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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 ML20198J0921997-09-18018 September 1997 Safety Evaluation Authorizing Licensee & Suppls & 16 Request for Approval of Alternative Reactor Vessel Weld Exam,Per 10CFR50.55a(g)(6)(ii)(A)(5) for Plant, Unit 2 for Next 2 Operating Cycles ML20198H2351997-09-0808 September 1997 Safety Evaluation Approving Licensee 970311 Request for Use of ASME Code Case N-509 & Relief from ASME Code Section IX Requirements for Exam of Hpcip Studs for Plant,Units 1 & 2 ML20137A4831997-03-18018 March 1997 SER Re CP&L Review of Power Uprate Process & Commitment Preventing Operation at Uprated Power Levels for Plant, Units 1 & 2 ML20129E0821996-09-26026 September 1996 Safety Evaluation Supporting Request to Use Certain Portions of Later Edition of ASME Code for Inservice Leakage Testing Valves for Brunswick Steam Electric Plant Units 1 & 2 ML20056D6761993-07-28028 July 1993 Safety Evaluation Concluding That Interior Masonry Walls May Be Downgraded to non-fire Related ML20128K7711993-02-11011 February 1993 Safety Evaluation Granting Relief from Certain Inservice Testing Program Requirements for Several Pumps & Valves ML20198E5081992-11-23023 November 1992 Safety Evaluation Accepting Licensee 120-day Response to Suppl 1 to GL 87-02 ML20246D6811989-08-18018 August 1989 Safety Evaluation Supporting Installation & Design of Nitrogen Pneumatic Sys,Per Generic Ltr 84-09,by Adding New Check Valves to Existing Drywell Noninterruptible Instrument Air Lines ML20246C4201989-06-27027 June 1989 SER Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Operating Reactors ML20247P6201989-06-0101 June 1989 Safety Evaluation Supporting Util SAFER/GESTR-LOCA Analysis ML20247M1911989-05-25025 May 1989 Safety Evaluation Re Denial of Amend Request to Licenses DPR-71 & DPR-62 ML20246P9401989-05-10010 May 1989 Safety Evaluation Accepting Plant Second 10-yr Interval Inservice Insp Program ML20246J5531989-05-0909 May 1989 Safety Evaluation Concluding That Plant Can Be Safely Operated for Another 18-month Fuel Cycle in Configuration Following Reload 5,per Improvements,Insps & Repairs to Plant IGSCC ML20245D3761989-04-25025 April 1989 Safety Evaluation Supporting Licensee IGSCC Program for Refuel 7 Outage ML20236D5481989-03-17017 March 1989 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability ML20236D5381989-03-17017 March 1989 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety-related Components ML20236D4641989-03-15015 March 1989 Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Concerning Equipment Classification & Vendor Interface for Reactor Trip Sys Components ML20235Z2841989-03-0808 March 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 ML20235Z3451989-03-0808 March 1989 Safety Evaluation Supporting Util Compliance W/Atws Rule, 10CFR50.62 Re Power Testability Features of Alternate Rod Insertion Sys & Recirculating Pump Trip Design ML20235M5771989-02-16016 February 1989 Safety Evaluation Supporting Control Room Habitability Sys of Plant & Acceptability of Existing Tech Spec Re Control Room Pressurization Requirement ML20147G0661988-03-0202 March 1988 Safety Evaluation Supporting Proposed Functional Testing Plan for Snubbers ML20236D1311987-10-22022 October 1987 Safety Evaluation Re Util Request for Relief from Schedular Requirements for Performance of Visual Insp & Hydrostatic Test of CRD Withdrawal & Insert Lines.Granting of Request Recommended ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable NUREG-0661, Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved1987-05-0707 May 1987 Safety Evaluation Re Util 840831 Submittal of Addendum to Plant Unique Analysis Rept on Mark I Containment Mod Program.Safety/Relief Valve Load Cases C3.2 & C3.3 Adequately Addressed & Resolved ML20212H5671987-01-16016 January 1987 Safety Evaluation Supporting Util Response to Generic Ltr 83-08 Re Restoring Safety Margins of Vacuum Breakers by Replacing Critical Parts W/Adequate Matls ML20207A8531986-11-0505 November 1986 Safety Evaluation Supporting Operation for Full Fuel Cycle W/O mid-cycle Insp for Crack Growth ML20215N3771986-10-30030 October 1986 Safety Evaluation Re Util 860320 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii). Licensee Should Remove All Potential Oxygen Sources from Containments ML20203N0081986-09-17017 September 1986 Safety Evaluation Supporting Util 850919 Request for Relief from Installing Excess Flow Switch & Automatic Shutoff Valve in Diesel Fire Pump Fuel Line to Provide Protection in Event of Fuel Line Rupture ML20212N0201986-08-22022 August 1986 Safety