ML051390039
ML051390039 | |
Person / Time | |
---|---|
Site: | Calvert Cliffs ![]() |
Issue date: | 06/15/2005 |
From: | Richard Guzman NRC/NRR/DLPM/LPD1 |
To: | Vanderheyden G Calvert Cliffs |
Guzman R, NRR/DLPM 415-1030 | |
References | |
TAC MC4017, TAC MC4018 | |
Download: ML051390039 (15) | |
Text
June 15, 2005 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 -
ISSUANCE OF AMENDMENTS RE: LICENSE CONDITION 2.E, FIRE PROTECTION (TAC NOS. MC4017 AND MC4018)
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 273 to Renewed Facility Operating License No. DPR-53 and Amendment No. 250 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Operating License in response to your application transmitted by letter dated July 13, 2004, as supplemented on April 21, 2005.
These amendments revised License Condition 2.E of each unit's operating license by replacing the current wording with wording from Generic Letter (GL) 86-10, "Implementation of Fire Protection Requirements."
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/
Richard V. Guzman, 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. 273 to DPR-53
- 2. Amendment No. 250 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page
Mr. George Vanderheyden, Vice President Calvert Cliffs Nuclear Power Plant, Inc. June 15, 2005 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: LICENSE CONDITION 2.E, FIRE PROTECTION (TAC NOS. MC4017 AND MC4018)
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 273 to Renewed Facility Operating License No. DPR-53 and Amendment No. 250 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Operating License in response to your application transmitted by letter dated July 13, 2004, as supplemented on April 21, 2005.
These amendments revised License Condition 2.E of each unit's operating license by replacing the current wording with wording from Generic Letter (GL) 86-10, "Implementation of Fire Protection Requirements."
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/
Richard V. Guzman, 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. 273 to DPR-53
- 2. Amendment No. 250 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page Distribution PUBLIC PDI-1 R/F R. Laufer S. Little R. Guzman OGC G. Hill (2) T. Boyce R. Galluci P. Hearn S. Weerakkody ACRS J. Trapp, RI
- Provided SE input by memo. No substantive changes made.
Accession Number: ML051390039 OFFICE PDI-1/PM PDI-1/LA SPLB/SC IROB/SC OGC PDI-1/SC NAME RGuzman SLittle SWeerakkody* TBoyce JHull RLaufer DATE 6/6/05 6/6/05 5/10/05 6/10/05 6/13/05 6/15/05 OFFICIAL RECORD COPY
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. 273 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 July 13, 2004, as revised by letter on April 21, 2005, 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, License Condition 2.E of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:
E. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979 and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire..
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
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
Attachment:
Changes to the Technical Specifications Date of Issuance: June 15, 2005
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317 Replace the following page of the Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.
Remove Page Insert Page 4 4
- c. Identification of process sampling points;
- d. Procedure for recording and management of data;
- e. Procedures defining corrective actions for off control point chemistry conditions; and
- f. A procedure identifying the authority responsible fo the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.
D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 12, 2004, as supplemented by the letter dated October 21, 2004.
E. The licensee shall implement and maintain in effect all provisions of the l approved fire protection program as described in the Updated Final Safety l Analysis Report for the facility and as approved in the SER dated September 14, l 1979 and Supplements dated October 2, 1980; March 18, 1982; and l September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; l March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following l provision: The licensee may make changes to the approved fire protection l program without prior approval of the Commission only if those changes would l not adversely affect the ability to achieve and maintain safe shutdown in the l event of a fire. l F. At the time of the next scheduled update to the FSAR required pursuant to 10 CFR 50.71(e)(4) following the issuance of this renewed license, the licensee shall update the FSAR to include the FSAR supplement submitted pursuant to 10 CFR 54.21(d), as amended and supplemented by the program descriptions in Appendix E to the Safety Evaluation Report, NUREG-1705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
G. Any future actions listed in Appendix E to the Safety Evaluation Report, NUREG-1705, shall be included in the FSAR. The licensee shall complete these actions by July 31, 2014, except for the volumetric inspections of the control element drive mechanisms, which must be completed no later than 2029 for Unit 1 (Appendix E, Item 65).
