ML20217P060
| ML20217P060 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/21/1997 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | Schopfer D SARGENT & LUNDY, INC. |
| References | |
| NUDOCS 9708260430 | |
| Download: ML20217P060 (6) | |
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August 21,1997 Mr. Don Schopfer, Verification Team Manager Sargent & Lundy 55 E. Monroe Street Chicago,IL 60603
Dear IAr. Schopfer:
The staff of the Special Projects Office (SPO) of the Office of Nuclear Reactor Regulation (NRR) has reviewed the sampling criteria that you provided in your August 5,1997, submittal for reviewing some aspects of the pipe support and pipe stress calculations associated with the Independent Corrective Action Verification Program (ICAVP) you are performing at Millstone Unit 3. Your submittal specifically addressed the scope of the samples for the first group of systems to be included in the Tier i system vertical slice review (SVSR) at Millstone Unit 3.
4 It is the SPO staffs understanding that you are proposing a two-level approach for reviewing pipe stress calculations for those areas where you do not plan to perform a 100% review. The two-level approach for review of pipe stress calculation involves: (1) a review of 100% of the calculations to verify that the design information as stated in the calculation is consistent with the system design package, applicable design enteria, and other references provided in the calculations; and (2) a 10% sample of the population of pipe stress calculations to be subject to a review that will verify that the design information was correctly and accurately entered into the NUPIPE computer code and that the resultant computer output supports the conclusions of the calculations. You propose to apply this two-level process to your review of the large bore stress calculations, tubing stress calculations, and vent and drain stress calculations. Also, you indicated that S&L plans to review 100% of the small bore stress calculations and time history calculations.
As ind;cated in your submittal, you proposed to review 100% of the master support calculations and to select a 10% sample for the (1) non standard pipe support calculations, (2) non-standard tubing support calculations, (3) standard pipe support calculations, (4) standard tubing support calculations, (5) liner plate calculations, (6) embedment plate calculations, and (7) structural steel calculations. To select your 10% sample of each calculation type you proposed to: (1) review and group by component type the total population of support calculations; (2) select a 10% sample of the total population of each component type, with a minimum sample size of two samples for any population greater than one; and (3) select a sample based on consideration of the magnitude of the loads, thermal movements resulting in additional friction loads, and the configuration types to ensure that potentially highly stressed conditions are selected.
The SPO staff finds this approach to the review of pipe stress and pipe support calculations acceptable and approves the sampling methodology with the following comments:
1.
The 10% sample selected for both piping analyses and piping supports should contain the most critical calculations based on the engineering judgement of the technical j
reviewers.
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- 2.
In selecting the 10% sample, the methodology stated in paragraph B.3 of your letter dated, August 5,1997, should be modified to indicate a minimum sample which is the greater of three or 10% of each type of component f populations of ten or greater or a sample size which is the lessor of either three or the number of components for populations between one and ten.
3.
If discrepancies are identified in review of the sample selected, the NRC will evaluate the necessity to expand the sample size.
4.
The sample criteria specified also applies to the systems associated with the emergency diesel generators and the ventilation systems selected for review. If, based on your review of the piping analyses and supports associated with the recirculation spray system or quench spray system, you believe the conclusions drawn are applicable to the other systems selected we would consider a readjustment of the sample size for these systems, if appropriate justification was provided, if you have any questions or comments please contact me at (301) 415-14M Sincerely, Original Signed by; Eugene Imbro, Deputy Director ICAVP Oversight Special Projects Office Office of Nuclear Reactor Regulation ec: See next page DISTRIBUTION:
Docket Files (Docket 50 423)
WUBLIC.
WTravers JAndersen SPO R/F PMcKee DOCUMENT NAME: G:\\Nakoski\\sampl2.S&L to r c.e,. a copy or this occum nt, ino: cat in the box "c" = copy without attacN.nel"E" e CopLwith attacNonci "N" a No copy OFFICE ICAVP/SPO E
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ICAVP/SPO ICAVP/SPO NAME JANakoski LBeny "
SReynolddyb EVlmbrc N Y / I/97 I/2//97
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DATE
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1
Northeast Nuclear Energy Company Millstone Nuclear Power Station a
Unit 3 cc:
Lillian M. Cuoco Esquire Citizens Regulatory Commission Senior Nucler r Counsel ATTN: Ms. Susan Perry Luxton Northeast Utilities Service Company 180 Great Neck Road P. O. Box 270 Waterford, Connecticut 06385 Hartford, CT 06141-0270 Mr. F. C. Rothen Mr. Kevin T. A. McCarthy, Director Vice President - Nuclear Work Services
- Monitoring and Radiation Division Northeast Nuclear Energy Company Department of Environmental P.O. Box 128 Protection Waterford, CT 06385 79 Elm Street Hartford, CT 06106-5127 Charles Brinkman, Manager Washington Nuclear Operations Mr. Allan Johanson, Assistant Director ABB Combustion Engineering Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 Policy Development and Planning Rockville, MD 20852 Divisiot.
