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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20153C5061998-09-21021 September 1998
SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1
ML20237A1341998-08-0707 August 1998
Safety Evaluation Supporting Amend 163 to License DPR-25
ML20203K5201998-02-25025 February 1998
Safety Evaluation Supporting Amends 165 & 160 to Licenses DPR-19 & DPR-25,respectively
ML20203H2441998-02-25025 February 1998
Safety Evaluation Supporting Amends 166 & 161 to Licenses DPR-19 & DPR-25,respectively
ML20202E2971998-01-0505 January 1998
Safety Evaluation Supporting Amends 164,159,179 & 177 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20216J8861997-09-10010 September 1997
Safety Evaluation Supporting Amends 162 & 157 to Licenses DPR-19 & DPR-25,respectively
ML20210Q4461997-08-21021 August 1997
SE Supporting Amends 161 & 156 to Licenses DPR-19 & DPR-25, Respectively
ML20197B9171997-07-23023 July 1997
Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints
ML20141E1681997-05-16016 May 1997
Safety Evaluation Supporting Amends 159 & 154 to Licenses DPR-19 & DPR-25,respectively
ML20140E9741997-04-30030 April 1997
Safety Evaluation Supporting Amends 157 & 152 to Licenses DPR-19 & DPR-25,respectively
ML20138D1791997-04-25025 April 1997
Safety Evaluation Supporting Amends 158 & 153 to Licenses DPR-19 & DPR-25,respectively
ML20137R6431997-04-10010 April 1997
Safety Evaluation Supporting Amends 156 & 151 to Licenses DPR-19 & DPR-25,respectively
ML20136G7731997-03-14014 March 1997
Safety Evaluation Approving Amends 155,150,174 & 170 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20135E1551997-02-28028 February 1997
Safety Evaluation Supporting Amends 153,148,172 & 168 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20134H7601997-02-0707 February 1997
Safety Evaluation Approving Rev 65c of Ceco QA TR CE-1-A
ML20112E3921996-05-31031 May 1996
Safety Evaluation Supporting Amend 144 to License DPR-25
ML20092M5091995-09-21021 September 1995
Safety Evaluation Supporting Amends 140,134,162 & 158 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20086C1941995-06-23023 June 1995
Safety Evaluation Supporting Amends 136,130,157 & 153 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20085L6961995-06-14014 June 1995
Safety Evaluation Supporting Amends 135,129,156 & 152 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20085H0301995-06-13013 June 1995
Safety Evaluation Supporting Amends 134,128,155 & 151 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20085K3391995-06-0808 June 1995
Safety Evaluation Supporting Amends 133,127,154 & 150 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20078S8681995-02-22022 February 1995
Safety Evaluation Supporting Amends 132 & 126 to Licenses DPR-19 & DPR-25,respectively
ML20078S8301995-02-16016 February 1995
Safety Evaluation Supporting Amends 131,125,152 & 148 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20071G1671994-07-0606 July 1994
Safety Evaluation Supporting Amends 128,122,148 & 144 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20029C9771994-04-25025 April 1994
SE Concluding That Revised EAL Consistent W/Guidance in NUMARC/NESP-007 & Therefore Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50
ML20065J4511994-04-0505 April 1994
Safety Evaluation Supporting Amends 126 & 120 to Licenses DPR-19 & DPR-25,respectively
ML20059C5481993-12-28028 December 1993
Safety Evaluation Supporting Amends 124 & 118 to Licenses DPR-19 & DPR-25,respectively
ML20034G9441993-03-0303 March 1993
Safety Evaluation Supporting Amend 123 to License DPR-19
ML20128C2961992-11-23023 November 1992
Safety Evaluation Supporting Amend 121 to License DPR-19
ML20116A8901992-10-19019 October 1992
Safety Evaluation Supporting Amends 119,115,138 & 134 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20105C7421992-09-11011 September 1992
Safety Evaluation Granting Licensee 920228 Request for Relief Concerning Inservice Testing Program for Facility
ML20105A7461992-09-11011 September 1992
Safety Evaluation Supporting Amends 118 & 114 to Licenses DPR-19 & DPR-25,respectively
ML20113H6381992-07-24024 July 1992
Safety Evaluation Supporting Amend 117 to License DPR-19
ML20114A5691992-07-24024 July 1992
Safety Evaluation Supporting Amends 113,116,131,& 135 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30
ML20077K9611991-08-0505 August 1991
Safety Evaluation Supporting Amend 110 to License DPR-25
ML20063P9621990-08-0909 August 1990
Safety Evaluation Supporting Amends 112 & 108 to Licenses DPR-19 & DPR-25,respectively
ML20246C8561989-06-30030 June 1989
Safety Evaluation Supporting Amends 106 & 101 to Licenses DPR-19 & DPR-25,respectively
ML20246H0101989-04-26026 April 1989
Safety Evaluation Supporting Amends 117,113,105 & 100 to Licenses DPR-29,DPR-30,DPR-19 & DPR-25,respectively
ML20205L2051988-10-26026 October 1988
Safety Evaluation Supporting Amends 101 & 97 to Licenses DPR-19 & DPR-25,respectively
ML20154B8841988-09-0909 September 1988
Safety Evaluation Accepting Response to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
ML20153D3181988-08-24024 August 1988
Safety Evaluation Supporting Amends 100 & 96 to Licenses DPR-19 & DPR-25,respectively
ML20207B7091988-07-21021 July 1988
SER Accepting one-time Exemption from 2-yr Type B & Type C Test Interval Requirements as Prescribed in App J,Until 880326,per Util Request
ML20150D6151988-06-20020 June 1988
Safety Evaluation Supporting Amend 94 to License DPR-25
ML20147A7431988-02-19019 February 1988
Safety Evaluation Supporting Amends 98 & 93 to Licenses DPR-19 & DPR-25,respectively
ML20235W8321987-10-0909 October 1987
