. This means basically that high quality coatings that are generically known to be suitable for nuclear service will be specified, but in accordance with Regulatory Guide 1.54/ ANSI N101.4-1972,
" quality assurance and/or documentation -- is not mandatory and shall be used only to the extent required by the project specification". Thus, while high quality proven coatings will be verified, no interface requirements are necessary from a p nuclear safety standpoint for the protective coating systems V inside the containment building for the balance-of plant.
However, Section 6.1.2, " Organic Materials" and Table 1.8-2 have been revised to clearly state that protective coatings inside containment are not safety related.
o WAPWR-PSSS 281-1 AMENDMENT 2 7017e:1d OCTOBER, 1987
281.2 Describe the system to be used to adjust the pH value of the A (6.1.3, containment sump water to the range of 8.0 to 10.5 during U 6.5.2) recirculation, and provide the interface requirements of the system for the balance-of plant.
RESPONSE
O Following a LOCA, the potential for chloride induced stress corrosion cracking of stainless steel components, boric acid attack on carbon steel components, and the volume of hydrogen produced by the corrosion of galvanizing and zine based paints is minimized, and the iodine retained in solution is maximized, by raising the pH of the recirculating core cooling solution into the range of 7 to 9.5.
Westinghouse proposes to perform the pH adjustment utilizing l trisodium phosphate (TSP) in a passive basket system installed in-containment.
Baskets containing TSP will be located in the compartment containing the RCDT and RCDT pump. The TSP will dissolve and mix with the containment spray water which drains into the RCDT compartment from the refueling cavity and then flows up to the j EWST spillway pipes. J The mass of trisodium phosphate, crystalline (Na PO4 3 + 12H 2O) required to raise the pH of the recirculating solution to 7.0 is approximately 18,000 lbs.
O Nodule 13 Questions 281.3 through 281.7 are addressed in Amendment 1 to RESAR-SP/90 PDA Module 13, " Auxiliary Systems".
I O 281-2 AMENDMENT 2 i WAPWR-PSSS '
7017e:1d OCTOBER, 1987
, TABLE 1.8-2 (Cont'd)
,e-(J RG Wo. 1.54 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS Rev. O APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS (JUNE 1973)
O Q Nodule Refer- All protective coatings inside containment are non-safety ence Section 6.1 related (Nuclear Service Level II). In accordance with Regulatory Guide 1.54/ ANSI N101.4-1972, quality assurance and documentation is not mandatory from a safety point of view. Nevertheless, high quality protective coatings are highly desirable from the standpoint of corrosion protection, plant cleanliness, low maintenance and decontaminability. Therefore, equipment located in the containment building is separated into four categories to identify the degree of quality assurance necessary to achieve these aims. These categories of equipment are as follows:
Category 1 - Large equipment Category 2 - Intermediate equipment Category 3 - Small equipment Category 4 - Insulated / stainless steel equipment A discussion of each equipment category follows:
- a. Category 1 - Large Equipment The Category 1 equipment consist of the following:
Reactor coolant system supports.
Reactor coolant pumps (motor and motor stand).
Accumulator tanks.
Manipulated crane.
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l WAPWR-PSSS 1.8-7 OCTOBER, 1987 5952e:1d AMENDMENT 2 l
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. TABLE 1.8-2 (Cont'd)
O RG No. 1.54 Since this equipment has a large surface area and is (cont'd) procured from only a few vendors, it is possible to implement tight controls over these items.
Stringent requirements have been specified for protective coatings on equipment through the use of a painting g specification in our procurement documents. This
\ specification defines requirements for:
- 1. Preparation of vendor procedures.
- 2. Use of specific coating systems which are qualified to ANSI N101.2.
- 3. Surface preparation.
- 4. Application of the coating systems in accordance with the paint manufacturer's instructions.
- 5. Inspections and nondestructive examinations.
- 6. Exclusion of certain materials.
- 7. Identification of all noncomformances.
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- 8. Certifications of compliance.
The vendor's procedures are subject to review by
,, engineering personne., and the vendor's implementation of the specification requirements is monitored during the Westinghouse quality assurance surveillance activities.
O WAPWR-PSSS 1.8-8 OCTOBER, 1987 E952e:Id AMENDMENT 2
TABLE 1.8-2-(Cont'd)
RG No. 1.54 This system of controls provides assurance that the (cont'd) protective coatings will give satisfactory performance in service.
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- b. Cateaory 2 - Intermediate Equipment The Category 2 equipment consists of the following:
Seismic platform and tie rods.
Reactor internals lifting rig.