450 Capitol Avenue - MS 52ERN Mr. D. M. Goebel P. O. Box 341441 Vice President - Nuclear Oversight Hartford, CT 06134-1441 Northeast Nuclear Energy Company P. O. Box 128 Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Senior Resident inspector King of Prussia, PA 19406 Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission First Selectmen P. O. Box 513 Town of Waterford Niantic, CT 06357 Hall of Records 200 Boston Post Road Mr. M. H. Brothers Waterford, CT 06385 Vice President - Millstone Unit 3 Northeast Nuclear Energy Company Deborah Katt f.wjent P. O. Box 128 Citizens Awareness Network Waterford, CT 06385 P. O. Box 83 Shelburne f alls, MA 03170 Mr. J. K. Thayer Recovery Officer - Nuclear Mr. Wayne D. Lanning Engineering and Support Deputy Director of inspections Northeast Nuclear Energy Company Special Projects Office P. O. Box 128 475 Allendale Road Waterford, CT 06385 King of P.=ussia, PA 19406-1415 Burlington Electric Department Mr. M. R. Scully, Executive Director clo Robert E. Fletcher, Esq.
Connecticut Municipal Electric 271 South Union Street Energy Cooperative Bunington, VT 05402 30 Stott Avenue Norwich, CT 06360
Northeast Nuclear Energy Company Millstone Nuclear Power Station a
Unit 3 cc:
Mr. William D. Melaert Mr. John Buckingham Nuclear Engineer Department of Public Utility Control
- Massachusetts Municipal Wholesale Electric Unit Electric Company 10 Liberty Square P. O. Box 426 New Britain, CT 06051 -
Ludlow, MA 01056 Mr. James S. Robinson Ernest C. Hadley, Esq.
Manager, Nuclear Investments and 1040 B Main Street Administration P. O. Box 54g
- New England Power Company West Wareham, MA 02576 25 Research Drive Westborough, MA 01582
- Joseph R. Egan, Esq.
Egan & Associates, P.C.
Mr. B. D. Kenyon.
2300 N Street, NW President and Chief Executive Officer
. Washington, D.C. 20037 Northeast Nuclear Energy Ccmpany P. O. Box 128 The Honorable Terry Concannon Waterford, CT 06385 Co-Chair Nuclear Energy Advisory Council Mr. John C. Markowicz Room 4035 Nuclear Energy Advisory Council Legislative Office Building -
g Susan Terrace Capitol Avenue Waterford, CT 06385-3515 Hartford, Connecticut 06106 Mr. Daniel L. Curry Mr. Evan Woollacott Project Director Co-Chair Millstone Project Nuclear Energy Advisory Council Parsons Power Group Inc.
128 Terrys Plain Road 2675 Morgantown Road Simsbury, CT 06070 Reading, PA 19607 Ms. P. Loftus Director-Regulatory Affairs for Millstone Station Northeast Nuclear Energy Company _
P. O. Box 128 Waterford, CT 06385 Mr. N. S. Cams Senior Vice President and.
Chief Nuclear Officer Northeast Nuclear Energy Company P. O. Box 128 Waterford, CT 06385
Mr. Don Schopfer 2.
In selecting the 10% sample, the methodology stated in B.3 should be modifjed to indicate a minimum sample which is the greater of three or 10% of each typ6 of
- component for populations of ten or greater or a sample size which is thelessor of either three or the number of components for populations between one and teri.
3.
If discrepancies are identified in review of the sample selected ttje NRC will evaluate the necessity to expand the sample size.
,/
4.
The sample criteria specified also applies to the systems,a ociated with the emergency diesel generators and the ventilation systems selected for review. If, based on your review of the piping analyses and t,upports associated stith the recirculation spray system or quench spray system, you believe the conclusions drawn are applicable to the other systems we would consider a readjustmerit of the sample size for these systems, if appropriate justification was provided if you have any questions or comments please conta me at (301) 415-1490..
Sincerely, Eugene Imbro, Deputy Director ICAVP Oversight Special Projects Office Office of Nuclear Reactor Regulation ec: See next page DISTRIBUTION:
Docket Files (Docket 50-4 )
PUBLIC W, Travers JAndersen SPO R/F PMcKee' DOCUMENT NAME: G:\\Nakoski\\sampl1.S&L To receive a copy of this document, Indkate in the bon "C" e Copy without attacNoncl"E* a Copy with attacNenct "N" a No copy OFFICE ICAVP/SPO E
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ICAVP/SPO b
ICAVP/SPO NAME JANakoski V LBerry SReyrolds M EVimbro h
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DATE OFFICIAL RECORD COPY
.. e Mr. Don Schopfer - 2.
If one error that brings into question the conclusions of a calculation is identified in any calculation included in the first 10% sample, the sample population shall be increased to 20%.
3.
If an additional error that brings into question the conclusions of a calculation is identified in any of the calculations included in the 20% sample, the sample population shall be increased to 100%.
4.
The sample selection should be distributed between the systems ' proportion to the -
number of calculations associated with each system, if you have any questions or comments please contact me at (301) 415-1490 or e-mail EXI@NRC. GOV.
Sincer y, Eugene Imbro, Deputy Director ICAVP Oversight Special Projects Office Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
Docket Files (Docket 50-423)
PUBLIC WTravers Andersen.
SPO R/F-PMcKee DOCUMENT NAME: G:\\Na oski\\sampl1.S&L To receive a copy of thle document, Indicate in the hos "C" = Copy without attachsenci"E" e Copy with attachtenct "'#'s No copy OFFICE ICAVP/SPOc C LA nC ICAVP/SPO
-ICAVP/SPO JANakoski h'
- LBerry, SReynolds EVlmbro NAME=
DATE Y /}Il97
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OFFICIAL RECORD COPY l
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