L-2011-277, Confirmatory Dose Assessment for Control Room Emergency Ventilation System Air Intake Modification to Satisfy Operating License Conditions 3.H.1

Confirmatory Dose Assessment for Control Room Emergency Ventilation System Air Intake Modification to Satisfy Operating License Conditions 3.H.1

ML11228A011
Person / Time
Site:	Turkey Point
Issue date:	08/11/2011
From:	Kiley M Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2011-277
Download: ML11228A011 (7)

Text

0 FPL. I=PL. 10AUG 12011 CFR150.90 L-2011-277 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Confirmatory Dose Assessment for Control Room Emergency Ventilation System Air Intake Modification to Satisfy Operating License Conditions 3.H.1 for DPR-31 and 3.1.1 for DPR-41

References:

(1) W. Jefferson (FPL) to U.S. Nuclear Regulatory Commission (L-2009-133), "License Amendment Request 196: Alternative Source Term and Conforming Amendment,"

Accession No. ML092050277, June 25, 2009.

(2) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-137), "Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 196," Accession No. ML101800222, June 25, 2010.

(3) J. Paige (NRC) to M. Nazar (FPL), "Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Alternative Source Term (TAC NOS. ME 1624 and ME1625)," Accession No. ML110800666, June 23, 2011.

By letter L-2009-133 dated June 25, 2009 [Reference 1], the Florida Power and Light Company (FPL) requested to amend Facility Operating Licenses DPR-31 and DPR-41 and revise the Turkey Point Nuclear Plant (PTN) Units 3 and 4 Technical Specifications (TS). The proposed amendments were to revise the TS to adopt the alternative source term (AST) as allowed in 10 CFR 50.67. On June 25, 2010, FPL submitted a supplement to AST License Amendment Request (LAR) No. 196 that revised the radiological dose consequence analyses due to required changes in the supporting meteorological data for 2005-2009 [Reference 2]. The revised design basis radiological dose consequences analyses included Loss-of-Coolant Accident (LOCA), Main Steam Line Break (MSLB),

Steam Generator Tube Rupture (SGTR), Locked-Rotor, Rod Cluster Control Assembly (RCCA) Ejection, Fuel Handling Accident (FHA), Waste Gas Decay Tank (WGDT)

Rupture, and Spent Fuel Cask Drop.

On June 23, 2011, the NRC approved LAR No. 196, Alternative Source Term (AST) and Conforming Amendment, and issued Amendments 244 and 240 [Reference 3]. Per Operating License Condition 3.H. 1 for DPR-31 and 3.1.1 for DPR-41:

"FPL willprovide to the NRC a confirmatory assessment which demonstrates that the requirements of 10 CFR 50 Appendix A, GDC 19 will be met. The confirmatory assessment willfollow the methodology in Amendment 244/240

[alternativesource term amendment] inch/ding the methods usedfor the establishmentof the atmosphericdispersionfactors (X/Q values)."

The required confirmatory dose assessment is provided in the Attachment to this letter.

