ML20079P425
| ML20079P425 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1983 |
| From: | John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Clark R, Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 0CAN02318, CAN2318, NUDOCS 8303040611 | |
| Download: ML20079P425 (3) | |
Text
r ARKANSAS POWER & LIGHT COMPANY POST OFMCE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 February 28, 1983 BCAN028318 Director of Nuclear Reactor Regulation ATTN:
Mr. J. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Director of Nuclear Reactor Regulation ATTN: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 NRC Request for Technical Specification Revision for Snubber Surveillance Gentlemen:
The purpose of this letter is to submit our resolution to the snubber surveillance issue for Arkansas Nuclear One - Units 1 and 2 (ANO-1&2).
In response to your letter dated September 21, 1982, (0CNA098209) which requested AP&L to submit revised Technical Specifications for ANO-1&2 snubber surveillance, we are proposing a program to test those mechanical and hydraulic snubbers (except greater than 50,000 lb. capacity) which are nuclear safety related in accordance with ANSI /ASME OM-4 1982.
AP&L will submit revised Technical Specifications to reference ANSI /ASME OM-4 1982 by June 30, 1983.
Following is a brief overview of the events leading up to l
this submittal and a proposed snubber surveillance program which can be implemented at ANO-1&2 to address NRC's concerns.
Your letter dated November 20, 1980, (0CNA118080) requested AP&L to submit licen,e amendment applications to incorporate applicable portions of NRC's revised Standard Technical Specifications for snubber surveillance into our Appendix "A" Technical Specifications for ANO-1&2.
In response, we proposed in our April 1, 1981, letter (0CAN048101) to wait for the inclusion of the ASME Committee on Operations and Maintenance's Standard for inservice 8303040611 830228 PDR ADOCK 05000313 MEMBEFI MIODLE SOUTH UTILITIES SYSTEM
Mr. Stolz/Mr. Citrk February 28, IMs testing of nuclear plant snubbers (OM-4) into Section XI of the ASME Boiler and Pressure Vessel Code (ASME Code or Code).
We felt this approach would avoid putting unnecessary detail in our Technical Specifications because (a) we understood that the OM-4 Standard was being davaloped to replace the snubber testing requirements in Section XI of the ASME Code, and (b) in response to IE Bulletin 81-01 we subsequently completed 100% inspections of the ANO-1&2 safety related mechanical snubbers and concluded that no generic defects were apparent.
Due to our inspection efforts for ANO-1&2, we felt this should resolve any concern regarding a delay in awaiting the Section XI
- revision, i.e., before mechanical snubber inspections were included by reference in our Technical Specifications.
Since that time, a series of letters were exchanged on this issue.
- However, in response to your September 21, 1982, (0CNA098209) correspondence, we l
agreed in our November 26, 1982, (0CAN118222) letter to provide NRC by February 28, 1983, with our resolution to the matter of snubber surveillance requirements for ANO-1&2.
We have now completed our review of the ANSI /ASME OM4-1982 Standard which was formally issued on October 31, 1982, and have determined that the attached snubber surveillance program should be implemented at ANO-1&2 in lieu of our submitting revised Technical Specifications to incorporate the Standard Technical Specifications as requested in your November 20, 1980, letter. AP&L has elected to reference the OM-4 Standard as a means to avoid putting unnecessary and unwarranted detail into our ANO-1&2 Technical Specifications. We feel our proposed program is realistic and adequately l
addresses the intent of NRC's model Technical Specifications for nuclear l
safety related snubber surveillance at Arkansas Nuclear One, Units 1 and 2.
Very truly yours, ohn R. Marshall Manager, Licensing JRM:DET:sl Attachment t
/
r (Attachment to 9CAN028318)
-ARKANSAS NUCLEAR ONE, UNITS 1 & 2 PROPOSED SNUSBER SURVEILLANCE PROGRAM 1.
Mechanical and hydraulic snubbers (except those greater than 50,000 lb.
capacity) at ANO-1&2 which are nuclear safety related will be tested in accordance with ANSI /ASME OM4-1982.
2.
AP&L will utilize past visual inspections as a baseline for the inspection program proposed in Item 1 above.
3.
All mechanical and hydraulic snubbers (including those greater than 50,000 lb. capacity) which are nuclear safety related will be identified in table format-and grouped per ANSI /ASME OM4-1982.
During the next scheduled refueling outage on each unit, a walkdown will be conducted to verify completeness of the tables.
4.
AP&L will submit the following information to NRC:
a.
By June 30, 1983, AP&L will submit revised Technical Specifications for AN0-1&2 to reference ANSI /ASME OM4-1982; and b.
Within 60 days of the end of the next scheduled refueling outage for each unit, AP&L will submit to NRC a list of all mechanical and hydraulic snubbers which are nuclear safety related in the verified table format in Item 3 above.
Our resolution to the ability to test the greater than 50,000 lb.
snubbers which are nuclear safety related will be included with the submittal of the above tables to NRC following each respective
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refueling outage.
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