ML082820390
| ML082820390 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/03/2008 |
| From: | Plant Licensing Branch 1 |
| To: | |
| vaidya B, NRR/Dorl/lpl1-1, 415-3308 | |
| References | |
| TAC MD8556 | |
| Download: ML082820390 (8) | |
Text
- 3 (4)
ENO 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 without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.
(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, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and 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 subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement NO.1 dated February 1, 1973; the SER Supplement NO.2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978),80 (dated May 22,1984),134 (dated July 19,1989),135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16,1992),177 (dated February 10,1992),186 (dated February 19,1993),190 (dated June 29,1993),191 (dated July 7,1993),
206 (dated February 28,1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 SUbject to the following provision:
Amendment No. 292 Renewed License No. DPR 59
Definitions 1.1 1.1 Definitions (continued)
LINEAR HEATGENERATION RATE (lHGR)
LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)
MODE OPERABLE - OPERABILITY PRESSURE AND TEMPERATURE LIMITS REPORT (pTLR)
The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
The MCPRshall be the smallest critical power that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
A MODE shall correspond to anyone inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolttenslonlng specified in Table 1.1-1 with fuel in the reactor vessel.
A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem. division, component. or device to perform its specified safety function(s) are also capable of performing their related support function(s).
The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
(continued)
JAFNPP 1.1-4 Amendment 2q2
RCS PIT Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCSPressure and Temperature (PIT) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.
APPLICABILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
- - - - - NOTE - - - - - -
Required Action A.2 shall be completed if this Condition is entered.
Requirements of the LCO not met in MODE 1,2, or 3.
A.1 ANQ A.2 Restore parameter(s) to within limits.
Determine RCS is acceptable for continued operation.
30 minutes 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
Required Action and associated Completion Time of Condition A not met.
B.l AND Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.2 Be in MODE 4.
- 36. hours (continued)
JAFNPP 3.4.9-1 Amendment 2q2
RCS PIT limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1
NOTE-----------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
~---
Verify:
- a.
RCS pressure and RCS temperature are within the limits specified In the curves in the PTLR as applicable; and
- b.
RCS temperature change averaged over a one hour period is:
- 1.
5: 100°F when the RCS pressure and RCS temperature are on or to the right of curve C in the PTLR as applicable, during inservice leak and hydrostatic testing;
- 2.
s 20°F when the RCS pressure and RCS temperature are to the left of curve C In the PTLR as applicable, during inservice leak and hydrostatic testing; and
- 3.
5: 100°F during other heatup and cooldown operations.
30 minutes (continued)
JAFNPP 3.4.9-3 Amendment 292
RCS PIT Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within the criticality limits specified in the PTLR.
Once within 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3
--- --- - - NOTES-----------
- 1.
Only required to be met in MODES 1, 2, 3, and 4 during reclrcutatlon pump startup.
- 2.
Not required to be performed if SR 3.4.9.4 is satisfied.
Verify the difference between the bottom head coolant temperature and the reactor pressure vessel (RPV) coolant temperature is within the limits specified in the PTLR.
Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.4
-- - NOTES -- ------ --
- 1.
Only required to be met in MODES 1, 2,3, and 4 during recirculation pump startup.
- 2.
Not required to be met if SR 3.4.9.3 is satisfied.
Verify the active recircUlation pump flow exceeds 40%
of rated pump flow or the active recirculation pump has been operating below 40% rated flow for a period no longer than 30 minutes..
Once within 15 minutes prior to each startup of a Ireclrculatlon pump (continued)
JAFNPP 3.4.9-4 Amendment 292
RCS PfT limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SR 3.4.9.5 SURVEILLANCE
--- NOTES -------- --
Only required to be met in MODES 1. 2. 3. and 4 during recirculation pump startup.
Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.
FREQUENCY Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.6
NorrS-----------
Only required to be performed when tensioning the reactor vessel head bolting studs.
Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
30 Minutes SR 3.4.9.7
- - - - - - - - - - NOTES - - - - - - - - - - -
Not required to be performed until 30 minutes after RCS temperature s 80°F with any reactor vessel head bolting stud tensioned.
Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
30 minutes (continued)
JAFNPP 3.4.9-5 Amendment 292
RCS PjT Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.4.9.8
-- -- NOTES-----------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature s 100°F with any reactor vessel head bolting stud tensioned.
Verify, when the reactor vessel head bolting studs are under tension, reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.
FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> JAFNPP 3.4.9-6 Amendment ~2
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 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 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.
5.6.6 PAM Report When a report is required by Condition B or F of LCO 3.3.3.1, 'Post Accident Monitoring (PAM) Instrumentation,* a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.7 Reactor Coolant System (RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
- a.
RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:
i) Limiting Conditions for Operation Section 3.4.9 "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.9 "RCS Pressure and Temperature (PIT) Limits"
- b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
i) SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors" ii) SIA Calculation 0800846.301, "2" Instrument Nozzle Stress Analysis"
- c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
JAFNPP 5.6-3 Amendment No. 292