ML20076F395
| ML20076F395 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/31/1983 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8306140071 | |
| Download: ML20076F395 (3) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Meiling Address
+
Alabama Power Company s600 North 18th Street e
Post Offica Box 2641 Birmingh:m. Alabama 35291 USNRC REGlDh.*
Telephone 205 783-6081 m a Wt. ^EOPGl^
F. L. Claylon, Jr.
Senior %ce President AlabamaPbwer Flintridge Building j y[j g pll l { h tre southem ekxttc system May 31, 1983 Docket Nos. 50-348 S0-364 U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N. E.
Atlanta, GA 30303 Attention:
Mr. J. P. O'Reilly, Administrator Joseph M. Farley Nuclear Plant - Units 1 and 2 IE Bulletin Number 82-02 Gentlemen:
In accordance with IE Bulletin 82-02, subject:
" Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants," the following is submitted:
NRC REQUEST:
Submit a statement that where procedures do not exist, develop and implement maintenance procedures for threaded f astener practices.
These procedures should include, but not [be] limited to the following:
(1) maintenance crew training of proper bolting / stud practices, tools application, specifications and requirements, (2) detensioning and retensioning practices (torque iteration),
specified tolerances, and other controls for disassembly and reassembly of component closure / seal connections, (3) gasket installation and controls, and (4) retensioning methods and other measures to eliminate reactor coolant leakage during operation.
8306140071 830531 PDR ADOCK 05000348 G
PDR h ~1~EI(
Mr. J. P. O'Reilly May 31, 1983 U. S. Nuclear Regulatory Commission Page 2 Quality assurance measures should also be established for proper selection, procurement, and application of fastener lubricants and injection sealant compounds to minimize fastener susceptibility to SCC envi ronments.
APC0 RESPONSE:
i The maintenance and quality assurance measures listed above have been implemented for the Farley Nuclear Plant.
Formal documentation via procedures has been established for items 2, 3 and 4.
Training associated with item I has been conducted and documented.
This represents a clarification of the January 17, 1983 submittal for Unit 2.
NRC REQUEST:
Threaded fasteners of closure connections, identified in t
the scope of this bulletin, when opened for component inspection or maintenance shall be removed, cleaned, and inspected per IWA-2210 and IWA-2220 of ASME Code Section XI (1974 edition or later) before being reused.
Identify the specific connections examined and provide the results of this examination.
APC0 RESPONSE:
The below listed threaded fasteners of closure connections were routinely opened for component inspection / maintenance during the recent Unit I refueling outage with the following results:
Closure Type of Description Examination Results Reactor Coolant Pumps A Removed - Wet Magnetic No degradation and B #1 Seal Housing Particle, Ultrasonic and Visual l
i Steam Generator C Hot and Removed - Dye Pene-No degradation I
Cold Leg Manways trant and Visual l
Mr. J. P. O'Reilly May 31, 1983 U. S. Nuclear Regulatory Commission Page 3 Closure Type of Description Examination Results Hi/Lo Head SI Check Valve Removed - Dye Pene-No degradation Q1E11V051A trant and Visual Hi/Lo Head SI Check Valve Removed - Dye Pene-No degradation Q1E11V051B trant and Visual Hi/Lo Head SI Check Valve Removed - Dye Pene-No degradation Q1E11V051C trant and Visual Hi/Lo Head SI Check Valve Removed - Dye Pene-No degradation Q1E11V077A trant and Visual Accumulator Discharge Check Removed - Dye Pene-No degradation Valve Q1E21V032B trant and Visual A number of f asteners in the inspected components were disqualified f or reuse due to physical thread damage consisting of nicks and chips.
No borated water corrosion wastage, erosion - corrosion damage or stress corrosion cracking was identified.
All damaged f asteners were replaced with new f asteners which were examined before installation.
If you have any questions, please advise.
Yours very truly,
~
9 t/]
m W
. L. Clayton Jr.
FLCJr/ JAR:ddr-D37 cc:
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. S. A. Varga SWORN TO AND SUBSCSIBED BEFORE ME Mr. E. A. Reeves THIS 2; O DAY OF /(l W
,1983 l
/l Mr. W. H. Bradford G
disdahndau Notary Public My Commission Expires H o-87 l
i I
4