NG-97-0574, Forwards Revs to Performance Test Schedule for 1996-1999
| ML20137S831 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/04/1997 |
| From: | Franz J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-1262, RTR-REGGD-01.149, RTR-REGGD-1.149 NG-97-0574, NG-97-574, NUDOCS 9704150257 | |
| Download: ML20137S831 (9) | |
Text
IES Utihties Inc.
200 First Stmet S E.
Po. Box 351 Cedar Rapids, IA 52406-0351 Telephone 319 398 8162 Fax 319 398 8192 UTILITIES
.sonn v. rrenar.
Vce Presidtent, Nuclear April 4,1997 NG-97-0574 U.S. Nuclear Regulatory Commission i
Attn: Document Control Desk I
Mail Station Pl-37 Washington, D.C. 20555-0001
Subject:
Duane Arnold Energy Center Docket No: 50-331 I
Op. License No: DPR-49 Plant-Referenced Simulator Certification Report
Reference:
Letter, IES Utilities to NRC dated November 7,1996, NG-96-2344 i
File A-102
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Dear Sir:
This letter regards a change to the content of the above referenced letter. This letter is provided as a follow-up to a telephone conversation between Mr. Frank Collins of your staff and Mr. Phillip Meek (lES Utilities) on January 15,1997.
Upon further review of Regulatory Guide 1.149, Revision 1, ANS/ ANSI-3.5-1985, and NUREG 1262, it has been determined that there are additional requirements for simulator certification testing, not contemplated by the revision j
to the Duane Arnold Energy Center (DAEC) testing program stated in Nuclear Regulatory Commission Form 474 dated November 6,1996 and detailed in i
attachments to the above referenced letter.
Changes were necessary to the information provided in the above reference. The changes to Attachment 1 are under the section heading " Major Changes to the 4
Testing Schedule." That section is included as Attachment I to this letter. has been completely revised and is included as Attachment 2 to this letter.
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poSi 1501 "'"5 Isilylmppilll41,14 9704150257 970404 PDR ADOCK 05000331 P
PDR An IES Industnes Cornpany
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. April 4,1997 NG-97-0574 Page 2 These attachments describe changes to the DAEC Plant-Referenced Simulator Certification Testing Program. These changes represent a commitment to testing in accordance with Regulatory Guide 1.149, Revision 1, and ANS/ ANSI-3.5-1985.
j If you have any questions, please call Keith Young, Manager, Nuclear Training, at (319)-851-7229.
Sincerely, i-ohn F. Franz Vice President, Nuclear t
Attachments: 1) Major Changes to the Testing Schedule 1
- 2) Performance Test Schedule for 1996-1999 cc:
R. Murrell L Root G. Kelly (NRC-NRR) i l
A. B. Beach (Region III)
NRC Resident Office DOCU 1
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i Attachment I to NG-97-0574 Page 1 of 2 MAJOR CIIANGES TO TIIE TESTING SCIIEDULE describes the malfunctions to be tested for the period from 1996 to 1999. This is a reduction in the number of malfunctions to be tested and will meet or exceed the General Requirements of ANS/ ANSI-3.5-1985, Section 3.1.2, Malfunctions.
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Remote Function Testing will no longer be performed as part of the performance tests but will be utilized as necessary to validate modifications.
Surveillance Test Procedures (STPs) which are performed on Safety Systems by l
plant control room operators and which require action be taken on equipment which is located in the simulator control room will be tested on the Duane Arnold Energy Center (DAEC) simulator at the rate of 25% of the available STPs each year for the 4-year certification cycle. (NUREG 1262, Q.195).
1 A physical fidelity audit was performed each year in the past to ensure that the l
simulator environment matches the reference plant main control room and remote shutdown panels as closely as is reasonable and practical. This audit will no longer be performed. However, physical fidelity will be maintained through the simulator modification process.
l ANS/ ANSI-3.5-1985 Section 3.1.1, Normal Plant Evolutions, will be performed as follows:
0 Items 1,2,3,5,6,7, and 8 will be perfomied once every four years. These items concern plant startup, shutdown, operations at hot standby, load changes, operation with less than full reactor coolant flow and plant shutdown.
l It is acceptable to perform these tests any time within the four year period, l
rather than attempting to schedule them on a 25% per year basis.
O Item 4, " Reactor trip followed by recovery to rated power," has nes been performed as a plant evolution at the DAEC. It is administratively prohibhed at the DAEC and therefore will not be tested on the simulator.
