ML20205F256
| ML20205F256 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/25/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Spangenberg F ILLINOIS POWER CO. |
| References | |
| NUDOCS 8703310125 | |
| Download: ML20205F256 (6) | |
Text
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' s' March 25, 1987 DISTRIBUTION
[NE M0'Brien Docket No. 50-461 NRC PDR ACRS(10)
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LKintner-RBernero Mr.: Frank A.' Spangenberg Pirfo,0GC Manager-Licensing and Safety EJordan Clinton Power Station BGrimes 4
P. O. Box 678 JPartlow Mail Code V920 NThompson Clinton, Illinois 61727 BSiegel
Dear Mr. Spangenberg:
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE CLINTON POWER STATION'S
'FIRST. TEN YEAR INTERVAL INSPECTION PROGRAM The staff with technical assistance from Idaho National Engineering Laboratory has reviewed and evaluated your November 2, 1986 submittal for the Inservice Inspection Program for Clinton Power Station for the first ten year interval of operation. The enclosure describes the scope and status of the review performed and'contains a request for additional information (RAI)..It is requested that your response to this RAI be provided within 60 days of receipt.
of this. letter.
If you have any questions regarding the RAI or problem meeting the proposed schedule for response please contact the staff's licensing project manager,
.ByronSiegel,at(301)492-9474.-
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Sincerely,
/s/
Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page t
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- h WASHINGTON, D. C. 20$55 March 25, 1987 Docket No. 50-461 Mr. Frank A. Spangenberg Manager-Licensing and Safety Clinton Power Station P. O. Box 678 Mail Code V920 Clinton, Illinois 61727
Dear Mr. Spangenberg:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE CLINTON POWER STATION'S FIRST TEN YEAR INTERVAL INSPECTION PROGRAM The staff with technical assistance from Idaho National Engineering Laboratory has reviewed and evaluated your November 2, 1986 submittal for the Inservice Inspection-Program for Clinton Power Station for the first ten year interval of operation. The enclosure describes the scope and status of the review performed and contains a request for additional information (RAI).
It is requested that your response to this RAI be provided within 60 days of receipt of this letter.
If you have any questions regarding the RAI or problem meeting the proposed schedule for response please contact the staff's licensing project manager, ByronSiegel,at(301)492-9474.
Sincerely, Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
-8 Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Company Unit 1 CC:
Mark Jason Mr. Donald Schopfer Assistant Attorney General Project Manager Public Utilities Division Sargent & Lundy Engineers Office.of the Attorney General 55 East Monroe Street State of Illinois Center Chicago, Illinois 60603 100 West Randolph Street - 12th Floor Chicago, Illinois 60601 Mr. L. Larson Project Manager Mr. D. P. Hall General Electric Company Vice President 175 Curtner Avenue, N/C 395 Clinton Power Station San Jose, California 95125 P. O. Box 678 Clinton, Illinois, 61727 Regional Administrator, Region III 799 Roosevelt Road.
Mr. Wilfred Connell Glen Ellyn, Illinois 60137 Manager-fluclear Station Engineering Dpt.
~Clinton Power Station Richard B. Hubbard P. O. Box 678 Vice President Clinton, Illinois 61727 Technical Associates.
1723 Hamilton Avenue - Suite K Sheldon Zabel, Esquire San Jose, California 95125 Schiff, Hardin & Waite 7200 Sears Tower Chairman of Dewitt County 233 Wacker Drive e/o County Clerk's Office Chicago, Illinois 60606 DeWitt County Courthouse Clinton, Illinois 61727 Resident Inspector U. S. Nuclear Regulatory Commission Illinois Department of Nuclear Safety RR 3, Box 229 A Division of Engineering Clinton, Illinois 61727 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 l
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ENCLOSURE Request for Additional Information - First 10-Year Interval Inservice Inspection Program Plan Scope / Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that components (including supports) which are classified as American Society of tiechanical Engineers (ASME) Boiler and Pressure Vessel Code 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, geometry, and materials of construction of ti.a components. This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during the initial 120-month inspection interval shall comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the date of issuance of the operating license, subject to the limitations and modifications listed thereine The components (including supports) may meet requirements set forth in subsequent editions and addenda of this Code which are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
The Licensee, Illinois Power Company, has prepared the Inservice Inspection (ISI) Program Plan to meet the requirements of the 1980 Edition, Winter 1981 Addenda (80W81) of the ASME Code Section XI except that the extent of examination for Code Class 2 piping welds in Residual Heat Removal (RHR) Systems, Emergency Core Cooling (ECC) Systems, and Containment Heat Removal (CHR) Systems has been determined by the 1974 Edition through Summer 1975 Addenda i
(74575).
