Safety Evaluation Granting Three of Seven Requests Submitted by Util 861020 Ltr for Relief from Inservice Insp & Testing Requirements.Four Requests Withdrawn,Per 870122,0410 & 0507 LtrsML20216C111 |
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Site: |
Yankee Rowe |
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Issue date: |
06/18/1987 |
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From: |
Office of Nuclear Reactor Regulation |
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To: |
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Shared Package |
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ML20216C085 |
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References |
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NUDOCS 8706300218 |
Download: ML20216C111 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20211J3361999-08-27027 August 1999 Safety Evaluation Supporting Amend 152 to License DPR-3 ML20207F9491999-03-0505 March 1999 Safety Evaluation Supporting Amend 151 to License DPR-3 ML20202H5871999-02-0303 February 1999 Safety Evaluation Supporting Amend 150 to License DPR-3 ML20249A7901998-06-17017 June 1998 Safety Evaluation Supporting Amend 149 to License DPR-3 ML20237F1671993-02-19019 February 1993 Safety Evaluation Supporting Amend 147 to License DPR-3 ML20058F2201990-11-0202 November 1990 Safety Evaluation Accepting Util Response to Generic Ltr 83-28 Re post-trip Review - Data & Info Capability ML20058C4061990-10-22022 October 1990 Safety Evaluation Supporting Amend 137 to License DPR-3 ML20059G2411990-09-0606 September 1990 Safety Evaluation Supporting Amend 135 to License DPR-3 ML20058L6651990-08-0202 August 1990 Safety Evaluation Supporting Amend 134 to License DPR-3 ML20058L0321990-08-0202 August 1990 Safety Evaluation Supporting Amend 133 to License DPR-3 ML20055C8601990-06-18018 June 1990 Safety Evaluation Supporting Amend 132 to License DPR-3 ML20248H7391989-10-0303 October 1989 Safety Evaluation Not Accepting Procedure Generating Program for Plant.Program Should Be Revised to Reflect Items Described in Section 2 of Rept.Revision Need Not Be Submitted to NRC ML20247F1431989-09-0707 September 1989 Safety Evaluation Supporting Amend 124 to License DPR-3 ML20247E6831989-08-31031 August 1989 Safety Evaluation Supporting Amend 123 to License DPR-3 ML20246F2771989-07-11011 July 1989 Safety Evaluation Supporting Mods to ECCS Evaluation Model, Including Changes to FLECHT-based Reflood Heat Transfer Correlation,Steam Cooling Model & post-critical Heat Flux Heat Transfer Model ML20195D6701988-11-0101 November 1988 Safety Evaluation Supporting Amend 120 to License DPR-3 ML20205G1961988-10-25025 October 1988 Safety Evaluation Supporting Amend 119 to License DPR-3 ML20204G4871988-10-17017 October 1988 Safety Evaluation Supporting Amend 118 to License DPR-3 ML20205C4061988-10-14014 October 1988 Safety Evaluation Supporting Amend 117 to License DPR-3 ML20207L7051988-10-12012 October 1988 Safety Evaluation Supporting Amend 116 to License DPR-3 ML20207E8151988-08-0505 August 1988 Safety Evaluation Supporting Amend 115 to License DPR-3 ML20151M4911988-07-29029 July 1988 Safety Evaluation Supporting Amend 114 to License DPR-3 ML20151K3801988-07-25025 July 1988 Safety Evaluation Supporting Amend 113 to License DPR-3 ML20151K8571988-07-19019 July 1988 Safety Evaluation Supporting Amend 112 to License DPR-3 ML20153A8661988-06-29029 June 1988 Safety Evaluation Accepting Util Proposed Reflood Steam Cooling Model ML20196K2741988-06-28028 June 1988 Safety Evaluation Supporting Amend 111 to License DPR-3 ML20195K1501988-06-17017 June 1988 Safety Evaluation Supporting Amend 110 to License DPR-3 ML20195C5851988-06-13013 June 1988 Safety Evaluation Supporting Amend 109 to License DPR-3 ML20155K5141988-06-0909 June 1988 Safety Evaluation