ML041460462

From kanterella
Revision as of 19:16, 17 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Technical Specification Bases Changes
ML041460462
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 05/17/2004
From: Jamil D
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041460462 (6)


Text

Duke,\ D.M. JAMIL

.. ItPowere Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CN01 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax May 17, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of 10CFR 50.59.

Any questions regarding this information should be directed to L. J. Rudy, Regulatory Compliance, at (803) 831-3084.

I certify that I am a duly authorized officer of Duke Energy Corporation and that the information contained herein accurately represents changes made to the Technical Specification Bases since the previews submittal.

Attachment 0DO www.duke-energy.com

U.S. Nuclear Regulatory Commission May 17, 2004 Page 2 xc: L. A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II S. E. Peters, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, Mail Stop 0-8-G9 E. G. Guthrie Senior Resident Inspector Catawba Nuclear Station

IP Duke DUKE ENERGY CORPORATION vEnergye Catawba Nuclear Station 4800 Concord Rd.

York, SC 29745 May 17, 2004 Re: Catawba Nuclear Station Technical Specifications (TS) Manual Please replace the corresponding pages in your copy of the Catawba Technical Specifications Manual as follows:

REMOVE THESE PAGES INSERT THESE PAGES List of Effective Pages Page 23 Page 23 Tab 3.5.2 Bases B 3.5.2 B 3.5.2-8 B 3.5.2 B 3.5.2-8 If you have any questions concerning the contents of this Technical Specification update, contact Jill Ferguson at (803) 831-3938.

L e Keller Manager, Regulatory Compliance www.duke -energy.com

Page Number Amendment Revision Date B 3.5.2-2 Revision 0 9/30/98 B 3.5.2-3 Revision 1 10/02/00 B 3.5.2-4 Revision 0 9/30/98 B 3.5.2-5 Revision 0 9/30/98 B 3.5.2-6 Revision 0 9/30/98 B 3.5.2-7 Revision 0 9/30/98 B 3.5.2-8 Revision 1 5/17/04 B 3.5.2-9 Revision 1 2/26/99 B 3.5.2-10 Revision 0 9/30/98 B 3.5.3-1 Revision 0 9/30/98 B 3.5.3-2 Revision 0 9/30/98 B 3.5.3-3 Revision 0 9/30/98 B 3.5.4-1 Revision 0 9/30/98 B 3.5.4-2 Revision 0 9/30/98 B 3.5.4-3 Revision I 4/26/00 B 3.5.4-4 Revision 1 4/26/00 B 3.5.4-5 Revision 1 4/26/00 B 3.5.5-1 Revision 0 9/30/98 B 3.5.5-2 Revision 0 9/30/98 B 3.5.5-3 Revision 0 9/30/98 B 3.5.5-4 Revision 0 9/30/98 B 3.6.1-1 Revision 1 7/31/01 B 3.6.1-2 Revision 1 7/31/01 B 3.6.1-3 Revision 1 7/31/01 B 3.6.1-4 Revision 1 7/31/01 B 3.6.1-5 Revision 1 7/31/01 B 3.6.2-1 Revision 0 9/30/98 B 3.6.2-2 Revision 1 7/31/01 B 3.6.2-3 Revision 1 7/31/01 B 3.6.2-4 Revision 1 7/31/01 B 3.6.2-5 Revision 1 7/31/01 B 3.6.2-6 Revision 1 7/31/01 Catawba Units 1 and 2 Page 23 4/17/04

ECCS - Operating B 3.52 BASES ACTIONS (continued)

An event accompanied by a loss of offsite power and the failure of an EDG can disable one ECCS train until power is restored. A reliability analysis (Ref. 6) has shown that the impact of having one full ECCS train inoperable is sufficiently small to justify continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Reference 7 describes situations in which one component, such as an RHR crossover valve, can disable both ECCS trains. With one or more component(s) inoperable such that 100% of the flow equivalent to a single OPERABLE ECCS train is not available, the facility is in a condition outside the accident analysis. Therefore, LCO 3.0.3 must be immediately entered.

B.1 and 8.2 If the inoperable trains cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.5.2.1 REQUIREMENTS Verification of proper valve position ensures that the flow path from the ECCS pumps to the RCS is maintained. Misalignment of these valves could render both ECCS trains inoperable. Securing these valves using the power disconnect switches in the correct position ensures that they cannot change position as a result of an active failure or be inadvertently misaligned. These valves are of the type, described in Reference 7, that can disable the function of both ECCS trains and invalidate the accident analyses. A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered reasonable in view of other administrative controls that will ensure a mispositioned valve is unlikely.

SR 3.5.2.2 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these were verified to be in the correct position prior to locking, sealing, Catawba Units 1 and 2 B 3.5.2-7 Revision No. 0

ECCS - Operating B 3.5.2 BASES SURVEILLANCE REQUIREMENTS (continued) or securing. A valve that receives an actuation signal is allowed to be in a nonaccident position provided the valve will automatically reposition within the proper stroke time. This Surveillance does not require any testing or valve manipulation. Rather, it involves verification that those valves capable of being mispositioned are in the correct position. The 31 day Frequency is appropriate because the valves are operated under administrative control.

This Frequency has been shown to be acceptable through operating experience.

SR 3.5.2.3 With the exception of the operating centrifugal charging pump, the ECCS pumps are normally in a standby, nonoperating mode. As such, flow path piping has the potential to develop voids and pockets of entrained gases.

ECCS piping is verified to be water filled by venting to remove gas from accessible locations susceptible to gas accumulation. Alternative means may be used to verify water filled conditions (e.g., ultrasonic testing or high point sight glass observation). Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly, injecting its full capacity into the RCS upon demand.

This will also prevent water hammer, pump cavitation, and pumping of noncondensible gas (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an SI signal or during shutdown cooling. The 31 day Frequency takes into consideration the gradual nature of gas accumulation in the ECCS piping and the procedural controls governing system operation.

SR 3.5.2.4 Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by Section Xi of the ASME Code. This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve. This verifies both that the measured performance is within an acceptable tolerance of the original pump baseline performance and that the performance at the test flow is greater than or equal to the performance assumed in the plant safety analysis. SRs are specified in the Inservice Testing Program, which encompasses Section Xl of the ASME Code. Section Xl of the ASME Code provides the activities and Frequencies necessary to satisfy the requirements.

Catawba Units 1 and 2 B 3.5.2-8 Revision No. 1