Head lifting rig.
Electrical cabinets.
Since these items are procured from a large number of vendors, and individually have smaller surface areas,12 it is not practical to enforce the complete set of stringent requirements which are applied to Category 1 items. However, another specification has been implemented in the NSSS procurement documents. This specification defines to the vendors the requirements for:
- 1. Use of specific coating systems which are qualified to ANSI N 101.2.
( 2. Surface preparation.
- 3. Application of the coating systems in accordance with the paint manufacturer's instructions.
O WAPWR-PSSS 1.8-9 OCTOBER, 1987 l E952e:Id AMENDMENT 2
, TABLE 1.8-2 (Cont) ]
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RG No. 1.54 The vendor's compliance with the requirements is also (cont'd) checked during the quality assurance surveillance .!
activities in the vendor's plant. These measures of control provide a high degree of assurance that the protective coatings will give satisfactory performance in service. 2
- c. Category 3 - Small Equipment Category 3 equipment consists of the following:
Transmitters Alarm horns Small instruments Valves Heat exchanger supports These items are procured from several different vendors and are painted by the vendor in accordance with conventional industry practices. Because the total exposed surface area is very small, rio further requirements are specified.
- d. Category 4 - Insulated or Stainless Steel Equipment Category 4 equipment consists of the following:
Steam generators - covered with blanket insulation.
[ Pressurizer - covered with blanket insulation.
O WAPWR-PSSS 1.8-10 DCTOBER, 1987 595'e:1d AMENDMENT 2
. TABLE 1.8-2 (Cont'd)
O RG No. 1.54 Reactor pressure vessel -
covered with rigid (cont'd) reflective insulation.
Reactor cooling piping - stainless steel.
I Reactor coolant pump casings - stainless steel.
Since Category 4 equipment is insulated or is stainless steel, no painted surface areas are exposed within the containment. Therefore, quality assurance 2
requirements are not applicable.
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O O WAPWR-PSSS 1.8-11 OCTOBER, 1987 5952e:1d AMENDMENT 2 L-- - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
SECTION 6.0 ENGINEERED SAFETY FEATURES 6.1 ENGINEERED SAFETY FEATURE MATERIALS
. 6.1.1 Metallic Materials s
6.1.1.1 Naterials Selection and Fabrication
/ Typical materials specifications used for ISS components in the engineered safety features are listed in Table 6.1-1. In some cases, this list of materials may not be totally inclusive. However, the listed specifications are representative of those materials used. Materials utilized conform with the requirements of the ASME Code,Section III, plus applicable and appropriate addenda and code cases.
The welding materials used for joining the ferritic base materials of the engineered safety features conform to or are equivalent to ASME Material Specifications SFA 5.1, 5.2, 5.5, 5.17, 5.18, and 5.20. The welding materials
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v used for joining nickel-chromium-iron alloy in similar base material combination and in dissimilar ferritic or austenitic base material combination, conform to ASME Material Specifications SFA 5.11 and 5.14. The welding materials used for joining the austenitic stainless steel base materials conform to ASME Material Specifications SFA 5.4 and 5.9. These materials are qualified to the requirements of the ASME Code,Section III and Section IX, and are used in procedures which have been qualified to these same rules. The methods utilized to control delta ferrite content in austenitic stainless steel weldments are discussed in the " Reactor Systems" module.
All parts of components in contact with borated water are th. .;ated of or clad with austenitic stainless steel or' equivalent corrosion resistant j
- material. The integrity of the safety-related components of the engineered safety features is maintained during all stages of component manufacture.
Austenitic stainless steel is utilized in the final heat treated condition as required by the respective ASME Code,Section II, material specification for WAPWR-PSSS 6.1-1 OCTOBER, 1987 D437e:1d AMENDMENT 2 l
the particular type or grade of alloy. Furthermore, austenitic stainless steel materials used in the engineered safety features components are handled, protected, stored, and cleaned according to recognized and accepted methods which are designed to minimize contamination which could lead to stress corrosion cracking. These controls are stipulated in Westinghouse
, specifications. Additional information concerning austenitic stainless steel, b including the avoidance of sensitization and the prevention of intergranular attack will be provided in the " Reactor Coolant System" Module. No cold worked austenitic stainless steels having yield strengths greater than 90,000 psi are used for components of the engineered safety features.
Materials utilized in engineered safety features components within the containment that would be exposed to core cooling water and containment sprays in the event of a loss-of-coolant accident are included in Table 6.1-1. These components are manufactured primarily of stainless steel or other corrosion resistant material.
