ML20078D840
| ML20078D840 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/07/1995 |
| From: | Fortin A GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19311B683 | List: |
| References | |
| 25A5668, 25A5668-R02, 25A5668-R2, NUDOCS 9501310016 | |
| Download: ML20078D840 (13) | |
Text
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25A5668 SH NO.1 REV.2 EIS IDENT: SHROUD STABILIZER HDW REVISION STATUS SHEET DOC TITLE SHROUD STABILIZER HARDWARE LEGEND OR DESCRIPTION OF GROUPS
'1TPE: DESIGN SPECIFICATION FhfF:
QUAD CITIES 1 AND 2 MPL NO: PRODUCT SUMhfARY SEC. 7 TIIIS ITEM IS OR CONTAINS A SAFETYREIATED ITEM YIS 2 NO O EOUIP CIASS CODE P.
REVISION C
0 RM-01586 OCT 311994 1
JL TROVATO RJA NOV 161994 CN01849 CHK BY:JL TROVATO ER MOHTASHEMI DAN O 71995 o
RJA JL TROVATO CN02047 CHK BY:JL TROVATO ER MOHTASHEMI PRINTS TO MADEIW APPROVALS GENERAL ELECTRIC COMPAhY 175 CURTNER AVENUE A. FORTIN 10/18/94 E.R. MOllTASIIEMI 10/18/94 SANJOSE, CALIFORNIA 95125 CHK BY ISSUED OCT 31 1994 A. FORTIN 10/18/94 R.J. AIIMANN CONT ON SHEET 2 MS-WORD 9501310016 950116 PDR ADDCK 05000254 O
PDR 1
t 25A5668 SH NO. 2 ED REV. 2 f
1
- 1. SCOPE l.l' This document defines the design and performance requirements for stabilizers for the core i
shroud which will funcdonally replace welds H1 through H7. In addition, the circumferentialjet pump support plate H8 weld is cracked completely through and 360 degrees around. A sketch of the welds and their nomenclature is given in Figure 1. All AShfE Code requirements are given in j
the document of Paragraph 2.1.1.g. This specification herein contains those requirements that are not AShiE Code requirements.
- 2. APPLICABLE DOCUhiENTS 2.1 General Electric Documents. The following documents form a part of the specification to the extent specified herein.
2.1.1 Sunnortine Documents Arc Welding of Austenitic Stainless Steel P50YP102 Rev.10 a.
b.
Sensitization Tests for Austenitic Stainless Steel, hfodified ASThf E50YP13 Rev.2 A262 Pracdce E Determination of Carbide Precipitadon in Wrought Austenitic E50YP20 Rev.4 c.
Stainless Steel (hfodified ASThi A262 Practice A) d.
Examination for Intergranular Surface Attack E50YP11 Rev.3 Age Hardening of NI-CR-FE Alloy X750 P10JYP2 Rev.12 c.
f.
Liquid Penetrant Examination E50YP22A Rev.3 g.
Reactor Pressure Vessel-Code Design Specification 25A5669 Rev.2 h.
Reactor Vessel Thermal Cycles 921D265 Rev.1 i.
Scismic Analysis of Quad Cides 1 and 2 Reactor Vessel and 257HA925 Rev.1 Internals j.
Seismic Response of Quad Cities Reactor Pressure Vessel and
- DAR93, Rev.1 Internals k.
Quad Cities Seismic Analysis - Sdff Stabilizer RA199 Dated 1/29/70 L.
NEDC-32406, Class II, September 1994, " Final Test Report CRD Peformance Evaluation Testing with Driveline hicasurement."
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i 2.1.2 Supplemental Documents. Documents under the following identities are to be used with this specification:
l Reactor Components 383HA715 Rev. 4 a.
l b.
Essential Components 22A3041 Rev.1 2.2 Codes and Standards. The following documents of the latest issue (or specified issue) form a part of this specification to the extent specified herein.
2.2.1 American Society of Mechanical Encineers (ASME) Boiler and Pressure Vessel (B&PV)
Code Section III, Appendices,1989 Edition.
a.
I i
b.
Section IX, Welding and Brazing Qualifications,1989 Edition.
c.
Section III, Subsection NG,1989 Edition.
l d.
Section XI, Rules for Insenice Inspection,1989 Edition with no Addenda.
Section II, Materials Specification, Latest edition.
c.
2.2.2 American Society for Testine and Materials (ASTM)
ASTM A-182, Specification for Forged or Rolled Alloy-Steel Pipe Flanges, Forged Fittings, and a.
