ML092250339
| ML092250339 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/31/2009 |
| From: | John Hughey Plant Licensing Branch 1 |
| To: | Pardee C Exelon Generation Co |
| Hughey J, NRR/DORL, 301-415-3204 | |
| References | |
| TAC MD9434, TAC MD9435, TAC MD9447, TAC MD9448, TAC MD9449, TAC MD9450, TAC MD9451, TAC MD9452, TAC MD9454, TAC MD9455, TAC MD9456, TAC MD9457 | |
| Download: ML092250339 (25) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 31,2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB..IECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 -ISSUANCE OF AMENDMENTS RE: INCORPORATION OF PREVIOUSLY NRC APPROVED TSTFS AND OTHER ADMINISTRATIVE CHANGES (TAC NOS.
MD9434, MD9435, MD9447, MD9448, MD9449, MD9450, MD9451, MD9452, MD9454, MD9455, MD9456 AND MD9457)
Dear Mr. Pardee:
The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 273 and 277 to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 7,2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082240520), as supplemented by letter dated May 7, 2009 (ADAMS Accession No. ML091280686).
The amendments revise the PBAPS Units 2 and 3 TSs as follows:
Example 1.4-1 in TS Section 1.4 is modified to reflect the ability to enter a MODE or other specified condition in the applicability of a limiting condition for operation (LCO) without the associated Surveillance being performed within the Frequency requirements of Surveillance Requirement (SR) 3.0.2, and not result in a violation of SR 3.0.4.
- TS Table 3.3.8.1-1, "Loss of Power Instrumentation," is revised to remove note (a) at the bottom of the Table. TS Table 3.3.8.1-1 lists the TS functions associated with the Loss of Power Instrumentation.
PBAPS Unit 2 TS Table 3.3.3.1-1, "Post Accident Monitoring Instrumentation," is revised to correct an error in the title for Function 8.
- Table 3.3.1.1-1, "Reactor Protection System Instrumentation," is modified to delete the "NA" designation from the Allowable Value column for Function 2.1, "OPRM [oscillation power range monitor] Upscale."
C. Pardee
- 2 The proposed amendment also included changes based on Technical Specification Task Force (TSTF) traveler 439, Revision 2, "Eliminate Second Completion Times Limiting Time From Discovery of Failure to Meet an LCO," TSTF traveler 363, Revision 0, "Revise Topical Report references in ITS [Improved Technical Specifications] 5.6.5, COLR [core operating limit report],"
and TSTF traveler 400, Revision 1, "Clarify SR on Bypass of DG [diesel generator] Automatic Trips." These TSTF travelers remain under review by the NRC staff and will be dispositioned separately from the requested changes listed above. Therefore, TAC Nos. MD9434, MD9435, MD9447, MD9448, MD9449 and MD9450 will remain open. All work is complete on TAC Nos.
MD9451, MD9452, MD9454, MD9455, MD9456 and MD9457 and these TACs will be closed.
A copy of our Safety Evaluation is enclosed and a Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Amendment No. 273 to Renewed DPR-44
- 2. Amendment No. 277 to Renewed DPR-56
- 3. Safety Evaluation cc: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 273 License No. DPR-44
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated August 7,2008, as supplemented by letter dated May 7,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Renewed Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 273, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
Implementation Requirements:
This license amendment is effective as of the date of issuance, and shall be implemented within 90 days of issuance. Implementation of the amendment shall include updating the Updated Final Safety Analysis Report in accordance with 10 CFR 50.71(e).
FOR T~E NUCLE~R REGULAT7RYMMISSION C
': / /(~
~~Old-;~ino~, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: August 31, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 273 RENEWED FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page 3 Page 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove 1.4 - 3 3.3-7 3.3 - 26 3.3 - 65 1.4 - 3 3.3-7 3.3 -26 3.3 -65
(5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C.
This renewed 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 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment NO.273,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
(3)
Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualiFication, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled: "Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
(4)
Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report (SER) dated May 23, 1979, and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:
The Exelon Generation Company may make changes to the approved The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-44 Revised by letter dated October 28, 2004 Revised by Letter dated May 29,2007 Amendment No.273 Page 3
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)
If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable.
The Surveillance must be performed within the Frequency requirements of SR 3.0.2 as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1), and LCO 3.0.4 becomes applicable.
EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE Verify flow is within limits.
