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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 ML20244C3311989-04-10010 April 1989 Safety Evaluation Supporting Amend 137 to License DPR-26 ML20215A7821986-05-0808 May 1986 Sser Re Util Response to Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip. Licensee Should Submit Proposed Tech Specs Consistent W/Generic Ltr 85-09 Guidance for NRC Review.Salp Input Also Encl ML20028C3851983-01-0505 January 1983 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Continued Operation Presents No Undue Risk.Two Major Qualification Deficiencies Listed ML20052H3621982-05-10010 May 1982 Safety Evaluation Supporting Amend 44 to License DPR-64 ML19345E7771981-01-15015 January 1981 Safety Evaluation Supporting Amend 34 to License DPR-64 ML19340E6121980-12-18018 December 1980 Safety Evaluation Re Susceptibility of safety-related Sys to Flooding from Failure of Noncategory I Sys ML20062D2601978-11-0606 November 1978 Safety Eval Supporting Amend 18 to Facil Oper Lic DPR-64 for Subj Facil.Changes Incl Reduction in Maximum Pressurizer Heatup Rate & Change in Definition of Quadrant Pwr Tilt Ratio ML20062C9391978-10-17017 October 1978 Safety Eval Supporting Amend 42 to Facil Oper Lic DPR-26. Concludes That No Harm Will Ensue 1999-02-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated ML20236V4281998-07-13013 July 1998 Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable ML20236T5511998-06-24024 June 1998 Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C ML20248B2371998-03-31031 March 1998 Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML1005008001997-02-28028 February 1997 Conditional Extension of Rod Misalignment TS for Indian Point 3. ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20096E5101995-12-31031 December 1995 Resubmitted Rev 13 to QA Program 05000286/LER-1994-010, :on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised1994-11-0707 November 1994
- on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised
ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML20029C7801994-03-31031 March 1994 Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20062J2281993-07-23023 July 1993 Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993 ML20044B8461993-03-0404 March 1993 Part 21 Rept Re Possible Safety Implications in Motor Operated Valve Evaluation Software Program Re Use of Total Thrust Multiplier.Utils Advised of Problem & Recommended Corrective Action in Encl Customer Bulletin 92-06 ML20118A2681992-12-31031 December 1992 Consolidated Edison Co of Ny Indian Point,Unit 2 Exercise Scenario,1992 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20096H2301992-05-21021 May 1992 Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested ML20079F9181991-05-31031 May 1991 Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification ML20059E9461990-08-31031 August 1990 Nonproprietary Rev 2 to Indian Point 2 Tube Fatigue Reevaluation ML20059G2011990-07-31031 July 1990 Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp ML20058K4151990-06-30030 June 1990 Steam Generator Insp,Repair & Restoration Program Presentation to Nrc ML20058K4121990-06-30030 June 1990 Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc ML20043A4891990-05-30030 May 1990 Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program JPN-90-035, New York Power Authority Annual Rept for 19891989-12-31031 December 1989 New York Power Authority Annual Rept for 1989 ML19332B9371989-11-30030 November 1989 Nonproprietary Info Presented to NRC Re Indian Point Unit 2 Steam Generator Secondary Side Loose Objects. ML19332D6661989-10-31031 October 1989 Nonproprietary Rev 2 to Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage. ML20247J8161989-07-31031 July 1989 Safety Evaluation for UHS Temp Increase to 95 F at Indian Point Unit 3 05000286/LER-1989-013-01, :on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities1989-07-28028 July 1989
- on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities
ML20248D3631989-06-30030 June 1989 Rev 1,to Indian Point Unit 3 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20248B3171989-06-30030 June 1989 Rev 1 to Nonproprietary WCAP-12294, Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept,Spring 1989 Outage ML20247N5331989-05-31031 May 1989 Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage ML20247J8071989-05-31031 May 1989 Containment Margin Improvement Analysis for Indian Point Unit 3 ML20247G5171989-04-30030 April 1989 Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point 05000286/LER-1989-007, :on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained1989-04-17017 April 1989
- on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained
ML20244C3311989-04-10010 April 1989 Safety Evaluation Supporting Amend 137 to License DPR-26 ML20248F4211989-03-31031 March 1989 NSSS Stretch Rating-3,083.4 Mwt Licensing Rept 05000286/LER-1989-001, :on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded1989-03-0303 March 1989
- on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded
ML20235V5931989-03-0202 March 1989 Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed 05000286/LER-1989-003-01, :on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed1989-02-23023 February 1989
- on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed
ML20248F3001988-12-31031 December 1988 10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988 ML20246E2711988-12-31031 December 1988 Con Edison 1988 Annual Rept ML20196D3011988-10-31031 October 1988 Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V ML20155H2541988-09-30030 September 1988 Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations ML20154M5661988-08-31031 August 1988 Monthly Operating Rept for Aug 1988 for Indian Point Station Unit 2 1999-02-09
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED'T0 AMENDMENT NO.137 TO FACILITY OPERATING LICENSE NO. DPR-26 CONSOLIDATED EDIS0N COMPANY OF NEW YORK. INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 1.0 IN'TRODUCTION By letter dated August 18, 1986, Consolidated Edison Company (licensee) proposed changes and additions to the Indian Point 2 Technical Specifications which would require the operability and surveillance testing of the shunt trip attachments of the reactor trip breakers as required by Generic Letter 83-28, Item 4.3.
