ML16152A765
| ML16152A765 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/09/1988 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML16152A766 | List: |
| References | |
| NUDOCS 8812210063 | |
| Download: ML16152A765 (6) | |
Text
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ACCELERATED DlbTRIBUTION DEMONSTRATION SYSTEM REGULPORY INFORMATION DISTRIBUT*
SYSTEM (RIDS)
ACCESSION NBR-:8812210063 \\.DOC.DATE: 88/12/09 NOTARIZED: NO DOCKET #
FACIL:50-269 Oconee NUclear Station, Unit 1, Duke Power Co.
05000269 50-270 Oconee Nuclear Station, Unit 2, Duke Power Co.
05000270 50-287 Oconee Nuclear Station, Unit 3, Duke Power Co.
05000287 AUTH.NAME AUTHOR AFFILIATION TUCKER,H.B.
Duke Power Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Requests relief from requirements of Section XI of ASME Boiler & Pressure Vessel Code re second 10-yr insp interval.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR / ENCL L SIZE:
TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 LA 1
0 PD2-3 PD 5
5 PASTIS,H 1
1 INTERNAL: ACRS 6
6 AEOD/DSP/TPAB 1
1 ARM/DAF/LFMB 1
0 NRR/DEST/MEB 9H 1
1 NRR/DEST/MTB 9H 1
1
,NkE)0C~w.ABSTRACT 1
1 OGC/HDS2 1
0 RE FI E 01 1
1 RES/DSIR/EIB 1
1 EXTERNAL: EG&G ROCKHOLD,H 1
1 LPDR 1
1 NL 007 HEMMING 1
1 NRC PDR 1
1 NSIC 1
1 I
NOTE TO AL-L "IDS" RECIPIENTS:
PLEASE HEL US TO REDUCE WST!
CDNTCT THE DOMENT ODNTRL DESK, ROOM4 Pl-37 (EXT.
20079) To ELIMMINT MOU NAM FROMK DISTRIBUTION LISTS MOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED:' LTTR 26 ENCL 23
Duke Power Company HAL B. Tcker P 0. Box 33198 Vice President Charlotte, NC 28242 Nuclear Production (704)373-4531 DUKE POWER December 9, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Oconee Nuclear Station Docket Nos. 50-269, -270, -287 Second Ten Year Interval Request for Relief No. 88-'09 Gentlemen:
Pursuant to 10CFR 50, 50.55a, please find attached request for relief number 88-09 from the requirements of Section XI of the ASME Boiler and Pressure Vessel Code (with Addenda through Winter 1980).
This request is being submitted due to the impracticality of pressure testing specific welds as required by the Code following repair.
The attached 'requests concern the inservice inspection at Oconee Unit 1 being performed during the second ten year interval.
This 'request is considered to supplement the request made by my letter dated September 13, 1984. As such, no additional fees are required.
Very truly yours, Hal B. Tucker SEL/368/mmf Attachment 8812210063 881209 04l PDR ADOCK 05000269 p
PN
Document ContrQl Desk December 9, 1988 Page 2 xc:
w/o diagrams Mr. M.L. Ernst Deputy Regional Administrator U.S. Nuclear Regulatory Commission -
Region II 101 Marietta St. NW Suite 2900 - Atlanta, GA 30323 Ms. Helen Pastis Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Heyward Shealy, Chief Bureau of Radiological Health S.C. Department of Health and Environmental Control 2600 Bull Street Columbus, S.C. 29201 Mr. P.H. Skinner NRC Resident Inspector Oconee Nuclear Station
Document Control Desk December 9, 1988 Page 1 of 2 Duke Power Company Oconee Nuclear Station Second Ten Year Interval Request for Relief No. 88-09 I. Component for which relief is requested:
(a) Name and Number:
Spent Fuel Pool Cooling system welds for installing valve 1SF-89 (see attached flow diagram).
(b) Function:
Valve 1SF-89 is a check valve which prevents backflow through Spent Fuel Cooling Pump 1C.
(c) ISI Class/Duke Class:
ISI Class C/Duke Class C (d) IWV-2000 Valve Category: C II. Reference Code requirement that has been determined to be impractical:
ASME Boiler and Pressure Vessel Code Section XI, 1980 Edition (with Addenda through Winter 1980) paragraph IWA-4400(a), which states that after repairs by welding on the pressure retaining boundary, a system hydrostatic test shall be performed in accordance with IWA-5000.
III. Basis for requesting relief:
Valve 1SF-89 cannot be isolated from the discharge of the 1C Spent Fuel Pool Cooling Pump.
Hydrostatic testing of the pump could damage mechanical seals which are rated for 150 psig.
IV. Alternate examination:
Subject welds will be 100% radiographed and a VT-2 inspection will be performed at operating temperature and pressure.
V.
Evaluation of acceptability of proposed alternate testing with respect to the level of quality and safety as well as public health and safety:
The specified method of hydrostatic testing verifies that there are not leaks at 1.25 times the design pressure.
The alternate examination of a 100% radiograph of welds assures that no significant flaws are evident in the welds. The VT-2 inspection indicates that no leaks are detectable when the system is at operating temperature and pressure.
Document Control Desk December 9, 1988 Page 2 of 2 The alternate tests provide an equivalent method to indicate a leak at the higher stress level which is normally verified by the specified method of hydrostatic testing. As such, the proposed alternate examinations provide an acceptable level of quality and safety and will not endanger the health and safety of the public.
I. Implementation Schedule:
The 100% radiograph will be performed when welding is complete.
The VT-2 inspection will be performed during system startup.
OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS APERTURE CARD/HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH FTS 492-8989