FREQUENCY Once withi n 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
- 25% RTP 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Example 1.4-2 has two Frequencies.
The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1.
The logical connector "AND" indicates that both Frequency requirements must be met.
Each time reactor power is increased from a power level < 25% RTP to
- 25% RTP. the Surveillance must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").
This type of Frequency does not qualify for the extension allowed by SR 3.0.2.
(continued)
- 1. 4 - 3 Amendment N0'273
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REOUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REOUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.I REOUIREMENTS VALUE I.
Wide Range Neutron Monitors
- a.
Period Short G
SR SR SR SR SR 3.3.1.1.1 3.3.1.1.5 3.3.1.1.12 3.3.1.1.17 3.3.1.1.18
- 0, 13 seconds SR SR SR SR SR 3.3.1.1.1 3.3.1.1.6 3.3.1.1.12 3.3.1.1.17 3.3.1.1.18
- 0, 13 seconds
- b.
Inop G
SR SR 3.3.1.1.5 3.3.1.1.17 NA H
SR SR 3.3.1.1.6 3.3.1.1.17 NA
- 2.
Average Power Ra nge Monitors
- a.
Neutron FIux-High (Setdown) 2 3(c)
G SR SR SR SR 3.3.1.1. 1 3.3.1.1.8 3.3.1.1.11 3.3.1.1.12 s 15.0% RTP
- b.
Simulated Thermal Power-High 3(c)
SR SR SR SR SR 3.3.1.1.1 3.3.1.1.2 3.3.1.1.8 3.3.1.1.11 3.3.1.1.12 s 0.65 W
+ 63.7% RTP(bl and S 118.0%
- c.
Neutron Flux High SR SR SR SR SR 3.3.1.1.1 3.3.1.1.2 3.3.1.1.8
- 3. 3.1.1.11
- 3. 3.1.1.12 s 119.7% RTP
- d.
[nop 1.2 G
SR 3.3.1.1.11 NA
- e.
2-0ut Of*4 Voter 1.2 G
SR SR SR SR 3.3. I. I. I 3.3. l.1. II 3.3.1.1.17 3.3.1.1.18 NA
- f.
OPRM Upscale
- 0,25%
RTP SR SR SR SR SR 3.3.1.1.1 3.3.1.1.8 3.3.1.1. II 3.3.1.1.12 3.3.1.1.I9 rol (continued)
(a ) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
lbl 0.65 (W - jW) + 63.7% RTP when neset fan single loop operation per LCD 3.4.1, "Recirculation Loops Operating."
Ic)
Each APRM channel provides inputs to both tnip systems.
(d)
See COLR for OPRM period based detection algorithm (PBOA) setpoint limits.
PBAPS UN IT 2 3.3-7 Amendment No.273
PAM Instrumentation 3.3.3.1 Post Table 3.3.3.1-1 (page I of I)
Accident Monitoring Instrumentation CONDITIONS REFERENC ED REQUIRED FROM REQUIREO FUNCTION CHANNELS ACTION 0.1
- 1.
Reactor Pressure 2
- 2.
Reactor Vessel Water Le Ye 1 (Wide Range) 2
- 3.
Reactor Vessel Water Le ve1 (Fuel Zone) 2
- 4.
Suppression Chamber Water Level (Wide Rangel
- 5.
Orywell Pressure (Wide Range)
- 6.
Orywe II Pressure (Subatmospheric Range) 2
- 7.
Orywell High Range Radiation
- 8.
Penetration Flow Path PCIV Position per penetration path (a)(b) flow
- 9.
Oeleted
- 10.
Oeleted II.
Suppression Chamber Water Temperature (al Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactiYated automatic valve. closed manual Yalve, blind flange, or check yalye with flow through the valve secured, (bJ Only one position indication channel control room indication channel.
is required for penetration flow paths with only one installed (c)
Each channel requires RTOs inoperable.
10 resistance temperature detectors (RTOs) to be OPERABLE with no two adjacent PBAPS UNIT 2 3.3-26 Amendment No.273
LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)
Loss of Power Instrumentation REQUIRED CHANNELS SURVEI LLANCE ALLOWABLE FUNCTI ON PER BUS REQUIREMENTS VALUE
- 1. 4 kV Emergency Bus Undervoltage (Loss of Voltage)
- a. Bus Undervoltage SR 3.3.8.1.3 NA SR 3.3.8.1.4
- 2. 4 kV Emergency Bus Undervoltage (Degraded Voltage Low Setting)
- a.
