ML20086U545

Forwards Response to NRC Request for Addl Info Re Incorporation of Operating Experience in Advanced BWR

ML20086U545
Person / Time
Site:	05000605
Issue date:	01/06/1992
From:	Marriott P GENERAL ELECTRIC CO.
To:	Pierson R Office of Nuclear Reactor Regulation
References
EEN-9202, TAC-M81870, NUDOCS 9201080099
Download: ML20086U545 (16)

Text

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Gf th',.u 1e c;y January 6,1992 MFN No. 005-92 nocket No. STN 50-605 EN-9202 1

Document Control Desk U.S. Nucleac Regulatory Commission Washington, D.C. 20555 Attention: Robert C. Piccson, Director Standardization and Non. Power Reactor Project Directorate

Subject:

GE Response to the Request for Additional Information on the Incorporation of Operating Esperience in the AllWR

Reference:

Letter, Victor M. hicCree to Patrick W. Marriott," Incorporation of Operating Experience in the Advanced Boiling Watet Reactor (ABWR) Certification Review Process (TAC NO.

Af 81870)", December,1991 Enclosed are thirty-four(34) copies of the GE response to the subject request for operating expenence, it is intended that GE will amend the SSAR with this response in a future amendment. _

Sincerely,

.O fl\i\ {h%

P.W. M9rriott, Manager Regulatory and Analysis Services M/C 382, (408) 925-6948 cc: F. A. Ross (DOE)

N. D. Fletcher (DOE)

V. M. McCree (NRC)

R. C. Berglund (GE)

J. F. Quirk (GE) 0 m c_-mm. m,D-tp e,nn R 1A o r

ABWR uumc

' haDIl. aid Plant arv c; 1.8 CONFOR31ANCE WITil STANDARD Standard Plant / remainder of plant interface REVIEW PLAN AND APPLICABILITY OF impact. See Subsection 1.8.4 for interface CODES AND STANDARDS requirements.

4--- /WJE R T A 1.8.1 Conforrnance With Standard 1.8.4 Interfaces Resicu Plan The SRP sections to be addressed and the The subsection provides the information applicable regulatory guides and experience required by 10 CPR 50.3J(g) showing conformance information for the remainder of the plant are with the Standard Review Pin (SRP). The summary t h o s e o f T a bl e 1.8 19, 1.S 20 a n d 1.8 2 2 of differences from the SRP section is presented identified in the comment colum n, as by SRP section in Tables 1.S 1 through 1.818. "in t e r f a c e ". .

See Subsection 1.S.4 for interface requirements.

1.8.2 Applicability of Codes and Standards J

Standard Review Plans, Branch Technical Positions, Regulatory Guides and Industrial Codes and Standards which are applicable to the ABWR design are provided in Tables 1.8 19,1.8 20 a n d 1.S41. Applicable revisions are also shown.

l See Subscetion 1.8.4 for interface requirements.

1.8.3 Applicability of Experience Inforrnation Experience information is routinely made available and distibuted to design personnel in the desicn t racest Nuclear field experience it maintained in hard copy form in functional component and library files and in the GE uorld wide computer retrieval system.

Generic Letters and IE Bulletins, Information Notices and Circulars covering the decade including 1950 through the current issues (% /a/& /9#

W were reviewed for applicability to the ABWR design. The review was enhanced by associating retaicd experiences and tracing referenced occurences. This was accomplished starting with the current issues of the Generic Letters and proceeding back into the decade. The Circulars, Bulletins and Notices were reviewed in that order. Interfacing experience was incujed in the r evie w. The selection of ABWR information was based on the significance to future design and operation guidance. Included is a list of NUREGs related to the closing of current safety issues.

Experience that resulted in applicable rules, codes and standards was not repeated. Table 1.5-22 list the experience information tha: has been included in the ABWR design or has ABWR (b *

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l ,

+

INSERT A A systematic procedure encompassing available resources was used to identify the applicability of experience information resu) ting in Table 1.8-22. Engineering management surveyed the indices of annual experience information to identify those very unlikely to be applicable to the ABWR. The remaining potentially applicable experiences were reviewed individuclly. Experience information not deemed applicable to the ABWR design (issues pertaining to other reactor types, scram discharge volume, etc.) were not included in Table 1.8-22. The experience information categories applicable to the ABWR design in Table 1.8-22 include experience information accommodated by a design change, covered by review of USIs/GSIs or a issue that impacts the ABWR design but must be addressed by the party referencing the ABWR design on a specific application. This later ca,tegory is included as an interface requirement.

