ML090500233
| ML090500233 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/18/2009 |
| From: | Bhalchandra Vaidya Plant Licensing Branch 1 |
| To: | Spence W PPL Corp |
| Vaidya B, NRR/DORL/LP4, 415-3308 | |
| References | |
| TAC MD9572, TAC MD9573 | |
| Download: ML090500233 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William H. Spence Executive Vice President Chief Operating Officer/Chief Nuclear Officer PPL Corporation Two North Ninth Street, GENTW16 Allentown, PA 18101-1179
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATION CHANGE TO TECHNICAL SPECIFICATION 3.6.1.3 TO INCREASE THE MAXIMUM ALLOWABLE SECONDARY CONTAINMENT BYPASS LEAKAGE LIMIT (TAC NOS. MD9572 AND MD9573)
Dear Mr. Spence:
The Commission has issued the enclosed Amendment No. 251 to Facility Operating License No. NPF-14 and Amendment No.
731 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated, July 31, 2008.
The amendments changed the PPL Susquehanna, LLC (PPL) Units 1 and 2 Technical Specification (TSs) 3.6.1.3 "Primary Containment Isolation Valves (PCIVs)." It revised the Secondary Containment Bypass Leakage (SCBL) limit in Surveillance Requirement 3.6.1.3.11 from "less than or equal to 9 standard cubic foot/feet per hour (scfh)" to "less than or equal to 15 scfh when pressurized to greater than or equal to P;."
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular Biweekly Federa/ Register Notice.
Sincerely,
~
~
Bhalchandra K. Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 251 to License No. NPF-14
- 2. Amendment No. 231 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: Distribution via Listserve
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 251 License No. NPF-14
- 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the PPL Susquehanna, LLC, dated July 31, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 set forth in 10 CFR Chapter I; 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 the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 251 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Mark G. Kowal, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: Mlrch 1R, 2f'J:1l
ATTACHMENT TO LICENSE AMENDMENT NO. 2')1 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 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 INSERT 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 TS 3.6-15 TS 3.6-15
-3 (4)
PPL Susquehanna, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as 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)
PPL Susquehanna, LLC, 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. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(36), 2.C.(37), 2.C.(38), and 2.C.(39) to this license shall be completed as specified.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2')1 and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.
(3)
Conduct of Work Activities During Fuel Load and Initial Startup The operating licensee shall review by committee all facility construction, Preoperational Testing, and System Demonstration activities performed concurrently with facility initial fuel loading or with the facility Startup Test Amendment No. a, 4-4J, ++8, 4-W, ~'21r' 2Ja,~, 23+, ass. ~, 24G, ~, ~, ~, 244, ~, ~,
~,~, 24E),~,
PPL Rev.
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System.
24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11
N()TES---------------------------
Only required to be met in M()DES 1, 2, and 3.
Verify the combined leakage rate for all secondary containment bypass leakage paths is < 15 scfh when pressurized to ~ Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.12
N()TES---------------------------
Only required to be met in M()DES 1, 2, and 3.
Verify leakage rate through each MSIV is s 100 scfh and ~300 scfh for the combined leakage including the leakage from the MS Line Drains, when the MSIVs are tested at ~ 24.3 psig or Pa and the MS Line Drains are tested at Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
(continued)
SUSQUEHANNA - UNIT 1 TS/3.6-15 Amendment +00, 246,251
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. NPF-22
- 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the PPL Susquehanna, LLC, dated JUly 31, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 set forth in 10 CFR Chapter I; 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 the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 211 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Mark G. Kowal, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
M3rch lR, 2,(1"P
ATIACHMENT TO LICENSE AMENDMENT NO. 231 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 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 INSERT 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 TS 3.6-15 TS 3.6-15
-3 (4)
PPL Susquehanna, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as 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)
PPL Susquehanna, LLC, 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. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 PPL Susquehanna, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational test, startup tests and other items identified in License Conditions 2.C.(20), 2.C.(21), 2.C.(22), and 2.C.(23) to this license shall be completed as specified.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 231 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151. including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151.
2.C.(3)
PPL Susquehanna, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection dated August 9, 1989, Safety Evaluation Amendment No. 4-, ~, 4-W, 4-W, 4-&1-, -+aJ, ~, 4-99, ~, ~, ~4, 2-+a, ~, U1, ~, 24-9,
~,~,~,~,~,~,~, ~,~, ~, 231
PPL Rev.
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.11
N()TES-------------------------
Only required to be met in M()DES 1, 2, and 3.
Verify the combined leakage rate for all secondary containment bypass leakage paths is s 15 scfh when pressurized to
- >
- Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.12
N()-rES-------------------------
Only required to be met in M()DES 1, 2, and 3.
Verify leakage rate through each MSIV is
~1 00 scfh and 5. 300 scfh for the combined leakage including the leakage from the MS Line Drains when the MSIVs are tested at z 24.3 psig or Pa and the MS Line Drains are tested at Pa.
In accordance with the Primary Containment Leakage Rate Testing Program.