Supporting Amend 108 to License DPR-3 ML20154J7661988-05-18018 May 1988 Safety Evaluation Supporting Amend 107 to License DPR-3 ML20216J4081987-06-26026 June 1987 Safety Evaluation Supporting Amend 106 to License DPR-3 ML20216C1111987-06-18018 June 1987 Safety Evaluation Granting Three of Seven Requests Submitted by Util for Relief from Inservice Insp & Testing Requirements.Four Requests Withdrawn,Per 870122,0410 & 0507 Ltrs ML20215C5881987-06-0404 June 1987 Safety Evaluation Supporting Util 860505,870402,& 0506 Submittals Re Seismic Reevaluation of Plant.Concludes That Foundation Soils Under Reactor & Under Vapor Container Have Adequate Strength to Support Seismic Load from Earthquake ML20213G9161987-05-13013 May 1987 Safety Evaluation Supporting Amend 105 to License DPR-3 NUREG-0825, Safety Evaluation Supporting Util 840709,1231 & 851024 Repts Re Evaluation of Plant for Wind & Tornado Events as Requested in Integrated Plant Safety Assessment Rept, Sections 4.5 & 4.8.Risk from Wind/Tornado Events Assessed1987-05-13013 May 1987 Safety Evaluation Supporting Util 840709,1231 & 851024 Repts Re Evaluation of Plant for Wind & Tornado Events as Requested in Integrated Plant Safety Assessment Rept, Sections 4.5 & 4.8.Risk from Wind/Tornado Events Assessed ML20213D9671987-05-0707 May 1987 Safety Evaluation Supporting Amend 104 to License DPR-3 ML20207S6231987-03-10010 March 1987 Safety Evaluation Supporting Util 860122,0812,1028 & 870204 Submittals Re Fracture Toughness Requirements for Protection Against PTS Events ML20211N5881987-02-19019 February 1987 Safety Evaluation Re First Level Undervoltage Protection Testing.Testing Unnecessary ML20211L3951987-02-17017 February 1987 Safety Evaluation Supporting Amend 103 to License DPR-3 Re Max Nominal Enrichment of Fuel ML20207N8811987-01-0707 January 1987 Safety Evaluation Supporting Amend 102 to License DPR-3 ML20207N4261987-01-0606 January 1987 Safety Evaluation Supporting Amend 101 to License DPR-3 ML20207J9451986-12-30030 December 1986 SER Accepting Util 831105 & 850709 Responses to Generic Ltr 83-28,Item 2.1 (Part 2), Vendor Interface Program - Reactor Trip Sys Components ML20215E1201986-12-0909 December 1986 Safety Evaluation Supporting Util 830419 & 0830,840119, 851022 & 860930 Responses Re Conformance to Reg Guide 1.97. Plant Design Acceptable W/Exception of Neutron Flux Variable ML20214X3391986-12-0101 December 1986 Safety Evaluation Supporting Amend 100 to License DPR-3 ML20214J8521986-11-18018 November 1986 Sser Accepting SPDS Contingent Upon Resolution of Concerns Re Maint & Improvement of Placement & Visual Access of Containment Isolation Panel & Minor Human Factors Engineering Concerns ML20215E6471986-10-0202 October 1986 Safety Evaluation Supporting Util Requests for Exemption from Specific Requirements in App R to 10CFR50.Existing Fire Protection Provides Level of Protection Equivalent to Technical Requirements of App R ML20210S1791986-09-23023 September 1986 Safety Evaluation Supporting Amend 99 to License DPR-3 ML20212Q1151986-08-27027 August 1986 Safety Evaluation Supporting Util 830412 Proposal to Provide Integrated Safe Shutdown Sys Which Could Be Used for Safe Shutdown in Event of Fire at Facility ML20212N0161986-08-20020 August 1986 Safety Evaluation Supporting Amend 98 to License DPR-3 1999-08-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C1311999-10-0808 October 1999 Safety Evaluation Supporting Amend 153 to License DPR-3 ML20211J5111999-08-31031 August 1999 Rev 29 to Yankee Decommissioning QA Program ML20211J3361999-08-27027 August 1999 Safety Evaluation Supporting Amend 152 to License DPR-3 ML20209D5391999-06-22022 June 1999 Rev 29 to Yaec Decommissioning QA Program ML20207F9491999-03-0505 March 1999 Safety Evaluation Supporting Amend 151 to License DPR-3 ML20202H5871999-02-0303 February 1999 Safety