ML111220078

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Correction Letter for License Amendment Nos. 240 and 244 for Renewed Facility Operating Licenses DPR-24 and DPR-27, Alternate Source Term (AST)
ML111220078
Person / Time
Site: Point Beach  
Issue date: 05/04/2011
From: Beltz T
Plant Licensing Branch III
To: Meyer L
Point Beach
beltz T, NRR/DORL/LPL3-1, 301-415-3049
References
TAC ME0219, TAC ME0220
Download: ML111220078 (7)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2011 Mr. Larry Meyer Site Vice President NextEra Energy Point Beach, LLC Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241-9516 SUB~IECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION LETTER, LICENSE AMENDMENT NOS. 240 AND 244, FOR RENEWED FACILITY OPERATING LICENSES DPR-24 AND DPR-27, RESPECTIVELY, REGARDING ALTERNATE SOURCE TERM (AST) (TAC NOS. ME0219 AND ME0220)

Dear Mr. Meyer:

The Nuclear Regulatory Commission (NRC), by letter dated April 14, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110240054) issued Amendment No. 240 to Renewed Facility Operating License (FOL) DPR-24 and Amendment No. 244 to Renewed FOL DPR-27, for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The amendments consisted of changes to the Technical Specifications (TSs) in response to your application dated December 8,2008.

The following editorial corrections are required:

The TS pages numbered 5.5-16,5.5-18, and 5.5-19, issued with the April 14, 2011, license amendment should be replaced with pages numbered 5.5.15, 5.5-17, and 5.5-18, respectively.

Your staff has been informed of the page numbering error and that corrections are required to your current TSs associated with Section 5.5.

In your AST application dated December 8,2008, (ADAMS Accession No. ML083450683), your staff provided the correct page number (5.5-15) requiring revision. In your AST supplement dated July 8, 2010 (ADAMS Accession No. ML101890783), incorrect page numbers (new pages 5.5-18 and 5.5-19) were submitted. The final "clean copies" of the TS pages to support the AST license amendment request were submitted and the pages incorrectly numbered. The mistake was not identified by the NRC staff prior to issuance of the approved amendment.

Find enclosed the corrected TS pages for Amendment Nos. 240 and 244, to Renewed FOLs DPR-24 and DPR-27, as discussed above.

L. Meyer

- 2 If you have any questions, please call me at 301-415-3049.

Sincerely, rT~A B It7-S

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p/!....-.-tM----

erry. e z, enlor rOJec anager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosure:

TS Page 5.5-15 TS Page 5.5-17 TS Page 5.5-18 cc w/encl: Distribution via Listserv

ENCLOSURE

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

b.

The peak design containment internal accident pressure, Pa, is 60 psig.

c.

The maximum allowable containment leakage rate, La at P a, shall be 0.2% of containment air weight per day.

d.

Leakage rate acceptance criteria are:

1.

Containment leakage rate acceptance criterion is ~ 1.0 La.

2.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance are ~ 0.6 La for the combined Type B and Type C tests and::;; 0.75 La for the Type A tests.

3.

Air lock testing acceptance criteria are:

i.

Overall air lock leakage rate is ~ 0.05 La when tested at ~

Pa, ii.

For each door seal, leakage rate is equivalent to ~ 0.02 La at ~ Pe when tested at a differential pressure of ~ to 10 inches of Hg,

e.

The provisions of SR 3.0.2 do not apply to the test frequencies in the Containment Leakage Rate Testing Program.

f.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

Point Beach 5.5-15 Unit 1 - Amendment No. 240 Unit 2 - Amendment No. 244

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Filtration System (CREFS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. Additionally, separate from the CREFS, the program shall ensure CRE occupants can maintain the reactor in a safe condition following a hazardous chemical release or smoke challenge. The program shall include the following elements:

a.

The definition of the CRE and the CRE boundary.

b.

Requirements for maintaining the CRE boundary in its design condition incliJding configuration control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision O.

d.

Measurement, at designated locations, of the CRE Pressure relative to all external areas adjacent to the CRE boundary during the technical specification emergency mode of operation by the CREFS, operating at the flow rate required by the VFTP, at a Frequency of 18 months. The results shall be trended at a frequency of 18 months and used as part of the periodic assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in Paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA conseq uences.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by Paragraphs c and d, respectively.

Point Beach 5.5-17 Unit 1 - Amendment No. 240 Unit 2 - Amendment No. 244

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitabilitv Program (continued)

g.

An adequate supply of self contained breathing apparatus (SCBA) units in the CRE to protect CRE occupants from a hazardous chemical release.

h.

Portable smoke ejection equipment per the Fire Protection Evaluation Report and Safe Shutdown Analysis Report to address a potential smoke challenge.

Point Beach Unit 1 - Amendment No. 240 Unit 2 - Amendment No. 244

'.. ML111220078 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NRR/LPL3-lIPM NAME TBeitz BTuily RPascarelli TBeitz DATE 5/4/11 5/4/11 5/4/11 5/4/11