ML083180198
| ML083180198 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/26/2009 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Spina J Calvert Cliffs |
| Pickett D | |
| References | |
| TAC MD9549, TAC MD9550 | |
| Download: ML083180198 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Janrnry 2(-" :zrry:l Mr. James A. Spina, 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: REMOVAL OF THE MAIN STEAM ISOLATION VALVE CLOSURE TIME FROM TECHNICAL SPECIFICATIONS (TAC NOS. MD9549 AND MD9550)
Dear Mr. Spina:
The Commission has issued the enclosed Amendment No. 289 to Renewed Facility Operating License No. DPR-53 and Amendment No. 265 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, respectively. These amendments consist of changes to Technical Specification (TS) 3.7.2, "Main Steam Isolation Valves (MSIVs)," in response to your application dated August 28,2008.
These amendments revise TS Surveillance Requirement 3.7.2.1 by replacing the MSIV closure time with the phrase "within limits." The MSIV closure time is relocated to the licensee controlled document that is referenced in the TS Bases. The changes are consistent with the Nuclear Regulatory Commission approved Technical Specification Task Force (TSTF)-491, Revision 2, "Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications. "
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
~Vf~
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 289 to DPR-53
- 2. Amendment No. 265 to DPR-69
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CALVERT CUFFS NUCLEAR POWER PLANT, INC.
DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 289 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 August 28,2008, 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:
-2
- 2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 289, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Mark G. Kowal, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: J:rr1l8!Y 26, 2fIf)
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 265 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 August 28, 2008, 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:
-2
- 2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 265, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Mark G. Kowal, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office ot Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance: JarIlEry >>, 2flR
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 289 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following page of the Facility Operating License 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 3 3 Replace the following page of the Appendix A Technical Specifications 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 3.7.2-2 3.7.2-2
-3 rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 289, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Speci'fications.
(a) For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. OPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.
(3) Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 267 are hereby incorporated into this license. Calvert Cliffs Nuclear Power Plant, Inc. shall operate the facility in accordance with the Additional Conditions.
(4) 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. Identi'fication 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; Amendment No. 289
-3 C. This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now and hereafter applicable; and is subject to the additional conditions specified and incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reactor steady-state core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 265 are hereby incorporated into this license.
The licensee shall operate the facility in accordnace with the Technical Specifications.
(a) For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.
(3) Less Than Four Pump Operation The licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.
(4) Environmental Monitoring Program If harmful effects or evidence of irreversible damage are detected by the biological monitoring program, hydrological monitoring program, and the radiological monitoring program specified in the Appendix B Technical Specifications, the licensee will provide to the staff a detailed analysis of the problem and a program of remedial action to be taken to eliminate or significantly reduce the detrimental effects or damage.
Amendment No. 265
MSIVs 3.7.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition C AND not met.
D.2 Be in MODE 4. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.7.2.1 Verify closure time of each MSIV is within In accordance limits. with the Inservice Testing Program CALVERT CLIFFS - UNIT 1 3.7.2-2 Amendment No. 289 CALVERT CLIFFS - UNIT 2 Amendment No. 265
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 289 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 265 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 August 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082410667), the Calvert Cliffs Nuclear Power Plant, Inc.
(the licensee) proposed changes to Technical Specification (TS) 3.7.2, "Main Steam Isolation Valves (MSIVs)," for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP). The proposed changes will revise TS Surveillance Requirement (SR) 3.7.2.1 by replacing the criterion of "< 5.2 seconds" with the phrase "within limits." The MSIV valve closure time will be relocated to a licensee controlled document (LCD) referenced in the TS Bases.
The requested changes are a partial adoption of Technical Specification Task Force Traveler No. 491 (TSTF-491), Revision 2, "Removal of Main Steam and Feedwater Valve Isolation Times." The proposed changes do not adopt the portion of TSTF-491 regarding the main feedwater isolation valves because valve closure times for the main feedwater valves are already incorporated into the Inservice Testing (1ST) Program in TS SR 3.7.15.1. TSTF-491, Revision 2, was announced for availability in the Federal Register on December 29, 2006, as part of the consolidated line item improvement process (CLlIP).
2.0 REGULATORY EVALUATION
Section 182(a) of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public. The Commission's regulatory requirements related to the content of the TSs are contained in 10 CFR Section 50.36. That regulation requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1)); (2) limiting conditions for operation (50.36(c)(2)); (3) SRs (50.36(c)(3)); (4) design features (50.36(c)(4)); and (5) administrative controls (50.36(c)(5)).
-2 In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. This amendment deals with the second class of changes.