Bus Undervoltage 2
~ 2286 V and s 2706 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 1.5 seconds and (1 per SR 3.3.8.1.2 S 2.1 seconds source)
- 3. 4 kV Emergency Bus Undervoltage (Degraded Voltage High Setting)
- a.
Bus Undervoltage 2
~ 3409 V and s 3829 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 23.0 seconds and (1 per SR 3.3.8.1.2 S 37.0 seconds source)
- 4. 4 kV Emergency Bus Undervoltage (Degraded Voltage LOCA)
- a.
Bus Undervoltage 2
~ 3766 V and S 3836 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 9.2 seconds and (1 per SR 3.3.8.1.2 s Hl.8 seconds source)
- 5. 4 kV Emergency Bus Undervoltage (Degraded Voltage non-LOCAl
- a.
Bus Undervoltage 2
~ 4116 V and S 4186 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 57.8 seconds and S 64.2 (1 per SR 3.3.8.1.2 seconds source)
SR 3.3.8.1.4 PBAPS UN IT 2 3.3-65 Amendment No.273
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 277 License No. DPR-56
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (Exelon Generation Company), and PSEG Nuclear LLC (the licensees), dated August 7,2008, as supplemented by letter dated May 7,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Renewed Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 277,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
Implementation Requirements:
This license amendment is effective as of the date of issuance, and shall be implemented within 90 days of issuance. Implementation of the amendment shall include updating the Updated Final Safety Analysis Report in accordance with 10 CFR 50.71(e).
FOR THE NUCLEAR REGULATORY COMMISSION
- 1,-//?W~;/
Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
August 31, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 277 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Facility Operating License with the attached revised page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page 3 Page 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove 1.4 - 3 3.3 -7 3.3 - 65 1.4 - 3 3.3 -7 3.3 - 65
(5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C.
This renewed 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 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level Exelon Generation Company is authorized to operate the Peach Bottom Atomic Power Station, Unit No.3, at steady state reactor core power levels not in excess of 3514 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 277,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.'
(3)
Physical Protection Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans", submitted by letter dated May 17, 2006, is entitled: Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.
(4)
Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in
'Licensed power level was revised by Amendment No. 250, dated November 22,2002, and will be implemented following the 14th refueling outage currently scheduled for Fall 2003.
2The training and Qualification Plan and Safeguards Contingency Plan and Appendices to the Security Plan.
Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised by letter dated November 5,2004 Revised by letter dated May 29,2007 Amendment NO.277 Page 3
Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)
If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable.
The Surveillance must be performed within the Frequency requirements of SR 3.0.2 as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1), and LCO 3.0.4 becomes applicable.
EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS FREQUENCY SURVEILLANCE Verify flow is within limits.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
~ 25% RTP 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Example 1.4-2 has two Frequencies.
The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1.
The logical connector "AND" indicates that both Frequency requirements must be met.
Each time reactor power is increased from a power 1evel < 25% RTP to
~ 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "ill").
This type of Frequency does not qualify for the extension allowed by SR 3.0.2.
(continued)
- 1. 4 - 3 Amendment No.2??
RPS Instrumentation 3.3.1.1 Table 3.3.1.1*1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICA BLE CONDITIONS MODES OR REOUIRED REFERENCED OTHER CHANNELS FROM SPEC IFlED PER TRIP REOUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION 0.1 REQUIREMENTS VALUE
- 1.
Wide Range Neutron Monitors
- a.
Period*Short G
SR 3.3.1. I. 1
~ 13 seconds SR 3.3.1.1.5 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.1
~ 13 seconds SR 3.3.1.1.6 SR 3.3.1.1.12 SR 3.3.1.1.17 SR 3.3.1.1.18
- b. Inop 2
3 G
SR 3.3.1.1.5 NA SR 3.3.1.1.]7 5(a )
3 SR 3.3.1.1.6 NA SR 3.3.1.1.17
- 2. Average Power Range Monitors 31c)
- a.
Neutron Flux*High G
SR 3.3.1. 1.1
" 15.0% RTP (Setdown)
SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 3(c)
- b. Simulated Thermal SR 3.3.1.1.1
" 0.65 W Power*High SR 3.3.1.1.2
+ 63.7% RTP(b) and" 118.0%
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- c.
