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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211J3531999-09-0101 September 1999 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
[Table view] 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
- on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With
ML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With 05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With1999-09-20020 September 1999
- on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With
ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20211J3531999-09-0101 September 1999 Safety Evaluation Supporting Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr 05000317/LER-1999-004, :on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With1999-08-23023 August 1999
- on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With
05000317/LER-1999-005, :on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With1999-08-23023 August 1999
- on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With
ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-003, :on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With1999-07-30030 July 1999
- on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With
ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-039, Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified LD-99-035, Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed 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 ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-002, :on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With1999-05-25025 May 1999
- on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With
ML20206U7031999-05-18018 May 1999 Rev 1 to Ran 97-031, Main CR Fire Analysis for IPEEE Section 4-1 ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored 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 ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With 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 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons 05000317/LER-1997-010, :on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With1999-01-29029 January 1999
- on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With
ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 05000317/LER-1998-009, :on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With1999-01-0808 January 1999
- on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With
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 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative 05000317/LER-1998-008, :on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With1998-11-11011 November 1998
- on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With
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
[Table view] |
Text
-
UNITED STATES l
68 NUCLEAR REGULATORY COMMISSION o
r.
j WASHINGTON, D. C. 20555
~s.,*.../
1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM INSERVICE PRESSURE TEST REQUIREMENTS BALTIMORE GAS AND ELECTRIC CALVERT CLIFFS NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 INTRODUCTION The Technical Specifications for the Calvert Cliffs Nuclear Power Plant Units 1 and 2 state that inservice examination of ASME B&PV Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific 3
written relief has been granted by the Commission. The Examination Program is based upon the requirements of the 1974 Edition with the Addenda through the Sumer of 1975. Certain requirements of this Edition and Addenda of Section XI are impractical to perfonn on older plants because of the plants' design, component geometry, materials of construction or the need for extensive temporary modifications and the resultant substantial radiation exposure to plant personnel.
By letter dated August 28, 1985, the Baltimore Electric Company requested relief from the pressure test inspection requirements of the Code for sections of pipes detennined to be impractical to perform these tests.
Requests for Relief Relief is requested for Class 2 piping from the High Pressure Safety Injection (HPSI) Auxiliary HPSI, and Low Pressure Safety Inspection (LPSI) Loop Isolation MOVs to the Reactor Coolant System (RCS).
The following lines are affected:
8511220422 851114 PDR ADOCK 05000317 P
PDR
UNIT 1 UNIT 2 FROM TO LINE N05.
FROM TO LINE NOS.
1-51-118 1-SI-615-MOV 6"CC-13-1001 2-SI-118 2-615-MOV 6"CC-13-2001 1-SI-616-MOV 2"CC-13-1019 2-SI-616-MOV 2"CC-13-2019 1-SI-617-MOV 3"CC-13-1014 2-SI-617-MOV 3"CC-13-2014 2"CC-13-1005 2"CC-13-2005 2"CC-6-1002 2"CC-6-2002 1-SI-128 1-SI-625-MOV 6"CC-13-1002 2-51-128 2-SI-625-MOV 6"CC-13-2002 1-SI-626-MOV 2"CC-13-1018 2-SI-626-MOV 2"CC-13-2018 1-SI-627-MOV 3"CC-13-1015 2-SI-627-MOV 3"CC-13-2015 2"CC-13-1006 2"CC-13-2006 2"CC-6-1004 2"CC-6-2004 1-51-138 1-SI-635-MOV 6"CC-13-1003 2-51-138 2-SI-635-MOV 6"CC-13-2003 1-SI-636-MOV 2"CC-13-1016 2-SI-636-MOV 2"CC-13-2016 1-SI-637-MOV 3"CC-13-1021 2-SI-637-MOV 3"CC-13-2021 2"CC-13-1007 2"CC-13-2007 2"CC-6-1005 2"CC-6-2005 1-51-148 1-SI-645-MOV 6"CC-13-1004 2-SI-148 2-SI-645-MOV 6"CC-13-2004 1-SI-646-MOV
' 2"CC-13-1017 2-SI-646-MOV 2"CC-13-2017 1-SI-647-MOV 3"CC-13-1020 2-SI-647-MOV 3"CC-13-2020 2"CC-13-1008 2"CC-13-2008 2"CC-6-1005 2"CC-6-2006
ISI Code Class 2 Requirements f
ASME Code Section XI requires hydrostatic testing of all Class 2 piping and components as set forth in Articles IWA-5000 and IWC-5000.
The test pressure requirement for Class 2 piping and components is 1.25 times the design pressure when tested at a temperature not less than 100*F.
i Basis for Relief Request A.
The listed portion of Class 2 piping from HPSI, Aux. HPSI, and LPSI i
Loop Isolation MOV to RCS cannot be isolated from the RCS.
Licensee's Proposed Alternative Tests 1
The licensee proposes to perform a hydrostatic pressure test of the above listed piping, excluding the piping listed in the relief request Item B.
below, to the pressure test requirements of IWB-5000 for Class 1 piping.
This piping can be pressurized via alignment of the charging system to the i
Aux. HPSI header.
j B.
The portions of piping listed below cannot be hydrostatically tested due
- to inability to align charging pumps to pressurize this piping and the l
operability requirements of these portions when the RCS is pressurized.
i i
4 UNIT 1
{
FROM TO LINE NO.
1-51-114 1-SI-615-MOV 6"CC-13-1001 7
1-51-124 1-SI-625-MOV 6"CC-13-1002 1-SI-134 1-SI-635-MOV 6"CC-13-1003 1-51-144 1-SI-645-MOV 6"CC-13-1004
)
UNIT 2 FROM T_0 LINE NO.
2-51-114 2-SI-615-MOV 6"CC-13-2001 2-51-124 2-SI-625-MOV 6"CC-13-2002 2-51-134 2-SI-635-MOV 6"CC-13-2003 2-51-144 2-SI-645-MOV 6"CC-13-2004 Licensee's Proposed Alternate Tests The following tests and examinations are proposed in lieu of hydrostatic testing for proving.the integrity of the piping listed in Item B. above.
1.
Each refueling cycle, a leakage test of this piping is performed in accordance with Technical Specification 6.14.
In this test the piping listed in Item B. is pressurized to LPSI pump discharge pressure and a visual examination for leakage is conducted.
2.
Welds will be selected and examined per Section XI, Article IWC-2000.
Evaluation
.s.
The section of piping upstream of check valves51-118,-128,-138,-148, for Units 1 and 2, cannot be tested at a pressure of 1.25 times design pressure without making extensive temporary modifications to keep the valves closed.
The modifications would require:
(1)disassemblyofthevalves,(2), welding of temporary blocks (on the downstream side) inside the valve bodi,es to hold a" jackscrew"typearrangementtokeepthevalveclosed,(3)removalofthe temporary blocking devices from the valves after testing and (4) performing necessary nondestructive testing to assure the integrity of the valve bodies
before returning them to service. Without the temporary modifications to the check valves, the Class 1 system downstream of the check valves would be pressurized to the test pressure of the Class 2 system. This pressure exceeds the Class I hydrostatic pressure requirements.
Conclusion I
Based upon a review of the system design, the basis for relief request, and the licensee's proposed alternate tests, the staff concludes that relief granted from examination and pressure test requirements and alternate methods imposed through this document give reasonable assurance of the piping pressure boundary 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 l
and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the facility. Therefore, in accordance i
with 10 CFR 50.55a (g)(6)(1), relief is granted.
i Principal Contributor:
B. Turovlin Date: November 14, 1985
.