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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20058F1151993-11-23023 November 1993 Safety Evaluation Supporting Amends 170,69,169 & 86 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20059G6411993-11-0101 November 1993 Safety Evaluation Supporting Amend 169 to License DPR-61 ML20059G5261993-10-27027 October 1993 Safety Evaluation Supporting Amend 168 to License DPR-61 ML20057E2011993-10-0404 October 1993 Safety Evaluation Supporting Amend 167 to License DPR-61 ML20057E1921993-10-0404 October 1993 Safety Evaluation Supporting Amend 166 to License DPR-61 ML20058M9051993-09-29029 September 1993 Safety Evaluation Supporting Amend 165 to License DPR-61 ML20058M9291993-09-29029 September 1993 SE Re SEP Topics III-2 & III-4.A, Wind & Tornado Loadings & Tornado Missiles. Licensee Estimated Reactor Core Damage Frequency Reduced Signficantly Such That Likelihood of Core Damage Reasonably Low ML20057A3501993-09-0202 September 1993 Safety Evaluation Supporting Amend 164 to License DPR-61 ML20057A3551993-09-0202 September 1993 Safety Evaluation Supporting Amend 163 to License DPR-61 ML20056G2891993-08-25025 August 1993 Safety Evaluation Supporting Amend 162 to License DPR-61 ML20056D7061993-07-26026 July 1993 Safety Evaluation on SEP VI-4 Re Containment Isolation Sys for Plant.All Penetrations Either Meet Provisions of or Intent of GDCs 54-57 Except for Penetration 39 ML20128E3291993-02-0404 February 1993 Safety Evaluation Granting Util Request for Authorization to Use Portion of Section XI of 1986 Edition of ASME Code for Visual Exams VT-3 & VT-4 to Be Combined Into Single VT-3 ML20128D5231992-11-25025 November 1992 Safety Evaluation Accepting 120-day Response to Suppl 1 to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46, ML20210E1891992-06-12012 June 1992 Safety Evaluation Considers SEP Topic III-5.B to Be Complete in That If Pipe Breaks Outside Containment,Plant Can Safely Shut Down W/O Loss of Containment Integrity ML20062B7411990-10-22022 October 1990 Safety Evaluation Supporting Amend 132 to License DPR-61 ML20059H3101990-09-0606 September 1990 Revised Safety Evaluation Clarifying Individual Rod Position Indication Testing Exception & Bases for Approving Test Exception ML20059A8021990-08-14014 August 1990 Supplemental Safety Evaluation Accepting Electrical Design of New Switchgear Room at Plant ML20056A5641990-08-0303 August 1990 Safety Evaluation Concluding That Pressurizer Has Sufficient Fracture Toughness to Preclude Fracture of Head W/Flaws Remaining in Component & Pressurizer Acceptable for Continued Svc ML20055G5441990-07-19019 July 1990 Safety Evaluation Supporting Amend 128 to License DPR-61 ML20055G5561990-07-19019 July 1990 Safety Evaluation Supporting Amend 129 to License DPR-61 ML20055E2361990-07-0202 July 1990 Safety Evaluation Supporting Amend 126 to License DPR-61 ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247A4841989-09-0505 September 1989 Safety Evaluation Supporting Amend 121 to License DPR-61 ML20245J0121989-08-14014 August 1989 Safety Evaluation Accepting Extension of Surveillance Intervals ML20247E6551989-07-20020 July 1989 Safety Evaluation Supporting Amend 120 to License DPR-61 ML20247E6841989-07-18018 July 1989 Safety Evaluation Supporting Amend 119 to License DPR-61 ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20246A8541989-06-23023 June 1989 Safety Evaluation Concluding That Large Containment at Plant Results in Slow Hydrogen Accumulation Rate & Ensures That Sufficient Time Available to Implement Addl Hydrogen Control Features After Accident.Requirements of 10CFR50.44 Met ML20244C4451989-06-0101 June 1989 Safety Evaluation Supporting Amend 117 to License DPR-61 ML20248B3001989-05-31031 May 1989 Safety Evaluation Supporting Amend 116 to License DPR-61 ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20245E8941989-04-21021 April 1989 Safeguards Evaluation Rept Supporting Amend 113 to License DPR-61 ML20235Z0881989-03-0707 March 1989 Safety Evaluation Supporting Amend 112 to License DPR-61 ML20196D8641988-12-0606 December 1988 Safety Evaluation Supporting Amend 109 to License DPR-61 