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MONTHYEARML20205C6521987-03-19019 March 1987 Requests NRC Approval to Remove Primary Containment Head Prior to Connection of Standby Gas Treatment Sys (SGTS) to Refueling Floor.Handling of Primary Containment Head Per NUREG-0612 Will Not Damage Fuel Requiring SGTS Use.Fee Paid Project stage: Request ML20214F5871987-05-18018 May 1987 SER Granting Util 870422 Request for Approval of Plans Allowing Removal of Reactor Pressure Vessel Head Spray & Vent Piping & Detensioning Reactor Pressure Vessel Head Studs Prior to Connecting Standby Gas Treatment Sys Project stage: Other ML20214F5751987-05-18018 May 1987 Forwards SER Granting Util 870422 Request for Approval for Plans Re Refueling Outage for Removal of 6-inch Reactor Pressure Vessel Head Spray & 4-inch Reactor Vessel Vent Piping.Plan Consistent W/License Condition 2.C.14 Project stage: Approval 1987-03-19
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively ML20203B4241998-02-0404 February 1998 Safety Evaluation Accepting Alternative to ASME Code Section XI Requirements to Use Code Case N-516-1 for Underwater Welding ML20203A6521998-02-0303 February 1998 Safety Evaluation Accepting Lgs,Units 1 & 2 Main Turbine Rotor Replacement,Extension of Turbine Rotor Insp Intervals & Valve Testing Frequencies ML20217J6321997-10-0909 October 1997 Safety Evaluation Re Request for Relief Re Inservice Insp Program for Limerick Generating Station,Units 1 & 2 ML20148Q6611997-06-26026 June 1997 Safety Evaluation Accepting Proposed Alternatives Identified in Rev 6 of Plant Quality Assurance Program Re Lead Auditor Qualifications & Annual Supplier Evaluation ML20133N3781997-01-16016 January 1997 SER Approving Request for Relief Re Inservice Testing of Automatic Depressurization Sys Safety/Relief Valves at Plant ML20133N6571996-12-31031 December 1996 SER Approving Licensee Use of Portions of Latest Edition of ASME Code Incorporated by Ref in Paragraph (B) of Section 50.55a for IST Leakage Rate Testing of Containment Isolation Valves ML20132F0761996-12-0909 December 1996 Safety Evaluation Supporting Planned Channel re-use, Acceptable W/Respect to Channel Control Blade Interaction ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20057D7641993-09-27027 September 1993 SE Granting Relief to Verify RHR Recirculation Flow Check Valves Open to Pass Design Flow by Determining Flow Rate Using Pump Reference Curve Per 10CFR50.55(f)(6)(i) Based on Impracticality of Measuring Flow Rate Directly ML20056H6451993-09-0707 September 1993 Safety Evaluation Permitting Use of 1989 Edition of ASME Code Section XI,IWA-5250(a)(2) Until End of Current Fuel Cycle for Removal of Bolting from Flanged Joint ML20128N5311993-02-17017 February 1993 Safety Evaluation Granting Inservice Testing Relief Requests from 10CFR50.55,requiring IST of Certain ASME Code Class 1, 2 & 3 Pumps ML20062G4581990-11-20020 November 1990 SER Accepting Util Actions to Address Indication in Reactor Vessel Recirculation Riser nozzle-to-safe End Weld ML20058A5891990-10-22022 October 1990 Safety Evaluation Supporting Util Responses to Generic Ltr 88-10, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping ML20245E6251989-06-20020 June 1989 SER Accepting Util Response to NRC Bulletin 88-005.Util Conducted Adequate Matl Property Tests & Structural Analyses of Nonconforming Flanges & Fittings Using Acceptable & Conservative Analytical Methods & Evaluation Criteria ML20245A3581989-06-14014 June 1989 Safety Evaluation Re Increased Core Flow Analysis Partial Feedwater Heating Analysis & Extended Load Line Limit Analysis ML20247D2271989-05-0909 May 1989 Safety Evaluation Re Generic Ltr 83-28, Reactor Trip Sys Reliability on Line Testing. Ltr Acceptable ML20246J8351989-05-0909 May 1989 Safety Evaluation Re Low Pressure Turbine Maint Program. Program Acceptable ML20245K7621989-05-0202 May 1989 Safety Evaluation Accepting Ultrasonic Test Indications in N2H nozzle-to-safe End Weld During Cycle 3 ML20151T5191988-08-0303 August 1988 Safeguards Evaluation Rept Supporting Amend 9 to License NPF-39 ML20154A8931988-05-0303 May 1988 Safety Evaluation Supporting Request for Extension of Const Dates for CP CPPR-107 ML20196H9341988-03-0404 March 1988 Safety Evaluation Supporting First 10-yr Interval Insp Program ML20236J2621987-11-0303 November 1987 Safety Evaluation Accepting