ML20107L638
| ML20107L638 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/23/1996 |
| From: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.147, RTR-REGGD-1.147 NUDOCS 9604290386 | |
| Download: ML20107L638 (7) | |
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South Carolina E11ctric & Gis Cornpiny Giry J.T or Jenkinsville, SC 29065 Nuclear Operations j
(803) 345-4344 SCE&G 1
ASCAREl Company April 23,1996 1
i Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
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Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 j
ASME SECTION XI RELIEF REQUEST (NRR 960001) REVISION 1
Reference:
Letter from G. J. Taylor to Document Control Desk, dated March 28,1996 l
A relief request was submitted by our "RC-96-0087, Forwards ISI Pressure Test Program Relief Request NRR 960001,requesting That ASME Nuclear [[Code case" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Be Approved for Use Prior to Inclusion in RG 1.147,as Alternative to Requirements of ASME Section XI-1989|letter dated March 28,1996]],which required NRC l
approval prior to use. This relief request proposes alternative testing per 10 CFR Part j
50.55a(a)(3) within the V. C. Sumnier Nuclea' Station (VCSNS) Inservice inspection Pressure Test Program.
VCSNS desires to revise Attachment I to remove penetrations not required to be tested using Code Case N-522. This revision contains no new additions or changes to our previous request.
We request that the ASME Nuclear Code Case N-522, "Fressure Testing of Containment Penetration Piping," be approved for use prior to its inclusion in Regu atory Guide 1.147.
Code Case N-522 (Attachment 2) accepts t le test requirements of 10 CFR Part 50, Appendix J as an alternative to the test requirements of ASME Section XI, Table IWC-2500-1, Category C-H. This would significantly reduce the redundant testing required by the imposition of both ASME Section XI and 10 CFR Part 50, Appendix J.
In accordance with 10 CFR Part 50.55a(a)(3), approval of this relief request is requested as an alternative to the requirements of ASME Section XI-1989.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Should you have questions, please call Mr. M. J. Zaccone at (803) 345-4328.
Ver tru rs, 9604290386 960423 PDR ADOCK 05000395
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S PDR ry.
pyl MJZ/GJT/nkk Attachments (2) c:
J. L. Skolds NRC Resident inspector W. F. Conway (w/o Attachments)
J. B. Knotts J r.
R. R. Mahan NSRC t \\
R. J. White DMS (RC-96-0118)
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S. D. Ebr, eter RTS (NRR 960001)
J. l. Zimrt erman File (810.19-2) 200101@
Document Control Dtsk Attachmsnt 1, Rev.1 NRR 960001 RC-96-0118 Page 1 of 4 ATTACHMENT 1 SOUTH CAROLINA ELECTRIC & GAS V. C. SUMMER NUCLEAR STATION DOCKET 50/395 INSERVICE INSPECTION PRESSURE TEST PROGRAM - REQUEST FOR RELIEF RELIEF REQUEST NRR 960001
. Document Control Dask l', Rev.1 NRR 960001 RC-96 0118 l
Page 2 of 4 l
. RELIEF REQUEST NUMBER NRR 960001 COMPONENTIDENTIFICATION Code Class:
2
References:
IWA-5211 1
IWA-5240 l
Table IWC-2500-1 IWC-5210(a)
Examination Category:
C-H i
Description Alternative Pressure Testing of Containment Penetration Piping l
Containment isolation System (CIS) l Penetrations to be Tested Using Code Case N-522 l
Procedure Penetration Dwg Penetration Description Number Number N o.
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XRP0204 302-612 RC PUMPS CC SUPPLY HEADER PENETRATION STP-215.004 XRP0208 302-852 CRDM COOLING WATER INLET PEN STP-215.004 XRP0209 302-852 CRDM COOLING WATER RETURN PEN STP-215.004 i
XRP0231 302-715 DEMINERAllZED WATER PENETRATION STP-215.004 XRP0310 302-241 REACTOR BLDG STATION SERVICE AIR PENETR STP-215.002A XRP0311 302-273 REACTOR BLDG INSTRUMENT AIR PENETR STP-215.002A XRP0312 302-612 RC i :<lP BRG CLG SUP HDR PENETRATION STP-215.004 XRP0313 302-311 NITROGEN SUPPLY TO FEEDWATER LINES STP-215.002A XRP0317 302-692 ACCUMULATOR FILL LINE PENETRATION STP-215.003A XRP0320 302-692 ACCUMULATOR NITROGEN SUPPLY PENETR STP-215.003A XRP0321 302-692 ACCUMULATOR TEST LINE PENETRATION STP-215.003A XRP0324 302-274 BREATHING AIR PEN STP-215.002A XRP0330 302-612 COMPONENT COOLING FROM RCP BEARINGS STP-215.004 XRP0404 302 231 FIRE SERVICE HOSE REEL SUPPLY PENETR STP-215.004 XRP0417D 302-772 SAMPLE RETURN TO PRT PEN STP-215.005 XRPO418 302-735 RC DRAIN TANK TO VENT HEADER & H2 STP-215.003A XRP0420 302-602 PRESSURE RELIEF TANK PENETRATION STP-215.003A XRP0422 302-602 PRESSURE RELIEF TANK MAKE-UP PENETRATION STP-215.003A XRPO423 302-735 RC DRAIN TANK PENETRATION STP-215.003A XRP0424 302-821 REACTOR BUILDING SUMP DRAIN PENE7R STP-215.003A XRP0427 302-231 FIRE SERVICE DELUGE PENETRATION STP-215.004 -
Document Control Desk i.
