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Category:Inspection Report
MONTHYEARIR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 IR 05000259/20234022023-06-12012 June 2023 Material Control and Accounting Program Inspection Report 05000259 2023402, 05000260 2023402 and 05000296 2023402 IR 05000259/20230912023-05-0808 May 2023 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter; NRC Inspection Report 05000259/2023091 IR 05000259/20230012023-05-0303 May 2023 Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001 IR 05000259/20234402023-03-23023 March 2023 Special Inspection Supplemental Report 05000259 2023440 and 05000260 2023440 and 05000296 2023440 Cover Letter IR 05000259/20234012023-03-0808 March 2023 Security Baseline Inspection Report 05000259 2023401 and 05000260/2023401 and 05000296/2023401 IR 05000259/20230902023-03-0202 March 2023 NRC Inspection Report 05000259/2023090 and 05000260 2023090 and Preliminary White Finding and Apparent Violation IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 IR 05000259/20220042023-02-0707 February 2023 Integrated Inspection Report 05000259/2022004, 05000260/2022004 and 05000296/2022004 IR 05000259/20220032022-11-0909 November 2022 Browns Perry Nuclear Plant - Integrated Inspection Report 05000259/2022003, 05000260/2022003 and 05000296/2022003 IR 05000259/20220122022-09-20020 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012 IR 05000259/20220112022-09-16016 September 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000259/2022011 and 05000260/2022011 and 05000296/2022011 IR 05000259/20224022022-09-0606 September 2022 Security Baseline Inspection Report 05000259/2022402 and 05000260/2022402 and 05000296/2022402 Cover Letter IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 IR 05000259/20220022022-08-0808 August 2022 Integrated Inspection Report 05000259/2022002, 05000260/2022002 and 05000296/2022002 IR 05000259/20224202022-07-19019 July 2022 Security Baseline Inspection Report 05000259/2022420, 05000260/2022420 and 05000296/2022420 ML22181A9562022-06-29029 June 2022 Bf Report 2022-401 Base Public Cover Letter ML22173A1622022-06-21021 June 2022 Replacement Steam Dryer Visual Inspection Results (U3R20) IR 05000259/20220012022-05-12012 May 2022 Integrated Inspection Report 05000259/2022001, 05000260/2022001, 05000296/2022001 and Exercise of Enforcement Discretion IR 05000259/20220102022-03-30030 March 2022 Triennial Fire Protection Inspection Report 05000259/2022010 and 05000260/2022010 and 05000296/2022010 and Apparent Violation IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 IR 05000259/20210042022-01-31031 January 2022 Integrated Inspection Report 05000259/2021004, 05000260/2021004 and 05000296/2021004 IR 05000259/20214032022-01-19019 January 2022 NRC Inspection Report 05000259/2021403, 05000260/2021403 and 05000296/2021403 IR 05000259/20214022022-01-18018 January 2022 Brows Ferry Nuclear Plant - Security Baseline Inspection Report 05000259/2021402 and 05000260/2021402 and 05000296/2021402 IR 05000259/20210032021-11-0909 November 2021 Integrated Inspection Report 05000259/2021003, 05000260/2021003, 05000296/2021003 and 07200052/2021001 IR 05000259/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000259/2021401 and 05000260/2021401 and 05000296/2021401 IR 05000259/20210112021-08-24024 August 2021 Temporary Instruction 2515/TI-193 Inspection Report 05000259/2021011, 05000260/2021011, and 05000296/2021011 IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 ML21217A2832021-08-0505 August 2021 Resident Integrated Inspection Report 2021-002 IR 05000259/20213012021-07-28028 July 2021 NRC Operator License Examination Report Nos. 05000259/2021301, 05000260/2021301, 05000296/2021301 IR 05000259/20210102021-07-26026 July 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 IR 05000259/20204012021-05-26026 May 2021 Security Baseline Inspection Report 05000259/2020401 and 05000260/2020401 and 05000296/2020401(U) IR 05000259/20210012021-04-28028 April 2021 Integrated Inspection Report 05000259/2021001, 05000260/2021001 and 05000296/2021001 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 IR 05000259/20200042021-01-28028 January 2021 Integrated Inspection Report 05000259/2020004, 