Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power StationML20235V734 |
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Pilgrim |
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03/03/1989 |
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NRC |
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ML20235V732 |
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NUDOCS 8903100314 |
Download: ML20235V734 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20137D0511997-03-20020 March 1997 Safety Evaluation Approving Third 10 Yr Interval ISI Program & Requests for Relief ML20134K2621997-02-10010 February 1997 Safety Evaluation Accepting Licensee one-time Request to Defer Insp of N2A & N2B safe-end Welds,Per GL 88-01 ML20129H3901996-10-30030 October 1996 Safety Evaluation Re Facility IPE Submittal for Internal Events & Internal Flood ML20129F4031996-09-27027 September 1996 Safety Evaluation Accepting Second ten-year Interval Inservice Insp Program Plan Request for Relief ML20059C3751993-12-29029 December 1993 Safety Evaluation Granting Exemption & Approving Alternative DAC Values for Use in Place of Generic Value for Radionuclides Specified in App B to 10CFR20.1001 - 20.2402 ML20058G2781993-11-29029 November 1993 Safety Evaluation Granting IST Program Relief Per 10CFR50.55a(f)(6)(i) & Approving Alternatives Per 10CFR50.55a(f)(4)(iv) ML20056F5301993-08-11011 August 1993 Safety Evaluation Re Licensee Response to Reg Guide 1.97, BWR Neutron Flux Monitoring. Criteria of NEDO-31558, Acceptable for Current BWR Operating License & Const Permit Holders ML20127P5431993-01-25025 January 1993 Safety Evaluation Supporting Amend 145 to License DPR-35 ML20126F8121992-12-23023 December 1992 Safety Evaluation Accepting Facility Design W/Respect to RG 1.97 ML20244C2901989-06-0606 June 1989 Draft Safety Evaluation of Util Compliance W/Atws Rule (10CFR50.62) Re Alternate Rod Injection & Recirculation Pump Trip Sys.Alternate Rod Injection Sys Not in Compliance W/Atws Rule Re Diversity ML20235V7341989-03-0303 March 1989 Safety Evaluation Accepting Util Revised Temp Profile,Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station ML20154P6611988-09-28028 September 1988 SER Approving Rev 3 to Plant Second 10-yr Inservice Insp Program,Per 10CFR50.55a(g)(4) ML20151D0551988-07-18018 July 1988 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20151E2041988-07-15015 July 1988 Safety Evaluation Supporting Incorporation of Reactor Protection Sys Circuitry Into Tech Specs & Deletion of 6- Month Channel Functional Test ML20154J9101988-05-17017 May 1988 Safety Evaluation Accepting Util Technical Evaluations & Acceptance Criteria Re Fire door-to-frame,frame-to-wall & Anchor Bolt Irregularities ML20155F8871988-03-24024 March 1988 Safety Evaluation Concluding That Internal Smoke Seals for Conduits Passing Through Fire Barriers from One Fire Area to Another Consistent W/Branch Technical Position 9.5-1 & Acceptable,Per Util 880203 Submittal ML20236Y3991987-11-10010 November 1987 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Equipment Classification.Salp Input Encl ML20236V3081987-10-28028 October 1987 Safety Evaluation Supporting Acceptance of Offsite Dose Calculation Manual Updated Through Rev 1 on Interim Basis. App D to Technical Evaluation Rept EGG-PHY-7725 Encl ML20235M1611987-09-30030 September 1987 Safety Evaluation Supporting Util 870708 Proposed Change to Tech Specs Concerning LPCI Subsystem Testing ML20236Y3591987-07-22022 July 1987 Safety Evaluation Accepting Licensee Request to Modify Standby Liquid Control Sys Tech Specs,Per Requirements of ATWS rule,10CFR50.62.C.4.SALP Input Also Encl ML20206G8141987-03-26026 March 1987 Safety Evaluation Re Util Requests for Relief from Inservice Insp Requirements for Surface & Volumetric Exam of RHR Sys HX Nozzles & Exam of 100% Required Vol for nozzle-to-vessel Welds.Requests Granted W/Listed Conditions ML20215H9581987-03-17017 March 1987 Safety Evaluation Supporting Tech Spec Change Re Control Room High Efficiency Air Filter Sys.Salp Input Encl ML20212L8941987-01-15015 January 1987 Safety Evaluation Supporting Vacuum Breaker Analysis Performed to Predict Impact Velocities & Resulting Stresses ML20236Y3501986-09-0303 September 1986 Safety Evaluation Accepting Licensee 850813 Response Re Generic Ltr 83-28,Item 1.1 on post-trip Review.Salp Input Encl ML20212N8401986-08-22022 August 1986 SER Supporting Util Response to Item 1.C of NRC Re No Specific Time Limit Necessary