ML20205M5731988-10-26026 October 1988 Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20204G8641988-10-18018 October 1988 Safety Evaluation Supporting Licensee Analysis of Consequences of Steam Generator Tube Rupture Accident at Facility Followed by Minimization of Water in Affected Steam Generator After Tube Rupture ML20155G4801988-09-28028 September 1988 Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively ML20151T7641988-08-0909 August 1988 Safety Evaluation Supporting Amend 106 to License DPR-61 ML20150A9551988-07-0101 July 1988 Safety Evaluation Supporting Amend 105 to License DPR-61 ML20155F9811988-06-0101 June 1988 Safety Evaluation Supporting Amend 104 to License DPR-13 ML20155G5031988-05-26026 May 1988 Safety Evaluation Supporting Amend 103 to License DPR-61 ML20153G9671988-04-28028 April 1988 Corrected Safety Evaluation Supporting Amend 97 to License DPR-61 1999-04-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 CY-99-047, Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use1999-03-23023 March 1999 Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use ML20206F1971998-12-31031 December 1998 Annual Rept for 1998 for Cyap. with CY-99-027, Annual Rept for 10CFR50.59, for Jan-Dec 1998.With1998-12-31031 December 1998 Annual Rept for 10CFR50.59, for Jan-Dec 1998.With ML20198G9101998-12-22022 December 1998 Proposed Rev 2 of Cyap QAP for Haddam Neck Plant. Marked Up Rev 1 Included ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co CY-98-136, Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line1998-08-12012 August 1998 Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line ML20237B7461998-07-22022 July 1998 1998 Defueled Emergency Plan Exercise Scenario Manual, Conducted on 980722 ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 CY-98-068, Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms1998-04-15015 April 1998 Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms CY-98-045, Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing1998-04-13013 April 1998 Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing ML20217F0611998-03-31031 March 1998 Historical Review Team Rept ML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 CY-98-046, Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal1998-03-12012 March 1998 Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal ML20216D6531998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Haddam Neck Plant ML20217D7381998-02-28028 February 1998 Revised MOR for Feb 1998 Haddam Neck Plant CY-98-012, Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant CY-98-010, Annual Rept for 10CFR50.59,Jan-Dec,19971997-12-31031 December 1997 Annual Rept for 10CFR50.59,Jan-Dec,1997 ML20198N6681997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Haddam Neck Plant ML20217P4861997-12-31031 December 1997 1997 Annual Financial Rept, for Cyap ML20199L5891997-12-24024 December 1997 Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant ML20203K4271997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Haddam Neck Plant ML20199B1141997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Haddam Neck Plant ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20198J8811997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Haddam Neck Plant ML20210P8721997-08-31031 August 1997 Post Decommissioning Activities Rept, for Aug 1997 ML20217Q3171997-08-31031 August 1997 Addl Changes to Proposed Rev 1 to QA Program ML20210U9301997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Haddam Neck Plant CY-97-082, Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys1997-08-14014 August 1997 Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys ML20210L0521997-07-31031 July 1997 Monthly Operating Rept for July 1997 for HNP ML20149E4451997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Haddam Neck Plant ML20141A0041997-05-31031 May 1997 Independent Assessment of Radiological Controls Program at Cyap Haddam Neck Plant Final Rept May 1997 ML20140H5241997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Haddam Neck Plant ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20141D4141997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Connecticut