IR 05000416/2002003
| ML021290660 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/09/2002 |
| From: | Marschall C NRC/RGN-IV/DRS/EMB |
| To: | Eaton W Entergy Operations |
| References | |
| IR-02-003 | |
| Download: ML021290660 (25) | |
Text
May 9, 2002
SUBJECT:
GRAND GULF NUCLEAR STATION - NRC INSPECTION REPORT 50-416/02-03
Dear Mr. Eaton:
On April 5, 2002, the NRC completed an inspection at your Grand Gulf Nuclear Station. The enclosed report documents the inspection findings, which were discussed on April 4, 2002, with Mr. J. B. Edwards, General Manager, Plant Operations, and other members of your staff.
A supplemental exit meeting was conducted by telephone on April 25, 2002, with Mr. J. B. Edwards, General Manager, Plant Operations, and other members of licensee management.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and your response will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Charles M. Marschall, Chief Engineering and Maintenance Branch Division of Reactor Safety Docket: 50-416 License: NPF-29
Entergy Operations, Inc.
-2-
Enclosure:
NRC Inspection Report 50-416/02-03
REGION IV==
Docket:
50-416 License:
NPF-29 Report No:
50-416/ 02-03 Licensee:
Entergy Operations, Inc.
Facility:
Grand Gulf Nuclear Station Location:
Waterloo Road Port Gibson, Mississippi 39150 Dates:
March 18 through April 5, 2002 Team Leader:
L. E. Ellershaw, Senior Reactor Inspector, Engineering Maintenance Branch Inspectors:
P.A. Goldberg, Reactor Inspector, Engineering Maintenance Branch J.F. Melfi, Reactor Inspector, Engineering Maintenance Branch R. P. Mullikin, Senior Reactor Inspector, Engineering Maintenance Branch R. L. Nease, Senior Reactor Inspector, Engineering Maintenance Branch C. J. Paulk, Senior Reactor Inspector, Engineering Maintenance Branch Accompanying Personnel:
J. L. Taylor, Reactor Inspector, Engineering Maintenance Branch G. Miller, Reactor Inspector, Engineering Maintenance Branch Approved By:
Charles S. Marschall, Chief Engineering Maintenance Branch Division of Reactor Safety
-2-SUMMARY OF FINDINGS IR 05000416-02-03 on 03/18-04/05/2002; Entergy Operations, Inc., Grand Gulf Nuclear Station, safety system design and performance capability, and evaluation of changes, tests, or experiments.
The inspections were conducted by six regional inspectors. No findings of significance were identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) and determined by using Inspection Manual Chapter 0609, "Significance Determination Process (SDP)." Findings for which the SDP does not apply are indicated by "No Color" or by the severity level of the applicable violation. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described at its Reactor Oversight Process website at http://www.nrc.gov/NRR/OVERSIGHT/index.html.
Report Details
REACTOR SAFETY Introduction A team inspection was performed to verify that facility safety system design and performance capability were adequate and that the initial design and subsequent modifications have preserved the current design basis of the systems selected for review. The scope of the review also included any necessary nonsafety-related structures, systems, and components that provided functions to support safety functions. The inspection effort also reviewed the licensees programs and methods for monitoring the capability of the selected systems to perform the current design basis functions. This inspection verified aspects of the initiating events, mitigating systems, and barrier cornerstones.
The probabilistic risk assessment model for Grand Gulf Nuclear Station is based on the capability of the as-built safety systems to perform their intended safety functions successfully. The area and scope of the inspection were determined by reviewing the licensees probabilistic risk analysis models to identify the most risk significant systems, structures, and components according to their ranking and potential contribution to dominant accident sequences and/or initiators. Deterministic effort was also applied in the selection process by considering recent inspection history, recent problem area history, and all modifications developed and implemented within the past 3 years. The team reviewed in detail the standby service water system. The primary review prompted parallel review and examination of support systems, such as, electrical power, instrumentation, room cooling systems, and related structures and components.
The objective of this inspection was to assess the adequacy of calculations, analyses, engineering processes, and engineering and operating practices that were used to support the performance of the safety systems selected for review and the necessary support systems during normal, abnormal, and accident conditions. Acceptance criteria utilized by the NRC inspection team included NRC regulations, the technical specifications, applicable sections of the Final Safety Analysis Report, applicable industry codes and standards, as well as, industry initiatives implemented by the licensees programs.
