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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20216F0221998-03-0606 March 1998 Safety Evaluation Accepting Request Re Temporary Use of Current Procedure for Containment Repair & Replacement Activities at Plant ML20197B9171997-07-23023 July 1997 Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints ML20141E5091997-05-16016 May 1997 Safety Evaluation Supporting TR EMF-96-051(P), Application of Anfb Critical Power Correlation to Coresident GE Fuel for Plant,Unit 2 Cycle 15 ML20137G6071997-03-13013 March 1997 Safety Evaluation Supporting Proposed Changes to TS & Bases Ceco ML20134H7601997-02-0707 February 1997 Safety Evaluation Approving Rev 65c of Ceco QA TR CE-1-A ML20149F4151994-08-0404 August 1994 Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) ML20058L2711993-12-0808 December 1993 Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe Operation ML20056C4601993-06-17017 June 1993 Safety Evaluation Accepting Proposed Repair of Weld in Recirculation Piping Sys for One Cycle of Operation ML20128F9731993-02-10010 February 1993 Safety Evaluation Granting Licensee 910930 Request Not to Perform Code Exam on 100% of Attachment Welds on Stabilizer Brackets to Reactor Vessel Under 10CFR50.55(a)(3)(ii) ML20055F9221990-07-17017 July 1990 Safety Evaluation Supporting Util Responses to NRC Bulletin 88-010 Re Molded Case Circuit Breaker Replacement ML20248J2431989-10-0303 October 1989 Safety Evaluation Accepting Util 880122,0601,0714 & 0816 Submittals Re Insp Results,Mitigation,Flaw Evaluations & Overlay Repairs of Welds Susceptible to IGSCC to Support Operation of Unit 2,for Another 18-month Fuel Cycle ML20246K1611989-08-24024 August 1989 Revised SER Supporting Amends 112 & 108 to Licenses DPR-29 & DPR-30,respectively,changing Setpoints of Main Steam Line Radiation Monitors & Correcting Typos in Tech Specs ML20248B8911989-06-0606 June 1989 Safety Evaluation Concluding That IGSCC Insp Scope for Class 1 Piping Meets NRC Requirements & Guidelines of Generic Ltr 84-11 ML20151X3431988-08-16016 August 1988 SER Accepting Basis & Findings That Util post-accident Monitoring Instrumentation Meets Guidelines of Reg Guide 1.97 Except for Variable Neutron Flux Instrumentation ML20151M6901988-07-21021 July 1988 Revised Safety Evaluation Supporting Exemption Requests from Regulatory Requirements of 10CFR50,App R,Section Iii.G ML20195E2091988-06-0909 June 1988 Safeguards Evaluation Rept Supporting Amends 108 & 103 to Licenses DPR-29 & DPR-30,respectively ML20151U1201988-04-20020 April 1988 Revised Safety Evaluation Accepting Util Interim Compensatory Measures & Request for Exemption from 10CFR50, App R,Section Iii.G Requirement Re Hot Shutdown Repair for Fire Event in Plant ML20149M5301987-12-11011 December 1987 Marked-up Safety Evaluation Supporting Request for Exemptions from App R ML20236W4851987-12-0101 December 1987 Safety Evaluation Accepting Proposed Approaches for Resolving fire-related Concerns,Including Spurious Operations,High Impedance Faults & Electrical Isolation Deficiency.Granting of Exemption Requests Recommended ML20235S8541987-10-0202 October 1987 Safety Evaluation Supporting Interim Approval of Rev 3 to Process Control Program for Plant ML20237H7061987-08-19019 August 1987 SER Supporting Util Response to Item 2.1 (Part 1) of Generic Ltr 83-28 Re Equipment Classification.Licensee Statements Confirm Program Exists for Identifying,Classifying & Treating Components as safety-related.Program Acceptable ML20236H1341987-07-27027 July 1987 Safety Evaluation Re Acceptance of Updated Rev 11 to Offsite Dose Calculation Manual ML20205H1351987-03-23023 March 1987 Safety Evaluation Re Insps for & Repairs of Igscc.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration ML20214X1111986-11-26026 November 1986 Safety Evaluation Supporting Util Analytical Methods Used to Evaluate Stresses of Critical Components for Vacuum Breaker Integrity Re Mark I Containment Program ML20214Q3851986-11-17017 November 1986 Safety Evaluation Re Insp & Repair of Reactor Coolant Piping Sys ML20141D2291986-03-31031 March 1986 Safety Evaluation Granting Util Request for Relief from Certain Requirements of Section XI of ASME Code Re Inservice Insp for Second 10-yr Interval ML20141P0491986-03-13013 March 1986 Safety Evaluation Supporting Licensee 831105 & 851219 Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability) ML20137A3931986-01-0707 January 1986 Safety Evaluation Supporting Reactor Coolant Piping Sys IGSCC Insp & Repair Per Generic Ltr 84-11 & Return to Operation for 18-month Cycle ML20133F0291985-07-30030 July 1985 Safety Evaluation Accepting Util 831105 & 850605 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review (Program Description & Procedure) ML20126F4561985-05-31031 May 1985 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing Verification ML20062B8351982-07-28028 July 1982 Safety Evaluation Supporting Plant Compliance W/Esf Reset Controls Per NRC Criteria ML20126C3461980-03-20020 March 1980 Safety Evaluation Supporting Amend 51 to License DPR-30 ML20235D0971966-12-30030 December 1966 Safety Evaluation Supporting Util 660531 Proposal to Const & Operate Single Cycle BWR of 2,255 Mwt 1999-09-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities 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 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities 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 SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves 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 SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30
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SAFEGUARDS EVALUATION REPORT HISCELLANEOUS AMENDMENTS AND SEARCH REQUIREMENTS COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION, UNITS 1 AND 2
1.0 INTRODUCTION
The Commonwealth Edison Company (CEC 0, the licensee) has filed with the Nuclear Regulatory Comission revisions to their Physical Security Plan for the Quad-Cities Nuclear Power Station, Units 1 and 2.
