ML103330501
| ML103330501 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/24/2010 |
| From: | Bajestani M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML103330501 (22) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 November 24, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 10 CFR 50.4 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - INSTRUMENTATION AND CONTROLS STAFF INFORMATION REQUESTS
Reference:
- 1. Licensee Open Items to be Resolved for SER Approval List The purpose of this letter is to provide TVA's responses to NRC's information requests on the "Licensee Open Items to be Resolved for SER Approval List." Enclosure 1 to this letter provides TVA's responses to the information requested by NRC. contains the supporting documents for TVA's responses to NRC's requests/
questions provided in Enclosure 1. Enclosure 3 contains a list of references on which TVA's responses are based. Enclosure 4 provides the new regulatory commitment contained in this letter. If you have any questions, please contact William Crouch at (423) 365-2004.
I declare under the penalty of perjury that the foregoing is true and correct. Executed on the 2 4 th day of November, 2010.
Sincerely, Masoud B tani Watts Ba nit 2 Vice President Enclos rs:
- 1. Responses to Licensee Open Items To Be Resolved For SER Approval
- 2. Attachments
- 3. References
- 4. Regulatory Commitment gtb(~
U.S. Nuclear Regulatory Commission Page 2 November 24, 2010 cc (Enclosures):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval For some NRC Requests for Additional Information (RAI), this letter provides TVA's initial response. For the other NRC RAI requests in this letter, a response has been provided in previous TVA letters to the NRC and the NRC has subsequently requested additional information. For these requests, the initial TVA response is not included. Additional NRC information requests are identified in this letter as "Follow-up NRC Requests." TVA responses to these items are identified as "TVA Response to Follow-up NRC Request."
- 1. NRC Request (Item Number 276)
In order for the staff to review the effects of multi control systems failure, provide the summary of the analyses documenting the effect on the plant based on the following events: (1) loss of power to all control systems powered by a single power supply; (2) failure of each instrumentsensor which provides signal to two or more control systems; (3) Break of any sensor impulse line which is used for sensors providing signals to two or more control systems; and (4) failure of digital system based on the common cause software failure affecting two or more control systems. For each of these events, confirm that the consequences of these events will not be outside chapter 15 analyses or beyond the capabilityof operators or safety systems.
Follow-up NRC Request:
TVA needs to make a statement that all non-safety control systems have been evaluated againstthese criteriaand have determined that their failure does not have consequences which will put the plant outside chapter 15 analyses.
TVA Response to Follow-up NRC Request:
All non-safety related control systems were reviewed in the context of this question. Only those control systems (i.e. the Distributed Control System [DCS], Rod Control, and the Main Turbine Electro-hydraulic Control System) previously discussed in the TVA to NRC letter dated October 21, 2010 (Reference 3) are within the scope of this question. The review found that failures of non-safety-related control systems based on the scenarios in this RAI do not have consequences which will put the plant outside the Chapter 15 analyses.
- 2. NRC Request (Item Number 281)
For FSAR Section 7.6.8 in amendment 96, redline version has completely rewritten this section of the FSAR, however, the staff is not able to determine any changes made to the section. Explain what changes have been made to this FSAR Section.
Follow-up NRC Request:
Provide the basis for the changes. Look at Foxboro I/A impact.
1
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval TVA Response to Follow-up NRC Request:
There are no differences between Unit 1 and Unit 2 interlocks, operation of interlocks and operator interface for operation of the RCS Pressure Control. Primary sensing elements and final control elements are identical and operations of these devices are identical. For Unit 2, once signals are processed by the Eagle 21 system, interlock implementation is by software modules in the Foxboro I/A DCS. Hardware outputs, generated in the DCS, operate the PORVs. Section 7.6.8 in Amendment 101 of the WBN Unit 2 FSAR reflects the Unit 2 changes associated with implementation of the DCS.
- 3. NRC Request (Item Number 288)
(1) Can we add a section to chapter 7 giving a brief overview of the Foxboro Spec 200 in Section 7.3?
Additional Clarification provided by the NRC (2) TVA should include the list of all the functions where Spec 200 is used and discuss differences between unit 1 and unit 2. (3) This discussion should also include loops which are currently used for Unit 1 operation (4) If Spec 200 components have also been qualified to RG 1.209, it should be stated and if not why not.