Attach,msnt 1, Rav.1 NRR 960001 RC-96-0118 Page 3 of 4 i
i CODE REQUIREMENT IWA-5211 states, "The pressure retaining components within each system boundary i
shall be subject to system pressure tests under which conditions visual examination l
VT-2 is performed in accordance with IWA-5240 to detect leakages."
IWC-5210(a) states, "The pressure retaining components within each system boundary shall be subjected to a system pressure test conducted during functional test, a system pressure test conducted during a system inserv,a system i
ice test, or a j
hydrostatic test, and visually examined by the method specified in Table IWC-2500-1, Examination Category C-H Table IWC-2500-1, Examination Category C-H, specifies a frequency of examination of once per inspection period for inservice or functional testing and once per j
inspection interval for hydrostatic testing.
BASIS FOR RELIEF Pursuant to 10CFR50.55a(aP li), the proposed alternative provides an acceptable level of quality and safety.
The proposed alternative will reduce the level of redundant testing. Imposition of l
the IWC-2500-1 test requirements would result in additional testing as follows:
1.
Water systems would be flooded and pressurized through the associated penetration test tap and a VT-2 visual examination performed during the pressurization period.
2.
Air and gas systems would be tested in an identical fashion to 10CFR50, Appendix J test method and a VT-2 visual examination would be performed during the pressurization period.
For the penetrations listed,10CFR50, Appendix J testing is performed by draining the test volume,if required, venting downstream of the test volume and pressurizing the test volume to 53.5 to 57 ps determined and compared to acceptance cn,ig. The rate of makeu p flow is teria based on allowable containment leak rate.
Leakage from water systems would be indicated during the 10CFR50, Appendix J test more readily than the IWC-25001 test due to the lower density of the air test medium. Based on this fact,the use of the Appendix J test program is conservative when compared to the ASME Section XI program.
Leakage from air and other gas systems would be indicated by 10CFR50, Appendix J l
testing in a similar manner to an IWC-2500-1 test. Based on this fact, the two programs are essentially equivalent.
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Document Control Desk 4
4 Attachinant 1, Rev.1
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NRR 960001 RC-96-0118 Page 4 of 4 4
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-The specified frequency of testing for the 10CFR50, Appendix J test program is once per refueling cycle, which is approximately 18 months. The IWC-2500-1 specified test frequen,cy is once per inspection aeriod which is approximately 3-1/3 years. A comparison of the specified test frequencies indicates the 10CFR50, Appendix J test i
program is conservative when compared to the ASME Section XI test program.
VCSNS 10CFR50, Appendix J testing is performed by Test Specialists who are certified as VT-2 Level ll exam,ners in accordance with Section XI. Therefore, A3pendix J i
i testing is performed by personnel trained to recognize unacceptable l eakage from a
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pressure boundary.
i PROPOSED ALTERNATIVE I
in lieu of the requirements specified in IWA-5211 and IWC-5210, VCSNS will follow the guidance of Code Case N 522 for pressure testing of safety class 2 containment penetrations associated with non-safety class systems.
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Testing required by 10CFR50, Appendix J may be used as an alternative to the rules in Table IWC-2500-1, Category C-H, for pressure testing piping that penetrates a containment vessel,when:
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> the piping and isolation valves that are part of the containment
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i system are Class 2, but the balance of the piping system is outside l
the scope of Section XI.
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Pipe wall leakage will be evaluated during the Appendix J test.
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i APPL! CABLE TIME PERIOD l
The proposed alternative is reque:,ted for the second ten-year interval of the Inservice Inspection Program for VCSNS,which concludes in January 2004.
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Document Control Desk i'
Attrchment 2 NRR 960001 i
RC-96-0118 l
Page 1 of 2 d
i ATTACHMENT 2 l
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SOUTH CAROLINA ELECTRIC & GAS V. C. SUMMER NUCLEAR STATION
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DOCKET 50/395 3
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I INSERVICE INSPECTION PRESSURE TEST PROGRAM - REQUESTS FOR RELIEF ASME CODE CASE N-522 T
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Document Control Desk l
NitR 960001 i
RC-96-0118 l
Page 2 of 2 4
i CASE N-522 i
1 1
i CASES OF ASME BOILER AND PRESSURE VESSEL CODE i
ApprovalDate: December 9,1993 j
See NumericalIndex for expiration
{
andanyreaffirmation dates 1
Case N-522 i
Pressure Testing, of Containment Penetration Piping l
Section XI, Division 1 inquiry: What alternative to the rules of Table IWC-2500-1, Category C-H may be i
used for pressure testing piping that penetrates a containment vessel, when the piping and isolation valves that are part of the containment system are Class 2 but the balance of the piping system is outside the scope of Section XI?
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Reply: it is the opinion of the Committee that 10 CFR 50, Appendix J, may be used as an alternative to the rules in Table IWC-2500-1, Category C-H, for 3ressure testing piping that penetrates a containment vessel, when the piping anc isolation valves that are part of the containment system are Class 2 but the balance of the piping system is outside the scope of Section XI.
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