Amendment No. 237, 273 Revised by letters dated 10/28/04, 12/21/04
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. 250 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 July 13, 2004, as revised by letter on April 21, 2005, 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, License Condition 2.E of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:
E. The Calvert Cliffs Nuclear Power Plant, Inc. shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979, and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The Calvert Cliffs Nuclear Power Plant, Inc. may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
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
Attachment:
Changes to the Technical Specifications Date of Issuance: June 15, 2005
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following page of the Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change.
Remove Page Insert Page 4 4
(5) Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 211 are hereby incorporated into this license. Calvert Cliffs Nuclear Power Plant, Inc., shall operate the facility in accordance with the Additional Conditions.
(6) Secondary Water Chemistry Monitoring Program The Calvert Cliffs Nuclear Power Plant, Inc. shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
- a. Identification of a sampling schedule for the critical parameters and control points for these parameters;
- b. Identification of the procedures used to quantify parameters that are critical to control points;;
- c. Identification of process sampling points;
- d. Procedure for recording and management of data;
- e. Procedures defining corrective actions for off control point chemistry conditions; and
- f. A procedure identifying the authority responsible fo the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.
D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 12, 2004, as supplemented by letter dated October 21, 2004.
E. The Calvert Cliffs Nuclear Power Plant, Inc. shall implement and maintain in l effect all provisions of the approved fire protection program as described in the l Updated Final Safety Analysis Report for the facility and as approved in the SER l dated September 14, 1979, and Supplements dated October 2, 1980; March 18, l 1982; and September 27, 1982; and Exemptions dated August 16, 1982; l April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to l the following provision: The Calvert Cliffs Nuclear Power Plant, Inc. may make l changes to the approved fire protection program without prior approval of the l Commission only if those changes would not adversely affect the ability to l achieve and maintain safe shutdown in the event of a fire. l Amendment No. 211, 250 Revised by letters dated 10/28/04, 12/21/04
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 250 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 July 13, 2004 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042010022), the Calvert Cliffs Nuclear Power Plant, Inc. (CCNPPI or the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Operating License. The requested change would revise License Condition 2.E of each unit's operating license by replacing the current wording with wording from Generic Letter (GL) 86-10, "Implementation of Fire Protection Requirements." The supplement dated April 21, 2005 (Accession No. ML051180017), provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on December 7, 2004 (69 FR 70715).
In a previous application for amendment dated December 4, 1996 (Accession No.
9612120185), the licensee proposed to convert the TSs to the Improved Standard Technical Specifications. Specific in that application was the proposal to relocate the fire protection requirements from the TSs to licensee-controlled documents in accordance with GL 86-10 and 88-12, "Removal of Fire Protection Requirements from Technical Specifications." All the changes specified by these GLs, except the change regarding use of standard wording in the license condition, were requested by the licensee and were approved by the Nuclear Regulatory Commission (NRC) staff as Amendment Nos. 227 and 201, respectively, for the units. The current application attempts to correct such oversight.
2.0 REGULATORY EVALUATION
One of the principal objectives of the commercial nuclear power plant fire protection program is to ensure that the risk of fire-induced radiological hazards to the public, environment, and plant personnel is minimized. To meet this objective, Title 10 of the Code of Federal Regulations (10 CFR) 50.48, Fire protection, requires each operating nuclear power plant to have the means to limit fire damage to structures, systems, or components (SSCs) important to safety so
that the capability to shutdown the plant safely is ensured. The objective of the plant safe-shutdown is to assure that at least one means of achieving and maintaining safe-shutdown capability is available during and after any postulated fire.
Section 50.48(a) of 10 CFR requires that each operating nuclear power plant have a fire protection plan which satisfies General Design Criterion (GDC) 3, "Fire Protection," of Appendix A to 10 CFR Part 50. The approved fire protection plan is the plan required to satisfy 10 CFR 50.48(a). Specific fire protection features deemed necessary to ensure this capability are delineated in Appendix R to 10 CFR Part 50. For areas of the nuclear power plant where fire protection features cannot ensure safe-shutdown capability,Section II.D of Appendix R to 10 CFR Part 50 requires that an alternative shutdown capability be provided. Specific design criteria and performance goals of the alternative shutdown capability are contained in Section III.G.3 and III.L of Appendix R.
GDC 3 requires that SSCs important to safety be designed and located to minimize the probability and effect of fire and explosions. It further requires that the fire-fighting systems shall be designed to assure that their rupture or inadvertent operation does not significantly impair the capability of these SSCs.