TVA Response:
(1) and (2) The following new section and reference will be added to the WBN Unit 2 FSAR as part of Amendment 102:
7.3.1.1.3 Analog Instrumentation The miscellaneous safety-related analog process control and indication loops are made up of discrete analog modules that have been tested and qualified for use in safety related systems. The various components have been qualified to IEEE Standard 323-1983 (R-1996) IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations, IEEE Standard 344-1987 (R-1993) IEEE Standard Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations, and IEEE Standard 384-1984 (R-1992) IEEE Standard Criteria for Independence of Class IE Equipment and Circuits. The modules are arranged in instrument loops to provide the safety functions listed below:
- Turbine driven AFW Pump Flow Control
- Motor driven AFW pump differential pressure indication and recirculation valve control
- Steam generator AFW flow and level indication and control
- Containment Pressure indication
" Upper and Lower Compartment Containment Ambient Temperature indication
- Sample Heat Exchanger Header CCS Differential Flow
" ERCW Strainer Differential Pressure, Backwash and Flush Control
- CCS Heat Exchanger B Inlet Pressure 2
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval
" CCS Surge Tank Level Control
- CCS Heat Exchanger B Outlet Temperature
- Reactor Vessel Head Vent Throttle Manual Loading Station (Unit 2 Only)
- EGTS Annulus Differential Pressure Control The components are physically arranged in the racks to meet the requirements of IEEE-279 and Watts Bar Design Criteria WB-DC-30-4, Separation/Isolation (Unit 2 Only). Two IE analog modules are used to isolate IE to Non-IE signals. These are the Contact Output Isolator and Voltage-to-Current Converter, both of which have the Input and Output signals isolated.
EMI testing and acceptance by TVA of the Foxboro Spec 200 hardware is documented in Referencef[8].
Reference:
(8) Invensys Process Systems Document No. 800063-1830, "Electromagnetic Compatibility Test Reports," dated August 21, 2008, Rev. 0.
(2) As agreed to by TVA and the NRC reviewer, the level of detail necessary to describe the differences between Unit 1 and Unit 2 is down to the specific hardware manufacturer.
This level of detail was agreed to not be appropriate in Chapter 7 which discusses the functions and design requirements for the plant control systems. The hardware manufacturer level of detail is addressed in Chapter 3.10 which describes the qualification of the specific hardware for safety-related functions.
(3) While not specifically identified as such, loops in service for Unit 1 (Essential Raw Cooling Water, etc.) are described in the FSAR chapters describing the systems the loops serve.
(4) Reg. Guide 1.209, "Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants," is not applicable to the analog Foxboro Spec 200 hardware.
- 4. NRC Request (Item Number 300)
Need Radiation Monitoring System Description/DesignCriteria Are detectors different from Unit 1? Describe any differences.
Are there any commercially dedicatedparts in the RM- 1000? If so, how are they dedicated?
Please confirm that digital communication ports availablein RM- 1000 are not used.
3
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Follow-up NRC Request:
TVA to clarify that GA has a commercial dedicationprogram in place and that GA is an approved 10CFR50, App. B supplier.
TVA Response to Follow-up NRC Request:
General Atomics Electronics Systems, Inc., is an approved 10 CFR 50 Appendix B supplier. They have a commercial grade dedication program.
- 5. NRC Request (Item Number 301)
- 1. TVA is requested to address the consequences of software common cause failure including all potential resulting failures (i.e. total loss of CERPI, system fail as-is).
- 2. In addition, address how the actions stipulatedin the plant Technical Specifications will be taken when the CERPI system indicationsare lost. Information Notice IN 2010-10 (ML100080281) addresses the need to considersoftware failures and the actions required to assure that the plant will stay within its licensing basis.
- 3. Provide FMEA in support of your response.
- 4. FSAR Table 7.7-1, Plant Control System Interlocks lists interlock C- 11 to block automatic rod withdrawal when 1/1 Control Bank D rod position is above setpoint. This interlock capabilitywould be lost in case of total loss of CERPI. How is the rod block assured for this event?
