ML040640795
| ML040640795 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  (DPR-053, DPR-069) |
| Issue date: | 04/05/2004 |
| From: | Vissing G NRC/NRR/DLPM/LPD1 |
| To: | Vanderheyden G Calvert Cliffs |
| Vissing G, NRR/DLPM, 415-1441 | |
| References | |
| TAC MC2183, TAC MC2184 | |
| Download: ML040640795 (12) | |
Text
April 5, 2004 Mr. George Vanderheyden, Vice President 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: REVISION TO THE IMPLEMENTATION DATE FOR COOLDOWN RATES FOR PRESSURE-TEMPERATURE LIMITS (TAC NOS.
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 263 to Renewed Facility Operating License No. DPR-53 and Amendment No. 240 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. The amendments consist of changes to the implementation date of new cooldown rates for pressure-temperature (P-T) limits that were established for Amendment Nos. 261 and 238 for Calvert Cliffs, Unit Nos.
1 and 2, respectively, in response to your application transmitted by letter dated February 25, 2004.
These amendments change the implementation date for the new cooldown rates for P-T limits established by Amendment Nos. 261 and 238 for Calvert Cliffs, Units 1 and 2 from April 7, 2004, to July 1, 2004.
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/
Guy S. Vissing, Senior 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. 263 to DPR-53
- 2. Amendment No. 240 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page
April 5, 2004 Mr. George Vanderheyden, Vice President 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: REVISION TO THE IMPLEMENTATION DATE FOR COOLDOWN RATES FOR PRESSURE-TEMPERATURE LIMITS (TAC NOS.
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 263 to Renewed Facility Operating License No. DPR-53 and Amendment No. 240 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. The amendments consist of changes to the implementation date of new cooldown rates for pressure-temperature (P-T) limits that were established for Amendment Nos. 261 and 238 for Calvert Cliffs, Unit Nos.
1 and 2, respectively, in response to your application transmitted by letter dated February 25, 2004.
These amendments change the implementation date for the new cooldown rates for P-T limits established by Amendment Nos. 261 and 238 for Calvert Cliffs, Units 1 and 2 from April 7, 2004, to July 1, 2004.
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/
Guy S. Vissing, Senior 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. 263 to DPR-53
- 2. Amendment No. 240 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page Accession Number: ML040640795 OFFICE PDI-1/PM PDI-1/LA OGC PDI-1/SC NAME PTam for GVissing SLittle HMcGurren PTam for RLaufer DATE 3/11/04 3/11/04 3/17/04 3/19/04 OFFICIAL RECORD COPY
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 M. Petro, Esquire Counsel Constellation Energy Group, Inc.
750 East Pratt Street, 5th floor 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 Kristen A. Burger, Esquire Maryland Peoples 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
DATED: April 6, 2004 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 CALVERT CLIFFS UNIT 1 AMENDMENT NO. 240 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS UNIT 2 PUBLIC PDI-1 R/F RLaufer SLittle GVissing OGC GHill (2)
TBoyce WBeckner ACRS CBixler, RI cc: Plant Service list
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. 263 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 February 25, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. DPR-53 is amended to extend the implementation date of Amendment No. 261, issued December 9, 2003, to July 1, 2004.
3.
This license amendment is effective as of the date of its issuance, immediately changing the implementation date of Amendment No. 261 to July 1, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by PTam for/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: April 5, 2004
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. 240 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 February 25, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. DPR-69 is amended to extend the implementation date of Amendment No. 238, issued December 9, 2003, to July 1, 2004.
3.
This license amendment is effective as of the date of its issuance, immediately changing the implementation date of Amendment No. 238 to July 1, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: April 5, 2004
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 240 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 February 25, 2004 (Accession No. ML040610678), Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2, licenses. The proposed amendments would change the implementation date for the new cooldown rates for pressure-temperature (P-T) limits established by Amendment Nos. 261 and 238 for Calvert Cliffs, Units 1 and 2, respectively, from 120 days after issuance, to July 1, 2004.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) staff delineated the regulatory evaluation for Amendment Nos. 261 and 238, dated December 9, 2003, in the associated safety evaluation (SE), also dated December 9, 2003. The licensees February 25, 2004, application does not propose to change any of the technical aspects of those amendments; therefore, the regulatory evaluation in the December 9, 2003, SE still stands.
