PLA-6055, Supplement to Proposed Amendments 281 and 251, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67.: Difference between revisions

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{{#Wiki_filter:Robert A. Saccone Vice President  
{{#Wiki_filter:Robert A. Saccone Vice President - Nuclear Operations PPLSusquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 PIaI F I
-Nuclear Operations PPLSusquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3698 Fax 570.542.1504 rasacconeepplweb.com
                                                                                                        %
% I a P I a ' I F%N % a a --P W MAY 18 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT TO PROPOSED AMENDMENT NO. 281 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 251 TO LICENSE NPF-22: "APPLICATION FOR LICENSE AMENDMENT AND RELATED TECHNICAL SPECIFICATION CHANGES TO IMPLEMENT FULL-SCOPE ALTERNATIVE SOURCE TERM IN ACCORDANCE WITH 10 CFR 50.67" Docket Nos. 50-387 PLA-6055 and 50-388  
                                                                                                    %Na%a a
                                                                                                            '
                                                                                                              -  -
Tel. 570.542.3698 Fax 570.542.1504 rasacconeepplweb.com P             W MAY 18 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT TO PROPOSED AMENDMENT NO. 281 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 251 TO LICENSE NPF-22: "APPLICATION FOR LICENSE AMENDMENT AND RELATED TECHNICAL SPECIFICATION CHANGES TO IMPLEMENT FULL-SCOPE ALTERNATIVE SOURCE TERM IN ACCORDANCE WITH 10 CFR 50.67"                                                     Docket Nos. 50-387 PLA-6055                                                                                     and 50-388


==References:==
==References:==
: 1) PLA-5963, Mr. B. T.McKinney (PPL) to Docunent ControlDesk (USNRC)
ProposedAmendment No. 281 to License NPF-14 and ProposedAmendment No. 251 to License NPF-22: "ApplicationforLicenseAmendment andRelated Techlnical Specification Changes To Implement Full-Scope Alternative Source Term In Accordance with 10 CFR 50.67, " dated October 13, 2005.
The purpose of this letter is to supplement the Reference l request for an amendment to the licensing basis for the Susquehanna Steam Electric Station (SSES) Units 1 and 2 that supports a full implementation application of an Alternative Source Term (AST) methodology.
In Reference 1, PPL indicated that the Recirculation Pump Seizure Event AST Analysis would be provided as a separate document at a later date. PPL revised the Recirculation Pump Seizure Analysis and has concluded, in accordance with 10 CFR 50.59, that NRC approval is not required. Thus, a separate submittal will not be provided to NRC for the AST impacts on the Recirculation Pump Seizure Analysis.
As discussed with the SSES Project Manager on January 10, 2006, PPL identified an error subsequent to the submittal of Reference 1. The error involved incorrect transposition of calculation results in a calculation result summary table which was then also carried into results tables presented in Sections 4.6.5 and 4.6.6 of the detailed AST Safety Assessment Report (Attachment 2 of Reference 1). Attachment l to this letter contains the markup of the Reference 1, Attachment 2 affected page showing the correct values.
Awl


1)PLA-5963, Mr. B. T. McKinney (PPL) to Docunent Control Desk (USNRC)Proposed Amendment No. 281 to License NPF-14 and Proposed Amendment No. 251 to License NPF-22: "Application forLicenseAmendment and Related Techlnical Specification Changes To Implement Full-Scope Alternative Source Term In Accordance with 10 CFR 50.67, " dated October 13, 2005.The purpose of this letter is to supplement the Reference l request for an amendment to the licensing basis for the Susquehanna Steam Electric Station (SSES) Units 1 and 2 that supports a full implementation application of an Alternative Source Term (AST)methodology.
Document Control Desk PLA-6055 to this letter contains the revised calculation EC-RADN-1 126, Revision 1, provided to replace the Revision 0 version of the calculation originally provided in 2 of Reference 1.
In Reference 1, PPL indicated that the Recirculation Pump Seizure Event AST Analysis would be provided as a separate document at a later date. PPL revised the Recirculation Pump Seizure Analysis and has concluded, in accordance with 10 CFR 50.59, that NRC approval is not required.
If you have any questions regarding this submittal, please contact Mr. Michael H. Crowthers at (610) 774-7766.
Thus, a separate submittal will not be provided to NRC for the AST impacts on the Recirculation Pump Seizure Analysis.As discussed with the SSES Project Manager on January 10, 2006, PPL identified an error subsequent to the submittal of Reference
I declare under penalty of perjury that the foregoing is true and correct.
: 1. The error involved incorrect transposition of calculation results in a calculation result summary table which was then also carried into results tables presented in Sections 4.6.5 and 4.6.6 of the detailed AST Safety Assessment Report (Attachment 2 of Reference 1). Attachment l to this letter contains the markup of the Reference 1, Attachment 2 affected page showing the correct values.Awl  Document Control Desk PLA-6055 Attachment 2 to this letter contains the revised calculation EC-RADN-1 126, Revision 1, provided to replace the Revision 0 version of the calculation originally provided in Attachment 12 of Reference 1.If you have any questions regarding this submittal, please contact Mr. Michael H. Crowthers at (610) 774-7766.I declare under penalty of perjury that the foregoing is true and correct.Executed on: C 6 Respectfully, Robert accone Vice President  
Executed on: C 6 Respectfully, Robert accone Vice President - Nuclear Operations Attachments:
-Nuclear Operations Attachments:
Attachment 1 - Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values Attachment 2 - Revised Calculation EC-RADN-I 126, Revision I cc:     NRC Region I Mr. A. Blarney, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP
Attachment 1 -Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values Attachment 2 -Revised Calculation EC-RADN-I 126, Revision I cc: NRC Region I Mr. A. Blarney, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP Attachment 1 to PLA-6055 Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values Attachment 2 to PLA-5963 Page 49 of 60 An unidentified unfiltered inleakage rate of 500 cfm is borservatively assumed in the RADTRAD model. This inleakage bounds the tracer gas test results (including error band)from the December 2004 SSES CRHE inleakage test.In addition, 10 cfm of unfiltered inleakage is added to the CRHE to account for ingress/egress of personnel.
 
