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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210B7941999-07-15015 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 ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 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 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 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) ML20203E9741998-02-11011 February 1998 SER Accepting IST Program Requests for Relief Submitted for Third 10-yr Intervals for Pumps & Valves for Plant 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 ML20197G1291997-12-15015 December 1997 Safety Evaluation Accepting Revised Withdrawal Schedules for Plant,Units 1 & 2 ML20134G5291997-02-0707 February 1997 Safety Evaluation Re Request Relief from ASME Code Requirement for Calvert Cliffs Nuclear Power Plant,Unit 1 ML20058G0561993-11-29029 November 1993 Safety Evaluation Granting Relief from Installation Requirements of Section Iii,Article 9 of 1968 Edition of ASME Boiler & Pressure Vessel Code for Plant ML20057C3831993-09-22022 September 1993 Sser Accepting Licensee 930707 Response to Station Blackout Rule,Per 10CFR50.63 ML20127C0571992-12-23023 December 1992 Safety Evaluation Accepting Clarification of Previous Reactor Vessel Surveillance Program Actions & Withdrawal Schedule Change for Reactor Matl Surveillance Capsule ML20128B9371992-11-20020 November 1992 Safety Evaluation Accepting Licensee Response to Suppl 1 to GL 87-02 IR 05000317/19900801990-11-21021 November 1990 SER Determining That Load Profile Used During Surveillance Test Procedure Meets Requirement of Tech Spec 4.8.2.3.2.e, Per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 ML20059N2251990-10-0101 October 1990 Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 ML20245E8561989-06-22022 June 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20247D0361989-03-24024 March 1989 Safety Evaluation Supporting Amend 119 to License DPR-69 ML20205P6491988-11-0202 November 1988 Safety Evaluation Re Compliance w/10CFR50.62 ATWS Rule. Auxiliary Feedwater Actuation Sys Designs in Conformance W/ Requirements of TMI Action Plan Item II.E.1.2,surveillance Testing,Complies W/Atws Rule ML20238A3141987-08-24024 August 1987 Safety Evaluation of Encl Technical Evaluation Repts EGG-NTA-7243,EGG-NTA-7720 & EGG-NTA-7463 & Licensee Submittals in Response to Generic Ltr 83-28,Items 2.1.1, 2.1.2 & 4.5.2.Responses Acceptable ML20213E8731987-05-11011 May 1987 Safety Evaluation Supporting Util 861002 Request for Relief from Inservice Insp Requirements of ASME Code Section XI Re Peripheral CRD Housings ML20205R7061987-03-26026 March 1987 Safety Evaluation Supporting Relief from Certain ASME Code Hoop Stress Requirements Until Next Refueling Outage to Repair Flaw in Base Metal of Steam Generator Main Steam Line 12 ML20210P0911987-02-0404 February 1987 Safety Evaluation Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Util Must Submit Reevaluation of Resistance Temp PTS ML20207P0721987-01-0606 January 1987 Safety Evaluation Supporting Conformance to Reg Guide 1.97 W/Noted Exceptions ML20198G6971986-05-22022 May 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20210P2801986-05-0606 May 1986 Safety Evaluation Accepting Licensee Response to Items 3.1.3 & 3.2.3, Post-Maint Testing of...Safety-Related Components, of Generic Ltr 83-28 ML20202E0721986-03-31031 March 1986 Safety Evaluation Supporting Amend 116 to License DPR-53 ML20141N7691986-03-10010 March 1986 Safety Evaluation Granting Util 850913 & 860113 Requests for Relief from ASME Boiler & Pressure Vessel Code,Section XI Re Observation of Lubricant Level or Pressure During Pump Testing ML20136G7371985-11-14014 November 1985 Safety Evaluation Granting Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirement Re Pressure Testing of Class 2 Piping Associated W/Rcs ML20138E2821985-10-10010 October 1985 Safety Evaluation Re Extended Burnup of C-E PWR Fuel. Methodologies Acceptable for Extended Burnup Application ML20137W8811985-09-18018 September 1985 Safety Evaluation Granting Relief from Radiographic & Visual Insp of Reactor Coolant Pump Casings ML20126L8241985-07-18018 July 1985 Suppl to Safety Evaluation Supporting Response to IE Bulletin 80-11 Re Reevaluation of 22 Masonry Walls,Utilizing Methods Other than Energy Balance Technique ML20133E1101985-07-18018 July 1985 Corrected Suppl to Safety Evaluation Accepting Util 850612 Reevaluation of Masonry Wall Design Using Linear Elastic Methodology.Action Completed on IE Bulletin 80-11 ML20205B2591985-07-10010 