There is no published regulatory requirements or guidance on the duration of the implementation period for amendments. Usually, an amendment imposes an implementation schedule with a deadline falling some time after the date of issuance of the amendment. For Amendment Nos. 261 and 238, the licensee proposed the implementation deadline be 120 days after issuance (see licensees letter dated November 25, 2003). The NRC staff had no basis to differ from this recommendation, and had accordingly imposed an implementation deadline of 120 days. This duration is within range of schedules imposed by amendments issued to CCNPPI and other licensees.
3.0 TECHNICAL EVALUATION
Amendment Nos. 261 and 238 were issued on December 9, 2003. These amendments revised the reactor pressure vessel P-T limit cooldown rates for both Units 1 and 2. These amendments were issued in response to the licensees amendment request dated May 28, 2003, as supplemented on November 25, 2003.
The licensee verbally requested withholding issuance of the amendments until the end of 2003 (as opposed to issuing the amendment on December 1, 2003, as was originally proposed in the application). Such month-long withholding would make the 120-day implementation deadline to fall after the start of the Unit 1 refueling outage. However, despite the licensees verbal request to withhold issuance, the amendments were inadvertently issued by the NRC staff on December 9, 2003, making the 120-day implementation deadline to fall on April 7, 2004 (i.e., at the start of the Unit 1 refueling outage). The licensee found that while the duration for implementation appears to match what the licensee originally requested in its application, the duration covers a calendar period that poses significant logistical problems (e.g., extensive procedural changes, necessary operator training, refueling outage activities). Thus, the licensee determined that it needed to change the implementation date to after the beginning of the refueling outage.
In the May 28, 2003, application, the licensee indicated that the existing reactor pressure vessel P-T limit cooldown rates are non-conservative over the life of the units, but they remain valid through the end of 2004. Therefore, there is no technical issue with implementing the Amendment Nos. 261 and 238 changes until after the 2004 outage. The NRC staff found that the proposed delay of implementation from April 7 to July 1, 2004, is well within the time that the existing cooldown rates remain effective, and is, therefore, acceptable.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION The Commissions regulations in 10 CFR 50.92 state that the Commission may make a final determination that a license amendment involves no significant hazards consideration if operation of the facility, in accordance with the amendment, would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
1.
[I]involve a significant increase in the probability or consequences of an accident previously evaluated; or The proposed amendment extends the implementation period specified in Item 3 of Amendment Nos. 261 and 238 for CCNPP Units 1 and 2 respectively from 120 days to July 1, 2004. Since the existing reactor pressure vessel pressure-temperature limit cooldown rates are valid through the end of 2004, there is no technical or safety issue associated with this request. The proposed amendment is purely administrative.
The request does not involve a change in the operation of the plant and no new accident initiation mechanism is created by the proposed change. The proposed change does not involve a physical alteration of the plant.
Therefore, the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated 2.
[C]reate the possibility of a new or different [kind] of accident from any accident previously evaluated; or The proposed amendment extends the implementation period specified in Item 3 of Amendment Nos. 261 and 238 from 120 days to July 1, 2004. Since the existing reactor pressure vessel pressure-temperature limit cooldown rates are valid through the end of 2004, there is no technical or safety issue associated with this request. The proposed amendment is purely administrative.
This request does not involve a change in the operation of the plant and no new accident initiation mechanism is created by the proposed change. The proposed change does not involve a physical alteration of the plant.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
3.
[I]nvolve a significant reduction in a margin of safety.
The margin of safety is maintained during the period of extended implementation because the existing reactor pressure vessel pressure-temperature limit cooldown rates are valid through to end of 2004.
The proposed amendment extends the implementation period specified in Item 3 of Amendment Nos. 261 and 238 from 120 days to July 1, 2004. Since the existing reactor pressure vessel pressure-temperature limit cooldown rates are valid through the end of 2004, there is no technical or safety issue associated with this request. The proposed amendment is purely administrative.
Therefore, this proposed change does not significantly reduce [a] margin of safety.
Based on the above considerations, the NRC staff concludes that the amendments meet the three criteria of 10 CFR 50.92. Therefore, the NRC staff has made a final determination that the proposed amendments do not involve a significant hazards consideration.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Maryland State official was notified of the proposed issuance of the amendments. The State official had no comments.
6.0 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 (69 FR 10487). 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.
7.0 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 Commissions 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: Peter Tam Date: April 5, 2004