Similar Documents at Zion |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 ML20236U6331998-07-24024 July 1998 Safety Evaluation Supporting Amends 179 & 166 to Licenses DPR-39 & DPR-48,respectively ML20236S3281998-07-20020 July 1998 Safety Evaluation Supporting Certified Fuel Handlers Training & Retraining Program ML20198P8361998-01-0909 January 1998 SER Accepting Determination of Zone of Influnce for Coatings in Containment of Plant,Units 1 & 2 ML20198P8721998-01-0909 January 1998 Safety Evaluation Accepting Request for Alternative Insp Requirements for Augmented Exam of Reactor Presure Vessels for Zion Nuclear Power Station,Units 1 & 2 ML20202F0761997-12-0202 December 1997 Safety Evaluation Denying Licensee Proposed Alternative Contained in Request for Relief CR-13,Rev 1,of Removing Only Insulation Classified as Removable.Staff Determined That Submittal Does Not Provide Acceptable Level of Quality ML20132F5111996-12-20020 December 1996 Safety Evaluation Supporting Amends 177 & 164 to Licenses DPR-39 & DPR-48,respectively ML20135D8971996-11-25025 November 1996 Corrected SE Supporting Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively ML20134P7941996-11-25025 November 1996 Safety Evaluation Supporting Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively ML20134H6781996-11-12012 November 1996 Safety Evaluation Supporting Amends 175 & 162 to Licenses DPR-39 & DPR-48,respectively ML20134F9851996-11-0606 November 1996 Safety Evaluation Supporting Amends 174 & 161 to Licenses DPR-39 & DPR-48,respectively ML20129H2901996-10-29029 October 1996 Safety Evaluation Supporting Amends 173 & 160 to Licenses DPR-39 & DPR-48,respectively ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20058G2981993-11-29029 November 1993 Safety Evaluation Supporting Amends 151 & 139 to Licenses DPR-39 & DPR-48 ML20059M7851993-11-15015 November 1993 Safety Evaluation Supporting Amends 150 & 138 to Licenses DPR-39 & DPR-48,respectively ML20059L7511993-11-10010 November 1993 Safety Evaluation Accepting Category 3 Qualification in Lieu of Category 2 for Pressure Monitoring Instrumentation ML20059L6801993-11-0909 November 1993 Safety Evaluation Re Update to Plant Reg Guide 1.97 Parameter Summary Table ML20058E6661993-10-22022 October 1993 Corrected SE Re Revised Fuel Handling Accident Inside Containment.Se Mistakenly Gives Decontamination Factor for Elemental Iodine Value of 100 Instead of 133 ML20059B1961993-10-22022 October 1993 Safety Evaluation Accepting Util 930913 Reanalysis of Fuel Handling Accident Inside Containment ML20059A7211993-10-14014 October 1993 Safety Evaluation Supporting Amends 149 & 137 to Licenses DPR-39 & DPR-48,respectively ML20059C5521993-10-13013 October 1993 Corrected Safety Evaluation Supporting Amends 148 & 136 to Licenses DPR-39 & DPR-48,respectively ML20057F8351993-10-13013 October 1993 Safety Evaluation Supporting Amends 148 & 136 to Licenses DPR-39 & DPR-48,respectively ML20057A2091993-08-31031 August 1993 Safety Evaluation Denying Addl Exemptions from Fire Protection Requirements of 10CFR50,app R.Conclusions Reached When Granting Exemptions in 830307 & 880607 SEs Still Valid ML20056H5001993-08-27027 August 1993 Safety Evaluation Re Fire Protection Open Items from Section 3.2.1 of 780310 Safety Evaluation ML20057B1711993-03-24024 March 1993 Safety Evaluation Granting Relief Requests to Licenses DPR-39 & DPR-48 Re Second 10-yr Interval Inservice Testing Plan for Pumps & Valves ML20056C0501992-06-0909 June 1992 Safety Evaluation Supporting Amends 138 & 127 to Licenses DPR-39 & DPR-48,respectively ML20058D8081990-10-31031 October 1990 Safety Evaluation Supporting Amends 120 & 109 to Licenses DPR-39 & DPR-48,respectively ML20247E7421989-09-0808 September 1989 Safety Evaluation Supporting Amends 118 & 107 to Licenses DPR-39 & DPR-48,respectively ML20245F1631989-08-0101 August 1989 Safety Evaluation Supporting Amends 117 & 106 to Licenses DPR-39 & DPR-48,respectively ML20247P9591989-05-30030 May 1989 Safety Evaluation Supporting Amends 116 & 105 to Licenses DPR-39 & DPR-48,respectively ML20247M7431989-05-22022 May 1989 Safety Evaluation Supporting Util Compliance W/Atws Rule 10CFR50.62 ML20245H8051989-04-27027 April 1989 Safety Evaluation Supporting Amends 115 & 104 to Licenses DPR-39 & DPR-48,respectively ML20244E4141989-04-14014 April 1989 Safety Evaluation Supporting Util post-accident Monitoring Instrumentation Per Reg Guide 1.97 & Generic Ltr 82-33 ML20196B8081988-12-0202 December 1988 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements ML20207K9971988-10-11011 October 1988 SER Supporting Amends 113 & 102 to Licenses DPR-39 & DPR-48, Respectively ML20155G5771988-06-0707 June 1988 Safety Evaluation Recommending That Util 840727 Exemption