ML20207Q598

From kanterella
Jump to navigation Jump to search
Forwards Inservice Insp Program Relief Requests RI-20 Re Component Supports within Suppression Pool Containment Structure & RI-21 Re Insp of ASME Section XI Components. RI-21 Applicable Only to Unit 1
ML20207Q598
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/20/1987
From: Allen C
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2623K, NUDOCS 8701280308
Download: ML20207Q598 (4)


Text

, m'N Commonwealth Edison

/

_ 2 One First National Plaza, Chicago, Illinois

(

~

\\

7 Address Reply to: Post Office Box 767 Chicago, Illinois 60690 0767 January 20, 1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

LaSalle County '3tation 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 1 ASME period is only applicable to Unit 1.

If you have any additional questions regarding this matter, please contact this office.

C. M. Allen Nuclear Licensing Administrator 1m httachments cc:

Dr. A. Bournia - NRR Regional Administrator - RIII NRC Resident Inspector - LSCS l

8701280308 870120 DR ADOCK 05000373 h0 i

2623K l

l l

l i

LASALLE COUNTY STATION Page _1_,of 1 LafIT S_,1._

I@I RELIEF R8 QUEST RI-20 t

AFFECTED SYSTEfEi-SYSTEM CLASS CATEGORY / ITEM MLNBER HPCS 2

N/A LPCS 2

N/A

[

MS 3

N/A RHR 2

N/A j

RCIC 2

N/A 1

i EXEfrTED COhPONENT:

Component supports located within the Suppression Pool Containment Structure.

2 i

l SBCTION XI TEST REDUIREFERNT:

VT-3 Visual Bramination of component Support Assembly.

[

BASIS FOR RELIEF:

These component supports are either guides or rigid struts and are all located j

within the Suppression Pool. In order to perform a meaningful VT-3 exassination on l

these components, removal of surface residues from the supports would be necessary

}

prior to inspection. The cleaning process would be relatively involved and would j

present safety and contamination hazards to personnel involved. The Suppression j

Pool would most likely need to be drained for this process and scaffolding l

erected. A VT-3 inspection of these component supports is considered to be impractical.

6 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 t

performed during reactor shutdown prior to each Type A Containment Leak Rate Test, i

i thus exceeding the inspection frequency of ASIE Section XI.

t I

j I

l 1

DOCUMENT ID 2582r/

i

.~

LASALLE COUNTY STATION Page L of _.L L2 FIT # 1 ISI CELIEF REQUEST RI-20 AFFBCTED SYSTEMS; i

SYSTEM CLASS CAT 800RY/ ITEM WUPEMER l

HPCS 2

N/A I

LPCS 2

N/A MS 3

N/A 2

2 N/A 1

RHR RCIC 2

N/A EXEFESTED COMPONENT; Component supports located within the Suppression Pool Containment Structure.

SECTION XI TEST REOUIREMENT:

VT-3 Visual Examination of Component Support Assembly.

1 BASIS POR 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 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 woeild 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.

I ALTERNATE TEST; Personnel will perform a general visual inspection of Suppression Pool internal structural elements for evidence of apparent changes in proper pipe support orientation. This will not be a VT-3 examination. The inspection will be l

performed during reactor shutdown prior to each Type A Containment Leak Rate Test, thus exceeding the inspection frequency of ASPEE Section XI.

i i

o,w s

i DOCUMENT ID 2582r/

9 Page _1_ of _ L LASALLE COUNTY STATION LalIT #_L I

ISI RELIBF RBQUEST HI-21 AFFBCTED SYSTEMS:

SYSTEM CLASS CAT 800RY/ ITEM NUIERER ALL 1,2,3 ALL ASfEE XI SYSTEMS All ASME Section XI Components requiring inspection during the 1st AS M Period.

EXEfrTED CCfr0NENT:

The 1st Period inspections are required to be completed within a maximum time saCTION XI TEST RBOUIRBfEEWT:

period of 4 years (3 years plus the 1 year extension allowed by IWB-2412(b)).

Due to the unexpected extension of the 1st refueling outage (Winter 85, 11 mo.

BASIS POR RELIEF:

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 allowed period extension of IWB-2412(b) is applied. The Commercial Service date for Unit 1 is January 1, 1984, and the 2nd refueling outage is scheduled for December of 198~l.

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 ASM 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 I

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 the 2nd refueling outage.

l 1

l DOCUMENT ID 2582r/

.