ML032510905
| ML032510905 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/26/2003 |
| From: | Hartz L Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 03-313B, NLOS/ETS | |
| Download: ML032510905 (8) | |
Text
VIRGcrnqA ELECTRIC AND POWER COMEAXY:
R-ICHxOwD,VVIRGINoA 23261 August 26, 2003 U. S. Nuclear Regulatory Commission Serial No.
03-313B Attention: Document Control Desk NLOSIETS Washington, D.C. 20555 Docket Nos. 50-338/339 License Nos. NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS I AND 2 REVISED REALISTIC LARGE BREAK LOCA (RLBLOCA) RESULTS REFLECTING ASSESSMENT OF VESSEL-FLUID VOLUME INPUT ERROR FOR USE OF FRAMATOME ANP ADVANCED MARK-BW FUEL PROPOSED -TECHNICAL SPECIFICATIONS CHANGES AND EXEMPTION REQUEST FOR USE OF FRAMATOME ANP ADVANCED MARK-BW FUEL In letters dated May 6,2003 (Serial No.03-313), and July 18, 2003 (Serial No.03-407),
Dominion submitted results of the Realistic Large Break LOCA (RLBLOCA) analyses for Advanced Mark-BW -fuel in North Anna Units 2 and 1, respectively. -The RLBLOCA information was presented in the form of supplements to the evaluation report provided in our March 28, 2002 letter (specifically, report Section 7.2). In subsequent reviews of these results, Framatome ANP has discovered an input error that affects the analyses for North Anna Units 1 and 2. The error involves an incorrect calculation of the fluid volume for the upper plenum and upper head fluid nodes, which is described in further detail in Attachment 1. Summary results for the limiting case from both the Unit 1 and the Unit 2 analyses are also presented in Attachment 1. The calculated changes in the limiting case peak cladding temperature (PCT) results are minimal and are as follows:
Unit 1 (+330F); Unit 2 (no change).- The results in Attachment 1 are provided to supplement the material originally submitted in the letters cited above, and to allow NRC staff to continue their review. It is anticipated that this change will only negligibly impact the ongoing NRC review for use of the Advanced Mark-BW fuel at North Anna.
To support the use of Framatome Advanced Mark-BW fuel in North Anna Unit 2, Cycle 17, we respectfully request the NRC to complete their review and approval of the license amendment and exemptions by: September 30, 2003. We appreciate your consideration of our technical and schedular requests. If you have any questions or require additional information, please contact us.
Very truly yours, Leslie N. Har-Vice President - Nuclear Engineering Commitments made in this letter: None
- AeI
cc:
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 Commissioner Bureau of Radiological Health 1500 East Main Street Suite 240 Richmond, VA 23218 Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station Mr. S. R. Monarque NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 8-H12 Rockville, MD 20852
I SN: 03-313B Docket Nos.: 50-338/339
Subject:
Revised RLBLOCA Results Reflecting Assessment of Vessel Fluid Volume Input Error Use of Framatome ANP Advanced Mark-BW Fuel Proposed TS Change COMMONWEALTH OF VIRGINIA
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COUNTY OF HENRICO
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The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Leslie N. Hartz, who is Vice President - Nuclear Engineering, of Virginia Electric and Power Company. She has affirmed before me that she is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements In the document are true to the best of her knowledge and belief.
Acknowledged before me this 26th day of August, 2003.
My Commission Expires: March 31, 2004.
(JlNotary Public e.
Revised Realistic Large Break LOCA (RLBLOCA) Results Reflecting Assessment Of Vessel Fluid Volume Input Error North Anna Power Station Units 1 and 2 Framatome Fuel Transition Program Technical Specification Change Virginia Electric and Power Company (Dominion)
North Anna Power Station Units 1 and 2
Revised RLBLOCA Analysis - Corrected Reactor Vessel Fluid Volumes This summary provides a description of revised RLBLOCA analyses results for Framatome ANP (FANP) Advanced Mark-BW fuel In North Anna Power Station Units I and 2.
These analyses were revised to correct an error discovered in the prior RLBLOCA analyses submitted -for North Anna Units 1 and 2 (References 1 and 2). The fluid volumes in the reactor vessel (RV) upper plenum and upper head were incorrectly calculated. The region contained additional liquid (approximately 220 ft3) attributable to upper control rod guide tube structures, which are modeled separately from the upper plenum/head region. Hence, the guide tube fluid was double accounted for - incorrectly in the upper plenum/head control volumes and correctly in the guide tube control volumes. The extra liquid volume was removed from the upper plenum/head region and the case sets for both units were rerun (the random number seeds from the original case sets were unchanged). All other input parameters and limits supported by the analyses are identical to those submitted in References 1 and 2. No significant change in results was noted. The criteria of 1 OCFR5O.46(b) are met with ample margins.
NAPS Unit I Large Break LOCA Results; The limiting PCT is 2,025 IF. In the Reference 1 analysis, the limiting PCT was 1 9920F.
