ML031820452
| ML031820452 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/03/2003 |
| From: | Bhalchandra Vaidya NRC/NRR/DLPM/LPD4 |
| To: | Gerald Williams Entergy Operations |
| References | |
| Download: ML031820452 (3) | |
Text
NN (32)
Partial Feedwater Heating (Section 15.1. SER, SSER #2)
Operation of the plant in the partial feedwater heating mode for the purpose of extending the normal fuel cycle shall'be prohibited until analyses which justify that operation are provided to and approved by the NRC staff.
(33) NUREG-0737 Conditions (Section 22.2)
The following conditions shall be completed to the satisfaction of the NRC.
These conditions reference the appropriate items in Section 22.2. "TMI Action Plan Requirements for Applicants for Operating Licenses", in the Safety Evaluation Report and Supplements 1, 2, 3, 4, and 5 to NUREG-0831.
(a) Control Room Design Review (I.D.1, SER; Appendix E, SSER #2, SSER #4, SSER #5)
Prior to startup following the first refueling outage, SERI shall demonstrate the ability to maintain an 'effective temperature" condition of 85OF or less in the remote shutdown panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 950F.
(b) Training During Low-Power Testing (I.G.1, SER)
Prior to restart following the first refueling outage, MP&L shall complete the additional training and testing related to TMI Action Plan I.G.1 as described in Section 2.3 of the MP&L submittal dated April 3, 1986.
(c) Deleted (d) Hvdrogen Control (Section II.B.7, SER. SSER #2, SSER #3. SSER
- 4, SSER #5)
(1)
During the first cycle of operation, MP&L shall maintain a suitable program of analysis and testing of the installed hydrogen ignition system.
EOI shall submit to the NRC quarterly reports on the status of their research programs.
12 Amendment No. 6", L.M
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued) affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems Include the:
- a.
LPCS System;
- b.
HPCS System;
- c.
RHR System outside containment containing steam or water, except the line to the liquid radwaste system and headers that are isolated by manual valves;
- d.
RCIC System outside containment containing steam or water, except the drain line to the main condenser;
- e.
Hydrogen analyzers of the Combustible Gas Control System;
- f.
Post Accident Sampling System (until such time as a modification eliminates the PASS penetration as a potential leakage path);
- g.
Feedwater Leakage Control System; and
- h.
Suppression pool level detection portion of the Suppression Pool Makeup System.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at refueling cycle intervals or less.
(continued)
GRAND GULF 5.0-8 Amendment No. 44, 15
Programs and Manuals 5.5 5.5 Programs and Manual (continued) 5.5.3 Deleted 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
The program shall be contained in the OCM, shall be implemented by procedures, and shall Include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
- a.
Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;
- b.
Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in 10 CFR 20, Appendix B. Table 2, Column 2;
- c.
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;
- d.
Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; (continued)
GRAND GULF 5.0- 9 Amendment No. 44I1.58