O ltem 9, " Core performance testing such as plant heat balance, determination of shutdown margin, and measurement of reactivity coefficients and control rod worth using permanently installed instrumentation," will not be specifically tested on the simulator. This information is provided by Reactor Engineers utilizing computer code and is not determined by operators. The plant process computer (PPC) displays are used to provide information to the operators l
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Attachment I to NG 97-0574 1
Page 2 of 2 related to those items. Related data is gathered during the performance of transients malfunction testing, as well as some of the STPs. Therefore, this data gathering is sufficient to provide information necessary to determine if the simulation and PPC computers at the simulator are within required accuracy for item 9.
D. Item 10, " Operator conducted surveillance testing on safety-related equipment i
or systems," will be tested as discussed above.
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N'i-97-0574 Page1of5 PERFORMANCE TEST SCIIEDULE FOR 1996-1999 i
t 1996 MALFUNCTION PERFORMAFE TESTS Section 3.1.2 Loss of all feedwater (normal and emergency), includes the following DAEC malfunctions:
FWO2-A/B:
Condensate Pump Trip lip 02:
IIPCI Turbine Trip RC02:
RCIC Turbine Trip STCS01:
Core Spray injection Valve Fails to Open - MO-2117 STCS02:
Core Spray injection Valve Fails to Open - MO-2137 STR1101:
LPCI Inject Valve MO2003 Fails to Auto-Open STRH02:
LPCI Inject Valve MOl903 Fails to Auto-Open Section 3.1.2 Inability to drive control rods, includes the following DAEC malfunction:
RDIl-A/B:
CRD Hydraulic Pump Trip Section 3.1.2 Maia steam line as well as main feed line break (both inside and outside containment), includes the following DAEC malfunctions:
FW18-A:
Main Feedwater Line Break Outside Primary Containment i
l FW20-B:
Feedwater Break Inside Containment - Isolable 1
MS03-A:
MSL Rupture Inside Primary Containment MSO4-A:
MSL Rupture Outside Primary Containment Section 3.1.2 Passive malfunctions in systems, such as engineered safety systems, emergency feedwater systems, includes the following DAEC malfunctions:
CSO4-A:
Core Spray Thermal Overload Valve (s) Fail (s) to Operate MS28-A:
Group 5 Isolation Valve (s) Fail (s) to Close l~
Section 3.1.2 Failure of the automatic reactor trip system, includes the following i
DAEC malfunction:
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RP05-A/B/C/D/E/F: RPS Scram Circuit Failure (ATWS)
Section 3.1.2 Reactor pressure control system failure including turbine bypass failure, includes the following DAEC malfunction:
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TC07-A/B:
EHC Pressure Transmitter Failure 2
' to NG-97-0574 Page 2 of 5 e
1997 M ALFUNCTION PERFORMANCE TESTS i
i Section 3.1.2 Loss of coolant, includes the following DAEC malfunctions:
i CU10:
Coolant Leakage Outside the Primary Containmen.
RRIS-A/B:
Recirculation Loop Rupture (Design Basis LOCA)
RR30:
Coolant Leakage Inside Primary Containment AD01-A&D:
Reactor Pressure Relief or Safety Valve Leakage - PSV4400 &
PSV4403 Section 3.1.2 Loss of condenser vacuum including loss of condenser level control, includes the following DAEC malfunctions:
FW01-A:
Condenser llotwell Level Controller Failure MC04:
Main Condenser Air Inleakage Section 3.1.2 Loss of service water or cooling to individual components, includes the following DAEC malfunctions:
MC01-A/B:
Main Circulating Water Pump Trip SW19-A/B/C/D:
River Water Supply Pump Trip SW22-A:
Drywell Cooling Units Well Water Flow Blockage SW29-A:
Loss of Cooling to Generator 112 Coolers i
SW34-A/C:
RHR Service Water Pump Trips i
Section 3.1.2 Loss of shutdown cooling, includes the following DAEC malfunction-1 i
MS25:
Spurious Group 4 isolation Section 3.1.2 Loss of component cooling system or cooling to individual components, includes the following DAEC malfunctions:
