ML020330092
| ML020330092 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/04/2002 |
| From: | Skay D NRC/NRR/DLPM/LPD1 |
| To: | Cruse C Calvert Cliffs |
| Skay D | |
| Shared Package | |
| ML020650303 | List: |
| References | |
| TAC MB2538, TAC MB2539 | |
| Download: ML020330092 (12) | |
Text
March 4, 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 -
AMENDMENTS RE: CONTROL ROOM EMERGENCY VENTILATION SYSTEM AND CONTROL ROOM EMERGENCY TEMPERATURE SYSTEM OPERABILITY DURING FUEL MOVEMENT (TAC NOS. MB2538 AND MB2539)
Dear Mr. Cruse:
The Commission has issued the enclosed Amendment No. 250 to Renewed Facility Operating License No. DPR-53 and Amendment No. 226 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated July 27, 2001.
The amendments modify the conditions and required actions for the control room emergency ventilation system of Technical Specification 3.7.8. Note 2 is added to TS 3.7.8 to specify the control room emergency ventilation system train operability requirements during the movement of irradiated fuel assemblies. The amendments also modify the conditions and required actions for the control room emergency temperature system of TS 3.7.9 to specify operability during the movement of irradiated fuel assemblies.
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. 250 to DPR-53
- 2. Amendment No. 226 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page
Mr. Charles H. Cruse March 4, 2002 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 -
AMENDMENTS RE: CONTROL ROOM EMERGENCY VENTILATION SYSTEM AND CONTROL ROOM EMERGENCY TEMPERATURE SYSTEM OPERABILITY DURING FUEL MOVEMENT (TAC NOS. MB2538 AND MB2539)
Dear Mr. Cruse:
The Commission has issued the enclosed Amendment No. 250 to Renewed Facility Operating License No. DPR-53 and Amendment No. 226 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. This amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated July 27, 2001.
The amendments modify the conditions and required actions for the control room emergency ventilation system of Technical Specification 3.7.8. Note 2 is added to TS 3.7.8 to specify the control room emergency ventilation system train operability requirements during the movement of irradiated fuel assemblies. The amendments also modify the conditions and required actions for the control room emergency temperature system of TS 3.7.9 to specify operability during the movement of irradiated fuel assemblies.
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. 250 to DPR-53
- 2. Amendment No. 226 to DPR-69
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC OGC PDI-1 R/F GHill (4)
EAndensam WBeckner JMunday ACRS SLittle BPlatchek, RI DSkay RGiardina Package: ML020650303 ACCESSION NO.: ML020330092 TSs: ML020640619
- input provided by safety evaluation dated 01/31/02, incorporated with no significant changes.
OFFICE PDI-1/PM PDI-1/LA BC:RTSB PDI-1/ASC OGC NAME DSkay SLittle WBeckner*
JMunday ANicosia for JMoore DATE 2-6-02 2/7/02 01/31/02 2/20/02 2/13/02 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 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. 250 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 27, 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 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.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 250, 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 30 days.
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:
Changes to the Technical Specifications Date of Issuance: March 4, 2002
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. 226 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 27, 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 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.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 226, 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 30 days.
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:
Changes to the Technical Specifications Date of Issuance: March 4, 2002
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 226 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.7.8-1 3.7.8-1 3.7.8-2 3.7.8-2 3.7.8-3 3.7.8-3 3.7.9-1 3.7.9-1 3.7.9-2 3.7.9-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 250 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 226 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 27, 2001, the Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Technical Specifications (TSs). The requested changes would modify TS 3.7.8, Control Room Emergency Ventilation System (CREVS), and TS 3.7.9, Control Room Emergency Temperature System (CRETS) to more accurately reflect the licensing basis for these two systems when irradiated fuel assemblies are being moved.
2.0 BACKGROUND
During the conversion to the Improved Technical Specification (ITS) from 1996 to 1998, the CREVS TS (TS 3.7.8) and CRETS TS (TS 3.7.9) were created from the TS requirements in effect at that time. Previous to the conversion, the TS requirements for both the CREVS and CRETS were contained in one TS and were only required during Modes 1 through 4. However, it was acknowledged that CREVS and CRETS were also needed during a fuel-handling accident (FHA) to provide protection for the control room operators. Thus, the applicability for the CREVS and CRETS was expanded to include movement of irradiated fuel assemblies and appropriate Conditions and Required Actions were developed that recognized the new applicability. However, the staff and the licensee were not able to anticipate how restrictive these new Conditions would prove and that the current Conditions would create a situation that is more restrictive than the licensing basis for the plant. The licensing basis for Calvert Cliffs Units 1 and 2 is that only one train of CREVS and one train of CRETS is required to be OPERABLE during movement of irradiated fuel assemblies.
