ML20238D721
| ML20238D721 | |
| 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 | |
| ML20238D723 | List: |
| References | |
| NLS-87-185, NUDOCS 8709110355 | |
| Download: ML20238D721 (5) | |
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CD&L Carolina Power & Light Company.
- SEP 4 3987 -
SERIAL: ' NLS-87-185 10CFR50.90 87TSB03 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT.NOS.1 AND 2 DOCKET NOS. 50-325 & 50-326/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT ELIMINATION OF CYCLE SPECIFIC VARIABLES Gentlemen:
SUMMARY
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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 for the Brunswick Steam Electric Plant, Units 1 and 2. The proposed amendment removes from the Technical Specifications the cycle specific and fuel bundle type specific power distribution operating limits for Minimum Critical Power Ratio, Average Planar Linear Heat Generation Rates, and Average Power Range Monitor setpoints and the associated bases for the NRC approved analysis methodologies. In their place is a reference to the Supplemental Reload Licensing Report in which these limits i
and applicable bases are documented. Redundant requirements for Linear Heat Generation Rate are also being removed from the Technical Specifications. In addition, changes to Section 1.0 -- Definitions, administrative changes such as repagination, and revisions to the Bases are being made to support the removal of the cycle specific and fuel bundle type specific variables.
DISCUSSION Currently, the Brunswick Plant Technical Specifications include the following cycle specific and fuel bundle type specific power distribution operating limits: Minimum Critical Power Ratio (MCPR); Average Planar Linear Heat Generation Rates (APLHGR);
Linear Heat Generation Rates (LHGR); and Average Power Range Monitor (APRM) setpoints. Typically, changes to the power distribution limits, such as MCPR, APLHGR, and LHGR, are required each refueling to reflect upcoming cycle specific
. characteristics. These frequent license amendments represent a significant periodic impact on the Company's as well as the NRC's resources, o : 9 r
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Document Control Desk NLS-87-185 / Page 2 1
The proposed amendment removes the cycle specific and fuel bundle type specific limits and in their place references the Supplemental Reload Licensing Report (SRLR). The SRLR is a unit specific document containing the power distribution limits and bases for the analysis methodology that are applicable for a specific operating cycle. NRC approved analytical methodology is used as the basis for the results reported in the SRLR. The SRLR for future operating cycles will be submitted to the NRC prior to startup from each refueling outage.
In addition, changes to Section 1.0 - Definitions, the deletion of Specification 3/4.2.4 -
Linear Heat Generation Rate, administrative changes such as repagination, and revisions to the Bases have been made to support the removal of tl'e cycle specific and fuel bundle type specific variables.
Definitions for Core Maximum Average Planar Linear Heat Generation Rate Ratio (CMAPRAT), Fraction of Rated Thermal Power (FRTP), Maximum Average Planar Linear Heat Generation Rate Ratio (MAPRAT), and the Supplemental Reload Licensing Report (SRLR) have been added. These new definitions are used to establish revised operating limits and have been presented to the NRC for review in proposed Amendment 19 to NEDE-240ll-P-A (CESTAR !!).
Specification 3/4.2.4 - Linear Heat Generation Rate has been deleted from the Technical Specifications. This specification is redundant since the mechanical design analysis limit (i.e., LHGR) is used in the determination of the APLHGR limit and, therefore, cannot be exceeded if the APLHGR limit is met. The definition in Section 1.0 and the Bases associated with the LHGR have also been deleted. General Electric has presented a similar request to the NRC Staf f for review in proposed Amendment 19 to NEDE-240ll-P-A. General Electric has informed the Company that the review has been completed and a draf t Safety Evaluation Report for Amendment 19 has been prepared and forwarded to the Committee for Review of Generic Requirements for concurrence.
Finally, Surveillance Requirement 4.2.2 was revised to remove reference to the Maximum Total Peaking Factor (MTPF) and the ratio of fuel bundle type specific design Total Peaking Factor (TPF) divided by the MTPF. This ratio is specified as T.