Request from Sections III.G.2 & III.G.3 of 10CFR50,App R Be Granted.One Exemption Request Determined as Unnecessary ML20154A7781988-04-15015 April 1988 Safety Evaluation Supporting Amends 112 & 110 to Licenses DPR-39 & DPR-48,respectively ML20151M1281988-04-0606 April 1988 Safety Evaluation Supporting Amends 111 & 100 to Licenses DPR-39 & DPR-48,respectively ML20148P4951988-04-0404 April 1988 Safety Evaluation Supporting Amends 110 & 99 to Licenses DPR-39 & DPR-48,respectively ML20150F0601988-03-28028 March 1988 Safety Evaluation Supporting Amends 109 & 98 to Licenses DPR-39 & DPR-48,respectively ML20147B8831988-02-26026 February 1988 SER Re Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Nrc Concludes That Many of 30 Measurements Added to List in WCAP-10962 Not Credible ML20149H5541988-02-0505 February 1988 Safety Evaluation Supporting Amend 108 to License DPR-39 ML20237H5511987-08-17017 August 1987 Safety Evaluation Supporting Amends 107 & 97 to Licenses DPR-39 & DPR-48,respectively ML20236J3961987-07-20020 July 1987 Safety Evaluation Supporting Amends 106 & 96 to Licenses DPR-39 & DPR-48,respectively ML20235E9171987-06-23023 June 1987 Safety Evaluation Supporting Amends 105 & 95 to Licenses DPR-39 & DPR-48,respectively ML20213G6351987-05-0808 May 1987 Safety Evaluation Supporting Amends 104 & 94 to Licenses DPR-39 & DPR-48,respectively ML20215K3831987-05-0707 May 1987 Safety Evaluation Re Util 861229 Submittal Concerning Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61.Reported Values of Copper & Nickel Content Unacceptable ML20205Q9561987-03-26026 March 1987 Safety Evaluation Supporting Amends 103 & 93 to Licenses DPR-39 & DPR-48,respectively ML20205G7221987-03-19019 March 1987 Safety Evaluation Supporting Amends 102 & 92 to Licenses DPR-39 & DPR-48 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 A99022, Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Zion Nuclear Power Station,Units 1 & 2.With A99021, Monthly Operating Repts for June 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Zion Nuclear Power Station,Units 1 & 2.With A99019, Monthly Operating Repts for May 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations A99016, Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20195H9521999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Zion Nuclear Power Station,Units 1 & 2 A99013, Monthly Operating Repts for Mar 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results A990101, Monthly Operating Repts for Feb 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with A99002, Monthly Operating Repts for Dec 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98062, Monthly Operating Repts for Nov 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Zion Nuclear Power Station,Units 1 & 2.With ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB A98057, Monthly Operating Repts for Oct 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98052, Monthly Operating Rept for Sept 1998 for Zion Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Zion Nuclear Power Station,Units 1 & 2.With A98049, Special Rept 304-123-98-001SR:on 980902,valid Failure Rept for 2A EDG Occurred.Cause Unknown.Util Submitted Written Certification of Permanent Cessation of Operations at Zion Station,Units 1 & 21998-09-25025 September 1998 Special Rept 304-123-98-001SR:on 980902,valid Failure Rept for 2A EDG Occurred.Cause Unknown.Util Submitted Written Certification of Permanent Cessation of Operations at Zion Station,Units 1 & 2 ML20195D1221998-08-31031 August 1998 DSAR, for Zion Station A98048, Monthly Operating Repts for Aug 1998 for Zion Station,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Zion Station,Units 1 & 2.With ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept A98042, Monthly Operating Repts for July 1998 for Zion Station,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Zion Station,Units 1 & 2 ML20236U6331998-07-24024 July 1998 Safety Evaluation Supporting Amends 179 & 166 to Licenses DPR-39 & DPR-48,respectively ML20236S3281998-07-20020 July 1998 Safety Evaluation Supporting Certified Fuel Handlers Training & Retraining Program A98041, Monthly Operating Repts for June 1998 for Zion Nuclear Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Zion Nuclear Station,Units 1 & 2 ML20236J7911998-06-12012 June 1998 LER 98-S02-00:on 980517,first Shift Security Officer Reported Being Wounded by Unknown Subject Who Fled Area. Caused by accidental,self-inflicted Gunshot Wound.Removed Officer from Duty & Charged Officer W/Filing False Rept A98039, Monthly Operating Repts for May 1998 for Zion Generating Station,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Zion Generating Station,Units 1 & 2 A98035, Monthly Operating Repts