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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
ML20217G9961999-10-14014 October 1999
SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 &
ML20217C9121999-10-12012 October 1999
SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change
ML20217F9091999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With
ML20249C8491999-09-30030 September 1999
1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with
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
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
ML20217H5221999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With
ML20217P6351999-09-29029 September 1999
Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations
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
ML20212A7441999-09-10010 September 1999
Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety
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
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
ML20212B9261999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Byron 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
BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With
ML20212C4501999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With
ML20210R6421999-08-13013 August 1999
ISI Outage Rept for A2R07
ML20210U8111999-08-0404 August 1999
SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a
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
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
BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With
ML20210R6081999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With
ML20210R3431999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With
ML20210R0671999-07-31031 July 1999
Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With
ML20210K9861999-07-30030 July 1999
Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs
ML20210E2251999-07-21021 July 1999
B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424
M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999
Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function
ML20216D3841999-07-12012 July 1999
Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function
ML20210C1681999-07-0909 July 1999
Seventh Refueling Outage ASME Section XI Summary Rept
ML20209G1751999-07-0808 July 1999
SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09)
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
ML20209E1291999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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
BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With
ML20210D3071999-06-30030 June 1999
Corrected Page 8 to MOR for June 1999 for DNPS Unit 3
ML20209J3481999-06-30030 June 1999
1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With
ML20207H7771999-06-30030 June 1999
Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2
ML20207H7851999-06-30030 June 1999
Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation
ML20209H3711999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML20207H8071999-06-30030 June 1999
Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations
ML20207H7941999-06-30030 June 1999
Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation
ML20209H1501999-06-30030 June 1999
Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With
ML20207H7561999-06-28028 June 1999
Pressure Temp Limits Rept (Ptlr)
ML20207H7621999-06-28028 June 1999
Pressure Temp Limits Rept (Ptlr)
1999-09-30
[Table view]
Category:TOPICAL REPORT EVALUATION
MONTHYEARML20196A4191998-11-19019 November 1998
Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB
ML20205E8791985-10-28028 October 1985
Topical Rept Evaluation of WCAP 10456, Effects of Thermal Aging on Structural Integrity of Cast Stainless Steel Piping for Westinghouse Nsss. Proposed Model May Be Used to Predict Cast Stainless Steel Matl Embrittlement Heat
ML20140F7701974-09-12012 September 1974
Topical Rept Evaluation of Nedo 10859, Steam Vent Clearing Phenomena & Structural Response of BWR Torus. Portion of Rept Re Structural Response & Stress Analysis Unacceptable. Viewgraphs Encl
1998-11-19
[Table view] |
Text
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uruq a k UNITED STATES
[
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001 4 o 4.....g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION QUALITY ASSURANCE TOPICAL REPORT CE-1-A. REVISION 86 COMMONWEALTH EDISON COMPANY BYRON STATION. UNITS 1 AND 2 J
BRAIDWOOD STATION. UNITS 1 AND 2 i
DRESDEN NUCLEAR POWER STATION. UNITS 2 AND 3 LASALLE COUNTY STATION. UNITS 1 AND 2 QUAD CITIES NUCLEAR POWER STATION. UNITS 1 AND 2 ZION NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS. STN 50-454. STN 50-455. STN 50-456. STN 50-457. 50-10.
50-237. 50-249. 50-373.50-374.50-254.50-265.50-295. 50-304
1.0 INTRODUCTION
Pursuant to 10 CFR 50.54(a)(3) and 10 CFR 50.4(b)(7), the Commonwealth Edison Company (Comed, the licensee) submitted actual and proposed changes to its Quality Assurance Topical Report (QATR) CE-1-A, Revision 66, as described in Comed's letter to the NRC dated April 23, l' 1998. A Comed letter to the NRC dated August 21,1998, modified the April 23,1998, submittal and clarified some of the proposed changes to the QATR. A telephone conference was held between representatives of Comed and the NRC on October 13,1998. As a result of this telephone conference and NRC review comments in an NRC letter to Comed dated October 20,1998, Comed submitted a letter on October 27,1998, with additional modifications.
Revision 66 to the QATR was initiated to make changes in the independent and onsite review organization by creating the Nuclear Safety Review Board (NSRB). The NSRB will provide the oversight function previously performed by the Offsite Review and investigative Function.
Comed does not consider these changes as a reduction in commitment. However, Comed does consider the periodic effectiveness review process and the five-year audit frequency of NSRB activities as a reduction in commitment.
9811270158 981119 PDR ADOCK 05000010 W PDR ENCLOSURE
c i
l l 4 l 2.0 EVALUATION i
- The proposed revlsion to the QATR will eliminate the Offsite Review and Investigative Function j for Comed's operating plants. The NSRB will provide the oversight function previously
- performed by the Offsite Review and investigative Function. The NSRB will conduct reviews of i each of the subjects delineated in proposed QATR Section 20A, Article 3.4. A separate group, j under the auspices of the NSRB and independent of the organization responsible for the j subject to be reviewed, may perform these reviews and report the results of its reviews to the NSRB. This group rnay also recommend full NSRB review of the subjects, as appropriate.
Specifically, the QATR has been modified to require the NSRB to review written safety i evaluations of changes to the facility procedures and tests or experiments completed under the
! provisions of 10 CFR 50.59. This review will verify that such changes do not involve unreviewed safety questions and may be performed using a separate group under the auspices
- of the NSRB. This change is not considered a reduction in commitment by the licensee, j therefore, the mooification was not reviewed by the staff.
4 Currently in QATR, Section 18, Article 3.1.2, audits of the Offsite and Onsite Review Functions 4 are conducted on a planned and periodic 2-year frequency. However, as a result of changing l l the independent and onsite review organizations, the licensee proposes to conduct audits of the i NSRB for the operating pla" at a frequency not to exceed 5 years (QATR, Revision 66,
! Section 18, Article 3.1.2). a NSRB activities will be periodically reviewed for effectiveness at 4 a frequency not to exceec years by an experienced Nuclear Oversight personnel and/or
- industry peer. This review wdlinclude an evaluation of NSRB activities for compliance with the
[ QATR requirements (QATR, Revision 66, Section 20A, Article 3.8).
3.0 CONCLUSION
i The creation of the NSRB was not reviewed. The proposed reduction in commitment that modifies the audit frequency and includes a description of the review process for effectiveness of the independent review activities is acceptable because (1) an audit of the independent review activities will be performed at a frequency not to exceed 5 years; (2) an effectiveness review of the independent review activities will be conducted at a frequency not to exceed 2 years; (3) Nuclear Oversight (certifying authority for audit personnel) will be rasponsible for conducting the review using experienced personnel and/or industry peers; and (4) this review will include an evaluation of independent review activities for compliance with the quality assurance program requirements. The reduction in commitment in QATR, Revision 66, continues to comply with the criteria of Appendix B to 10 CFR Part 50.
Principal Reviewer: M. Bugg Dated: November 19, 1998
