ML20213G759
| ML20213G759 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/11/1986 |
| From: | Kingsley O MISSISSIPPI POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20213G756 | List: |
| References | |
| TAC-61607, TAC-63558, TAC-64095, NUDOCS 8611180316 | |
| Download: ML20213G759 (4) | |
Text
{{#Wiki_filter:. BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE N0. NPF-29 DOCKET N0. 50-416 'IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC. and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, 0. D. Kingsley, Jr., being duly sworn, stated that I am Vice President, Nuclear Operations of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power & Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Nuclear Operations of Mississippi Power & Light Company; and that the statements made and the matters set forth therein are true and correct to best of my knowledge, information and belief. .\\ 't). IK King STATE OF MISSISSIPPI COUNTY OF HINDS day of Y/#v6dv, in and for the me, a N,oJiary Publjc SUBSCRIBED AND SWORN T0 befo , 1986. County and State above named, this / (SEAL) $24L4 kJ My commission exg, ires: Ny Cor.mbtlan ErrJa Sg. n.1937 $bkbgbOO416 11 PDR p J13AECM86111001 - 4
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Item 1 NLS-86/16 RPV Pressure-Temperature Curve Graph Correction
SUBJECT:
Technical Specification Figure 3.4.6.1-1 and Bases 3/4 4.6; pages 3/4 4-21, and B3/4 4-4 DISCUSSION: The proposed change would correct Figure 3.4.6.1-1 by adding the pressure-temperature curves BB' and CC' below 312 psig and deleting the reference to NED0-21778-A which has been superseded by 10CFR50 Appendix G (1983). In addition, there is an editorial correction to Bases 3/4.4.6. JUSTIFICATION: The current RPV pressure-temperature graph, Figure 3.4.6.1-1 was revised and submitted to the NRC on June 17, 1984 in order to comply with 1983 revisions to 10CFR50, Appendix G and H. The revised figure was incorporated into the GGNS Operating License NPF-13 by Amendment 13 dated August 31, 1984. This figure was subsequently incorporated into GGNS Operating License NPF-29 issued November 1, 1984. During a recent review of 1985 FSAR updates, an inconsistency was discovered in which UFSAR Figure 5.3-4 and Technical Specification Figure 3.4.6.1-1 (which are identical) do not correspond to the General Electric (GE) supplied curves. This proposed change is being submitted in order to have the correct RPV pressure-temperature limit curves incorporated into the GGNS Technical Specifications. These corrected curves which have been provided by General Electric for the Unit I reactor pressure vessel are a composite of the most conservative values from 10CFR50 Appendix G (1983) limits and vessel discontinuities which includes bottom head penetration and feedwater nozzle limits. General Electric has performed an evaluation concerning the discrepancies between the existing Technical Specification Figure 3.4.6.1-1 and this proposed change which provides the corrected figure. While GE does recommend that the present pressure-temperature graph should be corrected, GE has concluded that operating with the current graph represents no significant impact on plant safety. This conclusion is based on the nature of BWR operating characteristics and practices. In the case of normal system heatup and pressurization GGNS standard operating procedures avoid the restricted region. A review of plant records regarding plant operations since August 31, 1984 confirmed that the plant has not been operated in the region restricted by the missing segments below 312 psig. The reference to the NED0-21778-A report in the notes on Figure 3.4.6.1-1 was deleted since the latest update of 10CFR50, Appendix G supersedes NED0-21778-A as a basis for curve C. J13TS86110502 - 1
As discussed above the same pressure-temperature curve appears in the plant's Updated FSAR. Following NRC review and approval of the proposed change, appropriate revisions to the UFSAR will be made. In the Technical Specification Bases 3/4.4.6 in the fourth paragraph, seventh sentence the statement "as well as adjustments for possible errors in the pressure and temperature sensing instruments" should be deleted. The pressure / temperature limit curves A', B' and C' predicted adjustments were based only on the shift in RT for the end of life fluence. PossiblesensinginstrumentUh[orswerenot used for the generation of these curves. SIGNIFICANT HAZARDS CONSIDERATIONS: The proposed changes do not involve a significant hazards consideration because operation of Grand Gulf Nuclear Station in accordance with these changes would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated. This change has been evaluated by GE and it has determined that operating the GGNS reactor within the corrected pressure-temperature curve limits would ensure that the design basis conditions would not be exceeded. The plant has been operated only in the acceptable region of the corrected figure. (2) create the possibility of a new or different kind of accident from any accident previously evaluated since this proposed change imposes more stringent pressure-temperature limits on the RPV than the present ~ Technical Specification limits. (3) result in a significant reduction in the margin of safety since the corrected curves are more conservative than those in the current figure. J13TS86110502 - 2 m}}