ML20076K756
ML20076K756 | |
Person / Time | |
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Site: | Calvert Cliffs |
Issue date: | 10/21/1994 |
From: | Office of Nuclear Reactor Regulation |
To: | |
Shared Package | |
ML20076K749 | List: |
References | |
NUDOCS 9411020083 | |
Download: ML20076K756 (3) | |
Similar Documents at Calvert Cliffs | |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211J3531999-09-0101 September 1999
[Table view]Safety Evaluation Supporting Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20205J8331999-04-0707 April 1999 Safety Evaluation Concluding That Security Lighting,Portable Lighting & Helmet Lights,As Described by Licensee Satisfies Underlying Purpose of 10CFR50,App R,Section Iii.J.Grants Licensee Request for Exemption ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20204B5961999-03-17017 March 1999 Corrected Page 7 to SER for Amend 205 for License DPR-69. Staff Deleted Word Not on Line One of Page 7 ML20207L2991999-03-0808 March 1999 Safety Evaluation Supporting Amend 205 to License DPR-69 ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20195D4271998-11-0505 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-69 ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20248B0241998-05-23023 May 1998 Safety Evaluation Supporting Amends 228 & 202 to Licenses DPR-53 & DPR-69,respectively ML20217Q7971998-05-0404 May 1998 Safety Evaluation Supporting Amends 227 & 201 to Licenses DPR-53 & DPR-69,respectively ML20217P7441998-04-0707 April 1998 SE Accepting Licensee Request for Second 10-yr Insp Interval to Use ASME Section IX Code Case N-416-1, Alternative Pressure Test Requirement for Replacement Items by Welding, Class 1,2 & 3,Div 1 at Plant Per 10CFR50.55a(a)(3)(i) ML20216H1811998-03-17017 March 1998 Safety Evaluation Supporting Amends 226 & 200 to Licenses DPR-53 & DPR-69,respectively ML20203E9741998-02-11011 February 1998 SER Accepting IST Program Requests for Relief Submitted for Third 10-yr Intervals for Pumps & Valves for Plant ML20203A6581998-02-10010 February 1998 Safety Evaluation Supporting Amend 225 to License DPR-53 ML20203A1311998-02-0404 February 1998 SER Re Emergency Diesel Generator Qualification Rept Granting Licensee Proposed Temporary Exemption from GDC-2 ML20198L3001998-01-0808 January 1998 Correction to SE Supporting Amends 223 & 199 to License DPR-53 & DPR-69 Re Rev to Error on Pages 1 & 5 ML20198K5511998-01-0505 January 1998 Safety Evaluation Supporting Amend 224 to License DPR-53 ML20198K3741998-01-0505 January 1998 Safety Evaluation Authorizing Second 10-yr ISI Interval for Plant,Units 1 & 2 Relief Request from ASME Boiler & Pressure Vessel Code Requirements to Use Performance Demonstration Initiative Program ML20198B4611997-12-15015 December 1997 Corrected Page 3 of SE for Amends 222 & 198 Issued to FOLs DPR-53 & DPR-69,respectively,on 971002.Page 3 Revised to State That Consequences of Previously Analyzed Accident Will Be Significantly Decreased ML20197G1291997-12-15015 December 1997 Safety Evaluation Accepting Revised Withdrawal Schedules for Plant,Units 1 & 2 ML20202C3661997-11-18018 November 1997 Safety Evaluation Supporting Amends 223 & 199 to Licenses DPR-53 & DPR-69,respectively ML20211J4891997-10-0202 October 1997 Safety Evaluation Supporting Amends 222 & 198 to Licenses DPR-53 & DPR-69,respectively ML20135F8001997-03-0707 March 1997 Safety Evaluation Supporting Amends 221 & 197 to Licenses DPR-53 & DPR-69 ML20134K7341997-02-11011 February 1997 Safety Evaluation Supporting Amends 219 & 196 to Licenses DPR-53 & DPR-69 ML20134G5291997-02-0707 February 1997 Safety Evaluation Re Request Relief from ASME Code Requirement for Calvert Cliffs Nuclear Power Plant,Unit 1 ML20134A9651997-01-23023 January 1997 Safety Evaluation Supporting Amends 218 & 195 to Licenses DPR-53 & DPR-69,respectively ML20112J3361996-06-17017 June 1996 Safety Evaluation Supporting Amends 215 & 192 to Licenses DPR-53 & DPR-69,respectively ML20101G9251996-03-22022 March 1996 Safety Evaluation Supporting Amends 213 & 190 to Licenses DPR-53 & DPR-69,respectively ML20101G2881996-03-13013 March 1996 Safety Evaluation Supporting Amends 212 & 189 to Licenses DPR-53 & DPR-69,respectively ML20100H1421996-02-21021 February 1996 Safety Evaluation Supporting Amend 211 to License DPR-53 ML20097E3561996-02-0505 February 1996 Safety Evaluation Supporting Amends 210 & 188 to Licenses DPR-53 & DPR-69 ML20095H7831995-12-19019 December 1995 Safety Evaluation Supporting Amend 187 to License DPR-69 ML20093B4501995-10-0505 October 1995 Safety Evaluation Supporting Amends 207 & 185 to Licenses DPR-53 & DPR-69,respectively ML20092N3191995-09-26026 September 1995 Safety Evaluation Supporting Amends 206 & 184 to Licenses DPR-53 & DPR-69,respectively ML20082V2981995-05-0202 May 1995 Safety Evaluation Supporting Amend 205 to License DPR-53 ML20082G8561995-04-10010 April 1995 Safety Evaluation Supporting Amend 183 to License DPR-69 ML20081B2401995-03-14014 March 1995 Safety Evaluation Supporting Amends 204 & 182 to Licenses DPR-53 & DPR-69,respectively ML20081A0591995-03-0303 March 1995 Safety Evaluation Supporting Amends 203 & 181 to Licenses DPR-53 & DPR-69,respectively ML20077C6081994-11-29029 November 1994 Safety Evaluation Supporting Amends 201 & 179 to Licenses DPR-53 & DPR-69,respectively ML20076M6351994-11-0101 November 1994 Safety Evaluation Supporting Amend 178 to License DPR-69 ML20078C3421994-10-21021 October 1994 Safety Evaluation Supporting Amends 200 & 177 to Licenses DPR-53 & DPR-69,respectively 1999-09-01 Category:TEXT-SAFETY REPORT MONTHYEAR05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With1999-10-22022 October 1999
[Table view]
ML20195D4271998-11-0505 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-69 ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With 1999-09-30 |