EG12:
Loss of Stator Water Cooling Water Flow MS23-A:
Spurious Group 3 Isolation S W O8:
RBCCW IIX GSW Flow Blockage SW10-A/B/C: RBCCW Pump Trip SW33:
RWCU Non-Regenerative Heat Exchanger RBCCW Flow Blockage Section 3.1.2 Loss of normal feedwater or normal feedwater system failure, includes the following DAEC malfunctions:
FWO9-A/B:
Reactor Feedwater Pump Trip FW12-C:
FW Reg Valve Controller Failure (Auto)
FW16-A/B:
FW Reg Valve Lockup
- to NG-97-0574 Page 3 of 5 1998 MALFUNCTION PERFORM ANCE TESTS Section 3.1.2 Loss or degraded electrical power to the station, includes the following DAEC malfunctions:
DG01-A/B:
Diesel Generator Fails to Start ED01-A/B/C/D/E/F:
Loss of Offsite Power Sources ED05-A/B:
Any Transformer Cooling Loss E D08-A/B/C/D/E/F/G/II/1/J/K/L/M/N: 4.16KV/480V Bus F ult ED09-A/B/C/D/E/F/G/II/1/J/K/L/M/N
/0/P/Q/R/S/T/U/V/W/X/Y/Z/
AA/AB/AC/AD/AE/AF:
480 VAC Motor Control Center Fault ED10-A/B/C:
120 VAC Instrument Bus Fault EDil:
120 VAC Uninterruptible Bus Fault ED12-A/B/C:
250 VDC Distribution Panel Fault ED13-A/B/C/D/E:
125 VDC Distribution Panel Fault EDl4-A/B:
+/- 24 VDC Distribution Panel Fault EDl8:
Total Loss of 125 VDC System i EDl9:
Total Loss of 125 VDC System 2 FWl 1-A/B:
Feedwater Inverter Fails 11P07:
HPCI Inverter Trouble RC05:
RCIC Inverter Trouble RP02-A/B:
RPS EPA Breaker Trip Section 3.1.2 Loss of forced core coolant flow due to single or multiple pump failure, includes the following DAEC malfunction.
j RR06-A/B:
Recire M-G Drive Motor Breaker Trip j
l Section 3.1.2 Loss of protective system channel, includes the following DAEC malfunction:
AD07-A:
ADS Logic Power Failure Section 3.1.2 Fuel cladding failure, includes the following DAEC malfunction:
RX01:
Fuel Cladding Failure Section 3.1.2 Generator trip, includes the following DAEC malfunction:
i EG01-A:
Main Generator Trip - Primary Lockout (286/P)
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Section 3.1.2 Reactor trip, includes the following DAEC malfunction:
RP03:
Spurious Scram
- to NG-97-0574 Page 4 of 5 1999 MAISUNCTION PERFORMANCE TESTS Section 3.1.2 Loss of instrument air, includes the following DAEC malfunction:
lA01:
Loss ofInstrument Air Section 3.1.2 Control rod failure, includes the following DAEC malfunctions:
RD01:
Control Rod Drifts Out RD02:
Control Rod Blade Stuck RD03:
Control Rod Uncoupled RD06:
Control Rod Drives in RD08:
Control Rod Scrams RX02:
Control Rod Worth Change, Any Control Rod Section 3.1.2 Turbine trip, includes the following DAEC malfunction:
TC01:
Main Turbine Trip Section 3.1.2 Failure in automatic control system (s) that affect reactivity and core heat removal, includes the following DAEC malfunction:
RRl 7-A:
Recire M-G Flow Controller Fails, Auto / Man Modes Section 3.1.2 Nuclear instrumentation failure (s), includes the following DAEC malfunctions:
NM02-A:
SRM Channel Fails, Inoperable NMOS-B:
IRM Channel Fails, Inoperable N M 07:
LPRM Channel Fails NM08-B:
APRM Channel Fails Section 3.1.2 Process instrumentation, alarms, and control system failures, includes the following DAEC malfunctions:
RR20:
Narrow Range Level Transmitter Failure (GEMAC)
RR24A:
RPV Pressure Transmitter Failure RR32-A1/A2: Lo-Lo-Lo Level Switch Failure Open/ Closed l
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. to NG-97-0574 Page 5 of 5 COMMON PERFORM ASCE TESTS FOR 1996 TIf ROUGli 1999 Appendix B Steady State, Stability, and Transient Tests will be performed annually.
Section 3.1.1, Normal Plant Evolutions listed in Attachment I will be performed once every four year cenification cycle, with the exception of Surveillance Test Procedures as noted below.
Section 3.1.1 - 10, Surveillance Test Procedures will be tested at the rate of 25% of the available STPs each year for the four year cenification cycle.
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