Safety Evaluation Supporting Amends 96 & 91 to Licenses DPR-19 & DPR-25,respectively
ML20213G5011986-11-10010 November 1986
Safety Evaluation Supporting Amends 94 & 90 to Licenses DPR-19 & DPR-25,respectively
ML20209B9291986-09-0202 September 1986
Safety Evaluation Supporting Amend 89 to License DPR-25
ML20214K5491986-08-13013 August 1986
Safety Evaluation Supporting Amends 93 & 88 to Licenses DPR-19 & DPR-25,respectively
ML20206M6761986-08-13013 August 1986
Safety Evaluation Accepting Util 840410 Request to Acquire & Operate Mobile Low Level Radwaste Vol Reduction Sys Incinerator
ML20195C8101986-05-27027 May 1986
Safety Evaluation Supporting Amend 86 to License DPR-25
1998-09-21
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999
1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. 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
ML20210R6081999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With
ML20209E1291999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20209J3481999-06-30030 June 1999
1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With
ML20210D3071999-06-30030 June 1999
Corrected Page 8 to MOR for June 1999 for DNPS Unit 3
ML20195G6381999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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
ML20206N2821999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20206B1901999-03-31031 March 1999
First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with
ML20205N7491999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20207M6921999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20207E9311999-02-26026 February 1999
Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced
ML20199M0891999-01-22022 January 1999
Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc
ML20199D3261998-12-31031 December 1998
10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With
ML20205M7061998-12-31031 December 1998
Unicom Corp 1998 Summary Annual Rept. with
ML20199C8951998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3
ML20197G8591998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With
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
ML20196J0061998-11-19019 November 1998
Rev 66 to Topical Rept CE-1-A, QA Program
ML20195D2861998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With
ML20154N4131998-09-30030 September 1998
1998 Third Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments
ML20154L3681998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20153C5061998-09-21021 September 1998
SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station,Unit 1
ML20151Y2711998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Dresden Nuclear Power Station,Units 1,2 & 3.With
ML20237E2331998-08-21021 August 1998
Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept
ML20237A1341998-08-0707 August 1998
Safety Evaluation Supporting Amend 163 to License DPR-25
ML20237A7161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20236M6041998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20236T8391998-06-30030 June 1998
Rev 1 to EMF-96-141, Dresden Unit 3 Cycle 15 Reload Analysis Rept
ML20236T8331998-06-30030 June 1998
COLR for Dresden Station Unit 3,Cycle 15
ML20236F8131998-06-30030 June 1998
Rev 0 to Defueled SAR Dresden Nuclear Power Station Unit 1 Commonwealth Edison Co
ML20236Q5851998-06-30030 June 1998
1998 Second Quarter 10CFR50.59 Rept, for Dresden Nuclear Power Station of Completed Changes,Tests & Experiments
ML20248M3021998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML20247F3391998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
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
ML20216C9651998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Dresden Nuclear Power Station,Units 1,2 & 3
ML20216D4411998-03-31031 March 1998
First Quarter Rept of Completed Changes,Tests & Experiments for 10CFR5059
ML20216E2531998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for Dresden Nuclear Power Station
ML20203K5201998-02-25025 February 1998
Safety Evaluation Supporting Amends 165 & 160 to Licenses DPR-19 & DPR-25,respectively
ML20203H2441998-02-25025 February 1998
Safety Evaluation Supporting Amends 166 & 161 to Licenses DPR-19 & DPR-25,respectively
ML20202F7831998-01-31031 January 1998
Monthly Operating Repts for Jan 1998 for Dresden Nuclear Power Station
ML20199K1651998-01-23023 January 1998
Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr
ML20202E2971998-01-0505 January 1998
Safety Evaluation Supporting Amends 164,159,179 & 177 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively
ML20198P7021997-12-31031 December 1997
Fourth Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59
ML20216D3611997-12-31031 December 1997
Unicom Corp 1997 Summary Annual Rept
ML20198P5321997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for Dresden Nuclear Power Station
ML20203F8781997-11-30030 November 1997
Monthly Operating Repts for Nov 1997 for Dresden Nuclear Power Station
ML20199B0701997-10-31031 October 1997
Monthly Operating Repts for Oct 1997 for Dresden Nuclear Power Station
1999-09-30
[Table view] |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 156 TO FACILITY OPERATING LICENSE NO. DPR-19 AND AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. DPR-25 COMONWEALTH EDISON COMPANY DRESDEN NUCLEAR POWER STATION. UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249
1.0 INTRODUCTION
By letter dated February 19, 1997, as supplemented April 3,1997, Commonwealth Edison Company (Comed, the licensee) submitted a license amendment requesting a change to the Technical Specifications (TSs) to remove the 24/48 Volt direct current (Vdc) batteries, battery changers and distribution systems from the TS.