for Apr 1998 for Zion Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Zion Station,Units 1 & 2 A98033, Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 2 A98029, Monthly Operating Repts for Feb 1998 for Zion Station,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Zion Station,Units 1 & 2 A98015, Monthly Operating Repts for Jan 1998 for Zion Station,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Zion Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr ML20198P8361998-01-0909 January 1998 SER Accepting Determination of Zone of Influnce for Coatings in Containment of Plant,Units 1 & 2 ML20198P8721998-01-0909 January 1998 Safety Evaluation Accepting Request for Alternative Insp Requirements for Augmented Exam of Reactor Presure Vessels for Zion Nuclear Power Station,Units 1 & 2 A98034, 1997 Annual 10CFR50.59 Summary Rept1997-12-31031 December 1997 1997 Annual 10CFR50.59 Summary Rept ML20216D3611997-12-31031 December 1997 Unicom Corp 1997 Summary Annual Rept A98004, Monthly Operating Repts for Dec 1997 for Zion Station,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Zion Station,Units 1 & 2 ML20202F1451997-12-0303 December 1997 Independent Investigation Team Rept on Safety Conscious Work Environment at Zion Station ML20202F0761997-12-0202 December 1997 Safety Evaluation Denying Licensee Proposed Alternative Contained in Request for Relief CR-13,Rev 1,of Removing Only Insulation Classified as Removable.Staff Determined That Submittal Does Not Provide Acceptable Level of Quality A97076, Monthly Operating Repts for Nov 1997 for Zion Station,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Zion Station,Units 1 & 2 ML20199J5931997-11-26026 November 1997 SG Insp Results,Fall 1996 Refueling Outage 14 (Z2R14) A97063, Special Rept 295-123-97-002SR:on 971014,failure of 1B EDG Occurred.Exam of Nipple Fractured Surface Revealed Failure Occurred Through Thread Root.Unit 1 Defueled & Unit 2 in Mode 5 Throughout Event1997-11-13013 November 1997 Special Rept 295-123-97-002SR:on 971014,failure of 1B EDG Occurred.Exam of Nipple Fractured Surface Revealed Failure Occurred Through Thread Root.Unit 1 Defueled & Unit 2 in Mode 5 Throughout Event A97069, Monthly Operating Repts for Oct 1997 for Zion Station,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Zion Station,Units 1 & 2 ML20211M0181997-10-0707 October 1997 Special Rept 295-123-97-001SR:on 970904,OA Motor Declared Inoperable Due to Pin Hole Leaks Identified on Pressure Regulating Relief valve,0FP0052.Procedure Was Rewritten to Ensure 0FP0052 Would Maintain Same Pressure When Fully Open A97058, Monthly Operating Repts for Sept 1997 for Zion Generating Station,Units 1 & 21997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Zion Generating Station,Units 1 & 2 ML20210V2401997-09-19019 September 1997 Rev 65g to Topical Rept CE-1-A, Comm Ed QA Manual 1999-09-30
[Table view] |
Text
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pweg jo,, UNITED $TATES Enclosure g g NUCLEAR REGULATORY COMMISSION
. -p WASHINGTON, D. C. 20555 SAFETYEVALUATiONBY ._
THE OFFICE OF NUCLEAR REACIOR REGULATION . . _
RELA!tD TO OPERATION OF .
ZION NUCLEAR POWER STATION UNIT NOS. 1 AND 2 .
COMMUNWEALTH EDISON CD.
DOCKET N05. 50-295 AND 50-304 I. INTRODUCTION 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 after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined 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
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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 February 28, 1983, the NRC Executive Director for Operations (ED0), 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 reportedinNUREG-1000."GenericImplicationsofATWSEventsattheSalem l
Nuclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to certain generic concerns. These concerns are categorized into four areas: (1) Post-TripReview.(2) Equipment ClassificationandVendorInterface,(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 Infomation Capability." This safety evaluation report (SER) addresses Action Item 1.1 only.
8500010105 E50717 PDR ADOCK 05000295 P PDR
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II. REVIEW GUIDELINES The following review guidelines were developed after initial evaluation of various utility responses to Item 1.1 of Generic Letter 83-28, and incorporate the best features of these submittals. As such, these review guidelines in effect represent a " good practices" approach to post-trip review. We have reviewed the licensee's response to Item 1.1 against these guidelines:
A. The licensee or applicant should have systematic safety assessment procedures established that will ensure that the following restart criteria are met before restart is authorized.
