ML051790208
| ML051790208 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/16/2005 |
| From: | Jamil D Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML051790208 (8) | |
Text
Duke D.M. JAMIL WPower.
Vice President Duke Power Catawba Nuclear Station 4800 Concord Road / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax June 16, 2005 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 1OCPR 50.59.
Any questions regarding this information should be directed to Larry 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 previous submittal.
Dhiaa M. Jamil Attachment Catawba Nudear Station20th Anniersary www.dukepower.com 1985 -2005
U.S. Nuclear Regulatory Commission June 16, 2005 Page 2 xc:
W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 S. E. Peters (addressee only)
NRC Project Manager (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, SC 20555-0001 E. F. Guthrie Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission Catawba Nuclear Station
ftDuke L Power.
A DWA, E£C'p.G y
Duke Power Catawba Nuclear Station 4800 Concord Road York, SC 29745 (803) 831-3000 June 16, 2005 Re:
Catawba Nuclear Station Technical Specifications Bases Please replace the corresponding pages in your copy of the Catawba Technical Specifications Manual as follows:
REMOVE THESE PAGES INSERT THESE PAGES Page 16 List of Effective Pages Tab 3.3.1 Page 16 B 3.3.1 B 3.3.1-48 B 3.3.1 B 3.3.1-48 If you have any questions concerning the contents of this Technical Specification update, contact Jill Ferguson at (803) 831-3938.
Lee Keller Manager, Regulatory Compliance
Page Number B 3.3.1-19 B 3.3.1-20 B 3.3.1-21 B 3.3.1-22 B 3.3.1-23 B 3.3.1-24 B 3.3.1-25 B 3.3.1-26 B 3.3.1-27 B 3.3.1-28 B 3.3.1-29 B 3.3.1-30 B 3.3.1-31 B 3.3.1-32 B 3.3.1-33 B 3.3.1-34 B 3.3.1-35 B 3.3.1-36 B 3.3.1-37 B 3.3.1-38 B 3.3.1-39 B 3.3.1-40 B 3.3.1-41 B 3.3.1-42 B 3.3.1-43 B 3.3.1-44 B 3.3.1-45 B 3.3.1-46 B 3.3.1-47 B 3.3.1-48 B 3.3.1-49 B 3.3.1-50 Amendment Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision I Revision 1 Revision 0 Revision 0 Revision 0 Revision 1 Revision 1 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 0 Revision 2 Revision 2 Revision 1 Revision 0 Revision 1 Revision 1 Revision Date 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 8/13/99 8/13/99 9/30/98 9/30/98 9/30/98 7/29/03 7/29/03 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 9/30/98 6/13/05 6113/05 6/13/05 9/30/98 11/24/04 4/22/02 I
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Catawba Units I and 2 Page 16 6113/05
RTS Instrumentation B 3.3.1 BASES SURVEILLANCE REQUIREMENTS (continued) condition, thus preventing inadvertent actuation. Through the semiautomatic tester, all possible logic combinations, with and without applicable permissives, are tested for each protection function. The Frequency of every 31 days on a STAGGERED TEST BASIS is adequate. It is based on industry operating experience, considering instrument reliability and operating history data.
SR 3.3.1.6 SR 3.3.1.6 is a calibration of the excore channels to the incore channels.
If the measurements do not agree, the excore channels are not declared inoperable but -must be calibrated to agree with the incore detector m'easurements. If the excore channels cannot be adjusted, the channels are declared inoperable. This Surveillance is performed to verify the f(Al) input to the overtemperature AT Function and overpower AT Function.
At Beginning of Cycle (BOC), the excore channels are compared to the incore detector measurements prior to exceeding 75% power. Excore detectors are adjusted as necessary. This low power surveillance satisfies the initial performance of SR 3.3.1.6 with subsequent surveillances conducted at least every 92 EFPD.
At BOC, after reaching full power steady.state conditions, additional incore and excore measurements are taken at various Al conditions to determine the MJ factors. The Mj factors are normally only determined at BOC,' but they may be changed at other points in the fuel cycle if the relationship between excore and incore measurements changes significantly.,.
A Note'modifies SR 3.3.1.6. The Note states that this Surveillance is required o'nly if reactor power is > 75% RTP and that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed
,for completing the first surveillance after reaching 75%.RTP.
The Frequency of 92 EFPD is adeq'uate. It is based on industry
' operating experience, considering instrument reliability and operating history data for instrument drift.
' SR 3.3.1.7 is the performance of a COT every 92 days.
A COT Is performed on each required channel to ensure the channel will Catawba Units 1 and 2
-_.. -B 3.3.145 '
Revision No. 2
I II RTS Instrumentation B 3.3.1 BASES SURVEILLANCE REQUIREMENTS (continued) perform the intended Function.
The tested portion of the loop must trip within the Allowable Values specified in Table 3.3.1-1.
The setpoint shall be left set consistent with the assumptions of the setpoint methodology.
