ML020330002
ML020330002 | |
Person / Time | |
---|---|
Site: | Calvert Cliffs ![]() |
Issue date: | 02/26/2002 |
From: | Skay D NRC/NRR/DLPM/LPD1 |
To: | Cruse C Calvert Cliffs |
Skay D | |
References | |
TAC MB3442, TAC MB3443 | |
Download: ML020330002 (17) | |
Text
February 26, 2002 Mr. Charles H. Cruse Vice President - Nuclear Energy Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
AMENDMENT RE: REANALYSIS OF LOSS OF FEEDWATER EVENT (TAC NOS. MB3442 AND MB3443)
Dear Mr. Cruse:
The Commission has issued the enclosed Amendment No. 248 to Renewed Facility Operating License No. DPR-53 and Amendment No. 224 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2. The amendments were issued in response to your application transmitted by letter dated November 19, 2001.
The amendments authorize revisions to the CCNPP Updated Final Safety Analysis Report to incorporate revisions to the loss of feedwater flow analysis. These changes require Nuclear Regulatory Commission approval pursuant to 10 CFR 50.59.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA by PTam for DSkay/
Donna Skay, Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 248 to DPR-53
- 2. Amendment No. 224 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page
February 26, 2002 Mr. Charles H. Cruse Vice President - Nuclear Energy Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
AMENDMENT RE: REANALYSIS OF LOSS OF FEEDWATER EVENT (TAC NOS. MB3442 AND MB3443)
Dear Mr. Cruse:
The Commission has issued the enclosed Amendment No. 248 to Renewed Facility Operating License No. DPR-53 and Amendment No. 224 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2. The amendments were issued in response to your application transmitted by letter dated November 19, 2001.
The amendments authorize revisions to the CCNPP Updated Final Safety Analysis Report to incorporate revisions to the loss of feedwater flow analysis. These changes require Nuclear Regulatory Commission approval pursuant to 10 CFR 50.59.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA by PTam for DSkay/
Donna Skay, Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 248 to DPR-53
- 2. Amendment No. 224 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page Accession Number: ML020330002
- input provided by safety evaluation dated 01/25/02 incorporated with no significant changes.
OFFICE PDI-1/PM PDI-1/LA BC:SRXB PDI-1/ASC OGC NAME DSkay SLittle JWermiel*
JMunday ANicosia for JMoore DATE 2/7/02 2/7/02 01/25/02 2/25/02 2/15/02 OFFICIAL RECORD COPY
DATED: February 26, 2002 AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 CALVERT CLIFFS UNIT 1 AMENDMENT NO. 224 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS UNIT 2 DISTRIBUTION:
PUBLIC PDI-1 R/F EAdensam JMunday SLittle DSkay OGC GHill (4)
WBeckner ACRS BPlatchek, RI KDesai cc: Plant Service list
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2 cc:
President Calvert County Board of Commissioners 175 Main Street Prince Frederick, MD 20678 James Petro, Esquire Counsel Constellation Power Source 111 Market Street Baltimore, MD 21202 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge 2300 N Street, NW Washington, DC 20037 Mark Geckle Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Joseph H. Walter, Chief Engineer Public Service Commission of Maryland Engineering Division 6 St. Paul Centre Baltimore, MD 21202-6806 Kristen A. Burger, Esquire Maryland People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631 Patricia T. Birnie, Esquire Co-Director Maryland Safe Energy Coalition P.O. Box 33111 Baltimore, MD 21218 Mr. Loren F. Donatell NRC Technical Training Center 5700 Brainerd Road Chattanooga, TN 37411-4017
CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 Renewed License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated November 19, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by revising paragraph 2.C.3 of Renewed Facility Operating License No. DPR-53 to read as follows:
(3)
Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 248, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions 3.
The license is also amended by addition of a new condition to Appendix C to read:
This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.
4.
This license amendment is effective as of the date of its issuance and shall be implemented in conformance with the scheduling requirements specified in 10 CFR 50.71e.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Joel Munday, Acting Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Appendix C Date of Issuance: February 26, 2002
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following page of Appendix C with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page Page 4 Page 4 Amendment No.
