ML030560015

Units, 1 and 2, Licensing Amendments 256 & 233 Shutdown Cooling

ML030560015
Person / Time
Site:	Calvert Cliffs
Issue date:	02/25/2003
From:	Tam P NRC/NRR/DLPM/LPD1
To:	Katz P Calvert Cliffs
Tam P NRR/415-1451
References
TAC MB6412, TAC MB6413
Download: ML030560015 (14)

Text

February 25, 2003 Mr. P. E. Katz, 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: SHUTDOWN COOLING (TAC NOS. MB6412 AND MB6413)

Dear Mr. Katz:

The Commission has issued the enclosed Amendment No. 256 to Renewed Facility Operating License No. DPR-53 and Amendment No. 233 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 Technical Specifications in response to your application transmitted by letter dated September 20, 2002.

These amendments adopt the generic changes approved by Technical Specification Task Force (TSTF) change travelers TSTF-349, Revision 1, and TSTF-361, Revision 2, for NUREG-1430, Revision 1, Standard Technical Specifications, Babcock and Wilcox Plants, dated April 1995, and incorporated into NUREG-1430, Revision 2, dated June 2001. Specifically, Section 3.9.5, Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level, is revised to add two notes to allow operational changes in the shutdown cooling system.

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/

Peter S. Tam, 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. 256 to DPR-53

2. Amendment No. 233 to DPR-69

3. Safety Evaluation cc w/encls: See next page

February 25, 2003 Mr. P. E. Katz, 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: SHUTDOWN COOLING (TAC NOS. MB6412 AND MB6413)

Dear Mr. Katz:

The Commission has issued the enclosed Amendment No. 256 to Renewed Facility Operating License No. DPR-53 and Amendment No. 233 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 Technical Specifications in response to your application transmitted by letter dated September 20, 2002.

These amendments adopt the generic changes approved by Technical Specification Task Force (TSTF) change travelers TSTF-349, Revision 1, and TSTF-361, Revision 2, for NUREG-1430, Revision 1, Standard Technical Specifications, Babcock and Wilcox Plants, dated April 1995, and incorporated into NUREG-1430, Revision 2, dated June 2001. Specifically, Section 3.9.5, Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level, is revised to add two notes to allow operational changes in the shutdown cooling system.

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/

Peter S. Tam, 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. 256 to DPR-53

2. Amendment No. 233 to DPR-69

3. Safety Evaluation cc w/encls: See next page C:\ORPCheckout\FileNET\ML030560015.wpd Accession Number: ML030560015 *See previous concurrence OFFICE PDI-1/PM PDI-1/LA RORP/SC* OGC* PDI-1/SC NAME PTam SLittle RDennig** AHodgdon RLaufer DATE 2/24/03 2/23/03 1/8/03 1/27/03 2/24/03 OFFICIAL RECORD COPY

• • SE transmitted by memo of 01/08/03

DATED: February 25, 2003 AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 CALVERT CLIFFS UNIT 1 AMENDMENT NO. 233 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS UNIT 2 PUBLIC PDI-1 R/F RLaufer SLittle DSkay OGC GHill (2)

WBeckner TTjader ACRS BPlatchek, 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. 256 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 September 20, 2002, 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, 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. 256, 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 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: February 25, 2003

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. 233 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 September 20, 2002, 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, 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. 233, 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/

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: February 25, 2003

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 233 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of 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 3.9.5-1 3.9.5-1 3.9.5-2 3.9.5-2 3.9.5-3 3.9.5-3

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 233 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 September 20, 2002, 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 adopt the generic TS changes approved by Technical Specification Task Force (TSTF) change travelers TSTF-349, Revision 1, and TSTF-361, Revision 2, for NUREG-1430, Revision 1, Standard Technical Specifications, Babcock and Wilcox Plants, dated April 1995, and incorporated into NUREG-1430, Revision 2, dated June 2001. Specifically, these proposed changes would revise TS Section 3.9.5, Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level, for Units 1 and 2 to add two notes to allow operational changes in the SDC system to support operations and testing.

TS Section 3.9.5 currently requires that two SDC loops be operable and one be in operation whenever the water level is lower than 23 feet above the irradiated fuel in the reactor vessel.

The two proposed notes would: (1) allow SDC pumps to be de-energized for up to 15 minutes when switching from one train to another; and, (2) allow one SDC loop to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other loop is operable and in operation.