Valves and Parts for High-Temperature.
b.
ASTM A-240, Specification for Heat-Resisting Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels.
ASTM A-262, Detecting Susceptibility to Intergranular Attack in Stainless Steel.
c.
d.
ASTM A-479, Specification for Stainless and Heat-Resisting Steel Bars and Shapes for Use in Boilers and Other Pressure Vessels.
ASTM A-480, Specification for General Requirements for Flat-Rolled Stainless and Heat-e.
Resisting Steel Plate, Sheet, and Strip.
f.
ASTM B-637, Specification for Precipitation Hardening Nickel Alloy Bars, Forgings, and Forging Stock for High-Temperature Senice.
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ASTM A-276, Standard Practices for Detecting Susceptibility to Intergranular Attack in Austenitic Stainless Steel.
2.3 Comed Documents Quad Cities 1 and 2 UFSAR, Chapter 3 and Appendix C.
a.
b.
Comed Technical Requirements document for Dresden/ Quad Cities Core Shroud Repair, NEC-12-4056, Rev. O.
c.
Comed Purchase Order No. 354964.
d.
Babcock & Wilcox Stress Report #8, Rev.1 (GE VPF# 1744-211-1), " Support Skirt Analysis,"
Page C-1-1.
2.4 Other Documents Project Instruction - Shroud Repair for H1 through H7 Welds for Commonwealth Edison a.
i Quad Cities Nuclear Power Station GENE-771-634994, Rev.1.
h.
BWROG -VIP, Core Shroud Repair Design Criteria, latest revision.
GENE-L12-00819-05, DRF L12-00819 (26), September 1994, Class 3, " Core Shroud Blowdown c.
Load Calculation During Recirculation Suction Line Break by TRACG Analysis for Dresden Units 2 & 3 and Quad Cities Nuclear Power Stations, Units 1 & 2.
d.
DRF B13-01740, " Comed Shroud Fix for Quad Cities."
GENE-771-71-1094, Rev.1; " Quad Cities Units 1&2 Shroud Repair Seismic Analysis."
e.
l 2.5 U.S. Federal Recister Code of Federal Reculations (CFR) 10CFR50.55a(a)(3), Use of an Alternate to Code Requirements.
a.
l b.
10CFR50-Title 10, Energy: Chapter 1, Nuclear Regulatory Commission, Part 50, Licensing of l
Producdon and Utilization Facilities, Appendix B, Quality Assurance Criteria for Nuclear Power Plants.
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- 3. GENERALDESCRIPTION 3.1 The purpose of the shroud stabilizers is to structurally replace welds H1 through H7. Welds H1 through H6 are all of the circumferential welds in the shroud, as well as the (H7) bimetallic attachment weld of the shroud to the shroud support cylinder. These welds were required to both vertically and horizontally support the core top guide, core support plate, and shroud head; and l
to prevent core flow bypass into the downcomer region. Weld H8 is a circumferential inconnel to-inconnel weld between the shroud support ring and jet pump support plate which provides i
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25A5668 SH NO 5 W
GENuclearEnangy aty. 2 horizontal support for the core shroud. The core top guide and core support plate horizontally support the fuel assemblies and maintain the correct fuel channel spacing to permit control rod insertion.
- 4. REQUIREMENTS 4.1 Code 4.1.1 The shroud stabilizer components are not classified as ASME Section III Code components.
i However, material strength properties shall be obtained from the document in Paragraph 2.2.1.a.
Material Physical Properties may be obtained from the document in Paragraph 2.2.1.e or documents in Paragraph 2.2.2, as deemed appropriate. Welding qualification shall be performed in accordance with the document in Paragraph 2.2.1.b. The nomenclature for stress intensity l
used in this document is the same as that used in the document of Paragraph 2.2.1.c.
4.2 Structural Criteria 4.2.1 All structural analysis shall be performed in accordance with the criteria given in the Quad Cities UFSAR, Comed Technical Requirements Document for Dresden/ Quad Cities Core Shroud Repair (Ref. 2.3.b) and BWROG - VIP, Core Shroud Repair Design Criteria (Ref. 2.4.b). All of the load combinations given in Paragraph 4.3.5 shall be shown to satisfy the primary stress limits given in the Quad Cities UFSAR, with values of SFmin as defined in Paragraph 4.3.6.
The appropriate SFmin values have been incorporated into the allowabic stress intensity values given in Paragraphs 4.2.1.1 and 4.2.1.2.
