ML100900319
| ML100900319 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/30/2010 |
| From: | John Hughey Plant Licensing Branch 1 |
| To: | Pardee C Exelon Generation Co |
| Hughey J, NRR/DORL, 301-415-3204 | |
| References | |
| TAC MD9447, TAC MD9448 | |
| Download: ML100900319 (18) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2010 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS RE: ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE (TSTF) TRAVELER 400-A, REVISION 1, "CLARIFY SR
[SURVEILLANCE REQUIREMENT] ON BYPASS OF DG [DIESEL GENERATOR] AUTOMATIC TRIPS (TAC NOS. MD9447 AND MD9448)
Dear Mr. Pardee:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos275 and 279to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The 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 letters dated May 7,2009, and January 19, 2010 (ADAMS Accession Nos. ML091280686 and ML100200086). The August 7,2008, submittal contained several areas of review that are being dispositioned as separate amendment requests.
The amendments issued with this letter revise the PBAPS Units 2 and 3 TSs to delete the list of emergency diesel generator (DG) critical trips from TS Surveillance Requirement (SR) 3.8.1.13 and clarify that the purpose of the SR is to verify that the non-critical trips are bypassed. This TS change adopts TSTF Traveler 400-A, Revision 1, "Clarify SR on Bypass of DG Automatic Trips," (ADAMS Accession No. ML083380672).
C. Pardee
- 2 All work is complete on TAC Nos. MD9447 and MD9448. Accordingly, these TAC Nos. 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.
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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. 275 to Renewed DPR-44
- 2. Amendment No.279 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. 275 Renewed 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 letters dated May 7,2009, and January 19, 2010, 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.
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 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 275,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
Implementation Requirements:
The Peach Bottom Atomic Power Station Updated Final Safety Analysis Report shall be updated in accordance with 10 CFR 50.71(e) to add the following items:
- 1) A list of the critical emergency diesel generator trips and a list of noncritical trips.
- 2) A description of the testing of the emergency diesel generator critical trips including, but not limited to, the administrative controls used to accomplish and control testing of the critical emergency diesel generator protective trip functions. The description shall also include the manner in which the trip functions are tested including a discussion of inputting or simulating appropriate signals and demonstrating that the associated instrumentation logic will function to actuate a trip of the emergency diesel generator.
This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
rold 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: Apri 1 30, 2010
ATTACHMENT TO LICENSE AMENDMENT NO.275 RENEWED FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following page of the Renewed 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 page of the Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove 3.8 - 13 3.8 -13
(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. 275,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. 275 Page 3
3.8.1 AC Sources-Operating SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.8.1.13
- - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - -
A single test at the specified Frequency will satisfy this Surveillance for both units.
Verify each DG's noncritical automatic trips are bypassed on an actual or simulated ECCS initiation signal.
24 months (continued)
PBAPS UN IT 2 3.8-13 Amendment No 275
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. 279 Renewed 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 letters dated May 7,2009, and January 19, 2010, 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.
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 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.279
,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.
- 3.
Implementation Requirements:
The Peach Bottom Atomic Power Station Updated Final Safety Analysis Report shall be updated in accordance with 10 CFR 50.71(e) to add the following items:
- 1) A list of the critical emergency diesel generator trips and a list of noncritical trips.
- 3) A description of the testing of the emergency diesel generator critical trips including, but not limited to, the administrative controls used to accomplish and control testing of the critical emergency diesel generator protective trip functions. The description shall also include the manner in which the trip functions are tested including a discussion of inputting or simulating appropriate signals and demonstrating that the associated instrumentation logic will function to actuate a trip of the emergency diesel generator.
This license amendment is effective as of the date of issuance, and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i{dL,~
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: Apri 1 30, 2010
ATTACHMENT TO LICENSE AMENDMENT NO.279 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Renewed 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 page of the Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.8 - 13 3.8 - 13
(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. 279,are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Speciftcatlona.'
(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.279 Page 3
3.8.1 AC Sources-Operating SR 3.8.1.13 SURVEJ LLANCE FREOUENCY
- ~
~ - - - - - - - - - - - - - - ~ NOTE- - - - - - - - - - - - - - - - - - - -
A single test at the specified Frequency will satisfy this Surveillance for both units.
