ML20086H840
| ML20086H840 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/10/1991 |
| From: | Zach J WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-139 VPNPD-91-422, NUDOCS 9112100004 | |
| Download: ML20086H840 (5) | |
Text
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,4 Wisconsin
! Electnc POWER COMPANY m w u,cno:n to b 20e vwuw w L3m IM ?N23e VPNPD-91-422 NRC-02 139 U.
S.
HUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station P1-137 Washington, D.
C.
20555 Gentlemen:
DOCKET 50-266
,U{-SEBy_LQUll.SJECTION PROGRAtt POINT BEACH NUCLEAR PLANT, UNIT 1 By letter dated December 20, 1990, Wisconsin Electric Power Company submitted our program For the third 10-year interval for in-service inspection at Point Beach Nuclear Plant, Unit 1.
Included with this submittal was a request foi relief from the code-required surface examination of the reactor vessel safety injaction safe-end to nozzle welds RC-04-SI-1001-33 and RC-04-SI-1002-19.
This was given our identifier RR-1-02.
Subsequent to our submittal, additional information was requested by your lettcr dated July 12, 1991, and further discussed in telephone conversations on September 24, Snptember 26, and October 4,-1991, between members of your staff and Wisconsin Electric personnel.
It is our anderstanding that the alternate examination proposed in our request for relief would be acceptable provided the following conditions are met:
1.
The volumetric examination includes the entire weld volume and heat-affected zone.
2.
The ultrasonic test instrumentation and procedures are demonstrated to be capable of detecting O.
D.
surface-connected, circumferentially oriented defects.
The defects are to be cracks and not machine notches.
Wisconsin Electric Power Company has evaluated these two conditions.
Our proposed ultrasonic examination of the SI safe-
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4 NRC Document Control Desk December 4, 1991 Page 2 j
end to nozzle welde from the I. D.
surface will include the entire wold volume and heat-affected zone.
The examination will not be limited to the inner one-third vclume as specified in the 1986 edition of ASME Section XI.
Wisconsin Electric Power Company will perform a demonstration of the ultrasonic instrumentation and procedures capability to detect-0.
D.
surface-connected defeccs.
Blocks with cracks are presently not available in materials and dimensions similar to our SI safe-end to nozzle welds.
Appropriate blocks will be fabricated, and O.
D.
surface cracks included for use in the demonstration.
The demonstration will be completed prior to the next 10-year reactor vessel examination.
Records of the demonstration will he available to the NRC for review.
i We understand that the relief from the code-required surface examination.will be granted based upon the statements above.
A copy of the revised relief request is attached for your review.
If further information is required to consider this issue closed, please let me know.
Very truly yours, j
W$
7 b
James J.
Zach Vice President Nuclear Power Enclosure-r l
Copies to Boyd Brown, Idaho National Laboratories NRC Regional Administrator, Region III NRC Resident Inspector
JR 1-02 COMPQN M Reactor Pressure Vessel Safety inject!on Safe-End to Nozzle Wolds (2 nozzles).
. EXAM AREA 1.
RC-04-St 100133 Safety injection Safe End te Nozzle at 288.5 Deg.
2.
RC-04-SI 1001 19 - Safety injection Safe-Erd to Nozzh: at 108.5 Deg.
ISOMETRIC OR COMPONENT DRAWING Figure 1 ISI-PRI 1127 Figure 2 ISI-PRI 1129 ASME SECTiON XI CATEGORY BF ASME SECTION XI ITEM NUMBER B5.10 ASME SECTION XI EXAMINATION REQUIREMENT A surface and volumetric examination of each Safe-End to Nozzle weld every 10 years.
ALTERNATIVE EXAMINATION No surface exam will be performed. A volumetric examination of each Safe-End to Nozzle weld will be
- performed every 10 years. The volumetric examination will be performed from the ID of the nozzle using mechanized equipment, including the entire weld volume and heat affected zone.. The examination wa not be limited to the inner one-third volume as specified in the 198e edition of ASME Section XI. The ultrasonic test instrumentation and procedures will be demonstrated to be capable of detecting O D.
surface connected circumferentially oriented defects. Appropriate blocks will be fabricated and O. D.
surface cracks induced for use in the demonstration. The demonstration will be completed prior to the next 10-year reactor vessel examination. Records of the demonstration will be available to the NRC for review.
REASON FOR LIMITATION A surface examination is not possible due to the inaccessibility of this area. These welds are located between the vessel and biological shield wah.
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