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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
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION-BALTIMORE GA5 & ELECTRIC COMPANY CALVERT CLIFF 5 NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET N05. 50-317 AND 318 RELIEF FROM INSERVICE INSPECTION REOUIREMENTS OF SECTION XI 0F THE ASME CODE
1.0 INTRODUCTION
i The Technical Specifications for the Calvert Cliffs Units 1 and 2 require that inservice examination of ASME Code Class 1, 2 and 3 components shall
. be performed in accordance with Section XI of the ASME Code as required by 10 CFR 50.55afg)(4) except where specific written relief has been granted by the Commission. Some plants were designed in conformance to early editions of this Code Section, consequently certain requirements of later editions and addenda of Section XI are impractical to perform because of the plant's design, component geometry, and material of construction. Paragraph 10 CFR 50.55a(g)(6)(1) authorizes the Commission to grant relief from those requirements upon making the necessary findings.
In a letter dated October 2,1986, as supplemented December 4,1986, the Baltimore Gas & Electric Company (BG&E), the licensee, identified specific ASME Code reauirements that BG&E determihad to be imoractical to perform at Calvert Cliffs and requested relief from these requirements.
The staff has evaluated the licensee's supporting technical justification and finds it to be acceptable.
2.0 EVALUATION OF RELIEF RE0 VESTS The licensee requested relief from specific inservice inspection (ISI) requirements and provided supporting technical information. The staff reviewed this information as related to the existing design, geometry and materials of construction of the components.
A.
Relief Request No. 1, Examination Categories B-G-1, B-G-2 and C-D, ASME Code Class 1 and 2 Bolting.
Code Requirements: ASME Section XI, 1974 Edition including Addenda through Sumer 1975, requires the following:
- 1. Class 1 Bolting (a) B-G-1 Volumetric examination is required on pressure-retaining bolting that is 2 inches and larger in diameter.
(b) B-G-2 Visual examination is rwuired for pressure-retaining bolting that is smaller than 2 inches in diameter.
I 11 Dohk &S50317 PDR
- 2. Class 2 Bolting: .
C-D Visual and either surface or volumetric examina-tions are required for pressure-retaining bolting exceeding 1 inch in diameter.
Code Relief Request: The licensee proposed to meet the require-ments of the 1977 Edition of Section XI and later editions and addenda of ASME Section XI, in which Examination Categories B-G-1, B-G-2 and C-D are redefined. Category B-G-1 is redefined as pressure-retaining Class 1 bolting, larger than 2 inches in diameter. Category B-G-2 is redefined as pressure-retaining Class 1 bolting, 2 inches and smaller in diameter. Bolting that is exactly 2 inches in diameter is shifted from Category B-G-1 to B-G-2. Similarly, Category C-D is redefined as pressure-retaining Class 2 bolting exceeding 2 inches in diameter. The licensee proposed to adopt the definitions set forth in the later editions and addenda of Section XI Code to define the boundaries for Categories B-G-1, B-G-2 and C-D.
Basis for Relief Later editions and addenda of the Section XI Code are approved for use, as per paragraph (g) of 10 CFR 50.55a of the Code of Federal Regulations. Paragraph g(4)(iv) allows the adoption of portions of later approved editions and addenda to the Code provided that all related requirements of the respective editions and addenda are met. The licensee feels that the above stated adoptions are in compliance with the stated regulations.
Staff Evaluation Paragraph 10 CFR 50.55a(g)(4)(iv) states: " Inservice examinations of components, tests of pumps and valves, and system pressure tests, may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in paragraph (b) of this section and subject to Comission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met."
The licensee intends to use provisions from the 1977 and later approved Section XI ASME Code editions and addenda. Even though the extent and method of examinations have been reduced, other licensees with ISI programs based on the later ASME Code documents are following these requirements pursuant to 10 CFR 50.55a(g)(41 The staff has determined that the licensee's proposal confonns to the requirements of the regulation that "all related requirements
of the respective editions or addenda are met." Therefore, the staff concludes that the licensee's proposal is acceptable.
B. Relief Request No. 2, Examination Category B-0, Peripheral Control Rod Drive Housings Code Requirements: Article IWB-2600 of ASME Section XI, 1974 Edition including Addenda through Summer 1975 requires a volumetric examination to include 100% of the welds in 10% of the peripheral control rod drive (CRD) housings during each inspection interval.
