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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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Text
..__ _ _.._ . _ _...- _._ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ . _ _ _ _ _ _ ___ _
gemastg g* t UNITED STATES g j NUCLEAR REGULATORY COMMISSION
' g WASHINGTON, D.C. 3046H001
% * * * * * /g SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO WELDING SA-351. GRADE CD4MCu MATERIAL
, PUBLIC SERVICE ELECTRIC AND GAS COMPANY 4
! ATLANTIC CITY ELECTRIC COMPANY i
HOPE CREEK GENERATING STATION i
DOCKET NO. 50-15.i
1.0 INTRODUCTION
The Technical Specifications (TSs) for the Hope Creek Generating Station
. (HCGS) state 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 Yessel Code (ASME Code) and applicable addenda as required by Title 10 of the Code of 1 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)(1).
The requirements of 10 CFR 50.55a(a)(3) state that alternatives to the may be used, when authorized by the NRC, if requirements of paragraph the proposed alternatives wou (g)ld )rovide an acceptable level of quality and(i) safety or (ii) compliance with t ie s)ecified requirements would result in hardship or unusual difficulties wit 1out 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 preservice examination requirements, set forth in the ASME i 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 Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications a listed therein. The appitcable edition of Section XI of the ASME Code during the first 10-year laservice ins)ection (ISI) interval for the Hope Creek Generating Station (HCGS), is tie 1983 Editinn including the Summer 1983 Addenda. By letter dated March 17, 1995, the NRC authorized the use of ASME Code Case N-498-1, ' Alternative Rules for 10-year Systym Hydrostatic Testing for Class 1, 2 and 3 Systems," for HCGS.
I Nk p
00$ NOONS 4 PDR
with an examination requireme(nt of Section XI of the ASME Code is notPursuant to 10 CF 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, pursuant to 10 CFR 50.55a alternative re(g)(6)(1), the Commission may grant relief and may impose endanger life,quirements thatcommon property, or the are determined to be defense and authorized security, by othenvise and are law, will not in the public intetest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
In a letter dated July 15, 1997, Public Service Electric and Gas Company (PSE&G), the licensee, submitted to the NRC its request for relief from the requirement of ASME Code Case N-498-1, " Alternative Rules for 10-Year System Hydrostatic Testing for Class 1.-2 and 3 Systems," of a 4-hour hold time at nominal operating pressure to a reduced hold time during system pressure testing of an insulated system at HCGS. The NRC staff has revis ad and evaluated the licensee's request for relief from the requirement of the Code Case based on the supporting information provided for HCGS.
2.0 DISCUSS 10N Component Description Insulated portions of High Pressure Coolant Injection piping, HPCI turbine steam supply and exhaust lines, dan(HPCI) associated pump discharge drains and vents.
ASME Code Class ASME Section XI Class 2 and Class 3 components Examination Requirement of Code Case N-498-1 (Asstated)
ASME Section XI Code Case N-498-1 was approved for use at Hope Creek Generating Station by NRC letter dated March 17, 1995. Code Case N-498-1 allows a system pressure test to be performed at nominal operating pressure on Class 2 and Class 3 components as an alternative to the ten year system hydrostatic test required by ASME Code,Section XI, Table IWC-2500-1 Category C-H (for Class 2), and Table IWD-2500-1, Categories D-A, 0-B, and D-C (for Class 3). However, the system pressure test alternative provided by the Code Case requires a four hour hold time at nominal operating pressure before performing the required visual examination for components which are insulated. Since the components identified above are insulated, a four hour hold time would be required for this test. Therefore, a reduction in the four hour hold time is the requirement from which relief is being requested.
Licensee's Basis for Relief (Asstated) r'ursuant to 10 CFR 50.55a(a)(3)(ii), F.iE&G is requesting this relief on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
As part of the Emergency Core Cooling System (ECCS), the HPCI system is not required to operate during normal plant operation. However, the system is periodically tested in accordance with applicable requirements.
These periodic tests are conducted to verify the operability of the applicable components. The functional test of the HPCI pump and turbine normally includes about thirty (30) minutes of pues run time. In order to satisfy the hold time requirement of Code Case 1-498-1, the test would require a HPCI pump run in excess of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (hold time plus examination time). Running the HPCI pump for this duration is not practical and represents an undue hardship on the facility without a compensating increase in the level of quality and safety.
Operating the HPCI pump for the period of time required to satisfy the four hour hold time would subject the facility to unnecessarily excessive j heat loads. Control of these heat loads would require the operation of additional ECCS subsystems to remove heat from the suppression pool.
Extended operation of the HPCI pump would also challenge the Technical Specification limitation on maximum suppression pool water temperature.