Protective coatings are applied on carbon steel equipment located inside containment (see Section 6.1.2).
The integrity of the materials of construction for engineered safety features equipment when exposed to post-design basis accident conditions have been evaluated. Post-design basis accident conditions were conservatively represented by test conditions. The test program (Reference 6.1.3-1) performed by Westinghouse considered spray and core cooling solutions of the design chemical compositions, as well as the design chemical compositions contaminated with corrosion and deterioration products which may be transferred to the solution during recirculation. The effects of chlorine s (chloride), and fluorine (fluoride) on austenitic stainless steels were considered. Based on the results of this investigation, as well as testing by Oak Ridge National Laboratory and others, the behavior of austenitic stainless steels in the post-design basis accident environment will be acceptable. No
\ cracking is anticipated on any equipment even in the presence of postulated levels of contaminants, provided the core cooling and spray solution pH is maintained at an adequate level. The inhibitive properties of alkalinity O WAPWR-PSSS 6.1-2 OCTOBER, 1987 5437e:1d AMENDMENT 2
(hydroxylion)againstchloridecrackingand the inhibitive characteristic of' boric acid on fluoride cracking have been demonstrated.
1 Information concerning the degree of compliance with Regulatory Guides 1.31, l
" Control of Ferrite Content in Stainless Steel Weld Metal," 1.36, " Nonmetallic )
Thermal Insulation for Austenitic Stainless Steel," 1.37, " Quality Assurance i
O Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants," and 1.44, " Control of the Use of Sensitized Stainless Steel," is provided in Section 1.8.
O- 6.1.1.2 Composition, Compatibility, and Stability of Containment and Core Spray Coolants l
The vessels used for storing engineered safety features coolants include the accumulators, core reflood tanks, and the emergency water storage tank. I I
I The accumulators are carbon steel clad with austenitic stainless steel.
Because of the errosion resistance of these materials, significant corrosive attack on the accumulators is not expected.
The accumulators and core reflood tanks are vessels filled with borated water and pressurized with nitrogen gas. The nominal boron concentration, as boric acid, is 2500 ppm. Samples of the solution are taken periodically for checks of boron concentration. Principal design parameters of the accumulators and core reflood tanks are listed in Table 6.3-2.
The emergency water storage tank is located inside containment and provide the source of borated cooling water for core cooling and containment spray. The O- nominal boron concentration, as boric acid, is 2500 ppm. A description and principal design parameters of the tanks are given in Section 6.3.2.2 and ,
Table 6.3-2.
6.1.2 Organic Materials Since the EWST recirculation flow paths have been specifically designed to accommodate virtually unlimited quantities of failed protective coating (and i
WAPWR-PSSS 6.1-3 DCTOBER, 1987 5437e:1d AMENDMENT 2 i
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other) debris,withoutsignificantsumpscreenblockageor ingestion into the ISS, protective coatings inside conatinment are not considered safety related systems (Nuclear Service Level I). Therefore, the specifications and quality assurance requirements for protective coatings inside containment will be for
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l Nuclear Service Level II. This means basically that generic coatings that 2 l have proven to be suitable for use in nuclear containment will be specified for all ISS components located inside containment, and quality assurance j
specified commensurate with corrosion protection, plant cleanliness, low maintenance, and good decontaminability. An estimation of the amounts of protective coatings on ISS components located inside containment is given in Table 6.1-2; the painted surfaces of this equipment comprise a small percentage of the total painted surfaces inside containment.
For large equipment requiring protective coatings, Westinghouse specifies or l2 approves the type of coating systems utilized; requirements with which the coating system must comply are stipulated in Westinghouse process specifications, which supplement the equipment specifications. For these components, the generic types of coatings used are zine rich silicate or epoxy O based primer with or without chemically-cured epoxy or epoxy modified phenolic tepcoat. Tests have shown that certain epoxy and modified phenolic systems are satisfactory for use inside containment. This evaluation (Reference 6.1.3-2) considered resistance to high temperature and chemical conditions 2 anticipated during a loss-of-coolant accident, as wall as high radiation resistance.
The remaining equipment requires protective coatings on much smaller surface areas and is procured from numerous vendors; for this equipment, Westinghouse specifications require that high quality coatings be applied using good Os commercial practices. Table 6.1-2 includes identification of this equipment and total quantities of protective coatings on such equipment.
p Information regarding compliance with Regulatory Guide 1.54, " Quality V Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," is provided in Section 1.8. >
O WAPWR-PSSS 6.1-4 OCTOBER, 1987 0437e:1d AMENDMENT 2
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- 6.1.3 References I O 6.1.3-1. Whyte, D. D. and Picone, L. F., " Behavior of Austenitic Stainless Steel in Post Hypothetical Loss-of-Coolant Environment," WCAP-7798-L (Proprietary), November, 1971 and WCAP-7803 '(Non-Proprietary),
December, 1971.