An inspection to assess the performance of the licensee's program to meet the regulatory requirements of 10 CFR Part 50.59, "Changes, Tests, And Experiments," was also conducted by one member of the team during the first week of the inspection.
1R02 Evaluations of Changes, Tests, or Experiments (71111.02)
a.
Inspection Scope The inspectors reviewed a selected sample of 8 safety evaluations to verify that the licensee had appropriately considered the conditions under which the licensee may make changes to the facility or procedures or conduct tests or experiments without prior NRC approval. In addition, the inspectors reviewed Procedure LI-101, 10CFR50.59 Review Program, Revision 2, which implemented the new safety evaluation program.
-2-The team reviewed a selected sample of 12 safety evaluation screenings, in which the licensee determined that safety evaluations were not required, to ensure that the licensees exclusion of a full evaluation was consistent with the requirements of 10 CFR 50.59, "Evaluations of Changes, Tests, or Experiments."
The team reviewed 10 condition reports initiated by the licensee that addressed problems or deficiencies associated with 10 CFR 50.59 requirements to ensure that appropriate corrective actions were being taken.
b.
Findings No findings of significance were identified.
1R21 Safety System Design and Performance Capability (71111.21)
.1 System Requirements a.
Inspection Scope The team reviewed the following attributes for the standby service water system:
(1) process medium (water, steam, and air), (2) energy sources, (3) control systems, and (4) equipment protection. The team verified that procedural instructions to operators were consistent with operator actions required to meet, prevent, and/or mitigate design basis accidents. The review also considered requirements and commitments identified in the Final Safety Analysis Report, technical specifications, design basis documents, and plant drawings. These reviews further verified that required support functions for the standby service water system would be available.
b.
Findings No findings of significance were identified.
.2 System Condition and Capability a.
Inspection Scope The team reviewed the periodic testing procedures for the standby service water system to verify that the design requirements were adequately demonstrated. The team reviewed the environmental qualification of a sample of system components to verify the capability to operate under design environmental conditions and the assumed operating parameters including: voltage, speed, power, flow, temperature, and pressure.
The team also reviewed the systems operations by conducting system walkdowns; reviewing normal, abnormal, and emergency operating procedures; and reviewing the Final Safety Analysis Report, technical specifications, design calculations, drawings, and procedures.
-3-b.
Findings No findings of significance were identified.
.3 Identification and Resolution of Problems a.
Inspection Scope The team reviewed a sample of problems identified by the licensee in the corrective action program to evaluate the effectiveness of corrective actions related to design issues. The sample included open and closed condition reports written or initiated in the past 3 years that identified issues related to or affecting the standby service water system.
The team also reviewed a sample of deficiency reports concerning the standby service water system which documented deficiencies resulting from the licensees review of their Final Safety Evaluation Report. The team reviewed these deficiency reports to verify that condition reports were written in accordance with the corrective action program as appropriate.
b.
Findings No findings of significance were identified.
.4 System Walkdowns a.
Inspection Scope The team performed walkdowns of the accessible portions of the standby service water system as well as the required support systems. The walkdowns focused on the installation and configuration of power supplies, piping, components, and instruments.
During the walkdowns, the team assessed:
The placement of protective barriers and systems,
The susceptibility to flooding, fire, or environmental conditions,
The physical separation of trains and the provisions for seismic concerns,
Accessibility and lighting for any required local operator action,
The material condition and preservation of systems and equipment, and
The conformance of the currently installed system configurations to the current design and licensing bases.
-4-b.
Findings No findings of significance were identified.
.5 Design Review a.
Inspection Scope The team reviewed the current as-built instrumentation and control, electrical, and mechanical design of the standby service water system. These reviews included a review of design assumptions, calculations, required system thermal-hydraulic performance, electrical power system performance, protective relaying, and instrument setpoints and uncertainties. The team also performed a single failure review of individual components to determine the effects of such failures on the capability of the systems to perform their design safety functions.
The team reviewed calculations, drawings, specifications, vendor documents, Final Safety Analysis Report, technical specifications, emergency operating procedures, and temporary and permanent modifications.
b.
