Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: 05000206/LER-1981-013, Forwards LER 81-013/99X-0.Detailed Event Analysis Submitted, 05000206/LER-1981-013-99, /99X-0:on 810618,power Operated Relief Valve Controller Opened Twice During Normal Pressure Transient Following Reactor Trip.Caused by Setting Time Constant to Off to Satisfy NUREG-0737,Item II.K.3.9, L-81-029, Forwards Proposed Licensing Exam Schedule for 1981-82 for Reactor & Senior Operator Candidates,Per 810807 Request, L-82-002, Informs That Necessary Procedures Per NUREG-0737,Item I.A.1.3 Re Use of Overtime Required by Generic Ltr 82-12 Will Be Implemented by 821001.Tech Spec Will Not Be Submitted for Review Pending Receipt of Model Tech Specs, ML13308A671, ML13308B064, ML13308B821, ML13308B925, ML13310A775, ML13310A777, ML13310A778, ML13310A826, ML13310A828, ML13310A923, ML13310A926, ML13310B078, ML13310B081, ML13310B120, ML13310B280, ML13310B546, ML13310B619, ML13311B030, ML13316B714, ML13317A133, ML13317A134, ML13317A166, ML13317A190, ML13317A263, ML13317A267, ML13317A289, ML13317A367, ML13317A369, ML13317A377, ML13317A391, ML13317A427, ML13317A450, ML13317A454, ML13317A468, ML13317A478, ML13317A479, ML13317A484, ML13317A488, ML13317A490, ML13317A507, ML13317A512, ML13317A519, ML13317A553, ML13317A567, ML13317A581, ML13317A616... further results
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MONTHYEARML13333A4221979-10-22022 October 1979
Forwards Responses to NRC post-TMI Requirements Re Design & Analysis,Operations,Rcs High Point Vents,Emergency Preparedness & Instrumentation to Monitor Containment Conditions
Project stage: Other
ML13303A7381979-10-30030 October 1979
Summary of 790927 Meeting W/Utils in San Clemente,Ca Re Emergency Plan Review
Project stage: Request
ML13322A6191979-11-15015 November 1979
Summary of 791108 Telcon W/Util Re Unacceptable Schedule for Implementing Lessons Learned Task Force Items
Project stage: Other
ML13333A4571979-12-14014 December 1979
Forwards Revisions to Util 790913 Commitments Re Compliance w/short-term TMI Lessons Learned Task Force Requirements Per NUREG-0578
Project stage: Other
IR 05000206/19790161980-01-0404 January 1980
IE Insp Rept 50-206/79-16 on 791101-02 & 26.No Noncompliance Noted.Major Areas Inspected:Scope & Methods of Field Insp for IE Bulletin 79-14,repair of Shorted Electrical Buswork & Licensee Design Change Proposal
Project stage: Request
ML13311B0301980-01-21021 January 1980
Discusses Response to NRC 800102 Order to Show Cause Re Implementation of NUREG-0578 Category a Requirements.Will Continue Operation Until 800315.Shutdown on 800131 Would Severely Impact Power Reliability in Pacific Northwest
Project stage: Other
ML13333A4781980-01-23023 January 1980
Advises That Responses to NRC Requesting Info Re Small Break LOCA Guidelines Will Be Submitted by 800228. Bulletin Response Will Be Sent by 800228
Project stage: Other
ML13333A4811980-01-24024 January 1980
Forwards Corrected Page 3 of App 10 to Enclosure a of Re Power Reliability Info.Omitted Info Sent to R Weiner of DOE on 800118
Project stage: Other
ML13333A4831980-01-29029 January 1980
Confirms 800124 & 25 Telcons Re Facility 800126 Shutdown for Implementation of Lessons Learned Task Force Category a short-term Requirements Re Reopening of Containment Isolation Valves
Project stage: Other
ML13308B0641980-01-30030 January 1980
Concludes That Inadequate Justification Exists to Extend Util 800131 Deadline to 800315 for Response to 800102 Order to Show Cause Why All Category a Lessons Learned Requirements Should Not Be Implemented
Project stage: Other
ML19290E8091980-02-0101 February 1980
Denies Request for Shutdown Extension Until 800315 to Complete Category a Requirements W/Available Equipment. Reopening of Containment Isolation Valves Until Further Mods Completed Acceptable
Project stage: Other
ML13333A4981980-02-0808 February 1980
Submits Addl Info Re Commitment Schedule for short-term Lessons Learned Task Force Requirements.Circuitry to Close Auxiliary Feedwater Motor Operated Discharge Valve Will Be Installed During Apr 1980 Refueling Outage
Project stage: Other
ML13333A5031980-02-13013 February 1980
Forwards Justification for RCS Subcooling Setpoint,In Response to NRC 791227 Request.Addl Info Will Be Forwarded in Response to IE Bulletin 79-27 by 800228
