ML20207K162
| ML20207K162 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/07/1987 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| 10CFR50.62, NLS-86-475, NUDOCS 8701090333 | |
| Download: ML20207K162 (1) | |
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CD&L Carolina Power & Light Company 37 g SERIAL: NLS-86-475 10 CFR 50.62 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NOS. 50-325/ LICENSE NO. DPR-71 ATWS RULE (10 CFR 50.62) IMPLEMENTATION SCHEDULE
Dear Sir:
Carolina Power & Light Company (CP&L) plans to comply with the requirements of 10 CFR 50.62, the ATWS Rule for Brunswick Unit No. I during the Reload 6 outage, currently scheduled to begin December 24,1988. The rule requires justification if im lementation is to be completed later than the second refueling outage af ter Ju 1984. Brunswick-1 ts currently scheduled to begin its second refueling outage (R
- 5) on February 13,1987 The following discussion provides justification for our implementation schecule.
On October 21,1986, the Staff issued a Safety Evaluation of Topical Report NEDE-31096-P, " Anticipated Transient Without Scram: Response To ATWS Rule, 10 CFR 50.62," which was submitted in December of 1985. In the evaluation of the Recirculation Pump Trip (RPT) System the Staff concluded that the two acceptable RPT designs are the Modified Hatch design o,r the Monticello design. A third option, which was endorsed by the BWROG in Topical Report NEDE-31096-P, was the Original BWR/4 design or a combination of the three designs. The proposed RPT design for Brunswick is similar to the Monticello design, but has only one trip coil per recirculation pump.
The Company learned of the StafI's position regarding RPT design on December 8,1986.
A conference call was held on December 11,1 86, to present the proposed design for Brunswick. In that call, the NRC indicated reluctance to accept any design other than the ones endorsed in the October 21,1986 Safety Evaluation. Due to this reluctance and the imminent start of the Brunswick-1 Reload 5 outage, the Company determined that the most prudent course of action would be to postpone the scheduled ATWS-RPT modification until the Reload 6 outage. The Alternate Rod Injection s modifications are a subset of the ATWS-RPT modifications; therefore,ystem this work will also be performed during the Brunswick-1 Reload 6 outage. The Standby Liquid Control Modification will be performed during the upcoming Reload 5 outage as originally planned.
(919) 836-6242.y questions regarding this matter to Mr. Sherwood R. Zimmerman at Please refer an 8701090333 870107 DR ADOCK 0500 5
A. B. Cutter - Vice Ibsident ABC/ BAT /bmc (5098 BAT)
Nuclear Engineering & Licensing cc:
Mr. W. H. Rutand (NRC-BNP)
Dr. 3. Nelson Grace (NRC-Ril)
Mr. E. Sylvester (NRC) 411 FayeMevme Sueet P. o Box 15$1
- Raleigh. N C, 27602 gl 1
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