ML18152A752
| ML18152A752 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Surry, 05000000 |
| Issue date: | 02/08/1988 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-707, NUDOCS 8802180157 | |
| Download: ML18152A752 (12) | |
Text
t VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA. 23261 W. L. STEWAUT VxcE PRESIDENT NucLEAB OPERATIONS February 8, 1988 U. S. Nuclear Regulatory Commissi.on Attention:
Document Control Desk Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNITS I ANO 2 RESPONSE TO UNRESOLVED ITEMS IN IEIR 50-281/86-36 Serial No.
NOD/ETS:vlh Docket Nos.
License Nos.87-707 R3 50-280 50-281 DPR-32 DPR-37 In Inspection Report 50-281/86-36 unresolved issues were identified associated with our Containment Integrated Leak Rate Testing {CILRT) Program.
These items include:
- 1) plant operation and containment leak rate testing with the containment liner weld leak-chase channel plugs installed; and, 2) exclusion of certain Type C test results from the overall containment integrated leak rate.
We committed to provide our evaluation and the technical basis to resolve the two issues in our letter to Dr. J. Nelson Grace, Serial No.
87-375A, dated December 23, 1987. This letter provides our evaluation and the technical basis for plant operation and containment leak rate testing with the containment liner weld leak-chase channel plugs installed.
As discussed in a telephone conversation on January 29, 1988, with Mr. Alan Herdt of your staff, we will submit our evaluation and technical basis for excluding certain penetrations from Type C testing requirements and the overall integrated containment leak rate by Febr.uary 29, 1988.
The Station Nuclear and Safety and Operation Committee has reviewed this information and determined that an unreviewed safety question does not exist for plant operations or containment testing with the weld leak-chase channel plugs installed.
Attachment
- 1.
Technical Evaluation for Surry Containment Liner We.ld Leak-Chase Channels
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cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager Project Directorate II-2 Division of Reactor Projects-I/II
ATTACHMENT I Technical Evaluation for Surry Containment Liner Weld Leak-Chase Channels
~
Background
The NRC has reviewed and approved other plant's evaluation and technical basis for plant operation and containment leak rate testing with containment liner weld leak-chase channel plugs installed.
We intend to establish by comparison that the Beaver Valley and Surry containments are adequately similar.in order to reference the Beaver Valley evaluation as the technical.basis for concluding that plant operation and containment leak rate testing with the containment liner weld leak-chase channel plugs installed is acceptable.
Comparison of Containment and Liners:
Tables 1 and 2 provide a comparison of the geometric properties and materials of the containment and liner for Beaver Valley Unit 1 and Surry Units 1 and 2.
These tables show that the reinforced concrete containment and 1 iner are essentially identical for both plants except for the liner plate material.
The first three rings of liner plates for Beaver Valley Unit 1 are specified as SA-537 Grade B, whereas the Surry liner plates are specified as ASTM-A4.42 or SA-516 Grade 60 materials.
The physical properties of these materials are described. in Table 3.
The other materials that form the liner pressure boundary have essentially the same physical properties.
The deformations of the liner are dictated by the design of the reinforced concrete containment, which provides the strength element to resist internal press.ure and temperature.
Si nee the reinforced concrete containments are essentially the same, and the internal pressure and temperatures described in Table 4 are essentially the same, the liners will have similar deformations.
Therefore, both the Surry and Beaver Va 11 ey Unit 1 1 i ners are di sp 1 acement limited by the containment structure. The leak chase systems would experience these same limited displacements. Thus, the different liner materials for the first three rings of the liners has no impact on the leak chase system even though the physical properties of the liners are slightly different.
The reactor containment liners for Surry Unit 1, Surry Unit 2, and Beaver Valley Unit 1 were fabricated and erected by Graver Tank & Mfg. Co.
in accordance with Specifications NUS-56 for Surry and BVS-136 for Beaver Valley Unit 1.
Both specifications required that "all welding shall conform strictly to the requirements of Section IX of the ASME B&PV code, and shall be performed in accordance with the Seller's welding procedures. as approved by the engineers."
The specifications further required that "all welds shall be either dye.P~,J.letrant or magnetic particle checked."
.:;;~!&~~. ~
The design'}t~~.t1tept and construction details for Beaver Valley Unit 1 and both Surry contalnments and 1 i ners are extremely similar.
The leak chase system was installed to.provide a means for testing the liner welds during
- construction.
Although the leak chase channels were not d~signed as structural elements nor as a pressure boundary, they do provide additional containment leak protection.