Neutron Flux*High SR 3.3.1.1.1
,,119.7% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12
- d.
Inop 1,2 G
SR 3.3.1.1.11 NA
- e.
2*0ut Of*4 Voter 1.2 G
SR 3.3.1.1.1 NA SR 3.3.1.1.Jl SR 3.3.1.1.17 SR 3.3.1.1.18
- f. OPRM Upscale
~25%
SR 3.3.1. 1.1 (d)
RTP SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.19 (continued)
(e : With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(bl 0.65 (W. 4W) + 63.71 RTP when reset for single loop operation per LCD 3.4.1, "Recirculation Loops Operating."
(el Each APRM channel provides inputs to both trip systems.
(dl See COLR for OPRM periOd based detection algorithm (PBDAI setpoint limits.
PBAPS UN IT 3 3.3-7 Amendment No. 277
LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)
Loss of Power Instrumentation REQUIRED CHANNELS SURVEILLANCE ALLOWABLE FUNCTION PER BUS REQUIREMENTS VALUE
- 1. 4 kV Emergency Bus Undervoltage (Loss of Voltage)
- a. Bus Undervoltage SR 3.3.8.1.3 NA SR 3.3.8.1.4
- 2. 4 kV Emergency Bus Undervoltage (Degraded Voltage Low Setting)
- a.
Bus Undervoltage 2
~ 2286 V and ~ 2706 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 1.5 seconds and (1 per SR 3.3.8.1.2 s 2.1 seconds source)
- 3. 4 kV Emergency Bus Undervoltage (Degraded Voltage High Setting)
- a.
Bus Undervoltage 2
~ 3409 V and ~ 3829 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 23.0 seconds and (1 per SR 3.3.8.1.2 s 37.0 seconds source)
- 4. 4 kV Emergency Bus Undervoltage (Degraded Voltage LOCA)
- a.
Bus Undervoltage 2
~ 3766 V and ~ 3836 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 9.2 seconds and (1 per SR 3.3.8.1.2 s 10.8 seconds source)
- 5. 4 kV Emergency Bus Undervoltage (Degraded Voltage non-LOCAl
- a.
Bus Undervoltage 2
~ 4116 V and ~ 4186 V (1 per SR 3.3.8.1.2 source)
- b. Time Delay 2
~ 57.8 seconds and ~ 64.2 (1 per SR 3.3.8.1.2 seconds source)
SR 3.3.8.1.4 PBAPS UN IT 3 3.3-65 Amendment No. 277
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AND AMENDMENT NO.277 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR, LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278
1.0 INTRODUCTION
By letter dated August 7,2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. IVIL082240520), as supplemented by letter dated May 7,2009, (ADAMS Accession No. ML091280686), Exelon Generation Company, LLC, the licensee for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, requested to amend the Technical Specifications (TSs), Appendix A, of Renewed Facility Operating License numbers DPR-44 and DPR-56 for PBAPS Units 2 and 3. The submittal requested that the PBAPS Units 2 and 3 TSs be revised as follows:
Implementation of Technical Specification Task Force (TSTF) traveler 485-A, Revision 0, "Correct Example 1.4-1." The change modifies TS Section 1.4, "Frequency," Example 1.4-1 to be consistent with Surveillance Requirement (SR) 3.0.4 which was revised by TS Amendments 252 and 255 (ADAMS Accession No. ML050490123) which incorporated changes based on TSTF-359, Revision 9. The current version of TS Example 1.4-1 is modified to reflect that it is possible to enter the MODE or other specified condition in the applicability of limiting condition for operation (LCO) without the associated Surveillance being performed within the Frequency requirements of SR 3.0.2, and not result in a violation of SR 3.0.4.
- TS Table 3.3.8.1-1, "Loss of Power Instrumentation," is revised to remove note (a) at the bottom of the Table. The note provided transition information while associated plant modifications were being installed. The modifications are complete and the note is no longer necessary.
- 2 PBAPS Unit 2 TS Table 3.3.3.1-1, "Post Accident Monitoring Instrumentation," is revised to correct an error in the title for Function 8. A previous license amendment incorporated into the TS for PBAPS Unit 2 and 3 revised the title for Function 8 in TS Table 3.3.3.1-1 from, "PCIV [primary containment isolation valve] Position," to "Penetration Flow Path PCIV Position." However, Function 8 was inadvertently revised on the PBAPS, Unit 2 page to state "Penetration Flaw [emphasis added] Path PCIV Position." The amendment corrects this error for Function 8 in Table 3.3.3.1-1 of the Unit 2 PBAPS TSs.
