ML030550236
| ML030550236 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/04/2003 |
| From: | Dugger C Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.03.006 | |
| Download: ML030550236 (12) | |
Text
"
Entergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Charles M. Dugger Vice President - Operations February 4, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket 50-293 License No. DPR-35 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request LETTER NUMBER:
2.03.006
Dear Sir or Madam:
The NRC and Entergy conducted teleconferences on January 3, 2003 and January 13, 2003 to discuss NRC questions related to the Entergy Power Uprate Request. Attachment 1 of this letter provides the responses to the requested information. Attachment 2 is a disk with a zip file of the requested meteorological data for 1978.
This response and the previous responses to requests for additional information do not change the no significant hazard conclusions previously submitted in Entergy Letter 2.02.048, dated July 5, 2002.
Should you have any questions or comments concerning this submittal, please contact Bryan Ford at (508) 830-8403.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of February 2003.
Sin(
0 JRH/dd 203006
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Attachments: 1.
2.
Letter Number: 2.03.006 Page 2 Response to NRC Request for Additional Information (6 pages)
Disk Containing Meteorological Data for 1978 cc:
Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Robert Walker Radiation Control Program Commonwealth of Massachusetts Exec Offices of Health & Human Services 174 Portland Street Boston, MA 02114 Mr. Steve McGrail, Director Mass. Emergency Management Agency 400 Worcester Road P.O. Box 1496 Framingham, MA 01702 203006
ATTACHMENT 1 LETTER NUMBER 2.03.006 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery-Power Uprate Request 203006
Letter Number: 2.03.006 Page 1 of 6 NRC Request:
Provide the Pilgrim specific accident analysis input values in similar format to the example information provided.
Response
The attached three tables provide the requested information in the tabular format of the examples provided.
203006
Letter Number: 2.03.006 Page 2 of 6 Table 1 Main Steam Line Break Accident Analysis Parameters Source Term TS 3.6.B Limit, RCS maximum total iodine concentration uCVmL (1) 20 Operational RCS Iodine Concentration, jiCi/mL (2) 1-131 6.1E-2 1-132 3.OE-1 1-133 3.6E-1 1-134 4.3E-1 1-135 4.4E-1 Coolant Release Mass, Ibm (3)
Steam 25,000 Liquid 60,000 Coolant Release Duration (MSIV Closure), seconds (3) 10.5 Other Parameters Dose conversion factors RG 1.109 Offsite breathing rate, offsite, m3/s 0-8 hours 3.47E-4 8-24 hours 1.75E-4 Atmospheric dispersion factors, s/m 3 - ground-level (4)
EAB, 0-2 hrs:
2.08E-3 LPZ, 0-8 hrs:
1.94E-5 (1) PNPS Technical Specifications (2) PNPS specific value from General Electric source term (3) FSAR Section 14.5 value (4) PNPS specific calculation value 203006
Letter Number: 2.03.006 Page 3 of 6 Table 2 Loss of Coolant Accident Analysis Parameters Source Term Reactor power (1998 x 1.02 (Uncertainty in power measurements) ), MWt Release into primary containment Noble gas in containment (Percent of activity in core)
Iodine in containment (Percent of activity in core)
Iodine species distribution Elemental Organic Particulate Release Data Direct release to atmosphere through SGTS - no hold-up in reactor building SGTS filter efficiency, % (Includes 1 % filter bypass) (1)
Elemental Organic Particulate 2038 Instantaneous 100 25 0.91 0.04 0.05 99 99 99 Primary Containment Primary containment volume, ft3 Suppression pool minimum water volume, ft3 RCS volume (reactor vessel + piping)
Primary containment leakage, % volume/day (2) 147,900 84,000 10,000 1.25 Secondary Containment Mixing No mixing ESF Release ESF leak data (directly to SGTS), gallons/min (3) 0 - 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 5 - 720 hrs ESF flashing fraction, %
ESF source term, % of core iodine inventory 203006 9
3 10 50
Letter Number: 2.03.006 Page 4 of 6 MSIV Leak Data MSIV total leak rate (4 MSIV's), scfh (4) 46 Drywell pressure for MSIV leak rate, psia (5) 59.7 Containment temperature for MSIV leak rate, deg. F(5) 292 Standard pressure, psia 14.7 Standard temperature, deg. C 0
Decontamination factors in main steam piping: (6)
Elemental 100 Organic 1
Particulate 100 MSIV leakage split: (7)
To condenser/LPT (%)
59 To high pressure turbine (%)
41 Condenser/LPT volume (ft3)
(8) 88,400 High Pressure turbine volume (ft3) (8) 800 Iodine plateout in condenser (6) 2 Condenser leak rate to environment (%/day) (9) 0.5 Other Parameters Dose conversion factors RG 1.109 Offsite breathing rate, offsite, m3/s 0-8 hours 3.47E-4 8-24 hours 1.75E-4
>24 hours 2.32E-4 Atmospheric dispersion factors Table 4 (1) Regulatory Guide 1.52 and PNPS TS Bases (2) TS Bases reference using AEC value (3) PNPS specific calculation (4) PNPSTS (5) PNPS Specification E-536 (environmental parameters for post-accident conditions)
(6) BECo letter #81-37/NRC letter of June 24, 1982 (7) NUREG/CR-1169 (8) PNPS specific calculation (9) AEC SER dated August 25, 1971 and BECo letter #81-37/NRC letter of June 24, 1982 203006
Letter Number: 2.03.006 Page 5 of 6 Table 4 Atmospheric Relative Concentration (X/0) Values Receptor Location Ground level X/Q Stack X/Q EAB 0 - 2 hrs 2.08E-3 5.85E-04*
LPZ 0 -4 hrs 1.94E-5 1.91 E-5**
4 - 8 hrs 1.94E-5 2.94E-6 8 - 24 hrs 1.11 E-5 1.77E-6 1 - 4 days 3.72E-6 5.87E-7 4 - 30 days 8.39E-7 1.21 E-7
- The LOCA assumes a stack release with fumigation for 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for EAB (RG 1.145)
Letter Number: 2.03.006 Page 6 of 6 NRC Request:
Describe the meaning of analysis basis setpoints in Table 1 of RAI #6 from Entergy to NRC Letter # 2.02.102 and provide references to NRC approved documents supporting this information.