on Containment Purging & Venting During Reactor Operation ML20155F8931986-08-20020 August 1986 Safety Evaluation Accepting Util 831116 Request for Four Exemptions from 10CFR50,App R,Section Iii.G.Level of Fire Safety in Listed Fire Zones Equivalent to Safety Achieved by Compliance W/Requirements ML20206L9511986-08-12012 August 1986 Safety Evaluation on Util Response to Generic Ltr 83-28, Items 3.1.1,3.1.2,.3.2.1,3.2.2 & 4.5.1 Re Maint & Test Procedures for safety-related Equipment & on-line Functional Testing of Reactor Trip Sys.Responses Acceptable ML20205C0621986-07-31031 July 1986 Safety Evaluation Accepting Util 831107 Response to Generic Ltr 83-28,Item 2.1, Post-Trip Review. BWR Parameter List Encl ML20236Y3361986-07-10010 July 1986 Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 1.2 on post-trip Review & Data & Info Capability ML20199L2541986-07-0101 July 1986 Safety Evaluation Supporting Amend 96 to License DPR-35 ML20206D1741986-06-0606 June 1986 Safety Evaluation Supporting Util Response to IE Bulletin 80-11 Re Reevaluation & Testing Requirements in Items 2(b) & 3 Concerning Masonry Wall Design ML20203N3801986-04-30030 April 1986 Safety Evaluation Supporting Util 840625,1204,06,850521 & 1011 Responses to Generic Ltr 86-04 Concerning Recombiner Capability Requirements of 10CFR50.44(c)(3)(ii).Facility Does Not Require Recombiner Capability ML20236Y3711986-04-0101 April 1986 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components,Respectively. SALP Input Also Encl ML20137V7621986-02-12012 February 1986 SER Supporting Partial Relief from Generic Ltr 84-11 Re Performance of Visual Exam of Reactor Coolant Piping ML20135E5211985-09-11011 September 1985 Safety Evaluation Supporting post-trip Review Program & Procedures ML20134H3571985-08-13013 August 1985 Safety Evaluation Granting 821203,0804,831201,840628 & 850212 Relief Requests from ASME Code Requirements of Inservice Insp Program,Except for Items B9.10-B9.40 & C5.10-C5.32 Re Pressure Retaining Welds ML20140G1431985-07-0505 July 1985 Interim Safety Evaluation Supporting Util Response to Generic Ltr 83-36 Re NUREG-0737 Tech Specs ML20129C6901985-05-16016 May 1985 Safety Evaluation Re Dcrdr.Supplemental Rept Addressing Concerns Identified Necessary to Meet Requirements of NUREG-0737,Suppl 1 ML20206K6161985-03-13013 March 1985 SER Supporting Proposed Tech Spec Change to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Testing of Hydrogen Addition Water Chemistry.Related Documentation Encl 1999-09-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
[Table view] |
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Enclosure SAFETY EVALUATION DRYWELL TEMPERATURE ANALYSIS PILGRIM NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-?93
1.0 INTRODUCTION
By letter dated March 15, 1988, Boston Edison (the licensee) submitted a proposal to revise the drywell temperature profile used for equipment qualification purposes. Attached to their submittal was a General Electric (GE) report containing the supporting analytical justification for the temperature modification. The GE report consisted of an evaluation of a spectrum of postulated Main Steam Line Breaks (MSLB) within the drywell. The purpose of the evaluation was to develop a temperature profile which bounded the individual profiles of the series of breaks considered. The resulting composite profile, when used for equipment qualification purposes, could then be assured of.being conservative with respect to any given MSLB. The licensee provided additional information via a letter dated September 7, 1988.
A critical assumption used by the licensee in the development of the series of temperature profiles was the time when the drywell sprays would be initiated.
Based on the information available to the operators and the availability of the RHR spray pumps, the licensee concluded that 30 minutes into the event was a reasonably conservative value. As a result, all analyses assumed full sprays 30 minutes into the event.
2.0 EVALUATION
'he GE report contained a series of computer code analyses which were run to etermine the drywell airspace temperature profiles resulting from various size main steam line breaks. The resulting temperature profiles were overlayed one on top of the other and a composite profile was developed which enveloped the resulting curve. In other words, only those portions of the individual profiles were used that represented the maximum temperatures for that selected time zone.
