|
---|
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] |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
eneog w
y '4 UNITED STATES
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066tW1001
\*****/
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING REVISION 1 TO QUALITY ASSURANCE PRODRAM FOR CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT - DOCKET NO. 50-213
1.0 INTRODUCTION
By letter dated April 25,1997, Connecticut Yankee Atomic Power Company (CYAPCO) transmitted proposed Revision 1 to the Connecticut Yaakee Quality Assurance Program (CYOAP)in accordance with 10 CFR 50.54(a). The proposed revision was then amended by letter dated August 21,1997.
2.0 BACKGROUND
Pursuant to the requirements of 10 CFR 50.82, CYAPCO submitted a letter, dated December 5,1996, informing the Commission that tb, Haddam Neck Plant (Plant) had permanently ceased power operations and that all nuclear fuel had been removed from the ,
reactor vessel.
By letter dated February 20,1997, CYAPCO notified the Commission that it was reviewing Plant programs with the intent of making revisions to reflect the permanently shutdown status of the plant and that it was adopting,in its entirety, approved Revision 18 of the Northeast Utilities Quality Assursace Program (NUGAP) as the " Quality Assurance Program for the Haddam Neck Plant," Revision O. (Revision 18 was generically applicable to the Plant and the Millstone Units.) The intent of this purely administrative action was to allow CYAPCO to make changes specific to the Plant quality assurance program independent of the Millstone Station. Revision 1 of the CYOt.P, submitted by lettor dated April 25,1997, and subsequently amended by letter dated August 21,1997, reflects the permanently defueled condition.
3.0 EVALUATION The major change to Revision 0 of the CYOAP involvos the Plant organization reflecting the transition from an operating plant to a defueled plant undergoing decontamination and decommissicning. By letter dateo N ay 22,1997, the NRC issued license Amendment No.191 to the Plant operating license, which revises Administrative Controls Section 6.0 of the Technical Specifications (TS) to implement changes in msnagement responsibilities and titles that reflect the permanently shutdown status of the plant. Section 1.0,
" Organization", of the CYOAP, Revision 1, reflects changes in the Plant organization and is cot.sistent with License Amendment No.191.
9710300008 971014 PDR ADOCK 05000213 W PDR
< ~ _ I
'l_ is ;
m In addition, Section 1.0 of the CYQAP has been revised to minimize refstences to Millstone programs. Still referenced NUQAP organizations include Nuclear Oversight and Nuclear
- Safety Engineering, in addition, the program for offsite audits; evaluations, and inspections of vendors, conducted by the Nuclear Materials and Documentation organization, remains a
- Millstone function; receipt inspection is also, primarily, a Millstone function. Revision.19 of
- the NUQAP describes the responsibilities of these organizations.
Structures, systems, and components (SSCs) important to safety are identified in Section 3.2.1 of the CY Updated Final Safety Analysis Report (UFSAR). These SSCs, to which the requkements of Appendix 8 to 10 CFR Part 50 (App. B) are applied, are addressed by Appendix A of the CYOAP. While Revision 0 of the CYOAP pertains to an
- operating plant, Revision 1 partains to the current status of the facility, that is, one
, undergoing docommissioning and decontamination.
The remaining scope of SSCs falling under the requirements of App. B are primarily'the spent fuel storage pool _and supporting systems. This scope is consistent with a proposed May 30,1997 revision to the TS currently unJer review by the staff, and provides an appropriate description of the scope of the Piant Quality Assurance Program. In addition to l
these SSCs, augmented programs for fire protection and radiation protection have been
. retained.within the scope of the CYOAP.
Decommissioning activities are being corducted in accordance with the final rule for decommissioning of _ nuclear p.ower reactors, promulgated in the Federal Register on July 29, 1996. Certification that feel has been permanently removed from the reactor pursuant to
._10 CFR 50.82(a) was submitted to the Commission by letter dated December 5,1997. -
Reclassification of SSCs is controlled by the CY design control process in compliance with-
- 10 CFR 50.59. TS applicable to the decommissioning process are being developed on a
' case by-case basis pursuant to the requirements of -10 CFR 50.36(c)(6). Due to the -
- permanently shut down status of the plant, the overall reduction in the number of SSCs
- under the scope.of the CYOAP program is acceptable, as many less SSCs are now required
'to safely _ operate and decommission the plant.
14.0: CONCLUSIONS The proposed revisions to the CYOAP has been reviewed in accordance with 10 CFR 50.54(a). On the basis of this review, the staff has determined that the CYOAP, Revision 1, meets the requirements _of App. B and meets the additional requirements of
. 10 CFR 50.34(b)(6)il) and is therefore acceptable.
' 5.0 ' REFERENCE MATERIAL USED BY REVIEWERS (1)' Letter, dated August 10.1995, from U.S. Nuclear Regulatory Commission to Mr. J. F.
Opeka transmitting NRC review and approval of Revision 18 to the Northeast Utilities
' Quality Assurance Topical Report (2) Letter, dated February _20,1997, from D. M. Goebel to the U.S. Nuclear Regulatory
- Commission, "Haddam Neck Plant Quality Assurance Program"
{
m i. . P .
v 3-
'(3) Letter, dated April 25,1997, from Mr. T. C. Feigenbaum to the U.S. Nuclear -
- Regulatory Commission transmitting Proposed Revision 1 to the Quality Assurance Program for. Connecticut Yankee Atomic Power Company's Haddam Neck Plant
~(4) Letter,' dated June 3,1997, from B. D. Kenyon to the U.S. Nuclear Regulatory Commission transmitting Proposed Revision 19 to the Northeast Utilities Quality Assurance Program Topical Report - Millstone Nuclear Power Station (5)- Letter, dated December 5,1996, from Mr. T. C. Feigenbaum to the U.S. Nuclear Regulatory Commission, " Certification of Permanent Cessation of Power Operation and
- that Fuel Has Been Permanently Removed from the Reactor" l
-(6) " Decommissioning of Nuclear Powsc Reactors," U.S. Nuclear Regulatory Commission, -
10 CFR Parts 2, 50, and 51, Federal RegisterNol. 61, No.146, July 29,1996 '
(7) Letter, dated May 22,1997, from U.S. Nuclear Regulatory Commission to Mr. T. C.
Folgenbaum transmitting issuance of Amendment 191 r- (8) -- - Letter, dated May 30,1997, from T. C. Feigenbaum to the U.S. Nuclear Regulatory Commission, transmitting Proposed Revision to Operating License and Technical Specifications, Defueled Operating License and Technical Specifications
-(9) Le..er, dated June 24,1997, from J. R. Haley to UFSAR Controlled Copyholders transmitting Change No. 28 to the Haddam Neck Plant Updated Final Safety Analysis Report (10) Letter, dated August 21,1997, from T. C. Feigenbaum to the U.S. Nuclear Regulatory Commission transmitting Additional Changes to Proposed Revision 1 to the Quality
-.; Assurance Program for Connecticut Yankee Atomic Power Company Haddam Neck Plant - -
Principle Reviewer: Kenneth Heck Datedi October 14, 1997 s
4