Experiencos related to identified regulatory or industry developed resolutions were eliminated to avoid repetition except for selected experiences that have a nuisance potential for reoccurring. Lead system engineers r assified the more complex experiences.

Reference to the new or novel design features used in the ABWR are provided below:

Feature Sff,R Section Fine Motion Control Rod Drive 4.6 Internal Reactor Pumps 5.4.1 Multiplexing 7A.2 Digital / Solid State Control 7A.7 Overpressure Protection System 6.2.5.2.6 6.2.5.3 6.2.5.4 AC-Independent Water Addition System 5.4.7.1.1.10 Lower Drywell Flooder 9.5.1.2 9

. ABWR :wrue

, Standard Plant PIV c Table 1.8 22 EXPERIENCE INFOR51ATION APPLICABLE TO ABWR (Continued)

TYPE: GENERIC LETTERS Issue M Datt. Ilt!! Comment 89 07 4/2S/S9 Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs 89 07 4/21/89 Power Reactor Safeguards Contingency Planning for Suppl Surface Vehide Bombs 80 05 5/2/S9 Erosion /Corrision Induced Pipe Wall Thinning 59 10 6/2S/89 Safety Related Motor Operated Vahe Testing Interface and Suncillance S9 11 6/30/99 Resolution of Generic issue 101 ' Boiling Water Subsection Reactor Water Level Redundancy 19B.2.16 89 13 7/IS/S9 Service Water System Problems Affecting Safety interface Related Equipment S9 14 S/21/$9 Line item improvements in Technical Specifications.

Removal of the 3.25 Limit on Extending Surveillance Intervak S9 15 S/21/S9 Emergency Response Data System Interface S9 18 9/6/59 Resolution of USl A 17, Systems Interactions Subsection 19B.2 3 89 19 9/20/S9 Request for Action Related to Resolution of Subsection Unresohtd SafetyIssue A 47'Safetyimplication 19B.2 5 of Control Systems in LWR Nuclear Power Plants

• Pvrsuant to 10 CFR 50.54(f) 89-22 10/19/89 Potential for increased Roof Loads and Plant Area Flood Runoff Depth at Licensed Nuclear Power Plants Due To Recent Change in Probable Maximum Precipit-ation Criteria Developed By The National Weather Senice

> INSER7 6 eenemeyt' i sa 1

1 1

D I N S E ft.T B

, i 90 02 31/01/90 Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications.

90 05- _06/15/90 Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2 and 3 Piping, 90 09 12/11/90 Alternate Requirements For Snubber Visual Inspection Intervals And Corrective Actions.

91 03 03/06/91 Reporting of Safeguards Events. Interface 91-04 04/02/91 Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle.

91 05 04/04/91 Licensee Commercial-Grade Procurement and Dedication Programs.

91 06 -04/29/91 Resolution of Generic Issue A-30, Subsection

" Adequacy of Safety-Related DC 19B.2.24 Power Supplies." Pursuant to 10CFR50.54(f).

91 10 07/08/91 Explosive Searches at Protected Interface Area Portals, 91-11 07/19/91 -Resolution of Generic Issues 48, Subsection "LCOs for Class IE Tie Breakers" 1B.2.24 Pursuant To 10 CFR 50.54(f).

91-14 09/23/91 Emergency Telecommunications.

91-16 10/03/91 Licensed Operators' and Other Interface Nuclear Facility Personnel Fitness for Duty.

17 10/17/91 Generic Safety Issue 29,

" Bolting D. gradation or Failure in Nuclear Power Plants".

