ML20039B670
| ML20039B670 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/17/1981 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NO-81-2066, NUDOCS 8112230369 | |
| Download: ML20039B670 (2) | |
Text
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s Cp&L Carolina Power & Light Company December 17, 1981 File: NG-3514(B)
Serial No.: NO-81-2066 Office of Nuclear Reactor Regulation ATTN:
Mr. T. A. Ippolito, Chief Operating Reactors Branch No. 2
,<IN / q 7W United States Nuclear Regulatory Commission
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Washington, D.C.
20555
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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 h/
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e DOCKET NOS. 50-325 AND 50-324 OOIM T Dgg g*
i LICENSE NOS. DPR-71 AND DPR-62 1
BWR FEEDWATER AND CRD RETURN LINE N0ZZLE CRACKING
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Dear Mr. Ippolito:
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SUMMARY
l Carolina Power & Light Company (CP&L) has received your November 2, 1981 letter which requested additional information for the Brunswick Steam i
I Electric Plant Unit Nos. 1 and 2 regarding the feedwater and CRD return line nozzle cracking issue. Your letter was in response to CP&L's October 7,1981 letter. Our responses are provided below:
DISCUSSION In your November 2 letter, you requested clarification of Item 3,
" Modifications to the Control Rod Drive (CRD) System." CP&L intends to cut and cap the 3" CRD return line without rerouting.
Since it is our intent to replace the carbon steel pipe in the flow stabilizer loop with stainless steel and reroute directly to the tooling water header, flush ports at high and low points of the normal drive movement exhaust water header will not be installed.
Furthermore, the request in our October 7,1981 letter to perform a liquid penetrant (L.P.) test on only the accessible blend radius surfaces of the Unit No. 2 feedwater nozzles was intended for the next refueling (1982) f only. This request is based on the facts that the current Brunswick Unit No. 2 feedwater thermal sleeves are extremely tight fitting as evidenced by I
attempted removal in 1979, and that no cracks were discovered by liquid penetrant examination.
Removal of the spargers will result in increased lh cicarances, allowing more bypass leakage.
Based on this operating history, ALARA considerations, and the fact that the spargers will be replaced in 1983, CP&L believes that the request to perform an L.P. of the accessible areas only on a one-time basis is a valid one and warrants your careful consideration.
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8112230369 811217 PDR ADOCK 05000324 411 Fayetteville Street
- P. O. Box 1551
- Raleigh, N. C 27502 P
PDR m-~m w m = ----- -
Mr. T. A. Ippolito December 17, 1981 We agree at this time with your assessment that there is not enough field experience with the new spargers/ thermal sleeves to allow any w;$ er of the inspection intervals or techniques given in NUREG-0619. As stated in our letter of October 7, 1981, Carolina Power & Light Company intends to perform the Unit No. 2 feedwater clad removal /sparger replacement modification during the 1983 refueling outage. Adherence to the NUREG-0619 Tabic 2 Inspection Requirements (i.e., every nine refueling cycles or 135 start-up/ shutdown cycles) will begin at that time.
Should you have any questions concerning the above information, please contact my staff.
Yours very truly,
?
L. W. Eury Senior Vice President Power Supply PG/JM/ir (6789)