Evaluation Supporting Amend 150 to License DPR-3 ML20154P9691998-10-16016 October 1998 Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program ML20249A7901998-06-17017 June 1998 Safety Evaluation Supporting Amend 149 to License DPR-3 ML20216C4581998-02-27027 February 1998 Response to NRC Demand for Info (NRC OI Rept 1-95-050) ML20203L1931998-02-25025 February 1998 Duke Energy Corp,Duke Engineering & Svcs,Inc,Yankee Atomic Small Break LOCA Technical Review Rept ML20203L2451998-02-23023 February 1998 Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc ML20203L1621998-02-18018 February 1998 Rept of Root Cause Assessment Review ML20203L2691998-02-16016 February 1998 Duke Engineering & Svcs Assessment Process Review Rept ML20199B4601998-01-20020 January 1998 Special Rept:On 980105,meteorological Monnitoring Instrumentation for Air Temp Delta T Inoperable for More than 7 Days.Caused by Breakdown in Wiring Between Junction Box at 199 Foot Level.Wiring Replaced ML20203J3001997-12-31031 December 1997 Ynps 1997 Annual Rept ML20217N0981997-08-21021 August 1997 LER 97-S02-00:on 970725,discovered Uncontrolled Safeguards Documents.Caused by Personnel Error.Matls Retrieved & Stored in Safeguards Repositories ML20210H0991997-08-0707 August 1997 LER 97-S01-00:on 970709,potential Compromise of Safeguards Info Occurred.Caused by Human error.Stand-alone Personal Computer & Printer Not Connected to Network,Have Been Located within Text Graphics Svc Dept ML20149K7781997-07-24024 July 1997 Special Rept:On 970520 & 0714,air Temp Delta T Channel Indicated Temp Difference Between Top & Bottom of Meteorological Tower.Caused by Reversed Input Wiring to Channel.Restored Air Temp Delta T Channel Operability ML20141E4671997-05-30030 May 1997 Rev 28 to Operational QA Program ML20135C8461996-12-31031 December 1996 Yankee Nuclear Power Station 1996 Annual Rept ML20132G6771996-12-20020 December 1996 Rev 27 to YOQAP-I-A, Operational QA Program ML20058N4771993-12-20020 December 1993 Rev 0.0 to Yankee Nuclear Power Station Decommissioning Plan ML20059K8491993-12-15015 December 1993 Clarifications to Pages 2,41,43 & 44 of 44 in Section I, Organization of YOQAP-I-A,Rev 24, Operational QA Program ML20059C5011993-10-29029 October 1993 Special Rept:On 931019,meteorological Instrumentation Channel for Delta T Declared Inoperable.Caused by Ceased Aspirator Motor Located at Top of Tower.Motor Replaced ML20056H1741993-06-10010 June 1993 Preliminary Assessment of Potential Human Exposures to Routine Tritium Emissions from Yankee Atomic Electric Co Nuclear Power Facility Located Near Rowe,Ma ML20237F1671993-02-19019 February 1993 Safety Evaluation Supporting Amend 147 to License DPR-3 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 ML20198D2541992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Recertification Program ML20198D2481992-05-13013 May 1992 Yankee Nuclear Power Station Certified Fuel Handler Initial Certification Program ML20062H1981990-11-30030 November 1990 Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor ML20058H2841990-11-0303 November 1990 Special Rept:On 901101,control Rod 24 Found Disconnected from Drive Shaft.Drive Shaft Latching Will Be Initiated ML20058F2201990-11-0202 November 1990 Safety Evaluation Accepting Util Response to Generic Ltr 83-28 Re post-trip Review - Data & Info Capability ML20062E8331990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Yankee Atomic Power Station ML20058G1471990-10-31031 October 1990 Vol 2 to Star Methodology Application for PWRs Control Rod Ejection Main Steam Line Break ML20058C4061990-10-22022 October 1990 Safety Evaluation Supporting Amend 137 to License DPR-3 ML20062B6751990-09-30030 September 1990 Monthly Operating Rept for Yankee Atomic Power Station for Sept 1990 ML20059G2411990-09-0606 September 1990 Safety Evaluation Supporting Amend 