The post-trip review team has determined the root cause and sequence of events resulting in the plant trip.
Near term corrective actions have been taken to remedy the cause of the trip.
- The post-trip review team has performed an analysis and determined that the major safety systems responded to the event within specified limits of the primary system parameters.
The post-trip review has not resulted in the discovery of a potential safety concern (e.g., the root cause of the event occurs with a frequency significantly larger than expected).
If any of the above restart criteria are not met, then an independent assessment of the event is performed by the Plant ;
Operations Review Committee (PORC), or another designated group j with similar authority and experience.
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B. The responsibilities and authorities of the personnel who will perform the review and analysis should be well defined.
The post-trip review team leader should be a member of plant management at the shift supervisor level or above and should hold or should have held an SR0 license on the plant. The team leader
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should be charged with overall responsibility for directing the post-trip review, including data gathering and data assessment and he/she should have the necessary authority to obtain all personnel and data needed for the post-trip review.
A second person on the review team should be an STA or should hold a relevant engineering degree with special transient analysis training.
The team leader and the STA (Engineer) should be responsible to concur on a decision /reconnendation to restart the plant. A nonconcurrence from either of these persons should be sufficient to prevent restart until the trip has been reviewed by the PORC or equivalent organization.
C. The licensee or applicant should indicate that the plant response to the trip event will be evaluated and a determination made as to whether the plant response was within acceptable limits. The evaluation should include:
A verification of the proper operation of plant systems and equipment by comparison of the pertinent data obtained during the post-trip review to the applicable data provided in the FSAR.
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- An analysis of the sequence of events to verify the proper functioning of safety related and other important equipment. Where possible, comparisons with previous similar events should be made.
D. The licensee or applicant should have procedures to ensure that all physical evidence necessary for an independent assessment is preserved.
E. Each licensee or applicant should provide in its submittal, copies of the plant procedures which contain the information required in Items A through D. As a minimum, these should include the following:
- The criteria for determining the acceptability of restart
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- The qualifications, responsibilities and authorities of key personnel involved in the post-trip review process
- The methods and criteria for determining whether the plant variables and system responses were within the limits as described in the FSAR
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- The criteria for detennining the need for an independent review.
III. EVALUATION AND CONCLUSION By letters dated November 5,1983 and June 5,1985, the licensee of Zion Nuclear Power Station, Units 1 and 2, provided information regarding its Post-Trip Review Program and Procedures. We have evaluated the licensee's program and procedures against the review guidelines developed as described in Section II. A brief description of the licensee's response and the l staff's evaluation of the response against each of the review guidelines is i provided below:
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.s A. With regard to the criteria for determining the acceptability of restart, the licensee referred to a Corporate Directive, " Plant Start-up After Trip," which provides guidance for post-trip analysis, 1 determination of root cause and approval for startup. The licensee indicated that prior to the authorization of restart, the Corporate Directive requires: a determination of the root cause of the event; a !
satisfactory evaluation of equipment performance; and an understanding of the cause of any degraded, abnomal, or unexpected perfomance of safety-related equipment. Based on our review, we find that the ;
licensee's criteria for detemining the acceptability of restart are acceptable.
B. The licensee indicated that a Shift Supervisor has the responsibility and authority to obtain all necessary personnel and any special assistance considered necessary to ensure a thorough post-trip review.
The Station Superintendent has the final authority to authorize plant restart. The personnel performing the review and analysis will be shift management personnel (i.e., Shift Engineer, Shift Foreman and Station Control Room Engineer). These are all SRO licensed shift positions. We
. find that the qualifications, responsibilities and authorities of the personnel who will authorize the restart and/or perfom the post-trip review and analysis have been clearly defined and are acceptable.
C. The licensee has addressed the methods and criteria for comparing the event information with known or expected plant behavior. Based on our review, we find them acceptable.
D. With regard to the need of independent assessment of an event, the f licensee has indicated that station Technical Specifications require all unscheduled reactor trips to be assessed by the Onsite Review and Investigative Function and again by the Offsite Fieview and Investigative Function. In addition, the licensee has established procedures to l
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ensure that all physical evidence necessary for an independent assessment is preserved. We find that these actions taken by the licensee conform with the guidelines as described in the above Sections II.A and D.
E. The licensee has provided for our review a systematic safety assessment program to assess unscheduled reactor trips. Based on our review, we find that this program is acceptable.
Based on our review, we conclude that the licensee's Post-Trip Review Program and Procedures for Zion Nuclear Power Station, Units 1 and 2, are acceptable.
Principal Contributor:
D. Shum l
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