F:jniO1032:tjm P

ABWR :3y , n c

' Standard Plant nrs c Table 1.8 22 EXPERIENCE INFORMATION APPLICABLE TO ABWR (Continued) 1TPE: IE BULLETINS Issue

& lhtto Iult Comment

$8 07, 12/30/53 Power Oscillations in Boihng Water Reactors (BWRs)

Supp1

> I N sv:,GL T C 1 B *3 Amendmce().V

I N SGRT C 90 01 03/09/90 Loss of Fill-Oil in Transmitters Manufactured by Rosemount.

90 02 03/20/90 Loss of Thermal Margin Caused By Channel Box Bow.

91 01 10/18/91 Reporting Loss of Criticality Safety Controls.

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. . ABWR  : mum

, Stanfiard Pl. tnt art c l

Table 1.8 22 EXPERIENCE INFORMATION APPLICABLE TO ABWR (Continued)

TYPE: IE INFORMATION NOTICES Issue

& Dal.t. Illis Comment 89 53 12/11/S9 Sustained Degraded Voltage on the Offsite Electrical Interface Grid and Loss of Other Generating Stations as a Result of a Plant Trip 89 S7 10/19/89 Disabling of Emergency Diesel Generators by Their Neutral Ground Fault Protection Circuitry 89 SS 12/16/$9 Recent !!RC Sponsored Testing of Motor. Operated Vahes D i N SE FCT h Amendment % 1 B-57 l____________________. . . _ . - - . . . . . . . _ _ . - _ _ . _ _ -

~

, \WSERT D 90 02 01/22/90 Potential Degradation of Secondary Containment.

90 05 01/29/90 Inter-System Discharge of Reactor Coolant, 90 07 01/30/90 New Information Regarding Insulation Material Performance and Debris Blockage of PVR Containment S umps .

90 08 02/01/90 KR 85 Hazards From decayed Fuel.

90-13 03/05/90 Importance of Review and Interface Analysis of Safeguards Event Logs, 90 20 03/22/90 Personnel Injuries Resulting Interface From Improper Operation of Radwaste Incinerators, 90 21 c92/90 Potential Failure of Interface Motor Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated, 90-22 03/23/90 Unanticipated Equipment Interface Actuations Following Restoration of Power to Rosemount Transmitter Trip Units, 90-25 04/16/90 Loss of Vital AC Power With Interface Subsequent Reactor Coolant System Heatup.

90-25 03/11/91 Loss of Vital AC Power With Interface Supp. 1 Subsequent Reactor Coolant System Heatup, 90-26 04/24/90 Inadequate Flow of Essential Interface Service Water To Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems.

90-30 05/01/90 Ultrasonic Inspection Techniques for Dissimilar Metal Welds.

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1NSERT D (couT) 90 33 05/09/90 Sources of Unexpected- Interface Occupationat Radiation Exposures at Spent Fuel Storage Pools, 90-39 06/01/90 Recent Problems with Service Interface Water Systems.

90 40 06/05/90 Results of NRC Sponsored Interface Testing of Motor-Operated Valves.

90-42 06/19/90 Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances.

90-47 07/27/90 Unplanned Radiation Exposures Interface To Personnel Extremities Due to Improper Handling of Potentially Highly Radioactive Sources.

90-50 08/08/90 Minimization of Methane Gas in Interface Plant Systems and Radwaste Shipping Containerc.

90-53 08/16/90 Potential Failures of Auxiliary Steam Piping and the Possible Effects on the Operability of Vital Equipment.

90-54 08/28/90 Summary of Requalification Interface Program Deficiencies.

90-61 09/20/90 Potential For Residual Heat Removal Pump Damage Caused By Parallel Pump Interaction, 90-63 10/03/90 Management Attention To The Interface Establishment And Maintenance of A-Nuclear Criticality Safety Program.

90-67 10/29/90 Potential Security Equipment Weaknesses.

90-68 10/30/90 Stress Corrosion Cracking of Reactor Coolant Pump Bolts.

90 69 10/31/90 Adequacy of Emergency and Essential Lighting, ,

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IN SE 8T D (Coa) 90 70 11/06/90 Pump Explosions Involving Ammonium Nitrate.

90-72 11/28/90 Testing of Parallel Disc Gate Valves in Europe.

90-74 12/04/90 Information on Precursors To Severe Accidents, 90-78 12/18/90 Previously Unidentified Release Path From Boiling Water Reactor Control Rod llydraulic Units.

