Letter Sequence Other |
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Results
Other: ML19327A527, ML19327A533, ML19330B521, ML19330B523, ML19331B934, ML19336A759, ML19340B179, ML19344B508, ML19347C984, ML19347C997, ML19350A630, ML20053A188, ML20080J137, ML20080P638, ML20083D856, ML20083E087, ML20083H776, ML20084D339, ML20085B165, ML20092A427, ML20135G519, ML20137F772, ML20213G752, ML20214F390, ML20244B663, ML20244B666
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MONTHYEARML19330B5211980-07-25025 July 1980 Responds to IE Bulletin 80-17,Suppl 2, Failure of 76 of 185 Control Rods to Fully Insert During Scram at Bwr. No Mod Required for Units 1 & 2 Vent Sys Since as-built Sys Satisfies Requirements of Bulletin Project stage: Other ML19330B5231980-07-25025 July 1980 Responds to IE Bulletin 80-14, Degradation of BWR Scram Discharge Vol Capability. Investigation to Determine How Frequently Scram Discharge Vol Vent & Drain Valves Should Be Tested Underway Project stage: Other ML19327A5331980-07-28028 July 1980 Responds to IE Bulletin 80-17.Provides Manual & Automatic Scram Test Results.Scram Discharge Vol Vent Lines Verified & Emergency Operating Procedure Changes Completed Project stage: Other ML19327A5271980-07-31031 July 1980 Responds to IE Bulletin 80-17 & Provides Manual Scram Test Results.Scram Discharge Vol Vents Lines Verified as Functional & Full Operator Training to Be Completed as of 800802.Recirculation Pump Trip Installed Project stage: Other ML19331B9341980-08-0505 August 1980 Responds to IE Bulletin 80-17, Failure of Control Rods to Insert During Scram at Bwr. Automatic Scram Performed & Scram Discharge Vol Responded Properly.Automatic Scram Test Results Enncl Project stage: Other ML19340B1791980-10-10010 October 1980 Responds to NRC Requesting Tech Spec Mods Re Scram Discharge Vol.Present Tech Specs Assume Control Drive Sys Operability & Scram Discharge Vol Piping Is Sized to Assure Complete Scram.Mods Will Not Increase Reliability Project stage: Other ML19344B5081980-10-14014 October 1980 Responds to Mar 1980 Comments Made at White House Issues Briefing session.NUREG-0625 Is Not Intended to Be Sole Basis for Judging Sites.Evacuation Plans Considered in Licensing Actions Leading to Cp.Foundation Will Be Evaluated Project stage: Other ML19336A7591980-10-24024 October 1980 Responds to 801001 Request Re Participation in Development of Scram Sys Design & Performance Criteria.Not Active Member in Subgroup Considering Criteria.Plans to Consolidate Reviews of Design Rather than Performing Separate Reviews Project stage: Other ML19341C7971981-02-26026 February 1981 Semiannual Rept,Plant Radioactive Effluent Releases,Jul-Dec 1980 Project stage: Request ML19347C9841981-02-26026 February 1981 Tech Spec Tables 3.6.3-1,3.7-1 & Page 3.7-20 for Primary Containment Isolation Valves Project stage: Other ML19347C9811981-02-26026 February 1981 Application for Amend to Licenses NPF-5 & DPR-57,submitted as Proposed Changes to Tech Specs Re BWR Scram Sys Design Project stage: Request ML19347C9971981-03-0404 March 1981 Submits Addl Info Re BWR Scram Discharge Sys Mods,Per 801001 Request.Mods Will Be Implemented as Needed to Result in Conformance to Owners Group Criteria by End of 1982 Provided Qualified Equipment Is Commercially Available Project stage: Other ML19350A6301981-03-0606 March 1981 Notifies That Util 801010 Commitments to BWR Scram Discharge Sys long-term Mods Do Not Satisfy NRC Criteria.Revised Tech Specs Must Be Proposed at Least 3 Months in Advance of Mod Completion Dates Project stage: Other ML20010E8921981-09-0101 September 1981 Forwards Franklin Research Ctr Request for Addl Info Re BWR Scram Discharge Vol long-term Mods.Info Requested within 45 Days of Receipt of Ltr Project stage: RAI ML19280B1321981-10-0101 October 1981 Responds to 810901 Request for Addl Info from Franklin Research Ctr Re Util 810226 Proposed Tech Spec Mods for Scram Discharge Vol.Util Will Submit Amend to Unit 1 Rod Block Setpoint & Surveillance Requirements Project stage: Request ML20244B6661982-01-13013 January 1982 BWR Scram Discharge Vol Long-Term Mods,Ga Power Co,Hatch Nuclear Plant,Unit 1, Technical Evaluation Rept Project stage: Other ML20244B6631982-01-13013 January 1982 BWR Scram Discharge Vol Long-Term Mods, Technical Evaluation Rept