ML20136D612
| ML20136D612 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/07/1997 |
| From: | Tam P NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| TAC-M97465, NUDOCS 9703120423 | |
| Download: ML20136D612 (5) | |
Text
Mr. William R. McCollua 2
Site Vice President March 7, 1997 Catawba Nuclear Station Duke Power Company 480C Ccncord Poad York, South Carolina 29745-9635
SUBJECT:
CATAWBA NUCLEAR STAT!0N,' UNIT 1.. REQUEST FOR~ ADDITIONAL INFORMATION REGARDING SECOND 10-YEAR INTERVAL INSERVICE' INSPECTION PROGRAM PLAN REQUEST FOR RELIEF 96-04 (TAC NO. M97465)
Dear Mr. McCollum:
The staff, with assistance from its contractor, ' Idaho National Engineering Laboratory (INEL), is reviewing and evaluating your request for relief dated December 12, 1996, from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PV) Code,Section XI requirements for Catawba Nuclear Station, Unit 1.
Additional information is needed in order for the staff to complete its review. The enclosure provides details of this request for additional information.
We request a response within 60 days. To expedite the review process, please send a copy of your response to NRC's contractor, INEL, at the following address:
Michael T. Anderson INEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 If you would like the staff to clarify any of the questions, or need additional time to respond, please contact me at 301-415-1451.
Sincerely, Original signed by:
Peter S. Tam, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation rpl
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Docket No. 50-413
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Enclosure:
Request for Additional Information cc w/ enc 1: See next page 120234 NRC File CENTER C Distribution Docket File OGC PUBLIC SVarga PDII-2 Reading
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March 7, 1997 Mr. William R. McCollum Site Vice President Catawba Nuclear Station Duke Power Company 4800 Concord Road York, South Carolina 29745-9635
SUBJECT:
CATAWBA' NUCLEAR STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION i
REGARDING SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF 96-04 (TAC NO. M97465)
Dear Mr. McCollum:
The staff, with assistance from its contractor, Idaho National Engineering Laboratory (INEL), is reviewing and evaluating your request for relief dated December 12, 1996, from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PV) Code,Section XI requirements for Catawba i
Nuclear Station, Unit 1.
Additional information is needed in order for the staff to complete its review.
The enclosure provides details of this request j
for additional information.
We request a response within 60 days. To expedite the review process, please send a copy of your response to NRC's contractor, INEL, at the following i
address:
Michael T. Anderson INEL Research Center i
2151 North Boulevard i
P.O. Box 1625 Idaho Falls, Idaho 83115-2209
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If you would like the staff to clarify any of the questions, or need additional time to respond, please contact me at 301-415-1451.
j Sincerely, i
a Peter S. Tam, Senior Project Manager Project Directorate II-2 i
Division of Reactor Projects - I/I.I l
Office of N0 clear Reactor Regulation j
Docket No. 50-413
Enclosure:
Request for Additional Information cc w/ enc 1: See next page 1
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Duke Power Company Catawba Nuclear Station cc:
Mr. M. S. Kitlan North Carolina Electric Membership i
Regulatory Compliance Manager Corporation i
Duke Power Company P. O. Box 27306 i
4800 Concord Road Raleigh, North Carolina 27611 Vork, South Carolina 29745 Senior Resident Inspector Mr. Paul R. Newton 4830 Concord Road l
Legal Department (PB05E)
York, South Carolina 29745 Duke Power Company i
422 South Church Street Regional Administrator, Region II 1
Charlotte, North Carolina 28242-0001 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 J. Michael McGarry, III, Esquire Atlanta, Georgia 30323 Winston and Strawn 1400 L Street, NW Max Batavia, Chief Washington, DC 20005 Bureau of Radiological Health South Carolina Department of North Carolina Municipal Power Health and Environmental Control Agency Number 1 2600 Bull Street 1427 Meadowwood Boulevard Columbia, South Carolina 29201 P. O. Box 29513 Raleigh, North Carolina 27626-0513 Mr. G. A. Copp Licensing - EC050 Mr. Peter R. Harden, IV Duke Power Company Account Sales Manager 526 South Church Street Westinghouse Electric Corporation Charlotte, North Carolina 28242-0001 Power Systems Field Sales P. O. Box 7288 Saluda River Electric Charlotte, North Carolina 28241 P. O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse.