135 to License DPR-3 ML20059E3071990-08-31031 August 1990 Safety Assessment of Yaec 1735, Reactor Pressure Vessel Evaluation Rept for Yankee Nuclear Power Station. Detailed Plan of Action W/Listed Elements Requested within 60 Days After Restart to Demonstrate Ability to Operate Longer ML20059E8001990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Yankee Atomic Power Station ML20058P7841990-08-14014 August 1990 Part 21 Rept Re Misapplication of Fluorolube FS-5 Oil in Main Steam Line Pressure Gauges.All Four Indicators Replaced W/Spare Gauges Which Utilize High Temp Silicone Oil ML20058N6581990-08-13013 August 1990 Special Rept Re Diesel Fire Pump & Tank Inoperable for Greater than Seven Days for Draining,Cleaning & Insp.During Period Redundant Pumping Capacity Available Via Two Remaining Electric Driven Fire Pumps ML20058L0321990-08-0202 August 1990 Safety Evaluation Supporting Amend 133 to License DPR-3 ML20058L6651990-08-0202 August 1990 Safety Evaluation Supporting Amend 134 to License DPR-3 ML20056A1961990-08-0101 August 1990 Special Rept:Two Fire Pumps Inoperable at Same Time.Caused by Necessity to Accomplish Surveillance to Verify Capability to Start Pump on Emergency Diesel Generator 3 & Planned 18-month Insp of Diesel Per Tech Specs ML20055G6801990-07-31031 July 1990 Yankee Plant Small Break LOCA Analysis ML20055G7011990-07-31031 July 1990 Yankee Nuclear Power Station Core 21 Performance Analysis ML20055E1591990-07-31031 July 1990 Reactor Pressure Vessel Evaluation Rept ML20055J3221990-07-25025 July 1990 Decommissioning Funding Assurance Rept & Certification ML20055G7051990-07-19019 July 1990 Rev 0 to Yankee Cycle 21 Core Operating Limits Rept ML20055F6751990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Yankee Atomic Power Station 1999-08-31
[Table view] |
Text
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- UNI'TED STATES NUCLEAR REGULATORY COMMISSION l
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SAFETY EVALUATION BY-OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RE0 VEST FOR' RELIEF FROM INSERVICE l INSPECTION AND TESTING REQUIREMENTS' j c
, YANKEE ATOMIC ELECTRIC COMPANY 5 YANKEE NUCLEAR POWER. STATION L4 DOCKET N0. 50-029-l INTRODUCTION' .1 4
By letter dated October 20, 1986, the licensee, Yankee Atomic Electric, Company l (YAEC)submittedsevenreliefrequestsdealingwithinserviceinspection,(ISI)'.
and inservice testing (IST) requirements. 4
-j In letters' dated January 22,1987, April 10,1987'and May 7,1987, YAEC . .
' withdrew.four~of the requests, which are not addressed further'in this safety' i evaluation. The remaining relief requests are evaluated below.
EVALUATION OF RELIEF RE00ESTS j
- 1. Relief- Request No. '1, Charging.and Volume Control System, Class 2, Code Category G-H ClassL 2 portions of the charging system -(from CH-M0V'-522/523 to -
CH-V-611/CH-V-617)areinvolved.
Code Examination Requirement (1977 Edition through Summer 1978 Addenda)
IWC-5222(a): . The system hydrostatic test' pressure shall.be:at.least 1.10 times the' system pressure P with de least1.25 times'thesystemfressure'signtemperature'of200*F.orless,andat s
P for systems'with' design' temperature sy above 200'F.-
j Code Relief Request i
~
Relief is requested from pressure test requirements of-IWC-5222(a) for portions of'the charging system, i
1
.i) 8706300218 B70618 3
- DR. ADOCK0500g9 L
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Licensee ~BasisDfor Relief The subject' portions of .the charging ~ system cannot be.hydrostatically.testedi
. ati the Class .2 required pressure. This would result in overpressurization of
- the unisolatable Class 1 piping. .,
- Licensee Proposed Alternative Test' This section of piping will.be subjected to a hydrostatic test at the Class 11 required pressure which provides assurance of pressure boundary integrity.