The revised case is characterized in Tables 1 and 2. The maximum oxidation (2.5%)
and total oxidation (0.07%) results are reported in Table 2. The plots of key parameters exhibit the same trends as the original analysis. The hot fuel rod results and event times for the limiting PCT case are provided in Tables 2 and 3, respectively. The nominal PCT is 1,5031F.
NAPS Unit 2 Large Break LOCA Results The limiting PCT is 2,0320F, the same as in the Reference 2 analysis. The case is characterized in Tables 4 and 5. The maximum oxidation (3.7%) and total oxidation (0.09%) results are also reported in Table 5. The plots of key parameters exhibit the same trends as the original analysis. The hot fuel rod results and event times for the limiting PCT case are given in Tables 5 and 6, respectively. The nominal PCT is 1,483-F.
Large Break LOCA Conclusions The revised RLBLOCA results reported herein represent minimal changes relative to the results originally submitted in References 1 and 2.
The revised results were obtained using the identical analytical methodology and inputs as in the original analyses, excepting the RV upper plenum/head liquid volume. The revised results meet the acceptance criteria of 1 OCFR50.46(b).
Page 1 of 4
1 References
- 1.
Letter, Eugene S. Grecheck (Virginia Electric and Power Company) to USNRC,
'North Anna Powet Station Units 1 and 2, Realistic Large Break Loss of Coolant Accident (RLBLOCA) Analysis Results for the Proposed Technical Specifications Changes and Exemption Request for Use of Framatome ANP Advanced Mark-BW Fuel," Serial No.03-407, July 18, 2003 [transmits Unit 1 RLBLOCA results]
- 2.
Letter, Leslie N. Hartz (Virginia Electric and Power Company) to USNRC, "North Anna Power Station Units 1 and 2, Realistic Large Break Loss of Coolant Accident (RLBLOCA) Analysis Results for the Proposed Technical Specifications Changes and Exemption Request for Use of Framatome ANP Advanced Mark-BW Fuel," Serial No.03-313, May 6, 2003 [transmits Unit 2 RLBLOCA results]
Page 2 of 4
.~
-I Table 1: Summary of Major Parameters for Limiting NAPS Unit 1 Transient Time (hrs) 5,455 Bumup (MWd/mtU) 11,800 Core Power (MWt) 2,862 Core Peaking (Fo) 2.284 Radial Peak (FAH) 1.65 Local Peaking (R) 1.06 Break Type DEGB Break Size per Side (ft2) 2.45 (-60 %)
Offsite Power Available No Decay Heat Multiplier 0.9412 Table 2: Summary of Results for the NAPS Unit 1 Limiting PCT Case PCT Temperature 2,025 0F Time 70.7 seconds Elevation
-9.6 ft Metal-Water Reaction -____
% Oxidation Maximum 2.5 %
% Total Oxidation 0.07 %
Total Hydrogen 1.15 Ibm Table 3: Calculated Event Times for the NAPS Unit 1 Limiting PCT Case Event Time (sec)
Begin Analysis 0.0 Break Opens 0.0 RCP Trip 0.0 Si ACTUATION SIGNAL Issued 0.8 Start of Broken Loop Accumulator Injection 10 Start of Intact Loop Accumulator Injection 12 End of Bypass 26 Start of HHSI 28 Start of LHSI 28 Beginning of Core Recovery (Beginning of Reflood) 29 Broken Loop Accumulator Empties 40 Intact Loop Accumulators Empty 41, 41 PCT Occurs (2,025 OF) 70.7 Page 3 of 4
Table 4: Summary of Major Parameters for Limiting NAPS Unit 2 Transient Time (hrs)
.601 Bumup (MWd/mtU) 1,200 Core Power (MWt) 2,926 Core Peaking (F0) 2.294 Radial Peak (FAH) 1.65 Local Peaking (Fl) 1.12 Break Type DEGB Break Size per Side (ft2) 3.31 (-80%)
Offsite Power Available Yes Decay Heat Multiplier 0.9899 Table 5: Summary of Results for the NAPS Unit 2 Limiting PCT Case PCT Temperature 2,032 OF Time 70.2 seconds Elevation
-9.6 ft Metal-Water Reaction
% Oxidation Maximumr 3.7 %
% Total Oxidation 0.09 %
Total Hydrogen 1.44 Ibm Table 6: Calculated Event Times for the NAPS Unit 2 Limiting PCT Case Event Time (sec)
Begin Analysis 0.0 Break Opens 0.0 RCP Trip N/A Si ACTUATION SIGNAL Issued 0.7 Start of Broken Loop Accumulator Injection 10 Start of Intact Loop Accumulator Injection 13 Start of HHSI 14 Start of LHSI 14 End of Bypass 25 Beginning of Core Recovery (Beginning of Reflood) 29 Broken Loop Accumulator Empties 38 Intact Loop Accumulators Empty 40,40 PCT Occurs (2,032 F) 70.2 Page 4 of 4