July 1985 Safety Evaluation Accepting Licensee Position on Generic Ltr 83-28 Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability ML20127N2351985-05-0909 May 1985 SER Re NUREG/CR-3511, Interim Reliability Evaluation Program:Analysis of Calvert Cliffs Unit 1 Nuclear Power Plant. Use of PRA Results Out of PRA Context Clearly Inappropriate ML20132B8731984-03-21021 March 1984 SER on Multi-Plant Action C-14 Re Seismic Qualification of Auxiliary Feedwater Sys ML20148A9641978-01-0404 January 1978 Safety Evaluation Supporting Amends 27 & 12 to Licenses DPR-53 & DPR-69,respectively 1999-07-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant 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 ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. 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 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 ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With 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 ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models 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 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 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 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 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors 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 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. 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 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 ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 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 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
[Table view] |
Text
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- t. g j NUCLEAR REGULATORY COMMISSION WAsMINGToN, o.C. 30806 0001 l
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON ASME CODE CASE N-416-1 l
EQB l CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 AND 2 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NOS. 50-317 AND 50-318 I
1.0 INTRODUCTION
l l The Technical Specifications for Calvert Cliffs Nuclear Power Plant, Unit Nos.1 and 2 state that .
the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) l Code Class 1,2, and 3 components shall be performed in accordance with Section XI of the ;
ASME Boiler and Pressure Vessel Code (ASME Code) and applicable Addenda as required by l l 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(l).10 CFR 50.55a(a)(3) states that attematives to the l requirements of paragraph (g) may be used, when authorized by the NRC, if (1) the proposed altematives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the AS;'E Code,Section XI, " Rules for Inservice i Inspection of Nuclear Power Plant Components," to thw axtent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that p
inservice examnation of components and system pressure tests conducted during the first ten-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the ,
date twelve months prior to the start of the 120-month interval, sub.ilet to the limitations and }
- modifications listed therein. The applicabie edition of Section XI of the ASME Code for the ;
second ten-year inservice inspection interval for Calvert Cliffs Units 1 and 2 is the 1983 Edition, including the Summer 1983 Addenda. The components (including supports) must meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
Pursuant to 10 CFR 50.55a(g)(5)(iii), if the licensee determines that conformance with certain code requirements is impractical for its facility, the licenses shall submit information to support the determination. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(1), the l Commission may grant relief and may impose attemative requirements that are determined to be '
9004100176 980407 PDR ADOCK0500g7 Enclosure o.
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't 2-authorized by law; will not endanger life, property, or the common defense and security; and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated February 25,1998, Baltimore Gas and Electric Company (licensee) requested approval for the implementation of the altemative rules of ASME Section XI Code Case N-416-1 dated February 15,1994, titled "Altemative Pressure Test Requirement for Welded Repairs or installation of Replacement items by Wolding Class 1,2, and 3,Section XI, Division 1," pursuant
- to 10 CFR 50.55a(a)(3)(i) to be applied to the inservice inspection (181) program for Calvert Cliffs Units 1 and 2. . _ _. _ _ . _ . . .
