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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20198S3031998-01-14014 January 1998 Supplemental SE Accepting RG 1.97,rev 2 Recommendations for Containment Isolation Valve Position Indication Instrumentation at NPP ML20128G2441993-02-0909 February 1993 Correction to NRC SE Associated W/Ts Amend 184,dtd 921217. SE Restates Portion of Section 2.0 ML20126F4771992-12-23023 December 1992 Safety Evaluation Granting Licensee Relief from ASME Code Requirements for Repair of RWCU Equalizing Line Until Next Refueling Outage ML20059K4331990-09-13013 September 1990 Safety Evaluation Accepting Util 881110,890328 & 900129 Submittals Re IGSCC Insp & Repair for Facility Reload 8/ Cycle 9 Refuel Outage ML20056B4011990-08-20020 August 1990 Safety Evaluation Approving Licensee Relief Request R14 & Denying Requests R15 & R5A Re Hydrostatic Test Requirements ML20058P4331990-08-13013 August 1990 Safety Evaluation Accepting ATWS Recirculation Pump Trip Sys Design Mod ML20206F5701988-11-18018 November 1988 Safety Evaluation Re Compliance w/10CFR50.62 ATWS Rule Re Alternate Rod Injection & Recirculating Pump Trip Sys ML20206D5231988-11-10010 November 1988 Safety Evaluation Supporting 880309 Request for Relief from Hydrostatic Test Requirement for HPCI & Rcic,Provided That Alternative Testing Performed ML20148B1001988-03-14014 March 1988 Safety Evaluation Accepting Util Justification for Deviations from Reg Guide 1.97 for post-accident Monitoring Variables ML20236G5801987-10-27027 October 1987 Safety Evaluation Supporting Util 850930,860827 & 1208 Submittals of Second 10-yr Inservice Insp Program Plan & Associated Relief Requests from ASME Code Insp Requirements ML20238E1461987-09-0808 September 1987 Safety Evaluation of Util 870415 Proposed Design for Standby Liquid Control Sys.Design Meets Requirements of 10CFR50.62 Re ATWS ML20237L5241987-09-0101 September 1987 Safety Evaluation Supporting Util 831109,840629 & 850702 Responses to Generic Ltr 83-28,Items 2.1 & 4.5.2 Re Equipment Classification & Vendor Interface & Reactor Trip Sys Reliability, Respectively ML20236J8151987-07-30030 July 1987 Safety Evaluation Re Insps for & Repairs of IGSCC During Reload 7/Cycle 8 Refueling Outage.Facility Can Be Safely Operated for One 18-month Fuel Cycle in Present Configuration ML20212F9421986-12-31031 December 1986 Safety Evaluation Supporting Amend to License DPR-59, Changing Tech Specs Re Second Level of Undervoltage Protection ML20214R5871986-11-24024 November 1986 Safety Evaluation Accepting Util Actions to Ensure Structural Integrity of Vacuum Breakers in Mark I Containments ML20210T3101986-10-0202 October 1986 Safety Evaluation Accepting Util 860228 Submittal of Rev 2 to Offsite Dose Calculation Manual on Interim Basis ML20205E3601986-08-0606 August 1986 Safety Evaluation on Util 830806,1109 & 840330 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1. Licensee Complied W/All Items ML20210K5571986-04-18018 April 1986 Safety Evaluation Supporting Util Request for Relief from First 10-yr Inservice Insp Requirements for Class 1,2 & 3 Components ML20137S9901985-09-26026 September 1985 Safety Evaluation Accepting MSIV Leakage Control Sys,Per GDC 54, Piping Sys Penetrating Containment ML20134D2071985-08-0909 August 1985 Safety Evaluation of Util 831109 & 840629 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review (Program Description & Procedure). Program & Procedures Acceptable ML20133F0011985-07-30030 July 1985 Safety Evaluation Accepting Util 831109 & 840629 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing ML20129E1721985-07-0101 July 1985 Safety Evaluation Re Radiological Consequences of Hypothetical LOCA While Purging Containment at Power. Radiological Consequences Acceptable ML20129E1411985-07-0101 July 1985 Safety Evaluation Supporting Demonstration of Containment Purge & Vent Valve Operability.Info Submitted Demonstrates Ability of 20-inch & 24-inch Purge & Vent Valves to Close Against Buildup of Containment Pressure During Dba/Loca ML20127E7221985-06-17017 June 1985 SER Supporting Util 840629 Response to Generic Ltr 84-09, Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii) ML20127B3251985-06-10010 June 1985 Interim Safety Evaluation Approving Util 830630 Procedures Generation Package (PGP) for Emergency Operating Procedures Upon Resolution of Exceptions Noted in Section 2.PGP Submitted Per Generic Ltr 82-33 Re Suppl 1 to NUREG-0737 ML20127C7961985-06-0606 June 1985 Safety Evaluation Re Insp & Repair of RCS Piping.Plant Can Be Safely Returned to Operation in Present Configuration for Duration of Cycle 7 ML20140G5731975-07-15015 July 1975 Safety Evaluation Supporting Tech Spec Changes to License DPR-59 to Revise Suppression Pool Water Temp Limits 1999-07-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
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'# % UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 u.../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT!]