The licensees may make changes to their approved fire protection program (FPP) without prior staff approval only if those changes would not adversely affect the ability to achieve and maintain safe-shutdown in the event of a fire. This is based on the licensee having the standard fire protection license condition that was published in GL 86-10, Implementation of Fire Protection Requirements. All changes to the FPP must ensure that compliance is maintained with the requirements of 10 CFR 50.48(a).
3.0 TECHNICAL EVALUATION
The current wording of License Condition 2.E states, for Unit 1 and 2, respectively:
The licensee is required to implement and maintain the administrative controls identified in Section 6 of the NRCs Fire Protection Safety Evaluation on the facility dated September 14, 1979.
The Calvert Cliffs Nuclear Power Plant, Inc., is required to implement and maintain the administrative controls identified in Section 6 of the NRCs Fire Protection Safety Evaluation on the facility dated September 14, 1979.
The licensee proposed to revise this wording to substantially follow the guidance of GL 86-10.
Subsequently, by letter dated April 21, 2005, the licensee modified the proposed wording to be in accordance with the standard license condition language set forth in GL 86-10, as follows:
[For Unit 1] The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979 and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following
provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
[For Unit 2] The Calvert Cliffs Nuclear Power Plant, Inc. shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14, 1979 and Supplements dated October 2, 1980; March 18, 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999; subject to the following provision: The Calvert Cliffs Nuclear Power Plant, Inc. may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Unit 1 was licensed to operate on July 31, 1974, and Unit 2 was licensed to operate on November 30, 1976. NRC regulations at 10 CFR 50.48(b) backfit certain requirements on plants licensed to operate prior to January 1, 1979. Specifically, 10 CFR 50.48(b)(2) specifies that all pre-1979 plants must satisfy the applicable requirements of Appendix R to 10 CFR Part 50, including Sections III.G, III.J, and III.O. Pre-1979 plants, including Calvert Cliffs, were reviewed under an NRC guidance document identified as Branch Technical Position APCSB 9.5-1, Appendix A. The NRC staff evaluated the Calvert Cliffs FPP in a series of documents: safety evaluation report (SER) dated September 14, 1979, and supplements dated October 2, 1980 (Accession No. 8010290363); March 18, 1982 (Accession No. 8203300243);
and September 27, 1982 (Accession No. 8210120134); and Exemptions dated August 16, 1982 (Accession No. 8209230588); April 21, 1983 (Accession No. 8305060077); March 15, 1984 (Accession No. 8404090077); August 22, 1990 (Accession No. 9008270043); and April 7, 1999 (Accession No. 9904120208). The proposed change to the License Condition 2.E would reference all these documents, as compared to only one document being referenced in the current wording (i.e., the September 14, 1979 SER).
In summary, the proposed amendments to the Calvert Cliffs Unit Nos. 1 and 2 operating licenses do not involve any changes to the units' FPP, but only involve changes to the wording in the standard license conditions to correspond with the wording from GL 86-10. As such, no technical evaluation was required or performed, only a review of the reworded license conditions to ensure strict compliance with GL 86-10. In addition, the referenced SER, supplements and exemptions were verified to ensure their citations are accurate in the reworded standard license conditions.
On the basis of its review and evaluation of the information provided in the application for amendment and supplement, the NRC staff concludes that the licensee has provided a thorough description of the proposed change to the wording of the standard license conditions for the FPP at CCNPP 1 & 2. The NRC staff, therefore, finds the licensees proposed wording change to License Condition 2.E for each Calvert Cliffs unit 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 facility components 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 70715). 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: R. Gallucci Date: June 15, 2005
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc:
President Patricia T. Birnie, Esquire Calvert County Board of Co-Director Commissioners Maryland Safe Energy Coalition 175 Main Street P.O. Box 33111 Prince Frederick, MD 20678 Baltimore, MD 21218 Carey Fleming, Esquire Mr. Loren F. Donatell Sr. Counsel - Nuclear Generation NRC Technical Training Center Constellation Generation Group, LLC 5700 Brainerd Road 750 East Pratt Street, 17th floor Chattanooga, TN 37411-4017 Baltimore, MD 21202 Lou Larragoite 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. R. I. McLean, Administrator Radioecology Environ Impact Prog Department of Natural Resources Nuclear Evaluations 580 Taylor Avenue Tawes State Office Building 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 People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631