The original required changes wert clarified and modified by Generic l
Letter 85-09. The licensee's proposal was reviewed and additional changes to make the Technical Specifications confonn more fully to the requirements of Generic Letter 85-09 were made during a meeting with the licensee held on December 12, 1988. These changes were incorporated by the licensee's submittal of January 25, 1989 and are reviewed in this SER, 2.0 EVALUATION The licensee's Technical Specifications differ in many respects from the Standard Westinghouse. Technical Specifications which were used as the basis for the requirements of Generic Letter 85-09. Consequently, the changes proposed'in the August 18, 1986 letter addressing the operability and surveillance test requirements for the shunt trip attachment of the reactor trip breakers did not fully meet the requirements of Generic Letter 85-09.
In a meeting with the staff on December 12, 1988, the licensee agreed that the originally proposed allowed out-of-service time (A0T) of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with one train inoperable would be chang?d to six hours which is in accordance with Generic Letter 85-09 recommendations. The licensee's submittal of
-January 25, 1989 contained this change.
The modified Technical Specification changes now provide for testing the manual reactor trip switch functions independently for the shunt and undervoltage trip attachments of the reactor trip breakers and the reactor tripswitchcontactsandwiringateachrefueling(outage.ReactorTripBreakers),and The action statements for Items 18 (Reactor Trip Logic),19 a note to Table 3.5-2 were chariged to conform more closely to the guidance of Generic Letter 85-09. The previous Technical Specification changes contained in the licensee's submittal of August 18, 1986 which addressed changes to "kfD^E0!E8:8Q
Item 25 and.added Items 42 -43, and 44 to Table 4.1-1 were left in place. The licensee's test procedure PT-M14A was revised to reflect the installation of the automatic shunt trip modification.
In addition, the licensee proposed j
increasing the time a reactor trip breaker or its associated logic channel could be bypassed for maintenance or surveillance testing from the two hours specified in Generic Letter 85-09 to eight hours. This increased A0T is required to perform the required surveillance test since Indian Point Unit 2 uses relay protection logic rather than solid state protection logic as was envisioned when the requirements of Generic Letter 85-09 were developed. We agree that relay protection logic requires this additional amount of time to perforin the required testing.
3.0 CONCLUSION
We find that the proposed changes to the Indian Point Unit 2 Technical Specifications presented in the licensee's submittals and agreed to in the December 12, 1988 meeting meet the requirements of both Generic Letter 83-28, Item 4.3 and Generic Letter 85-09 and are, therefore, acceptable.
ENVIRONMENTAL CONSIDERATION The amendment changes 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 changes surveillance requirements. The staff has determined that this amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed fin A q that this amendment involves no significant hazards consideration and h e has been no public comment on such finding. Accordingly, this amendme:nt meets the eli criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)gibility (9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) there
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is reasonable assurance that the health and safety of the public will not be i
endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of j
this amendment will not be inimical to the common defense and security or to the health and safety of the public.
j Dated: April 10, 1989 PRINCIPAL CONTR_IBUTOR:
D. Lasher
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