REQUESTFORRELIEFFROMHYDROSTATICTESTREQUIREM1NT JAMESA.FITgPATRICKNUCLEARPOWERPLANT DOCKET NO. 50-333 L
1.0 INTRODUCTION
In a letter dated March 9, 1988, the Power Authority of the State of New York (the licensee) requested relief from the hydrostatic test requirements of ASME I Code Section XI for the High Pressure Coolant Injection (HPCI) and the Reactor
- Core Injection Cooling (RCIC) systems at James A. Fit 1 Patrick Nuclear Power Plant. The reouest for relief covered the first and second ten-year inservice inspection (ISI) intervals, i Pursuant to 10 CFR Part 50.55afg)(5), should the licensee detemine that certain j ASME Section XI Code examination requirements are impractical and requests relief, the licensee shall subtrit infomation to the Nuclear Regulatory
- Commission (NRC) to support that detennination. ;
! Pursuant to 10 CFR Part 50.55a(g)(6), the Connission will evaluate the determination that Code requir.;ments are impractical. The Comission ray <
grant relief and/or impose alternative requirements that are determined to be
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authorized by law, will not endanger life or property or the comon defense and security, and are otherwise in the public interest, giving due ;
consideration to the burden upon the Itcensee that could result if the ,
requirements were imposed on the facility. l In a [[letter::JPN-88-048, Forwards Request for Relief from Hydrostatic Test Requirements for HPCI & RCIC Steam Supply & Exhaust Piping in Inservice Insp Program for Welds & Supports|letter dated September 9, 1988]], the licensee revised the relief request i from the hydrostatic test requirements for the HPCI and RCIC steam supply and !
exhaust pipino to a relief request for the steam exhaust piping only. The licensee concluded that the inservice functional testing performed in August 1988 on this piping met the intent of the hydrostatic test requirements .
. of Section XI of the ASME Code. I In a letter dated September 30, 1988 additinnal details were supplied describing i the difficulty of performing the tests. ;
r 2.0 EVALUATION
?.1 SCOPE The licensee requested relief from the requirements of IWC-5000 and [
IWD-5000 of the ASME Section XI,1974 Edition through Summer 1975 Addenda, system hydrostatic tests for the HPCI and RCIC systems for r the first ten-year interval inservice inspection program. This relief l t i GG11170121 931110 i j PDR ADOCK 05000333 r F PDC
request applies to HPCI and RCIC turbine steam exhaust piping. It does not include the turbine steam inlet, pump suction, or discharge piping which will be tested in accordance with Code requirements.
The relief request also applies to the second ten-year interval ISI
-program. The ASME Code, which governs the second ten-year interval, is the 1980 Edition through Winter 1981 Addenda. The licensee is presently within the first inspection period of the second ten-interval.
2.2 TECHNICAL BASIS FOR RELIEF l
The licensee's letter dated September 30, 1988 provided the following basis for the reovest for relief.
The FitzPatrick HPCI and RCIC turbine exhaust lines were not designed for hydrostatic testing as evidenced by the design pressure of the turbine seals (30 psig), the interferences which exist with other systems, and the difficulty of installin; temporary closures (pancakes / blind flanges, etc.). These interferences were described by the licensee, along with a series of photographs which are on file.
Interferences in the HPCI system, the estimated work effort and estimated 4
exposure are:
i
- Lines 23-2"-WCP-15?-12 from the lube oil cooler and gland seal
- condenser returning to HPCI booster pump suction runs directly I over the HPCI turbine exhaust flange and would have to be
! removed for access. This line is 2" schedule 80 carbon steel l pipe with socket weld connections. Cutting and rewelding would be required. Approximately 24 man-hours and 0.288 man-rem would be required.
! - Stem seal leak-off lines from the turbine control valve to the gland seal condenser also run directly over the exhaust flange and would need to be removed for access to the exhaust l flange. Approximately 24 man-hours and 0.288 man-rem would be l
required.
l 1
- Fire protection lines run near the exhaust flange which may need to be removed for access. Approximately 24 man-hours and l 0.288 man-rem would be required.
- A unit cooler drain line (2" Sch 80) runs near the vertical run of the HPCI turbine exhaust line and would require removal by cutting and rewelding. Approximately 24 man-hours and 0.288 j man-rem would be reouired.
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- 2. .
- The following electrical conduits would need to be moved for access or to allow exhaust line movement for blank installation. ;
Approximately 24 man-hours and 0.288 man-rem would be required.
ICC591BH1 to 23LS-98 1CC59185 to 23A0V-53 1CC591BR to 23LS-100
- Four temporary pipe supports and support modifications would be required to carry the weight of the exhaust line filled with water.