Code Relief Request: In the October 2, 1986 submittal, the licensee proposed to meet the requirements of Article IWB-2600 of the 1977 Edition of Section XI and later editions and addenda of the Section XI Code, which require surface or volumetric examination of 100% of the welds in 10% of the peripheral CRD housings. The licensee proposed to perfonn surface examinations, as per later editions of the code, rather than volumetric examinations.
On December 4,1986, the licensee modified this relief request after detennining that these requirements were impractical due to difficulties experienced in the perfonnance of the surface examinations on the Unit I peripheral CRD housings, lhere are 28 peripheral CRD housings in the installed configuration.
After removal of the reactor vessel (RV) head shroud and insulation, the licensee attempted to inspect 100% of the welds on three peripheral CRD housings and detennined that only part of the CRD housing welds could be examined as the welds extend into the RV head itself.
An alternative CR0 housing surface examination was conducted by inspecting 75% of the welds on three CR0 housings and 50% of the welds on two CRD housings.
Basis for Relief (1) Later editions and addenda of the Section XI Code are approved for use, as per paragraph (g) of 10 CFR 50.55a of the Code of Federal Regulations. Paragraph g(4)(iv) allows the adoption of portions of later approved editions and addenda to the code provided that all related requirements of the respective editions and addenda are met. The licensee feels that the above stated adoptions are in compliance with the stated regulations.
(2) Volumetric examination of these welds is inpractical due to design configuration, accessibility and materials of construction as described in CE Drawing No. 233-412, Weld Details, which'has been provided to the staff.
(a) Ultrasonic examination will not provide meaningful results due to the geometeric configuration of the joint and mater-ial properties (inconel-to-stainless steel welds).
(b) Radiographic examination cannot be performed due to the design configuration and accessibility.
(3) Proposed alternatives to the requirements of Section XI of the ASME Code which are determined to be impractical, may be permitted by 10 CFR 50.55a(g)(6)(1) if the proposed alternatives are detemined to be authorized by law and will not endanger life or property or the comon defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Staff Evaluation The licensee's letter of October 2,1986 proposes to use provisions from the 1977 and later approved Section XI ASME Code editions and addenda. The staff has determined that this pro with the requirements of 10 CFR 50.55a(g)(4)(iv)posal does conform that " portions of editions or addenda may be used provided that all related requirements of the editions or addenda are met."
In addition, the staff has determined that the requirement to examine 100% of the welds on three peripheral CRD housings is impractical due to the physical constraints of the installed configuration of the housings and the reactor vessel head. The alternative examination method as proposed in the licensee's De,cember 4,1986 submittal has been detemined to oe acceptable pursuant to 10 CFR 50.55a(g)(6)(i) and contingent upon the licensee's performance of 100% weld examinations on the peripheral CRD housings in the event this examination is feasible (e.g., if the CRD housing is physically removed from the reactor vessel head). This contingency i shall be applicable to all future 10-year inservice inspection intervals for each unit.
3.0 CONCLUSION
The staff has completed the review of the licensee's letters dated October 2, 1986 and December 4,1986 based on the provisions of 10 CFR 50.55afgM6)(i).
The staff concludes that the licensee's proposal to update to the 1977 l Section XI requirements of the ASME Code for Class 1 and 2 boltina and CRD housings meets the provisions of 10 CFR 50.55a(g)(4)(iv), is acceptable, l
l and therefore, the licensee shall be granted relief to update to the requirements of the 1977 and later editions and addenda of Section XI of the ASME Code for the Class 1 and 2 bolting and the CRD housing
examinations. In addition, the staff has detemined that the'1977 ASME Code (and 1974 ASME Code, too) requirement to examine 100% of the welds on three peripheral CRD housings is impractical and that this relief shall be granted contingent upon the perfomance of these 100% CRD housing weld inspections when physically possible. This granting of relief is authorized by law and will not endanger life or property or the connon defense and security and is otherwise in the public interest, considering the burden that could result if these ASME Code Section XI requirements for the CRD housing examinations were imposed on the facility. Therefore, in accordance with 10 CFR 50.55a(g)(6)(1), this relief is granted.
Date: May 11, 1987 Principal Contributors:
M. Hum, S. McNeil l
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