90-81 12/24/90 Fitness For Duty. Interface 90-82 12/31/90 Requirements For Use of Interface Nuclear Regulatory Commission-(NRC) Approved Transport Packages For Shipment of Type A Quantities Of Radioactive Material.

i l

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_ _ _ _ _ _ - _ _ _ - _ _ _ _ _ - _ _ _ - _ _ D

1 N S G 9LT D ( Co T

l. .

91-04 01/28/91 Reactor Scram Following Control Rod Vithdrawal Associated With Low Power Turbine Testing.

91-06 0131/90 Lock-up of Emergency Diesel Generator And Load Sequencer Control Circuits Preventing Restart of Tripped Emergency Diesel Generator.

91 12 02/15/91 . Potential Loss of Net Positive Suction Head (NPSH) of Standby Liquid Control System Pumps.

91-13 03/04/91 Inadequate Testing of Emergency Diesel Generators (EDGs) 91-14 03/05/91 Recent Safety-Related Incidents at Large Irradiators.

91-17 03/11/91 Fire Safety of Temporary Interface Installations of Services.

91-19 03/12/91 High Energy Piping Failures Caused by Wall Thinning.

91-22 03/19/91 Four Plant Outage Events Involving Loss of AC Power or Coolant Spills, 91-23 03/26/91 Accident Radiation Interface Overexposures to Personnel Due to Industrial Radiography Accessory Equipment Malfunctions.

91-29 04/15/91 Deficiencies Identified During Electrical Distribution System Functional Inspections.

91-33 05/31/91 Reactor Safety Information for Interface States During Exercises and Emergencies.

91-34 06/03/91 Potential Problems in Identifying Causes of Emergency Diesel Generator Malfunctions.

91-37 06/10/91 Compressed Gas Cylinder Interface Missile Hazards.

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I N S G Gt.~t D(Cowi) 91 38 06/13/91 Thermal Stratification in Feedwater System Piping.

91 40 06/19/91 Contamination of Interfaco Nonradioactive System and Resulting Possibility for Unmonitored Uncontrolled Release to the Environment.

91-41 06/27/91 Potential Problems with the Interface Use of Freeze Seals.

91-42 07/27/91 Plant Outage Events Involving Interface Poor Coordination Between Operations and Maintenance Personnel During Valve Testing and Manipulations.

91-46 07/18/91 Degradation of Emergency Interface Diesel Generator Fuel Oil Delivery Systems.

91-47 08/06/91 Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test.

91 49 08/15/91 Enforcement of Safety Interface Requirements for Radiographers.

91 50 08/20/91 A Review of Water Hammer Events After 1985.

91-51 08-20/91 Inndequate Fuse Control Interface Ptsgrams.

91-57 09/19/91 Operational Experience on Bus Transfers.

91-58 09/20/91 Dependency of Offset Disc outterfly Valve's Operation of Orientation With Respect to Flow.

91-59 09/23/91 Problems With Access Interface Authorization Programs.

91-60 11/01/91 Reissuance of Information Interface Notice 91-60: False Alarms of Alarm Ratemeters Because of Radio Frequency Interference.

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. . ( N s srcT o ( co w7 )

'1 61 9 09/30/91 Preliminary Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment.

91 63 10/03/91 Natural Gas Hazards at Fort Interface St. Vrain Nuclear Generating Station.

91 64 10/09/91 Site Area Emergency Resulting From a Loss of Non Class 1E Uninterruptible Power Supplies.

91-65 10/17/91 Emergency Access to Low Level Interface Radioactive Waste Disposal Facilities.

91 66 10/18/91 (1) Erroneous Date in " Nuclear Safety Guide, TID 7016, Revision 2," (NUREG/CR-0095, ORNL/NUREG/CSD-6 (1978) And (2) Thermal Scattering Data Limitation in the Cross-Section Sets Provided With the Keno and Scale Codes.

91 68 10/28/91 Careful Planning Significantly Interface Reduces the Potential Adverse Impacts of Loss of Offsite Power Events During Shutdown.

