ML051030138

Correction of the Safety Evaluation to Amendment 100 Regarding the Alternative Source Term

ML051030138
Person / Time
Site:	Seabrook
Issue date:	04/15/2005
From:	Nerses V NRC/NRR/DLPM/LPD1
To:	Peschel J, Warner M Florida Power & Light Energy Seabrook
Nerses V, NRR//DLPM, 415-1484
References
TAC MC1097
Download: ML051030138 (7)

Text

April 15, 2005 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - CORRECTION OF THE SAFETY EVALUATION TO AMENDMENT REGARDING THE ALTERNATIVE SOURCE TERM (TAC NO. MC1097)

Dear Mr. Warner:

By letter dated February 24, 2005, (Accession No. ML050320373) the Nuclear Regulatory Commission (NRC) issued Amendment No. 100 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No.1 (SS) to revise the SS licensing basis to incorporate a full-scope application of an alternative source term methodology. The Safety Evaluation (SE) enclosed with Amendment No. 100 contained administrative or typographical errors on pages 16 and 30.

Therefore, the NRC is enclosing corrected SE pages 16 and 30.

We regret any inconvenience this may have caused. If there are any further questions, please contact me at (301) 415-1484 or vxn@nrc.gov.

Sincerely,

/RA/

Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

As stated cc w/encl: See next page

Seabrook Station, Unit No. 1 cc:

Mr. J. A. Stall Mr. Stephen McGrail, Director Senior Vice President, Nuclear and ATTN: James Muckerheide Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Philip T. McLaughlin, Attorney General Mr. Peter Brann Steven M. Houran, Deputy Attorney Assistant Attorney General General State House, Station #6 33 Capitol Street Augusta, ME 04333 Concord, NH 03301 Resident Inspector Mr. Bruce Cheney, Director U.S. Nuclear Regulatory Commission New Hampshire Office of Emergency Seabrook Nuclear Power Station Management P.O. Box 1149 State Office Park South Seabrook, NH 03874 107 Pleasant Street Concord, NH 03301 Town of Exeter 10 Front Street Mr. Gene F. St. Pierre Exeter, NH 03823 Station Director Seabrook Station Regional Administrator, Region I FPL Energy Seabrook, LLC U.S. Nuclear Regulatory Commission P.O. Box 300 475 Allendale Road Seabrook, NH 03874 King of Prussia, PA 19406 Mr. M. S. Ross, Managing Attorney Office of the Attorney General Florida Power & Light Company One Ashburton Place, 20th Floor P.O. Box 14000 Boston, MA 02108 Juno Beach, FL 33408-0420 Board of Selectmen Mr. Rajiv S. Kundalkar Town of Amesbury Vice President - Nuclear Engineering Town Hall Florida Power & Light Company Amesbury, MA 01913 P.O. Box 14000 Juno Beach, FL 33408-0420 Ms. Deborah Bell Federal Emergency Management Agency James M. Peschel Region I Regulatory Programs Manager J.W. McCormack P.O. & Seabrook Station Courthouse Building, Room 401 FPL Energy Seabrook, LLC Boston, MA 02109 PO Box 300 Seabrook, NH 03874 Mr. Tom Crimmins Polestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019

Seabrook Station, Unit No. 1 cc:

David Moore Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Ave., NW Suite 220 Washington, DC 20004

April 15, 2005 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT NO. 1 - CORRECTION OF THE SAFETY EVALUATION TO AMENDMENT REGARDING THE ALTERNATIVE SOURCE TERM (TAC NO. MC1097)

Dear Mr. Warner:

By letter dated February 24, 2005, (Accession No. ML050320373) the Nuclear Regulatory Commission (NRC) issued Amendment No. 100 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No.1 (SS) to revise the SS licensing basis to incorporate a full-scope application of an alternative source term methodology. The Safety Evaluation (SE) enclosed with Amendment No. 100 contained administrative or typographical errors on pages 16 and 30.