(continued)
SUSQUEHANNA - UNIT 2 TS / 3.6-15 Amendment +ea, ~,231
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 251 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 231 TO FACILITY OPERATING LICENSE NO. NPF-22 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE. INC.
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 388
1.0 INTRODUCTION
By application dated July 31,2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082421142), PPL Susquehanna, LLC (the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Units 1 and 2 (SSES-1 and 2).
The proposed amendments would change the PPL Susquehanna, LLC (PPL) Units 1 and 2 Technical Specification (TSs) 3.6.1.3 "Primary Containment Isolation Valves (PCIVs)." It proposes to revise the Secondary Containment Bypass Leakage (SCBL) limit in Surveillance Requirement (SR) 3.6.1.3.11 from "less than or equal to 9 standard cubic foot/feet per hour (scfh)" to "less than or equal to 15 scfh when pressurized to greater than or equal to Pa."
1.1 BACKGROUND
The current alternative source term (AST) analyses for SSES 1 and 2 were submitted on October 13, 2005 (ADAMS Accession No. ML060120353). The licensee performed radiological consequence analyses for the following four design-basis accidents (DBAs) that result in control room and offsite exposure.
Loss-of-Coolant Accident (LOCA)
Fuel-handling Accidents (FHA)
Control Rod Drop Accident (CRDA)
Main Steam Line Break (MSLB)
That submittal also included changes to the SSES 1 and 2 TS and associated Bases to reflect implementation of AST assumptions in accordance with Title 10 of the Code of Federal Regulations (10 CFR 50.67.) The U.S. Nuclear Regulatory Commission (NRC) approved these changes by letter dated January 31,2007 (ADAMS Accession No. ML070080301), and issued
- 2 Amendment No. 239 to SSES Unit 1 and Amendment No. 216 to SSES Unit 2. Subsequently, the NRC letter dated May 10, 2007 (ADAMS Accession No. ML070080301) contained editorial corrections to the January 31, 2007, letter.
2.0 REGULATORY EVALUATION
The NRC staff finds that the licensee in Section 5.0 of the Enclosure of its submittal, identified the applicable regulatory requirements. The primary regulatory requirements on which the NRC staff based its acceptance are:
Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TS as part of the license. These TS are derived from the plant safety analyses.
10 CFR 50.36 contains the requirements for the content of TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits (SLs), limiting safety system settings (LSSSs), and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
In general, there are two classes of changes to TSs: (1) changes needed to reflect contents of the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. This amendment deals with the first class of change, namely, a change that reflects a change to the DBA-LOCA Dose model. The NRC staff reviewed the proposed change for compliance with 10 CFR 50.36. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.
The current SSES 1 and 2 licensing basis includes a full implementation of an AST, in accordance with 10 CFR 50.67, "Accident source term" as supplemented by accident-specific criteria in Section 15 of NUREG-0800, "Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants" (SRP), and 10 CFR Part 50, Appendix A, General Design Criterion 19 (GDC-19),
"Control room," as supplemented by Section 6.4 of the SRP.
The NRC staff also used the following regulatory and guidance documents during the review:
10 CFR Part 50, Appendix A, GDC 16 - "Containment Design, GDC 50 - "Containment design basis,"
GDC 54 - "Piping systems penetrating primary containment,"
GDC 55 - "Reactor coolant pressure boundary penetrating containment,"
GDC 56 - "Primary containment isolation,"
- 3 Regulatory Guide 1.163 (RG), "Performance Based Containment Leak Rate Test Program,"
RG 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessment at Nuclear Power Plants,"
RG 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,"
RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Assessments at Nuclear Power Plants," and NUREG-0800, SRP Section 15.0.1, "Radiological Consequence Analysis Using Alternative Source Terms."
3.0 TECHNICAL EVALUATION
This section addresses the impact of the proposed change on previously analyzed DBA radiological consequences and the acceptability of the revised analysis. The current TS SR 3.6.1.3 ensures that facility operation will be within safety limits specified in 10 CFR 50.67 by limiting SCBL to s 9 scfh when pressurized to ~ Pa. The licensee proposed revising the SR 3.6.1.3 containment bypass leakage limit frorn s 9 scfh to s 15. The NRC staff evaluated the change and determined that it results in a less restrictive condition since the allowed bypass leakage would increase. The NRC staff has determined that the licensee provided acceptable detailed justification for the change in Attachment 2 to the License Amendment Request dated July 31,2008. Therefore, the NRC staff finds that the change meets the regulatory requirements of 10 CFR 50.36.
SCBL is considered in the licensee's current LOCA dose analysis for SSES 1 and 2 and is a leakage pathway modeled as a ground level release from primary containment directly to the environment based on the drywell volume for the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the combined drywell and wetwell volumes for the remainder of the accident. The LOCA dose analysis assumed that a small amount of the primary containment atmosphere will leak directly to the environment bypassing the secondary containment. Additionally, the LOCA dose analysis assumes that the maximum TS combined leakage rate for all miscellaneous SCBL pathways is 9 scfh for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and it is reduced by 50% after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post-LOCA. The analyses for other DBAs do not consider SBCL as a leakage pathway.
