ML20071G841
| ML20071G841 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/17/1983 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TAC-51577, NUDOCS 8305240404 | |
| Download: ML20071G841 (7) | |
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Telennone (412) 45s4090 Nuclear Division P.O. Box 4 May 17, 1983 Shippingport. PA 15077-0004 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission A t tn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Powcr Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 RHR Heat Exchanger Nozzle Relief Requast Gentlemen:
Enclosed are:
1.
Three (3) originals and thirty-sevan (37) copies of an Application requesting relief from the Inservice Inspection requirements (of Item C1.2, Examination Category C-B) for the volumetric examination of the Residual Heat Removal (RHR) Heat Exchanger Nozzle to Vessel Welds.
2.
Forty (40) copies of Attachment A which sets forth a discussion of the relief request, a basis for relief from Code requirements and suggested examination require-ments for the RHR nozzles.
The RHR heat exchaagers are to be disassembled this outage (third refueling). The Technical Specification Amendment No. 22 Safety Evalua-tion requires that in the event the heat exchangers are disassembled, the Code required examination shall be performcJ.
In lieu of the volumetric examination, we are proposing alternate examination requirements to be perf ormed once per forty months:
1.
Visually examine the nozzle reinforcement ring area (including the telltale '. ole) f or evidence of leakage and degradation, and 2.
Perform a surface examination of the reinforcement ring weld surface.
OO 3305240404 830517 PDR ADOCK 050GJL34 G
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O Beaver Valley Power Station, Unit No. 1 Docket No. 50-324, License No. DPR-66 REP Heat Exchanger Nozzle Relief Request Page 2 This proposed change to our Inservice Inspection program will not remove or relax any existing requirement related to the probability or consequences of accidents previously considered and does not involve a significant hazards consideration.
The third refueling outage is expected to begin in June 1983, in order that we may modify our refueling schedule to reflect these changes, we would appreciate your response to this request by June 11, 1983.
It is cur understanding that similar requests have been granted for the subject heat exchanges at Conn. Yankee and Farley, Unit No. 1.
We have determined this to be a Class III request and a check for
$4,000.00 will be submitted under separate cover in accordance with 10 CFP 170.22.
Very uly yours, J. Carey Vice President, Nuclear cc:
Mr. Thomas M. Gerusky, Cirector Bureau of Radiation Protection Pennsylvania Department of Environmentat Resources P. O. Box 2063 Ha rrisburg, Pennsyvlania 17120 Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 Mr. ' Peter Tam, Project Manager U. S. Nuclear Regulatory Commission Phillipe Building Washington, DC 20555
- Mail Stop 438 -
U. S. Nuclear Regulatory Commission c/o Document Managment Branch Washington, DC 20555
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Duquesne Light Company
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Docket No. 50-334 (Beaver Valley Power Station, Unit No.1)
)
APPLICATION FOR RELIEF OF INSERVICE INSPECTION REQUIREMENTS Pursuant to Section 50.90 of the regulations of the U. S. Nuclear Regulatory Commission (the " Commission"), Duquesne Light Company ("DLC"),
holder of Provisional Operating License No. DPR-66, hereby requests relief from the Inservice Inspection requirements (of item C1.2, Exam-ination Category C-B) for the volumetric examination of the RHR Heat Exchanger Nozzle to Vessel Welds.
The proposed relief request is set forth in Attachment A to this Application. The proposed change does not involve a significant change in the types or a significant increase in the amounts of ef fluents or any change in the authorized power level of the facility. The change involves a single safety issue, relief from the Inservice Inspection requirements (of Item C1.2, Examination Cateogry C-B) for the volumetric examination of the RHR Heat Exchanger Nozzle to Vessel Welds and is in accordance with 10 CFR 170.22.
WHEREFORE, Applicant respectfully requests that the Inservice Inspec-tion requirements to Provisional Operating License No. DPR-66 be amended in the form attached hereto as Attachment A.
Duquesne Lig t Company By J."(jJ Carey /
Vice President, Nuclear Subscribed and sworn to before me on this /f day of N
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ATTACHMENT A RHR Nozzle Relief Request Request relief from volumetric examination of nozzle to vessel welds on the residual heat exchangers.
(Item C1.2, Examination Category C-B)
Code Requirement Volumetric examination of 100% of the nozzle to vessel attachment weld over the service lifetime of the component.
Basis for Requesting Relief The residual heat removal heat exchanger nozzle to vessel weld is covered by a reinforcement ring and is not accessible for examination as required by IWC-2600.
Amendment #22 Relief Inspection Requirements The nozzle and reinforcement ring areas are to be visually inspected during the inspection period.
In the event the residual heat removal heat exhanger is disassemblied for maintenance and the welds are accessible for examination from the inside surface, the Code required examination shall be performed.
Relief request from the volumetric examination required by Amendment #22 from the inside surface upon disassembly.
Basis for Requesting Rolief The amount of associated effort and supporting work for an inside surface ultrasonic examination of the nozzle to vessel weld is not justified for the following reasons:
a.
An anticipated high radiation work environment.
b.
The weld geometry will likely yield only a partial examination (see Attachments),
The examination surf ace area has not been prepared for ultra-c.
sonic examination.
d.
Surface preparation via grinding and/or polishing would signi-t ficantly increase the man-rem exposure and create a severe problem in maintaining the system cleanliness raquirements, e.
The material to be examined is austenitic stainless steel.
Austenitic materials display anisotropic properties and are in-homogeneous in nature leading to the anomalous behavior of the sound beam as it passes through the material.
Viable ultrasonic examination procedures of this material have not been developed to the satisfaction of the ASME Code Committees.
7
RHR Nozzle Relief Request (Continued - Page 2) f.
The NDE Examiner would have to perform the examination under a suspended load (the heat exchanger shell and tube bundle) or under a cribbed load. Working under a suspended load presents serious safety concerns to personnel and equipment.
Suggested Examination Requirements for RHR Nozzles Visually examine the nozzle reinforcement ring area (including the telltale hole) for evider.:e of leakage and degradation once each Code period (40 months).
In addition, perform a surface examination of the reinforcement ring weld surfaces once during each Code period (40 months).
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