Project stage: Other ML20053A1881982-05-18018 May 1982 Requests Extension of 821231 Commitment Date for Installation of Qualified Level Transmitters in Scram Discharge Sys to 831231 Project stage: Other ML20085B1651983-06-24024 June 1983 Order Confirming Licensee Commitments to Install Mods to Scram Discharge Sys by 831231 Project stage: Other ML20080J1371983-09-19019 September 1983 Proposed Tech Spec Changes Re Scram Discharge Sys Project stage: Other ML20080J1161983-09-19019 September 1983 Application to Amend Licenses DPR-57 & NPF-5,changing Tech Specs to Reflect Mods to Scram Discharge Sys,As Required by NRC Project stage: Request ML20080P6381983-10-0303 October 1983 Requests That Re Proposed Tech Spec Changes Concerning Scram Discharge Sys Be Superseded by 830919 Submittal Project stage: Other ML20083E0061983-12-14014 December 1983 Suppl to 830919 Application to Amend Licenses DPR-57 & NPF-5,changing Tech Specs Re Scram Discharge Vol Closure Times Project stage: Request ML20083E0871983-12-14014 December 1983 Proposed Tech Spec Changes Re Scram Discharge Vol Closure Times Project stage: Other ML20083D8561983-12-20020 December 1983 Corrects Changing Tech Specs Re Scram Discharge Sys Operability.Outboard Scram Discharge Vol Vent & Drain Valves Close Vs Open within 5 After Closure of Inboard Valves Project stage: Other ML20083H7761983-12-22022 December 1983 Forwards Addl Info Re Requesting Substitution of Longer Values for Scram Discharge Vol Vent & Drain Valve Closure Times.Closure Times Proposed in Do Not Meet Acceptance Criteria in SER Project stage: Other ML20084D3391984-04-23023 April 1984 Submits Results of GE Review of 831222 Analysis of Scram Discharge Vol Vent & Drain Valve Closure Times in Excess of 30 S.Ge Does Not Concur W/Analysis.Closure Times Should Be Accepted as Is.Continued Plant Operation Justified Project stage: Other ML20092A4271984-06-14014 June 1984 Submits Schedule Requested in Re Implementation of Mods Resulting in Scram Discharge Vol Vent & Drain Valve Closure Times Which Meet GE Requirements of 30 S.Tests Will Be Performed to Determine Extent of Mods Project stage: Other ML20135G5191985-09-13013 September 1985 Proposed Tech Spec,Adding 60 Scram Discharge Vol Vent & Drain Valve Closure Time Requirement Project stage: Other ML20135G5101985-09-13013 September 1985 Application for Amends to Licenses DPR-57 & NPF-5,adding 60 Scram Discharge Vol Vent & Drain Valve Closure Time Requirement to Tech Specs.Fee Paid Project stage: Request ML20136J4051985-11-18018 November 1985 Responds to Request for Addl Info Re 850913 Application for Amends to Licenses DPR-57 & NPF-5,allowing 60 Closure Time Limit for Scram Discharge Vol Vent & Drain Valves.Figure 6.2.2 from GE NEDO-24342 Re Scram Sys Pipe Breaks Encl Project stage: Request ML20137F3011986-01-0606 January 1986 Rev to 850913 Application for Amend to Licenses DPR-57 & NPF-5,revising Tech Spec to Provide Value of 45 Closure Time Requirement for Scram Discharge Vol Vent & Drain Valves for Unit 1 Project stage: Request ML20137F7721986-01-0606 January 1986 Proposed Tech Spec Changes Providing Value of 45 Closure Time Requirement for Scram Discharge Vol Vent & Drain Valves Project stage: Other ML20204A2781986-04-28028 April 1986 Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days Project stage: RAI ML20211G6301986-06-12012 June 1986 Forwards Request for Addl Info Re Util Listed Requests to Amend Tech Specs to Provide Closure Time Requirements for Scram Discharge Vol Vent & Drain Valves.Info Requested within 45 Days of Ltr Receipt Project stage: RAI ML20210T7521986-09-23023 September 1986 Responds to NRC 860612 Request for Addl Info Re Scram Discharge Vol Vent & Drain Valve Closure Times Project stage: Request ML20213G7521986-11-11011 November 1986 Forwards Bechtel Calculation Sheets Re CRD Scram Discharge Header Drain Piping Project stage: Other ML20214F3901987-05-13013 May 1987 Amends 136 & 75 to Licenses DPR-57 & NPF-5,respectively, Providing Closure Time Requirements for Scram Discharge Vol Vent & Drain Valves Project stage: Other ML20214F3951987-05-13013 May 1987 Safety Evaluation Supporting Amends 136 & 75 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval 1983-10-03
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Text
1 Gw>rg a Power Corrpy o
