ML20209B683
| ML20209B683 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/28/1987 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20209B687 | List: |
| References | |
| NLS-86-388, NUDOCS 8702040100 | |
| Download: ML20209B683 (3) | |
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Cp&L Carolina Power & Light Company JAN 2 81987 SERIAL: NLS-86-388 85TSB28 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT BWR CORE THERMAL HYDRAULIC STABILITY
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 Steam Electric Plant (BSEP), Unit Nos. I and 2.
The proposed changes incorporate requirements for the detection and suppression of core thermal hydraulic instabilities. These requirements are consistent with the recommendations provided by General Electric Company in Service Information Letter (SIL) 380, Revision 1.
DISCUSSION General Electric (GE) issued Service Information Letter (SIL) 380, Revision 1, on February 10,1984. The NRC endorsed GE's recommendations in the Safety Evaluation for Amendment 8 to GESTAR II, dated April 24,1985. The BWR Owners' Group (BWROG) prepared draf t thermal hydraulic stability TS based on GE's recommendations.
The BWROG draf t TS require that APRM and LPRM noise levels be determined at specified intervals when core flow is less than 45% and thermal power is greater than the specified limit. The pro _ posed BSEP TS include similar requirements as well as additional ACTION Statements (cX1) and (cX2) which give the operator the option of immediately taking the corrective action required to meet the limiting condition for operation instead of determining if noise levels are too high. The Company chose to add the two additional ACTION options to provide more immediate correction of potential instabilities.
ACTION Statement (cX3) requires that two noise limits, three times the established baseline and 5% peak-to-peak, be surpassed before the prescribed operator actions to withdraw from the region would be necessary. The inclusion of the second limit reduces the difficulties of solely administering the three times baseline limit with low flux noise levels.
8702040100 870128 PDR ADOCK 05000324 P
PDR 411 Fayetteville street e P o Box 1s51
- Aaleigh. N C 27602
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,U. S. Nuclear Regulatory Commission JAN 2 81987
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NLS-86-388 / page 2 In addition, the proposed BSEP TS require that APRM and LPRM noise levels be determined within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter under the specified conditions. The Owners' Group recommends that the APRM and LPRM noise levels be determined within 30 minutes and at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when core flow is less than a specified value. The Company has evaluated the proposed time limits and has determined that they meet the intent of SIL-380, and their deviation from the Owners' Group recommendation is not significant. Technical Specifications using alternate noise level determination time criteria have previously been reviewed by the NRC and were approved for several other utilities.
In the proposed change, when two Reactor Coolant System (RCS) recirculation loops are in operation and total core flow is less than 35 million pounds per hcur and thermal power is greater than the specified limit, three actions may be taken within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:(1) reduce thermal power to less than the specified limit, or (2) increase core flow to greater than 35 million pounds per hour, or (3) determine the APRM and LPRM neutron flux noise levels. If Action (3)is taken and noise levels are less than three times their established baseline levels or less than 5% peak-to-peak, noise levels will be determined at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and within one hour of a thermal power increase of at least 5% of rated power. If noise levels are greater than three times their established baseline levels and greater than 5% peak-to-peak, corrective actions will immediately be initiated and noise levels restored to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by increasing core flow or reducing thermal power.
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 sig(nificant 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. CP&L has reviewed this request and determined that:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. Core stability decay ratios have been demonstrated analytically to be acceptable (i.e., less than 1.0) which indicates that undamped flux oscillations should not occur. If flux oscillations should occur, however, the proposed TS revisions are adequate for promptly identifying such oscillations and suppressing them.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. The NRC staff has reviewed and issued a Safety Evaluation Report concerning thermal hydraulic stability licensing criteria based on General Electric Company's SIL 380, Revision 1, which provides acceptable recommendations for assuring compliance with GDC-10 and GDC-12. These recommendations have been reviewed and incorporated in the proposed Brunswick-1 and Brunswick-2 TS revisions.
3.
The proposed amendment does not involve a significant reduction in the margin of safety. The proposed revisions incorporate additional, more restrictive surveillance requirements and actions to ensure the prompt detection and control of neutron flux oscillations consistent with the recommendations of General Electric Company's SIL 380, Revision 1.
.U. S. Nuclear Regulatory Commission NLS-86-388 / pag 3 JAN 2 81987 Based on the above reasoning, CP&L has determined that the proposed changes involve no significant hazards consideration.
ADMINISTRATIVE INFORMATION The revised Brunswick Technical Specification pages are provided in Enclosures 1 and 2.
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 in payment of this fee.
Please refer any questions regarding this submittal to Mr. Sherwood R. Zimmerman at (919) 836-6242.
You very tr 1, J
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A. B. Cutter - Vice President Nuclear Engineering & Licensing ABC/ BAT /bmc (5026 BAT)
- cc:
Mr. W. H. Ruland (NRC-BNP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. E. Sylvester (NRC)
Mr. Dayne H. Brown
- All with Enclosures 1 and 2 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 officers, employees, contractors, and agents of Carolina Power & Light Company.
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