==
Conclusion:==
Based on the comparisons discussed above, the containment liner for Surry Units I and 2 is determined to be sufficfently similar to the Beaver Valley Unit I liner to justify referencing the Beaver Valley evaluation for Surry.
Based on the approved Beaver Valley evaluation, we conclude that the test channels are capable of withstanding loads that might be imposed on them during normal test and upset conditions without any loss of function and that the presence of the test channels does not in any way impair the performance of the containment liner itself.
Therefore, supported by our Safety Evaluation and the conclusion that no unreviewed safety question exists, we conclude that the leak-chase channels can be designated as an integral part of the containment liner and operation with the channel plugs installed will not affect containment operation.
Accordingly, we intend to revise the Surry UFSAR to identify the leak-chase channels with the plugs installed as an i ntegra 1 part of the containment design.
This change will be included in a future UFSAR update submittal.
'i
- TABLE I COMPARISON OF GEOMETRIC PROPERTIES OF THE CONTAINMENT & LINER Vertical Cylindrical Wall Thickness (Concrete)
Dome Thickness (Concrete)
Cylindrical Wall Height Overall Inside Height Dome Inside Radius Inside Diam of Cont Shell Cylindrical Wall Liner Seam Welds Anchorage Dome Liner Plate ~~J~kness Seam Welds Anchorage SURRY UNITS 1 & 2 4' -6" 2' -6" 122'-l" 185'-l" 63'-0" 126' -0".
3/8" min Double butt welded except for the lower 30' of the cylindrical shell liner plate where the liner plates are welded using a backing plate.
Continuously anchored to the concrete shell with 5/8" dia x 6 8/16" LG concrete anchor studs (Nelson or Equal)@ 12" staggered spacing starting approx 19" from top of mat.
1/2" nominal wall Double butt welded Continuously anchored to the concrete dome with 5/8" dia x 6 9/16" LG concrete anchor studs (Nelson or Equal).
BEAVER VALLEY UNIT 1 4' -6" 2' -6" 122'-l" 185'-l" 63'-0" 126'-0" 3/8" min Double butt welded except for the lower 30' of the cylindrical shell liner plate where the liner plates are welded using a backing plate.
Continuously anchored to the concrete shell with 5/8" diz x 3'-10" LG Nelson deformed anchors bars spaced@ 12w starting at approx 20" from top of mat then continuing with 5/8" dia x 6 9/16" LG con anchor studs (Nelson or Equal).
1/2" min Double butt welded Continuously anchored to the concrete dome with 5/8" dia x 6 9/16" LG concrete anchor studs (Nelson or Equal).
Bottom Liner Plate Thickness Welds Backing Plates Gas Testing Channels Gas Testing Angles Bridging Bars Connection of Gas - Testing Channels & Angles to Liner Pl'ate pical Test Connection Plug TABLE I (Cont'd)
SURRY UNITS 1 & 2 1/4" min All welds of the 1/4" plate to either bridging bars or bridging plates are made with a backing plate.
PL 1/4" x 1 1/2" Ch 1 1/2" x l" x 3/16" L 1 1/2" X 1 1/4" X 3/16" PL 1/2" x 7" 1/4" Fillet Weld (Typ) 1/8" 6000 lbs SCRD half coupling with socket head pipe plug, ASTM-A350 Gr. LFl.
One each test segment.
1/8" NPT socket heat pipe plug.
ASTM-A350 Gr. LFl.
BEAVER VALLEY UNIT 1 1/4" min All welds of the 1/4"
. plate to either bridging bars or bridging plates*
are made with a backing plate.
PL 1/4" x. 1 1/2" Ch 1 1/2" X l" X 3/16" L 1 1/2" X 1 1/4" X 3/16" PL 1/2" x 7" 3/16" & 1/4" Fillet Welds (Typ) 1/8" 6000 lbs SCRD half coupling with socket head
- pipe plug, ASTM-A350 Gr. LF2.
One each test segment.
l/8K NPT socket head pipe plug.
ASTM-A350 Gr. LF2.
