ML19320C967
| ML19320C967 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/13/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-80-08, IEB-80-8, LAC-6984, NUDOCS 8007180355 | |
| Download: ML19320C967 (3) | |
Text
Y/6 A
D YLAND k
COOPERAT/VE. p o Box 837 i
2615 EAST AV SOUTH. LA CROSSE. WISCONSIN 54601 (608) 788 4 000 June 13, 1980 In reply, please refer to LAC-6984 DOCKET NO. 50-409 Mr. James G. Keppler Regional Director U.
S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DRR-45 IE BULLETIN NO. 80 EXAMINATION OF CONTAINMENT LINER PENETRATION WELDS
Reference:
(1)
NRC Letter, Keppler to Linder, dated April 9, 1980 - Enclosing IE Bulletin No. 80-08.
Dear Mr. Keppler:
In response to your letter (Reference 1) which contained the subject bulletin and required a written response, we are submitting the following comments.
Item 1.
Determine if your facility contains the flued head design for penetration connections, or other designe with contain-ment boundary butt veld (s) between the penetration eteeve and process piping as illustrated in Figure NE 1120-1, Winter 1975 Addenda to the 1974 and later editions of the ASME B&PV Code.
DPC RESPONSE:
LACBWR does not have any containment penetrations that utilize the flued head design.
LACBWR does have three penetration connections with containment boundary butt welds.
They are similar to illustration (e) on Figure NEll20-1, 1977 Edition of the ASME B&PV Code.
The penetrations are used for passage of the reactor plant main steam piping, feedwater piping, and one penetration used for passage of heating steam into the Containment Bsilding and heating steam condensate out of the Containment Building.
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h Mr. James G.
Keppler, Regional Director LAC-6984 U.
S. Nuclear Regulatory Commission June 13, 1980 l
Item 2.
If an affirmative ansuer is reached for Item 1, determine the foltouing:
i Applicability of the ASME Code including year and a.
addenda and/or Regulatory Guide 1.19.
DPC RESPONSE:
The Containment Building and the penetrations were constructed to the 1962 Edition of Section VIII of the ASME B&PV Code.
b.
Type of nondestructive examinatione performed during construction.
I DPC RESPONSE:
On the butt welds specifically addressed in Reference (1), there was a ieak test.
The sleeve (penetration connection) butt welds of the LACBWR vessel were excluded from radiography by Paragraph UW-ll(a) (5) of Code Edition in 2.1. above.
c.
Type of veld joint (including pipe material and size) and whether or not backing bare vere used.
DPC RESPONSE:
Open "V" single welded butt without backing bar.
Main steam penetra-tion is plate, 61-5/16" x 1/2" rolled, seam welded.
Feedwater pene-tration is plate 41-15/32" x 1/2" rolled, seam welded.
Both plates are carbon steel per ASTM A201B and test requirements of A300.
The heating steam and condensate penetration is 12", Schedule 40 pipe to ASTM A333, Grade C.
d.
Results of construction nondestructive examinatione,
- i. e., if repaire vere required, this should be identi-fied including extent of repaire and description of defecte encountered during repair, if known.
DPC RESPONSE:
After completion of the vessel penetrations, a pneumatic leak-rate test was performed at 5 psig internal pressure and penetration welds checked for leaks by the soap-suds method.
The internal pressure was subsequently increased to 52 psig and held for 2 days with no evidence of leakage by the soap-suds method, from the penetration butt welds.
No repairs were performed on any of the three penetrations. - _.
i',
Mr. James G. Keppler, Regional Director LAC-6984 U. S. Nuclear Regulatory Commission June 13, 1980 Item 3.
For thoac facilities committed during construction to perform volumetric examination of such penetratione through SAR commitmente uhich have not performed radio-graphy, justify not performing radiography or submit plane and schedules for performing radiographic examin-ations.
DPC RESPONSE:
No volumetric examination of the above penetrations was committed to in the SAR (Final Safeguards Report ACNP-65544, dated August 1967) and subsequent answers to questions of DRL.
If you have any questions concerning this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE
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Frank Linder, General Manager FL: EAT:af cc:
Director Division of Reactor Construction Inspection U. S. Nuclear Regulatory Commission Washington, D. C.
20555
.