At Dresden Nuclear Power Station, the Unit 3, Division I and II, Analog Trip System (ATS) instrumentation loads and the Unit 2, Division I, ATS loads are currently supplied by the 24/48 Vdc safety-related system, while the Unit 2, Division II, loads are supplied by the 125 Vdc safety-related system. During the D3R14 refueling outage, the direct current (DC) supply to the Unit 3, Division I and II, ATS instrumentation loads will be switched to the safety-related 125 Vdc system. Because the Unit 3, 24/48 Vdc system will not provide a safety-related function, Comed proposes to remove the TS requirements for the 24/48 Vdc batteries, chargers, and distribution systems to licensee-controlled documents in accordance with the NRC's final policy statement as l
specified in Section 50.36 of Title 10 of the Code of Federal Reaulations (10 CFR 50.36). The April 3,1997, submittal provided additional clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 EVALUATION j
The proposed amendment would delete the 24/48 volt batteries, chargers, and distribution systems from the Dresden TSs for Unit 3.
The proposed change will affect TSs for the DC sources required for operation by TS Section (3.9.C), the DC sources required for shutdown by TS Section (3.9.D), the distribution systems required for operation by TS Section (3.9.E), the distribution systems required during shutdown by TS Section (3.9.F), and the i
associated surveillance requirements for the respective operating conditions, At Dresden, the Unit 3, Division I and II, ATS instrumentations loads and the Unit 2, Division I, ATS loads are currently supplied by the 24/48 Vdc system.
During the upcoming D3R14 outage, the DC supply to the Unit 3, Division I 9704140190 970410 PDR ADOCK 05300237 P
PDR
and II, ATS instrumentation loads will be switched tu the safety-related 125 Vdc system.
Removal of the ATS loads from the Unit 3, 24/48 Vdc system removes the only loads required for safe shutdown, and the batteries, chargers, and distribution systems will no longer be required to assure safe operation of Unit 3.
The remaining loads on the Unit 3, 24/48 Vdc system do not provide a safety-related function.
The Unit 2, Division I, ATS instrumentation are supplied by the 24/48 Vdc batteries: the Division II, ATS instrumentation loads are supplied by the safety-related 125 Vdc batteries. The Unit 2, Division I, ATS instrumentation loads will remain supplieJ by the 24/48 Vdc system until the next Unit 2 refueling outage, at which time a license amendment application may be submitted to remove this TS requirement for Unit 2.
Therefore, because the TSs for Unit 2 and Unit 3 are combined, Comed will leave the reference to the 24/48 Vdc batteries, chargers, and distribution systems in the Dresden TSs until all the safety-related loads are removed from the Unit 2, 24/48 Vdc system. However, there will be a note added to the TSs that will specify that the reference to the 24/48 Vdc battery system is applicable only to Unit 2.
3.0
SUMMARY
The removal of the 24/48 Vdc system from the TSs for Unit 3 is found to be acceptable because the system no longer provides a safety-related functicn.
Additionally, the staff finds the note added to the Dresden TSs specifying applicability of the 24/48 Vdc system to Unit 2 acceptable.
The proposed note is appropriate because the 24/48 Vdc system for Unit 2 still provides a i
safety-related function and would be required to remain in the Dresden TSs in accordance with 10 CFR 50.36.
Based on the above, the staff finds the i
proposed TS changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (62 FR 10088). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR i
9
. 51.z2(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
M. Pratt S. Saba Date: April 10, 1997 t
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