~J Shell Plates Shell Plates Dome Plates Bottom Plates
~ping Penetration Sleeves Piping Penetration Reinforcing Rings Piping Penetration Reinforcing Bar Anchoring Plates Piping Penetration End Caps Backing Plates and Anchors
~as Testing Channels TABLE 2 COMPARISON OF MATERIAL SPECIFICATION SURRY UNITS 1 & 2 SPECIFICATION NUS-56 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-A333, Gr. 0 ASTM-A442, Gr. 60/ASTM-A518, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-A350, Gr. LF2/
ASTM-A516, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 ASTM-Al31, Gr. C (Rolled Shape)
BEAVER VALLEY UNIT 1 SPECIFICATION BVS-136 Shell plates el. 690'-ll" to el. 720'-ll", ASTM-A537, Gr. B, quenched and tempered minimum NDT-50 F Shell plates above el. 720'-ll", ASTM-A516, Gr. 60, quenched and tempered minimum NDT-20F ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-A516, Gr. 60 fine grained, normalized, min, NDT-20F ASTM-A333, Gr.a ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-A516, Gr. 60, fine grained,* normal fzed, min, NDT-20F Piping penetration end caps over 4 in. diam, ASTM-A234, Gr. WPB, annealed and normalized piping penetration end caps 4 in. diam and under ASTM-Al05, Gr. II, annealed and normalized ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-Al31, Gr. C (Formed Shape)
ITEM Equipment Hatch Insert Equipment Hatch Flanges Equipment Hatch Head Equipment Hatch Insert Reinforcing Bar Equipment Hatch Bolts
.uipment Hatch Nuts uipment Hatch Gasket Personnel Hatch/
Personnel Air Lock Personnel Hatch Gaskets/Personnel Air Lock Gaskets Bridging Bars Backing Strips Liner Insert Plates TABLE 2 (Cont'd)
SURRY UNITS 1 & 2 SPECIFICATION NUS-56 ASTM-A516, Gr. 60 ASTM-A5I6, Gr. 60 ASTM-A5I6, Gr. 60 ASTM-A516, Gr. 60 ASTM-AI93, Gr. B7 ASTM-A194, Gr. 2H Type "W" Neoprene, 40-5 shore a deg ASTM-A516, Gr. 60 Type "W" Neoprene, 40-5 shore a deg ASTM-A350, Gr. LF3 normalized and tempered minimum NDT-20F ASTM-A442, Gr. 60/ASTM-A517, Gr. 60 ASTM-A442, Gr. 60/ASTM-A516, Gr. 60 BEAVER VALLEY UNIT 1 SPECIFICATION BVS-136 ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-A516, Gr. 60, fine
- grained, normalized, min, NDT-20F ASTM-A5I6, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F ASTM-AI93, Gr. 87 ASTM-A194, Gr. 2H Type "W" Neoprene, 40-5 shore a deg ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F Type "W" Neoprene, 40-5 shore a deg ASTM-A350, Gr. LF3 normalized and tempered minimum NDT-20F ASTM-A516, Gr. 60, fine
- grained, normalized, min,
. NDT-20F ASTM-A516, Gr. 60, fine grained, normalized, min, NDT-20F or ASTM-A516, Gr. 55, fine grained, normalized, min, NDT-20F
.,_1 Welding Electrodes Carbon Steel to Carbon Steel Welding Electrodes Stainless Steel to Stainless Steel Welding Electrodes Carbon Steel to Stainless Steel TABLE 2 (Cont'd)
SURRY UNITS 1 & 2 SPECIFICATION NUS-56 ASTM-E7018 ASTM-E308 ASTM-E309 BEAVER VALLEY UNIT 1 SPECIFICATION BVS-136 ASTM-E7018 ASTM-E308 ASTM-E309
TABLE 3 COMPARISON OF PHYSICAL PROPERTIES OF MATERIALS Yield Strength, Ksi (Min)
Tensile Strength, Ksi Elongation in 2 In.,%
Elongatidn in 4 In., less than or equal to,%
Elongation in greater than 4 In., %
Elongation in 8 In.,*%
ield Strength, Ksi (Min)
- Tensile Strength, Ksi Elongation in 2 In.,%
Elongation in 4 In., leass than or equal to,%
Elongation in greater than 4 In., %
Elongatjion in 8 In.l %
SURRY UNITS 1 & 2 ASTM A442, Gr. 60 32 60-80 23 20 ASTM A516, Gr. 60 32 60-80 25 21 BEAVER VALLEY UNIT 1 ASTM A537, Gr. B 60 80-100 22 20
TABLE 4 COMPARISON OF FSAR/SPECIFICATION DESIGN CONDITTIONS ITEM SURRY UNITS 1 & 2 BEAVER VALLEY UNIT 1 Pressure, Psig 45 45 Temperature, °F 273 280 Design Basis Eq. (DBE) 0.15g 0.15g Horizontal Accel.
Operating Basis Eq. (OBE) 0.07g 0.07g Horizontal Accel.