ML18005A766
| ML18005A766 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/30/1989 |
| From: | Richey R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLS-89-015, NUDOCS 8902060188 | |
| Download: ML18005A766 (7) | |
Text
gqcE~RATED D1~BUT10N DEMONS'l7+10Y SY) TEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8902060188 DOC.DATE: 89/01/30 NOTARIZED-NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION RICHEY,R.B.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET I 05000400
SUBJECT:
Forwards Suppl '1 to Relief Request R2-001 re ISI plan for first 10-yr interval.
DISTRIBUTION *CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice Inspection/Testing/Reli f from ASME Code NOTES:Application for permit renewal filed.
0500040(P RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS ARM/DAF/LFMB NRR/DEST/MTB 9H OGC/HDS 1 RES/DSIR/EIB EXTERNAL EGGG ROCKHOLDI H NL 007 HEMMING NSIC COPIES LTTR ENCL 1
0 1
1 6
6 1
0 1
1 1
0 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD2-1 PD AEOD/DSP/TPAB NRR/DEST/MEB 9H NUDOCS-ABSTRACT E~~I Ol LPDR NRC PDR COPIES LTTR ENCL 5
5 1
1 1
1 1
1 1
1 1
1 1
1 R
I h
NCTE 'IO ALL "RZDS" RZCZPrWXS.
PIZASE HELP US 'IO REDUCE HASTE! ~CI'ZHE DOCUMENI'XWHKLDESK ROOM Pl-37 (EXT. 20079)
TO EXZKQQZE RXlR NME FMH DISTEKBVTIGN LISTS FOR DOCRKNTS YOU DON'T NEEDf TOTAL NUMBER OF,COPIES REQUIRED:
LTTR 26 ENCL 23
Carolina Power &LightCompany R O. Box 155t
~ Raleigh, N. C 27602 gAN 5 0
$989 R. B. RICHEY, Manager Nuclear Services Department SERIAL: NLS-89-015 10CFR50.55 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 INSERVICE INSPECTION RELIEF REQUEST Gentlemen:
Carolina Power
& Light Company hereby submits Supplement 1 to Relief Request No. R2-001.
This request was submitted on January 28, 1988 as part of the Shearon Harris Nuclear Power Plant Ten Year Inservice Inspection Plan for the first ten year interval.
The Staff approved this plan on September 30, 1988 'he proposed revision adds three additional Class 2 welds to the list of those welds for which performing 100% volumetric and/or surface examinations, as required by Section IX of the ASME Code, is not possible.
During the recent first refueling outage, the need for relief from the required surface examinations for three welds was identified.
Obstructions prevented a
100% examination of the welds.
These obstructions were not encountered during the Preservice Inspection (PSI) of these welds, which was completed while some construction activities were still in progress.
Since the PSI, pipe supports, structural
- braces, and cable tray supports have been installed which interfere with the surface examination of the subject welds.
The following list of affected welds shows the percent of the examination performed.
Examination Cate or Com onent ID Examination 0 Achieved Surface Volumetric CAT-FSAR ITNM0-6.6.8.E (augmented)
II-BD-011BD-FW-305 86%
N/A CAT C-F ITMNO-C5.21 II-MS-001MS-FW-284 90'00%
CAT C-F ITMNO-C5.21 II-MS-001MS-SW-A3 90'00%
A copy of Relief Request R2-001 is included for your information.
This provides the basis and technical justification for granting relief for i
8902060iSS 890i30 PDR ADOCK 05000400 9
.L t
Document Control Desk NLS-89-015 / Page 2
these three additional welds.
The original relief request along with its associated attachment is included in the Shearon Harris Nuclear Power Plant Ten Year Inservice Inspection Plan submitted on January 28, 1988.
Carolina Power
& Light Company requests approval of this supplement by November 1, 1989 in order to support the second SHNPP refueling outage, currently scheduled for November 1989.
Please refer any questions regarding this submittal to Mr. Mark A. Turkal at (919) 362-2985.
Yours very truly, R.
B, Richey RBR/MAT cc:
Mr. R. A. Becker Mr.
W. H. Bradford Mr. M. L. Ernst
REQUEST FOR RELIEF NO. R2-001:
PRESSURE'RETAINING WELDS IN IN PIPING, CATEGORY C-F, ITEM: C5.21; AND INTEGRAL WELDED ATTACHMENTS FOR VESSELS,
- PIPING, PUMPS AND VALVES'ATEGORY C-C, ITEMS: C3.20 and 3.30.
IDENTIFICATION OF COMPONENTS:
Pressure retaining circumferential piping welds; and integral welded attachments on vessels,
- piping, pumps and valves as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENTS:
Examination Category C-F, Item C5.21 requires, on pressure retaining circumferential welds in piping
> 1/2 in. nominal wall thickness, an inservice surface and volumetric examination be performed.
Examination Category C-C, Item(s)
C3.20 and C3.30 requires
.an inservice surface examination be performed on integral welded attachments meeting, the following condition:
(1) The attachment base material design wall thickness is 3/4 in. or greater.
CODE RELIEF REQUEST:
Relief is requested from performing 100% volumetric and/or surface examinations on listed circumferential piping welds
(> 1/2 in. nominal wall thickness) and listed integral welded attachments due to component configurations (pumps, valves) not being conducive to examination, and/or structural obstruc-tions (permanent
- hangers, saddle plates, support structures, or intervening members for other systems) not allowing access-ibility to perform 100% surface and/or volumetric examination, as applicable (see computer listing for component identifica-tion and predicted completion percentages, based on preservice baseline information, for the appropriate examinations).
ALTERNATE EXAMINATIONS:
Components will be subject to periodic systems pressure
- tests, as well as periodic hydrostatic and visual (VT-2) examination, to the maximum extent possible.
Welds will be volumetrically (U.T.) examined, to the maximum extent possible, in accordance with the Inservice Inspection Program Schedule.
In addition, the components will be subject to system pressure tests during each refueling outage.
CONSTRUCTION CODE EXAMINATION:
Volumetric (as applicable)
Surface (as applicable)
Page 1 of 2
aa, 1
R2-001 Cont.
TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF Component configurations (pumps, valves) and/or structural obstructions (hangers, saddle plates, support structures) will not allow 100% inservice volumetric and/or surface examination to be performed.
Components were subject to fabrication/construction volumetric and/or surface examinations, as applicable, which provides a high confidence level of structural integrity for long-term plant operations.
In addition, in response to NRC question 250.1 and FSAR Section 6.6.8, a large sample of welds in the
- ECCS, CHR and RHR Systems, as well as No Break Zone Crit-eria components were examined during preservice activities (1,064 examinations including 525 surface and 539 volumetric),
providing additional assurance of structural integrity.
Attached to this relief request is an itemized listing of components, percentages of completion based on preservice
- data, and identification of specific reasons as to why a l00%
ASME Section XI Code examinations can not be performed.
Should more advance nondestuctive method techniques to improve coverage become available, an evaluation will be performed for possible incorporation into the SHNPP ISI Program.
No impact on plant quality, safety or reliability is expected, as subject components will be examined to the maximum extent
- possible, as well as be subject to periodic pressure tests and visual examinations in accordance with the ASME Section XI
- Code, to ensure component intergrity.
This Request for Relief (R2-001) is applicable to the SHNPP Unit 1 First Ten (10) Year Inservice Inspection Program.
Page 2 of 2