- Table 3.3.1.1-1, "Reactor Protection System Instrumentation," is modified to delete the "NA" designation from the Allowable Value column for Function 2.f, "OPRM [oscillation power range monitor] Upscale." This change is incorporated as a clarification since trip setpoints are maintained in the core operating limits report (COLR). However, the reference to footnote "(d)," which states: "See COLR for OPRM period based detection algorithm (PBDA) setpoint limits," will remain in the Allowable Value column for Function 2.f in TS Table 3.3.1.1-1.
The proposed amendment also included changes based on TSTF traveler 439, Revision 2, "Eliminate Second Completion Times Limiting Time From Discovery of Failure to Meet an LCO,"
TSTF traveler 363, Revision 0, "Revise Topical Report references in ITS [Improved Technical Specifications] 5.6.5, COLR," and TSTF traveler 400, Revision 1, "Clarify SR on Bypass of DG
[diesel generator] Automatic Trips." These TSTF travelers remain under review by the NRC staff and will be dispositioned separately from the requested changes listed above.
Exelon Generation Company, LLC (the licensee), provided supplemental information by letter dated May 7,2009 (ADAMS Accession No. ML091280686). The supplemental information included a request that the originally-requested implementation time of 60 days be extended to 90 days. The supplement clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on May 5, 2009 (74 FR 20744).
The NRC staff has completed its review and finds that that the requested TS modifications are acceptable, as discussed in this safety evaluation.
2.0 REGULATORY EVALUATION
The NRC staff reviewed the proposed changes against the criteria of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 and the precedent as established in NUREG-1433, "Standard Technical Specifications (STS), General Electric Plants, BWR/4," Revision 3. Section 182a of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses. In 10 CFR 50.36, the NRC established its regulatory requirements related to the content of TSs. In accordance with 10 CFR 50.36(c)(3), SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. The proper use and application of SR frequency requirements are described in Section 1.4 of the PBAPS Units 2 and 3 TS.
- 3 Additionally, the staff performed this review using acceptance criteria in Chapter 7 of NUREG 0800, "Standard Review Plan (SRP)," Revision 5, issued March 2007. The SRP provides guidance for NRC staff reviewers regarding safety reviews of applications to construct or operate nuclear power plants. Chapter 7 of the SRP provides guidance for review of the instrumentation and control portions of applications for nuclear reactor licenses or permits and amendments to existing licenses.
3.0 TECHNICAL EVALUATION
3.1 Incorporation of TSTF-485-A, Revision 0, "Correct Example 1.4-1" The licensee proposes to incorporate TSTF-485-A, "Correct Example 1.4-1," Revision 0, to modify the PBAPS Units 2 and 3 TS Section 1.4, "Frequency." TS Example 1.4-1 is revised to be consistent with the requirements of SR 3.0.4, which was revised by license amendment numbers 252 and 255, for PBAPS Units 2 and 3, respectively (ADAMS Accession No. ML050490123). These amendments incorporated changes consistent with TSTF-359, "Increase Flexibility in Mode Restraints," Revision 9. Example 1.4-1 would be modified to reflect the acceptability of entering a MODE or other specified condition in the applicability of an LCO with a surveillance not performed within the frequency requirements of SR 3.0.2 without resulting in a violation of SR 3.0.4.
3.1.1 Proposed TS Changes TS 1.4, "Frequency," specifically, the second paragraph of Example 1.4-1 currently states the following:
If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.
The licensee proposes to modify the second paragraph of TS Example 1.4-1 to state the following:
If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1), and LCO 3.0.4 becomes applicable.
3.1.2 Evaluation As currently written, Example 1.4-1 describes that a required surveillance must be performed within the frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition where the SR is required. Failure to do so would result in a violation of SR 3.0.4.
TSTF-359 modified SR 3.0.4 and LCO 3.0.4 to provide conditions under which it is acceptable to enter the Applicability of an LCO with the LCO not met. Therefore, a conforming change to
- 4 Example 1.4-1 is needed to demonstrate how it is possible to enter the MODE or other specified condition in the Applicability of an LCO with a Surveillance not performed within the Frequency requirements of SR 3.0.2 and not have this action result in a violation of SR 3.0.4.