4.6.4 Radiological Transport Modeling (see Figures 4 & 11)'The radiological release modeled in this analysis is consistent with RG 1.183.The activity was released from the Reactor Building via the SGTS via the environment over a 2 hour period.The 0 -2 hour CRHE z/Q from the SGTS exhaust vent to the Control Room outside air intake of 1.45E-03 sec/in 3 was used in the analysis.4.6.5 Results -Control Room Operator Dose The RADTRAD computer code was used to determine the Control Room operator dose for the FHA/EHA events. Table 4.6-2 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.Table 4.6-2 FHA/EHA Control Room Operator D se (rem)Calculation TEDE RG 1.183 TEDE CR Operator Dose (FHA) 4.4-0 -0 I 5.0 CR Operator Dose (EHA) 0.13 5.0 4.6.6 Results -Offsite Doses The RADTRAD computer code was used to'determiiine the offsite doses. Table 4.6-3 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.Table 4.6-3 -FHA/EHA OffiAte Doses (rem)' " lCalculation TEDE l RGI1.183 TEDE FHA EAB Dose l -1.8CW q 6.3 LPZ Dose l : ,br 6.3 EAB Dose 1.74 ' 6.3 LPZ Dose 0.10 ' 6.3}}
Attachment 1 to PLA-6055 Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values
 
Attachment 2 to PLA-5963 Page 49 of 60 An unidentified unfiltered inleakage rate of 500 cfm is borservatively assumed in the RADTRAD model. This inleakage bounds the tracer gas test results (including error band) from the December 2004 SSES CRHE inleakage test.
In addition, 10 cfm of unfiltered inleakage is added to the CRHE to account for ingress/egress of personnel.
4.6.4 Radiological Transport Modeling (see Figures 4 & 11)
      'The radiological release modeled in this analysis is consistent with RG 1.183.
The activity was released from the Reactor Building via the SGTS via the environment over a 2 hour period.
The 0 - 2 hour CRHE z/Q from the SGTS exhaust vent to the Control Room outside air intake of 1.45E-03 sec/in3 was used in the analysis.
4.6.5   Results - Control Room Operator Dose The RADTRAD computer code was used to determine the Control Room operator dose for the FHA/EHA events. Table 4.6-2 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.
Table 4.6-2 FHA/EHA Control Room Operator D se (rem)
Calculation TEDE       RG 1.183 TEDE CR Operator Dose (FHA)                 4.4 0     I       5.0 CR Operator Dose (EHA)                   0.13                 5.0 4.6.6   Results - Offsite Doses The RADTRAD computer code was used to'determiiine the offsite doses. Table 4.6-3 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.
Table 4.6                                 FHA/EHA OffiAte Doses (rem)
                            ' " lCalculation TEDE l RGI1.183 TEDE FHA EAB Dose l               -1.8CW       q         6.3 LPZ Dose l                 :         ,br         6.3 EAB Dose                 1.74           '       6.3 LPZ Dose                 0.10             '     6.3}}

Revision as of 18:54, 23 November 2019

Supplement to Proposed Amendments 281 and 251, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67.
ML061520457
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/18/2006
From: Saccone R
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-6055
Download: ML061520457 (4)
v • d • e