Therefore, the NRC is enclosing corrected SE pages 16 and 30.

We regret any inconvenience this may have caused. If there are any further questions, please contact me at (301) 415-1484 or vxn@nrc.gov.

Sincerely,

/RA/

Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC D. Roberts C. Raynor OGC PDI-2 Reading V. Nerses G. Hill (2) ACRS C. Holden R. Dennig G. Matakas, RI Accession No.: ML051030138 OFFICE PDI-2/PM PDI-2/LA SPSB/SC PDI-2/SC NAME VNerses CRaynor RDennig REnnis for DRoberts DATE 4/13/05 4/14/05 4/12/054/12/05 4/15/05 OFFICIAL RECORD COPY

generator and 940 gpd total into the three unaffected steam generators. FPLE states that this allocation of the leakage yields the most limiting doses. The primary-to-secondary leakage continues until the RCS temperature is less than 212 "F (at about 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />). In converting the l TS maximum allowable volumetric flow to mass flow values for input to analyses, FPLE uses a density value of 62.4 lb/ft3. This is consistent with the guidance of RG 1.183 (see Appendix F, l Paragraph 5.2).

The leakage in the unaffected steam generators mixes with the bulk water and is released at the assumed steaming rate. This steaming from the unaffected steam generators is assumed to continue for eight hours. FPLE determined that the tubes in the unaffected steam generators would remain covered by the bulk water. FPLE assumes that the radionuclide concentration in the unaffected steam generator is partitioned such that one percent of the radionuclides in the bulk water enters the vapor space and is released to the environment.

FPLE assumes a CR isolation delay of 30 seconds to account for diesel generator sequencing, damper positioning, and instrumentation delays. This isolation would be actuated by either safety injection signals or by radiation levels greater than two times background on GM radiation detectors located in the ventilation intake ductwork. Following isolation, the filtered outside air makeup is 600 cfm, and the filtered recirculation flow is 390 cfm. FPLE assumes an unfiltered inleakage rate of 150 cfm, of which 20 cfm is via the emergency fire exit doors and the remainder via the diesel building. This assumed inleakage rate is greater than that determined in recently performed tracer gas infiltration tests.

The NRC staff found that FPLE used analysis assumptions and inputs consistent with applicable regulatory guidance identified in Section 2.0 of this SE. The assumptions found acceptable to the staff are presented in Table 1. Additionally, the NRC staff did independent calculations and confirmed the FPLE conclusions. The EAB, LPZ, and CR doses estimated by FPLE for the MSLB were found to meet the applicable accident dose criteria and are, therefore, acceptable.

3.4.4 SGTR The accident considered is the complete severance of a single tube in one of the steam generators resulting in the transfer of RCS water to the ruptured steam generator. The primary-to-secondary break flow through the ruptured tube following and SGTR results in radioactive contamination of the secondary system. A reactor trip occurs, safety injection actuates, and a LOOP occurs concurrently with the reactor trip. As this LOOP renders the main condenser unavailable, the plant is cooled down by releases of steam to the environment. A single atmospheric steam dump valve (ASDV) is assumed to fail open providing a continuous release path. Two cases are considered:

• A single ASDV fails open when the water level reaches 33 percent in the ruptured steam generator

• A single ASDV fails open three minutes after the reactor trip.

Secondary containment drawdown time, min 8 l Secondary containment filtration Aerosols/Elemental 95 Organic 85 Secondary containment bypass fraction 0.6 Release points Leakage Plant vent Secondary containment bypass containment surface ECCS Leakage Pathway Start of ECCS leakage, minutes 26 ECCS leak rate (includes 2x multiplier), gpd 48 Duration of release, days 30 Containment sump volume, ft3 69,159 Iodine flashing (fraction of total iodine in leakage) 0.1 Fraction of core inventory iodine in sump 0.4 Chemical form release fractions Elemental 0.97 Organic 0.03 Release pathway Plant vent