ML043140333
| ML043140333 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/08/2004 |
| From: | NRC/NRR/DLPM/LPD1 |
| To: | |
| References | |
| TAC MC1758, TAC MC1759 | |
| Download: ML043140333 (3) | |
Text
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.2 MINIMUM REACTOR VESSEL TEMPERATURE FOR PRESSURIZATION Applicability:
Applies to the minimum vessel temperature required for vessel pressurization.
Objective:
To assure that no substantial pressure is imposed on the reactor vessel unless its temperature is considerably above its Nil Ductility Transition Temperature (NDTT).
Specification:
- a.
During reactor vessel heatup and cooldown when the reactor is not critical, the reactor vessel temperature and pressure shall satisfy the requirements of Figures 3.2.2.a and 3.2.2.b.
- b.
During reactor vessel heatup and cooldown when the reactor is critical, the reactor vessel temperature and pressure shall satisfy the requirements of Figures 3.2.2.c and 3.2.2.d except when performing low power physics testing with the vessel head removed at power levels not to exceed 5 mw(t).
4.2.2 MINIMUM REACTOR VESSEL TEMPERATURE FOR PRESSURIZATION Applicability:
Applies to the required vessel temperature for pressurization.
Obiective:
To assure that the vessel is not subjected to any substantial pressure unless its temperature is greater than its Nil Ductility Transition Temperature (NDTT).
Specification:
- a. Reactor vessel temperature and pressure shall be monitored and controlled to assure that the pressure and temperature limits are met.
AMENDMENT NO. 442, 184 83
LaIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT
- c.
During leakage and hydrostatic testing, the reactor vessel temperature and pressure shall satisfy the requirements of Figure 3.2.2.e, if the core is not critical. During reactor vessel heatup and cooldown for the purpose of leakage and hydrostatic testing, the reactor vessel temperature and pressure shall satisfy the requirements of Figures 3.2.2.a and 3.2.2.b for non-critical heatup and cooldown, respectively.
- d.
The reactor vessel head bolting studs shall not be under tension unless the temperature of the vessel head flange and the head are equal to or greater than 100F.
AMENDMENT NO. 4 42,164,183, 184 84
- b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1.
NEDE-2401 1-P-A, -General Electric Standard Application for Reactor Fuel," U.S. Supplement, (NRC approved version specified in the COLR).
- c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as shutdown margin (SDM), transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
6.6.6 Special Reports Special reports shall be submitted within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a. - f. (Deleted)
- 9.
Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three months).
- h.
Accident Monitoring Instrumentation Report, Specification 3.6.11.a (Table 3.6.11-2, Action 3 or4) (Within 14 days following the event).
AMENDMENT NO. 142,157,162, 181, 15 358