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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20198H8121997-12-18018 December 1997 Corrected Safety Evaluation Supporting Amend 63 to License NPF-57,correcting Error Re Description of Min Core Thermal Power & Flow Conditions to Avoid Thermal Stratification ML20199C1441997-11-0606 November 1997 Safety Evaluation Supporting Amend 108 to License NPF-57 ML20198P3861997-10-31031 October 1997 Safety Evaluation Authorizing Licensee & Suppls & 1001,requesting Alternative to Perform RPV Circumferential Sheld Weld Exam Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1993 Edition ML20199B2021997-10-31031 October 1997 Safety Evaluation Concluding That Insufficient Info Was Available for Staff to Perform Any Detailed Evaluation of Adequacy of Licensee New Strainer Design ML20212C4481997-10-17017 October 1997 SER Accepting Alternative to ASME Section XI Code Requirements to Use Code N-432 & N-504-1 for Weld Overlay Repair for Hope Creek Generating Station ML20217D8341997-09-25025 September 1997 Safety Evaluation Authorizing Licensee Request for Relief RR-C2 for Plant,First 10-yr Interval Insp Program Plan ML20198F9981997-08-0404 August 1997 Safety Evaluation Accepting Proposed Changes to Rev 8 of HCGS Qap,Submitted on 970516 & 970606 by PSEG ML20133N6491996-12-24024 December 1996 Safety Evaluation Denying Amend Request Re Plant Svc Water Sys & Ultimate Heat Sink ML20134L7181996-11-12012 November 1996 Safety Evaluation Accepting Relief Request V-20 ML20128G2761996-09-26026 September 1996 SER Accepting Continuation of 18-month Test Schedule for Drywell to Suppression Chamber Vacuum Breakers ML20058G5171993-11-29029 November 1993 Safety Evaluation Supporting Amend 60 to License NPF-57 ML20058N8311990-08-13013 August 1990 Safety Evaluation Granting Relief Until Next Scheduled Outage Exceeding 30 Days & No Later than Next Scheduled Refueling Outage ML20055D3361990-06-27027 June 1990 Safety Evaluation Re Util 881128,900308 & 0417 Responses to Generic Ltr 88-11.Proposed Pressure/Temp Limits for RCS for Heatup,Cooldown,Leak Test & Criticality Acceptable & May Be Incorporated Into Plant Tech Specs,Per Reg Guide 1.99 ML20195H6751988-11-22022 November 1988 Safety Evaluation Re Part 2 of Item 2.1 to Generic Ltr 83-28, Vendor Interface Programs - Reactor Trip Sys Components ML20151E2751988-04-11011 April 1988 SER Supporting Util Responses to Part 1,Item 2.1 of Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events ML20148P6341988-01-19019 January 1988 Safety Evaluation Supporting Amend 14 to License NPF-57 ML20237B4611987-12-11011 December 1987 Safety Evaluation Granting Relief from Exams & Testing Requirements & Alternate Methods from First 10-yr Interval Inservice Insp Program ML20236V8151987-12-0101 December 1987 Safety Evaluation Supporting Program Existing for Identifying,Classifying & Treating Components Required for Performance of Reactor Trip Function as Safety Related. B&W Owners Group 870403 Internal Memo Also Encl ML20236U6151987-11-24024 November 1987 Safety Evaluation Supporting Amend 12 to License NPF-57 ML20236A8891987-10-14014 October 1987 Safety Evaluation Supporting Description of How Plant Alternate Rod Injection Sys,Atws Reactor Coolant Recirculation Pump Trip & Standby Liquid Control Sys Meet Requirements of ATWS Rule 10CFR50.62 ML20206G7201987-04-0909 April 1987 Safety Evaluation Supporting Util 861125 Rev 1 to Process Control Program ML20206G4001987-04-0707 April 1987 Safety Evaluation Supporting Amend 3 to License NPF-57 ML20206R0691986-06-25025 June 1986 Safety Evaluation Supporting Util 841217 Response to Generic Ltr 83-28,Items 3.1.1,3.2.1,3.2.2 & 4.5.1 Re Required Actions Based on Generic Implications of Salem ATWS Events ML20203N2221986-06-12012 June 1986 Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20154S2081986-03-27027 March 1986 SER Supporting Util 860127 Request to Use Later ASME Code Editions for Design & Fabrication of Components & Supports. Proposed FSAR Changes in ASME Code Section III Requirements Acceptable ML20137R9191986-02-0404 February 1986 Safety Evaluation Accepting Applicant 850821,1004 & 17,1106 & 1209 Proposed Mods to Tests 24,28E,25,28D,3,11,16,1 & 32 of Power Ascension Test Program