Util Compliance W/Atws Rule 10CFR50.62 Re Alternate Rod Injection Sys,Recirculation Pump Trip & Standby Liquid Control Sys ML20236J2121987-11-0303 November 1987 Safety Evaluation Accepting Util Turbine Sys Maint Program ML20236P8201987-08-0707 August 1987 Safety Evaluation Approving Request to Retain RHR Svc Water Process Radiation Monitors ML20214F5871987-05-18018 May 1987 SER Granting Util 870422 Request for Approval of Plans Allowing Removal of Reactor Pressure Vessel Head Spray & Vent Piping & Detensioning Reactor Pressure Vessel Head Studs Prior to Connecting Standby Gas Treatment Sys ML20213G8351987-05-12012 May 1987 SER Supporting Util 870319 Request for Approval to Remove Primary Containment Head Prior to Connection of Standby Gas Treatment Sys to Refueling Floor Area ML20215J2201987-05-0404 May 1987 Safety Evaluation Approving post-irradiation Fuel Surveillance Program ML20205L7241987-03-27027 March 1987 Safety Evaluation Supporting Util 860327,1224,870113 & 27 Proposals to Use ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Classes 1,2 & 3 Piping Sections,Section Iii,Div 1 ML20205L8741987-03-26026 March 1987 Safety Evaluation Accepting Util 831110,840508 & 0607 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20207T1721987-03-18018 March 1987 Safety Evaluation Supporting Util Proposal to Delete Cooldown Air Flow Path to Each Charcoal Adsorber in Reactor Enclosure Recirculation Sys Filter Trains ML20209J5691987-02-0404 February 1987 Safety Evaluation Supporting Util 861117 Proposed Tech Spec Changes Re Operation W/Partial Feedwater Heating & Increased Core Flow Limits NUREG-0578, Safety Evaluation Conditionally Supporting BWR Owners Group Evaluation of Radiological Consequences for Accidental Releases Through BWR 2-inch Vent & Purge Lines1986-05-20020 May 1986 Safety Evaluation Conditionally Supporting BWR Owners Group Evaluation of Radiological Consequences for Accidental Releases Through BWR 2-inch Vent & Purge Lines ML20155H0941986-04-23023 April 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20137L2021986-01-0606 January 1986 SER Supporting Util Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing (Reactor Trip Sys Components) ML20214E4211984-09-18018 September 1984 Safety Evaluation Supporting Util Responses Re Containment Pressure Boundary Matls Cited by GDC 51 ML20235C0101971-11-29029 November 1971 Safety Evaluation of Util Application for CP & OL for Dual Unit Nuclear Power Plant Facility 1999-09-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154H5691998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With ML20151X3511998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With ML20237F0291998-08-27027 August 1998 Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present ML20237D1041998-08-17017 August 1998 Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20237B4711998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2 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 ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20236P9781998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2 ML20196K1801998-06-30030 June 1998 Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with ML20249B3501998-06-11011 June 1998 Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5 ML20249A5331998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Limerick Units 1 & 2 ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20247H5071998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Limerick Generating Station ML20216F3601998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively 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 ML20216F9471998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2 ML20216F3471998-02-28028 February 1998 Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1 1999-09-30
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, , , ENCLOSURE
,e UNITED STATES y a, NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION REPORT LIMERICK GENERATING STATION UNIT 1 REMOVAL OF REACTOR HEAD SPRAY AND VENT PIPING AND VESSEL STUD DETENSIONING DOCKET NO. 50-352 (TAC 651461
- 1. INTRODUCTION By letter dated April 22, 1987, the Philadelphia Electric Company submitted a reouest to allow removal of the RPV head spray and vent piping and detensioning the RPV head studs prior to connecting the SGTS to the refueling area.