05000260/2020004, 05000296/2020004, 07200052/2020002 and Exercise of Enforcement Discretion IR 05000259/20204022021-01-0808 January 2021 Material Control and Accounting Program Inspection Report 05000259/2020402, 05000260/2020402 and 05000296/2020402 IR 05000259/20200032020-11-10010 November 2020 Integrated Inspection Report 05000259/2020003, 05000260/2020003 and 05000296/2020003 IR 05000254/20200032020-11-0909 November 2020 Integrated Inspection Report 05000254/2020003; 05000265/2020003 and 07200053/2020001 IR 05000259/20200112020-10-26026 October 2020 Biennial Problem Identification and Resolution Inspection Report 05000259/2020011, 05000260/2020011 and 05000296/2020011 IR 05000259/20204042020-09-29029 September 2020 NRC Security Inspection Report 05000259/2020404 and 05000260/2020404 and 05000296/2020404 and Apparent Violation (U) IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 IR 05000259/20200022020-08-0606 August 2020 Brown Ferry Nuclear Plant Integrated Inspection Report 05000259/2020002, 05000260/2020002, 05000296/2020002, and 07200052/2020001 IR 05000259/20200102020-06-19019 June 2020 Triennial Inspection of Evaluation of Changes, Test and Experiments Baseline Inspection Report 0500259/2020010 and 05000260/2020010 and 05000296/2020010 IR 05000259/20200012020-05-0707 May 2020 Integrated Inspection Report 05000259/2020001, 05000260/2020001, and 05000296/2020001 2023-08-29
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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830 Power Building TENNESSEE VALLEY AUTHORlTY CHATTANOOGA. TENNESSEE 37401 August 8, 1977 Mr. Norman C. Moseley, Director Office of Inspection and Enforcement U.ST Nuclear Regulatory Commission Region II Suite 1217 230 Peachtree Street, NW.
Atlanta, Georgia 30303
Dear Mr. Moseley:
This is in response to F. J ~ Long's July 19, 1977, letter, RII:JEO 50-259/77-8, 50-260/77-8, 50-296/77-8, which transmitted for our review an IE Inspection Report (same number) ~ We have reviewed that report and do not consider any part of it to be proprietary.
Very truly yours, J. E. Gilleland Assistant Manage of Power An Equal Opportunity Employer
0 0
RK00( UNITED STATES
~
(4~P,S Ip 0 NUCLEAR REGULATORY COMMISSION Cy g 1~
REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 0 ATLANTA,GEORGIA 30303 e
/p JUL 5. 9 1977 In Reply Refer To:
RII:JEO 50-259/77-8 50-260/77-8 50-296/77-8 Tennessee Valley Authority Attn: Mr. Godwin Williams, Jr.
Manager of Power 830 Power Building Chattanooga, Tennessee 37401 Gentlemen:
This refers to the inspection conducted by Mr. J. E. Ouzts of this office on June 30 July 1, 1977, of activities authorized by NRC License Nos. DPR-33, DPR-52 and DPR-68 for the Browns Ferry Unit 1, 2 and 3 facilities, and to the discussion of our findings held with Mr. J. G. Dewease at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the attached inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items of noncompliance were disclosed.
The licensee representative agreed to review the method he is currently using for deriving the feedwater signal from the feedwater flow instrument for use in the computer OD-3 program for core thermal power measurement and to report to NRC whether the current method was intended to be used in the original design.
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the attached inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office requesting that such information be withheld from public disclosure. If no proprietary information is identified, a written statement to that effect should be submitted. If an application is submitted, it must fully identify the bases for which information is claimed to be proprietary. The application should be prepared so that
Tennessee Valley Authority information sought to be withheld is incorporated in a separate paper and referenced in the application since the application will be placed in the Public Document Room. Your application, or written statement, should be submitted to us within 20 days. If we are not contacted as specified, the attached report and this letter may then be placed in the Public Document Room.
Should you have any questions concerning this letter, we will be glad to discuss them with you.