ML20151Z1081986-02-0303 February 1986 SER Supporting Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability) ML20151R2511986-01-22022 January 1986 Sser Supporting Power Ascension Test Program Acceleration. SALP Input Encl ML20137L7401986-01-22022 January 1986 SER Supporting Util 840330 Response to Generic Ltr 83-28, Items 1.1,3.1.3 & 3.2.3 Re post-trip Review (Program Description Procedure) & post-maint Testing ML20137M4001986-01-22022 January 1986 Safety Evaluation Accepting Power Ascension Program Proposed Test Mods ML20138M2421985-12-16016 December 1985 Sser Re Power Ascension Test Program Acceleration.Change Acceptable Except for Elimination of Testing at Test Condition 4.Justification for Deleting Testing at Test Condition 4 Insufficient ML20132A4481985-09-30030 September 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks 1999-09-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
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y*. 4 UNITED STATES i
, j .. j NUCLEAR REGULATORY COMMISSION WAf s..NGTON, D.C. 20555-0001 ll;rt
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RELATED TO ASME CODE CASE N 567 FOR PUBLIC SERVICE ELECTRIC & GAS COMPANY HOPE CREEK GENERATING STATION l l
DOCKET NO. 50-354 I l
1.0 INTRODUCTION
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Hope Creek Generating Station (HCGS) Technicsi Specification 4.0.5 states that the inservice inspection of the American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by Title 10 of the Code of Federal '
Reaulations (10 CFR) Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Section 10 CFR 50.55a(a)(3) states l that h%ernatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed attematives 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 Ed access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, " Rules for Inservice inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of the ASME Code,Section XI, incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code,Section XI, for Hope Creek, during the second 10-year inservice inspection (ISI) intervalis the 1989 Edition. The components (including supports) may 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.
9904070308 DR 990319 p ADOCK 05000354 PDR Enclosure
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Pursuant to 10 CFR .50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, i pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose l alternative requirements that are determined to be 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.
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By letter dated March 5,1999, Public Service Electric and Gas Company (PSE&G or the licensee), requested approval for implementing the alternative rules of the ASME,Section XI, 1 Code Case N-567, " Alternative Requirements for Class 1,2, and 3 Replacement Components, i Section XI, Division 1," for a specific situation at Hope Creek. The approval of Code Case !
N-567 was requested for replacing a valve in the containment atmosphere control system with i an identical valve that was constructed to an earlier version of the ASME Code than that of the valve being replaced. The staff has evaluated the provisions of Code Case N-567 as applicable to the replacement valve to ensure that the use of the code case would provide equivalent protection as that of the code to the health and safety of the public and, therefore, the licensee's proposed alternative would provide an acceptable level of quality and safety.
2.0 DISCUSSION
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Component to be Replaced One inch diameter,600# Edward Model 838 YT piston check valve constructed to the ASME Code, Section Ill,1974 Edition including the Summer 1975 Addendum. l l
Replacement Component !
Identical valve constructed to the ASME Code,1971 Edition including the Summer 1972 ]
Addendum.
Applicable Code Reauirement I l The ASME Code,Section XI,1989 Edition, Subsection IWA-7210 " Code Applicability" for j Replacement, states *(b) Any items to be used for replacement shall meet following l requirements unless the alternative of (c) below is adopted:
(1) the applicable Construction Code to which the original item was constructed; and i (2) the existing design requirements.
