ML19291C093
| ML19291C093 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/19/1979 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-17, NUDOCS 8001210016 | |
| Download: ML19291C093 (4) | |
Text
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Commonwealth Edison
[b One First National Plaza, Chicago, Ilknois Address Reply to: Post Office Box 767 Chicago, Illinois 60690
,r December 19, 1979 Mr. James G. Keppler, Director Directorate of Inspection and Enforcement - Region III U.S.
Nuclear Regulatory Commission 799 Roouvelt Road Glen Ellyn, IL 60137
Subject:
Zion Station Units 1 and 2 Additional Response to IE Bulletin No. 79-17, " Pipe Cracks In Stagnant Borated Water Systems at PWR Plants."
NRC Docket Nos. 50-295 and 50-304 References (a) :
July 26, 1979 letter from J.
G.
Keppler to Byron Lee, Jr.
(b) :
October 30, 1979 le tte r from J. G.
Keppler to Cordell Reed (c) : ' August 24, 1979 letter from Cordell Reed to J.
G.
Keppler
Dear Mr. Keppler:
Reference (a) transmitted IE Bulletin No. 79-17, " Pipe Cracks In Stagnant Borated Water Systems At PWR Plants."
Re fe re nce (b) transmitted Revision 1 to that Bulletin.
Reference (c) contained Commonwealth Edison Company's response to Bulletin Item 1.
Attach-ment 1 to this letter contains Commonwealth Edison's response to Iten 2 of this Bulletin.
As indicated in Attachment 1, there are no unresolved items with regard to this Bulletin.
Therefore, with this submittal Commonwealth Edison has fulfilled the require-ments of References (a) and (b).
Please address any additional questions that you might have concerning this matter to this office.
Very truly yours,
- 4 sh' 7
1791 026 0FC271979 D.
i,. ecopt s
-irector of Nuclear Licensing Attachment cc:
Director, Division of 8 001210 Ot6 Operating Reactors
./
NRC Docket Nos: 50-295 50-304 Commonwealth Edison Company Response to Item 2 of IE Bulletin No. 79-17 2
For Zion Station Introduction Zion Station completed the examinations required by Items 2(a) and 2(b) of I.E.
Bulletin No. 79-17 on October 29, 1979.
Item 2 of I.E.
Bulletin 79-17, Revision 1, states that inspections performed in accordance with the original bulletin satisfy the requirements of the revision.
This is the case for Zion Station.
Scope The normally accencible pn;tions of systems identified in Zion Station's response to Item 1 of the Bulletin, Reference (c), were examined as described below.
Further review of the plant design led to an addition to the scope of examinations.
All accessible portions of the Spent Fuel Cooling Systems, including all pipe diameters in the 2 1/2 to 24 inch range were inspected in accordance with Item 2 of the Bulletin.
The attached Table 1 lists the lines in this system and stand as an amendment to Table 1 of Reference (c).
Procedures and Personnel All examination procedures were approved prior to the examinations, and certification documents relative to personnel, equipment and materials were reviewed and determined to be sat-isfactory.
Examinations In August 1979 Zion Station performed the visual examina-tion required by Item 2(a) of the Bulletin, in accordance with A.S.M.C.
Section XI, IWA2210.
All accessible engineered safety systems were examined in both Unit 1 and 2.
Additionally, all accessible spent fuel piping was examined in accordance with IWA-2210.
From October 15, 1979 through October 29, 1979, volumetric and surface examinations were conducted as required by Item 2 (b) of the Bulletin.
The ultrasonic examinations were conducted using techniques proven reliable in detecting evidence of IGSCC (Inter-granular Stress Corrosion Cracking) in austentic stainless steel.
1791 027
Liquid penetrant examinations were also conducted to assist in dptecting cracking in contact with the piping outsice wall.
The sample plan utilized for Item 2(b) is listed below and consists of the total percentage of Unit 1, Unit 2 and the common spent fuel piping.
Additionally, the percentage inspected by piping diameters are listed.
This program represents an a
examination of 150 out of 1,117 weld areas.
Total Percent Per Piping Diameter Percentage 18" 12" 10" 8"
4 3"
Unit 1 13%
11%
15%
11%
15%
111 339 Unit 2 12%
11%
15%
13%
15%
10%
17%
Spent Fuel 17%
24%
15%
15%
Examisaation Results The results of the above examinations revealed no reportable evidence of intergranular stress corrosion cracking.
Corrective Action None required.
I791 028
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TABLE 1 PORTIONS OF SYSTEMS ADDITIONALLY IDENTIFIED FOR I.E. BULLETIN 79-17 Wall I.S.I.
Line Number Description Size Schedule Material Thickness Performed OSF001-10"AA Spent Fuel Cooling 10" 40S A312-Tp 304
.365" No OSF012-3"AA Spent Fuel Cooling 3"
40S
.216 No ISF 0 01-8" AA Spent Fuel Cooling 8"
40S
.322 Do 1SF001-10"AA Spent Fuel Cooling 10" 405
.365 No 1SF002-8"AA Spent Fuel Cooling 8"
40S
.322 No 1SF002-10"AA Spent Fuel Cooling 10" 40s
.365 No 1SF003-10"AA Spent Fuel Cooling 10" 40S
.365 No 1SF0 0 7-3" AA Spent Fuel Cooling 3"
40S
.216 No ISF015-3"AA Spent Fuel Cooling 3"
40S
.216 No 1SF022-3"AA Spent Fuel Cooling 3"
40S
.216 No 2SF001-10"AA Spent Fuel Cooling 10" 40s
.365 No 2SF0 01-8" AA Spent Fuel Cooling 8"
40S
.322 No 2SF002-10"AA Spent Fuel Cooling 10" 40S
.365 No 2SF002-8"AA Spent Fuel Cooling 8"
40S
.322 No 2SF003-10"AA Spent Fuel Cooling 10" 40s
.365 No 2SFOU7-3"AA Spent Fuel Cooling 3"
40S
.216 No 2SF015-3"AA Spent Fuel Cooling 3"
40S
.216 No 2SF022-3'AA Spent Fuel Cooling 3"
40S
.216 No 9
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