Project stage: Other
ML13316B7141980-03-0707 March 1980
Advises NRC of Delay in Responding to Item 4 of as Part of Response to IE Bulletin 79-27.Submittal Rescheduled from 800228 to 800701
Project stage: Other
ML13330A0251980-03-25025 March 1980
Forwards Addl Info for Implementation of TMI short-term Lessons Learned Task Force Requirements.Describes Mods to Backup Nitrogen Pneumatic Supply & Valve Position Indication.Drawing Available in Central Files Only
Project stage: Other
ML13330A0271980-03-28028 March 1980
Responds to NRC 800117 Request for Review of Draft Evaluation of SEP Topic XV-20, Radiological Consequences of Fuel Damaging Accidents,(Inside & Outside Containment). Review Confirms Facts as Correct
Project stage: Request
ML13330A0321980-04-11011 April 1980
Confirms 800410 Telcons W/Regulatory Personnel Re Implementation of Several Category a TMI Lessons Learned Task Force Requirements Described in
Project stage: Other
IR 05000206/19800041980-04-11011 April 1980
IE Insp Rept 50-206/80-04 on 800128-0229.Noncompliance Noted:Failure to Rept Reactor Protection Sys Setpoints Less Conservative than Those Established by Tech Specs & Use of Nonstandard Fitting
Project stage: Request
ML13331B3711980-05-0707 May 1980
Ro:On 800506,during Refueling Operations,After Lowering of Reactor Internal Instrumentation Package,Incore Instrumentation Package for Thimble Location D-7 Found Bent Outward.Caused by No Provision for Thimble Passage to Core
Project stage: Request
ML13330A0521980-05-22022 May 1980
Discusses Open Items Re Implementation of Category a Lessons Learned Task Force Requirements Per NRC 800502 Request.Open Items Involve Instrumentation for Inadequate Core Cooling, post-accident Sampling & Reactor Cooling Sys Venting
Project stage: Other
ML13330A0621980-06-13013 June 1980
Discusses Completed Review of NRC Forwarding Five Addl Items Resulting from post-TMI Reviews.Forwards Commitments to Meet Implementation Requirements for Items 1-5
Project stage: Other
ML13319A2131980-07-0909 July 1980
Forwards Post-Accident Sampling Sys,Capabilities & Description, & Drawings,In Response to Open Item Identified in NRC Re Implementation of TMI Lessons Learned Requirements.Drawings Available in Central Files Only
Project stage: Other
IR 05000206/19800201980-07-0909 July 1980
IE Insp Rept 50-206/80-20 on 800616-19.No Noncompliance Noted.Major Areas Inspected:Major Maint,Major Surveillance, IE Bulletin & Circular Followup & Independent Insp Effort
Project stage: Request
ML13322A7711980-07-0909 July 1980
Post-Accident Sampling Sys,Capabilities & Description
Project stage: Other
ML13302A4691980-09-12012 September 1980
Forwards Amend 20 to Fsar.Amend Contains Responses to NUREG- 0660 & NUREG-0694, TMI-Related Requirements for New Ols
Project stage: Request
ML13322A9461980-09-12012 September 1980
Notifies That Actions Required in NRC Re License Amend Application Concerning Implementation of TMI Lessons Learned Requirements Cannot Be Accomplished by 800912. License Amend Application Will Be Submitted by 810116
Project stage: Other
ML13330A1321980-10-0909 October 1980
Notifies That Date for Submittal of Info Re Design Details for Reactor Coolant Vents & Addl Info for Main Steam Line Piping Integrity Evaluation Will Be Submitted 801101 & 1201,respectively
Project stage: Other
ML13330A1351980-10-15015 October 1980
Provides Plans,Schedules & Commitments to Meet Interim Criteria for Shift Staffing & Administrative Controls,In Response to NRC 800731 Request.Full Compliance W/Criteria Will Be Achieved No Later than 820701
Project stage: Other
ML13316A5161980-10-31031 October 1980
Environ Qualification of Electrical Equipment
Project stage: Request
ML13330A1581980-12-23023 December 1980
Advises That Response to NRC Requesting Confirmation for Implementation Dates of TMI-related Items Will Be Submitted by 810105
Project stage: Other
ML13308B8211980-12-30030 December 1980
Submits Addl Info Re Description of Shift Technical Advisor Training Program & Plans for Requalification Training Per 791031 Request
Project stage: Other
ML13330A1661981-01-0707 January 1981
Notifies That License Amend Application to Incorporate Applicable Tech Specs for Implementing TMI-2 Lessons Learned Category a Items Will Be Submitted by 810401
Project stage: Request