Yankee Haddam Neck ML20138G5901997-04-25025 April 1997 Proposed Rev 1 to Cyap QA Program for Haddam Neck Plant ML20137W8051997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Haddam Neck Plant ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20137C6281997-03-14014 March 1997 Redacted Version of Rev 1 to Nuclear Training Loit/Lout Audit Reviews ML20137A0801997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Haddam Neck Plant ML20135C5101997-02-26026 February 1997 1996 Refuel Outage ISI Summary Rept for CT Yankee Atomic Power Co B16268, Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor1997-02-19019 February 1997 Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor ML20135E3221997-02-13013 February 1997 Independent Review Team Rept 1996 MP -1 Lout NRC Exam Failures ML20134L2751997-02-0303 February 1997 Draft Rev to GPRI-30, Spent Fuel Storage Facility Licensing Basis/Design Basis ML20138K5721997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Haddam Neck Plant.W/ ML20134L2791997-01-10010 January 1997 Rev 0 to QA Program Grpi ML20134L2911997-01-0808 January 1997 Rev 0 to UFSAR Rev Grpi ML20134L2721996-12-31031 December 1996 Commitment Mgt Grpi 1999-04-28
[Table view] |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REQUESTS FOR RELIEF FROM INSERVICE INSPECTION REQUIREMENTS CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213
1.0 INTRODUCTION
Technical Specification 4.10 for the Haddam Neck Plant states that inservice examination of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda, as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission. Certain requirements of later editions and addenda of Section XI are impractical to perform on older plants because of the plants design, component geometry, and materials of construction.
Thus,10 CFR 50.55a(g)(6)(f) authorizes the Comission to grant relief from those requirements upon making the necessary findings.
By letter dated April 9,1984, Connecticut Yankee Atomic Power Company submitted its updated inservice inspection program and information related to requests for relief from certain Code requirements determined to be impractical to perform on the Haddam Neck Plant beginning with the third period during the second ten-year inspection interval. The updated program is based on the requirements of the 1980 Edition, through Winter 1980 Addenda, of Section XI of the ASME Code. These will remain in effect until January 1, 1988, unless the program is modified or changed prior to the interval end date.
s605270126 860512 DR ADOCK 0500 2
1 l
2.0 EVALUATION Requests for relief from the requirements of Section XI which have been detennined to be impractical to perform have been reviewed by the staff's contractor, Science Applications International Corporation. The con- )
tractor's evaluations of the licensee's requests for relief and his '
recomendations are presented in the attached technical evaluation report (Attachment 1). The staff has reviewed the TER and agrees with the evaluations and recommendations. A sumary of the determinations made by the staff is presented in Tables 1 through 5.
3.0 CONCLUSION
Based on the review summarized in the technical evaluation report, the staff concludes that relief granted from the examination and testing requirements and alternate methods imposed through this document give {
reasonable assurance of the piping and component pressure boundary and support structural integrity, that granting relief where the Code
~
requirements are impractical is authorized by law and will not endanger life or property, or the comon defense and security, and is otherwise in the public interest considering the burden that could resul't if they were imposed on the facility.
Dated: May 12,1986
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TABLE 1 CLASS 1 COMPONENTS s
Licensee IWB-2500-1 IWB-2500-1 System or Proposed Item No. Area to be Required Alternative Exam. Cat. Component Examined Relief Request Method Exam Status B3.120 4-0 Pressurizer Nozzle Inside Volumetric None Radius Granted Provided
- Section Visual Exam (VT-2) is .
Performed During m
Code-Required System Pressure j Tests .