Findings No findings of significance were identified.
.6 Safety System Inspection and Testing a.
Inspection Scope The team reviewed the program and procedures for testing and inspecting selected components in the standby service water system. The review included the results of surveillance tests required by the technical specifications.
b.
Findings No findings of significance were identified.
.7 Generic Letter 89-13 Commitments a.
Inspection Scope The team reviewed the implementation of the licensees commitments made in response to Generic Letter 89-13, Service water System Problems Affecting Safety-Related Equipment, as documented in the licensees letter dated January 29, 1990. The review included procedures, and the results of surveillance tests and maintenance activities.
-5-b.
Findings No findings of significance were identified.
OTHER ACTIVITIES (ZA)
4OA6 Management Meetings Exit Meeting Summary The team leader presented the inspection results to Mr. J. B. Edwards, General Manager, Plant Operations, and other members of licensee management at the conclusion of the onsite inspection on April 4, 2002.
At the conclusion of this meeting, the team leader asked the licensees management whether any materials examined during the inspection should be considered proprietary.
No proprietary information was identified.
A supplemental exit meeting was conducted by telephone on April 25, 2002, with Mr. J.
B. Edwards, General Manager, Plant Operations, and other members of licensee management.
ATTACHMENT Licensee Contacts :
D. Barfield, Manager, Design Engineering C. Bottemiller, Manager, Licensing F. Brown, Senior Engineer, Electrical, Instrumentation and Controls M. Causey, System Engineer N. Deshpande, Supervisor, Design Engineering W. Eaton, Vice President J. Edwards, General Manager, Plant Operations D. Franklin, Supervisor, System Engineering A. Gallagher, Mechanical Engineer, Desing Engineering T. Holcombe, Shift Manager, Operations C. Holifield, Senior Licensing Engineer M. Humphries, Supervisor, Electrical, Instrumentation and Controls G. Ingram, Licensing Engineer G. Lantz, Senior Staff Engineer M. Renfroe, Manager, Engineering Programs and Components J. Roberts, Director, Nuclear Safety Assurance G. Sparks, Manager, Operations D. Wiles, Acting Engineering Director D. Wilson, Design Engineer R. Wright, Supervisor, System Engineering H. Yeldell, Manager, System Engineering NRC:
T. Hoeg, Senior Resident Inspector C. Marschall, Chief, Engineering and Maintenance Branch Documents Reviewed Licensing Document Change Requests 2001-083, Revise basis of Technical Specification surveillance requirements, May 23, 2001 2001-089, Fuel pool cooling and cleanup system, September 26, 2001 2001-090, Remove un-necessary details concerning procedures, June 4, 2001 2001-141, Loose parts detection system, August 27, 2001 2001-178, Modification of Inboard MSIV-LCS, November 13, 2001 10CFR 50.59 Safety Evaluations 2002-0001-R0, January 10, 2002 2002-0001-R1, January 15, 2001 2001-0073-R0, December 10, 2001 2001-0054-R00, June 4, 2001 2001-0059-R0, June 12, 2001 2001-0240-000-00, June 14, 2001 2001-0072-R0, August 31, 2001 2000-0086-00-02, January 9, 2000
