W3P89-0057, Responds to NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. Listed Actions Items to Be Completed,Based on 890213 Meeting Between Util & NRC
| ML20235T399 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/03/1989 |
| From: | Burski R LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-88-011, IEB-88-11, W3P89-0057, W3P89-57, NUDOCS 8903080265 | |
| Download: ML20235T399 (2) | |
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LOUISIANA P O W E R & L I G H T -] 317 BARONNE STREET P. O. BOX 60340 NEW ORLEANS, LOUISlANA 70160 (504) 595-3100
$T skNNsb March 3,'1989 W3P89-0057 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Contrst 9esk Washington, D.C. 205'.J
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Response to NRC Bulletin No. 88-11,
" Pressurizer Surge Line Thermal Stratification"
Dear Sir:
As requested by the subject NRC Bulletin, this letter informs the staff of actions taken to resolve NRC concerns associated with the issue of Pressurizer Surge Line Thermal Stratification. The Combustion Engineering Owners Group (CEOG) became aware of this issue in April 1987, when INFO issued a draft SER on surge line thermal cycling observed in a German nuclear plant. The CEOG proceeded to initiate a data collection program in June 1987, followed by actual data collection activities in two CEOG plants in June and August of 1988.
In October 1988, the CEOG authorized the ongoing CEOG program, " Reduction and Analysis of Pressurizer Surge Line Data Collected from CEOG Plants", to address surge line thermal stratification concerns. NRC Bulletin 88-11 was subsequently issued in December 1988. Action No. 1.b requested that within four months of receipt of the Bulletin, licensees of plants in operation demonstrate that the pressurizer surge line meets the applicable design codes and other regulatory commitments for the licensed life of the plant.
The staff suggested that this could be accomplished by performing a plant specific or generic bounding analysis. Licensees of plants in operation less than ten years were requested to complete the analysis within one year. These NRC Bulletin items prompted the CEOG to request a meeting with the NRC Staff.
The NRC Staff and the CEOG met on February 13, 1989, in the White Flint NRC offices. During this meeting, the CEOG presented the goals and scope of i
the ongoing CEOG surge line program which included a presentation of actual f
plant data and a discussion on the issue of thermal striping. The CEOG then requested relief from the one year schedule required by Action 1.b'and suggested that the CEOG program be allowed to proceed on schedule.
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As a result of this meeting, the CEOG and NRC Staff agreed on several action items to be completed as follows:
1.
The CEOG will perform a preliminary bounding analysis of CEOG surge lines using actual data collected from CEOG plants by July 1, 1989.
This activity will address the intent of Requested Action 1.b.
2.
Actual plant data will be used to define loading conditions for input to the fatigue and stress analyses.
3.
The CEOG agreed to meet with NRC Staff to discuss the load definitions before finalizing the bounding analysis described in item 1 above.
Bulletin 88-11 Action 1.a requires a visual surga line inspection upon a Cold Shutdown greater than seven-days. The inspection requires scaffolding assembly and disassembly, as well as removing and re-installing long runs of insulation.
Because forced outages have indeterminate length (e.g.,
uncovered problems may lengthen a two day outage to four), anticipating a seven-day outage is difficult. Waterford, instead, commits to complete Action 1.a during this Fall's Refueling Outage.
In conclusion, Waterford SES 3 is a participant in the CEOG program and agrees to support the action items and alternative schedule for responding to NRC Bulletin 88-11 Action 1.b.
The Bulletin's Reporting Requirement 2 asks for a letter within 60-days of receiving Bulletin 88-11, if Action 1.a through 1.d (for licensees operating PWRs) cannot be completed on the schedule spelled-out by the NRC.
On issuance of this letter, we consider Reporting Requirement 2 in the Bulletin appropriately addressed.
Very truly yours.
.h R.F. Burski Manager Nuclear Safety & Regulatory Affairs RFB:SEF:ssf cc:
R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR D.L. Wigginton, NRC-NRR NRC Resident Inspectors Office E.L. Blake W.M. Stevenson
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