ML070780059

Technical Specification 4.1.1 Regarding Control Rod System Surveillance Requirements

ML070780059
Person / Time
Site:	Nine Mile Point
Issue date:	03/15/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MD3360
Download: ML070780059 (7)

Text

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 193 is hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.

(3) The licensee shall submit an application for license amendment, including supporting analyses and evaluations by December 18, 1998. This amendment application shall contain the proposed methods for compliance with GDC 19 dose guidelines under accident conditions based upon system design and without reliance upon the use of potassium iodide.

Renewed License No. DPR-63

LI ITIN CONDITION FOR OPERATION LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT SURVEILLANCE REQUIREMENT

c. Scram Insertion Times c. Scram Insertion Times (1) The average scram insertion time of all The maximum scram insertion time shall be operable control rods, in the power operation demonstrated through measurement for*:

condition, shall be no greater than:

(1) All control rods prior to thermal power

% Inserted Average Scram exceeding 40% power with reactor pressure From Fully Insertion above 800 psig, after each major refueling Withdrawn Times (sec) outage or after a reactor shutdown that is greater than 120 days.

5. 0.375 20 0.90 (2) Specifically affected individual control rods 50 2.00 following maintenance on or modification to 90 5.00 the control rod or control rod drive system which could affect the scram insertion time of (2) Except as noted in 3.1.1.c(3), the maximum those specific control rods with reactor insertion scram time, in the power operation pressure above 800 psig.

condition, shall be no greater than:

(3) At least 20 control rods, on a rotating basis, on

% Inserted Maximum Scram a frequency of less than or equal to once per From Fully Insertion 180 days of cumulative power operation, with Withdrawn Times (sec) reactor pressure above 800 psig.

5 0,398 0.954 For single control rod scram time tests, the control 20 50 2.12 rod drive pumps shall be isolated from the 90 5.30 accumulators.

AMENDMENT NO. 442,193 33

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT (3) Control rods with longer scram insertion time will be permitted provided that no other control rod in a nine-rod square array around this rod has a:

(a) Scram insertion time greater than the maximum allowed, (b) Malfunctioned accumulator, (c) Valved out of service in a non-fully inserted position. -

d. Control Rod Accumulators d. Control Rod Accumulators At all reactor operating pressures, a rod Once a shift check the status of the accumulator accumulator may be out of service provided that pressure and level alarms in the control room.

no other control rod in a nine-rod square array around this rod has a:

(1) Malfunctioned accumulator, (2) Valved out of service in a non-fully inserted position, (3) Scram insertion greater than maximum permissible insertion time.

AMENDMENT NO. 142, 193 34

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until APLHGR at all nodes is within the prescribed limits.

b. Linear Heat Generation Rate, (LHGR) b. Linear Heat Generation Rate (LHGR)

During power operation, the Linear Heat The LHGR as a function of core height shall be Generation Rate (LHGR) of -any rod in any fuel checked daily during reactor operation at Ž_25%

assembly at any axial location shall not exceed rated thermal power.

the limiting value specified in the Core Operating Limits Report.

If at any time during power operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded at any location, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the LHGR at all locations is not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 10% per hour until LHGR at all locations is within the prescribed limits.

c. Minimum Critical Power Ratio (MCPR) c. Minimum Critical Power Ratio (MCPR)

During power operation, the MCPR for all fuel at (1) MCPR shall be determined daily during reactor rated power and flow shall be within the limit power operation at >25% rated thermal power.

provided in the Core Operating Limits Report.

(2) MCPR operating limit shall be determined If at any time during power operation it is within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of completing scram time determined by normal surveillance that the above testing as required in Specification 4.1.1 (c).

limit is no longer met, action shall be initiated within 15 minutes to restore operation to within AMENDMENT NO. 42,143, 193 66