Verify each DG's noncritical automatic 24 months trips are bypassed on an actual or simulated ECCS initiation signal.
(continued)
PBAPS UN IT 3 3.8-13 Amendment No.279
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AND AMENDMENT NO. 279 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. ML082240520), Exelon Generation Company, LLC, (the licensee) requested approval to amend the Technical Specifications (TS), Appendix A, of Renewed Facility Operating License numbers DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3. The August 7, 2008, submittal contained several areas of review that are being dispositioned as separate amendment requests.
The amendment request reviewed in this Safety Evaluation (SE) would revise the PBAPS Units 2 and 3 TSs to delete the list of emergency diesel generator (DG) critical trips from TS Surveillance Requirement (SR) 3.8.1.13 and clarify that the purpose of the SR is to verify that the non-critical trips are bypassed. This TS change adopts TSTF Traveler 400-A, Revision 1, "Clarify SR on Bypass of DG Automatic Trips," (ADAMS Accession No. ML083380672).
The licensee provided supplemental information by letters dated May 7, 2009, and January 19, 2010 (ADAMS Accession Nos. ML091280686 and ML100200086). The supplemental information included a request that the originally-requested implementation time of 60 days be extended to 120 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
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 NUREG-1433, "Standard Technical Specifications (STS), General Electric Plants, BWR/4," Revision 3. 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.
PBAPS Units 2 and 3 were designed and construction was commenced prior to the codification of the current General Design Criterion (GDC) of Appendix A to 10 CFR Part 50. However, Appendix H of the Updated Final Safety Analysis Report (UFSAR) for PBAPS Units 2 and 3 contains an evaluation of the design bases of the nuclear facility as measured against the General Design Criteria for Nuclear Power Plant Construction Permits that were proposed to be added to 10 CFR Part 50 as Appendix A in July 1967. The licensee concluded that PBAPS Units 2 and 3 conforms to the intent of the proposed General Design Criteria for Nuclear Power Plants, issued by the Atomic Energy Commission in July 1967.
The regulatory requirements and guidance which the NRC staff applied in its review of the amendment included the AEC, Draft Criterion 38, "Reliability and Testability of Engineered Safety Features," and GDC 18, "Inspection and Testing of Electric Power Systems." Regulatory guidance was also considered from Regulatory Guide (RG) 1.9, "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants," (Revision 2, December 1979; Revision 3, July 1993; Revision 4, March 2007).
AEC, Draft Criterion 38 includes the requirement that engineered safety features shall be designed to provide high functional reliability and ready testability. GDC 18, requires, in part, that "[e]lectric power systems important to safety shall be designed to permit appropriate periodic inspection and testing of important areas and features,.... " Regulatory Guide (RG) 1.9, "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants," Revision 4, March 2007, (ADAMS Accession No. ML070380553), describes an acceptable method for complying with the regulations with regard to design and testing of DGs. RG 1.9, Rev. 4, Section 2.2.11, "Perodlc Trip Bypass Test," recommends that the non-by-passed DG critical trips be tested.
- 3
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes
Presently, TS SR 3.8.1.13 states:
Verify each DG's automatic trips are bypassed on an actual or simulated ECCS
[emergency core cooling system] initiation signal except:
- a. Engine overspeed;
- b. Generator differential overcurrent;
- c. Generator ground neutral overcurrent; and
- d. Manual cardox initiation.
The proposed SR 3.8.1.13 states:
Verify each DG's noncritical automatic trips are bypassed on an actual or simulated ECCS initiation signal.