6.1.3-2. Picone, L. F., " Evaluation of Protective Coatings for use in Reactor Containment," WCAP-7198-L (Proprietary), April, 1968 and WCAP-7825 i (Non-Proprietary), December,1971.
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O O WAPWR-PSSS 6.1-5 OCTOBER, 1987 D437e:Id AMENDMENT 2 l
TABLE 6.1-1 (Sheet 1 of 3) ;
' ENGINEERED SAFETY FEATURE MATERIALS Valves i
Bodies SA-182, Grade F316 or SA-351, Grade CF8 or CF8M i i Bonnets SA-182, Grade F316 or SA-351, Grade CF8 or CF8M Discs SA-182, Grade F316 or SA-564, Grade 630 or j I
SA-351, Grade CE8 or CF8M Pressure retaining bolting SA-453, Grade 660 Pressure retaining nuts SA-453, Grade 660 or SA-194, Grade 6 ,
Auxiliary Heat Exchangers Heads SA-240, Type 304 Nozzle necks SA-182, Grade F304; SA-312, Grade TP304; SA-240. Type 304 ,
I Tubes SA-213, Grade TP304; SA-249, Grade TP304 '
Tube sheets SA-182, Grade F304; SA-240, Type 304; SA-516, Grade 70 with Stainless Steel Cladding A-8 Analysis Shells SA-240 and SA-312, Grade TP304; SA-351, Grade CF8 O WAPWR-PSSS 6.1-6 OCTOBER, 1987 D437e:1d AMENDMENT 2 l
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TABLE 6.1-1 (Sheet 2 of 3)
ENGINEERED SAFETY FEATURE NATERIALS Flanges- SA-182, Grade F304 or F316
-Auxiliary Pressure Vessels, Tanks, Filters, etc.
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Shells and heads SA-351, Grado CF8A; SA-240, Type 304; O SA-264 Clad Plate of SA-537, Class I with i
SA-240, Type 304 Clad and Stainless Steel Wald Overlay A-8 Analysis l l
l Flanges and nozzles SA-182, Grade F304; SA-350, Grade LF2 or LF3 with SA-240, Type 304 and Stainless Steel Weld Overlay A-8 Analysis Pipe SA-312 and SA-240, Grade TP304 or T'316 O Seamless l
Pipe fittings SA-403, Grade WP304 Seamless l Closure bolting and nuts SA-193, Grade B7 and SA-194, Grade 2H Auxiliary Pumps l
1 Pump casings and heads SA-351, Grade CFB or CF8M; SA-182, Grade F304 or'F316 l Flanges and nozzles SA-182, Grade F304 or F316; SA-403, Grade WP316L Seamless O Piping SA-132, Grade TP304 or TP316 Sesmiess 1
O WAPWR-PSSS 6.1-7 OCTOBER, 1987
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5437e:1d AMEN 0 MENT 2
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.- TABLE 6.1-1 (Sheet 3 of 3)
ENGINEEREG SAFETY FEATURE MATERIALS i
Stuffing or packing box cover SA-361,- Grade CF8 or CF8M, SA-240 Type O 304 or Type 316; SA-182, Grade F304 or F316 Pipe fittings SA-403, Grade WP316L Seamless; SA-213; Grade TP304, TP304L, TP316 or TP316L O Closure bolting and nuts SA-193, Grade B6, B7 . or B8M; SA-194, Grade 2H or BM; SA-453, Grade 660; and Nuts SA-194, Grade 2H, 6, 7, and 8M O
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O O WAPWR-PSSS 6.1-8 OCTOBER, 1987 5437e:1d AMENDMENT 2
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- TABLE 6.1-2 I
PROTECTIVE C0ATINGS ON WESTINGHOUSE SUPPLIED EQUIPMENT INSIDE CONTAINMENT 2
Component PaintedSurfaceArea(fty ISS system component supports 11,230 Accumulator tanks and core reflood tanks 7,600 Remaining equipment (such as valves, <5,000 auxiliary tanks and heat exchanger supports, transmitters, alarm horns, small instruments, etc.)
)
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O WAPWR-PSSS 6.1-9 OCTOBER, 1987 5437e:1d AMENDMENT 2 1
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