333 Petnant Avenue Attanta Georgia 30308 Teletrone 404 526 6526 M i+1tng Adfrew Post O!!ce Box 4M5 Attanta. Georqa 39302 Georgia Power L T. Gucwa ru urm mguc wwm Manager Nuc&ar Er7neet ng are en-t Nuciear E ve.,,
NED-84-204 April 23,1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Wa shi ng ton, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HATCH NUCLEAR PLANT UNITS 1, 2 SCRAM DIS 01ARGE VOLUME VEKr AND DRAIN CLOSURE TIMES Gentlemen:
By letter of December 22, 1983, Georgia Power Company provided to NRC an analysis concerning operation with scram discharge volume (SDV) vent and drain valve closure times in excess of 30 seconds (the current GE specification).
At NRC request, this analysis was provided to General Electric for myiew.
Additionally, GE was asked to provide bases for the 30 second closure time specification.
This letter provides the results of the GE review and our plans to resolve the closure time issue.
GE provided no quantitative basis for the 30 second closure times, and it appears that none exists.
However, qualitative bases addressing three areas were provided:
- 1) Hydrodynamic Loads; 2) CRD Leakage Flow; and 3)
High Temperatures.
1.
Hydrodynamic loads are caused when the SDV vent and drain valves close.
The nature and extent of these loads is very dependent on pipire configuration.
GE provided no correlation between hydrodynamic i
l loads and valve closure times.
2.
CRD leakage flow could fill the SDV, resulting in water flow through the vent lines if the vent valve has not closed. This could result in l
additional pipe loadings and possible radiological concerns.
3.
High temperatures exceeding the piping and equipment design temperature of 280 F are more likely to occur if the 30 second closure time limit is exceeded.
The design versus actual operating temperature of the scram discharge system has been the subject of considerable discussion among GE, industry, and NRC.
GE has since specified the 30 second limit, which was not one of the of the original Hatch design criteria, to help limit temperatures of the system following a scram.
8405010302 840423 PDR ADOCK 05000321 P
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GeorgiaPower d U. S. Nuclear Regulatory Commission Division of Licensing April 23,1984 Page 2 As a result of their assessment of items to be considered, which was qualitative in nature, and their industry-wide posture regarding the 30 second closure times, GE was unable to concur with our analysis as provided in the December 22, 1983, letter.
Since extensive analyses would be required to justify longer closure times, we are now investigating minor hartlware modifications to bring the closure times closer to the 30 second limit.
A test has been scheduled for Unit 2 during the current outage to determine minimum closure times obtainable with these minor system modifications.
If the results of this test indicate that minor modifications alone will not bring the closure times to within the 30 second limit, we have instructed our architect / engineer to expedite procurement and design of modifications necessary to achieve 30 second closure times.
Following completion of this test, we will provide you with a schedule for completion of necessary modifications.
We would like to reiterate that Hatch Unit I was designed, and has operated for nine years, with vent and drain valve closure times well in excess of the current GE specification.
In this time, the only damage to the SDV, SDV piping, or supports that has been found has been one bent hanger, attributed to an installation error.
Hatch Unit 2 did experience hydrodynamically caused damage to the floats in the SDV instrument w,Jumes.
This problem was attributed to instrument line routing and was corrected.
At the time this damage occurred, closure times for Unit 2 were measured and found to be under 30 seconds, indicatire that valve closure times were not a factor.
We therefore believe that continued operation with the longer closure times represents no risk to the health and safety of the public.
Please contact this office if you desire further information.
Very truly yours, f 7~ g e =
L. T. Gucwa REB /
xc:
H. C. Nix, Jr.
J. P. O'Reilly (NRC-RII)
Senior Resident Inspector, Plant Hatch 1
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