Letter Sequence Supplement |
|---|
|
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
|
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
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, February 24, 1982 213) 572-1401 SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention:
D. M. Crutchfield, Chief Operating Reactors Branch No. 5
?
FE82 5 1982 0
Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket 50-206 NUREG-0737, Item II.F.1, Noble Gas Effluent Monitor, Sampling and Analysis of Plant Effluents San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, Response to Order Confirming Commitments for TMI Related Requirements, August 6, 1981
- 2. Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, NUREG-0737, Item II.F.1, Attachment 2, Sampling and Analysis of Plant Effluents, November 25, 1981
- 3. Letter, D. M. Crutchfield, NRC, to R. Dietch, SCE, Status of NUREG-0737, Items II.F.1.1 and II.F.1.2, January 29, 1982 Reference 1 provided you with a system description and a statement of our design criteria for the San Onofre Unit 1 plant stack monitoring system, in response to the subject requirement. Reference 2 informed you of our deviation from the design criteria and a justification for the deviation.
Reference 3 is a summary of your understanding of the current status of the subject requirement at San Onofre Unit 1 and a request that we provide additional information, if necessary, to clarify the status of the requirement.
8203030331 820224 PDR ADOCK 05000206 P.
~
Mr. D.
February 24, 1982 This correspondence is intended to inform you of additional clarification needed to define the status and anticipated completion date of modifications in response to the subject requirements. We are also informing you of our effort to examine potential design alternatives which could alleviate the sample-line plate-out problem described below.
The stack monitoring system as described in Reference 1, further classified on the attached system description and associated equipment and layout drawings, has been designed in accordance with the guidance presented in NUREG-0737.
The supplemental guidance given in ANSI N13.1-1969 was also used to minimize the plate-out of particulates and iodines by locating the sampler as close as practical to the plant stack, attempting to minimize the horizontal component of the sample line, using long radius bends where bends were necessary, and heat tracing the sample lines. The sample skid was installed in June, 1981 and is presently located as indicated in the attached drawing 5161348-0, with the sample lines routed as indicated in the same drawing. These sample lines are planned to be relocated to a new location as indicated on the drawing titled "Proposed Sample Line to Vent Stack Wide Range Gas Monitor."
The rerouting of the lines is an attempt to reduce sample line particulates and iodine plate-out by reducing the horizontal component and reducing the number of bends in the sample line.
This modification is currently scheduled to be completed during the steam generator inspection outage to commence approximately March 1, 1982.
The noble gas effluent monitor and the radioiodine grab sampler at San Onofre Unit 1 are an integrated system on two skids located as discussed above. The noble gas effluent monitor was made operable on December 24, 1981 with the exception of the ability to sample when effluent conditions are 100%
relative humidity at 100-1100 F. This problem should be resolved and the noble gas effluent monitor made fully operational during the March 1, 1982 steam generator inspection outage. Sample line plate-out calculations for particulates were performed using the guidance presented in ANSI N13.1-1969, Appendix B. Based on our system configuration, the results of the calculations showed an anticipated 80% plate-out of particulates in the high flow--low radiation sample and 100% plate-out of particulates in the low flow--high radiation sample line. When the previously discussed sample line reroute is completed, the plate-out calculations will be recalculated using the new configuration, but current estimates do not anticipate an appreciable change in the percentage of sample-line plate-out.
Based on informal inquiries of ten (10) nuclear power stations, the plate-out problem is one of generic concern. Our inquiry indicated that although plate-out has been identified as a problem at other stations, an acceptable value for sample line plate-out has not been quantified or even calculated in a manner according to ANSI N13.1-1969, Appendix B. The current guidance presented in NUREG-0737 and ANSI N13.1-1969 suggests that the plate-out be evaluated, but does not establish any criteria for an acceptable level of plate-out.
Mr. D.
February 24, 1982 Based on the above discussion, the San Onofre Unit 1 post-accident effluent monitoring system has been designed and installed to comply with the existing criteria and no further modifications, other than those previously discussed, are planned. We are initiating an effort to examine design alternatives which would reduce the plate-out in the system and enable a grab sample to be taken. It is not currently known if redesign will reduce the sample line plate-out to an acceptable level but we will inform you of the results of our effort on June 1, 1982.
If you have any questions, please let me know.
Very truly yours, Enclosures cc:
R. H. Engelken, Director, OIE, Region V
SYSTEM DESCRIPTION STACK EFFLUENT RADIATION MONITORING SYSTEM INTRODUCTION The Stack Effluent Radiation Monitoring System, also described as Wide Range Gas Monitoring System (WRGHS),
Is designed to meet the recommendations of NUREG-0578, Item 2.1.8b-1.
The system provides the control room operator a continuous measurement of the noble gas radioactivity being released to the environment via plant effluent pathway, namely the stack.