The staff concurs with the licensee's approach used to develop the equipment qualification temperature profile. Use of the composite curves in the manner described, results in a bounding profile. In addition to the overall approach, the staff also reviewed the modeling assumptions used by GE to maximize the integrated steam release via the line break. The assumptions were found to be similar to analyses previously found to be conservative by the staff. Based on this similarity, the staff also finds the specific modeling assumptions used in the present analyses acceptable.
e903100314 890303 PDR ADOCK 0500033 P PDC
T A key factor in determining the short-tenn portion of the drywell temperature profile is the time when the drywell sprays are assumed to be actuated. This assumption is particularly important, since the sprays almost immediately remove all the superheat from tha dryw11 eirsnaca. Initially, the review focused on the procedures that directs the operator to initiate sprays. The licensee indicated that the Pilgrim emergency operating procedures require the operator to manually initiate sprays when either of two conditions exists; the drywell temperature exceeds the design value of 281 F or the wetwell pressure exceeds 11 psig. Both of these parameters are monitored in the control roora.
Based on discussions with the licensee, the instrumentation for both temperature and pressure monitors are safety grade. In light of the importance of this instrumentation, we require that the safety grade design of both the pressure and temperature instrumentation, used to determine when the sprays will be actuated, be included in the next update of the Updated Final Safety Analysis Report (FSAR).
Another important consideration which has a significant impact on the temperature profile is the actuation time of the sprays. The licensee believes that 10 minutes for operator action is appropriate, but they provided i analyses for both 10 and 30 minute actuation times. The staff has evaluated l the merits of both times and concludes that 30 minutes should be used in the development of the temperature profiles.
l The 10 minute actuation time was found to be unacceptable. First of all, the flow from one RHR pump must be diverted from its primary ECC function to initiate spray flow. Ten minutes is the absolute minimum time allowed for such diversion. Additionally, the consequences of not performing the task at this minimum time were felt to be too significant for such a small operating window. Finally, the amount of time the operator would realistically devote to equipment qualification level concerns was felt to be minimal during the first 10 minutes of the event. Based on the above rationale, the staff concluded that a 10 minute actuation time was unacceptable.
The 30 minute time, however, allows the operator about 20 minutes to monitor the containment conditions before a decision must be made relative to spray actuation. The selection of the two values which will be used to actuate the sprays are also important. The drywell temperature represents saturated conditions at design pressure. Therefore, any size steam line rupture will achieve the necessary initiation temperature, while breaks in the recirculation piping will not. However, the pressure set point of the wetwell pressure will actuate the sprays for almost all breaks.
The selection of the pressure and temperature set points, in a sense yields redundant instrumentation. For virtually all drywell breaks, the wetwell pressure will indicate the need for the sprays when all the drywell air is carried over to the wetwell. The temperature sensor, however, will only require sprays if some amount of superheat is present in the drywell. Since sprays are only required when superheat is present, this arrangement amounts to both redundancy and diversity of signal.
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1 Finally, the staff reviewed the modeling assumptions relative to the guidance provided in NUREG-0588. This NUREG provides specific guidance regarding the treatment of heat transfer to the structural heat sinks following a MSLB or LOCA for *quipment qualification purposes. Our revice indicates that the licensee conforms with this guidance and is therefore acceptable.
3.0 CONCLUSION
Based on the above, the staff concludes that the analysis presented by the licensee in the submittals dated March 15, 1988 and September 7, 1988, provides a reasonable basis for determining the drywell airspace temperature profile used for equipment qualification. This acceptance is based on the assumption that manual spray initiation occurs 30 minutes into the event.
Principal Contributors: J. Kudrick A. Notafrancisco
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Enclosure 2 SPLB SALP INPUT Plant Name: Pilgrim Nuclear Power Station SER
Subject:
Revised Drywell Temperature Profile TAC No.: 67809 Summary of Review / Inspection Activities The review was to determine whether or not the provided.drywell airspace temperature profile was acceptable for equipment qualification purposes. A major factor in the evaluation was the qualities and type of control room instrumentation which must be safety grade. It was determined that temperature instrumentation is safety grade after a series of telecons. .
Safety grade of the instrumentation should be explicitly stated in the docket.
Narrative Discussion of Licensee Performance - Functional Area The licensee has generally demonstrated understanding of the issue and provided information to resolve it.
Author: J. Kudrick Date:
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