Evaluation Denying Util 860325 Request for Relief from Inservice Insp Requirements of ASME Code Section XI, Table IWC-2500-1 for Volumetric Exam of HPCI Pump Studs ML20211G6081986-06-12012 June 1986 Safety Evaluation Supporting IGSCC Insp,Repair & Replacement Program During Dec 1985 Refueling Outage ML20205S2541986-06-0404 June 1986 Safety Evaluation Accepting Rev 2 to Nuclear Const Issues Group Spec 1, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants, for non-ASME Code Welds ML20211A8281986-06-0303 June 1986 Safety Evaluation Re Rev 4 to Offsite Dose Calculation Manual.Rev Acceptable ML20198S7281986-05-29029 May 1986 Safety Evaluation Supporting 851203 Proposal to Modify Tech Spec 3/4.5.3 to Clarify Min Amount of Condensate Storage Tank Water Required to Ensure Operability of Core Spray Sys During Operating Conditions 4 or 5.Rev to Tech Specs Encl ML20133N4141985-10-23023 October 1985 Safety Evaluation Re Util 831107 & 850828 Responses to Generic Ltr 83-28,Items 3.1.2 & 3.2.1 & 850701 Request for Addl Info.Responses Re Vendor & Engineering Test Guidance & Testing Requirements After Maint Acceptable ML20134P5211985-08-28028 August 1985 Safety Evaluation Approving Use of ASME Code Case N-411 for Damping Curves ML20128M2911985-07-16016 July 1985 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28, Salem ATWS Event, Items 3.1.3 & 3.2.3 Re post-maint Testing 1999-08-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied BSEP-99-0005, Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0231, Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0218, Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with BSEP-98-0210, Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired1998-10-30030 October 1998 Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 BSEP-98-0202, Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151Y6211998-09-14014 September 1998 BSEP Rept Describing Changes,Tests & Experiments, for Bsep,Units 1 & 2 ML20151Y6371998-09-14014 September 1998 Changes to QA Program, for Bsep,Units 1 & 2 BSEP-98-0185, Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 BSEP-98-0164, Monthly Operating Repts for July 1998 for BSEP Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for BSEP Units 1 & 2 ML20236T1961998-07-0101 July 1998 Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr ML20236T1921998-07-0101 July 1998 Rev 1 to 1B21-0537, Brunswick Unit 1,Cycle 12 Colr BSEP-98-0142, Monthly Operating Repts for June 1998 for BSEP Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for BSEP Units 1 & 2 ML20236T1971998-06-30030 June 1998 Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept BSEP-98-0129, Monthly Operating Repts for May 1998 for Bsep,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Bsep,Units 1 & 2 ML20151S9041998-05-31031 May 1998 Revised Pages to Monthly Operating Rept for May 1998 for Brunswick Steam Electric Plant,Unit 1 BSEP-98-0104, Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 2 ML20151S8991998-04-30030 April 1998 Revised Pages to Monthly Operating Rept for Apr 1998 for Brunswick Steam Electric Plant,Unit 1 ML20247N7501998-04-30030 April 1998 Rev 0 to BSEP Unit 1,Cycle 12 Colr ML20247N7721998-04-30030 April 1998 Rev 0 to J1103244SRLR, Supplemental Reload Licensing Rept for BSEP Unit 1,Reload 11,Cycle 12 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) BSEP-98-0080, Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 2 ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 1999-09-30
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO GENERIC LETTER 83-28, ITEM 1.2 - POST-TRIP REVIEW DATA AND INFORMATION CAPABILITY CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS.: 50-324, 50-325 I. INTRODUCTI0h On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant start-up and the reactor was tripped manually by the operator about 30 seconds af ter the initiation of the automatic trip signal. The failure of the circuit breakers has been detennined to be related to the sticking of the under voltage trip attachment. Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip. Following these incidents, on Februa ry 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Connission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983) all licensees of operating reactors, applicants for an operating license, and holders of I
8506240652 850610 4 DR ADOCK 050 -
construction permits to respond to certain generic concerns. These concerns are categorized into four areas: (1) Post-Trip Review, (2) Equipment Classification and Vendor Interface, (3) Post-Maintenance Testing, and (4) Reactor Trip System Reliability Improvements.