- 5. How is automatic rod withdrawalaffected in case of total loss of signals from the CERPI to the ICS? Is this interlock fail safe?
- 6. FSAR chapter 15, Section 2.3.2. 1 states that the resolution of the rod position indicator channel is 5%,of span (7.2 inches). The CERPI system accuracy specified in the CERPI System Requirements Specification, WNDS-DS-00001-WBT, Rev. 2 is 12 steps or 5.19%. The specified system accuracyseems to be greater than the accuracy assumed in the FSAR Chapter 15. Please clarify this anomaly.
TVA Response:
Items 1 and 3 through 6 were addressed in the partial response provided in TVA to NRC letter dated October 29, 2010 (Reference 1). Item 2 is addressed as follows by Westinghouse letter WBT-D-2636, "RFI-CERPI System Software Failure," (Reference 6):
Description of the CERPI systems installed at Watts Bar (Unit 1 & 2):
Each Programmable Logic Controller (PLC), Maintenance Test Panel (MTP), and Operators Module (OM) is isolated within its own Train, A or B. Rod position information is provided to the OMs in the main control room via redundant data links. Each train (PLC, MTP, and OM) is electrically isolated from the other train.
4
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Communications within a CERPI train (PLC, MTP, and OM) are continuously monitored. If communication is interrupted, this condition is annunciated to the operator in the control room. The MTP and OM display screens have rotating cursors in the upper right-hand corner of the display to indicate that the system is operating.
History of CERPI:
The basic PLC software associated with the CERPI system has been in use for over ten years. The first plant to utilize the CERPI PLC software was Beaver Valley. In 2003, the CERPI software was deployed with interfaces to the Common Q MTP and OM interfaces within the systems for Surry Units 1 & 2, and Watts Bar Unit 1. In 2009, the Watts Bar Unit 1 CERPI system was modified to allow for two independent trains of CERPI. The Watts Bar Unit 2 CERPI system is based on the Unit 1 design. Only the detectors and the detector interface boards are not redundant within the Watts Bar CERPI systems.
CERPI Software Failure Analysis With regard to the CERPI system software:
- The software used on PLC-A is identical to that used on PLC-B.
- The software used on MTP-A is identical to that used on MTP-B
" The software used on OM-A is identical to that used on OM-B.
A common cause failure affecting the software of one CERPI train would affect the other train as well. Common cause problems associated with the CERPI software were mitigated by the Westinghouse software development process, factory acceptance testing, and site acceptance testing. There is no "fail as-is" scenario. Any failure of a hardware/software component (resulting in processor lock-up) would be immediately annunciated (Main Control Room alarm). A loss of communication to the MTP, or OM would be annunciated, and the data values on the flat panel display would be displayed in magenta (indicating failure). A hardware/software failure in the PLC (resulting in processor lock-up) would result in an annunciator because of the watchdog alarm circuit associated with the PLC processor module.
A total loss of CERPI indication (e.g., loss of both AC power sources to the rod position cabinets) is possible, but this condition would be immediately annunciated. A complete loss of CERPI indication would lead to entering Technical Specification LCO 3.0.3. A more likely scenario would be loss of a single train of CERPI due to a hardware failure; in which case, there are no technical specification conditions to enter because a single train is capable of providing all rod indications needed for control.
- 6. NRC Request (Item Number 327)
Attachment 36 [of TVA to NRC Letter dated October 5, 2010 (Reference 2)] contains Foxboro proprietarydrawings 08F802403-SC-2001sheets 1 through 6. An affidavit for withholding and non-proprietaryversions of the drawings will be submitted by January31, 2011.
5
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval TVA Response:
In accordance with correspondence from Foxboro, there is no proprietary information contained in the 08F802403-SC-2001 drawings. Based on this, no affidavit for withholding is required. Attachment 1 contains versions of the drawings with the proprietary information block removed.
- 7. NRC Request (Item Number 330)
IE Bulletin 80-06 calls for review of engineeredsafety features with the objective of ensuring that no device will change position solely because of the 'reset'action.
In Supplement 3 of NUREG-0847, Section 7.3.5, the staff approvedthe design modifications proposed by the applicant that would allow certain devices to remain unchanged upon an ESF reset. The staff also found acceptable the applicant's justification for some safety-related equipment that does not remain in its emergency mode after an ESF reset.