Also, it would be difficult to rig the removal of the che spool piece above rupture disc 23Z-7 to allow for installation of a blind flange at this location. Approximately 120 man-hours and 1.44 man-rem would t,a required.
- The disconnection of an exhaust flange, movement of the exhaust line, installation of a blank insert and closure of an exnaust flange would be required to provide a test boundary at the exhaust flange.
Restoration to normal after the hydrotest would also be required.
Approximately 32 man-hours and 0.384 man-rem would be required.
Interferences in the RCIC system are the following:
- The RCIC tur~ine o covernor control box is directly over the turbine exhaust flange and would need to be removed for 4
temporary closure (blank) installation. Approximately 120 man-hours and 1.44 man-rem wuuld be reouired, t
- Pipe Supports PFSK-1914 and PFSK-1968 would require partial L disassembly to allow exhaust line movement for blank :
4 installation. This would require cutting / grinding welds and i rewelding to restore. Approximately 24 m n-hours and 0.288 man-ren would be required.
- Instrument lines and supports from root valves RCIC-800 and RCIC-801 to pressure switches 13PS-72A and 13PS-72R would require relocation (cut and reweld) to allow exhaust line movement. Approximately 12 man-hours and 0.144 man-rem would be required.
l - The disconnection of an exhaust flance, movement of the exhaust line, 4
installation of a blank insert and closure of an exhaust flange J would be required to provide a test boundary at the exhaust flange. ;
Restoration to normal after the hydrotest wculd also be required.
Approximately 16 man-hours and 0.192 man-rem would be required.
, The interference indicated above are shown on the file photographs. The photographs and discussion provide evidence of the impracticability of the l hydrostatic test of the HPCI and RCIC exhaust lines from the turbine exhaust !
< flange to the first isolation valve. The exhaust flanges are not designed for disconnection for routine maintenance. This is shown by the fact that the ,
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4
exhaust nozzle is on the lower turbine casing shell so that disconnection is not required for access to the rotor. The lack of accessibility discussed previously reinforces this fact. The installation of temporary closures .
would create additional local stresses which are-likely to result in local yielding at elbows and flanged connections. The possibility that other safety-related components could become damaged or improperly reinstalled is increased.
2.3 PROPOSED ALTERNATIVE EXAMINATION I
The licensee proposed that the system inservice test perfomed in August t 1988 be accepted in lieu of hydrostatic testing. This test was performed in accordance with IWA-5211 of the ASME Section XI Code. The intervice test included portions of the system (i.e., turbine and turbine xhaust to the torus) that would not be tested during a hydrostatic test examination. A VT-2 examination was conducted during the inservice test.
The licensee considers an inservice test superior to a system hydrostatic test for the following reasons:
- The inservice test included the complete ISI system boundary includir.g exempt components, the RCIC and HPCI turbines and steam exhaust piping. ,
1 - The inservice test was perfomed at the system's operating pressure i and teniperature, and, thus, is as effective as a hydrostatic test i for leakage detection during a VT-2 examination. The system l s
hydrostatic test would not effectively test the structural integrity '
- of the system as intended.
- The inservice test will avoid the anticipated radiation exposure of !
approximately 11.994 man-ren, t j
- During the installation of temporary supports and blank flanges, t there is a possibility of damage to the piping or other ad.iacent )
, components. l t
3.0
SUMMARY
4 We conclude that the ASME Section XI Code hydrostatic test requirements 4 for the steam exhaust piping are impractical to perform in the High Pressure Coolant In,iection and the Reactor Core Isolation Cooling systems i at the James A. FitzPatrick Nuclear Power Plant and would result in a !
2 burden on the licensee. In lieu of the hydrostatic test requirement, a !
system inservice test performed in accordance with Subsection lWA-5211 of l Section XI of the ASME Code, will satisfy the hydrostatic test requirement 4
i in the HPCI and RCIC systems steam exhaust piping during the first and second ten-year ISI interval. !
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4.0 CONCLUSION
The licensee has provided sufficient technical information to justify the detern.ination that the hydrostatic test requirement of Section XI of the ASME Code for the steam exhaust piping in the High Pressure Coolant Injection and the Reactor Core Isolation Cooling Systems is impractical to conduct at the James A. FitzPatrick Nuclear Power Plant. In lieu of the hydrostatic test requirement, an inservice test )erformed in accordance to Subsection IWA-5211 of Section XI of t1e ASME Code may be used to assure structural integrity of the steam exhaust piping. The Inservice Test perforr,ed in August 1988 satisfies this requirement for the first 10 year interval. An additional Inservice Test must be performed during the second ten year interval.
Pursuant to 10 CFR 50.55a(g)(6)(1), relief is granted as requested by the licensee in their letters dated March 9, 1988, September 9, 1988, and September 30, 1988, provided the alternative testing is performed. This relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden that could result if the code requiremencs were imposed.
Date:
PRINCIPAL CONTRIBUTOR:
F. Litton l
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