The first action item, Post-Trip Review, consists of Action Item 1.1,
" Program Description and Procedure" and Action Item 1.2, " Data and Information Capability." This safety evaluation report (SER) addresses Action Item 1.2 only.
II. REVIEW GUIDELINES The following review guidelines were developed after initial evaluation of the various utility responses to Item 1.2 of Generic Letter 83-28 and incorporate the best features of these submittals. As such, these review guidclines in effect represent a " good practices" approach to post-trip review. We have reviewed the licensee's response to Item 1.2 against these guidelines:
A. The equipment that provides the digital sequence of ever.ts (SOE) record and the analog time history records of an unscheduled shutdown should provide a reliable source of the necessary information to be used in the post-trip review. Each plant variable which is necessary to determine the cause and progression of the events following a plant trip should be monitored by at least one recorder (such as a sequence-of-events recorder or a plant process ccmputer) for digital parameterst and strip
charts, a plant process computer or analog recorder for analog (time history) variables. Performance characteristics guidelines for SOE and time history recorders are as follows:
Each sequence of events recorder should be capable of detecting and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses associated with each monitored safety-related system can be ascertained, and that a detemination can be made as to whether the time response is within acceptable limits based on FSAR Chapter 15 Accident Analyses. The recomended guidelines for the SOE time discrimination is approximately 100 milliseconds. If current SOE recorders do not have this time discrimination capability the licensee should show that the current time discrimination capability is sufficient for an adequate reconstruction of the course of the reactor trip and post-trip events. As a minimum this should include the ability to adequately reconstruct the transient and accident scenarios presented in Chapter 15 of the plant FSAR.
l Each analog time histnry data recorder should have a sample interval small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the licensee should be able to reconstruct the course of the transient and accident sequences evaluated in the accident analysis of
Chapter 15 of the plant FSAR. The recommended guideline for the sample interval is 10 seconds. If the time history eq'uipment does not meet this guideline, the iicensee should show that the time history capability is sufficient to accurately reconstruct the transient and accident sequences presented in Chapter 15 of the FSAR. To support the post-trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
All equipment used to record sequence of events and time history information should be powered from a reliable and non-interruptible power source. The power source used need not be safety related.
B. The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip and post-trip events can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the unscheduled shutdown, the progression of the reactor trip, and the response of the plant parameters and protection and safety systems to the unscheduled shutdowns. Specifically, all input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the proper functioning of these
systems shculd be recorded for use in the post-trip review. The parameters deemed necessary, as a minimum, to perform a post-trip review that would detennine if the plant remained within its safety limit design envelope are presented in Table 1. They were selected on the basis of staff engineering judgment following a complete evaluation of utility submittals. If the licensee's SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the accident conditions analyzed in Chapter 15 of the plant FSAR.