82.51, B2.-5? 8-8 Regenerative B2.51: Volumetric Visual Exam
& B2.60 Heat Granted
- Circumfer- (VT-2) During Exchanger ential Shell (Primary Code-Required Welds, System Side) B2.52: Leakage &
Longitudinal , Hydrostatic ' ,
'Shell Welds, Tests ~
82.60: i Tubesheet- _
to-Shell -
Welds -
83.140 B-D Steam;' , Nozzle Volumetric None Generator Inside '
Granted Provided (Primary Radius Visual Exam Side) Section (VT-2) is performed .
during Code-Required s
1 System Pressure Tests
,. r
TABLE 1 (continued)
Licensee IWB-2500-1 Proposed IWB-2500-1 System or Area to be Required Alternative Item No. Exam. Cat. Component Relief Request Examined Method Exam Status B3.150 B-D Regenerative Nozzle-to-Volumetric Visual Exam Granted Heat Vessel Welds (VT-2) During Exchanger Code-Required (Primary System Leakage Side) & Hydrostatic Tests
! B5.30 B-F Steam Nominal Pipe 1 Volumetric Surface Granted Provided Generator Size > 4 in., & Surface Volumetric Exam j
Nozzle-to- is Performed Safe End Butt to Extent -
Welds Practical
. B9.10, B-J Piping B9.10:
t 89.20, B9.30 89.10: Code-Required Not Granted
' Pressure Nominal Surface & Exam to
& B9.40 Boundary Pipe Size Volumetric, Extent 4
> 4 in., B9.20: Practical B.9.20: Surface, i
j Nominal B9.30:
1 P1pe Size Nominal j
< 4 in., Size > 2
! 89.30: in.,
Branch Pipe Surface &
Connection Volumetric; l Welds, Nominal Pipe B9.40: Size < 2 in.,
Socket Welds Surface,
[ B9.40:
Surface t
i i
TABLE 1 (continued)
Licensee IWB-2500-1 Proposed IWB-2500-1 System or Area to be Required Item No. Exam. Cat. Component Alternative Relief Request -
Examined Method Exam Status B6.180 B-G-1 Pumps Bolts & Studs Volumetric Surface Granted Provided Exam When Bolting is Bolts & Studs Removed From a are Removed Pump During Interval B12.16 & B-L-1 Pumps B12.10:
B12.20 812.10: Code-Required Granted Provided
& B-L-2 Pump Casing Volumetric, Welds, Visual (VT-3) Surface Exam is B12.20: Exam if a Pump Performed on B12.20: Visual, is Disassembled External Surface Pump Casing VT-3 for Mainte- of Pump Casing nance, Welds, and Vibration Code-Required Monitoring, Exam is and Visual Performed (VT-2) Exam if a Pump is of Pump Disassembled Casings During for System Leakage Maintenance
- & Hydrostatic Tests B6.210 B-G-1 Valves Bolts & Studs Volumet'ric Surface E'am x Granted When Bolts
& Studs are Removed
TABLE 2 CLASS 2 COMP 0NENTS i .
Licensee IWC-2500 Proposed
'; IWC-2500-1 System or Area to be Required Item No. Exam. Cat. Component Alternative Relief Request Examined Method Exam Status C2.22 C-B Steam Nozzle Inside Volumetric None Generator Radius Section Granted Provided (Shell Side) Visual Exam (VT-2 is Performed During Code-Required System Pressure Tests i
, 6
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S s T t N s _
E e N u _
3 O q P e
- E M R 7 L O
- B C f _
A e T 3 i l
S e S R A
L o C N e
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TABLE 4 COMPONENT SUPPORTS .
No Relief Requests G
e
.g.
TABLE 5 PRESSURE TESTS IWA-5000 IWB-5000 IWC-5000 & Licensee Proposed System or IWD-5000 Test Component Pressure Requirement Alternative Relief Request Test Pressure Status Class 2 IWC-5222:
(Chemical & System Hydrostatic T'est Pressure at Granted Volume control Operating Pressure Charging Test Pressure Shall System, Seal be at Least 1.25 Times
- System Pressure for t Injection Systems with Design System., & Temperature Above Letdown 200*F System) 1 i
i i
- _ . . _ - -