ML13308A6711981-01-13013 January 1981
Advises That Licensee Inadvertently Omitted Info from Re Plans for Implementation of Action Item II.K.3.25 in NUREG-0737 Re Effect of Loss of Ac Power on Pump Seals. Evaluation Will Be Submitted by 820101
Project stage: Other
ML13330A1911981-01-14014 January 1981
Informs That Radiochemical & Chemical Analysis Mods Promised in Util No Longer Necessary.Due to Other TMI Recommendations,Samples Can Be Analyzed Outside Lab.Cart Mounted Iodine Sampler W/Single Channel Analyzer to Be Used
Project stage: Other
ML14135A0051981-01-23023 January 1981
High Radiation Sampling Station General Piping Arrangement Plan
Project stage: Other
ML13330A1931981-02-0202 February 1981
Forwards Application for Amend 96 of License DPR-13
Project stage: Request
IR 05000206/19810041981-02-25025 February 1981
IE Insp Rept 50-206/81-04 on 801229-810130.No Noncompliance Noted.Major Areas Inspected:Followup on Systematic Appraisal of Licensee Performance & Allegation by Contractor Employee
Project stage: Request
ML13330A2411981-03-0606 March 1981
Responds to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Sys Automatic Initiation Will Occur on Low Steam Generator Level W/Setpoint at 5% of Narrow Range Instrument
Project stage: Other
ML13330A2661981-03-17017 March 1981
Forwards Listing Containing Brief Description of Design Changes Completed During 1980 Per 10CFR50.59b & Rept on Challenges to Relief & Safety Valves Per NUREG-0578
Project stage: Other
ML13330A2671981-03-18018 March 1981
Advises That post-accident Sampling Sys,Described in Licensee ,Will Not Include Capability to Perform Chloride Analysis,Per NUREG-0737 & NUREG-0578.Chloride Analyses Using Dilute Samples Are Inaccurate
Project stage: Other
ML13330A2911981-04-13013 April 1981
Responds to NRC 801031 Request for Clarification of NUREG-0737 Requirements & Confirmation of Implementation Date.Rept by NUS Corp, Control Room Habitability Evaluation San Onofre Generating Station,Unit 1 Encl
Project stage: Request
ML13302B0341981-04-13013 April 1981
Summary of 810310 Meeting W/Utils in Bethesda,Md Re Explosion Hazards.Attendance List & Applicant Handouts Encl
Project stage: Request
ML13331A0741981-04-17017 April 1981
Requests That NRC Finish Review of Util Compliance W/Ie Bulletin 79-06C, Nuclear Incident at TMI - Suppl. Review Completion Needed for Util to Complete Design Change to Assure Automatic Tripping of Reactor Coolant Pumps
Project stage: Other
ML13330A2991981-04-20020 April 1981
Forwards Response to NUREG-0737,Item II.K.3.17 Re ECCS Equipment Outages.Also Forwards Analysis of Probability of Toxic Gas Hazard for San Onofre Nuclear Generating Station as Result of Truck Accidents Near Plant
Project stage: Other
ML13317A6101981-05-0707 May 1981
Forwards Addl Info Re SEP Topic XV-16, Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Containment, Per 801215 & 810319 Requests
Project stage: Request
ML13317A6161981-05-12012 May 1981
Advises That TMI Action Plan Item II.K.3.9 Was Not Completed by 810101.Facility Has Been Shut Down Since Apr 1980.Item Will Be Completed Prior to Restart.Also Lists Completion Schedules for Items II.D.3,II.E.4.2.,II.G.1 & III.D.3.3
Project stage: Other
ML13317A6271981-06-0808 June 1981
Submits Results of Evaluation of Containment post-accident Pressure Reanalysis on Operational Limits,In Response to TMI Action Plan Item II.E.4.2(5).Peak post-accident Pressure & Temp in 770119 Analysis Is Still Applicable
Project stage: Other
ML20196A6141981-06-15015 June 1981
IE Review & Evaluation of Licensee Implementation of TMI Action Plan Requirement 1.C.5, `Procedures for Feedback of Operating Experience to Plant Staff
Project stage: Other
ML20196A6061981-06-15015 June 1981
IE Review & Evaluation of Licensee Conformance W/Tmi Action Plan Requirements 1.A.1.3, `Shift Manning Part 1,Limit Overtime
Project stage: Other
ML13317A6371981-06-17017 June 1981
Advises That Effluent Monitoring Sys,Per NUREG-0737,Item II.F.1 Will Not Be Completed Prior to Startup,As Remote Readout Gm Detector Has Been Removed.Interim Requirements of NUREG-0578 Will Be Met Per
Project stage: Other
1980-04-11
[Table View] |
Text
POST-ACCIDENT SAMPLING SYSTEM CAPABILITIES AND DESCRIPTION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 July, 1980 80071505r?