Thir Safeguards Evaluation Report (SGER) sumarizes how the licensee proposes to meet the Miscellaneous Amendments and Search Requirements revisions of 10 CFR Part 73.55.
Based on a review of the Physical Security Plan, the staff has concluded that the proposed changes satisfy Hiscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and accompanying 10 CFR 73.70 record reporting requirements. Accordingly, the protection provided will ensure that the public health and safety will not be endangered.
I 2.0 PERSONNEL SEARCH
! The licensee has provided comitments in the Physical Security Plan to provide a search of all individuals entering the protected area except bona fide Federal, State and local law enforcement personnel on official duty, through the use of equipment designed for the detection of fireanns, explosives, and incendiary devices. In addition, the licensee has provided comitments to conduct a physical
- pat-down search of an individual whenever the licensee has cause to suspect that I the individual is attempting to introduce firearms, explosives, or incendiary devices into the protected areas; or whenever firearms or explosives detection equipment is out of service or not operating satisfactorily,
- 3.0 VITAL AREA ACCESS l
CEC 0 has modified their Quad-Cities Nuclear Power Station, Units 1 and 2 Physical l Security Plan to limit unescorted access to vital areas during non-emergency con-ditions to individuals who require access in order to perform their duties. They have established current authorization access lists for each vital area which are updated and approved by the cognizant manager or supervisor at least once every 31 days. CEC 0 has assured that only individuals whose specific duties require
- access to vital areas during nonemergency conditions are included on their site
! access list. CEC 0 has provided further assurance by revoking access and retrieving
! badges and other entry devices prior, to or simultaneously with notification of tennination of an individual's unescorted facility access.
8806230320 080609 4 PDR ADOCK 0500 F
i 1 2
Based u3on comitments made by the licensee in revisions to their Physical Security Plan, tie staff has concluded that CEC 0 meets the vital area access requirenients of 10 CFR 73.55(d)(7)(1)(A),(B), and (C).
4.0 LOCKS AND KEYS The licensee has comitted to providing methods to reduce the probability of compromise of keys, locks, combinations, and related access control devices used to control access to their protected areas and vital areas. These methods include the rotation of keys, locks, combinations, and related access control devices every 12 months or the changing of these devices whenever there is evicence or suspicion that any key, lock, combination or related access control device may have been compromised or when an individual who has had access to any of these devices has had their access tenninated due to a lack of trustworthiness, reliability or inadequate work parformance. Only persons granted unescorted facility access are issued such entry devices.
Based upon comitments made by the licer.see in revisions to their Physical Security Flan, the staff has concluded that CECO meets the requirements of 10 CFR 73.55 (d)(9) to reduce the probability of compromise of keys, locks, combinations, and related access control devices.
5.0 EMERGENCY ACCESS The licensee has provided comitments to provide for the rapid ingress and egress of individuals during emergency conditions or situations that could lead to emergency conditions by assuring prompt access to vital equipment. An annual review of their physical security plans and contingency plans and procedures will be conducted to evaluate their potential impact on plant and personnel safety.
Emergency access is granted by a licensed senior operator.
Based upon comitments made by the licensee in revisions to their Physical Security Plan, the staff has concluded that CEC 0 meets the requirements of 10 CFR 73.55 (d)(7)(ii) to assure access to vital equipment during emergencies or to situations that may lead to an emergency.
6.0 PROTECTI_0N OF SECONDARY p0WER SUPPLIES The licensee has provided comitments to protect the on-site secondary power supply system for alann annunciator eqJipment and non-portable Comunications equipment by including such equipment within a vital area boundary.
Based upon comitments made by the licensee in revisions to their Physical Security Plan, the staff has concluded that CECO meets the requirerents of 10 CFR 73.55(e) l in protecting the secondary power supplies of alann annunciator equipment and non-portable comunications equipment.
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3 7.0 VITAL AREA ENTRY / EXIT LOGGING ,
The licei.:ee has connitted to maintaining a log indicating name, badge number, time of entry, ai.d time of exit of all individuals granted access to a vital area except those ,'ndividuals entering or exiting the reactor control room.
Based upon connitments made by the licensee in revisions to their Physical Security Plan, the staff his concluded that CEC 0 meets the requirements of 10 CFR 73.70(d) by maintaining ent y/ exit log of individuals accessing vital areas (except the reactor control ro'sm).
R.0 CONCLUSION b sed upon the above evaluation, we find that the licensee has met the requirements of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR Part 73.55 and the record reporting requirements of 10 CFR Part 73.70.
Principal Contributor: Robert F. Skelton Dated: June 9, 1988 l
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