The proposed change will increase the SCBL value to 15 scfh when pressurized to greater than or equal to Pa and consistent with the current SSES 1 and 2 LOCA dose analysis, this value will be reduced by 50% after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post-LOCA. The SCBL pathways are not a dose contributor for the other limiting radiological release events (FHA, CRDA, or MSLB), because SCBL is not a leakage pathway that was analyzed for these events. Therefore, only the LOCA dose analysis is impacted by an increase in the SCBL limit. The licensee used the guidance in RG 1.183 to perform the revised SSES 1 and 2 LOCA radiological consequences analysis. With the exception of the proposed change, the licensee's revised LOCA dose analysis uses identical modeling, methodology, assumptions and computer codes that were previously reviewed and approved by the NRC staff, in SSES 1 and 2 License Amendment Nos. 239 and 216. Because the licensee followed the guidance in RG 1.183, the NRC staff finds that the licensee's approach for calculating the revised LOCA dose analysis for SSES 1 and 2, for the proposed changes is acceptable.
- 4 According to SSES 1 and 2 TS 5.5.12, "Primary Containment Leakage Rate Testing Program,"
the maximum allowable primary containment leakage rate (La), at Pa, shall be 1% of the primary containment air weight per day. The SCBL is subtracted from the total primary containment leakage to obtain the primary containment to secondary containment leakage. Since the SCBL value used in the analysis increased, the primary to secondary containment leakage pathway was decreased to maintain the primary containment leakage at 1.0 La. The NRC staff finds that this calculation is acceptable, because it is consistent with the previously approved Safety Evaluations (SEs,) for Amendment Nos. 239 for Unit 1 and 216 for Unit 2 mentioned in Section 1.1 of this SE.
The atmospheric dispersion (X/O) values used in the current LOCA dose analysis have been previously approved by the NRC staff, in SSES 1 and 2 License Amendment Nos. 239 and 216.
The proposed amendment request does not impact the previously approved X/O values.
Therefore, the NRC staff finds that the use of these X/O values is acceptable in the revised LOCA dose analysis. Based on its review of the control room dose assessment and the dose assessment of exclusion area boundary (EAB) and outer boundary of the low population zone (LPZ ) for the proposed changes based on the results of the revised LOCA dose analysis, the NRC staff find these assessments acceptable The licensee used version 3.03 of the RADTRAD radiological consequences computer code, which is described in NUREG/CR-6604, "RADTRAD: A Simplified Model for RADionuclide Iransport and Removal ~nd Dose Estimation" in the current LOCA dose analysis, referenced in this SE, Section 1.1, "Background." The NRC staff uses the same computer code in its confirmatory analyses. The licensee provided printouts of the RADTRAD input files they used in their LOCA dose analyses for the proposed changes. The NRC staff did not perform independent confirmatory analyses because of the limited number of changes compared to the previously approved LOCA dose analysis. Based on the review of the RADTRAD input files and the LOCA dose analysis model, assumptions and input information provided in the licensee's July 31,2008, amendment request, the NRC staff finds that the licensee's LOCA dose analysis for the proposed changes for the increased allowable SCBL, follows the guidance in RG 1.183 and therefore the NRC staff finds it acceptable.
Total LOCA dose values from the licensee's LOCA dose calculations for the proposed changes are within the 10 CFR 50.67 dose criteria of: 1) 25 rem total effective dose equivalent (TEDE) to an individual located at the EAB for the maximum 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 2) 25 rem TEDE to an individual at the outer boundary of the LPZ for the 30 days, and 3) 5 rem TEDE to an individual in the control room for 30 days. The licensee's calculated TEDE results are: 1) 10.7 rem at the EAB,
The radiological consequences at the EAB, at the LPZ, and in the control room as calculated by the licensee are within the dose criteria specified in the 10 CFR 50.67, and therefore the NRC staff finds them acceptable.
Conclusion - Technical Evaluation As discussed above, the NRC staff reviewed the assumptions, inputs, and methods used by the licensee to assess the radiological impacts of increasing the TS allowable SCBL at SSES 1 and
- 2. The NRC staff finds that the licensee used analysis methods and assumptions consistent with the conservative regulatory requirements and guidance identified in Section 2.0 above.
- 5 The NRC staff compared the doses estimated by the licensee to the applicable criteria identified in Section 2.0. The NRC staff finds, with reasonable assurance that the licensee's estimates of the EAS, LPZ, and control room doses will continue to comply with these criteria. Therefore, the NRC staff finds the proposed revisions to TS 3.6.1.3 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 comments via e-mail and were considered in the staff's review of the licensee's application. The comments and the NRC staff responses can be viewed in ADAMS Accession No. ML090680808.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes 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 (73 FR 68455). Accordingly, the amendments 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: D. Duvigneaud Date: M=lrch lR, 2fUl
(*) - No substantial changes to the SE Input Memo OFFICE LPLI-1/PM LPLI-1/LA AADB/BC(*)
ITSB/BC OGC LPLI-1/BC NAME BVaidya SLittie RTaylor RElliot LSubin MKowal DATE 2/23/09 2/23/09 02/11/09 2/27/09 3/09/09 3/18/09