Additional Conditions Implementation Date 246 This amendment requires the licensee to Next update of the incorporate in the Updated Final Safety UFSAR Analysis Report (UFSAR) changes associated with the aircraft hazards analysis which was evaluated by the staff in the Safety Evaluation dated August 29, 2001.
248 This amendment requires the licensee to Next update of the incorporate in the Updated Final Safety Analysis UFSAR Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.
Amendment No. 248
CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 224 Renewed License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated November 19, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by revising paragraph 2.C.3 of Renewed Facility Operating License No. DPR-69 to read as follows:
(3)
Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 224, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Additional Conditions 3.
The license is also amended by addition of a new condition to Appendix C to read:
This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.
4.
This license amendment is effective as of the date of its issuance and shall be implemented in conformance with the scheduling requirements specified in 10 CFR 50.71e.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Joel Munday, Acting Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Appendix C Date of Issuance: February 26, 2002
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 224 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following page of Appendix C with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page Page 4 Page 4 Amendment No.
Additional Conditions Implementation Date 221 This amendment requires the licensee to Next update of the incorporate in the Updated Final Safety UFSAR Analysis Report (UFSAR) changes associated with the aircraft hazards analysis which was evaluated by the staff in the Safety Evaluation dated August 29, 2001.
224 This amendment requires the licensee to Next update of the incorporate in the Updated Final Safety Analysis UFSAR Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.
Amendment No. 224
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 224 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated November 19, 2001, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted a request to Renewed Facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2. These amendments authorize changes to the CCNPP Updated Final Safety Analysis Report (UFSAR) to incorporate revisions to the loss of feedwater (LOFW) analysis. These changes require Nuclear Regulatory Commission (NRC) approval pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Part 50.59.
2.0 BACKGROUND
An LOFW event is defined as a reduction in feedwater flow to the steam generator (SG) without a corresponding reduction in steam flow from the SG. The closure of the feedwater regulating valves, the loss of condensate or feedwater pumps, or a pipe break in the condensate or feedwater systems during steady-state operation would result in an LOFW event. The LOFW analysis is performed to evaluate reactor coolant system (RCS) pressure, secondary system pressure, and the depletion of SG inventory following such an event. For each scenario, the initial conditions, input parameters, and assumptions are selected to maximize the parameter of concern.
During a recent fire protection inspection, some non-conservative assumptions were discovered in the licensees current LOFW analysis. The assumptions in question are: (1) the use of normal steady-state conditions to calculate inventory versus level during LOFW conditions, (2) treatment of SG blowdown, (3) the single-failure treatment of the auxiliary feedwater system (AFW), and (4) sludge deposition in the SGs.
3.0 EVALUATION The licensee revised the LOFW analysis and proposed modifications to correct the non-conservative assumptions as follows:
(1)
Calculation of inventory vs. level - the inventory left in the SGs for a given low-level trip setpoint for the revised analysis is less than the amount previously assumed. This also leads to a delay in the time of trip since more inventory must be depleted before the setpoint would be reached. This change impacts both the peak secondary pressure analysis and inventory analysis.
(2)
Treatment of SG blowdown - The licensee will install a modification to isolate SG blowdown upon receipt of an auxliary feedwater actuation system (AFAS) signal to resolve this non-conservative assumption. This will prevent further SG inventory reduction in the event that an LOFW event were to occur. Prior to isolation of blowdown, the licensee used the computer code CESEC which is approved by the staff (SER dated February 14, 1984) to model SG blowdown flow. This change impacts the inventory analysis only.
(3)
The single-failure treatment of auxiliary feedwater system - The LOFW analysis assumes the worst single active failure within the AFW system. This failure is determined to be failure of the motor-driven AFW pump to deliver flow. An operator action is credited at 10 minutes to increase AFW flow from the steam-driven AFW pump. The operator action is consistent with their licensing basis Emergency Operating Procedures to ensure that the actions would occur in a time frame consistent with the analytical assumptions. Operators would have adequate indications to respond with the correct actions within the allotted time frame. This change impacts the inventory analysis only since the peak pressure analyses do not credit this system.