4.2.1.1 The primary stresses (Pm, P1, and Pl + Pb) in the existing shroud, during Normal and Upset events, shall be shown to be less than Sm,1.5Sm, and 1.5Sm respectively.
During Emergency events, the allowable stresses are increased by a factor of 1.5 times the values for Normal and Upset events. During Faulted events, the allowable stresses are increased by a factor of 2.0 times the values for Normal and Upset events.
4.2.1.2 The stresses (Pm, Pm + Pb, and Pm + Pb + Q) in the repairhardware, during Normal and Upset events, shall be shown to be less than Sm,1.5Sm, and 3.0Sm respectively.
During Emergency events, the allowable primary stresses are increased by a factor of 1.5 times the values for Normal and Upset events. During Faulted events, the allowable primary stresses are increased by a factor of 2.0 times the values for Normal and Upset events. Secondary stresses are notlimited during Emergency and Faulted events.
1 4.2.2 The values of Sm and Sy as well as any other required material property shall be obtained from the document in Paragraph 2.2.1.a (ASME Code,Section III Appendices), except for alloy X-750. The values of Sm and Sy for alloy X-750 at operating temperature are 47,500 psi and l
92,300 psi respectively. These values must be verified from the Certified Material Test Reports (CMTR's). The value of Sm must be determined using the method of Appendix III from the document of paragraph 2.2.1.a. If Certified Material Test Reports (CMTR's) are available, the l
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GENuclearEnergy 25A5668 SH NO. 6 aty. 2 value of Sm for XM-19, or for stainless steel may be determined using the method in Appendix III of the document in Paragraph 2.2.1.a.
4.2.3 Stress limit values for bolts shall be from Subsecdon NG-3230 of reference Document 2.2.1.c.
4.2.4 The maximum permanent deflection of any point on the shroud adjacent to either the H2 j
or the H3 weld shall be less than 2.1 inches divided by SFmin, during all of the load combinations specified in Paragraph 4.3.5. The maximum permanent deflecdon of any point on the shroud adjacent to either the H5 or H6 weld shall be less than 0.75 inch divided by SFmin, during all of the load combinations specified in Paragraph 4.3.5. The maximum transient elastic deflection during the seismic event adjacent to either the H5 or H6 weld shall be less than 1.68 inch divided by SFmin specified in Paragraph 4.3.6. The allowable deflections are based on test data from the document in Paragraph 2.1.1.L 4.3 Design Remiirements 4.3.1 General. The shroud repair hardware shall be designed to horizontally support the top guide, core support plate, the fuel assemblies and the shroud head. The shroud repair shall bc designed to prevent upward displacement of the shroud. The shroud repair shall be designed for 40 years, to include 30 effecdve full power years. The shroud repair shall be removable. Because any existing defects in the shroud horizontal welds will not be removed by implementing this repair, the requirements of IWB-3142 cannot be met.
Therefore, approval of this repair alternative must be granted by the office of the NRR.
i 4.3.2 Snring Preload 4.3.2.1 Installation Preload. All of the springs shall be installed with a preload due to bending deflection greater than the deflection resulting from the limiting design upset condition, exclusive ofseismic events. The required installadon spring bending preload is 0.07 inch for the upper springs, and 0.01 inch for the lower springs. (Middle spring is installed without bending preload).
4.3.2.2 Preload Relaxation. The design shall consider an End-of-Life preload relaxation of 5%
for the upper springs near the H2 and H3 welds and a relaxation of 5% for the middle spring near the H4 weld and a relaxadon of 5% for the lower springs near the H5 and H6 welds.
Preload relaxadon value of 5% is based on the reference document 2.4.d.
4.3.3 Emironmental Conditions i
4.3.3.1 Temperature. The design temperature for the repair hardware is 575 degrees F. The l
operating temperature is 550 degrees F. Operating temperature shall be used for emergency and i
faulted evaluations.
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25A5668 SH NO. 7 aev. 2 i
l 4.3.3.2 Radiation. The maximum neutron radiation level (flux) at the shroud stabilizers in the 2
shroud vessel annulus is 3.3E11 neutrons /cm /sec. This will not affect the properties of the stabilizer materials for the design life specified in Paragraph 4.3.1.
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4.3.3.3 Water Chemistry Cold Shutdown /
Power Ooeration Refuel (max Values) l Conductivity (@25 C) 0.3 umbo 2.0 umho/cm Chloride 5.0 PPB 100 PPB Sulfate 5.0 PPB 100 PPB pH @ 25'C) 7.0 5.3 - 8.6 Dissolved Oxygen (HWC) 20 PPB NA l
Dissolved Oxygen (NWC) 300 PPB 7.0 PPM j
4.3.3.4 Water Flowin the Annulus At and above thejet pump suction inlet-3,190,000 lbs/hr.
a.
b.