Pleaselist for Unit 1 and Unit 2 the safety-relatedequipment that does not remain in its emergency mode after an ESF reset.
TVA Response:
The original response to IE Bulletin 80-06 for both WBN Unit 1 and 2 was provided on TVA letter to NRC dated March 11, 1982 (ML073530129) (Reference 4). Subsequent design changes have impacted the original response such that some equipment that originally changed state no longer does so and some equipment has been deleted. There are no additions to the list originally provided in TVA letter to NRC dated March 11, 1982 (ML073530129) (Reference 4). The following is the current list of equipment that does not remain in its emergency mode after an ESF reset:
- 1. Unit 1 and 2 Equipment (prefix 1- (Unit 1) or prefix 2- (Unit 2))
- a. Auxiliary Feedwater (AFW) Pump Turbine Speed Control Valve, FCV-1-52
- b. Auxiliary Feedwater (AFW) Level Control Valves as listed below:
- i. LCV-3-172 - SG3 - Level Control Valve ii. LCV-3-173 - SG2 - Level Control Valve iii. LCV-3-174 - SG1 - Level Control Valve iv. LCV-3-175 - SG4 - Level Control Valve
- v. LIC-3-172 - SG3 - Level Indicating Controller vi. LIC-3-173 - SG2 - Level Indicating Controller vii. LIC-3-174 - SG1 - Level Indicating Controller viii. LIC-3-175 - SG4 - Level Indicating Controller ix. LCV-3-148 - SG3 - Level Valve
- x. LCV-3-156 -- SG2 - Level Valve xi. LCV-3-164 - SG1 - Level Valve xii. LCV-3-171 - SG4 - Level Valve xiii. LCV-3-148A - SG3 - Level Bypass Control Valve 6
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval xiv. LCV-3-156A - SG2 - Level Bypass Control Valve xv. LCV-3-164A - SG1 - Level Bypass Control Valve xvi. LCV-3-171A - SG4 - Level Bypass Control Valve xvii. LIC-3-148 - SG3 - Controller xviii. LIC-3-156 - SG2 - Controller xix. LIC-3-164 - SG1 - Controller xx. LIC-3-171 - SG4 - Controller
- c. Lower and Upper Compartment Cooler Fans and Control Rod Drive Mechanism Cooler Fan
- d. Penetration Room Cooler Fans Elevations 737, 692 and 713
- e. Pipe Chase Cooler Fans
- 2. Common Equipment
- a. Shutdown Board Room Pressurizing Fan
- b. Control Building Ventilation Dampers as listed below:
- i. 0-FCO-31-9 - Spreading Room Supply Fan Damper ii. 0-FCO-31-10 - Spreading Room Supply Fan Damper iii. 0-FCO-31-16 - Toilet and Locker Room Exhaust Fan Exhaust Damper iv. 0-FCO-31-17 - Toilet and Locker Room Exhaust Fan Exhaust.Damper
- v. 0-FCO-31-3 - Main Control Room Isolation Damper vi. 0-FCO-31-4 - Main Control Room Isolation Damper vii. 0-FCO-31-36 - Spreading Room Fresh Air Supply Damper viii. 0-FCO-31-37 - Spreading Room Fresh Air Supply Damper
- c. Cask Loading Exhaust Dampers as listed
- i. 0-FCO-30-122 - Cask Loading Area Exhaust Damper ii. 0-FCO-30-123 - Cask Loading Area Exhaust Damper
- d. Auxiliary Building General Supply Exhaust Fans Elevation 737
- e. Component Cooling System and AFW Pump Space Cooler Fans
- f. Spent Fuel Pit Pumps Space Coolers
- g. Emergency Gas Treatment System Room Coolers
- h. AFW and Boric Acid Space Coolers 7
Enclosure 1 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval
- 8. NRC Request (Item Number 336)
Re: RM- 1000 Report 04508905-OR Please check the page numbering in Appendix F, Closed Nonconforming Material Reports. Pages 1 and 6 are missing and page 2 is included multiple times. Also identify which page number is the last page number.