SR 3.3.1.7 is modified by a Note that provides a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> delay in the requirement to perform this Surv'eillanc~e for source range instrumentation when entering MODE 3 from'MODE 2. This Note allows a normal shutdown to proceed'withoit'a delay for testing in MODE 2 and for a short time in MODE 3 until the RTBs areopen and SR 3.3.1.7 is no longer required to be performed. If the &nit is to be in MODE 3 with the RTBs closed for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> this Surveillance must be completed within 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.
- The Frequency of 92 days is justified in Reference 7.
SR 3.3.1.8 SR 3.3.1.8 is the performance of a COT asidescribed in SR 3.3.1.7, except it' is modified by'a Note that this test shall' inciude verification that the P-6,'during the Intermediate Range COT, and P-10, during the Power Range COT, interlocks are in their required state for'the existing unit condition. The verification is-performed by visual observation of the permissive status light in the unit control room. -The Frequency is modified by a Note that allows this surveillance to be satisfied if it has been performed within 92 days of the Frequerncies prior to reactor startup and four hours after reducing power below P-I0 and P-6. The Frequency of "prior tQ startup" 'ensures this surveillance is performed prior to critical operations and applies to the source, intermediate and power range low instrument channels. The Fr'equency of "4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reducing power below P-lOi" (applicable't6 intermediate and power range low channels) and "4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reducing power below P-6" (applicable to source range channels) allows a normal shutdown to be completed and the unit removed from the MODE of Applicability for this surveillance without a delay to perform the testing required by this surveillance. The Frequency of every 92 days thereafter applies if the plant remains in the MODE of Applicability after the initial performances of prior to reactor startup and four hours after reducing power below P-10 or P-6. The MODE of
-Applicability for this surveillance is < P-1 for the power range low and intermediate range channels and < P-6 for the source range channels.
Catawba Units 1 and 2 B 3.3.146 Revision No. 2
s }
4i
'wA B RTS Instrumentation B 3.3.1 BASES SURVEILLANCE REQUIREMENTS (continued)
Once the unit is in MODE 3, this surveillance-is no longer required. If power is to be maintained < P-1 0 or < P-6 for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then the testing required by this surveillance must be performed prior to the expiration of the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limit. Four hours is a reasonable time to complete the required testing or place the unit in a MODE where this surveillance is no longer required. This test ensures that the NIS source, intermediate, and power range low channels are OPERABLE prior to taking the reactor critical and after reducing power into the applicable MODE (< P-10 or < P-6) for periods > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SR :3.3.1.9 SR 3.3.1.9 is the performance of a TADOT and is performed every 92 days, as justified in Reference 7.
The SR is modified by a Note that excludes verification of setpoints from the TADOT. Since this SR applies to RCP undervoltage and underfrequency relays, setpoint verification requires elaborate bench calibration and is accomplished during the CHANNEL CALIBRATION.
SR 3.3.1.10 A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test venrfies that the channel responds to a measured parameter within the necessary range and accuracy.
CHANNEL CALIBRATIONS Miust be performed consistent with the Iassumptions of the'setpoint methodology.
The Frequency of 18 months is based on the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology.
-SR 3.3.1.10 is modified by a Note stating that this test shall include verification that the time constants are adjusted to the prescribed values where applicable. The applicable time constants are shown in Table 3.3.1-1.,
Catawba Units I and 2 B 3.3.1-47 Revision No. I
RTS Instrumentation B 3.3.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.1.11 SR 3.3.1.1 1 is the performance of a CHANNEl CALIBRATION, as described ih'SR 3.3.1.10, every '18 months. This SR is modified by two notes. Note 1 states that neutron detectors are excluded from the CHANNEL CALIBRATION. The CHANNEL CALIBRATION for the power range neutron'detecitors consists of a normalization of the detectors based on a power calorimetric 'and flux'map'performred above 15% RTP.
The CHANNEL CALIBRATION for the source range and intermediate range neutron detectors consists of obtaining the high voltage detector plateau and discriminator curves for source range, and the high voltage detector plateau for intermediate range, evaluating those curves, and comparing the curves to the manufacturers data.: Note 2 states that this Surveillance is not required for theNIS power range detectors for entry into MODE 2 or 1,' and is not'required for the NIS intermediate range detectors for entry into MODE 2, because the unit must be in at least MODE 2 to perform the test for the intermediate range detectors and MODE 1 for the 'power range detectors. The 18 month Frequency is bas6d one th1e need to perforr this Surveillance under the conditions that apply durinig 'a plant outage and the 'potential for an unplanned transient if the Surveillance were performed with the'reactor at power. Operating experience has shown these components usually pass the Surveillance when performed on the 18 month Frequency.,
SR 3.3.1.12 SR 3.3.1.12 is the performance of a CHANNEL CALIBRATION, as described in SR 3.3.1.10, every 18 months.
The Frequency is justified by the assumption of an,18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.
SR '3.3.1.13 SR 3.3.1.13 is the performance of a COT of RTS interlocks every 18 months:
The Frequency is based on the known reliability of the Interlocks and the multichannel redundancy available, and has been shown to be acceptable through operating experience.
Catawba Units 1 and 2 B 3.3.1-48.
. Revision No. 0 -, -,,