-2-Specifications 9645-E-029.0, Technical Specification for 9000-Volt Power Cable 9645-E-030.2, Technical Specification for 600-Volt Multiconductor Control Cable Drawings 1A0AP41A,E,F and Q1P41C001A-A, Cable and raceway routing list for cables 1061A, Standby Service Water System, Unit 1, Revision 55 1061B, Standby Service Water System, Unit 1, Revision 43 1061C, Standby Service Water System, Unit 1, Revision 34 1061D, Standby Service Water System, Unit 1, Revision 35 1072A, Plant Service Water System, Unit 1, Revision 36 1072F, Plant Service Water System, Unit 1, Revision 8 E-0121-01, Revision 8 and DRN 7684 E-0121-02, Revision 8 and DRN 3139 E-0121-03, Revision 8 and DRN 7685 and 6702 E-0121-04, Revision 10 E-0663, Enlarged Site Raceway Plans, Revision 17 E-0665, Electrical Manhole Plans, Revision 12 E-0674, Enlarged Site Raceway Plans, Revision 17 E-0688, Raceway Plan Control Bldg. El. 111-0" Area 25A Unit 1, Revision 41 E-0690, Raceway Plan Control Bldg. Elev. 148-0" Area 25A, Revision 42 E-0701, Raceway Plan Control Building El. 111-0" Area 25B Unit 2, Revision 28 E-1052, Lube Oil Cooler #2020 Type SP - One Pass, Revision 2 E-1053, #2422 - Type SP - One Pass Jacket Water Cooler, Revision 15 E-1225-001, Standby Service Water Control System A, Revision 12 E-1225-002, Standby Service Water Control System B, Revision 13
-3-E-1225-003, P41 Standby Service Water System SSW Pump C0001A Unit 1, Revision 16 E-1225-009, Standby Service Water Recirculation to Basin MOV F006A-A, Revision 7, 8, and 12 E-1225-023, HPCS Standby Service Water Pump C001C, Revision 7, 8, and 17 E-1228-007, Service Water System Cross Tie MOV F067-B, Revision 8 E-1266-02, Y47 SSW Pump House Vent System SSW PMP HSE Fan Return Mod F001B-B, Revision 9 E-1266-03, Y47 SSW Pump House Vent System SW PMP HSE Fan Return Mod F003B-B, Revision 10 E-1266-04, Y47 SSW Pump House Vent System SSW PMP HSE Fan Intake Mod F002B-B, Revision 12 E-1288-002, RSS Transfer Panel Relays R1-R2, Revision 4 E-1716, Raceway Plan Standby Service Water Cooling Towers No. 1 & No. 2, Revision 19 E-7100, Raceway Plan Standby Service Water Cooling Towers No. 1 & No. 2, Revision 3 J-1321 Sh 6, P41 Trip Unit Fault Monitor, Revision 3 J-1321 Sh 7, P41 HPCS Service Water, Revision 7 J-1321 Sh 8, P41 Computer Interface, Revision 7 J-1321 Sh 9, P41 Computer Interface, Revision 7 J-1321-000, P41 Standby Service Water System Index, Revision 23 J-1321-001, P41 Power Distribution, Revision 14 J-1321-002, P41 Standby Service Water Loop A Leak Detection, Revision 10 J-1321-003, P41 Standby Service Water Loop B Leak Detection, Revision 11 J-1321-004, P41 Standby Service Water Pressure Basin Level & Temperature, Revision 6 J-1321-005, P41 Standby Service Water Pressure Basin Level & Temperature, Revision 7 J-1358 Sh 1, Y47 Power Distribution, Revision 3 J-1358-000, Y47 Standby Service Water Pump House Vent. System Index, Revision 6 J-1358-002, Y47 Standby Service Water Pump House A & B Temperature, Revision 5
-4-J-1358-003, Y47 Standby Service Water Pump House A Temperature, Revision 4 M-7207A, Standby Service Water System M.I.C. Inspection Locations, Revision 2 M-7207B, Standby Service Water System M.I.C. Inspection Locations, Revision 4 M-7207C, Standby Service Water System M.I.C. Inspection Locations, Revision 3 M-7207D, Standby Service Water System M.I.C. Inspection Locations, Revision 4 M-7207E, Standby Service Water System M.I.C. Inspection Locations, Revision 2 M0030B, Legend, Units 1 & 2, Revision 4 SFD-1061E, System Flow Diagram - Standby Service Water System, Revision 1 Protective Relaying and Coordination Curves PR28, R1, PR for Bus 15AA Incoming Feeder Breakers, June 24, 1999 PR53, R1, Relay Setting for SSW Pump Motor per DCP 8215020 PR63, R0, Relay Setting, Ground Sensing Relays, August 2, 1979 PR63A, R0, Ground Overcurrent Relay on Diesel Generator, February 14, 1978 PR143, R0, Relay Settings (Loss of Excitation Relay for DG), June 12, 1978 PR144, R0, Underfrequency Relays on Diesel Generators, June 9, 1978 PR145, R0, Relay Settings (Reverse Power Relay Device #132 on Diesel Generator),
