ML20212Q656
| ML20212Q656 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/21/1987 |
| From: | Allen C COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2623K, NUDOCS 8702020326 | |
| Download: ML20212Q656 (4) | |
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One Fir;t Nfional Plart Chicago, Illinois
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/ Address Reply to: Post Offica Box 767
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\\d Chicago, Illinois 60690 0767 January 21, 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 ISI Program Relief Requests RI-20 & 21 NRC Docket Nos. 50-373 and 50-374 Reference (a): Letter dated September 17, 1986 from C. M. Allen to H. R. Denton.
Dear Sir:
Attached are copies of two new ISI program relief requests, RI-20 and RI-21.
Relief request RI-20 regarding components supports within the Suppression Pool Containment Structure is applicable to both units. RI-21 regarding all ASME Section XI components during the first ASME period is only applicable to Unit 1.
If you have any additional questions regarding this matter, please contact this office.
&ytrulyyours, Ver df C. M. Allen Nuclear Licensing Administrator l
im Attachments cc:
Dr. A. Bournia - NRR Regional Administrator - RIII NRC Resident Inspector - LSCS j
2623K 8702020326 870121 DR ADOCK 05000373
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LASALLE COUNTY STATION
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1 ISI RELIEF RBQUEST RI-20 AFFECTED SYSTEMS:
SYSTEM CLASS CATBOORY/ ITEM NUMBER HPCS 2
N/A LPCS 2
N/A i
MS 3
N/A RHR 2
N/A RCIC 2
N/A j EXEN TED COWONENT:
Component supports located within the Suppression Pool Containment Structure.
j SBCTION XI TEST RBOUIREMENT:
VT-3 Visual Examination of Component Support Assembly.
BASIS FOR RELIEF:
These component supports are either guides or rigid struts and are all located within the Suppression Pool.
In order to perform a meaningful VT-3 examination on these components, removal of surface residues from the supports would be necessary prior to inspection. The cleaning process would be relatively involved and would present safety and contamination hazards to personnel involved. The Suppression Pool would most likely need to be drained for this process and scaffolding erected. A VT-3 inspection of these component supports is considered to be i
impractical.
Personnel will perform a general visual inspection of Suppression Pool internal ALTERNATE TEST:
j structural elements for evidence of apparent changes in proper pipe support i
orientation. This will not be a VT-3 examination. The inspection will be performed during reactor shutdown prior to each Type A Contahament Leak Rate Test, thus exceeding the inspection frequency of ASput Section XI.
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DOCUMENT ID 2582r/
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Page _.l_ of _.L.,
LASALLE COUNTY STATION UNIT #_2_
t ISI CELIBF R8 QUEST RI-20 t
AFFECTED SYSTEMS:
I SYSTEM CLASS CAT 8 GORY / ITEM NUMBER HPCS 2
N/A LPCS 2
N/A ns 3
N/A 2
N/A RHR 1
RCIC 2
N/A
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EXEN TED COW ONENT Component supports located.within the Suppression Pool Containment Structure.
SBCTION XI TEST REOUIREMENT; VT-3 Visual Examination of Component Support Assembly.
BASIS FOR RELIBF; These component supports are either guides or rigid struts and are all located within.the Suppression Pool.
In order to perform a meaningful VT-3 examination on these components, removal of sur' face residues from the supports would be necessary prior to inspection. The cleaning process would be relatively involved and would present safety and contamination hazards to personnel involved. The Suppression Pool would most likely need to be drained for this process and scaffolding erected. A VT-3 inspection of these component supports is considered to be impractical.
ALTERNATE TEST:
Personnel will perform a general visual inspection of Suppression Pool internal structural elements for evidence of apparent changes in proper pipe support i
orientation. This will not be a VT-3 examination. The inspection will be
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performed during reactor shutdown prior to each Type A Containment Leak Rate Test, 2
thus exceeding the inspection frequency of ASME Section XI.
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DOCUMENT ID 2582r/
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LASALLE COUNTY STATION UNIT # 1 4
I ISI RELIEF RBQUEST RI-21 AFFECTED SYSTEMS:
SYSTEM G14Ei CATBGORY/ ITEM NUMBER ALL 1,2,3 ALL j
ASME XI l
SYSTEMS All ASME Section XI Components requiring inspection during the 1st ASfB Period.
EXEfffED 00ff0NENT:
SECTIOff XI TEST RBOUIREfEDIT:
The 1st Period inspections are required to be completed within a maximum time period of 4 years (3 years plus the 1 year extension allowed by IWB-2412(b)).
BASIS FOR REZEF:
Due to the unexpected extension of the 1st refueling outage (Winter 85, 11 mo.
l outage) on LaSalle Unit 1, it is possible that a 2nd refueling outage will not occur within the 1st Section XI Inspection Period. This is true even when the l
allowed period extension of IWB-2412(b) is applied. The cosunercial Service date l
for Unit 1 is January 1, 1984, and the 2nd refueling outage is scheduled for December of 198~1.
If the start date of the 2nd refuel is delayed into 1988 we would not be able to meet the minimum completed inspection requirements of ASME Section XI, as found in Tables IWB-2412-1, IWC-2412-1, and IWD-2500-1.
We request that the end of the 1st Inspection Period on Unit 1 be extended to ALTERNATE TEST:
coincide with the unit's 2nd refueling outage. Subsequent Inspection Periods would then be completed in accordance with section XI.
When considering the total operating time on the unit, it is impractical to shutdown the unit for inspection prior to ae 2nd refueling outage.
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DOCUMENT ID 2582r/
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