In determining the acceptability of revising standard TS (STS) 3.7.2, the Nuclear Regulatory Commission (NRC) staff used the accumulation of generically approved guidance in NUREG-1432, "Standard Technical Specifications, Revision 3, Combustion Engineering Plants,"
dated June, 2004.
Licensees may revise the TSs to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered),
(2) the change is more restrictive than the licensee's current requirement, or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes. Nomenclature specific to the Westinghouse Plants is used in the following Technical Evaluation.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the justification for the proposed TSTF as described in the industry submittal dated September 13, 2005 (ADAMS Accession No. ML052590343). The licensee stated in their application dated August 28, 2008, that the justifications presented in the TSTF-491 proposal and the model SE prepared by the NRC staff are applicable to CCNPP for the incorporation of the changes to CCNPP TS 3.7.2. The detailed evaluation below will support the conclusion 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
3.1 Main Steam Isolation Valves (MSIV)
One MSIV is located in each main steam line outside of the containment. Closing the MSIVs isolates each steam generator from the others and isolates the turbine, steam bypass system and other auxiliary steam supplies from the steam generator.
By isolating the steam flow from the secondary side of the steam generator the MSIVs prevent over cooling the reactor core following a high energy line break (HELB). By preventing core overcooling, the MSIVs protect the reactor core from being damaged.
TSTF-491 is proposing to relocate the required closure times for the MSIVs to the LCD that is referenced in the Bases. Changes to the LCDs are subject to the 10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate assurance that prior staff review and approval will be requested by the licensee for changes to the Bases or LCD requirements with the potential to affect the safe operation of the plant. Furthermore, the MSIVs are subject to periodic testing
-3 and acceptance criteria in accordance with the 1ST Program. Compliance with the 1ST Program is required by Section 5.5.7 of the STS and 10 CFR 50.55a. The 1ST Program includes specific reference value baseline operating times for valves that are not subject to arbitrary changes.
10 CFR 50.36 requires the inclusion of the periodic testing of the MSIVs in the SRs not the actual closure time of the valves. TSTF-491 change maintains the periodic testing requirements for MSIVs in accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and 1ST Program, the NRC staff concludes that relocating the MSIV closure time to the LCD as referenced in the Bases is 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 the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The staff has determined that the amendment involves 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 amendment involves no significant hazards consideration and there has been no public comment on such finding published in the Federal Register October 7, 2008 (73 FR 58671).
Accordingly, the amendment meets 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 amendment.
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 Contributors: Douglas Pickett Jennifer Gall Date: Jaru3ry 26, 2JYA
January 26, 2009 Mr. James A. Spina, 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: REMOVAL OF THE MAIN STEAM ISOLATION VALVE CLOSURE TIME FROM TECHNICAL SPECIFICATIONS (TAC NOS. MD9549 AND MD9550)
Dear Mr. Spina:
The Commission has issued the enclosed Amendment No. 289 to Renewed Facility Operating License No. DPR-53 and Amendment No. 265 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, respectively. These amendments consist of changes to Technical Specification (TS) 3.7.2, "Main Steam Isolation Valves (MSIVs)," in response to your application dated August 28,2008.
These amendments revise TS Surveillance Requirement 3.7.2.1 by replacing the MSIV closure time with the phrase "within limits." The MSIV closure time is relocated to the licensee controlled document that is referenced in the TS Bases. The changes are consistent with the Nuclear Regulatory Commission approved Technical Specification Task Force (TSTF)-491, Revision 2, "Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications."
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice .
. Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 289 to DPR-53
- 2. Amendment No. 265 to DPR-69
- 3. Safety Evaluation cc w/encls: Distribution via Listserv Amendment No'.. ML083180198 OFFICE LPLI-1/GE LPLI-1/ LPLI-1/LA ITSB/BC OGC LPLI-1/BC NAME JGall DPickett SLittie RElliott BHams Mark Kowal DATE 12/16/08 12/16/08 12/11/08 1/05/09 1/08/09 1/26/09 OFFICIAL RECORD COpy
DATED: .Jaruary 26, 21XJl AMENDMENT NO. 289 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 CALVERT CLIFFS UNIT 1 AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS UNIT 2 PUBLIC LPLI-1 R1F M. Kowal RidsNrrDorlLpi-1 S. Little RidsNrrLASLittle D. Pickett RidsNrrPMDPickett OGC RidsOgcMaiICenter ACRS RidsAcrsAcnwMailCenter R. Elliott RidsNrrDirsltsb MHamm,ITSB G. Dentel, RI cc: Distribution via ListServ