PLA-5922, Proposed License Amendment Numbers 263 for Unit 1 & 228 for Unit 2 for a One-Time Change to TS 3.6.4.10 & 3.6.4.3, Completion Time for Secondary Containment & Standby Gas Treatment Subsystems Supplement No. 1
| ML052010115 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/08/2005 |
| From: | Saccone R Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-5922 | |
| Download: ML052010115 (5) | |
Text
Robert A. Saccone Vice President - Nuclear Operations PPL Susquohanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3698 Fax 570.542.1504 rasaccone@pplweb.com I
pp' I'
% T.4 JUL 0 8 2005 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION, PROPOSED LICENSE AMENDMENT NUMBERS 263 FOR UNIT I AND 228 FOR UNIT 2 FOR A ONE-TIME CHANGE TO TECHNICAL SPECIFICATIONS 3.6.4.1 AND 3.6.4.3, COMPLETION TIME FOR SECONDARY CONTAINMENT AND STANDBY GAS TREATMENT SUBSYSTEMS SUPPLEMENT NO. 1 Docket Nos. 50-387
-PLA-5922 and 50-388
Reference:
- 1) PLA-5734, B. T. McKinney (PPL) to Document Control Desk (USNRQ, "Proposed License Amendment Numbers 263 for Unit I and 228 for Unit 2 for a One-Tinme Change to Technictil Specifications 3.6.4.1 and 3.6.4.3, Completion Time for Secondary Containment and Standby Gas Treatment Subsystems,"
dated Septemnber 8, 2004..
In accordance with the provisions of 10 CFR 50.90, PPL Susquehanna, LLC (PPL) submitted a request for amendment to the Technical Specifications for Susquehanna Unit 1 and Unit 2 (Reference 1).
The enclosure to this letter provides responses to NRC questions that were discussed in a teleconference between NRC and PPL on June 23, 2005.
.The No Significant Hazards Consideration and the Environmental Consideration provided with Reference 1 are not affected by the supplemental information provided herein.
Should you have any questions or require additional information, please contact Mr. Duane L. Filchner at (610) 774-7819.
bD I Document Control Desk PLA-5922 I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
-7ZJ'/Os-A. Saccone
Enclosure:
PPL response to NRC Questions Copy:
NRC Region 1 Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident NRC Inspector
Enclosure to PLA-5922 Response to NRC Questions
- i
Enclosure to PLA-5922 Page 1 of 2 NRC Question 1 (paraphrased):
Provide the dose consequences to the control room operators and individuals located at the EAB and LPZ.
PPL Response:
Results of the control room and off-site dose analyses are summarized in the table below.
Using expected reactor building leakage rates consistent with DBA-LOCA conditions and ventilation systems inside the reactor building not operating, results of these analyses show that the 200-minute SGTS startup time is sufficient to restore the system without significantly impacting current DBA-LOCA doses as given in FSAR Section 15.6.5, and they remain well within the regulatory limits.
DBA-LOCA DOSE (REM)
CURRENT FSAR REGLATRY SECTION 15 200-MINUTE REGULATORY LICENSING SGTS DOSE TYPE/
LIMIT BASIS STARTUP LOCATION (REM)
ANALYSIS TIME --
THYROID 2 Hr Site Boundary 300.
45.1 44.4 30-Day LPZ 300.
24.2 25.5 WHOLE BODY 2 Hr Site Boundary
- 25.
2.19 0.68 30-Day LPZ
- 25.
0.36 0.31 CONTROL ROOM Thyroid
- 30.
10.8 11.0 Whole Body
- 5.
0.75 0.71 Beta Skin
- 75.
12.0 11.4
Enclosure to PLA-5922 Page2of 2 NRC Ouestion 2:
Will the facility continue to meet GDC 60 and 64 during the extended AOT?
PPL Response:
GDC 60 - Control of Releases of Radioactive Materials to the Environment states:
"The nuclear power unit design shall include means to control suitably the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operation, including anticipated operational occurrences. Sufficient holdup capacity shall be provided for retention of gaseous and liquid effluents containing radioactive materials, particularly where unfavorable site environmental conditions can be expected to impose unusual operational limitations upon the release of such effluents to the environment."
For Susquehanna, during normal plant operation, the Ventilation Exhaust Treatment Systems provide filtering of the appropriate Reactor Building and Turbine Building Ventilation exhaust. During an accident, the Reactor Building HVAC will isolate and the impact of an unfiltered release during the proposed 48-hour LCO would be no different than that of the current 4-hour LCO. Therefore GDC 60 continues to be met.
GDC 64 - Monitoring Radioactivity Releases states: "Means shall be provided for monitoring the reactor containment atmosphere, spaces containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents."
For Susquehanna, the normal radiation monitoring systems - i.e., Reactor Building and Turbine Building SPINGS, are not disabled by this TS change. During accident conditions, the Standby Gas Treatment System (SGTS) SPING would not provide meaningful information until a SGTS train is returned to service. This is the same as currently exists with the 4-hour LCO. Also, the Emergency Plan for Susquehanna would utilize Area Radiation Monitors, the Remote Monitoring System, and on-site and off-site monitoring teams to monitor reactor building effluent releases under accident conditions until SGTS is returned to service. Therefore GDC 64 continues to be met.