3.0 EVALUATION The proposed changes to TS 3.7.8 are:
1.
A second limiting condition for operation (LCO) Note is being added to reflect the licensing basis for the FHA.
2.
Condition F was aimed at providing requirements for when the required one CREVS train is inoperable during movement of irradiated fuel assemblies for various conditions. To ensure that Condition F meets the licensing basis, it is being modified by removing the second portion of the Condition which requires that movement of irradiated fuel assemblies be stopped immediately if the required train of CREVS is not OPERABLE for reasons other than Condition B (Toilet area exhaust isolation valve inoperable.)
3.
Condition G addresses the case where both trains of CREVS are inoperable and is being modified by adding the words or during movement of irradiated fuel assemblies to all portions of the Condition and adding Required Action G.2, which would require the suspension of movement of irradiated fuel assemblies, along with the current Required Action G.1, requiring entry into LCO 3.0.3 for the operating Unit.
The proposed changes to TS 3.7.9 are:
1.
The LCO Note is being modified to reflect the licensing basis for the FHA.
2.
Condition C was aimed at providing requirements for when the required one CRETS train is inoperable during movement of irradiated fuel assemblies. To ensure that the TS meets the licensing basis, Condition C is being deleted and Condition D is being modified.
3.
Condition D addresses the case where both trains of CRETS are inoperable. In this case, the movement of irradiated fuel assemblies would need to stop immediately because the operators would not be protected in the case of an FHA.
Condition D is being modified by adding the words or during movement of irradiated fuel assemblies and adding Required Action D.2, which would require the suspension of movement of irradiated fuel assemblies, along with the current Required Action D.1, requiring entry into LCO 3.0.3 for the operating Unit. With the deletion of the current Condition C, Condition D will be re-lettered as Condition C.
The CREVS and CRETS are shared systems providing protection to the common Control Room for both Units 1 and 2.
The CREVS provides automatic airborne radiological protection for the control room operators.
The CREVS is needed to respond to six different analyzed accidents. Five of the accidents that have an evaluated CREVS response are main steam line break, maximum hypothetical accident, steam generator tube rupture, control element assembly ejection event, and seized reactor coolant pump rotor event. The worst-case single active failure of a component of the CREVS, assuming a loss-of-offsite power, does not impair the ability of the system to perform its design function (except for one valve in the shared duct between the Control Room and the emergency recirculation filter trains). Therefore, in Modes 1, 2, 3, and 4, two CREVS trains must be OPERABLE to limit operator exposure during and following a design-basis accident.
The sixth accident the CREVS is credited for is a design basis FHA. The CREVS provides automatically-actuated airborne radiological protection for the control room operators during this event. The design basis FHA does not assume a single failure occurs. Therefore, during movement of irradiated fuel assemblies, only one CREVS train must be OPERABLE to cope with the release from an FHA.
The CRETS is a subsystem that provides temperature control for the Control Room following isolation of the Control Room. The CRETS is a shared system that is supported by the CREVS; since the CREVS must be operating for the CRETS to perform its safety function.
During events that require the Control Room to be isolated, the CRETS is designed to maintain the temperature below the required limit. Thus, the CRETS is needed to respond to the same six analyzed accidents as the CREVS. Therefore, in Modes 1, 2, 3, and 4, two CRETS trains must be OPERABLE and during movement of irradiated fuel assemblies, only one CRETS train must be OPERABLE.
As stated above, the FHA scenario does not require that a single failure be assumed. Thus, only one train of CREVS and CRETS is required when fuel movement is in progress. During the conversion process an attempt was made to address this licensing basis, and the intention was that TS 3.7.8 Condition F and TS 3.7.9 Condition C would only apply to the required one CREVS and CRETS train. However, the LCO Notes and the applicability do not convey the interpretation of the licensing basis, and could be interpreted to require both CREVS and CRETS trains to be OPERABLE during movement of irradiated fuel for various plant operating conditions. During some periods of plant operation, one Unit can be operating in Modes 1, 2, 3, or 4, while the other Unit is in an outage. Or an alternative case is where both Units are in Modes 1, 2, 3, or 4 and movement of irradiated fuel assemblies is underway in the spent fuel pool. It is possible to have different licensing bases apply to each Unit. The proposed changes to the TSs will clarify this and allow each unit to only enter the Condition that applies to that unit.
This would eliminate any possible confusion associated with a common Control Room, with a common redundant CREVS/CRETS, and different operating conditions for each unit.
The NRC staff has reviewed the changes and finds that modified Notes and revised conditions and Required Actions, more accurately reflect the licensing basis for the plant and are, therefore, 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 (66 FR 46475). 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. Giardina Date: March 4, 2002