ML20215J071
| ML20215J071 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/21/1986 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215J074 | List: |
| References | |
| NLS-86-338, NUDOCS 8610240286 | |
| Download: ML20215J071 (3) | |
Text
'
CD&L Carolina Power & Light Company SERIAL: NLS-86-338 gng Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM El.ECTRIC PLANT, UNIT NO. I DOCKET NOS. 50-325 / LICENSE NOS. DPR-74 REQUEST FOR LICENSE AMENDMENT FUEL CYCLE NO. 6 - RELOAD LICENSING
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 revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit No.1 (BSEP-1). The purpose of this amendment is to incorporate more conservative minimum critical power ratio (MCPR) values in Section 3/4.2.3 and Table 3.2.3.2-1, thereby allowing reload licensing for BSEP-1 Cycle 6 under the provision of 10 CFR 50.59. In addition, Table 3.2.3.2-1 is revised by combining the turbine trip / load reject without bypass and the feedwater control failure transients into a single pressurization transient.
DISCUSSION This amendment request provides more conservative power distribution limits for operation of BSEP-l. The current limits were supplied in the General Electric Report No. 23A4663, " Supplemental Reload Licensing Submittal for Brunswick Steam Electric Plant, Unit No.1, Reload 4" submitted April 26,1985. These more conservative limits will bound the BSEP-1 Reload 5 limits, allowing reload licensing for Brunswick-1 Cycle 6 under the provisions of 10 CFR 50.59. When the General Electric topical report for Reload 5 is received, a copy will be forwarded to your staff for informational purposes.
An additional change made in this request includes the combining of the TS Table 3.2.3.2-1, Transient Operating Limit MCPR Values for turbine trip / load reject without bypass and feedwater control failure into a common category of pressurization transients. Creation of the common pressurization transients category of MCPR values will aid future 10 CFR 50.59 reload licensing. For each pressurization transient MCPR value, a factor of conservatism was added to the limiting transient for each exposure range /ODYN Option combination. This results in pressurization transient MCPR values which bound both the original sets of MCPR values.
8610240286 861021 PDR ADOCK 05000325
\\
0 P
PDR 0
k.
m r y n vme sheet
- P O Ba 1551
- Rap N C MC2
Director of Nuclear Reactor Regulation NLS-86-338 / Page 2 The final core configuration resulting from this reload will consist of no fuel assemblies significantly different from those previously found acceptable to the NRC.
This amendment request is similar to that requested for BSEP-2 Reload 6 submitted an December 20,1985, and issued on April 30,1986. The submittal of December 20 was supplemented by a meeting on March 18,1986, between representatives of CP&L and the NRC. The meeting was held to discuss methodologies used by CP&L to arrive at the proposed MCPR limits and the applicability of General Electric SIL 380. On March 28,1986, CP&L submitted a summary of calculational methods discussed at the l
meeting. These same methods have been used to arrive at the conservative MCPR limits which bound the BSEP-1 Reload 5 core design.
SIGNIFICANT HAZARDS ANALYSIS The Commission has provided standards for determining whether a significant hazards consideration exists (10 CFR 50.92(c)). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance of 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 significant reduction in a margin of safety. Carolina Power & Light ~
i l
Company has reviewed this request and determined that:
1.
The proposed amendment does rat involve a significant increase in the probability or consequences of an accident previously evaluated because in each case the changes represent more conservative MCPR limits. Formation of a common pressure transient category of MCPR values in TS Table 3.2.3.2-1 was done for simplicity and has no impact on safety. In addition, the final core configuration will consist of no fuel assemblies significantly different from those previously found acceptable to the NRC.
2.
The proposed amendment does not create the possibility of a new or different accident because the final core configuration will consist of no fuel assemblies significantly different from those previously found acceptable to the NRC.
3.
The proposed amendment does not involve a significant reduction in a margin of safety because the plant will be operated under stricter power distribution limits as a result of the amendment.
l Based on the above reasoning, CP&L has determined that the proposed amendment does not involve a significant hazards consideration.
ADMINISTRATIVE INFORMATION The revised Brunswick-1 TS pages are 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 in payment of this fee. Issuance of this amendment is required by April 22, 1987 order to support startup of Brunswick-1.
Director of Nuclear Reactor Regulation NLS-86-338 / Page 3 Please refer questions regarding this submittal to Mr. S. R. Zimmerman at (919) 836-6242.
Yours very truly, I
&V
,/
A. B. Cutter - Vice hresident Nuclear Engineering & Licensing ABC/RWS/bmc (4078RWS)
Enclosures
- cc: Mr. W. H. Rutand (NRC-BNP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. E. Sylvester (NRC)
Mr. Dayne H. Brown
- All cc's with Enclosure 1 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.
'94 2. 771w Notary (Se:Fr0 My commission expires: ///A7/f?
%,,,,,,M o NOTARY i
I i
\\s rueuc ej i
s
_