Text

Robert A. Saccone Vice President - Nuclear Operations PPLSusquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 PIaI F I

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%Na%a a

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Tel. 570.542.3698 Fax 570.542.1504 rasacconeepplweb.com P W MAY 18 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION SUPPLEMENT TO PROPOSED AMENDMENT NO. 281 TO LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 251 TO LICENSE NPF-22: "APPLICATION FOR LICENSE AMENDMENT AND RELATED TECHNICAL SPECIFICATION CHANGES TO IMPLEMENT FULL-SCOPE ALTERNATIVE SOURCE TERM IN ACCORDANCE WITH 10 CFR 50.67" Docket Nos. 50-387 PLA-6055 and 50-388

References:

1) PLA-5963, Mr. B. T.McKinney (PPL) to Docunent ControlDesk (USNRC)

ProposedAmendment No. 281 to License NPF-14 and ProposedAmendment No. 251 to License NPF-22: "ApplicationforLicenseAmendment andRelated Techlnical Specification Changes To Implement Full-Scope Alternative Source Term In Accordance with 10 CFR 50.67, " dated October 13, 2005.

The purpose of this letter is to supplement the Reference l request for an amendment to the licensing basis for the Susquehanna Steam Electric Station (SSES) Units 1 and 2 that supports a full implementation application of an Alternative Source Term (AST) methodology.

In Reference 1, PPL indicated that the Recirculation Pump Seizure Event AST Analysis would be provided as a separate document at a later date. PPL revised the Recirculation Pump Seizure Analysis and has concluded, in accordance with 10 CFR 50.59, that NRC approval is not required. Thus, a separate submittal will not be provided to NRC for the AST impacts on the Recirculation Pump Seizure Analysis.

As discussed with the SSES Project Manager on January 10, 2006, PPL identified an error subsequent to the submittal of Reference 1. The error involved incorrect transposition of calculation results in a calculation result summary table which was then also carried into results tables presented in Sections 4.6.5 and 4.6.6 of the detailed AST Safety Assessment Report (Attachment 2 of Reference 1). Attachment l to this letter contains the markup of the Reference 1, Attachment 2 affected page showing the correct values.

Awl

Document Control Desk PLA-6055 to this letter contains the revised calculation EC-RADN-1 126, Revision 1, provided to replace the Revision 0 version of the calculation originally provided in 2 of Reference 1.

If you have any questions regarding this submittal, please contact Mr. Michael H. Crowthers at (610) 774-7766.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on: C 6 Respectfully, Robert accone Vice President - Nuclear Operations Attachments:

Attachment 1 - Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values Attachment 2 - Revised Calculation EC-RADN-I 126, Revision I cc: NRC Region I Mr. A. Blarney, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

Attachment 1 to PLA-6055 Markup of the Reference 1, Attachment 2 Affected Page Showing the Correct Values

Attachment 2 to PLA-5963 Page 49 of 60 An unidentified unfiltered inleakage rate of 500 cfm is borservatively assumed in the RADTRAD model. This inleakage bounds the tracer gas test results (including error band) from the December 2004 SSES CRHE inleakage test.

In addition, 10 cfm of unfiltered inleakage is added to the CRHE to account for ingress/egress of personnel.

4.6.4 Radiological Transport Modeling (see Figures 4 & 11)

'The radiological release modeled in this analysis is consistent with RG 1.183.

The activity was released from the Reactor Building via the SGTS via the environment over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.

The 0 - 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> CRHE z/Q from the SGTS exhaust vent to the Control Room outside air intake of 1.45E-03 sec/in3 was used in the analysis.

4.6.5 Results - Control Room Operator Dose The RADTRAD computer code was used to determine the Control Room operator dose for the FHA/EHA events. Table 4.6-2 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.

Table 4.6-2 FHA/EHA Control Room Operator D se (rem)

Calculation TEDE RG 1.183 TEDE CR Operator Dose (FHA) 4.4 0 I 5.0 CR Operator Dose (EHA) 0.13 5.0 4.6.6 Results - Offsite Doses The RADTRAD computer code was used to'determiiine the offsite doses. Table 4.6-3 shows the proposed licensing basis dose limit for the FHA/EHA compared to the regulatory limit.

Table 4.6 FHA/EHA OffiAte Doses (rem)

' " lCalculation TEDE l RGI1.183 TEDE FHA EAB Dose l -1.8CW q 6.3 LPZ Dose l  : ,br 6.3 EAB Dose 1.74 ' 6.3 LPZ Dose 0.10 ' 6.3

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