(4)
Sludge deposition in the SGs - In the current analysis, the sludge deposited in the SGs during normal operation is not accounted for when determining the inventory of water remaining in the SGs. The reanalysis considered sludge deposition in the inventory analysis. This issue has a small effect and although it affects only the current SGs, this will also account for any buildup of sludge in the replacement SGs. The impact in liquid inventory is minimal. It will only impact the inventory analysis.
The licensee performed an LOFW analysis for three distinct, separate scenarios: peak RCS pressure, peak secondary system pressure, and maximum depletion of SG inventory. Below are the results of the staffs review of these analyses:
Peak Pressure Analyses - Reactor Coolant System (RCS)
The initial conditions and inputs used to analyze the LOFW event are listed in Table 1 of the licensees November 19, 2001, letter. These inputs are designed to maximize peak pressures at 100 percent power with no inoperable main steam safety valves (MSSVs). The licensee included appropriate uncertainties for all values. Parametric cases were run on several parameters to determine the worst set of conditions. Power-operated relief valves, atmospheric dump valves, and turbine bypass valves were assumed to be unavailable, as this would provide primary and secondary pressure relief. For the peak pressure events, SG blowdown was assumed to be isolated prior to the event in order to delay the low-level trip. The worst case RCS pressure analysis assumed to be loss of AC power. The pressurizer pressure trip was credited in the analysis. The revised assumption regarding single-failure of the AFW system did not impact this scenario since the pressure analyses does not credit this system.
Using these assumptions, the licensee calculated the maximum RCS pressure to be 2620 psia which is below 110 percent of RCS design pressure, 2750 psia. The reactor protective system (RPS) and the pressurizer safety valves prevent the RCS from exceeding 110 percent of RCS design pressure.
Peak Pressure Analyses - Secondary System The peak secondary pressure scenario assumed 100-percent power with no inoperable MSSVs. This event credits either the high pressurizer pressure trip or the SG low-level trip.
The licensee calculated maximum SG pressure to be 1107 psia, including downcomer liquid head, which is below the 110 percent of SG design pressure limit of 1116.5 psia.
Steam Generator Inventory Depletion Analysis The most limiting initial conditions and inputs for this analysis are presented in Table 4 of the licensees November 19, 2001, submittal. The licensee included appropriate uncertainties for all values. Parametric cases were run on several parameters to determine the worst set of conditions. The worst case is with no loss of AC power. A change in the acceptance criteria from the current UFSAR analysis has been made for the inventory analysis portion only. The new acceptance criteria will be to demonstrate that the existing SG inventory, in combination with the low-level trip setpoint, auxiliary feedwater actuation signal setpoint, and AFW flow, is sufficient to prevent exceeding the RCS and SG design pressure limits and the specified acceptable fuel design limits (SAFDLs) for the departure from nucleate boiling ratio and linear heat rate. The actions of the RPS, engineered safety feature actuation system, MSSVs, pressurizer safety valves, and the AFW system prevent exceeding design pressures and SAFDLs. The LOFW event is an increasing pressure event and, therefore, the departure from nucleate boiling ratio of 1.21 is not limiting for this event. The LOFW event also results in a small power increase; however, the linear heat rate limit of 22kW/ft is not challenged. This is a heat-up transient and is most limiting at the beginning of the cycle. Therefore, extended fuel burn-up has no adverse impact on the event. The radiological consequences of this event are bounded by the loss of AC power event, which remains within 10 CFR Part 100 limits.
Conclusion The NRC staff has reviewed the information submitted by the licensee and concludes that the submitted analyses demonstrate that 110 percent of RCS and SG design pressures are not exceeded and SAFDLs are protected. The revised LOFW analysis used conservative assumptions and demonstrated acceptable results which are consistent with Standard Review Plan Section 15.2.7 acceptance criteria. Therefore, the staff finds this LOFW event reanalysis acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Maryland State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 925). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K. Desai Date: February 26, 2002