Below thejet pump suction inlet - 8,550,000 lbs/hr.
4.3.4 PhysicalInterfaces i
4.3.4.1 The shroud repair hardware shall restrain the shroud during all of the load combinations in Paragraph 4.3.5. The allowable permanent motion is dependent on the safety significance of the portion of the shroud under consideration. The allowable permanent motion for those portions of the shroud, which affect control rod insertion, is given in Paragraph 4.2.4. For the remaining portion of the shroud below H3, the allowable permanent motion is determined such hat the reflooding of the inside of the shroud up to two thirds of core height is assured. For the portion of the shroud above H2, the allowable motion is 2.56 inches, which assures that the core spray lines are not impacted by the shroud. The allowable motion of the Shroud Repair Hardware shall be less than 0.75 inch near thejet pump riser brace to prevent impact.
Note.
2.56 inches is estimated from; Shroud Dwg #713E861, Rev. 6 and Reactor Assembly Dwg #104R921, Rev.13.
0.75 inches is field measured by the Installer.
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GENuclearEnm R668 su N0 8 4.3.4.2 The shroud repair hardware must provide features which facilitate handling during installation and removal. The upper and lower springs shall be movable without removing the tie rod and without welding, in order to permit inspection of the reactor pressure vessel with GERIS 2000. The upper springs must also permit inspection of the core spray line and any clamp modification fix.
j 4.3.4.3 All parts shall be captured and held in place with a method that will last for the design life given in Paragraph 4.3.1.
4.3.5 Load Combinations. The load combinations that the shroud and the shroud repair shall be analyzed for are from the Quad Cities UFSAR, Comed Technical Requirements document for Dresden/ Quad Cities Core Shroud Repair, and BWROG - VIP shroud design criteria recommendations. The limiting Normal / Upset event is an Operating Basic Earthquake (OBE),
plus Normal pressure differences, plus dead weight plus Thermal Load. The Emergency 1 event is a Design Basis Earthquake (DBE), plus normal pressure differences, plus dead weight. The Emergency 2 event is a main steam line LOCA plus dead weight. The Emergency 3 event is a recirculation line LOCA plus dead weight. The Faulted 1 event is a Design Basis Earthquake (DBE), plus a main steam line LOCA, plus dead weight. The Faulted 2 event is a Design Basis Earthquake (DBE), plus a recirculation line LOCA, plus dead weight.
4.3.5.1 The pressure differences for normal / upset and faulted conditions are given in the table below. The pressure inside the shroud is higher than that outside of the shroud, and the pressure is higher below the core plate than above the core plate (Ref. 2.3.b).
Comnonent Normal / Unset Condition Faulted Condition Shroud Head and Upper 8 psi 20 psi Shroud Core Plate 17 psi 30 psi Lower Shroud 25 psi 43 psi 4.3.5.2 A new seismic analysis based on the documents in Paragraph 2.3 and 2.1.1.i,j and k shall be performed which includes the shroud stabilizers. The shroud stabilizers shall function for the entire continuum from an uncracked shroud to a fully cracked shroud. Therefore, multiple conditions must be analyzed, for both the DBE and the LOCA events. As a minimum, the j
following shroud conditions shall be analyzed:
l a.
The OBE in both the E-W and N-S directions for:
j 1.
Uncracked shroud 2.
Hinge at all welds l
3.
Hinge at H3 1
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GENuclearEnetyy nzy. 2 4.
Hinge at H4 5.
Hinge at H7 b.
The DBE in both the E-W and N-S directions for:
1.
Uncracked shroud 2.
Hinge at all welds 3.
Hinge at HS 4.
Hinge at H4 5.
Hinge at H7 6.
Roller at HI 7.
Roller at HS 8.
Roller at H4 9.
Roller at H7 The limiting seismic loads on the stabilizer are given in the table below (Ref. 2.4.e).
l DBE Comnonent OBE Emercency FaultsIl Upper Spring 47,700 lb.
95,400 lb.
94,600 lb Middle Spring 16,500 lb.
33,000 lb.
33,300 lb Lower Spring 79,500 lb.
159,000 lb 158,500 lb Set of 4 Tie Rods (each) 95,000 lb.
306,000 lb.
126,000 lb 4.3.5.3 Two steady state thermal conditions shall be evaluated. The first is Normal operation with the shroud at 550 degrees F, and the stabilizer assembly at 538 degrees F.