The staff has reviewed and evaluated the licensee's reausst and suppor1ing information to use Code Case N-4161 as a proposed altomative to the Code requirements for Calvert Cliffs Units 1 and 2.
2.0 DISCUSSION CODE CASE N-416-1 ALTERNATIVE PRESSURE TEST REQUIREMENT FOR WELDED REPAIRS OR INSTALLATION OF REPLACEMENT ITEMS BY WELDING CLASS 1,2, AND 3 -
SECTION XI, DIVISION 1 -
L System / Component AaaHe=M= to Use of CM C4se:
ASME Class 1, 2, sad 3 Components with welded repairs or replacements installed by welding.
Code Reauirement Affected by Use of cme C+==:
The 1983 Edition through Summer 1983 Addenda, ASME Code,Section XI, lWA-4400(a) requires that a system hydrostatic test be performed following repairs by welding. Similarly, a system hydrostatic test is to be performed following installation of replacement items by welding, as required by IWA-4600. The system hydrostatic tests are to be conducted in accordance with IWA-5000.
Licensee's Proposed Altemative to Code Reauirement:
"The attemative to hydrostatic pressure festbg provided by ASME Code Case N-416-1, subject to the condition outlined in Reference (b), will be utilized.
American Society of Mechanical Engineers Code Case N-416-1 states that,in lieu of a hydrostatic pressure test, a system leakage test may be used provided the following requirements are met.'
m) Non-destructive examination shall be performed in accordance with the methods and
. acceptance criteria of the applicable Subsection of the 1992 edition of ASME Section Ill.
b) Prior to or immediately upon retum to service, a visual examination (VT-2) shall be I performed in conjunction with a system leakage test, using the 1992 edition of 1 Section XI, in accordance with paragraph IWA-5000, at nominal operating pressure y and temperature.' '
(
i i
t ,
l 3- i
. c) Use of this case shall be documented on an NIS-2 Form.
The condition outlined in Reference (b) is that additional surface examinations should be performed on the root (pass) layer of butt and socket welds of the pressure retaining boundary of Class 3 components when the surface examination method is used in I accordance with Sechon lii."
Reference (b) in the above licensee's statement refers to
- Draft Regulatory Guide DG-1050.
(Revision 12 to Regulatory Guide 1.147) Inservice inspection Code Case Acceptability ASME !
. Section.XI, Division 1, February 1997." _ _ . .
l 3.0 ' EVALUATION In lieu of hydrostatic pressure testing for welded repairs or installation of replacement items by ;
welding, Code Case N-416-1 allows a system leakage test using the 1992 Edition of ASME l Code,Section XI, in accordance with paragraph IWA-5000, at nominal operating presture and !
temperature. This Code Case also specifies that the non-destructive examination (NDE) of l welds be performed in accordance with the applicable Subsection of the 1992 Edition of ASME '
Code, Section lil, The latest edition of ASME Code,Section XI and Section lil, referenced in 10 CFR 50.55a, is the 1989 Edition.' The staff has compared the system pressure test requirements of the 1992 Edition of Section XI to those of the 1989 Edition and determined that the 1992 Edition of the Code imposes a more uniform set of system pressure test requirements for Code Class 1,2, and 3 systems. The terminology associated with the system pressure test requirements for all three
]
code classes have been clarified and streamlined. The test frequency and test pressure associated with these tet,ts, have not been changed. The hold time for the test has either remained unchanged or increased. The corrective action with respect to removal of bolts from a leaking bolted connection, however, has been relaxed in the 1992 Edition and has been accepted by the staff in prulous safety evaluations. The NDE requirements of post-weld repair, remain the same in both versions of the Code. Therefore, the staff finds that the requirements of the 1992 ASME Code,Section XI, as referenced in Code Case N-416-1 are similar to those of l the 1989 ASME Code,Section XI. j l
Piping components are designed for a number of loadings that would be postulated to occur l under the various modes of plant operation. Hydrostatic testing only subjects the piping j components to a small increase in pressure over the design pressure and, therefore, does not {
present a significant challenge to pressure boundary integrity. Accordingly, hydrostatic pressure l
testing is primarily regarded as a means to enhance leakage detection during the examination of ;
components under pressure, rather than solely as a measure to determine the structuralintegrity j of the components.