3.2 Evaluation In the above proposed change, the list of critical signals (engine overspeed; generator differential overcurrent; generator ground neutral overcurrent; and manual cardox initiation) is deleted. In the license amendment request (LAR) dated August 7, 2008, Attachment 1, Section 2.2, the licensee provided following justification for the change:
Branch Technical Position ICSB-17, "Diesel Generator Protective Trip Circuit Bypasses," was replaced in 1981 by RG 1.9, Revision 2 (December 1979),
Position C.7. Regulatory Guide 1.9, Rev. 3, Position C.1.8, is essentially unchanged from the 1979 position. The Regulatory Guide only requires verification that the noncritical trips are bypassed and does not require verification that the critical trips are not bypassed. Regulatory Guide 1.9, Rev. 3, Section 2.2.12 states, "Protective Trip Bypass Test: Demonstrate that all automatic diesel generator trips (except engine overspeed, generator differential, and those retained with coincidental logic) are automatically bypassed on an SIAS." Therefore, this SR was intended to verify that the noncritical trips are bypassed so that a spurious actuation of a noncritical trip does not take a DG out of service during an emergency. The Branch Technical Position states that if bypasses of noncritical DG trips are used in the DG design, "the design of the bypass circuitry should include the capability for testing the status and operability of the bypass circuits." This requirement is the source of SR 3.8.1.13. However, as the SR and Bases are currently written, it is implied that it is not only
.necessary to verify that the bypasses are operable, but to verify the other channels are not bypassed. Therefore SR 3.8.1.13 and the associated Bases are revised to clarify the purpose of the SR. Testing to verify that critical DG trips are not bypassed is not required to satisfy the requirements of 10 CFR 50.36(d)(3).
TSTF400-A, Revision 1, was approved by the U. S. Nuclear Regulatory Commission staff, in a letter dated November 13, 2004.
- 4 While the licensee's proposed amendment conforms to approved TSTF-400-A, Revision 1, the NRC staff had a concern that the proposed change deleting the critical trips from SR 3.8.1.13 could result in changes to DG trips and the associated testing requirements without appropriate NRC review, since the proposed TS change would relocate the list of DG critical trips, and associated testing requirements, to the TS Bases and not the UFSAR. NRC practice, as exemplified in Generic Letter 95-10, "Relocation of Selected Technical Specifications Requirements Related to Instrumentation," December 15, 1995, (ADAMS Accession No. ML031070178) has been to accept relocation of information from the TS to the UFSAR. This practice ensures that the relocated information will be subject to evaluation under 10 CFR Section 50.59 since it resides, or is incorporated by reference, in the UFSAR. These concerns were described in NRC letters to the TSTF committee dated July 20,2009, and August 7,2009 (ADAMS Accession Nos. ML091910541 and ML092170688, respectively).
The licensee, in its letter dated January 19, 2010, stated that the following will be added to the PBAPS, Units 2 and 3, UFSAR:
- 1. A listing of the critical diesel generator trips. Also, a list of noncritical trips will be added to the PBAPS, Units 2 and 3, UFSAR. This will ensure that revisions to these trips will be evaluated per the criteria of 10 CFR 50.59 to determine if a license amendment request is required.
- 2. A description of the testing of the diesel generator critical trips similar to that below will be placed in the PBAPS, Units 2 and 3, UFSAR. This will ensure that application of the 10 CFR 50.59 screening criteria will result in an evaluation under 10 CFR 50.59.
"Critical diesel generator (DG) protective trip functions are tested periodically per station procedures. The critical DG protective trip functions are tested by inputting or simulating appropriate signals and demonstrating that the associated instrumentation logic will function to actuate a trip of the DG."
An implementation requirement for the proposed amendment to include the above items in the PBAPS, Units 2 and 3, UFSAR meets the intent of RG 1.9, Rev. 4, Section 2.2.11, and alleviates the NRC concerns.
3.3 Summary The NRC staff has reviewed the licensee's proposed TS change to SR 3.8.1.13 and additional proposed changes to the PBAP Units 2 and 3, UFSAR to resolve NRC staff concerns. Based on the review discussed above, the NRC staff concludes that the proposed change will not adversely impact the licensee's UFSAR description of conformance with AEC, Draft Criterion 38. Therefore, the NRC staff finds that the proposed change is 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 had no comments.
- 5
5.0 ENVIRONMENTAL CONSIDERATION
The NRC staff has determined that the amendments change requirements with respect to installation or use of a facility's components located within the restricted area as defined in 10 CFR Part 20 or a change to SRs. 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)(9). 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 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 Contributor:
Vijay Goel Date: Apri 1 30, 2010
C. Pardee
- 2 All work is complete on TAC Nos. MD9447 and MD9448. Accordingly, these TAC Nos. 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/
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. 275 to Renewed DPR-44
- 2. Amendment No. 279 to Renewed DPR-56
- 3. Safety Evaluation cc: Distribution via ListServ DISTRIBUTION:
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NAME 04/13/10 4/30/10 04/09/10 02/24/10 04/15/10 4/30/10 DATE OFFICIAL RECORD COPY