ML080080457
| ML080080457 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/03/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD6136 | |
| Download: ML080080457 (10) | |
Text
(5) ENO 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 amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: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. 289, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Fire Protection ENO shall implement and maintain in effect all provi sions 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 INRC 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), 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:
ENO 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. 289
(1) Recirculation Pump Motor Vibration Perform monitoring of recirculation pump motor vibration during initial Cycle 13 power ascension for uprated power conditions.
(2) Startup Test Program The licensee will follow a startup testing program, during Cycle 13 power ascension, as described in GE Licensing Topical Report NEDC-31 897P-1, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate."
The startup test program includes system testing of such process control systems as the feedwater flow and main steam pressure control systems. The licensee will collect steady-state operational data during various portions of the power ascension to the higher licensed power level so that predicted equipment performance characteristics can be verified. The licensee will do the startup testing program in accordance with its procedures. The licensee's approach is in conformance with the, test guidelines of GE Licensing Topical Report NEDC-31 897P-1, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate," June 1991 (proprietary), GE Licensing Topical Report NEDO-31 897, "Generic Guidelines for General Electric Boiling Water Reactor Power Uprate," February 1992 (nonproprietary), and NEDC-31897P-AA, Class Ill (proprietary), May 1992.
(3) Human Factors The licensee will review the results of the Cycle 13 startup test program to determine any potential effects on operator training. Training issues identified will be incorporated in Licensed Operator training during 1997. Simulator discrepancies identified will be addressed in accordance with simulator Configuration Management procedural requirements.
F. Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 289, are hereby incorporated into this license. ENO shall operate the facility in accordance with the Additional Conditions.
G. ENF and ENO shall take no action to cause Entergy Global Investments, Inc. or Entergy International Ltd. LLC, or their parent companies, to void, cancel, or modify the $70 million contingency commitment to provide funding for the facility as represented in the application for approval of the transfer of the facility license from PASNY to ENF and ENO, without the prior written consent of the Director, Office of Nuclear Reactor Regulation.
H. The decommissioning trust agreement shall provide that the use of assets in the decommissioning trust fund, in the first instance, shall be limited to the expenses related to decommissioning of the facility as defined by the NRC in its Amendment No. 289
CREVAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System ICO 3.7.3 Two CREVAS subsystems shall be OPERABLE
- - - - - - - - - - - - - NO - TE- - - - - - - - - - - - - - -
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, and 3 During movement of recently irradiated fuel assemblies in the secondary containment During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS______________________
CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVAS subsystem A-l. Restore CREVAS 7 days inoperable for reasons subsystem to OPERABLE other than Condition B. status.
B. One or more CREVAS B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.
boundary in MODE 1, 2, or 3. AND B.2 Verify mitigating actions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary to 90 days OPERABLE status.
(continued)
JAFNPP 3.7.3-1 JAFNP 3..3-1Amendment 289
CREVAS SYSTEM 3.7.3 ACTIONS (continued) _______________________
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion TIime of,Condition Aor B iAND not met in MODE 1, 2, or
- 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and--------------NOTE ----------
associated Completion LCO, 3.0.3 is not applicable.
Time of Condition. A not -- - ------ -----
met during movement of recently irradiated fuel D.1 Place OPERABLE . Immediately assemblies in the CREVAS subsystem in secondary containment isolate mode.
or during OPDR Vs.
OR 0.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.
AND D.2.2 Initiate action to suspend Immediately OPDRVs.
E. Two CREVAS subsystems E.1 Enter LCO 3.0.3 Immediately inoperable in MODE 1, 2, or 3 for reasons other then Condition B.
(continued)
JAFNPP 3.7.3-2 JAFNP 3..3-2Amendment 289
CREVAS SYSTEM 3.7.3 ACTIONS (continued)________________________
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVAS subsystems------------NOTE ----------
inoperable during LCO 3.0.3 is not applicable.
movement of recently ----- ---------
irradiated fuel assemblies in the F.1 Suspend movement of Immediately secondary containment recently irradiated fuel or during OPDRVs. assemblies in the secondary containment.