Ms. Karen E. Long 4
York, South Carolina 29745 Assistant Attorney General North Carolina Department of Justice Richard P. Wilson, Esquire P. O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 South Carolina Attorney General's Office Elaine Wathen, Lead REP Planner P. O. Box 11549 Division of Emergency Management Columbia, South Carolina 29211 116 West Jones Street Raleigh, North Carolina 27603-1335 Piedmont Municipal Power Agency 121 Village Drive Dayne H. Brown, Director Greer, South Carolina 29651 Division of Radiation Protection N.C. Department of Environment, Mr. T. Richard Puryear Health and Natural Resources Owners Group (NCEMC)
P. O. Box 27687 Duke Power Company Raleigh, North Carolina 27611-7687 4800 Concord Road York, South Carolina 29745
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DUKE POWER COMPANY 4
CATAWBA NUCLEAR STATION. UNIT 1 D0CKET NUMBER 50-413 EQEST FOR ADDITIONAL INFORMATION Scone and Status of Review
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_Throughout the service life of a water-cooled nuclear power facility, Title 10 of the Code of Federal Reaulations (10 CFR) Section 50.55a(g)(4) requires that components (including supports) that are classified as American Society of l
Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) 4 Class 1, Class 2, and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, l
geometry, and materials of constructicn of the components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during a 120-month inspection interval comply j
with the requirements in the latest edition and addenda of the Code i
incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval.
By letter dated December 12, 1996, the licensee submitted Request for Relief 96-04 for limited volumetric examinations of Class I circumferential welds in the Safety Injection System. The available information provided by the licensee the December 12, 1996, submittal, has been reviewed by the NRC staff and its contractor, Idaho National Engineering Laboratory.
Additional Information Reauired Based on the above review, the following information and/or clarification is needed to complete the review of Request for Relief 96-04:
A.
Based on the initial review of the licensee's submittal, the staff has concluded that either (a) the appropriate paragraph of the regulations has not been cited, or (b) the regulatory basis has not been adequately supported. Request for Relief 96-04 was submitted pursuant to 10 CFR 50.55a(a)(3)(ii), but no burden or undue hardship has been presented.
This request should be reviewed for the correct paragraph of the regulations to ensure that the request is evaluated in accordance with the appropriate criteria, as discussed below.
Enclosure u-
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i The regulations provide that a licensee may propose an alternative to the Code of Federal Reaulations or the Code requirements in accordance with 10
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CFR 50.55a(a)(3)(1) or 10 CFR 50.55a(a)(3)(11). Under 10 CFR 50.55a(a)(3)(1), the proposed alternative must be shown to provide an acce> table level of. quality and safety, i.e., essentially, be equivalent to tie original requirement in terms of quality and safety. Under l
.10 CFR 50.55a(a)(3)(ii), the licensee must show that compliance with the original requirement results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Examples of i
hardship and/or unusual difficulty include, but are not limited to, I
excessive radiation exposure, disassembly of components solely to provide access for examination, and development of sophisticated toolin would result in only minimal increases in examination coverage.g that A licensee may also suomit a request for relief from ASME requirements.
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In accordance with 10 CFR 50.55a(g)(5)(iii), if a licensee determines that
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conformance with certain Code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as i'
specified in Section 50.4, information to support that determination.
When a licensee determines that an inservice inspection requirement is impractical, e.g., the enmination is limited by physical restrictions and the component would have to be redesigned or replaced to enable inspection, the licensee'should cite 10 CFR 50.55a(g)(5)
The NRC may, giving due consideration to the burden placed on the(iii). licensee, impose an alternative examination requirement.
B.
Section XI, Appendix III, Paragraph 111-4420, Reflectors Parallel to the i
Weld Seam, requires examination coverage in two beam path directions to detect reflectors parallel to the weld seam. This can be accomplished by either scanning from two sides of the weld, or by using a sufficiently long beam path to provide two-directional coverage from one side of the weld. The requirement for two-directional axial scan coverage should also be reflected in the coverage calculations. However, the coverage calculations provided with the licensee's submittal only include scan coverage in one axial direction (with two angles) and it appears that the second axial direction was not included in the calculation. As a result, the calculated coverage may be overstated.
Provide a discussion regarding i
the examinations performed in the axial direction (s) and how the coverage j
was calculated.
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C.
The Code requires both surface and volumetric examination of the subject Class I circumferential welds. Confirm that the surface examination was j
performed to the extent required by the Code.
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