ML20212A348
| ML20212A348 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/16/1986 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Muller D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20212A352 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.1, TASK-TM NLS-86-440, NUDOCS 8612220381 | |
| Download: ML20212A348 (4) | |
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CASA Carolina Power & Light Company DEC 161986 SERIAL: NLS-86-440 86TSB21 Director of Nuclear Reactor Regulation Attention:
Mr. Dan Muller BWR Project Directorate #2 Division of BWR Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325/ LICENSE NO. DPR-71 REQUEST FOR LICENSE AMENDMENT PRIMARY CONTAINMENT ISOLATION VALVES
Dear Sir:
SUMMARY
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Stean Electric Plant, Unit 1. The proposed revision reflects modifications being made to the containment atmospheric dilution (CAD) system during the upcoming Brunswick-1 Reload 5 outage.
DISCUSSION The Brunswick-1 CAD system was modified to meet the requirements of NUREG-0737, Item II.E.4.1. during the Reload 4 outage. As installed, the primary means of containment purging is through purge exhaust isolation valve 1-CAC-V172, which discharges from the drywell through a 2-inch bypass line to the standby gas treatment system. The proposed change modifies the CAD system so that containment purging takes place through the suppression chamber rather than the drywell. Figure 1 provides a schematic of the proposed modification. This design is consistent with that approved for Brunswick-2 on May 5,1986 when Amendment 125 to the Brunswick-2 TS was issued.
The proposed modification allows for venting from the suppression chamber through purge exhaust isolation valve 1-CAC-V172 via a 2-inch bypass line to the standby gas treatment system. Valve 1-CAC-V172 will provide a bypass of the 20-inch, pneumatically operated, suppression chamber exhaust valve 1-CAC-V7. This is the preferred vent path under post-accident conditions because the suppression chamber water is utilized as a scrubbing agent for potential gaseous radioactivity. The modification does not affect the redundancy or single failure design of the system. Valve 1-CAC-V172 will retain its containment isolation signal override capability and this capability will be extended to include the drywell purge exhaust valve 1-CAC-V9. As such, the capability of post-accident venting directly from the drywell will be retained and there remains three paths by which venting can be performed. Only one of these paths is necessary during post-accident operation. The modified piping and components will be safety grade and the electrical equipment will conform to Class IE requirements.
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. The proposed modification has been reflected in TS Table 3.6.3-1 by revising the designation of valve 1-CAC-V172 from drywell purge exhaust isolation valve to suppression chamber purge exhaust isolation valve.
SIGNIFICANT HAZARDS ANALYSIS The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. Carolina Power & Light Company has reviewed this request and deterrained that:
1.
The proposed amendment does not involye a significant increase in the probability or consequences of an accident previously evaluated. The CAD system provides for post-accident control of combustible gases. Since this system provides ari accident mitigation function, its modification can not involve an increase in the probability of an accident previously evaluated. The proposed modification allows for controlled venting of the containment through the suppression chamber under post-accident l
conditions. This is the preferred venting pathway because the suppression chamber water will act as a scrubbing agent for potential gaseous radioactivity, thereby, reducing the consequences of an accident involving a radioactive release to the l
primary containment. The modification does not affect the redundancy or the single l
failure design of the CAD system. The modified piping and components will be j
safety grade and the electrical equipment will conform to Class IE requirements.
l The modified CAD system meets the requirements of NUREG-0737, Item II.E.4.1, l
and its design is consistent with that approved for Brunswick-2 on May 5,1986, when Amendment 125 to the Brunswick-2 TS was issued.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The CAD system provides post-accident combustible gas control through purging of the containment.
Post-accident venting of the containment can still be accomplished via three pathways, only one of which is necessary during post-accident operation. The modification merely makes the primary pathway through the suppression chamber rather than from the drywell. This is the preferred venting pathway because the suppression chamber water will act as a scrubber for potential gaseous radioactivity. This design has been reviewed and approved by the NRC for Brunswick-2 on May 5,1986, when Amendment 125 to the Brunswick-2 TS was issued.
3.
The proposed amendment does not involve a significant reduction in a margin of safety. Post-accident venting of the containment through the suppression chamber water provides scrubbing of potential radioactive gases, thereby, reducing the activity of potential releases. The modification does not affect the redundancy or the single failure design of the CAD system. The modified piping and components will be safety grade and the electrical equipment will conform to Class IE requirements. As such, the proposed amendment will increase the margin of safety.
Based on the above reasoning, Carolina Power & Light Company has determined that the proposed amendment does not involve a significant hazards consideration.
Director cf Nucl=r Rector Rtgulation NLS-86-440 / page 3 DEC 161986 ADMINISTRATIVE INFORMATION The revised Brunswick-1 TS page is provided in Enclosure 1. The Company has evaluated this request in accordance with the provisions of 10 CFR 170.12 and determined that a license amendment application fee is required. A check for $150 is enclosed for payment of this fee. Issuance of this amendment is required by April 22,1987, to support startup of Brunswick-1 from its Reload 5 outage.
Please refer any questions regarding this submittal to Mr. Sherwood R. Zimmerman at (919) 836-6242.
Yours very uly, 4 Ik A. B. Cutter - Vice President Nuclear Engineering & Licensing MAT /bmc (5074 MAT)
Attachment cc:
Mr. Dayne H. Brown Mr. W. H. Ruland (NRC-BNP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. E. Sylvester (NRC)
A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are of ficers, employees, contractors, and agents of Carolina Power & Light Company.
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