TVA Response:
General Atomics was not able to determine where the duplicate page 2 originated. The master document does not contain any duplicate pages. Due to a clerical error during document development, the master document starts at page 2 and ends at page 9, for a total of 8 pages. In May of this year, the NRC discovered that the master document was missing page 6. The master document was revised and re-submitted. Attachment 2 contains the missing page 6.
The Nonconforming Material (NCM) reports found on Appendix F are complete.
- 9. NRC Request (Item Number 337)
Re: RM- 1000 Report 04508905-QR Appendix C is titled as Seismic Test Fixture for RM2300, See Drawing 04619028. Please verify whether or not it applies to RM- 1000? If applicable, then please identify how it is applicable.
TVA Response:
The test fixture listed on Appendix C is applicable to the RM-1000, as indicated in the second and third paragraph of section 4.3.1, of the 04508905-QR report. The RM-1000s and the I/F converters are mounted on a standard 19 inch NIM-Bin, and this test rack is configured to simulate the field installation of a standard 19 inch rack.
This seismic test fixture was originally built for the seismic testing of the RM2300s which are also mounted on a standard 19 in NIM-Bin.
8
Enclosure 2 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Attachments
- 1. Foxboro 08F802403-SC-2001 drawings with proprietary information blocks removed
- 2. General Atomics Report 04508905-QR, page 6
Enclosure 2 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Attachment 1 Foxboro 08F802403-SC-2001 Drawings With Proprietary Information Blocks Removed
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& BOP (SYS 070-081)
OPS M/ASTATIONS (OTY = 3) 2-R-124 PANEL 2-M-18 SG 3 PORV RACK 2-R-137 C 8 Positlon (L) MN TB OIL TK TEMP (M-2) 8 Position (B) A- C Baseplate #3 (05) ROW H2 HTX TEMP (M-2) Baseplate #7 (06) -:
FBM/FCM i ',i RACK 2-R-142 RACK 2-R-125
-L8 Position (K) A - -- - - - - - - - - -
8 PositIon (D) 8 PoslMion (E)
Baseplate #2 (034) Baseplate #6 (05) Basep late #4(03)
FBM/FCM FBMIFCM FBIM GROUP 9, SDA3 RACK 2-R-142 ] RACK 2-R-125 8 Position (C) 8Posiilon (D)
Baseplate #5 (04) Basep late #3 (02) r FBM FBM RACK2-R-124 RACK 2-R-125 2 Position (E) Ak- 8 Posl dIon (C)
Baseplate Basep late #2 (01)
FCM FBM
" RACK 2-R-26 RACK 2-R-26 . 1' B E;PM 2[oito Ba3 r-A-xtnentspatelit -i * -
- C/FM C (SEESHEET 6)
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31 A A 07 1 1 1 1 03 /O9 IIS TL Ji CORKISO . ACRRERE..CcE NOTCES. rITt SYSTEM CONFIGURATION l3 ONVENSYS SYSTRES fT.
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AND SDMP & BOP (070-081) M SEL L A Y TE W .1 05OD1S1 .J 00 1/09 IS T J tErIO LPDTE I ALD9 AT
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7 6 4 2 I 8 764 OPS M/A STATIONS i MAIN CONTROL ROOM MAIN CONTROL ROOM OPS WA STATIONS (QTY = 7) 2-M*
4 Position (R) CHARGING FLOW PZR (M-S) D Baseplate #4 (06) EXCESS LTDN FLOW FBM BAT B RECIRC CNTL LETDOWN HX OUTLET OPS M/A STATIONS (QTY = 3) PANEL 2-M-18 LETDOWN PRESS CNTL 8 Position (Q) RHR LTDN CNTL PRZ PRESS LP1 SPRY Baseplate #3 (05) VCT LEVEL SP CNTL PRZ PRESS LP2 SPRY 2-FBM PRZ PRESS MASTER OPS M/A STATIONS (QTY =4) 8 Position (P) A. . ... ... ... ......... I *
- Baseplate #2 (04) B BA TO BLENDER CNTL FBM/FCM PW TO BLENDER CNTL RACK 2-R-2 . C BA BATCH COUNTER 8 Position (B) I AUXILIARY INSTRUMENT PW BATCH COUNTER ROOM Baseplate #5 (05)
FBM RACK 2-R-19 RACK 2-R-17 GROUP 12, 8(DI 1-1 8 Position (B)
PRESSURIZER A & BA Baseplate #4 (04) Baseplate #3 (02) GROUP 13 B
BLENDER FBM FBM PRESSURIZER B &
2-R-15 RACK 2-R-14 RACK 2-R-14 CvCS 2 Position (E) A6 Position (G)
RACK2-R-1 5 Baseplate Bf.. Baseplate #2 (01) 2-R-14 8 Position (F)
FCM - FBM Baseplate # 1(00.)