Scope Post-Accident Sampling System modifications are planned at San Onofre Unit 1 to satisfy the requirements of NUREG-0578, Section 2.1.8.a, as clarified by the NRC letter dated October 30, 1979.
The primary purpose of implementing Post-Accident Sampling System capabilities is to improve efforts to assess and control the course of an accident.
The system will provide information related to the extent of core damage that has occurred or may be occuring during an accident, to determine the types and quantities of fission products released to the containment in the liquid and gas phase and which may be released to the environment and to provide information on coolant chemistry (i.e., dissolved gas, boron and pH) and containment hydrogen.
Design Criteria The Post-Accident Sampling System will provide the capability to remotely collect the reactor coolant, containment sump liquid and containment atmos phere samples within one hour under accident conditions.
The system will provide remote readout of the results of chemical and radiological analyses and return radioactive samples inside containment.
The design criteria for the Post-Accident Sampling System are as follows:
- 1.
Quantification of the following within one hour of obtaining pressurized and unpressurized reactor
- coolant, containment sump liquid and containment atmosphere samples:
- a. isotopes that are indicators of core damage (i.e.,
noble gases, iodines, cesiums, and non-volatile isotopes), and
- b. dissolved gases (i.e.,
H2, 02),
boron, and pH of the reactor coolant.
- 2.
Remote override of the Containment Isolation Actuation Signal (CIAS) to reactor coolant, containment sump liquid and containment atmosphere sample line isolation valves will exist post-accident to ensure that the samples can be collected within one hour.
- 3. Post-accident sampling and analyses will not result in personnel radiation exposure in excess of 3 and 18 3/4 Rem to the whole body and extremities, respectively.
- 4.
The system will be capable of accommodating an initial reactor coolant radiochemical spectrum corresponding to a Regulatory Guide 1.4, Rev.
2, release.
- 5.
All post-accident sample purge flow will be returned to the containment to minimize contamination of other auxiliary systems and to ensure that high level waste remains isolated within the containment.
- 6.
Containment atmosphere sampling will be possible under both positive and negative containment pressures.
-2
- 7.
A reactor coolant sample will be drawn from the reactor coolant system and a containment liquid sample will be drawn from the containment sump.
- 8.
Samples will be cooled and
- diluted, as
- required, to facilitate measurement.
- 9.
Onsite multichannel analyzer equipment will be used for isotopic analysis of the reactor
- coolant, containment sump liquid and containment atmosphere samples.
- 10.
Downstream of the containment isolation valves, components and piping will be non-safety related, non-1E, non-Category A, and non-code (ASME B&PV Code,Section III).
- 11.
Total dissolved gas concentrations up to approximately 2000 cc/kg will be measured.
- 12.
Design parameters for the system are based on a reactor coolant design pressure and temperature of 2 4 85 psig and 650oF and a
containment atmosphere pressure and temperature of 65 psig and 300 0 F.
- 13.
Hydrogen monitors located inside containment will provide continuous indication.
- 14.
Diluted grab samples will be taken for further analysis (e.g., chlorides) on or offsite, as required.