91 72 11/19/91 Issuance of a Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

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.=

ABM meimc i Standard Plant ggy,_c 4

Table 1.8 22 EXPERIENCE INFORMATION APPLICABLE TO ABWR (Continued) 1YPE: NUREG Issue ,

i F_g, Dalg. Ihlg Comment 1150 6/89- Severe Au:ident Risks: An assessment for Five U.S.

Nudcar Power Plants, Vol.1 & 2.

1161 5/80 Recommended Revisions to USNRC Seismic Design Subsection Criteria 19B.2.27 1174 5/89 Evaluation of Systems Interactions in Nuclear Subsection Power Plants 19B.23 3_

1212 6/86 Status of Maintenance in the US Nuclear Power ladustry 1985 Vol.1,2 1216 8/86 Safety Evaluation PP2 Related to Operability and Reliability of Emergency Diesel Generators 1217 4/88 Evaluation of Safety implications of Control Systems Subsection in LWR Nuclear Powcx Plants Techaical Findings 19B.2.5

- Related to USI A-47

-1218 4/88 ' Regulatory Analysis for Resolution of1.'SI A 47 Subsection 19B.2.5 1229 8/89 Regulatory Analysis for Resolution of USI A 17 Subse':rion 19B.2.3 & 19B2.27 1233 9/89 Regulatory Analysis for USI A-O Subsection 10B.2.27 l 1273 4/88 Containment Integrity Check Tech: cal Finds Regulatory Analysis 1289 11/88 Regulatory and Eackfit Analysis: Unresc!ved Safety Subsection Issue A-45, Shutdown Dec.4/ Heat RernovalRequirements 19B.2.29

[c'er

-Fier Review of High Level Nuclear Waste 1296- 2/88 1341 5/89 Regulatory Analysis for Resolution of Generic Issue 115, Enhancement 1353' 4/89 Regulatory Analysis for the Resolution of Generic Subsection Issue 82,"Beyond Design Basis Accidents in Spent 19B.2.14 Fuel Pools" 1370 9/89 Resolution of USI A-48 ' **

}3Tf p/9l l/glyme 4; ftp}e#Ce fec]}ZC$ g Kero r t- ,SolenidOpd'rghkjdfrrek/ Valve & bless I 'i W90 Resoldhn o f Sterre fafe fisee 29: I"bf' *lA "

P Boffin 7 efrada Abs or f*e re in IU'A'IA xmum.ug L8-90 f'ec/cer f6 w W f/ariff

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4 23A6t00AC 4: Standard Plant arv c Table 1.8 22 EXPERIENCE INFORMATION APPLICABLE TO ABWR (Continued)

TYPE: NUREG issue He, Dalt Iltle Comment CR 3922 1/85 Survey and Evaluation of System Interaction Events Subsection and Sources Vol.1,2 19B.2.3 i CR 4261 3/86 Assessment of Systems Interactions in Nuclear Power Subsection Plants 19B.2.3 CR-4262 5/85 Effects of Control System Failures on Transients, Accidents at a GE BWR Vol.1 and 2 CR 4387 12/85 Effects of Control System Failures on Transient and Accidents and Core-Melt Frequencies at a GE BWR CR-4470 5/86 Survey and Evaluation of Vital Instrumentation and i Control Power Supply Events CR 5055 5/88 Atmospheric Diffusion for Control Room Habitability Subsection Assessment 19B 2.31 CR 5088 1/89 Fire Risk Scoping Study: InvestigaCon of Nuclear  ;

Power Plant Fire Risk, including Previously Unaddressed Issues. .

CR 5112 3/89 Evolution of Boiling Water Reactor Water Level Subsection Sensing Line Break and Single Failure 19B.2.16 r

CR-5230 4/89 Shutdown Decay Heat Removal Analysis: Plant Case Subsection-Studies and SpecialIssues 19B.2.29 CR 5347 6/89 Recommendations for Resolution of Public Comments Subsection on USI A-40 19B.2.27 CR 5458 12/89 Value Impact Assess for Candidate Operating Procedure Upg-ade Program en.94,/4 ffkr frecuor's to S k&;rI . Severe Gre Pwore t?cc i.len h Jerres Amendment.P" 18-9t c . . .. ..

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