June 15, 1978 PR146, R0, Diesel Generator Overcurrent Relay, June 7, 1978 Design Changes ER-GG-2000-0086-000, Provide engineering evaluation in response to CR 1999-1505. PSW thin wall piping in SSW A and B, Revision 2 ER-GG-2000-0240-000, Provide new fill location for existing SLC test barrels, October 1, 2000 Engineering Request 97-0330-02, Evaluation of SSW Basin Concrete, Revision 0
-5-Condition Reports CR-GGN-1996-00552 CR-GGN-1998-00995 CR-GGN-1999-00341 CR-GGN-1999-00742 CR-GGN-1999-00742 CR-GGN-1999-01264 CR-GGN-1999-01863 CR-GGN-1999-00419 CR-GGN-1999-00992 CR-GGN-1999-00360 CR-GGN-1999-01505 CR-GGN-2000-01459 CR-GGN-2000-00322 CR-GGN-2000-01107 CR-GGN-2000-01263 CR-GGN-2000-00822 CR-GGN-2001-00443 CR-GGN-2001-01100 CR-GGN-2001-01136 CR-GGN-2001-01184 CR-GGN-2001-01501 CR-GGN-2001-01944 CR-GGN-2001-00461 CR-GGN-2001-00130 CR-GGN-2001-00115 CR-GGN-2001-00841 CR-GGN-2001-01705 CR-GGN-2001-01714 CR-GGN-2001-01738 CR-GGN-2001-01849 CR-GGN-2001-00446 CR-GGN-2001-00023 CR-GGN-2001-00413 CR-GGN-2001-00488 CR-GGN-2001-00490 CR-GGN-2001-00591 CR-GGN-2001-01103 CR-GGN-2002-00226 CR-GGN-2002-00296 CR-GGN-2002-00300 CR-GGN-2002-00389 CR-GGN-2002-00511 CR-GGN-2002-00246 Discrepancy Forms D-9.2.1.3-2, Revision 1 D-9.2.1.3-3, Revision 1 D-9.2.1.3-4, Revision 1 D-9.2.1.3-7, Revision 0 D-9.2.1.3-9, Revision 1 D-9.2.1.3-10, Revision 0 D-9.2.1.3-14, Revision 0 D-9.2.1.3-20, Revision 0 D-9.2.1.3-29, Revision 1 D-9.2.5.2.-1, Revision 0 D-9.2Table 9.2-2-1, Revision 1 D-9.2Table9.2-5a-2, Revision 0 D-9.2Table9.2-6a-2, Revision 0 D-9.2Table9.2-17-1, Revision 0 D-9.2Table9.2-17-2, Revision 1 RG1.2.27-1, Revision 0 RG1.2.27-2, Revision 0 RG1.2.27-3, Revision 0 RG1.2.27-4, Revision 0 RG1.2.27-5, Revision 0 Procedures 01-S-03-10, GGNS Condition Report," Revision 1 04-1-01-E32-1, System Operating Instruction Main Steam Isolation Valve Leakage Control System Safety Related, Revision 26 04-1-01-P41-1, System Operating Instruction - Standby Service Water System, Revision 115 04-1-03-A30-1, Equipment Performance Instruction Cold Wether Protection Non-Safety Related, Revision 13 04-1-03-P41-1, Equipment Performance Instruction - SSW A Chemical Addition Run, Revision 2 04-1-03-P41-2, Equipment Performance Instruction - SSW B Chemical Addition Run, Revision 1
-6-04-1-03-P41-3, Equipment Performance Instruction - SSW C Chemical Addition Run, Revision 1 04-1-03-P46-1, Equipment Performance Instruction - A ESF Switchgear Room Coolers Flow Test, Revision 16 04-1-03-P46-2, Equipment Performance Instruction - B ESF Switchgear Room Coolers Flow Test, Revision 16 04-1-03-Z51-1, Equipment Performance Instruction - A Control Room Air Conditioner Flow Test, Revision 11 04-1-03-Z51-2, Equipment Performance Instruction - B Control Room Air Conditioner Flow Test, Revision 5 05-1-02-I-1, Off-Normal Event Procedure - Reactor Scram, Revision 109 05-1-02-II-1, Off-Normal Event Procedure shutdown from the Remote Shutdown Panel Safety Related, Revision 25 05-1-02-V-11, Off-Normal Event Procedure - Loss of Plant Service Water, Revision 21 05-ME-1000-R-0003, Safety and Relief Valve Functional Test, Revision 103 05-ME-1P41-R-0001, Internal Valve Inspection P41F-F174, Revision 101 06-CH-1000-V-0038, Surveillance Procedure Diesel Fuel Oil