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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 ML20247M9231989-05-23023 May 1989 Safety Evaluation Supporting Amend 106 to License DPR-54 ML20247K6871989-05-16016 May 1989 Safety Evaluation Supporting Amend 104 to License DPR-54 ML20246F4671989-05-0404 May 1989 Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable ML20245F9041989-04-18018 April 1989 Safety Evaluation Supporting Amend 103 to License DPR-54 ML20248E9371989-03-29029 March 1989 Safety Evaluation Supporting Amend 102 to License DPR-54 ML20155D3131988-09-28028 September 1988 Safety Evaluation Supporting Amend 100 to License DPR-54 ML20151L5511988-07-14014 July 1988 Redistributed Safety Evaluation Supporting Amend 99 to License DPR-54 ML20151A2771988-07-13013 July 1988 SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr Personnel ML20195C5571988-06-0808 June 1988 SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components) ML20195C9311988-06-0808 June 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Programs (Reactor Trip Sys) ML20150F2851988-03-28028 March 1988 Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility ML20148J8611988-03-17017 March 1988 Safety Evaluation Supporting Amend 98 to License DPR-54 ML20153B2911988-03-15015 March 1988 Safety Evaluation Supporting Amend 97 to License DPR-54 ML20055E3041988-02-12012 February 1988 Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents ML20149L6961988-02-12012 February 1988 Safety Evaluation Supporting Amend 95 to License DPR-54 ML20149L2761988-02-0909 February 1988 Safety Evaluation Supporting Amend 94 to License DPR-54 ML20148C7321988-01-0505 January 1988 Safety Evaluation Supporting Amend 93 to License DPR-54 ML20237B4141987-12-0707 December 1987 Safety Evaluation Supporting Amend 92 to License DPR-54 ML20236X1771987-12-0303 December 1987 Safety Evaluation Supporting Amend 91 to License DPR-54 ML20236X1111987-11-13013 November 1987 Safety Evaluation Supporting Amend 90 to License DPR-54 ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) ML20236J2671987-11-0303 November 1987 Safety Evaluation Supporting Amend 89 to License DPR-54 ML20245C7831987-10-27027 October 1987 Safety Evaluation Supporting Amend 88 to License DPR-54 ML20245C7051987-10-27027 October 1987 Safety Evaluation Supporting Amend 87 to License DPR-54 ML20236G8791987-10-23023 October 1987 Safety Evaluation Supporting Amend 86 to License DPR-54 ML20236D1361987-10-23023 October 1987 Safety Evaluation Supporting Util 870826 Request to Use Repair & Replacement Program Contained in ASME Section XI 1983 Edition Including Addenda Through Summer 1983 ML20238D4151987-09-0303 September 1987 Evaluation of Engineering Rept ERPT-E0220 Re Reactor Regulation of Util Approach to Compliance W/Reg Guide 1.75 for New Diesel Generator Installation at Plant.Licensee Approach to Demonstrating Compliance Acceptable ML20238B1771987-08-27027 August 1987 Safety Evaluation Supporting Amend 85 to License DPR-54 ML20236E3731987-07-24024 July 1987 Safety Evaluation Supporting Existing & Proposed Mods to Meteorological Program & W/Planned Improvements,Facility Will Satisfy Min Meteorological Emergency Preparedness Requirements of 10CFR50.47 & 10CFR50,Apps E & F ML20205T3021987-03-31031 March 1987 Safety Evaluation Supporting Amend 84 to License DPR-54 ML20205R7871987-03-26026 March 1987 Safety Evaluation Concluding Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing Permits on-line Functional Testing of Sys,Including Diverse Trip Features of Reactor Trip Breakers ML20205C3951987-03-13013 March 1987 Safety Evaluation Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20206B6561987-03-13013 March 1987 Corrected SER Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20205J0971987-03-11011 March 1987 Safety Evaluation Re Sys Selected for Facility Sys Review & Test Program.Sys Constitutes Adequate Scope for Sys Review & Test Program ML20211P2601987-02-19019 February 1987 Safety Evaluation Accepting Util 860116 Request for Amend to License DPR-54,redefining Fire Area Boundaries Required to Be Operable to Separate safety-related Fire Areas & Reassessing Adequacy of Components in Fire Area Assemblies ML20210D1011987-02-0303 February 1987 Safety Evaluation Supporting Issuance of Amend 83 to License DPR-54 ML20215N6881986-11-0404 November 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 4.4 Re Improvements in Maint & Test Procedures for B&W Plants 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
- on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.2
ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20033G6011990-03-30030 March 1990 Rev 1 to Defueled Requalification Training Program for NRC Licensed Operators ML20042E6921990-03-30030 March 1990 Special Rept 90-06:on 900301,06 & 14,listed Fire Barrier Penetrations That Failed Surveillance Test Not Restored to Operable Status within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified ML20033G6031990-03-30030 March 1990 Rev 1 to Defueling Training Programs for NRC License Candidates ML20042E6931990-03-30030 March 1990 Special Rept 90-07:on 900228,high Temp Detector Circuit for Zone 53 Not Restored to Operable Status within 14 Days When Circuit Failed Surveillance Test SP.345 & Would Not Alarm. Fire Watch Established.Detector Found Operable on 900316 NL-90-054, Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station1990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station ML20006F4181990-02-0909 February 1990 Special Repts 90-1,90-2,90-3 & 90-4:on 900110,16,18,19,30 & 31,fire Barriers Breached for More than 7 Days.All Fire Barrier Penetrations & Fire Doors Returned to Operable Status NL-90-035, Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station1990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 1999-08-13
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Text
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...s SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.102 TO FACILITY OPERATING LICENSE DPR-54 l
RANCHO SECO NUCLEAR GENERATING STATION, UNIT 1
_ DOCKET NO. 50-312
1.0 INTRODUCTION
By letter dated December 30, 1988, the Sacramento Municipal Utility District (SMUD, the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. DPR-54 for Rancho Seco huclear Genera-ting Station. The amendment would permit a one-time extension of the test period for local leakage rate test (LLRT) for certain containment penetrations from March 29, 1989, or later, until the next refueling outage, which is currently scheduled to begin the fall of 1989.
