ML20238C893
| ML20238C893 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/04/1987 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20238C895 | List: |
| References | |
| NLS-87-184, TS87B10, NUDOCS 8709100435 | |
| Download: ML20238C893 (5) | |
Text
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CD&L Carolina Power & Light Company SEP 4 B87 SERIAL: NLS-87-184 10CFR50.92 87TSB10 i
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 2055$
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NOS. 50-324/ LICENSE NO. DPR-62 REQUEST FOR LICENSE AMENDMENT j
FUEL CYCLE NO. 8 -- RELOAD LICENSING Gentlemen:
SUMMARY
in accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit 2. The purpose of this amendment is to incorporate operating lirpits for Cycle 8 (Reload 7) operation of the Brunswick Steam Electric Plant, Unit 2. A. dditional information concerning the schedule for review and issuance of this request is provioed in the Administrative Information section of this letter.
l DISCUSSION The purpose of this request is to revise the Technical Specifications to (1) incorporate the operating limits [ Average Power Range Monitor (APRM) setpoints, Minimum Critical Power Ratio (MCPR) values, Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) values, and Linear Heat Generation Rate (LHGR) requirements] for all fuel types for Cycle 8 operation of the Brunswick Steam Electric Plant, Unit 2 and (2) modify the Bases associated with the new reload fuel. The values of mu (p) and sigma (c) found in Specification 3.2.3.2 have been revised to conform with the advanced GEMINI /ODYN analysis methods. Revisions are also provided to the existing definitions for Critical Power Ratio and Physics Tests.
The MCPR values reflected in the proposed Technical Specifications include a conservative adder of 0.02 to the MCPR values provided in the Supplemental Reload Licensing Report. On occasion, operational conditions such as a main steam line isolation valve out-of-service or a feedwater heater out-of-service event have visen.
During past occurrences of these events, analyses of the impact on MCPR to support extended periods of operation with such conditions have been conservatively bounded by an adder value of 0.02. Thus, this adder has been included to preclude the need to request emergency / exigent Technical Specification relief that might otherwise be needed in the event of a similar operational condition.
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Document Control Desk NLS-87-184 / Page 2 The reload will use General Electric (GE) manufactured fuel assemblies that were analyzed by GE using methodologies approved by the NRC. Enclosed is a copy of the General Electric report entitled " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2, Reload 7, Cycle 8." This report summarizes the results of the GE reload analyses for the existing and new bundle types.
The reload for Cycle 8 is a normal reload with no unusual core features or characteristics. The Technical Specification changes primarily relate to the inclusion of new and/or revised MCPR limits, APRM setpoints, MAPLHGR limits, and LHGR limits for all fuel types using Cycle 8 core and transient parameters.
The new reload fuel for Cycle 8 is the GE extended burnup barrier fuel GE8x8EB. This fuel type has been approved by the NRC in the Safety Evaluation Report for Amendment 10 to GESTAR II(NEDE-240ll-P-A).
The values for mu (p) and sigma (a) found in Specification 3.2.3.2 reflect the GESTAR II (NEDE-240ll-P-A) requirement to conform with the advanced GEMINI /ODYN analysis methods for the Option B scram time insertion. Use of the GEMINI method has been previously reviewed and approved by the NRC for evaluation of operating limit MCPR values in the Safety Evaluation Report for Amendment 11 to GESTAR 11 (NEDE-240ll-P-A). The revised mu and sigma values are appropriate for 20% scram insertion time requirements (defined as the time from de-energization of the scram pilot valve solenoid to pickup of the control rod notch position 36 reed switch). In addition, a reference to notch 36 has been added to the Specification 3.2.3.2 limiting condition for operation for consistency. Notch 36 has already been established as the control rod position corresponding to the 20% scram time position and, as such, is currently referenced in the definition for mu and r Jn this specification.
SIGNIFICANT liAZARDS ANALYSIS The Commission has provided standards in 10CFR50.92(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 dif ferent 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 determined that:
1.