p

SOUTHEAST 'ORIGINAL MIRINTAýELOCATION:,' ýN 4.116 [ IN@NRT4643TM'R~T~LCn EW~v OUTHEAV AIRINTAKELOCATION:~ 'N 2.O ~E102,3U00 GRIGMNAI NORTHWAT AIRINTAK{E LOCATION:-, - 'N 4,618.00 ,E 1Ili.OO Figure 1: Routing and Location of CREVS Air Intakes Turkey Point Units 3 and 4 L-2011-277 Docket Nos. 50-250 and 50-251 Attachment Page 4 of 5 Table 1: Onsite Atmospheric Dispersion (X/Q) Factors for Analysis Events Release- Receptor 0-2 hour 2-8 hour 8-24 hour 1-4 days 4-30 days Receptor Release Point X/Q X/Q X/Q X/Q X/Q Pair Point (sec/m 3) (sec/mr3) (sec/m 3) (sec/m 3) (sec/m 3) A Plant stack Normal 1.86E-03 intake SE B Plant stack Emergency 7.52E-04 6.22E-04 2.32E-04 1.80E-04 1.34E-04 intake C Unit 4 RWST Normal 9.87E-04 intake SE D Unit 4 RWST Emergency 1.21E-03 9.53E-04 4.25E-04 2.98E-04 2.31E-04 intake Unit 4 Closest E MSSV noal 1.37E-02 (RV-4-1402) Unit 4 Closest SE F MSSV Emergency 6.94E-04 4.74E-04 1.82E-04 1.43E-04 1.02E-04 (RV-4-1413) intake Unit 4 Main Normal G Steam Line 1.59E-02 Closest Point Unit 4 Main SE H Steam Line Emergency 6.82E-04 4.99E-04 1.95E-04 1.51E-04 I.I1E-04 Closest Point intake Unit 4 I Personnel noal 1.04E-02 Hatchintake Hatch Unit 4 SE J Emergency Emergency 1.10E-03 8.61E-04 3.15E-04 2.59E-04 2.03E-04 Escape Lock intake Unit 4 Spent Normal K Fuel Building intake 2.36E-03 (NW corner) Unit 4 Spent SE L, Fuel Building Emergency 1.61E-03 4.90E-04 3.78E-04 (SE corner) intake Unit 3 Spent NE L2 Fuel Building Emergency 2.43E-03 6.87E-04 (NE corner) intake M Unit 4 SJAE Normal 5.81E-02 intake Unit 4 N Westernmost Normal 1.15E-02 Electrical intake Penetration Aux Building Normal 0 Vent Supply intake 2.84E-03 2.58E-03 1.28E-03 1.19E-03 8.45E-04 (V-0)

• Table 1 revises the information previously provided in Table 1.8.1-2 of L-2010-137 Attachment, "AST Licensing Technical Report NAI-1396-045 Revision 2 [Reference 31.

Turkey Point Units 3 and 4 L-2011-277 Docket Nos. 50-250 and 50-251 Attaclunent Page 5 of 5 Table 2: Summary of Radiological Consequences (rem TEDE) Accident ( Loss of Coolant Accident 3.64 (-0.83A) MSLB Pre-Accident Iodine Spike 1.59 SGTR Pre-Accident Iodine Spike 3.10 MSLB Concurrent Iodine Spike 1.60 SGTR Concurrent Iodine Spike 1.28 Locked Rotor - (CR Auto-Isolation) 1.29 (+0.05A) Locked Rotor - (CR Manual Isolation) 1.25 FHA - Containment Release 1.22 (-0.11A) FHA - Fuel Bldg Release 3.70 (-0.22A) 3 Spent Fuel Cask Drop N/A RCCA Ejection - Containment 2.07 (-0.22A) RCCA Ejection - Secondary Release (CR Auto-Isolation) 1.18 (+0.05A) RCCA Ejection - Secondary Release (CR Manual Isolation) 3.44 (+0.03A) WGDT Rupture 0.34 (+0.01A) Acceptance Criteria <5 Notes: I. Integrated 30-day dose.

2. Parenthetical values are the dose difference from those reported in Reference 3.

3. Spent Fuel Cask Drop no longer considered credible event (ISFSI Amendments 243 and 239).

References (1) J. Paige (NRC) to M. Nazar (FPL), "Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Alternative Source Term (TAC NOS. ME 1624 and ME 1625)," Accession No. MLI 10800666, June 23, 2011. (2) W. Jefferson (FPL) to U.S. Nuclear Regulatory Commission (L-2009-133), "License Amendment Request 196: Alternative Source Term and Conforming Amendment," Accession No. ML092050277, June 25, 2009. (3) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2010-137), "Revised Radiological Dose Consequences for Alternative Source Term and Conforming License Amendment Request 196," Accession No. ML101800220, June 25, 2010.