ML020440424
| ML020440424 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/24/2002 |
| From: | Gordon Peterson Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020440424 (11) | |
Text
Duke Power P Duke 4800 Concord Rd.
ADkEwer A Duke Energy Company York, SC 29710 (803) 831-4251 OFFICE (803) 831-3221 FAX grperers@duke-energy. corn Gary R. Peterson Vice President CatawbaNuclear Station January 24, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Proposed Technical Specifications and Bases Amendment 1.1, Definitions, Response Time 3.3.1, Reactor Trip System Instrumentation 3.3.2, Engineered Safety Feature Actuation System Instrumentation
Reference:
Letter to NRC, same subject, dated May 25, 2001 On January 7, 2002, a telephone conference call was held between representatives of Duke Energy Corporation and the NRC concerning the subject reference letter. In the conference call, the NRC requested Duke Energy Corporation to provide information concerning specific systems and components for which response time will no longer be measured, the response times that will be used for these components when actual response time is no longer measured, and the basis for these values. The attached pages to this letter contain the requested information.
No regulatory commitments are being made in this letter or the attached pages.
If you have any questions concerning this information, please call L.J. Rudy at (803) 831-3084.
Very tr y yours, Ga R.eterson LJR/s Attachment (8 pages) e0ý
U.S. Nuclear Regulatory Commission January 24, 2002 Page 2 G.R. Peterson 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.
G.R. Peterson, Vice President Subscribed and sworn to me: cc9 Date Notary 4lic My commission expires:
Date SEAL
U.S. Nuclear Regulatory Commission January 24, 2002 Page 3 xc (with attachment):
L.A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 D.J. Roberts Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station C.P. Patel (addressee only)
NRC Senior Project Manager (CNS)
U.S. Nuclear Regulatory Commission Mail Stop 08-H12 Washington, D.C. 20555-0001 R. Wingard, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A Rl This information has been developed and assembled in response to NRC request in support of approval for the license amendment request submittal dated May 25, 2001.
The Reactor Protection System (RPS) and Engineered Safety Features Actuation System (ESFAS) for Catawba Units 1 and 2 consist of the following:
a) Westinghouse 7300 Process Protection and Control System b) Westinghouse Solid State Protection System (SSPS) c) Westinghouse Nuclear Instrumentation System (NIS) d) Reactor Coolant Pump Monitoring Instrumentation e) Turbine Generator and Feedwater Instrumentation The Failure Modes and Effects Analysis (FMEA) contained in WCAP 14036-P-A Rev. 1, is applicable to the equipment installed at Catawba Units 1 and 2. The analysis is valid for the installed versions of boards and relays.
Where periodic testing for pressure sensors will be replaced by allocated response time, the values to be used will be the most conservative value that is derived via Methods (1, 2, 3) section (9) of WCAP-13632-P-A Rev. 2. Catawba has determined that the most conservative response time values for each specific model of a pressure sensor was yielded by applying Method (1) and rounding up for conservatism.
The established Plant Equipment Database (EDB) revisions (and/or other appropriate administrative controls) will stipulate that pressure sensors (i.e., transmitters and switches) utilizing capillary tubing must be subjected to response time testing after initial installation and following any maintenance or modification activity that could damage the device or capillary system. Currently there are no configurations of this type that are utilized at CNS which will require response time testing.
The established Plant EDB revisions (and/or other appropriate administrative controls) will stipulate that pressure transmitters equipped with variable damping capability, (i.e.,
as utilized in Reactor Trip System or Engineered Safety Features applications) which require periodic response time testing, must be subjected to testing prior to return to service, following any maintenance or modification activity.
Page 1
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A R1 The established Plant EDB revisions (and/or other appropriate administrative controls) will stipulate that following any maintenance or modification activity that may affect the response time of pressure sensors, other than stated above, which require periodic response time testing, must be subjected to testing prior to return to service.
The verification of acceptable performance for the Reactor Protection and Engineered Safety Features Systems within the required 'Function Total Response Time' will be accomplished by a series of sequential and/or overlapping activities, as allowed by the existing CNS Technical Specifications.