Receipt Analysis Safety Related, Revision 103 06-IC-1B21-Q-1014, Surveillance Procedure ADS Air Receiver Low Pressure Functional Test Safety Related, Revision 100 06-IC-1E31-Q-0021, Surveillance Procedure LPCS/RHR/HPCS Header Differential Pressure Functional Test Safety Related, Revision101 06-OP-1000-D-0001, Daily Operating Logs, Revision 112 06-OP-1B21-C-0004, Surveillance Procedure ADS Air System Valve Tests Safety Related, Revision 104 06-OP-1B21-V-0001, Surveillance Procedure MSIV Operability Test Safety Related, Revision 107 06-OP-1E51-Q-0002, Surveillance Procedure RCIC System Valve Operability Test Safety Related, Revision 106
-7-06-OP-1E51-Q-0003, Surveillance Procedure RCIC System Quarterly Pump Operability Verification Safety Related, Revision 113 06-OP-1P41-M-0004, Standby Service Water (SSW) Loop A Operability Check, Revision 107 06-OP-1P41-Q-0004, Standby Service Water Loop A Valve and Pump Operability Test, Revision 111 06-OP-1P41-Q-0005, Standby Service Water Loop B Valve and Pump Operability Test, Revision 114 06-OP-1P41-Q-0006, HPCS Service Water Valve and Pump Operability Test, Revision 105 06-OP-1P42-Q-0001, CCW Fuel Pool Heat Exchanger Valve Test, Revision 101 06-OP-1P72-C-0002, Drywell Chilled Water Cold Shutdown Valve Test, Revision 101 07-S-13-11, General Maintenance Instruction Calibration/Calibration Check of Thermocouple Points, Revision 9 07-S-13-41, General Maintenance Instruction Non-Modulating Pneumatic Valves Low Pressure Switch, Revision 2 07-S-14-395, General Maintenance Instruction Safety and Relief Valve Program Safety Related, Revision 4 07-S-53-19, Calibration of Bailey 771 Chart Recorder, Revision 5 07-S-53-25, Bailey Type 744 Difference Alarm Unit, Revision 2 07-S-53-38, Maintenance Calibration Instruction Rosemount 1151, 1152, and 1153 Pressure Transmitters, Revision 7 07-S-53-335, Maintenance Calibration Instruction Calibration of Westronics Recorders, Revision 2 07-S-53-P41-3, Loop Calibration Instruction SSW Basin A and B Level Control, Revision 2 07-S-53-P41-8, Loop Calibration Instruction Standby Service Water Pump Discharge Flow, Revision 10 07-S-53-P41-10, Loop Calibration Instruction Standby Service Water Basin Level Indication, Revision 7 07-S-53-P41-12, Loop Calibration Instruction HPCS SW Flow and SW Leakage High, Revision 10
-8-07-S-53-P41-14, Loop Calibration Instruction HPCS Service Water Pump Discharge Pressure, Revision 8 07-S-53-Y47-1, Loop Calibration Instruction Standby Service Water Pump House Ventilation Temperature, Revision 5 08-S-03-10, Chemistry Procedure - Chemistry Sampling Program, Revision 31 08-S-03-14, Chemistry Procedure - Chemistry Additions to Plant Systems, Revision 16 08-S-04-400, Chemistry Instruction - Chemistry Water Treatment Performance Monitors, Revision 1 17-S-06-21, Performance and System Engineering Instruction - ESF SWGR Room Cooler and Control Room AC Flow Trending Program, Revision 2 17-S-06-22, Performance and System Engineering Procedure - SSW A Performance, Revision 7 17-S-06-23, Performance and System Engineering Procedure - SSW B Performance, Revision 8 17-S-06-24, Performance and System Engineering Procedure - SSW A Performance, Revision 3 GGNS-MS-46, Program Plan for Monitoring Erosion/Corrosion in Moderate Energy Piping Components, Revision 2 GGNS-MS-51, Program Plan for Monitoring and Controlling Microbiologically Induced Corrosion (Safety Related), Revision 0 LI-102, Corrective Action Process," Revision 1 LL-101, 10CFR50.59 Review Program, Revision 2 LL-101, 10CFR50.59 Review Program, Revision 1-1A OE-100, Operating Experience Program, Revision 1 QAI 9.29, Radiographic Examination for Microbiological Induced Corrosion (MIC), Revision 4 Calculations 3.9.12, SGTS Infiltration Due to Pipe Break, Revision 2 EC-01R21-91041, Verification of Protective Coordination for 4.16 KV Div.II, Bus 16AB, Revision 0
