Letter Sequence Request |
|---|
|
|
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
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
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
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] |
Similar Documents at Hatch |
|---|
|
Text
Georgia Power Company 333 P;edmont Avenue Attanta Georgia 30308 Telephone 404 526-6526 Mailing Address:
Post office Box 4545 Atlanta. Georgia 30302 h
Georgia Power L T. Guewa trv southem electnc system Manager Nuclear Engineenrig and chief Nuclear Engineer NED-84-077 February 20, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Ccunission Washington, D. C.
20555 NRC DOCITTS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HA'ICH NUCLEAR l'IANT UNITS 1, 2 NUREX;-0737 ITEM II.B.3, POST-ACCIDENI' SAMPLING CAPABILITY Gentimen:
Our subnittal dated January 26, 1984 provided information demonstrating the extent of cmpliance of Plant Hatch with the criteria of the subject ite. A cmpletion schedule was proposed for the criteria which were not yet satisfied.
Mr. George Rivenbark, Hatch Licensing Project Manager, has requested additional justification for the proposed cmpletion schedule.
In response to that request, Enclosure 1 is subnitted.
Please contact this office if there are any questions.
Very truly yours,
[E p--;
L. T. Gucwa JH/m Enclosure xc: J. T. Beckhm, Jr.
H. C. Nix, Jr.
P. D. Rice J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector 1
1 1
$Ocd"0!$o$$
p PDR
.4-4 J.
a s-4-4 W
r 1
O f
t k
DK'IOSURE 1 EDKIN I. HAM NUCLEAR PIAMP UNITS 1 AND 2 10ST-ACCIDEMP SAMPLING CAPABILITY a
e J
b M
4 g--e--
,,--w- - - - - - - -. --,,- -.ee nen-.--
v %- w,
4,w-.,--,-,o.----
,,-,--w..
e,-
r,c..-,,
o
,,. ~., - -. - e e-..-
ei-
..-- =..-,--,v vww.w.w-w.-,--.-ere.
I.
INIPODUCTION In our letter of January 26, 1984 we indicated four items reained outstanding concerning full cmpletion of NUREG-0737 Its II.B.3.
%ese itms are discussed further below. Each of these four itms can be characterized as relatively current probles.
Initial comitments were based on the assumption operability of the Post-Accident Saple Systs (PASS) was all that was needed to satisfy the NUREG-0737 comitment.
Other utility experience, site inspections, and the proposed technical specifications and formal progra referenced by your Generic Letter 83-36 indicated a good deal more would be expected in the administrative aspects of this systs. 'Iwo of the outstanding itms relate specifically to these administrative aspects.
The other two items concern questions on probles that did not fully develop until Dec eber, 1983.
II.
SCHEDULE JUSTIFICATION A.
PROPOSED SCHEDUIE - SHIPPING CASK Criterion 8 of Item II.B.3 requires the capability to obtain and analyze (not necessarily on-site) grab saples as a backup if in-line monitoring is used for any analysis.
Plant Hatch is in partial empliance with this criterion in that the PASS provides the capability to obtain grab smples to back up its in-line monitors and arrangenents have been made for analysis at an off-site facility.
The shipping cask which is to be used for transportation of the saples, however, will not be available until May 1, 1984.
This date was proposed by GPC for completion of Criterion 8.
JUSTIFICATION
%e cask in question was developed for the Pooled Inventory Managenent (PIM) progra for use by numerous BWR utilities.
GPC has therefore had minimal control over the schedule for design, construction, licensing, and delivery of the casks to the PIM facility.
At the time the December 1,1983 cmpletion date for Item II.B.3 was proposed by GPC, the PIM casks were scheduled for delivery in late 1983.
As late as Novenber 21, 1983, GPC was informed that this schedule would be met.