- 1. Each Reactor Trip Function verification will be documented as follows:
" Pressure sensor allocated time plus 7300 allocated time plus SSPS allocated time plus Rx Trip Breaker measured time plus stationary gripper release time less than or equal to Allowed Total Response Time
" NIS allocated time plus 7300 allocated time plus SSPS allocated time plus Rx Trip Breaker measured time plus stationary gripper release time less than or equal to Allowed Total Response Time
" NIS allocated time plus SSPS allocated time plus Rx Trip Breaker measured time plus stationary gripper release time less than or equal to Allowed Total Response Time
" Reactor coolant pump Undervoltage/Underfrequency module measured time delay plus SSPS allocated time plus Rx Trip Breaker measured time plus stationary gripper release time less than or equal to Allowed Total Response Time
- 2. Each Engineered Safety Feature Function verification will be documented as follows:
Note: The allocation portion of each function will utilize 1 second of the Allowed Total Response Time. The remaining portion of each function will be measured and verified to be within the Allowed Total Response Time minus 1 second.
Page 2
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A Rl
"* Pressure sensor allocated time plus 7300 allocated time plus SSPS allocated time less than or equal to 1 second, or
"* Pressure sensor allocated time less than or equal to 1 second (this case is for the Auxiliary Feedwater Pump Suction Transfer which does not utilize the SSPS)
Tables 1 & 2 depict Catawba protection channel equipment configuration and assignment of response time allocation values.
Page 3
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A Rl Table 1 - Reactor Trip Function Sensor Sensor 7300 / NIS String 7300 SSPS SSPS Rx Trip Total Req'd Notes 2 & 3 Time Note 4 Time Relays Time Time Time Time Note 11 Note 5 Note 5 Note 6 </=
Pzr Press - Low ITT Barton 763 0.75s NLP + NAL 0.1 s Input 0.02s 0.3s 1.17s 2.0 s Pzr Press - High ITT Barton 763 0.75 s NLP + NAL 0.1 s Input 0.02 s 0.3 s 1.17 s 2.0 s S/G Level - Low Low ITT Barton 764 0.75 s NLP + NAL 0.1 s Input 0.02s 0.3s 1.17s 2.Os RCS Flow - Low Rosemount 1154HP5 0.75 s NLP + NAL 0.1 s Input 0.02 s 0.3 s 1.17 s 2.0 s OPDT (Vary Tavg) RDF 21232 Note 1 NRA + NSA + NSA + NSA + NSA + NAL 0.4 s Input 0.02 s 0.3 s 0.72 s 1.5 s OPDT (Vary DeltaT) RDF 21232 Note I NRA + NSA + NSA + NAL 0.4 s Input 0.02 s 0.3 s 0.72 s 1.5 s OPDT (Vary Flux) Detectors Exempt Note I NIS (ims) + NSA + NCH + NSA + NAL 0.401 s Input 0.02 s 0.3 s 0.721 s 1.5 s Note 10 OTDT (Vary Tavg) RDF 21232 Note 1 NRA + NSA + NSA + NSA + NAL 0.4 s Input 0.02 s 0.3 s 0.72 s 1.5 s
_______ I_____ I___ I___________ I] __ [
__ 1
___ 11 __
RPS Functions Acronyms Pzr - Pressurizer RCS - Reactor Coolant System OPDT - Overpower A Temperature SI - Safety Injection S/G - Steam Generator RCP - Reactor Coolant Pump OTDT - Overtemperature A Temperature NIS - Nuclear Instrumentation System ESFAS - Engineered Safety Features Actuation System Page 4
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A RI Table I - Reactor Trip (cont.)