C. The information gathered by the sequence of events and time history recorders should be stored in a manner that will allow for data retrieval and analysis. The data may be retained in either hardcopy, (e.g., computer printout, strip chart record), or in an accessible memory (e.g., magnetic disc or tape). This information should be presented in a readable and meaningful format, taking into consideration good human factors practices such as those outlined in NUREG-0700.
D. Retention of data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to subsequent unscheduled shutdowns. Information gathered during the post-trip review is to be
retained for the life of the plant for post-trip review comparisons of subsequent events.
III. EVALUATION AND CONCLUSION By letter dated November 7,1983, Carolina Power and Light Company provided ~
information regarding its post-trip review program data and information capabilities for Brunswick Steam Electric Plant Units 1 and 2. We have evaluated the licensee's submittal against the review guidelines described in Section II. Licensee deviations from the Guidelines of Section II were
. reviewed with the licensee by telephone on May 21, 24 and 30,1985. A brief description of the licensee's responses and the staff's evaluation of the response against each of the review guidelines is provided below:
A. The licensee has described the performance characteristics of the equipment used to record the sequence of events and time history data needed for post-trip review. Based on our review, we find that the sequence of events and time history recorder characteristics conforn to the guidelines described in Section II A, and are acceptable.
B. The licensee has established and identified the parameters to be monitored and recorded for post-trip review. The parameters identified in the subnittal of November 7,1983, as being recorded by the sequence of events and time history recorders did not correspond to the parameters specified in Section II B of this report. These parameters were missing: (1) Certainment Isolation, (2) Turbine Bypass Valve
Position, and (3) AC and DC System Status. By telecon on May 21, 24 and 30, 1985 Carolina Power and Light Company verified that these parameters are recorded and meet the criteria in Section II B of this report.
Infomation on these parameters is stored on the 80P Post Trip Log from two minutes before, to two minutes after, a reactor trip.
Although the DC System Status is not recorded on the SOE, the loss of any DC bus will be annunciated and recorded on the alam printer. This was detemined by telecon May 24, 1985. Based on our review of the November 7,1983 submittal and with the clarifying infomation obtained during our telephone calls, we find that the parameters selected by the licensee include all of those identified in Table 1 and conform to the guidelines described in Section II B and are, therefore, acceptable.
C. The licensee has described the means for storage 7.nd retrieval of the infomation gathered by the sequence of events and time history recorders, and for the presentation of this information for post-trip review and analysis. Based on our review, we find that this infomation will be presented in a readable and meaningful fomat, and that the storage, retrieval, and presentation confom to the guidelines of Section 11 C.
D. By telephone call on May 21, 1985, the licensee explained that the data and infomation used during post-trip reviews is retained in an accessible manner for the life of the plant. Based on our I
8-review, we find that the licensee's program for data retention conforms to the guidelines of Section II D, and is acceptable.
Based on our review, we conclude that the licensee's post-trip review data and information capabilities for Brunswick Steam Electric Plant Units 1 and 2 are acceptable.
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TABLE 1 BWR PARAMETER LIST SOE Time History Recorder Recorder Pa rameter/.'. ignal x Reactor Trip x Safety Injection x
Containment Isolation x Turbine Trip
. x Control Rod Position x (i) x Neutron Flux, power x (!) Main Steam Radiation
(?) Containment (Dry Well) Radiation x (.t) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Temperature x(1) x Primary System Pressure x (1) x Primary System level x MSIV Position x (1) Turbine Stop Valve / Control Valve Position x Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow, Pump Status x (1) Scram Discharge Level x (1) Condenser Vacuum
r SOE Time History Recorder Recorder Parameter /Sional x
AC and DC Systen Status (Bus Voltage)
(3) (4) Safety Injection; Flow, Pump / Valve Status x Diesel Generator Status (on/0ff, Start /Stop)
(1) Trip parameters (2) Parameter may be recorded by either an SOE or time history recorder.
(3) Acceptable recorder options are; (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or (c) equipment status recorded on an SOE recorder.
(4) Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
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