In addition, the licensee stated that Section 3.9.5 Bases will be revised to incorporate the changes associated with change travelers TSTF-349, Revision 1, and TSTF-361, Revision 2.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires that TSs be included in nuclear power plant operating licenses. In Title 10 of the Code of Federal Regulations, Part 50, Section 36 (10 CFR 50.36), the Nuclear Regulatory Commission (NRC, or Commission) established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. On February 6, 1987, the Commission issued an Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, setting forth

criteria for use in determining the content of TSs. During the period 1989 to 1992, utility groups and the NRC staff developed improved Standard Technical Specifications (STS). On July 22, 1993, the Commission issued its Final Policy Statement, which described the safety benefits of the improved STS, and encouraged licensees to use the improved STS as a basis for plant-specific license amendments, and for complete conversions to plant-specific improved TSs.

The Calvert Cliffs units converted to the improved STS in 1998.

The industry and the NRC staff have worked to refine the improved STS, and many generic changes have been developed. These approved generic changes have improved the adoption process for the STS plants for which the changes apply. Generic changes to the STS NUREGs are proposed to the NRC by Nuclear Energy Institute TSTF. After NRC approval, these TSTF changes, such as TSTF-349, Revision 1, and TSTF-361, Revision 2, are made available for adoption by plants.

3.0 TECHNICAL EVALUATION

The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment, which are described in the licensees September 20, 2002, application. The evaluation below supports 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 Commissions 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.

The SDC System is used to remove core decay heat and reactor coolant sensible heat during unit cooldown and cold shutdown, and to provide adequate mixing of borated coolant.

Currently, Section 3.9.5 requires two SDC loops to be operable and one in operation when a unit is in Mode 6 with <23 feet of water above the top of irradiated fuel assemblies in the reactor vessel. The licensee proposed to add two notes to allow operational changes in the SDC system to support operations and testing. The two proposed notes would: (1) allow SDC pumps to be de-energized for up to 15 minutes when switching from one train to another; and, (2) allow one SDC loop to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other loop is operable and in operation.

The first proposed change would allow both SDC pumps to be de-energized for no more than 15 minutes in order to switch from one pump to another. This is a short period of time to be without coolant flow through the reactor core. There are three restrictions to entering this condition: (1) the core outlet temperature must be maintained more than 10 degrees below saturation temperature, to ensure that bulk boiling does not occur; (2) no operations are permitted that would reduce boron concentration, so that the Updated Final Safety Analysis Report (UFSAR) analysis is applicable; and (3) no further draining of the reactor coolant system (RCS) is permitted while switching pumps. These restrictions will ensure that the SDC system will continue to adequately remove heat from the RCS, even with both pumps de-energized for a short period of time.

The second proposed change would allow one of the SDC loops to be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance testing, provided the other SDC loop is operable and operating.

The loss of one loop for a limited time will reduce the heat removal capability of the system.

Therefore, plant configuration and activities need to be carefully considered before entering this

condition. Consideration must be given to such factors as: time to bulk boiling in the core, potential RCS draining evolutions, and the capability to inject borated water into the core if needed.

The NRC staff notes that both of these proposed changes are consistent with allowances that are currently in TS Section 3.4.8, RSC - Loops Mode 5, Loops Not Filled, which is consistent with the plant condition allowed by TS Section 3.9.5.

Based on the above evaluations, the NRC staff agrees that the SDC loops and pumps can be removed from service, as proposed by the licensee, for a limited amount of time with operational restrictions as described above. Under such conditions, the UFSAR safety analysis assumptions will remain applicable. The approval of these proposed changes is consistent with the guidance of TSTF-349, Revision 1, and TSTF-361, Revision 2. Therefore, the proposed changes are 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 66007). 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: T. R. Tjader Date: February 25, 2003

Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2 cc:

President Kristen A. Burger, Esquire Calvert County Board of Maryland Peoples Counsel Commissioners 6 St. Paul Centre 175 Main Street Suite 2102 Prince Frederick, MD 20678 Baltimore, MD 21202-1631 James Petro, Esquire Patricia T. Birnie, Esquire Counsel Co-Director Constellation Power Source Maryland Safe Energy Coalition 111 Market Street P.O. Box 33111 Baltimore, MD 21202 Baltimore, MD 21218 Jay E. Silberg, Esquire Mr. Loren F. Donatell Shaw, Pittman, Potts, and Trowbridge NRC Technical Training Center 2300 N Street, NW 5700 Brainerd Road Washington, DC 20037 Chattanooga, TN 37411-4017 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