OR AND One or more CREVAS subsystems inoperable F.2 Initiate action to suspend Immediately due to an inoperable CRE OPDRVs.
boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
SURVEILLANCE REQUIREMENTS_________
SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREVAS subsystem for 2t 15 92 days minutes.
SR 3.7.3.2 Perform required CREVAS filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP)
(continued)
JAFNPP 3.7.3-3 JAFNP 3..3-3Amendment 289
CREVAS SYSTEM 3.7.3 SURVEILLANCE REQUIREMENTS (continued)__________
SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CR E unfiltered air in-leakage In accordance with testing in accordance with the Control Room the Control Room Envelope Habitability Program. Envelope Habitability Program JAFNPP 3.7.3-4 JAFNP3..3-4Amendment 289
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 'Configuration Risk Management Program (CRMP) (continued)
- d. Provisions for assessing the need for additional actions after the discovery of additional equipm~ent-out-of-service conditions while in the plant configuration descri bed by the LCO Condition(s).
- e. Provisions for considering other applicable risk significant contributors such as level 2 issues and external events, qualitatively or quantitatively.
5.5.14 Control Room Envelope Habitability Program AControl Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation Air Supply (CREVAS) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:
ýb. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
C. Requirements for (i)determining the unfiltered air inleakage past 'the CRE boundary into the CRE in accordance with the testing methods and at the J Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the isolate mode of operation by one subsystem of the CREVAS System, operating at the flow rate required by the VFrP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
(continued)
JAFNPP 5.5-1-4 JAFNPP5.5-14Amendment nF~
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14. Control Room Envelo~e, Habitability Program (continued)
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.
The'unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of SIR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d,respectively.
JAFNPP 5.5-15 JAFNP 5.-15Amendment 289
APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-59 Amendment Number Additional Conditions 243 Entergy Nuclear Operations, Inc. shall describe snubber operation and surveillance requirements in the Final Safety Analysis Report such that future changes to those requirements will be subject to the provisions of 10 CER 50.59.
250 Entergy Nuclear Operations, Inc. shall relocate operability and surveillance requirements for logic bus power monitors, core spray sparger differential pressure, and low pressure coolant injection cross-connect valve position instruments to an Entergy-controlled document where future changes to those relocated requirements are controlled under the provisions of 10 CFR 50.59.
274 Entergy Nuclear Operations, Inc. shall relocate the Technical Specification requirements identified in Table LA - "Removal of Details Matrix" and Table R - "Relocated Specifications" to licensee-contro lled documents, as described in the application as supplemented on, June 12, 2002, and the NRC staff's Safety Evaluation enclosed with Amendment No. 274, dated July 3, 2002. Further, relocations to the updated Final Safety Analysis Report (UFSAR) shall be reflected in the next UFSAR update required by 10 CFR 50.71 (e) following implementation of this amendment.
289 Control Room Envelope Habitability Upon Implementation of Amendment No. 289, adopting TSTF-448 Revision 3, the determination of control room envelope (ORE) unfiltered air inleakage required by SR 3.7.3.3 in accordance with TS 5.5.14.c.(i), the assessment of ORE habitability as required by ..
Specification 5.5.14.c.(ii) , and the measurement of ORE pressure as required by Specification 5.5.14.d shall be considered met. Following implementation:
(a) The first performance of SR 3.7.3.3 in accordance with specification 5.5.14.c(i) shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergy's letter "NRC Generic Letter 2003-0 1 Control Room Habitability Initial Action Summary Report" (JAFP-04-0159),
dated September 27, 2004, or within 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
Amendment No. 289
Appendix C (b) The first performance of the periodic assessment of CRE habitability Specification 5.5.14.c(ii) shall be within 3 years, plus the 9-month allowance of SR 3.0.2 as measured from June 28, 2004, the date of the most recent successful tracer gas test, as stated in Entergy's letter "NRC Generic Letter 2003-0.1 Control. Room Habitability Initial Action Summary Report" (JAFP-04-O1 59), dated September 27, 2004, or within 9 mo'nths if the time period since the most recent successful tracer gas test is greater than 3 years.
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d shall be within 18 months, plus the 138-day allowance of SR 3.0.2 as measured from the date of the most recent successful pressure measurement test or within 138 days if not performed previously.
Amendment No. 289