ML090430134

Response to Request for Additional Information in Regard to Proposed Technical Specification (TS) Amendment TS 3.3.1, Reactor Trip System (RTS) Instrumentation

ML090430134
Person / Time
Site:	Catawba
Issue date:	02/05/2009
From:	Morris J R Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML090430134 (9)

Text

Duke JAMES R. MORRIS, VICE PRESIDENT rEnergy Duke Energy Carolinas, LLC Carolinas Catawba Nuclear Station 4800 Concord Road CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax February 5, 2009 U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555

Subject:

Duke Energy Carolinas, LLC (Duke)Catawba Nuclear Station, Unit 2 Docket Number 50-414 Proposed Technical Specification (TS) Amendment TS 3.3.1, Reactor Trip System (RTS) Instrumentation

Reference:

Letter from Duke to NRC, same subject, dated January 20, 2009 The reference letter proposed a one-time exigent limited duration extension of TS Surveillance Requirement (SR) 3.3.1.4 Frequency.

SR 3.3.1.4 is a Trip Actuating Device Operational Test (TADOT) of the reactor trip breakers (RTBs) and reactor trip bypass breakers.

On December 30, 2008, the SR Frequency was revised by Catawba Amendments 247/240 to 62 days on a staggered test basis. The reference letter explains the issue associated with Train 2A reactor trip bypass breaker cubicle cell switch contacts as the reason for-proposing the one-time extension.

On February 2 and 3, 2009, telephone conference calls were held among Duke and NRC representatives.

Based on the results of these conference calls, Duke is providing information regarding the RTB and reactor trip bypass breaker configuration and the overall process associated with the testing of the RTBs. Duke is also providing a revised TS page incorporating the proposed SR Frequency extension directly into SR 3.3.1.4, as opposed to a facility operating license condition.

This information is contained in the attachment to this letter.The conclusions of the reference letter's regulatory and environmental analyses are not affected by this amendment request supplement.

There are no regulatory commitments associated with this amendment request supplement.

Pursuant to 10 CFR 50.91, a copy of this amendment request supplement is being sent to the appropriate State of South Carolina official.Should you have any questions concerning this information, please call R. D. Hart at (803) 701-3622 or L. J. Rudy at (803) 701-3084.-Aco/www.duke-energy.com rn&

U. S. Nuclear Regulatory Commission February 5, 2009 Page 2 of 5 Very truly yours, James R. Morris LJR/s Attachment U. S. Nuclear Regulatory Commission February 5, 2009 Page 3 of 5 James R. Morris affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.

Jam s .Morris, Vice President Subscribed and sworn to me: Date My commission expires: SEAL Dae -1 1 z Date U. S. Nuclear Regulatory Commission February 5, 2009 Page 4 of 5 xc (with attachment):

L. A. Reyes, Region II Administrator U. S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 J. H. Thompson, Project Manager (CNS)U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8G9A Rockville, MD 20852-2738 A. T. Sabisch, Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Station S. E. Jenkins, Section Manager Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 U. S. Nuclear Regulatory Commission February 5, 2009 Page 5 of 5 bxc (with attachment):

J. R. Morris (CNO1VP)J. W. Pitesa (CNO1SM)T. M. Hamilton (CNO ISA)R. D. Hart (CNO1RC)L. J. Rudy (CNO1RC)A. F. Driver (CNO1RC)R. L. Gill, Jr. (EC05P)K. L. Ashe (MGOIRC)NCMPA-1 NCEMC PMPA Document Control File 801.01 RGC File ELL-EC050 ATTACHMENT RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION The figure below represents a simplified diagram of the configuration of the reactor trip breakers, reactor trip bypass breakers, motor-generator (MG) sets, and control rod drive mechanisms (CRDMs).Reactor Trip Switchgear RTA RTB MG SETS -*-* CRDM BYA BYB Legend used in this figure: RTA = Reactor Trip Breaker Train A RTB = Reactor Trip Breaker Train B BYA = Reactor Trip Bypass Breaker Train A BYB = Reactor Trip Bypass Breaker Train B The summary text below describes the sequence associated with testing the reactor trip breakers (Train A is described as an example).All Catawba reactor trip breakers and bypass breakers are Westinghouse Type DS-416 metal clad breakers.

Each breaker has auxiliary switches mounted on the breaker frame.Contacts from these switches indicate the breaker open/closed status. Each trip breaker and bypass breaker cubicle has a Westinghouse Type W2 cell switch mounted in the rear of the breaker cubicle. The spring return cell switch is actuated when the breaker is 1 racked to the CONNECT position.

Contact with the rear frame of the breaker moves the cell switch lever as the breaker moves to the CONNECT position.There are three operational positions for reactor trip breakers and bypass breakers: " DISCONNECT

-no electrical connections and cell switch is not actuated.* TEST -power connections are open, control connections are made, cell switch is not actuated.* CONNECT -power connections are made, control connections are made, cell switch is actuated.At various stages of testing, the proper status of breaker auxiliary switch contacts and cubicle cell switch contacts are verified by electrical measurements.

Only one bypass breaker is allowed to be racked to the CONNECT position.

If both bypass breakers are racked to the CONNECT position and CLOSED, a reactor trip occurs. Following is a simplified summary of the breaker operations through the testing sequence.* Rack Train A Bypass Breaker (BYA) to TEST position* Close Train A Bypass Breaker (BYA)* Manually trip Train A Bypass Breaker (BYA)* Rack Train A Bypass Breaker (BYA) to CONNECT position* Close Train A Bypass Breaker (BYA)* Rack Train B Bypass Breaker (BYB) to TEST position* Close Train B Bypass Breaker (BYB)* Perform Train A Under Voltage Trip Test, Train A Reactor Trip Breaker (RTA)and Train B Bypass Breaker (BYB) should trip* Close Train A Reactor Trip Breaker (RTA)* Perform Shunt Trip Test, Train A Reactor Trip Breaker (RTA) should trip* Close Train A Reactor Trip Breaker (RTA)* Rack Train B Bypass Breaker (BYB) to DISCONNECT position* Verify that Train A Reactor Trip Breaker (RTA) is CLOSED* Open Train A Bypass Breaker (BYA)* Rack Train A Bypass Breaker (BYA) to DISCONNECT position 2 RTS Instrumentation

3.3.1 SURVEILLANCE

REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 ---------------------

NOTE -----------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.Perform TADOT. 62 days on a STAGGERED TEST BASIS*SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.1.6 ---------------------

NOTE-----------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 75% RTP.Calibrate excore channels to agree with incore detector 92 EFPD measurements.

SR 3.3.1.7 -----------------------

NOTE -----------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.Perform COT. 184 days (continued)

• The SR 3.3.1.4 Frequency of "62 days on a STAGGERED TEST BASIS" as it applies to Unit 2 Train 2A and Train 2B reactor trip breaker testing may be extended on a one-time basis to March 10, 2009 at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, upon which Unit 2 shall be in Mode 3 with reactor trip breakers open for the End of Cycle 16 Refueling Outage. Upon entry into Mode 3 with reactor trip breakers open for this refueling outage, this extension shall expire. The provisions of SR 3.0.2 are not applicable to this extension.

Catawba Units 1 and 2 3.3.1-10 Amendment Nos.