The proposed amendment does not involve a significant increase in the.
j probability or consequences of an a_cident previously evaluated. These changes are bounded by the analyses provided in the Updated Final Safety Analysis Report (FSAR). Operational transients analyzed in the Updated FSAR have been re-evaluated in detail. The Supplemental Reload Licensing Report provides a summary of the limiting operating transient, stability, and selected i
accident analyses for the proposed core arrangement. The 8x8 fuel assemblies j
to be installed in the core are not significantly different from the 8x8 fuel assemblies they are replacing. The NRC Staf f has previously approved the design of the GE8x8EB fuel assemblies in Amendment 10 of GESTAR II (NEDE-240ll-P-A). The.NRC Staf f has also approved in GESTAR 11 the analytical methods used to evaluate the ef fects of the replacement fuel on thermal-hydraulic limits and transients.
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l Document Control Desk
- NLS-87-l%1 Page 3 2.
The proposed amendment does not create the possibility of a new or different accident for the same reasons as stated in item 1. This reload merely changes 3
the initial conditions and/or final condition used in the existing analyses and j
does not create any new accident mode.
l 3.
The proposed amendment does not involve a significant reduction in a margin of safety because the plant will be operated under the same Safety Limits with Minimum Critical Power Ratio (MCPR), Maximum Average Planar Linear Heat Generation Rate (MAPLHGR), and Linear Heat Generation Rate (LHGR) operating limits comparable to those currently established. The Supplemental Reload Licensing Report provides a summary of the limiting operating transient, stability, and selected accident analyses for the proposed core arrangement. The MCPR, MAPLHGR, and LHGR limits have been revised to assure the margin of safety is maintained as demonstrated in the
" Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2, Reload 7, Cycle 8."
Based on the above reasoning, CP&L has determined that the proposed amendment does not involve a significant hazards consideration.
ADMINISTRATIVE INFORMATION The Company has evaluated this request in accordance with the provisions of -
10CFR170.12 and determined that a license amendment application fee is required. A check for $150 is enclosed in payment of the fee.
The revised BSEP Unit 2 TS pages are provided in Enclosure 1. A copy of the General Electric prepared " Supplemental Reload Licensing Report"is provided in Enclosure 2.-
Please note that Appendices A and B of the Supplemental Reload Licensing Report are not applicable to the Technical Specification revisions enclosed in this submittal. These appendices have been prepared to support a request to remove cycle-specific reload requirements from the Technical Specifications, which is being requested by separate submittal as described below. The loss of coolant accident analysis report for BSEP Unit 2 will be provided in a subsequent submittal by October 15,1987.
As previously discussed with the NRR Project Manager for the Brunswick Plant, CP&L is submitting two license amendment applications relating to reload licensing of BSEP Unit 2 for Cycle 8. This submittal provides proposed cycle-specific revisions to the Technical Specifications to reflect reload requirements for Cycle 8 operation. By a separate submittal, the Company is proposing revisions to remove cycle-specific reload requirements from the Technical Specifications. Issuance of one of these two requests is needed to support start-up of BSEP Unit 2 from the upcoming refueling outage.
Issuance of the submittal to remove cycle-specific reload requirements is being requested by March 1,1988. Should the NRC be unable to complete review of the request and issue the necessary amendment by that date, the Company requests that the NRC issue by March 1,1988 the Cycle 8 reload Technical Specifications enclosed in this application. If the request for removing cycle-specific reload requirements is issued as requested to support BSEP Unit 2 start-up, the Company will submit a letter to withdraw the Cycle 8 reload request.
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L Document Control Desk NLS-87-184 / Page 4 ~
Please refer any questions regarding this submittal to Mr. S. R. Zimmerman at (919) 836-6242.
Yours very truly,
~~
ffg L. W. Eury Senior Vice Pre dent Operations Support WRM/lah (5273WRM)
Enclosures cc:
Dr. J. Nelson Grace
- Mr. W. H. Ruland Mr. E. Sylvester Mr. M. W. Hodges Mr. D. Brown
- L. W. Eury, 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 t'~ information are officers, employees, contractors, and agents of Carolina Power & L.ght Company.
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