Very truly yours, F. J. Long, Chief Reactor Operations and Nuclear Support Branch Attachments:
RII Inspection Report Nos.
50-259/77-8, 50-260/77-8 and 50-296/77-8 cc: J. G. Dewease Plant Superintendent Box 2000 Decatur, Alabama 35602
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~P,R AEC0 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 230 PEACHTREE STREET, N.W. SUITE 1217 ATLANTA,GEORGIA 30303 4**~4 A endix A Report Nos.: 50-259/77-8, 50-260/77-8 and 50-296/77-8 Docket Nos.: 50-259, 50-260 and 50-296 License Nos.: DPR-33, DPR-52 and DPR-68 Licensee: Tennessee Valley Authority 818 Power Building Chattanooga, Tennessee 37401 Facility Name: Browns Ferry Units 1, 2 and 3 Inspection at: Browns Ferry site, Athens, Alabama Inspection conducted: June 30 and July 1, 1977 Inspector: J. E. Ouzt Reviewed by:
R. D. rtin, Chief D e Nuclear Support Section Reactor Operations and Nuclear Support Branch Ins ection Summar
~/>>-
Ins ection on June 30 Jul 1 1977 Re ort Nos. 50-259/77-8 Areas Ins ected: Routine, unannounced inspection of plant surveillance program, procedures and schedule pertaining to operations, emergencies, 50-260/77-8 maintenance and administration and review of APRM gain adjustment factor (GAF) data and the method used to obtain the feedwater flow signal for the process computer OD-3 program Thermal Power Measurement. The inspection involved 16 inspector-hours on site by one NRC inspector.
Results: Of the areas inspected no apparent items of noncompliance or deviations were identified.
l RII Rpt. Nos. 50-259/77-8, 50-260/77-8 and 50-296/77-8 DETAILS I Prepared by:
Ouzts, eactor Inspector Da e Nuclear Support Section Reactor Operations and Nuclear Support Branch Dates of Inspection: J e 30 July 1, 1977 Reviewed by:
R. D. rtin, C ief Nuclear Support Section Reactor Operations and Nuclear Support Branch
- 1. Persons Contacted
- J. E. Dewease, Plant Superintendent
- L. Blankner, Nuclear Engineer
- T. Bragg, QA Supervisor P. Crabb, Modifications Coordinator R. McGee, SI Coordinator Various Shift Engineers and Plant Operators
- Denotes those present at the exit interview.
- 2. Licensee Action on Previous Ins ection Findin s None
- 3. Unresolved Items (1) The APRM gain adjustment factors (GAFs) are higher than those given in Section 7 of the FSAR under the conditions they were taken. The inspector will discuss his findings with NRC management, and in addition will analyze more APRM dated prior to determing whether or not the maximum GAFs permitted are satisfactory with the present setpoints. This is identified as Unresolved Item 77-8/I-,l.,
(2) The inspector questioned the accuracy of the current method of obtaining the feedwater flow signal for the OD-3 program Core Thermal Power, as to the most accurate method available. The licensee will review the current method to determine if it is the method that was intended to be" used, and will report to NRC on his findings, along with justification for continuing using the current method, if used. This is identified as Unresolved Item 77-8/I-2.
RII Rpt. Nos. 50-259/77-8, 50-260/77-8 and 50-296/77-8 I-2
- 4. Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on July 1, 1977.
The inspector summarized the purpose and scope of the inspection and findings. No items of noncompliance or deviations were identi-fied.
- 5. Units 1 2 and 3 Procedures The inspector reviewed the following procedures and records to verify that reviews, approvals and changes were in accordance with the technical specifications and that changes reflected technical specification revisions and were in conformance with 10 CFR 50.59(a) requirements and that records of changes to procedures pursuant to 50.59(a) were being maintained:
(a) Nine operating procedures as required by technical specifications and identified in Paragraph C of Regulatory Guide 1.33.
(b) Six emergency procedures identified in Paragraph F of Regulatory Guide 1.33.
(c) Eight maintenance procedures associated with systems whose operating procedures were reviewed per 5(a) above.
(d) Three administrative procedures identified in Paragraph A of Regulatory Guide 1.33.
