BSEP 02-0189, Correction to Application for Technical Specification Change
| ML023310219 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/20/2002 |
| From: | O'Neil E Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 02-0189, TSC-2002-05 | |
| Download: ML023310219 (11) | |
Text
r CP&L A Progress Energy Compcay NOV 2 0 20OZ SERIAL: BSEP 02-0189 TSC-2002-05 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. I AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 CORRECTION TO APPLICATION FOR TECHNICAL SPECIFICATION CHANGE Ladies and Gentlemen:
By letter dated November 13, 2002 (i.e., Serial: BSEP 02-0159), Carolina Power & Light (CP&L) Company submitted a license amendment application to revise Post Accident Sampling System Technical Specification requirements for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. Due to an inadvertent omission, Enclosures 2 through 5 of the letter were not included as intended. The omitted enclosures are attached.
Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor - Licensing/Regulatory Programs, at (910) 457-2073.
Sincerely, Edward T. O'Neil Manager - Support Services Brunswick Steam Electric Plant Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461
SFT/sft
Enclosure:
Enclosures 2, 3, 4, and 5 for BSEP 02-0159 dated November 13, 2002 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission AT'TN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Ms. Brenda L. Mozafari (Mail Stop OWEN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Leonard N. Olshan (Mail Stop OWFN 8H12) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Allen G. Howe (Mail Stop OWFN 8G9) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Ms. Beverly 0. Hall, Section Chief Radiation Protection Section, Division of Environmental Health North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221
BSEP 02-0189 Enclosure ENCLOSURES 2,3,4, AND 5 FOR BSEP 02-0159 DATED NOVEMBER 13, 2002 (8 pages follow)
BSEP 02-0159 MARKED-UP TECHNICAL SPECIFICATION CHANGES FOR UNIT 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM)
(continued) indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolafion Cooling, and Reactor Water Cleanup.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at 24 month intervals or less.
The provisions of SR 3.0.2 are applicable to the 24 month PJJ re uenc for performing integrated system leak test activities.
5.5.3 Post Acciw tSamplin oamn and an ze reactor.olant, radio tive iodines nd particulate plant ga ous effluents and containm t
atmosphe samples un accident co tions. The ogram shall inclu the followi g:
Trainin personnel;
- b.
Pr edures for samp g and analys'
- and c
Provisions fo aintenance of mpling and ana sis equipment.
(continued)
Amendment No.
203 5.0-7 Brunswick Unit 1
BSEP 02-0159 MARKED-UP TECHNICAL SPECIFICATION CHANGES FOR UNIT 2
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM)
(continued) indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at 24 month intervals or less.
The provisions of SR 3.0.2 are applicable to the 24 month e
ncy for performing integrated system leak test activities.
5.5.3 Post ident Sa i
(continued)
Amendment No.
233 Brunswick Unit 2 5.0-7
BSEP 02-0159 REVISED TECHNICAL SPECIFICATION PAGES FOR UNIT 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Deleted.
(continued)
Amendment No.
I Offsite Dose Calculation Manual (ODCM)
(continued) indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at 24 month intervals or less.
The provisions of SR 3.0.2 are applicable to the 24 month frequency for performing integrated system leak test activities.
5.5.2 5.5.3 I
Brunswick Unit 1 5.0-7
BSEP 02-0159 REVISED TECHNICAL SPECIFICATION PAGES FOR UNIT 2
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Deleted.
(continued)
Amendment No.
I Offsite Dose Calculation Manual (ODCM)
(continued) indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable.
The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup.
The program shall include the following:
- a.
Preventive maintenance and periodic visual inspection requirements; and
- b.
Integrated leak test requirements for each system at 24 month intervals or less.
The provisions of SR 3.0.2 are applicable to the 24 month frequency for performing integrated system leak test activities.
5.5.2 5.5.3 I
Brunswick Unit 2 5.0-7