The proposed change to modify the text of TS 1.4 SR Example 1.4-1 modifies the example to demonstrate the proper application of SR 3.0.4. SR 3.0.4 was revised by license amendment numbers 252 and 255, for PBAPS Units 2 and 3, respectively. These amendments had the unintended consequence of making TS 1.4 SR Example 1.4-1 inconsistent with the current TS requirements. The proposed change is consistent with TSTF-485-A, revision 0, "Correct Example 1.4-1."
3.1.3 Summary The NRC staff finds that the proposed change to Example 1.4-1 is consistent with the previously-approved PBAPS amendments 252 and 255, which incorporated changes made in accordance with TSTF-359, revision 9. The change aligns the example with SR 3.0.4 and LCO 3.0.4 as written. Therefore, the NRC staff finds that the proposed change provides needed clarification to the TS, and is acceptable. The NRC staff also notes that the change is consistent with TSTF-485-A, revision O.
3.2 Removal of Obsolete Note for Technical Specification Table 3.3.8.1-1 (PBAPS, Units 2 and 3) and Correction to Table 3.3.3.1-1 (PBAPS, Unit 2)
The licensee's amendment request proposes to modify the PBAPS Units 2 and 3 TS to incorporate two administrative changes. The first change modifies TS Table 3.3.8.1-1, "Loss of Power Instrumentation." TS Table 3.3.8.1-1 lists the TS functions associated with the Loss of Power Instrumentation and include note (a) at the bottom of Table 3.3.8.1-1. The original intent of this footnote was to temporarily retain a record of the previous Loss of Power Instrumentation values to allow for appropriate transition during the period of time that the modifications were being installed on Units 2 and 3. This footnote was to expire no later than March 1, 2000 (as stated in the footnote). The note has expired and is no longer necessary. Therefore, note (a) at the bottom of Table 3.3.8.1-1 is eliminated as an administrative change to the TS.
The second change modifies TS Table 3.3.3.1-1, "Post Accident Monitoring Instrumentation," to correct a typographical error. Previous PBAPS license amendment numbers 259 and 262, dated May 10, 2006 (ADAMS Accession No. ML061070292), incorporated TSTF-295, Revision 0, "Post Accident Monitoring Clarifications." Changes associated with these amendments included changing the title for Function 8 in TS Table 3.3.3.1-1 from, "PCIV Position," to "Penetration Flow Path PCIV Position." However, Function 8 was inadvertently revised on the PBAPS, Unit 2 page to state "Penetration Flaw Path PCIV Position." The proposed change corrects this typographical error for Function 8 in Table 3.3.3.1-1 of the Unit 2 PBAPS TS.
- 5 3.2.1 Proposed TS Changes Note (a) at the bottom of TS Table 3.3.8.1-1 is deleted.
Function 8 in Table 3.3.3.1-1 of the Unit 2 PBAPS TS is revised to state, "Penetration Flow Path PCIV Position."
3.2.2 Evaluation Section 2.5 of the licensee's amendment request addresses two administrative changes. The first of these administrative changes is the removal of a footnote on TS Table 3.3.8.1-1, relating to the "4 kV Emergency Bus Undervoltage (Degraded Voltage LOCA [Ioss-of-coolant accident])"
and "4 kV Emergency Bus Undervoltage (Degraded Voltage non-LOCA)" functions. The original intent of this footnote was to temporarily retain a record of the previous Loss of Power Instrumentation values to allow for appropriatetransition during the period of time that the modifications were being installed on Units 2 and 3. This footnote was to expire no later than March 1, 2000 (as stated in the footnote). The NRC staff finds that the removal of this placeholder does not negatively impact TS criteria and that the edited TS still meets the requirement that the SRs assure that facility operation will be within safety limits per 10 CFR 50.36(d)(3).
The second administrative change requested within Section 2.5 of the licensee's amendment request is the correction of a typographical error within TS Table 3.3.3.1-1. Specifically, the title associated with Function 8 on TS Table 3.3.3.1-1 for Unit 2 incorrectly reads "Penetration Flaw Path PCIV Position." The correct title should be "Penetration Flow Path PCIV Position." Note that the corresponding Unit 3 page does not contain this typographical error. The NRC staff finds that this typographical edit does not negatively impact TS criteria and that the edited TS still meets the requirements stated in 10 CFR 50.36.