Function Sensor Sensor 7300 / NIS String 7300 SSPS SSPS Rx Trip Total Req'd Notes 2 & 3 Time Note 4 Time Relays Time Time Time Time Note 11 Note 5 Note 5 Note 6 </=
OTDT (Vary Delta T) RDF 21232 Note 1 NRA + NSA + NSA + NAL 0.4 s Input 0.02 s 0.3 s 0.72 s 1.5 s OTDT (Vary Press) ITT Barton 763 0.75 s NLP + NSA + NSA + NAL 0.4 s Input 0.02 s 0.3 s 1.47 s 1.5 s OTDT (Vary Flux) Detectors Exempt Note I NIS (lms) + NSA + NCH + NSA + NAL 0.401 s Input 0.02 s 0.3 s 0.721 s 1.5 s Note 10 RCP Undervoltage RIS 90634-100 Note 4:1 1 N/A N/A Input 0.02 s 0.3 s 1.27s 1.5s Note 7 RCP Underfrequency RIS 90634-100A Note I N/A N/A Input 0.02 s 0.3 0.52s 0.6Ns SLENote 8 NIS Level - Low Detectors Exempt Note I NIS FMEA (Note 9) 0.065 s Input 0.02 s 0.3 s 0.385 s 0.5 s NIS Level - High Detectors Exempt Note 1 NIS FMEA (Note 9) 0.065 s Input 0.02 s 0.3 s 0.385 s 0.5 s Containment Pressure ESFAS (SI) Input to ITT Barton 386A 0.75 s NLP + NAL 0.1 s Input 0.02 s 0.3 s 1.17 s 2.0 s Reactor Trip Pressurizer Pressure ESFAS (SI) Input to ITT Barton 763 0.75 s NLP + NAL 0.1 s Input 0.02 s 0.3 s 1.17 s 2.0 s Reactor Trip I I RPS Functions Acronyms Pzr - Pressurizer RCS - Reactor Coolant System OPDT - Overpower A Temperature SI - Safety Injection S/G - Steam Generator RCP - Reactor Coolant Pump OTDT - Overtemperature A Temperature NIS - Nuclear Instrumentation System ESFAS - Engineered Safety Features Actuation System Page 5
Catawba Nuclear Station (CNS)
Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification via Allocation Methodology WCAP-13632-P-A R2 and WCAP-14036-P-A Rl Table 2 - Engineered Safety Features Function Sensor Sensor 7300 / NIS String 7300 SSPS Relays SSPS Total Req'd Notes 2 & 3 Time Note 4 Time Note 5 Time Time </ =
Note 11 Note 5 Note 12 Containment Press - High ITT Barton 386A 0.75 s NLP + NAL 0.1 s Input + Master + Slave +Slave 0.124s 0.974s 1.Os (SI)
Containment Press - High ITT Barton 386A 0.75 s NLP + NAL 0.1 s Input + Master + Slave 0.088 s 0.938 s 1.0 s High (CS & CIOB & SLI)
Tobar 32PA Steam Pressure - Low Veritrak 76PG 0.75 s NLP + NAL 0.1 s Input + Master + Slave 0.088 s 0.938 s 1.0 s (SLI) Rosemount 1153GD9 Tobar 32PA Steam Pressure - Neg Rate Veritrak 76PG 0.75 s NLP + NAL 0.1 s Input + Master + Slave 0.088 s 0.938 s 1.0 s High (SLI) Rosemount 1153GD9 Pzr Pressure - Low (SI) ITT Barton 763 0.75 s NLP + NAL 0.1 s Input + Master + Slave + Slave 0.124 s 0.974 s 1.0 s RWST Level - Low Rosemount 1153DB5 0.75 s NLP + NAL 0.1 s Input + Master + Slave 0.088 s 0.938 s 1.0 s S/G Level-Low Low ITT Barton 764 0.75s NLP + NAL 0.1 s Input + Master + Slave 0.088s 0.938s 1.Os (AFW)
S/G Level - High High ITT Barton 764 0.75 s NLP + NAL 0.1 s Input + Master + Slave 0.088 s 0.938 s 1.0 s (TT & FWI) T rr AN N/AN/A_0.75_s_1.0_s AFW Suction Transfer ITT Barton 580A 0.75 s N/A N/A N/A N/A 0.75 s 1.0ss Engineered Safety Features Actuation System (ESFAS) Function Acronyms SI - Safety Injection FWI - Feedwater Isolation CS - Containment Spray AFW - Auxiliary Feedwater TT - Turbine Trip ClDA - Containment Isolation Phase A SLI - Steamline Isolation CICFB - Containment Isolation Phase B Page 6
Catawba Nuclear Station (CNS) Units 1 & 2 Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification - Allocation Tables Table 1 and 2 Notes
- 1. Sensors for these functions were not evaluated in WCAP-13632 P-A R2. Therefore, allocated sensor response times are not used and sensors will continue to be tested as required. NIS detectors are exempt from RTT per Technical Specifications.
