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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] |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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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.
Dohk &S50317 I
11 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
and therefore, the licensee shall be granted relief to update to the l
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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