In addition, the test period for the containment penetrations containing piping from the containment emergency sump to the decay heat removal suction valve would change from each refueling interval to once per 24 months.
2.0 BACKGROUND
Rancho Seco was shut down for a refueling outage in the summer of 1985.
This outage lasted much. longer than expected due to unforeseen events; restart did not begin until March 1988.
In anticipation of an earlier restart, LLRTs were successfully completed on the containment penetrations in May and June 1987.
In addition, the present operating cycle (Cycle 7) duration has been lengthened due to an extensive power escalation program and several short outages. Only three containment penetrations that are cue for testing prior to September 1989 have not had LLRTs completed during one of these outages.
3.0 EVALUATION
- a. One-Time Extension for Certain LLRTs By letter dated February 15, 1989, from D. R. Kenter, SMUD, to G. W. Knighton, 1
NRC, the licensee requested an exemption from the requirements of 10 CFR E0, Appendix J, so as to extend the two year testing interval for LLRTs
)
on certain Rancho Seco containment penetrations. This request for 1
exemption, if granted, would allow the licensee to perform the required LLRTs during the next scheduled refueling outage, which is currently scheduled to begin the fall of 1989.
In the request for amendment, dated December 30, 1988, as supplemented March 6, 1989, the licensee provided, for each containment penetration.,
information on the test results from previous LLRTs.
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- lhe staff has reviewed the information contained in the above referenced letters and has concluded that it would be acceptable to postpone, until the Fall 1989 scheduled refueling outage, the required LLRTs for contain-ment penetrations 14, 30, and 31 (TS 4.4.1.2.1(6) for penetration 14 and TS 4.5.3.2.A.3 for penetrations 30 and 31). Accordingly, an exemption from the requirements of 10 Part CFR 50, Appendix J should be granted for these penetrations until the fall of 1989.
The staff's conclusion that the LLRTs for the three containment penetrat-ions for Rancho Seco can be p::stponed until the Fall 1989 refueling outage without presenting a significant safety concern is cased on the following considerations:
1.
Since the last time these penetrations were tested, May and June 1987, the plant remained slutdown until March 1988 and.there have been several short outages since the flarch 1988 restart.
Plant components, including these penetrations, were not exposed to the normal operating temperature, pressure and radiation conditions durir.g the shutdown and the several short outages. The time interval of 24 months specified in 10 CFR Part 50, Appendix J, for LLRTs was based, in part, on the expected degradation of components exposed to the environment resulting from a full 24 months of normal plant operations. The total exposure time for the containment penetrations to the normal plant operating environment at Rancho Seco will be substantially less than 24 months, including the time period involved in the extension to the Fall 1989 refueling outage.
2.
The favorable results of previous LLRTs performed during past outages was a major factor in the staff's decision.
Each penetration. has a good history of substantially lower than normal leak rates based on the previous LLRTs. These previous test results provic'e a high degree of assurance that an extension in the 24 month test interval requirement will not result in a significant decrease in the integrity of these penetrations.
3.
The 24 month interval requirement for containment penetrations is ir, tended to be often enough to prevent significant deterioration from occurring and long enough to permit the LLRTs to be performed during plant outages.
Leak testing of the penetrations during plant shutdown is preferable because of the lower radiation exposures to plant personnel. Moreover, some penetrations, because of their intended functions, cannot be tested during power operation.
Testing of certain other penetrations during plant operation would cause a degradation in the plant's overall safety (e.g., the closing of a redundant line in a safety system),
in these situutions, the increase in confidence of containment integrity following a successful test is not significant enough to justify a plant shutdown specifically to perform the LLRTs within the 24 month time period, es long as the penetrations are in compliance wi?.h items 1 and 2 above.
i
+
t.
LLfC Interval for Decay Heat Removal Suction Piping Currently TS 4.5.3.2. A part 2 requires the piping from the containment emergency sump to the decay heat removal pump suction isolation valve to be tested as a LLRT under TS 4.4.1.2 during each refueling interval.
Refueling interval is defined in TS 1.9 as no more than 18 months with an option to extend the interval by a maximum of another 25 percent resulting in a maximum interval of 22.5 months.
TS.4.4.1.2, LLRTs, have an interval of not more than 24 months, with no option for extension.
Section III.D.3 of Appendix J to 10 CFR Part 50 states that the maximum interval between tests shall be no more than two years. The licensee proposes to change the TS interval for TS 4.5.3.2.A part 2 to no nore than 24 months, with no option to extend it an additional amount.
This proposal is consistent with the requirement of.10 Part CFR 50, Appendix J, and therefore the staff finds it to be acceptatle.
4.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Chief of the Radiological Health Branch, State Department of Health Services, State of California, of the proposed determination of no significant hazards consideration. No comments were received.
5.0 ElP.'IFO WENTAL CONSIDERATION This amendment involves changes in the installation or use of a facility conponer.t located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational. radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria foi categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pur.suant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
We have concluded, based on the considerations discussed above, that (1) will not be endangered by operation in the proposed manner, (2) public there is reasonable assurance that the health and safety of the such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to common defense and security or to the health and safety of the public.
Frincipal Contributor:
- 5. Reynolds Dated: 11 arch 29,1989
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