(e) Record of technical specifications changes recommended by plant personnel (24 documents reviewed for the period of February 1976 to June 1977).
(f) Correspondence from Power Production Department relating to technical specification changes (reviewed documents for the period between June 1976 and June 1977).
(g) Four Safety-related work packages to verify requirements to revise affected procedures and to evaluate the modification for safety evaluation requirements.
(h) Safety Evaluation Form TVA-10551-DED-2-76 (This form is included in all work packages.)
As a result of these reviews no apparent items of noncompliance or deviations were identified.
RII Rpt. Nos. 50-259/77-8, 50-260/77-8 and 296/77-8 I-3
- 6. Units 1 2 and 3 APRM Gain Ad ustment Factors GAF (a) Gain adjustment factors for all six APRM channels were deter-mined for data taken for 46 selected dates between January and June 1977. 276 sets of Surveillance Instruction 4.1.B.2 data were reviewed with the following observations:
(1) In 183 of the 276 sets of data the GAF was greater than 1.0.
(2) In 78 of the 276 sets of data the GAF was greater than 1.02.
(3) In 14 of the 276 sets of data the GAF was greater than 1.05.
(b) Section 7.5.7.4 and Figures 7.5.15 and 7.5.16 of the FSAR addresses the capabili,ty of the APRM channels to track core power. Figure 7.5.15 shows that the six APRM channels will track true core power with + 2% starting at 100% power and 100% flow to below the 65 flow point. Figure 7.5. 16 shows that the six APRM channels will track true core power within
+ 2% with control rod motion from the most restrictive case and full withdrawal of a control rod from limiting conditions at rated power. Section 7.5.74 further states that normal control rod manipulation results in good agreement (less than 5% deviation on the worst APRM,channel through a wide range of power levels and that the adequacy of the flow reference and APRM scram setpoint is demonstrated to be adequate in prevent-ing fuel damage as a result of abnormal operational transients by analyses in Section 14 of the FSAR.
(c) Following the discussion of SI-4.1.B.2 data results the licensee stated that the GAFs calculated from these data was not repre-sentative of GAFs maintained after power had been escalated to the operating level and steady state conditions achieved. He considers the GAFs obtained from the core performance computer printouts to be more representative of actual GAFs at steady state conditions. He also stated that he believed that they could justify an average GAF of as much as 1.05, but were attempting to maintain an average maximum GAF of 1.02 to 1.03.
This position does not appear to be consistent with the state-ments made in the FSAR, particularly since the FSAR instrument variations from true power as shown, are with flow and rod position transients. The inspector will review his findings with NRC management and in addition analyze more operating APRM data prior to determing if'he GAFs the licensee in maintaining are satisfactory with present APRM setpoint.
This is identified as Unresolved Item 77-8/I-l.
RII Rpt. Nos. 50-259/77-8, 50-260/77-8 and 50-296/77-8 I-4
- 7. Method of Obtainin Feedwater Flow Si nal for OD-3 Com uter Pro ram During a recent inspection by the inspector a review of the feedwater control system drawing and the OD-3 computer program showed that the feedwater flow signal for the OD-3 program Core Thermal Power Measurement, was taken after the square root converter in the feed-water flow circuitry. The circuit is different in this system from other BWR plants in R-II, in that this signal at other plants is taken ahead of the square root converter, and the square root conversion is part of the OD3 computer program, since the process computer can perform the square root conversion with greater accuracy than the feedwater flow instrument. During discussions with General Electric personnel it was learned that the signal should have been taken ahead of the square root converter in order to achieve the best accuracy in the core thermal power measurement.
The licensee will review his current method to determine if it is the method that was intended to be used, and will report to NRC on his findings, along with justification for continuing using the current method, if used. This is identified as Unresolved Item 77-8/I-2.
- 8. Tour of Control Room Areas A tour was made of Control Rooms 1, 2 and 3 and adjacent areas to inspect plant conditions, identify any limiting conditions for operation and discuss plant operations with the shift engineers and plant operators. As a result of this tour no apparent items of noncompliance or deviations were observed.