- ........ FBM B3 RACK 2-R-14 RACK 2-R-14 A 4 Position (D) 8 Position (F) j-RACK 2-R-1 5 RACK 2-R-1 Baseplate #1 (00)
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.L 2.
- 31) . ....
(SEE SHEET 6)
A B A
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UPS M/A STATMNS(mTY-B, 0IPS M/A STATI'I"NS(TY-7) 1S;G 1 PIRV CNTL SG 4 PnRV CNTL SG 3. PRV CNTL EXCESS L1BN FLIV LTIN HX MJTLTEJP RIR LTIN FLOWCTLT LTDN PRESSURE CNTL CHRGHMER FLDV CNTL CHARGINGFtLIV CNTL VCT LEVEL CERC. CL ACCUMN2 VENT RHR HXA 13UTLCN'TL 8Position (B) R4 X A51hC~
RHR BX8 MBM. CNTL s a #RHR HX A/B BYPASS
' 8 Position (A)
Baseplate #2 (01)
FBM-GROUP 14, ACR TRAIN A GROUP 1.5, ACR TRAIN B 2-L-1 lA 2-L-11B 4 Position (A) 4 Position Baseplate #1 (00) Baseplat(
4 Position (B)
B-s7eplat', #1(00)
A 4 Position (A) tRFCP/FBM FBM r 7- - Baseplate #1 (00)
M Baseplate #1 (00)
B FCP/FBM FBM L iý-*--------------- -------------------------------
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EACH A FIDER OPTIC CAKES TO CPAND EWS (16 TOTAL) AND [
ACR -- -- --
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Enclosure 2 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Attachment 2 General Atomics Report 04508905-QR, Page 6
NMR 15813, ITEMS 0001 AND 0002 RESOLUTION This information is in addition and supplementary for these NMR items that are closed.
DISCREPANCY/ FAILURE
SUMMARY
Before initiation of seismic testing, the shake table made a random jolting movement that was not part of the test. The abrupt hard jolt was caused by a faulty table actuator. Item 0001 of the NMR described that the internal PWAs of both the area and process RM-lOOOs were found to be out of their sockets. After the process RM-1000 boards were re-installed, it was operational. The area RM-1000 had a problem with incorrect 15 V operation and Diode D31 7 had a resistance of about ten ohms in both directions. Item 0002 was written for the area RM-1000 after the seismic test resumed after repairs were made to the shake table actuator RESOLUTION:
Due to the table misoperation, the dynamic loading on the RM-1000s was far in excess of required test conditions. The Output Board on the area RM-1000 was repaired with new parts and the test proceeded successfully.
6
Enclosure 3 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval References
- 1. TVA Letter to NRC "Watts Bar Nuclear Plant (WBN) Unit 2 - Instrumentation And Controls Staff Information Requests," dated October 29, 2010
- 2. TVA Letter to NRC "Watts Bar Nuclear Plant (WBN) Unit 2 - Instrumentation And Controls Staff Information Requests," dated October 5, 2010
- 3. TVA Letter to NRC "Watts Bar Nuclear Plant (WBN) Unit 2 - Instrumentation And Controls Staff Information Requests," dated October 21, 2010
- 4. TVA letter to NRC 'Watts Bar Units 1 and 2 Response to IE Bulletin 80-06, Question 31.147," dated March 11, 1982 (ML073530129)
- 5. Not Used
- 6. Westinghouse letter WBT-D-2636 "RFI-CERPI System Software Failure," dated November 11,2010
Enclosure 4 TVA Letter Dated November 24, 2010 Responses to Licensee Open Items to be Resolved for SER Approval Commitments