If the original item was constructed without Code requirements, the item to be used for .'
replacement shall be in accordance with the design, fabrication, and examination requirements for the originalitem unless the alternatives of (c) below is adopted.
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l (c) Alternatively, an item to be.used for replacement may meet all or portions of the requirements of later editions of the Construction Code or Section ill when the Construction Code was not Section Ill, provided that the following requirements are met.
The requirements affecting the design, fabrication, and examination of the item to be used for replacement are reconciled with the Owner's specification through the Stress Analysis Report, Design Report, or other suitable method that demonstrates the item is satisfactory for the specified design and operating conditions.
(2) Mechanical interfaces, fits, and tolerances that provide satisfactory performance are compatible with system and component requirements.
(3) Materials are compatible with installation and system requirements."
Code Case N-567. Alternative Reauirements for Class 1. 2. and 3 Reolacement ComponentsSection XI. Division 1 As an alternative to the requirements of IWA-7210 stated above, the Code Case N-567 imposes the following requirements to accept a component constructed to an earlier Edition or Addenda than that of the component being replaced.
(a) Any deviation from the Owner's requirements or the original Construction Code of the component being replaced shall be reconciled; (b) A report of the reconciliation shall be prepared and made part of the record in accordance with IWA-6340; and (c) Use of this code case shall be shown on the NIS-2 Form documenting installation of the component.
Licensee's Basis for Relief During the current HCGS refueling outage, the original piston check valve 1GSV-138 failed to meet the requirements of the localleak rate test and needs to be replaced. An identical replacement valve is available which was constructed to an earlier version of the ASME Code than that of the existing valve. Approval of Code Case N-567 is requested to allow use of the replacement valve, pursuant to 10 CFR 50.55a(a)(3).
3.0 EVALUATION The Owner's design specification specifies a particular construction code with edition and addenda for a component which provides the rules for design, fabrication and testing of a code component along with any additional requirements to meet its intended service during its design I life. The objective of the rules is to afford reasonably certain protection of life and property and to provide a margin for deterioration in service so as to give a reasonably long safe period of '
usefulness. However, Code Case N-567 allows use of a component constructed to an earlier edition of the code or addenda with the stipulation that any deviation from the Owner's l
requ rements or the original Construction Code of the component being replaced,is reconciled.
The code case further requires preparation of the report of reconciliation and retaining it with the Ir service Inspection Report as stated in Subsection IWA-6340 and also identifying use of the code case in the NIS-2 Fcrm. The requirement of the code case, therefore, is equivalent to having a component built to the original construction code and maintaining the records of replacement in the plant history file for the remaining life of the plant. For the specific case of the replacement valve 1GSV-138 (one inch /600# Edward Model 838YT piston check valve), the licensee intends using an identical valve constructed to 1971 ASME Code, Section Ill, with summer 1972 Addenda in place of the existing valve built to 1974 ASME Code, Section til, with summer 1975 Addenda. Both valves being identical but built to different versions of the Code, the staff made a comparison of the material, non-destructive examination and hydrostatic shell test pressure requirements of the applicable code for each valve. The staff determined that the requirements of the construction code of the replacement valve is in no way less restrictive than that of the existing valve in each of the above categories. In regard to the installation of the replacement valve, the staff, further, obtained clarification from the licensee that any and all j provisions of the licensee's quality assurance progrmn, the ASME Code administrative i requirements, ar.d other applicable regulatory requirements would necessarily be met. The )
staff, therefore, has determined that the use of the replacement valve built to an earlier version l of the Code than that of the existing valve is in compliance with Code Case N-567 and would !
provide an equivalent protection of health and safety of the public as that of the original I Construction Code.
4.0 CONCLUSION
The staff concludes that the licensee's proposed use of Code Case N-567 for the replacement valve would provide an acceptable level of quality and safety and is, therefore, authorized pursuant to 10 CFR 50.55a(a)(3)(i). PSE&G is authorized to use Code Case N-567 for the subject component only which will be permanently installed at HCGS and remain as a plant component for the licensed life of the plant.
Principal Contributor: P. Patnaik Date: March 19, 1999 l
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