ML20215G949
| ML20215G949 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/18/1987 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLS-87-128, NUDOCS 8706230453 | |
| Download: ML20215G949 (22) | |
Text
i CD&L Carolina Power & Light Company JUN 181987 SERIAL: NLS-87-128 10CFR50.62 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk j
Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 ATWS - ADDITIONAL INFORMATION Gentlemen:
A conference call was held on June 4,1987 concerning the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2, Recirculation Pump Trip (RPT) and Alternate Rod injection (ARI) systems. Information requested concerning (1) testing of the ARI and RPT;(2) missing figures from the April 14,1987 submittal; and (3) RPT setpoints is enclosed.
Carolina Power & Light Company would like to emphasize the need for timely review of this issue. Currently, ATWS RPT and ARI modifications on BSEP, Unit No. 2 are expected to be completed during the Reload 7 outage, scheduled to begin January 2, 1988. Should a significant delay in approval of this request occur or the proposed design prove to be unacceptable, sufficient time will not remain to complete the necessary engineering and procurement required to support the modifications prior to the upcoming refueling outage. If a Safety Evaluation Report approving the proposed design is not issued by August 1,1987, the Company may be required to submit a request for deferral of these ATWS modifications.
Please refer questions regarding this submittal to Mr. S. D. Floyd at (919) 836-6901.
j Yours very truly, haus" S.,
. Zi erman L-4 nager Nuclear Licensing Section BAT /lah (5221 BAT)
Enclosures cc:
Dr. 3. Nelson Grace (NRC-RII)
Mr. W. H. Ruland (NRC-BNP)
Mr. E. Sylvester (NRC) g
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411 Fayetteville Street
- P O Box 1s51
- Raleigh N C 27602 M C " " "" N #2E M EIi N " "
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t Enclosed is a logic diagram of the ARI/RPT systems along with associated reference drawings. The analog master trip units of the pressure transmitters are shown on Figures 1 and 2 and are represented by the "AND" gates at the top of the logic diagram.
The master trip unit output relays are shown schematically on Figures 3 and 4, along with the "K" relays. These are represented by the "0R" gates on the logic diagram. The test switches (S14A and B), switch contacts, associated test circuit indicating lights, and alarms are shown on Figures 5 through 9. Figure 8 shows the alarm to indicate test status from the test switch contacts for ARI which are shown on Figure 10. Figures 10 through 12 show the ARI schematic, and Figure 13 shows the alarm circuit that indicates ARI initiation.
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ATTACHMENT 2 Figures Missing From 1
April 14,1987 Submittal i
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ATTACHMENT 3 f
Information Concerning RPT Setpoints
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The existing reactor vessel water level - low level 2 and reactor vessel pressure - high setpoints were used for indicating ATWS RPT and ARI. These setpoints are, respectively,113 inches, level decreasing, and 1100 psi increasing. The existing BSEP Technical Specification page 3/4 3-80 lists trip setpoints of > + )12 inches for low level 2 and $ 1120 psig for vessel pressure - high. These setpoints have not changed since the original custom Technical Specifications were issued on September 8,1976 with the exception of redefinition of the water level setpoint so it would be based on reference level zero. Thus, the design bases has not changed since the plant was licensed. As stated in the Technical Specification bases, Section 3/4.3.6, the response of the plant to an ATWS event falls within the envelope of study results given in General Electric Company's Topical Report NEDO-10349, dated March 1971.
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