As required by 10 CFR 50.55a(g)(5), if the licensee determines that certain Code examination requirements are impractical and relief is requested, the licensee shall submit information to the Nuclear Regulatory Commission (NRC) to sur. port that determination.
The staff has reviewed the available information in the Clinton Power Station Unit 1 First 10-Year Interval ISI Program Plan, Revision 0, Change 2, submitted November 7, 1986 and the requests for relief from the ASME Code Section XI requirements which the Licensee has determined to be impractical.
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.a Additional Information Required Based on the above review, the staff has concluded that the following information~and/or clarification is required in order to complete the review of the ISI Program Plan:
A.
Provide the staff with the Boundary Diagrams which define.the ASME
~ Code Class 1, Class 2, and Class 3 boundaries for the systems in the Clinton Power Station Unit 1 First 10-Year Interval ISI Program Plan.
B.
Table 2, " Class 2 Line Examination Requirements," of the ISI Program Plan references paragraph IWC-1222(d) of 83W83 as the basis for exemption of Class 2 open-ended piping.
Since 83W83 has_not been approved per 10 CFR 50.55a, the Licensee should reference the NRC-approved Code Case N-408 paragraph (b)(4) instead of paragraph IWC-1222(d) of 83W83.
C.
Table 2, " Class 2 Line Examination Requirements," of.the ISI Program Plan (page 69) lists IWC-1220(a) as the basis for exemption of Class 2 piping that are 4 inch nominal pipe size and smaller.
If the exemption basis is because of the size of those lines l
listed, the reference should be changed to IWC-1220(c).
D.
The" Licensee should address the degree of compliance with Regulatory Guide 1.150, " Ultrasonic Testing Of Reactor Vessel Welds During Preservice and Inservice Examinations," for inservice examination of the Reactor Pressure Vessel welds.
E.
Review of the ISI Program Plan shows that welds in Control Rod Drive (CRD) scram discharge volume (SDV) piping may not be included for examination.
The staff finds that because the SDV piping is designed and fabricated according to the requirements of ASME Section III, Class 2, and because of its importance in achieving the scram function, it should, as a minimum, be subjected to the ISI requirements for Class 2 piping in ASME Code Section XI.
Therefore, the Licensee should incorporate the requirements of ASME 4
Code Section XI and the recommendations of NUREG-0803 in the CRD section of the Clinton Power Station Unit 1 First 10-Year Interval 1
ISI Program Plan.
F.
The relief request for weld No.1-RH-28-6-2 references a sketch which is not attached.
Provide the staff with this missing sketch.
i G.
The relief request for weld No.1-RI-13-8AQ1 states: "This weld is located underneath a component support and is inaccessible because the support is welded and its design does not allow for disassembly." The Licensee should provide a sketch of the j
obstruction and, if the subject weld is partially accessible, state the percentage of the weld that will receive the Code-required examination.
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The relief request for weld No. J-RH-25-9-3 states:
"This weld is-located inside the Auxiliary Building wall penetration sleeve number 1AB0011 and is inaccessible to perform any nondestructive examination." Isometric drawing No. B-21 does not show this weld to be located inside the wall penetration sleeve.
Verify that the subject weld is indeed located inside the sleeve and inaccessible for ISI examination.
If this weld is totally inaccessible, the Licensee should consider substituting the examination of an adjacent weld as an alternative to the Code requirement.
I.
The relief request for weld No.1-VP-6-1-5 states: "This weld is located inside the containment penetration sleeve number IMC-107 and is inaccessible to perform any examination." The Licensee should consider substituting the examination of an adjacent weld as an alternative to the Code requirement.
J.
Each relief request should be a " stand-alone" document (i.e., all of the supporting information should be included as part of the relief request).
The Licensee should revise the requests for relief to include the following:
(1) The ASME Section XI Code Class,' Examination Category, and Item Number (s).
(2) An identification of the specific ASME Code Section XI requirement that has been determined to be impractical.
Provide the staff with a complete submittal of the revised relief requests.
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