' Staff Evaluation'~
The subject portions of Class 2 piping cannot be isolated from the Class 1 ,
piping. LThe. hydrostatic test pressure for Class'1 piping is 1.10 times the i system nominal' operating pressure. P and is'1,ess than the Class ? test
pressure. As indicated by the lice 8see, the'. Class 2 test-pressure may result-
- in-overpressuring the unisolatable Class 1 portions of piping. ' The ,
alternative testing' proposed by.the licensee is to.perfonn the hydrostatic test;of the' subject Class _2. piping'together with:the'u'nisolatable Class 1 piping at the Class I required pressure. The alternative testing is i adequate'to provide assurance of the-structural integrity of the.; system. .
Relief from the' Class 2 pressure test requirements for the portions'of- the ,
charging system that cannot be isolated fromLClass 1 piping may be granted ast 6 requested.
- 2. Relief Request No. 6,- Shutdown Cooling System Piping, Cla'ss 12,' Code Category C-F Thirty-nine (39) pipe welds are involved.
- 3. Relief Request No. 7, Safety Injection Piping,iClass 2, Code' Category '
C-F .;
Thirty-three (33) pipe welds are involved. , .j Code Examination Requirement (1974 Edition through Summer 1975 Addenda) j IWC-2411(b): The examinations required by IWC-2520. shall . be -perfonned such that 100% of the required examinations of.the. components'will be completed over 1 the system's service lifetime, a IWC-2411(e): The required examinations assigned.to the components in.each. ;
stream of the system shall be completed by the:end of the service lifetime, i butdivided'amongthenumber.ofinspection' intervals-(e.g.,four' intervals.for.
40-year designjservice lifetime.) .
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4 1
I i
Code Relief Request l
Relief is requested from the requirement that 100% of the required l examinations be completed over the service lifetime of the plant. The i licensee proposes to prorate the number of welds required to be examined l during the first interval. j i
Licensee Basis for Relief j When the licensee completed its first inspection interval in 1974, examination (
of Safety Class 2 pipe welds were not required by Section XI. The intent of ;
Section XI is to examine a percentage of welds over time to identify any )
system degradation. . The licensee does not believe any benefit is obtained by j backfitting the number of welds required to be inspected for the first {
interval. In addition, these examinations would result in unnecessary radiation exposure as well as additional time and manpower considerations. !
Licensee Proposed Alternative Test The licensee will examine the remaining welds (or 75%) over the service lifetime of the plant. This would be 116 welds for the shutdown cooling system piping and 103 welds for the safety injection piping. ;
Safety Evaluation
(
Subparagraph IWC-2411 defines the selection criteria ,for ASE Class 2 welds ;
subject to examination over the service lifetime of the facility. . The service !
lifetime is divided into four 10-year intervals. The Code requires the i examination of 25% of Class 2 welds defined in IWC-2411 during each 10-year ;
inspection interval.
)
The examination requirements for ' Class 2 components were imposed by the -
i 1
updating provisions of the regulation after Yankee Rowe had operated and l performed inspections for over ten years. The licensee raised the issue to !
determine whether IWC-2411 requires the acceleration of Class 2 examinations ;
- to account for no examination during the first inspection interval. Table j IWC-2500 defines the examination requirements of components selected from i IWC-2400 during each interval. The licensee is performing the examination of j at least 25% of the welds during each interval. The population size, method, i and extent of examination change with Code editions. However, the regulation '
j requires that examination in each inspection interval is independent of previous intervals. The staff concludes that the licensee is meeting the Code ;
requirement for the current interval and no relief is required.
CONCLUSION l q
For two of the relief requests reviewed, the staff concludes that the Code requirements are satisfied by the licensee's proposal and that relief is not required. For the remaining request, the staff has concluded pursuant to 10 CFR 50.55a (g)(6) that relief granted from the examination and testing )
requirements and the alternate methods imposed by this document provide ;
reasonable assurance of system integrity, that granting of the relief where code requirements are impractical is authorized by law and will not endanger :
~-
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.5. _4_
l life or property or the' common defense and security, and -is otherwise.in the pub 1h drterest considering the burden that could result.if they were imposed upon the facility. The relief granted remains in effect for the ten-year l inspection interval- ending on July 1,1991, .unless. revised or~ modified prior.to l that date. '
Dete: @N181237 Prir.cipal Contributor: S. Lee t
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