3.2.3 Summary The !\\IRC staff finds that the removal of note (a) at the bottom of TS Table 3.3.8.1-1 and correction of the typographical error within TS Table 3.3.3.1-1 does not negatively impact TS criteria and that the edited TS still meet the requirements stated in 10 CFR 50.36. As such, the NRC staff finds these administrative changes to be acceptable.
3.3 Clarification of Allowable Value on Technical Specification Table 3.3.1.1-1 The licensee's amendment request proposes to modify the PBAPS Units 2 and 3 TS to incorporate an administrative change to Table 3.3.1.1-1, "Reactor Protection System Instrumentation." Specifically, the proposed change modifies TS Table 3.3.1.1-1 to delete the "NA" from the Allowable Value column for Function 2.1, "OPRM Upscale." The reference to footnote "(d)," which states: "See COLR for OPRM period based detection algorithm (PBDA) setpoint limits," will remain in the Allowable Value column for Function 2.f in TS Table 3.3.1.1-1.
Footnote "(d)" in TS Table 3.3.1.1-1 references the PBAPS COLR which contains the trip setpoint for setpoint limits associated with Function 2.f. Therefore, the "NA" designation associated with note "d" is eliminated to preclude possible confusion.
- 6 3.3.1 Proposed TS Changes The proposed change modifies TS Table 3.3.1.1-1 to delete the "NA" from the Allowable Value column for Function 2.1, "OPRM Upscale."
3.3.2 Evaluation Section 2.6 of the licensee's amendment request changes the current entry for the Allowable Value column for Function 2f "Average Power Range Monitors OPRM Upscale" within PBAPS TS Table 3.3.1.1-1, "Reactor Protection System Instrumentation" from "NA(d}" to "(d)." The text for footnote "(d)," which currently states, "See COLR for OPRM period based detection algorithm (PBDA) setpoint limits," will remain unchanged. The presence of this footnote has already been approved by the NRC via PBAPS amendment numbers 251 and 254, dated March 21,2005 (ADAMS Accession No. IVIL050270020).
3.3.3 Summary The NRC staff has previously found it acceptable to locate the upscale trip setpoint in the COLR. The NRC staff also finds that the clarification proposed in the licensee's amendment request to delete the "NA" text from the Allowable Value column for Function 2.1, "OPRM Upscale," in TS Table 3.3.1.1-1 does not negatively impact this TS and the edited TS still meets the requirements stated in 10 CFR 50.36. As such, the NRC staff finds this clarification to the TS to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official provided no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The changes discussed in this safety evaluation relate to administrative procedures or requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (74 FR 20744). The changes discussed in this safety evaluation meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the
- 7 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Victor Cusumano, Carl Schulten, Jonah Pezeshki Date: August 31, 2009
C. Pardee
- 2 The proposed amendment also included changes based on Technical Specification Task Force (TSTF) traveler 439, Revision 2, "Eliminate Second Completion Times Limiting Time From Discovery of Failure to Meet an LCO," TSTF traveler 363, Revision 0, "Revise Topical Report references in ITS [Improved Technical Specifications] 5.6.5, COLR [core operating limit report],"
and TSTF traveler 400, Revision 1, "Clarify SR on Bypass of DG [diesel generator] Automatic Trips." These TSTF travelers remain under review by the NRC staff and will be dispositioned separately from the requested changes listed above. Therefore, TAC Nos. MD9434, MD9435, MD9447, MD9448, MD9449 and MD9450 will remain open. All work is complete on TAC Nos.
MD9451, MD9452, MD9454, MD9455, MD9456 and MD9457 and these TACs will be closed.
A copy of our Safety Evaluation is enclosed and a Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Ira/ (Peter Bamford for)
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosures:
- 1. Amendment No. 273 to Renewed DPR-44
- 2. Amendment No. 277 to Renewed DPR-56
- 3. Safety Evaluation cc: Distribution via ListServ DISTRIBUTION:
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Accession No: ML092250339
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IV memo ae an memo ae OFFICE LPL1-2/PM NAME JHughey 8/28/09 DATE LPL1-2/LA ABaxter 08/18/09 EICB/BC*
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BHarris w/corrections HChernoff 04/06/09 03/16/09 08/26/09 8/31/09 OFFICIAL RECORD COpy