We discovered on January 24, 1984, however, that delivery had not been made and had been re-scheduled for May 1,1984.. - - -
i 4
t Had shipping cask availability been the only incmplete aspect of
^
Its II.B.3, it is expected that alternate shipping arrangements could have been made. Furthermore, the probability of an accident
- requiring use of the PASS is extreely low, grab smple analysis would only be used as a backup to in-line monitoring, and limited grab smple analysis capability would be available on-site.
B.
PROPOSED SCHEDULE - VALIDATION 'IESTING Criterion 10 of Its II.B.3. specifies that the accuracy range, and 4
j sensitivity -of the required isotopic and chemical analyses be adequate to provide pertinent data on the condition of the reactor
- coolant.
Clarification 10 of the August 24, 1982 NRC letter provided specific accuracies - which were to be achieved while performing the analyses in the presence of certain interferences (NRC test matrix).
Plant Hatch partially satisfies Criterion 10 in that factory tests, performed using the NRC test matrix, resulted in accuracies which substantially emplied with the recomendations of Clarification 10.
However, a full systs integrated test was not possible until site installation and initial operability were cepleted. To assure that the caponents and integrated syste perform as designed a series of verification /
validation tests are being carried out. GPC proposed May 1, 1984 as the completion date for this testing.
~
JUSTIFICATION
%e integrated systs tests could not be initiated until all system functions were established.
Reliable pressure control and flow throughout the system were not available until the latter part of January 1984.
Site verification tests and any necessary syste refinments are in progress and will be empleted by May 1, o
.1984.
C.
PROPOSED SCHEDULE - AININISTRATIVE PROGRAM Clarification 10 of the August 24, 1982 NRC letter specifies that equipnent testing, procedures :for sapling and analysis, and personnel training be adequate to ensure the availability of post-accident sapling and analysis capability.
It was noted that fortheming model Technical Specifications would provide guidance on the incorporation of these provisions. % e referenced guidance was provided in Generic Letter 83-36, dated Novmeber 1, 1983.
%is letter transmitted a model Technical Specification which required an administrative progra covering personnel training, maintenance of sapling and analysis equipnent, and procedures for sampling and analysis.
GPC proposed to implement such a progra by June 1, 1984... ~.
l JUSTIFICATION Based on Generic Letter 83-36 it was apparent that a formal administrative progran would be required.
'Ihis adninistrative program needs to address surveillance, calibration, procedures training, retraining, operability criteria, staffing (i.e. who is trained), etc.
While initial training, calibration, procedural developnent, and related functions have been acceplished, the establishment of a formal ongoing progran is not yet emplete.
Technical Specification and Program developnent will be cmpleted p
by June 1, 1984.
l i
D.
PROPOSED SCHEDULE - HEAT TRACING criterion 11 of Item II.B.3 requires that consideration be given to various aspects of equipnent design related.to representative sampling.
Clarification 11 of the August 24, 1982 NRC letter specifically mentions heat tracing as an item to be addressed.
l Plant Hatch partially cmplies with Criterion 11 in that the PASS design includes. all of the required considerations with the exception of heat tracing on the contairunent atmosphere sample
[
lines. GPC proposed to install the heat tracing by August 1,1984.
JUSTIFICATION Heat tracing was not a specific design criterion in the initial discussion of this iten. ' It was recognized that the contairunent atmosphere sanple must be respresentative for noble gases and radioiodines.
Initial engineering analyses indicated heat tracing was not. needed to assure sanple validity.
While subssjuent analyses do not clearly indicate heat tracing is either needed or l
not needed, it was decided that installation would be necessary to renove any doubt about sample validity.
Heat tracing has been
[
designed and is in the procurenent process.
The current schedule calls for installation by August 1, 1984.
III. CONCLUDING S& MARY As stated in our January 26, 1984 subnittal, the PASS systen is fully functional. All esponents are operating. 'Ihe four outstanding itens discussed need to be cmpleted, however, before GPC can state that Plant Hatch is in full-cmpliance with NUREG-0737 criteria for Post-Accident Sanpliag Capability.
_ _ _ _ _. _ _.. -,_,_..-,. _ _