The second condition is an Upset transient (scram with loss of feedwater pumps) with the shroud at 433 degrees F, and the stabilizer at 300 degrees F. The number of events is defined by 921D265 (document 2.1.1.h), except for upset transient condition which are 10 cycles. (Reference 2.3d) l l
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25A5668 SH NO.10 D)
E REV.2 4.3.5.4 During the recirculation line LOCA event, based on the document in Paragrpah 2.4.c.,
there is a resultant force applied to the shroud of 169,000 lbs, with a moment of 13.0E6 in-lb acting at the base of the shroud. This is due to asymmetric pressures in the annulus between the shroud and the RPV. This force exists for a sufficient time (~5 seconds) to be treated as a static force.
4.3.6 Required Safety Factors. The minimum safety factors (SFmin) shall be 2.25 for Normal and j
Upset events,1.5 for Emergency events, and 1.125 for Faulted events. These are based on GE j
l Design Safety Standards for Boiling Water Reactors (NEDE-1037D, Class II, 71NED 15, June 1971) These SFmin will be used to determine the acceptable displacements.
4.4 Materials. ASTM specification material is acceptable for the Shroud Repair. ChiTRs are required for all material. Materials shall be highly resistant to Intergranular Stress Corrosion Cracking (IGSCC) or Irradiation Assisted Stress Corrosion Cracking (IASCC).
4.4.1 The springs shall be made of nicke!<hrome-iron alloy X-750 (UNS N07750). The cobalt content shall be limited to a maximum of 0.09%. Alloy X-750 shall be purchased per ASTM B-637 and age hardened per P10JYP2. Alloy X-750 material shall be tested per E50YP11. In lien of testing per E50YP11, all finished components may incorporate the removal, after solution heat treatment, of a minimum of 0.030 inches of material from all surfaces of the original raw material t
l form.
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4.4.2 The tie rods may be made of either 304,304L,316, or 316L material with a maximum l
carbon content of 0.02%, and annealed at 1900 to 2100 degrees F followed by quenching in circulating water to a temperature below 400 degrees F. The tie rod material shall be tested per E50YP11 and E50YP20. The maximum hardness shall be R,90 for 304 and R,88 for 304L. The maximum hardness shall be R,92 for 316 and 316L. XM-19 with a maximum carbon content of l
0.04% may also be used for fabrication of the tie rods. XM-19 shall be annealed at 2,000 50 degrees F, followed by rapid cooling, and shall be tested per E50YP13, or per ASTM A-262 Practice E.
4.4.3 Other parts shall be made of any of the materials listed in Paragraph 4.4. The filler material i
for anyrequired weld buildups on 300 series stainless steel shall be Type 308L per P50YP102. All assembly welds shall satisfy P50YP102.
4.5 Leakace Due to Repair. Zero leakage is not required. However, the design shall control the normal operating condition leakage to prevent cavitation of thejet pumps. The leakage after any l
required load combination shall be limited such that core flooding to 2/3 the height of the core is assured.
4.6 Insnections. Liquid penetrant examination shall be performed on all final machined surfaces of all stabilizer components, and on all structural welds in accordance with the requirements E50YP22A.
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25A5668 SH NO. I1 GE' h h azv. 2 4.7 Fabricati n I
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Welding requirements are only included herein as a repair contingency.
4.7.1 Welder and Weld Procedure Qualification. Welders and weld procedures shall be qualified per the document in Paragraph 2.2.1.b. Welder qualifications shall include limited access similar to the actual welds'to be completed.
4.7.2 Root Pass. The root pass of all full penetration single sided stainless steel weldedjoints shall be made by the GTAW process. Protective gas back-purging is required for all full penetration single sided weldedjoints until a minimum of 3/16 inch of weld thickness is completed.
4.7.3 Weld Surface Finish. All welds shall have the final outer surface suitable for liquid penetrant examination. The final surface shall meet the hardness requirements of Paragraph 4.4.
- 5. QUALITYASSURANCE 5.1 The shroud repair hardware components are Safety Related as referenced in Paragraph 2.1.2.b, and design, fabrication, and installation activities shall be controlled per a QA Program which satisfies 10CFR50 Appendix B, in order to assure safe and reliable components.
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1 Figure 1. HorizontalWeld Locations l
NOTE: All dimensions are in inches.
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GENE Code Design Specification,25A5669, Revision 2 l
" Quad Cities Units 1 & 2 - Reactor Pressure Vesse!"
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