ML111790032

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Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 2B, Markup of Proposed Operating License and Technical Specifications Pages
ML111790032
Person / Time
Site: Byron  Constellation icon.png
Issue date: 06/23/2011
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
Shared Package
ML111790026 List:
References
Download: ML111790032 (8)
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Text

ATTACHMENT 2B Markup of Proposed Operating License and Technical Specifications Pages Byron Station, Units I and 2 Facility Operating License Nos. NPF-37 and NPF-66 REVISED OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES Operating License (Units 1 and 2), Page 3 TS Page 1.1-6 TS Page 2.0-1 TS Page 3.4.1-1 TS Page 3.4.1-2 TS Page 5.6-4

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, and use In amounts as required any byproduct, source or specia possess, material without restriction to chemical or physical form, for sample l nuclear analysis or instrument calibration or associated with radioactive apparatus or components: and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, separate, such byproduct and special nuclear materials as may bebut not produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions in the Commission's regulations set forth In 10 CFR Chapter specified applicable provisions of the Act and to the rules, regulations, andI and Is subjec t to all orders of the Commission now or hereafter In effect and is subject to the additio nal conditions specified or Incorporated below:

(1) MAMMgM P2M jevsl The licensee is author ized to Aerate the facility at reactor core power levels not in excess of megawatts thermal (1 00 percent power) in accordance with the conditions specified herein.

(2)

The Technical SpeciffqOetis' contained in Appendix A as revised through Amendment No, the Environmental Protection Plan contained In Appendix S. both of which are attached hereto, are hereby incorp orated into this license. The licensee shall operate the facility in accordance the Technical Specifications and the Environmental Protection Plan. with Deleted.

Deleted.

Deleted.

(8) The licensee sly Im;* ment and maintain In effect all provisions approv ed fire protection program as described In the lir see's of the Protection Report, and as approved in the SER dated February Fire 1987 through Supplement No. 8, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No,

(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 are required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in the Commission's regulation set forth in 10 CFR Chapter I 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 J'^ 46 The licensee Is authorized toAerate the facility at reactor core power levels not in excess of egawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) TechnicalSDecifiications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG 1113), as revised through Amendment No._f6 , and the Environmental Protection Plan contained in Appendix , bot of which are attached to License No, NPF-37, dated February 14, 1 5, are hereby incorporated into this license. The licensee shall open a the facility in accordance with the Technical Specifications and the nvironmental Protection Plan.

(3) Deleted.

(4) Deleted.

(5) Deleted.

Amendment No.-#%

Definitions 1.1 1.1 Definitions PRESSURE AND The PTLR is the unit specific document that TEMPERATURE LIMITS provides the reactor vessel pressure and REPORT (PTLR) temperature limits including heatup and cooldown rates, and the pressurizer Power Operated Relief Valve (PORV) lift settings for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector 3645 calibrated output to the average of the lower excore detector calibrated outputs, whichever is er.

RATED THERMAL POWER RTP shall be a to-r or core heat transfer (RTP) rate to the reactor coolant-6111,3686.6 MWt.

REACTOR TRIP The RTS RESPONSE TIME shall be that time interval SYSTEM (RTS) RESPONSE from when the monitored parameter exceeds its RTS TIME trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

RECENTLY IRRADIATED FUEL Fuel that has occupied part of a critical reactor core within the previous 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Note that all fuel that has been in a critical reactor core is referred to as irradiated fuel.

BYRON - UNITS 1 & 2 1.1 - 6 Amendment 448

SLs 2.0 2.0 SAFETY LIMITS (SLs) and >_ 1.19 for the ABB-NV DNB correlation for a thimble cell and a typical 2.1 SLs cell 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Re for Coolant System (RCS) highest loop ave r age temperature and pressurizer pressure shall not exceed the limits sp ified in the COLR; and the following SLs shall not e exceeded 2.1.1.1 In MODE 1, the Departure from Nucleate oiling Ratio (DNBR) shall be maintained ? 1 24 for the WRB-2 DNB correlation for a thimble cell and 1.25 for the WRB-2 DNB correlation for a typical cell!

2.1.1.2 In MODE 2, the DNBR shall be maintained >_ 1.17 for the WRB-2 DNB correlation, and carrel8$ian 2.1.1.3 In MODES 1 and 2, the peak fuel centerline temperatur shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU burnup.

1.13 for the ABB-NV correlation and ? 1.18 for 2.1.2 RCSPressure SL the WLOP DNB correlation In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained

< 2735 prig.

2.2 SL Violations 2.2.1 If SL 2.1. 1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

BYRON - UNITS 1 & 2 2.0 - 1 Amendment 424

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature (T), and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure within the limit specified in the COLR;
b. RCS average temperature (Tn) within the limit specified in the COLR; and
c. RCS total flow rate ? gpm and within the limit specified in the COLR.

386,004

..---------- NOTE ----------- - -------- - -------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or
b. THERMAL POWER step > 10% RTP.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> parameters not within parameter(s) to limits. within limit.

B. Required Action and 8.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

BYRON -- UNITS 1 & 2 3.4.1 - 1 Amendment 4-1-9

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is within the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature (Ta ) is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> w i t hi n the li m i t specifie d in the l O LR ,

SR 3.4.1.3 Verify RCS total flow rate is ? gpm 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an d w i t hi n th e li m i t spec ifi e d i n t h e SR 3.4.1.4 ------------------- NOTE --------------------

386,000 Not required to be performed until 7 days after ? 90% RIP.

Verify by precision heat balance that RCS 18 months total flow rate is ?@G,.900 gpm and within the limit specified in t COLR.

386,000 BYRON - UNITS 1 & 2 3.4.1 - 2 Amendment 4-19

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 C RE.OPERATING LIMITS REPORT (COLR) (continued)

5. ComEd letter from D. Saccomando to the Office of Nuclear Reactor Regulation dated December 21, 1994, transmitting an attachment that documents applicable sections of WCAP-11992/11993 and ComEd application of the UET methodology addressed in "Additional Information Regarding Application for Amendment to Facility Operating Licenses-Reactivity Control Systems,"
6. WCAP-16009-P-A, Revision 0, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005.
7. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985.
8. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using NOTRUMP Code," August 1985.
9. WCAP-10216-P-A, Revision 1, "Relaxation of Constant Axial Offset Control - F0 Surveillance Technical Specification," February 1994.
10. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions,"

September 1986-, .d C. T4 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; and

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
11. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis,"

October 1999; BYRON - UNITS 1 & 2 5.6 - 4 Amendment 440

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