Surveillance Requirement 4.2.2.c currently requires that the MTPF for each fuel bundle type be determined, the value of T calculated, and the flow-biased APRM scram and rod block trip setpoints be adjusted, as required, when the reactor is operating with the MTPF exceeding the design TPF for any fuel bundle type. The MTPF is a direct function of the maximum LHGR. With elimination of LHGR limits from the Technical Specifications, the APRM scram and rod block monitor setpoint setdowns are being redefined in the SRLR in terms of CMAPRAT and FRTP. This definition includes
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implicit reference (in the CMAPRAT value) to fuel bundle type characteristics. The definition will be used for APRM setpoint adjustment as specified in the proposed Amendment 19 to GESTAR II.
SIGNIFICANT liAZARDS ANALYSIS j
The Cominission has provided standards in 10CFR$0.92(c) for determining whether a l
significant hazards consideration exists. A proposed amendment to an operating license l
for a facility involves no significant hazards consideration if operation of the facility in I
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 l
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Document Control Desk NLS-87-185 / Page 3 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 determined that:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of any accident previously evaluated. The abnormal operational transients analyzed in the Updated Final Safety Analysis report will remain bounded. There will be no change in the operation of the facility as a result of the amendment. No safety-related equipment or function will be altered. The amendment merely removes cycle specific and fuel bundle type specific power distribution limits from the Technical Specifications and references their inclusion in the Supplement Reload Licensing Report (SRLR).
NRC approved analytical methodology will be used as the basis for the results reported in the SRLR.
2.
The proposed am^ndment does not create the possibility of a new or different kind of accident Erom any accident previously evaluated. As stated above, no safety-related eculpment, safety functions, or plant operations will be altered as a result of thi. amendment. The requested change does not create any new accident mode. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident.
3.
The proposed amendment does not involve a significant reduction in a margin of safety because the plant will continue to be operated under power distribution limits comparable to those currently established. NRC approved analytical methodology will be used to establish the cycle specific variables reported in the SRLR. The amendment merely removes cycle specific and fuel bundle type specific power distribution limits from the Technical Specifications and incorporates these limits in the SRLR, thereby reducing frequent number of reload license amendments that represent a significant periodic impact on the Company's and the NRC's resources.
Based on the above reasoning, CP&L has determined that the proposed amendment does not involve a significant hazards consideration.
ADMINISTRATIVE INFORMATION The revised BSEP-1 and BSEP-2 Technical Specification pages are provided in Enclosures 1 and 2. The " Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2, Reload 7, Cycle 8"is provided in Enclosure 3. The Supplemental Reload Licensing Report for the current Brunswick Plant, Unit 1 operating cycle will be provided in a subsequent submittal by October 15,1987. The loss of coolant accident analysis report for BSEP Unit 2 will also 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 revisions to remove cycle-specific reload requirements from the Technical Specifications. By a separate submittal, the Company is proposing cycle-specific revisions to the Technical Specifications to reflect reload requirements for Cycle 8 operation. Issuance of one of these two requests is needed to support start-up of BSEP Unit 2 from the upcorning refueling outage.
' Document Control Desk i
- NLS-87-185 / Page 4 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 !ssue by March 1,1988 the Cycle 8 reload Technical Specifications submitted under separate cover. 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.
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 this fee, t
Please refer any questions regarding this submittal to Mr. S. R. Zimmerman at -
(919) 836-6242.
Yours very truly, Q/
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p b 6' & 'j L. W. Eury Senior Vice Prf ident Op6 rations Support LWE/lah (5274WRM)
Attachments cc:
Dr. J. Nelson Grace Mr. W. H. Ruland Mr. E. Sylvester Mr. M. W. Hodges Mr. Dayne 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 his information are officers, employees, contractors, and agents of Carolina Power & Light Company.
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