ML15238B268
| ML15238B268 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/16/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8102040551 | |
| Download: ML15238B268 (5) | |
Text
JANUARY 6
DISTRIBUTION:
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- uisenhut, RReid MWairtile g6O Dockets Nos Od-269, 50-270 Rlngram and 50-287 OELD RPurple AEOD JRoe IE-36 ACRS-16 Mr 1
Wlliam 0. Parker, Jr.
Gray File Vice President - Steam Production Duke Power Company
,_HOrnsteln n P1 0. Box 2178 k
EBlackwoo 422 South Church Street Charlotte, North Carolina 2 8242
Dear Mr. Parker:
By letter dated January 13, 1981, Duk Power compay re uested relief from the Inservice Inspection (I) requirements of SM Boiler and Press ue Vessel Code Section XI, for 24-inc'diameter main feedwater system replacement check valve welds, a Code Class qoMponeny.Our Regulati ons in 10 CFR 50,5 a (g)(4) require that ISI be perkrmed in accordance with ecion XI of theCode to ithe extent practicable with n the liittn othean d e materials of construction of e c9Mponent.
In our license amendment of November 7, 1980, we revised jthe Oconee Nuclear Station Technical Specifica tions (TS) relating to the IST rogramn accord with 0 CFR 50.55ag and provided in-TS 4.2.1 that specic written relief may be -granted by the Com mission from Code requirements as provided In 10 CFR 50.55a( g(4).
ASME Section XI, 1980 Edition, Article IWC-50System Pressure Tests, is the specific Code requlrement from which relief is Atg-'sought.
This Artcle requires a leak test at a pressure of 1.25 times system des gnpessure
- for, replaced components in Code Class 2 systems.
Duke proposes insead to eak test the welds on the new check valves at operating pressure and to augment the program by performing both 1d% volumetric examination by radiography of each weld and a surface examination of each weld.
The licensee's basis for requesting relief is that there is no practicable means of isolating these 24-inch diameter check walves for hydrotest pressures greater than operating pressure.
The icensee discussed two means of isolating these valves, the first approach could result in overstress or distortion of the main steam system; the second approach woul d result inhi ra diat o exposures to personnel.
Evaluation By examination of the piping diagrams in the Duke anua 13, 1981 submittal it is clear that it is not ract cab the 24-inch diameter chec valves for a 1.25 times designpressure bydotest.
The licensee has prosed a pressure test at system pressure and e
by'both a volumetric weld examination and a wdi surface examination.
Theproposed 810 2040;<-c \\
Mr. illiam 0. Parker, Jri2 alternative testing and augmented weld examination are coparable to the ASME!Section XI IWC-5000 program.
We conclude that the alternative program will ensure leak tightness and weld integrity fo the replae nt check val ves and is thus acceptable; consequently this relief equestmay I
granted.
Sincerely, Original signed b Robert Wd. Reid Robert W. Reid, Chief Operating Reactors Branch #4
-.Division of Licensing cc:
See next page OFFICE) ORB#4:DL9 c
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NRC FORM 318(10/80) NRCM 0240 OFFICIAL RECORD COPY YSGPO 1980-329-824
UNITED STATES A
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 January 16, 1981 Dockets Nos. 50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.
Vice President -
Steam Production Duke Power Company P.;O. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
By letter dated January 13, 1981, Duke Power Company requested relief from the Inservice Inspection (ISI) requirements of the ASME Boiler and Pressure Vessel Code,Section XI, for 24-inch diameter main feedwater system replacement check valve welds, a Code Class 2 component. Our Regulations in 10 CFR 50.55a (g)(4) require that ISI be performed in accordance with Section XI of the Code to the extent practicable within the limitations of design, geometry and materials of construction of the component. In our license amendment of November 7, 1980, we revised the Oconee Nuclear Station Technical Specifica tions (TS) relating to the ISI Program in accord with 10 CFR 50.55a(g) and provided in TS 4.2.1 that specific written relief may be granted by the Com mission from Code requirements as provided in 10 CFR 50.55a(g)(4).
ASME Section XI, 1980 Edition, Article IWC 5000, System Pressure Tests, is the specific Code requirement from which relief is being sought. This Article requires a leak test at a pressure of 1.25 times system design pressure for replaced components in Code Class 2 systems. Duke proposes instead to leak test the welds on the new check valves at operating pressure and to augment the program by performing both 100% volumetric examination by radiography of each weld and a surface examination of each weld.
The licensee's basis for requesting relief is that there is no practicable means of isolating these 24-inch diameter check valves for hydrotest pressures greater than operating pressure. The licensee discussed two means of isolating these valves, the first approach could result in overstress or distortion of the main steam system; the second approach would result in high radiation exposures to personnel.
Evaluation By examination of the piping diagrams in the Duke January 13, 1981 submittal, it is clear that it is not practicable to isolate the 24-inch diameter check valves for a 1.25 times design pressure hydrotest. The licensee has proposed a pressure test at system pressure and temperature, augmented by both a 100%
volumetric weld examination and a weld surface examination.
The proposed
Mr. William 0. Parker, Jr.
-2 alternative testing and augmented weld examination are comparable to the ASME Section XI IWC-5000 program. We conclude that the alternative program will ensure leak tightness and weld integrity for the replacement check valves and is thus acceptable; consequently, this relief request may be granted.
Sincerely, Ro ert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing cc:
See next page
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P 0. Box 2178 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Wilhalla, South Carolina 29621 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C. 20460 U. S. Environmental Protection Agency R gion IV Office ATTN: EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nu6clear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS NUS Corporation 2536 Countryside Boulevard, Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 1200 17th Street, N.W.
.Washington, D. C. 20036