ML19347B163
| ML19347B163 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/26/1980 |
| From: | Moody D YANKEE ATOMIC ELECTRIC CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-17, IEB-79-17-R1, WYR-80-103, NUDOCS 8010010716 | |
| Download: ML19347B163 (4) | |
Text
T
- a 7*-
Telephone 617 366-9011 twx 710-390-0739 YANKEE ATOMIC ELECTRIC COMPANY s.4.1.1 WYR-80-103
,Yaux$
20 Turnpike Road Westborough, Massachusetts 01581 es
~
August 26, 1980 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Rcgion I 331 Park Avenue King of Prussia, Pennsylvania 19406 Attention:
Mr. Boyce H. Grier, Director
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) USNRC Circular 76-06, dated November 24, 1976 (c) YAEC letter to USNRC Region I, dated December 22, 1976 (WR 76-130)
(d) YAEC letter to USNRC Region I, dated September 23, 1977 (WR 77-91)
(e) USNRC letter to YAEC, dated July 26, 1979 I&E Bulletin 79-17 (f) UIC letter to USNRC Region I, dated August 24, 1979 (WR 79-93)
(g) USNRC letter to YAEC, dated October 29, 1979 I&E Bulletin 79 Rev. 1 (h) YAEC letter to USNRC Region I, dated November 27, 1979 (WR 79-147)
Subject:
Response to I&E Bulletin 79-17 (Rev. 1) Results of Inspection
Dear Sir:
The following information is being submitted in response to the commitments of Reference (h) and the requirements of Bulletin 79 Rev. 1
[ Reference (g)], paragraph 5.
The inspections required by Bulletin 79 Rev. O were performed in the fall of 1979.
The criteria of paragraph 2 of that Bulletin were followed to select and inspect the welds defined in the following table.
8010 0 l'0 7//p
o United States Nuclear Regulatory Commission August 26, 1980 Attention:
Mr. Boyce H. Crier, Director Page 2 1.
Bulletin 79-17 Fall 1979 Inspection Welds 10% sample by pipe size and system Pressurizer Decon Spray Size Total Inspected 1" (Socket Welded) 16 4
Loop Fill Size (Jul Inspected 2"
27 4
Shutdown Cooling System Size Total Inspected 6" (Class 1) 13 2
6" (Class 2) 54 6
8" 5
0 72 8
Safety Injection System - Includes:
HPSI/LPSI discharge headers SI Lines to individual loops Size Total Inspected 2" (Class 1) 32 4
2" (Class 2) 41 5
3" (Class 1) 13 2
3" (Class 2) 19 2
4" (Class 1) 61 8
4" (Class 2) 45 5
6" 16 4
8" 48 6
275 36
'IE Bulletin 79 Rev. I contained a definition of stagnate oxygenateu borated water systems which differed from our interpretation of the Rev. O Bulletin.
We submitted Reference (h) stating our intention to complete the additional exams required during the refueling outage of 1980.
The following table summarizes the extent of systems selected and inspected.
United States Nuclear Regulatory Commission August 26, 1980 t
Attention:
Mr. Boyce H. Grier, Director Page 3 II.
Bulletin 79-17 (Rev. 1)
Summer 1980 Inspection Welds 10% Sample by pipe size and system Safety Injection System - Includes:
HPSI/LPSI Suction HPSI/LPSI discharge (near pumps only)
HPSI/LPSI Recire.
Hot Leg Injection Size Total Inspected 2" (Socket Welded) 115 14 3"
23 4
4" 23 4
6" 60 6
8" 9
2 10" 22 4
252 34 Chemical Shutdown System - Boric Acid Mix Tank to Charging Suction Header Size Total Inspected 2-1/2" (Speedline) 6 1
3" (Speedline) 11 2
4" (Speedline) 25 3
42 6
The inspections were completed in August 1980 and the results are summarized below.
1.
No evidence of cracking due to stress corrosion was found in any of the systess shown in the previous tables.
2.
Indications were found and verified to be unacceptable per the code requirements.
These indications were lack of fusion in a repaired area of weld LPSI-17-4 and an area of lack of fusion and an area of slag in LPSI-17-2.
These joints were repaired, re-ext. mined, and found acceptable.
3.
Weld porosity and subsequent leakage was found on the fillet welds of valve CS-MOV-540. A report of this finding and corrective action was filed as LER-50-29/8-
,/03L-0.
i l
United States Nuclear Regulatory Commission August 26, 1980 Attention:
Mr. Boyce H. Grier, Director Page 4 4.
Various linear indictions were detected at the toe of the filler weld on the valve to coupling weld of six Cooper Alloy Valves.
Extensive metallurgical examination has indicated the defectc to be associated with casting procedures and subsequent machining of the castings. A separate report will be submitted to detail the study and its conclusions.
All of the conditions noted above have or will be corrected prior to return to power. The response of August 24, 1979 [ Reference (f)] and the examination results supplied herein complete the requirements specified in USNRC Bulletin 79 Rev. 1.
We trust this information is satisfactory; however, if you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY t!=Y
. E. Moody 7 nager of Operations i
JJL/jgh