Another effluent release path under certain postulated accident conditions Is the atmospheric steam dump valve and/or the steam generator safety valves.
The effluent monitoring system for this release path is described elsewhere.
SYSTEM COMPONENTS Since the plant personnel are to have access to certain components of the WRGMS (such as the particulate and iodine sample filters) during high range release conditions, the system is separated into distinct component assemblies which are located in such a way as to minimize personnel exposure to the postulated high levels of radiation.
There are six (6) component assemblies of the system which are:
- 1. Isokinetic Nozzles
- 2.
Sampling Rack
- 3.
Sample Conditioner
- 4. Wide Range Gas Detector
- 5.
Electronics
- 6.
Readouts ISOKINETIC NOZZLES There are two (2) sets of isokinetic nozzles, one for normal and one for high range conditions.
Both sets of nozzles are mounted on a common sample gantry in the stack.
Supplied with the isokinetic nozzles are pressure and temperature transducers to measure the effluent flow in the duct to provide computation of activity release rates in microcuries per second.
The nozzle assembly is located in the effluent stack at elevation 75'-7".
(See SCE Drawing No. 5161349.)
SAMPLE CONDITIONING SKID ASSEMBLY The sample conditioning skid assembly consists of sample rack and sample conditioner equipment.
Sampling rack is connected to the isokinetic nozzles and provides for collection of particulate and iodine samples.
There are two (2) sets of sampling hardware, one for normal operation and the other for high range conditions.
Filter holders and valves are provided to allow grab sample collection of particulates and iodines for isotopic analysis in the laboratory. The sampling rack is shielded to minimize personnel exposure.
-2 The sample conditioner functions only during high range conditions.
The purpose of the conditioner is to prevent contamination of the gas monitor by filtering out large concentrations of radiolodines and particulates.
To provide enough filtering material to contain radioiodines and particulates for the duration of the measurement period, multiple filters are employed. While one is being used to filter the sample, the other is purging automatically.
The sample conditioning skid assembly is located to the vest of the ventilation equipment room and outside of the concrete shield wall.
(See Drawing Nos. 5161348 and 5161350.)
WIDE RANGE GAS DETECTOR ASSEMBLY This assembly contains bree rtdioactive gas detectors to monitor noble gas concentrations from 10-to 10 microcuries per cubic centimeter, after the iodine and particulates have been removed.
This assembly also contains the necessary pumps, flow control valves, flow meters, etc.
Each detector has a solenoid actuated check source to verify proper operation.
The twelve (12) decades of noble gas concentrations are monitored by the three (3) detectors with at least one decade overlap between ranges of individual detectors.
There are two (2) flow paths to the detectors.
During normal operation, only the low-range detector is used and the mid-range and high-range detectors are bypassed.
As the low-range detectors begins to saturate, the flow path is automatically changed to mid-and high-range detectors while the low-range is purged.
The assembly is located adjacent to the Sample Conditioning Skid (see SCE Drawing No. 5161350).
ELECTRONICS ASSEMBLY This assembly consists of a G. A. Co.
Model RM-80 Microprocessor and a junction box for field terminations.
The microprocessor performs flow control, valve actuations, engineering conversions, and other calculations and control functions.
The microprocessor is located in a low radiation area in the Control Building (see SCE Drawing No. 5161363).
The processor communicates with the digital readout assembly in the main control room.
READOUTS The readout is mounted in the control room on panel C05 and consists of the digital module (G. A. Co.
Model RM-23 Readout) and a chart recorder.
The readout provides display of all monitor parameters, including channel activity in desired units, flow rates, alarm status, and check source actuation.
The multipoint recorder is provided to maintain a hard copy record of radioactive gas concentrations per unit volume (micro curies per cubic centimeter for each of the three detectors) as well as a record of rate of release of activity from the effluent point (micro curies per second).
The RM-80 Microprocessor maintains history files of twenty-four-10 minutes, twenty-four-1 hour and twenty-eight-1 day averages of channel activity that are available for recall via controls on the readout assembly. (See SCE Drawing No. 568730 and 5161353 for C05 panel mounted readout arrangement.)
DRAWING
REFERENCES:
SCE Drawing No.
Description 451942 Loop Diagram 568736 Vertical Board Arrangement 5161348 Installation Details -
Sample Lines 516349 Installation Details -
Isokinetie Nozzle Assembly 5161350 Installation Details - Skid Instruments 5161353 Installation Details -
Radiation Monitoring System GENERAL ATOMIC DRAWING DOCUMENTS Model RM-23 Readout User's Guide,No. E-115-809 Model RM-80 Equipment Manual, No. E-115-860 Wide Range Gas Monitors:
General Atomic Drawing Nos.
0366-0010 0366-0030 0366-0040 US:nps