Response
The analytical inputs for the SRV setpoints are consistent with the NRC approved GE Topical Licensing Report, "Qualification of the One-Dimensional Core Transient Model (ODYN) for Boiling Water Reactors," NEDC-24154P-A, Revision 1.
The second to last column of Table 1 of RAI #6 provides the upper limit setpoint for each SRV, which is calculated based on the nominal setpoint conservatively adjusted for the setpoint tolerance of 1% per the Technical Specifications. For the TPO ATWS analysis, one SRV was conservatively assumed to have a lift setpoint of 1136 psig. This assumption provides conservative results for the ATWS pressurization events, i.e., a slightly higher peak pressure.
PNPS is not changing the actual SRV setpoints as part of the TPO uprate.
The last column identifies the setpoint inputs used in the ODYN code analysis. These setpoint inputs are the result of a statistical spread around the upper limit of the valves in each value group. The statistical spread is derived using GE procedures rather than the ODYN code, and maintains the upper limit mean for each valve group. Consequently, the use of the statistical spread has an insignificant impact on the short-term analysis such as the ATWS peak pressure.
203006
CORRESPONDENCE REVIEW SIGNATURE SHEET #1 EXHIBIT 3 Sheet 1 of 2 TITLE:
Letter 2.03.006 Response To NRC Request For Additional Information Power Uprate Request Effect on safety and reliability of the plant has been evaluated adequately.
Information is accurate, complete, and consistent with NUORG business planning strategy.
Date
.2 0..
Preserves PNPS reputation for conservative decision making.
Explain:
C. M. Dugger 1/A -
1 Effect on safety and reliability of the plant has been evaluated adequately.
d Information is accurate, complete, and consistent with NUORG business planning Di~reo Iar Assessment strategy.
Dat 6Preserves PNPS reputation for conservative decision making.
Date T
3 W. J. Riggs Consistent with NUORG strategy governing regulatory activities.
Licensing Manager Information is accurate and complete.
Information has received proper review for factual content, commitment ownership, Date 4Aand fiscal oversight.
B. S. Ford Explain:
Applicable regulatory documents have been considered in content of letter.
Regulatory Affairs Superintendent.
Information is consistent with other regulatory strategies and commitments.
Information is accurate and complete.
Date Information is consistent with design and Licensing Basis.
Explain:
n o
m Information is accurate and complete.
" Regulatory Oairs/
Source documents verified.
Correspondence Team Leader Commitments are identified and owners assigned.
Date 3
Letter is grammatically correct and free of typographical errors.
Explain:
J. R. Haley NOP83A3 Rev. 5 Page 1 of 3
CORRESPONDENCE REVIEW SIGNATURE SHEET #2 1
EXHIBIT 3 Sheet 2 of 2 TITLE:
Letter 2.03.006 Response To NRC Request For Additional Information Power Uprate Request Configuration control of plant is maintained.
¶ G Plant safety, reputation, and costs have been properly considered.
Organizational interfaces are properly established to support Date information/commitment(s).
Explain:
S. Bethay Technical input provided by Department is properly represented in letter.
Department Manager Scope and schedule of commitment(s) can be met with existing resources.
Impact on existing analyses/operations has been appropriately considered.
Date Explain:
5e C.
/
4 C e L Technical input provided by Department is properly represented in letter.
TO PScope and schedule of commitment(s) can be met with existing resources.
TPO Project Manager Impact on existing analyses/operations has been appropriately considered.
Date Explain:
F. J. Mogolesko All statements, facts, and conclusions are true and accurately stated.
Explain Date S. Wollman "My basis for recommending approval is:
A) "
a-V-,-- Lt C-*
Date 1-"14/0-3 Explain:
P. Compagnone NOP83A3 Rev. 5 Page 2 of 3
CORRESPONDENCE REVIEW SIGNATURE SHEET #2 [
EXHIBIT 3 Sheet 2 of 2 TITLE:
Letter 2.03.006 Response To NRC Request For Additional Information Power Uprate Request Configuration control of plant is maintained.
Director, NESG Plant safety, reputation, and costs have been properly considered.
Organizational interfaces are properly established to support Date information/commitment(s)
Explain:
S. Bethay Technical input provided by Department is properly represented in letter.
Department Manager Scope and schedule of commitment(s) can be met with existing resources Impact on existing analyses/operations has been appropriately considered.
Date Explain:
Technical input provided by Department is properly represented in letter.
- 1 Project" Manager Scope and schedule of commitment(s) can be met with existing resources.
Prjc M nae Impact on existing analyses/operations has been appropriately considered.
Date Explain: K ý l
RA 7
-I c
F. J. Mogolesko All statements, facts, and conclusions are true and accurately stated.
D a te
/ //
E x p la in :
C o
- 7
- fd
- 'z e _
%W S. Wollman My basis for recommending approval is:
Explain:
Date P. Compagnone NOP83A3 Rev. 5 Page 2 of 3 CORRESPONDENCE REVIEW SIGNATURE SHEET #2