Sample Analysis Capabilities All required measurements, excepting chloride analysis, will be performed with on-line meters and detectors.
Onsite laboratory chloride analysis will be performed within one shift as required in NUREG-0578.
The sensitivity of onsite post-accident analyses will permit measurement of nuclide concentra tions from approximately 1 4ACi/gm to Regulatory Guide
- 1. 4 levels.
Hydrogen monitors located in containment, will be installed to provide continuous indication as required by NUREG-0578.
A preliminary piping and instrument diagram showing the Post-Accident Sampling System is attached as Figure
- 1. The system influent equipment design parameters are as follows:
Reactor Coolant Containment Atm Pressure atm -2485 psig
-2 in. Hg - 60 psig Temp 50-6500 F 50-300 0 F H2 2000 CC(STP) 0-10 Volume%
Kg 02 Saturated @ atm
-3 Reactor Coolant Containment Atm Boron 100-4400 ppm pH 3-12 C1-0-2 ppm Radio Chemistry Nuclides (gross y )
<107 P Ci/co
< 1o5, Ci/cc Sample line Dose Rate 5 x 104 R/hr 1 x 104 R/hr Dissolved Solids 5-20 ppm Iodine (1-131) 2.6 x 104 PCi/cc 3.5 x 102 pCi/cc Noble Gas (Kr-85) 4.3 x 102 pCi/cc 10 pCi/cc (Xe-133) 1 x 105 p Ci/co 2.8 x 1o3 pCi/cc
System Description
A shielded underground sample station will be constructed to house the Post-Accident Sample System.
The underground arrangement will minimize personnel exposure and preserve space for normal station activities.
Inside the sample station, a concrete shield wall will separate the control area from the sample process area. A preliminary site location plan showing the general arrangement of the Post-Accident Sampling System is attached as Figure 2.
A completely enclosed stairwell provides personnel access to the control area.
Enclosure of the stairwell is necessary to prevent the influx of drainage water and the associated moisture problems.
A removable roof panel above the control area will allow entry for large equipment (e.g.,
control panel).
Access to the sample process area for equipment installation and periodic maintenance is through a removable roof panel. The roof panel will be several feet thick requiring the use of heavy equipment for removal.
The roof panel geometry will prevent leakage into the sample process area.
Environmental conditions in the underground station will be monitored and maintained as required.
The sample process area will be maintained under slight negative pressure to assure that any air leakage is into the process area. A ventilation system will be included to control airborne radioacti vity.
The control area temperature and relatiave humidity will be monitored for the protection of electronic equipment (e.g.,
control panel and ampli fier).
High range portable survey instruments and personnel dosimeters will be provided to permit rapid assessment of high exposure rates and accumulated personnel exposure.
Interconnecting piping required for radioactive sample delivery and return will be routed from the containment isolation valves inside the Sphere Enclosure Building above grade and from the Sphere Enclosure Building to the sample process area in a shielded underground trench as shown on Figure 2.
Drainage of the trench will be into the process area sump in the underground station.
Removable panels will cover the trench and permit the future placement of additional piping as required.
The underground trench and sample station have been located to minimize the length of inlet piping required.
Long inlet piping runs pose shielding problems and promote particle plate out.
All sampling operations will be activated, monitored, and controlled remotely from the control panel located in the control area of the underground sample station.
- Pressure, temperature, and flow readout will be located on the control panel.
Throttling and isolation valves to control the sample flow process will be provided with pneumatic operators and controlled remotely at the control panel.
Manually operated reach rods extending through the shield wall will provide redundant operational capability.
Liquid and atmospheric samples will be collected and analyzed in the process area of the underground station.
Major hardware items including valves, collection vessels, tanks, and pumps will be housed in a 6' x 4' x 6' high cabinet.
The cabinet will be bolted to the floor and configured for ease of maintenance.
Two lead shielded germanium crystal gamma detectors, one for reactor coolant and containment sump liquid and one for containment atmosphere, will adjoin the shield wall on the control side of the sample station.
Location of the detectors in the control area of the underground station is required to minimize background radiation levels and facilitate weekly liquid nitrogen filling.
The spectrum results detected by the germanium detectors will be fed to a multichannel analyzer for analysis and readout.
Station procedures will be developed that identify the analyses required, measurement techniques and safety precautions.
These procedures will be implemented prior to placing the Post-Accident Sampling System into service.