- 2. Allocated sensor response times for the ITT Barton (model 763
- Pressurizer Pressure, model 764 - Steam Generator Level),
Tobar (model 32PA - Steamline Pressure) and Veritrak (model 76PG - Steamline Pressure) pressure sensors specified in Tables 1 and 2 are based on historical records (Method 1) of acceptable RTT obtained from the CNS response time testing program. The historical response time test data for these sensors is documented in various test reports from Analysis &
Measurement Services (AMS) produced from on-site in-situ testing performed via noise analysis method. The test reports span a time period from March 1991 through August 2001. These test results are not included but are available for NRC inspection upon request.
Due to equipment obsolescence, the Veritrak and Tobar transmitters used for Steamline Pressure will be replaced with Rosemount model 1153GD9 transmitters through the modification process. These style transmitters are covered by WCAP-13632-P-A R2, and the sensor response time will be measured upon initial installation to verify that they are below the allocated response time for the function. A review of data from AMS in-situ testing performed at the Duke Power McGuire Nuclear Station indicates that this will be acceptable.
- 3. Allocated sensor response times for the ITT Barton (model 386A - Containment Pressure, model 580A - Auxiliary Feedwater Pump Suction Pressure) and Rosemount (model 1153DB5 Refueling Water Storage Tank Level, model 1154HP5 - Reactor Coolant System Flow) pressure sensors specified in Tables 1 and 2 are based on historical records (Method 1) of acceptable RTT obtained from the CNS response time testing program. The historical response time test data for these sensors is documented in CNS plant test procedures performed via step input method. The test data span a time period from April 1985 through September 2001. These test results are not included but are available for NRC inspection upon request.
- 4. 7300 cards installed at CNS were evaluated in Section 4.5 of WCAP-14036-P-A R1 (card types NLP, NSA, NAL, NCH, and NRA).
The allocated response times for 7300 are derived from Table Page 7
Catawba Nuclear Station (CNS) Units 1 & 2 Reactor Protection System (RPS) / Engineered Safety Features Actuation System (ESFAS)
Response Time Verification - Allocation Tables 8-1 of the WCAP. There is a NLL lag card in each of the Delta T and the Tavg 7300 circuits which has a setpoint of zero seconds (e.g., no lag value). These NLL cards have been hard configured to eliminate the lag circuit. All other NLL type time domain cards will have their time domain characteristics verified within calibration procedures. This is consistent with discussion in Section 4.0 of WCAP-14036-P A R1.
- 5. Relays evaluated in Section 4.8 of WCAP-14036-P-A R1 and used in the CNS SSPS are as follows:
" Input and Master Relays: G. P. Clare GPl Series, Midtex/AEMCO 156, or Potter & Brumfield KH Series
" Slave Relays: Westinghouse Type AR and/or Potter &
Brumfield MDR series The following allocated response times for the SSPS relays are in accordance with Section 4.8 of WCAP-14036-P-A Rl; logic circuit response time was determined to be insignificant.
- Reactor Trip Functions: 20 msec (input relay)
- ESFAS Functions:
26 msec + 26 msec + 36 msec = 88 msec (input + master +
slave),
OR 26 msec + 26 msec + 36 msec + 36 msec = 124 msec (input +
master + 2 slaves in series)
- 6. Time includes: Reactor Trip breaker time < / 150 ms and Stationary Gripper Release Time < / = 150 ms.
- 7. Time includes: Undervoltage module delay time < / : 0.7 sec and Westinghouse assumed EMF Delay Time 250 ms.
- 8. Time includes: Underfrequency module delay time < / 0.2 sec.
- 9. The Power Range NIS cards installed at CNS were evaluated in Section 4.6 of WCAP-14036-P-A R1 (Detector Current Monitor, Summing and Level Amplifier, Level Trip Bistable, and Isolation Amplifier).
- 10. Includes allowance for both NIS and 7300.
- 11. The allocated response times are derived from Table 8-1 of the WCAP.
- 12. This value is 1 second of the Allowed Total Response Time.
The use of the 1 second value is an internal Catawba limit which supports plant overall time verification process.
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