-9-EC-Q1111-91039, Cable Amp Rating, Revision 0 JC-01Y7-N602-1, Instrument Loop Uncertainty & Setpoint Determination for System 1Y47 Loop N602 SSW Pump House Fan Damper Control, Revision 0 JC-Q1Y47-N602-1, Instrument Loop Uncertainty and Setpoint Determination for System 1Y47 Loop N602 SSW Pump House Fan Damper Control, Revision 0 MC-Q1P41-86007, Standby Service Water Ultimate Heat Exchanger Performance, Revision 0, and Supplement 1 MC-Q1P41-87215, "Evaluation of Low SSW (P41) Flow to the Standby Diesel Jacket Water Cooler," Revision 1 MC-Q1P41-97020, "Determination of Minimum Allowable SSW Flows (LOCA Lineup) to Safety Related Heat Exchangers," Revision 3 MC-Q1P41-97036, Determination of Fuel Pool Cooling & Cleanup Heat Exchanger Capability, Revision 0 MC-QSZ51-01001, "Determination of Control Room Heat Load at 90o F," Revision 0 MC-QSZ51-96006, "Thermal Performance Evaluation of the Control Room Air Conditioning System," Revision 1 Heat Exchanger Data Sheets Control Room A/B Air Conditioner Condensers Fuel Pool Cooling and Cleanup Heat Exchangers HPCS Diesel Generator Jacket Water Coolers RHR Heat Exchangers Standby Diesel Generator A/B Jacket Water Coolers Work Order 00199421 Maintenance Action Items 220259 250769 259055 259523 259524 260027 267515 270188 271031 272095 274993 275010 275013 281954 281955 281956 281957 282672 284609 287096 288354 292129 299815 305630
-10-Inservice Test Documents GGNS-01-002, Engineering Report for Testing Requirements of P44-F052, Revision 0 CEP-IST-1, Inservice Testing Bases Document, Entergy Nuclear South, Revision 2B Standby Service Water Pump B (1P41C001B) Inservice Testing Performance, 2/28/02 Summary of results for standby service water pressure relief valves for refueling outage 10 Summary of results for standby service water pressure relief valves for refueling outage 11 Miscellaneous Documents Desktop Guidelines, Updated Final Safety Analysis Report Consistency Review Project, Identification and Documentation of Discrepancies, dated September 30, 1997 Fire Pre-Plan A-04, Revision 1 Letter to the U.S. Nuclear Regulatory Commission from Entergy, providing their response to the NRC's request for information concerning the Grand Gulf Nuclear Station, pursuant to 10 CFR 50.54(f), dated February 6, 1997 Letter to the U.S. Nuclear Regulatory Commission from Entergy, providing an update on their review of the Grand Gulf Nuclear Station Updated Final Safety Analysis Report, dated December 28, 1999 Licensees January 29, 1990, letter to NRC in response to Generic Letter 89-13 Report on Engineering Self Assessment of the Grand Gulf Standby Service Water System, March 14, 2002 Results of "SSW 'B' Performance - Thermal Performance Test," July 17, 2001 Results of Technical Special Test Instruction TSTI SZ51-00-001-O-S, "Control Room Air Conditioning Unit Z51B002B Assumed Heat Load Demonstration," completed May 11, 2000 Specification No. M-500.0, Fire Hazards Analysis, Revision 12 Standard No. GGNS-MS-39.0, Revision 1 Summary of thermal performance test results for all safety-related heat exchangers Vendor Manual 460002161, Model 86 Temp-Matic Thermocouple Monitor, Revision 1