Hope Creek Technical Specifications require the suppression pool average water temperature to be maintained less than 105'F during testing which adds heat to the suppression chamber. Operating the HPCI pump for a period substantially longer than the system functional test could cause this temperature to be exceeded. If the suppression pool average water temperature exceeds 110'F, Technical Specifications require the reactor mode switch to be placed in the Shutdown position.
During normal plant operation, with the HPCI system in the standby condition, the HPCI pump discharge line is maintained continuously above atmospheric pressure by operation of the HPCI jockey pump. While this pressure is less than the nominal operating pressure required by Code Case N-498-1, it does provide assurance that any leakage at this lower pressure, if it is occurring, will migrate through insulation.
Removal of the insulation from the subject components in order to use the ten minutes hold time allowsI by Code Case N-498-1 would be equally burdensome. The costs associated with insulation removal and reinstallation, including resource diversion, radiation exposura and additional radwaste, are not justified by a compensating increase in the level of quality and safety.
0 Performing an HPCI system hydrostatic test would also be burdensome. A hydrostatic test would require installation of blank flanges and temporary pipe supports, and gagging or removal of relief valves. The time, costs and radiation exposure 'ncurred in carrying out a hydrostatic test would result in a hardship without a compensating increase in the level of quality and safety.
Licensee's proposed Alternate Examination (As stated)
The system pressure test described in Code Case N-498-1 will be conducted as required, except that a twenty minute hold time will be used in lieu of the four hour hold time requirement. The twenty minute hold period will allow time for potential leaks to migrate through the insulatten I without e,hallenging the lechnical Specification limitation on maximum l suppression pool water temperature.
l 3.0 EVALUATION The applicable ASME Code,Section XI, requires a 10-year system hydrostatic test for Class 2 and Class 3 pressure-retaining components. However, Code Case N-498-1 allows a system leakage test at nominal operating pressure in lieu of the Code-required hydrostatic test provided that the applicable hold time requirements are met (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated systems and 10 minutes for uninsulated systems). The intent of the hold time requirement is to allow leakage to penetrate the insulation prior to the visual intpection. The HPCI system at HCGS is an insulated system and, therefore, the 4-hour hold time requirement applies. The licensee, however, contends that it is an undue hardship on the facility without a compensating increase in the level of quality and safety, to maintain a 4-hour hold time during pressure testing of the HPCI system due to excessive increase in heat load to the suppression pool from the exhaust steam of the HPCI turbine pump. The increase in heat load would challenge the TS limit on the suppression pool average water temperature of 105 'F. Hence, if the requirement of Code Case N-498-1 with regard to the 4-hour hold time is imposed, the increase in heat load to the suppression pool must be controlled by operating additional ECCS subsystems to remove heat from the suppression pool. Alternatively, removal of insulation for the sole purpose of performing the 10-year hydrostatic pressure test per Code Case N-498-1) with a 10-minute hold time, would resu(or leakage test lt in excessive radiation exposure to plant personnel, which would cause hardship without a compensating increase in safety.
f- The staff has determined that the proposed alternative examination by the licensee to maintain a 20-minute hold time at nominal operating pressure prior to performing the VT-2 visual examination, operational readiness due to the following:provides reasonable assurance of
The HPCI pump discharge line is continuously maintained above atmospheric prsssure by operation of the HPCI jockey pump, which would cause any l
leakage to eventually migrate through the insulation and be capable of detection.
The HPCI turbine supply piping from the steam admission valve at the inlet to the test. turbine Hence, any is pressurized steam with leakage from thesteam to the reactor pressure during the through insulatirn and will be detected. piping will eventually migrate The turbine exhaust piping is open to the suppression pool during operation.
In accordance with demonstration of an open flow path is requi.id to satisfy the hydrostatic test requirements.
hold time. This can be verified within the 20-minute
4.0 CONCLUSION
i Based on the information provided in the licensee's relief request No. RR-C2 for HCGS, the NRC staff concludes that it is a hardship without a compensatin increase in safety during pressure testing of the insulated HPCI system by I complying with either the Code-required 4-hour hold time that results in l adding excessive heat to the suppression pool or removal of insulation from
) the components to utilize the 10-minute hold time requirement, which is associated with a high radiation penalty.
Nevertheless the licensee's pressure prior to VT-2 visual examinationproposed alternative to maintain a 20 operational readiness of the subject compo,nents.prcvides a reasonable assurance of Therefore request for relief is authorized-for the HPCI system only, p,ursuant tothe licsnsee's
, 10CFR50.55a(a)(3)(ii).
Principal Contributor: P. Patnaik Date: september 25, 1997 I -