ML022700103
| ML022700103 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-065) |
| Issue date: | 10/02/2002 |
| From: | Richard Ennis NRC/NRR/DLPM/LPD1 |
| To: | Price J, Danni Smith Dominion Nuclear Connecticut |
| Ennis R | |
| References | |
| TAC MB6105 | |
| Download: ML022700103 (7) | |
Text
October 2, 2002 Mr. J. A. Price Site Vice President - Millstone Dominion Nuclear Connecticut, Inc.
c/o Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, ANALYTICAL METHODS USED FOR CORE OPERATING LIMITS REPORT, MILLSTONE POWER STATION, UNIT NO. 2 (TAC NO. MB6105)
Dear Mr. Price:
By letter dated August 7, 2002, you submitted a proposed amendment to the technical specifications (TSs) for Millstone Power Station, Unit No. 2. The proposed amendment would revise TS 6.9.1.8, Core Operating Limits Report, to update the list of documents that describe the analytical methods used to determine the core operating limits.
The U.S. Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure. We request that the additional information be provided within 30 days of receipt of this letter. The 30-day response timeframe was discussed with Mr. Ravi Joshi of your staff on September 17, 2002. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.
Sincerely,
/RA/
Richard B. Ennis, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
Request for Additional Information cc w/encl: See next page
ML022700103 OFFICE PDI-2/PM PDI-2/LA SRXB/SC PDI-2/SC(A)
NAME RStarkey for REnnis MO'Brien FAkstulewicz JAndersen DATE 10-2-02 10/1/02 10/1/02 10/2/02
Millstone Power Station Unit 2 cc:
Ms. L. M. Cuoco Senior Nuclear Counsel Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Charles Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering 12300 Twinbrook Pkwy, Suite 330 Rockville, MD 20852 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Niantic, CT 06357 Mr. W. R. Matthews Vice President and Senior Nuclear Executive - Millstone Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ernest C. Hadley, Esquire P.O. Box 1104 West Falmouth, MA 02574-1104 Mr. P. J. Parulis Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. D. A. Christian Senior Vice President - Nuclear Operations and Chief Nuclear Officer Innsbrook Technical Center - 2SW 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Mr. D. A. Smith Manager - Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870
Millstone Power Station Unit 2 cc:
Mr. G. D. Hicks Director - Nuclear Station Safety and Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. J. A. Price Site Vice President - Millstone c/o Mr. David A. Smith Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. S. E. Scace Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS ANALYTICAL METHODS USED FOR CORE OPERATING LIMITS REPORT MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO 50-336 By letter dated August 7, 2002, Dominion Nuclear Connecticut, Inc. (the licensee) submitted a proposed amendment to the technical specifications (TSs) for Millstone Power Station, Unit No.
2 (MP2). The proposed amendment would revise TS 6.9.1.8, Core Operating Limits Report, to update the list of documents that describe the analytical methods used to determine the core operating limits.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed TS changes. In order for the staff to complete its evaluation, the following additional information is requested:
1)
The submittal dated August 7, 2002, stated that the proposed amendment would update the list of documents in TS 6.9.1.8 to delete the reference to Topical Report EMF-84-093(P)(A), Steamline Break Methodology for PWRs, since Topical Report EMF-2310(P)(A), SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors is the current topical report that is applicable to the Steam Line Break (SLB) methodology.
As discussed in the NRC staff's letter dated May 11, 2001, that transmitted the safety evaluation (SE) for topical report EMF-2310(P) to Framatome ANP, the topical report is acceptable for referencing in license applications to the extent specified, and under the limitations delineated in the report, and in the SE. The conclusions in the SE state that
...a generic topical report describing a code such as S-RELAP5 cannot provide full justification for each specific individual plant application. The individual applicant must still provide justification for the specific application of the code which is expected to include as a minimum, the nodalization, defense of the chosen parameters, any needed sensitivity studies, justification of the conservative nature of the input parameters, and calculated results. In addition, the SE conclusions state that [s]pecific plant applications may still require additional supporting assessment calculations should plant specific features or conditions be outside the range of the generic assessments.
Please provide the information needed to justify your plant-specific application of this methodology for the SLB analysis. Identify if any MP2 features or conditions are outside the range of the generic assessment.
2)
The submittal dated August 7, 2002, stated that the proposed amendment would update the list of documents in TS 6.9.1.8 to add a reference to topical report EMF-92-153(P)(A) and Supplement 1, HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel.
As discussed in the NRC staff's SE dated December 28, 1993, Topical Report EMF 153(P), is acceptable for referencing in license applications subject to the following restrictions:
(1)
The HTP (high thermal performance) critical heat flux correlation is applicable to fuels whose design characteristics fall within the correlation database in Table 2.
(2)
The application of the HTP correlation for departure from nucleate boiling analysis is restricted to the operating conditions given in Table 1.
TABLE 1 Range of Coolant Conditions Spanned by the HTP Correlation Variable Minimum Value Maximum Value Pressure (psia) 1775 2425 Local Mass Flux (Mlb/hr/ft2) 0.936 3.573 Inlet Enthalpy (Btu/lb) 382.3 649.9 Local Quality
-0.125 0.358 TABLE 2 Nominal Range of Fuel Design Parameters in HTP Correlation Database Parameter Value Fuel Rod Diameter, in.
0.360 - 0.440 Fuel Rod Pitch, in.
0.496 - 0.580 Axial Spacer Span, in.
10.5 - 26.2 Hydraulic Diameter, in.
0.4571 - 0.5334 Heated Length, ft.
8.0 - 14.0 Please specify how each of the restrictions is met for MP2.
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