ML20083M060
| ML20083M060 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/11/1995 |
| From: | Richard Anderson NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505190096 | |
| Download: ML20083M060 (3) | |
Text
.,s
.a.
/
Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonado Dr. East Welch, Minnesota 55089 May 11, 1995 10 CFR Part 50 Section 50.55s(g)
U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PiRrr Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Second Ten-year Interval ASME Section XI Inservice Inspection and Testing Program Reauest for Relief #63. Reactor Coolant Pump Casing Welds The purpose of this letter is to provide a revision to a relief request for the Unit 2 Second Ten-year Interval ASME Section XI Inservice Inspection und Testing Program.
The revision is being provided for your information.
Since the revision deletes a portion no longer necessary and leaves unchanged a portion previously approved, no review or approval is necessary.
Relief Request No. 63 was originally submitted on December 22, 1983 and approved by the NRC on December 28, 1984 for relief from the examination requirements for reactor coolant pump casement welds. Relief had been requested from ASME Code Section XI requirements B-L-1, Item B 12.10 and B-L-2, Item B 12.20 Code Case N-481 dated March 5, 1990, which has been approved for use by Regulatory Guide 1.147, is applicable as an alternate to the Code required volumetric examination in Category B-L-1, Item B 12.10.
We plan to use the alternate method of inspection described in Code Case N-481 in lieu of the volumetric requirement described in ASME Code Section XI Category B-L 1, Item B 12.10; therefore, the alternate examination, surface examination of the pump casement weld, as discussed in Revision 0 to Relief Request No. 63, will not be done. Relief Request No. 63 has been revised to delete reference to Category B-L-1, Item B 12.10.
Relief Request No. 63 also requested relief from examination requirement B-L-2, Item B 12.20, visual examination of pump internal surfaces. Relief Request No. 63 for Category B-L 2, Item B 12.20 remains unchanged.
In this letter we have made an NRC commitment to replace the original Relief Request #63 alternate examination requirements for the reactor coolant pump casement weld with the requirements listed in Code Case N-481.
d 9505190096 950511
' h PDR ADOCK 05000306 h
P PDR s
g _.
/'
USNRC:
NORTHERN STATES POWER COMPANY May 11,~1995 Page 2 Please contact Jack Leve111e (612 388-1121 Ext. 4662) if you have any questions related to this letter.
MAfd Roger 0 Anderson v.
Director Licensing and Management Issues c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg
Attachment:
- 63. Request for Relief (1 page), dated 3/27/95 RRf63. DOC
- ?
- 63. Request for Relief
~
Code Program Code Exam -
Component or item Class Table item Category Reactor Coolant Pump Casing 1
12.1 B12.20 B-L-2 I
Code Reauirements i
Visual Examination of pump internal surfaces.
Basis The pump manufacturer does not require or recommend pump disassembly to perform normal maintenance and inspection due to limited experienced personnel and possible damage or degradation to the pump.
Alternative l
If maintenance or operational problems are encountered which require the disassembly of the pump, the pump's interior surface will be visually inspected.
l Schedule for implementation December 21,1983 i
PI ISI/IST 2.5-40 2nd 10-YR Program Rev.13/27/95
.