i The industry experience has demonstrated that leaks are not being discovered as a result of ;
hydrostatic test pressures propagating a pre-existing flaw through walls. The experience, however, indicates that leaks in most cases are being found when the system is at normal j operating pressure. This is largely due to the fact that hydrostatic pressure testing is required only upon installation and then once every 10-year inspection intorval, while system leakage tests at nominal operating pressures are conducted a minimum of once each refueling outage for ,
Class 1 systems and each 40-month inspection period for Class 2 and 3 systems, in addition, !
. leaks may be identified by plant operators during system walkdowns which may be conducted as often as once a shift. ,
l
1
, , . . . - , j
- 4 i}
1 Follomng completion of welding, the Code requires volumetric examinaten of repairs or replacements in Code Class 1 and 2, but requires only a surface examination of the final {
weld pass in Code Class 3 components. There are no other NDE requirements for Code Class 3 components except for VT-2 visual examination for leaks in corjunction with the 10 year hydrostatic tests and the periodic pressure tests. i Considering the NDE performed on Code Class 1 and 2 systems and considering that the
~ hydrostatic pressure tests rarely resuWt in pressure boundary leaks that would not occur during system leakage tests, the staff believes that increased assurance of the integrity of Class 1 and 2
' welds is not commensurate with the burden of pefformity; hydrostatic testing. Considering the . ,
nature of NDE requirements for Code Class 3 components, the staff does not believe that 1
- elimination of the hydrostatic pressure testing while only performing system pressure testing is an :
acceptable attemative to hydrostatic testing unless additional surface examinations are performed on the root pass layer of butt and socket welds on the pressure retaining boundary of
)
I Class 3 components when the surface examination method is used in accordance with Section Ill. The Licensee, however, has proposed to examine the root (pass) layer of butt and socket welds. This proposal addresses the staffs concems and is acceptable.
For clarification, it should be noted that, consistent with the Code Case requiring performance of NDE in accordance with the methods and acceptance criteria of the 1992 Edition of Section lit, the scope of examination should also be in accordance with the 1992 Edition of Section Ill. The additional surface examination of the root layer of Class 3 pressure retaining weids should be performed only when those pressure retaining welds are required to have a surface examination performed in accordance with the 1992 Edition of Section lil. For those Class 3 welds receiving radiography in lieu of a surface examination in accordance with Section Ill, no additional surface examination of the root layer needs to be performed.
4.0 CONCLUSION
The staff concludes that use of Code Case N-416-1 with additional surface examination on the l root pass of butt and socket welds of Class 3 pressure retaining boundary would provide !
equivalent protection as that provided by the applicable Code. Therefore, the licensee's l proposed attemative would provide an acceptable level of quality and safety. Accordingly, the '
licensee's proposed altemative to use Code Case N-4161 is authorized for Calvert Cliffs Units 1 and 2, pursuant to 10 CFR 50.55a(s)(3)(i) provided that the additional surface examinations are performed on the root pass layer of butt and socket wolds on the pressure retaining boundary of Class 3 components when the surface examination method is used in accordance with Section Ill. Use of Code Case N-416-1, with the additional surface examination as noted above, is authorized for the duration of the second ten-year ISI interval at Calvert Cliffs Units 1 and 2, until such time as the Code %se is approved by reference in Regulatory Guide (RG) 1.147. At that time, if the licensee intends to continue to implement this Code Case, the licensee must follow all provisions in Code Case N-4161 with limitations issued in RG 1.147, if any.
k Principal Contributor: P. Patnisk I i
Date: April 7,1998 i
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