1he licensee had previously riade comitments that neither the primary containment head nor the reactor vessel head would be removed, without prior URC approval, before the SGTS is connected to the refueling floor zone. The NRC staff incorporated a portion of this commitment dealing with the reactor vessel head into license condition 2.c(14) as discussed in Section 6.2.3 of SSER-3.
By letter dated March 19, 1987, the licensee submitted a request removal of the primary containment head prior to connecting the SGTS to the refueling area. The NRC staff reviewed this submittal and issued an evaluation dated May 8,1987 which approved this operational procedures.
- 2. EVALUATION The staff's approval of the licensee's March 19, 1987 request, was based in part on the fact that the RPV would remain' intact. However, the licensee's April 22, 1987 request would allow a 6" line and a 4" line on the RPV to be temporarily open without the connection of SGTS to the refueling area. The licensee proposed to install blank flanges or HEPA filters imediately upon breaching the flanged connections between the 6" RPV head spray and the 4" vent piping and the reactor vessel, to prevent any substantial untreated release from the RPV.
The SGTS at Limerick Unit 1 is currenti connected to the Unit i reactor enclosure secondary containment (Zone I , but not to the refueling area {
secondary containment (Zone II). The licensee, during the refueling outage, '
plans to replace the 3000 cfm fans with 8400 cfm fans and associated ductwork to allow coverage of all zones. During the outage, until the 8400 cfm fans are installed and tested, the licensee plans to align the 3000 cfm fans from Zone I to Zone III. It is after plant shutdown while in Modes 4 and 5, but ;
before this realignment is accomplished, that the licensees NRC approval to proceed without SGTS.
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8705260166 DR 870518 ADOCK 05000352 -
PDR.
.p.
The licensee has proposed this procedure because it is helievcd that the r(lief from the current operating restrictions represents cnly a minor chance. The basis of this belief is based on the following rationale.
(1) Dreaching of the flanged connections of the 6" RPV head spray and 4" "ent piping is only for e very short tire. The licensee proposes to imediately install blenk flances cr HEPA fi'ters on these cpenings.
Therefore, the potertini for an untreated radicactive re' ease would he of sufficiertly low prchability to be considered acceptable.
(2) The reactor frei will remain in core entil the SGTS is connected. Also, the RtV head is not temoved. Geroval of the 6" RPV head spray and the 4" vent piping and detensioning the RPV head studs therefore can not result in (a hoe.vy load drop to cause) fuel damage, requiring the use of the SGTS to control the release of radiation.
(3) Vorkers in the refueling area are protected by continuous air crd floor radiatier ronitoring and health physics surveys are cerducted when the piping is coroletely removed.
(4) Thf licensee and the sta" have both performed of# site radiological dose analysis. A 10% fuel gap activity release to the reactor coolant was assured according to P,egulatory Guide 1.25. The results based on an eight hour assumed unfiltered release shows that the thyroid dose was below the 10 CFR 20 limit. Additionally, the licensee's recent sartpling of the reactor coolant ir.dicates a lever coolant activity level than assumed fer this analysis.
- 3. CONCLUSION The staff has reviewed this rationale and concurs W th the 'icersee that the reevested change represents a small change in the crcrating procedures. Or the basis of the above evaluation, the sta#f concludes that renovel of the 6" RPV Frcd spray and the 4" vent piping and detensionino the PPV head studs prior to connecting SGTS to the refuelir.c area, will rot endancer the safety and herith of the workers in the crea or that of the general public. The staff approves this recuest as proposed and also reminds the licersee that, as required by the testing procedures (Refueling Area Secondary rcr.tainment Integrity Verification (ST-6-076-360-0)'l, the SGTS trust be connected to 7cre
!!I and be tcsted before the total terrevai of the RPV head.
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