Letter Sequence Request |
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MONTHYEARML20104A2851979-03-0505 March 1979
Containment Leak Rate Test Program Incorporating Updated NRC Positions
Project stage: Other
ML19282B1571979-03-0505 March 1979
Forwards Reevaluation of Containment Leak Rate Test Program & Proposed Changes to Tech Specs Reflecting Provisions of Updated Program
Project stage: Request
ML20080J0871984-02-0707 February 1984
Informs That NRC Has Agreed to Issue Changed Pages Re Removal of Ref to Tech Spec 4.7.E Concerning 10CFR50,App J, Per 840127 Telcon
Project stage: Other
ML18031B3151986-05-14014 May 1986
Informs That Engineering Expertise on Shift Provided by Having Shift Technical Advisor on Duty,In Response to Generic Ltr 86-04.Bachelor Degree in Engineering Discipline Is Min Requirement for Shift Technical Advisor
Project stage: Request
ML20198B4641986-05-14014 May 1986
Submits Addl Info to Support 771116 Request for Changes to Containment Leak Test Program,Per Rivenbark & Kudrick Requests
Project stage: Request
ML20215N2381986-10-0707 October 1986
Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from App J Containment Leak Test Requirements
Project stage: Approval
ML20215N2241986-10-30030 October 1986
Amend 131 to License DPR-57,revising Tech Specs to Delete Ref to Specific Dtd Versions of App J Re Containment Leak Testing Requirements
Project stage: Other
ML20215N2461986-10-30030 October 1986
Exemption from Certain Requirements of 10CFR50,App J Re Containment Leak Testing
Project stage: Approval
ML20215N2511986-10-30030 October 1986
Notice of Denial of Application to Amend License DPR-57, Deleting Specific Dtd Version of App J Re Containment Leak Testing Requirements.Hearing May Be Requested
Project stage: Other
ML20215N2911986-10-30030 October 1986
Safety Evaluation Supporting Exemption from 10CFR50,App J & Amend 131 to License DPR-57
Project stage: Approval
ML20212N0121987-03-0404 March 1987
Proposed Tech Specs Deleting App J Leak Rate Testing Requirements for Certain Valves from Table 3.7-4 & Providing Administrative Correction to MSIV Test Pressure Requirement
Project stage: Other
IR 05000321/19870041987-03-0404 March 1987
Insp Rept 50-321/87-04 & 50-366/87-04 on 870223-27.No Violations Noted.Major Areas Inspected:External Exposure Controls,General Employee Training,Facilities & Equipment & Licensee Program to Maintain Low Exposures
Project stage: Request
ML20212N0011987-03-0404 March 1987
Application for Amend to License DPR-57,deleting App J Leak Rate Testing Requirements for Certain Valves from Table 3.7-4 & Providing Administrative Correction to MSIV Test Pressure Requirements.Fee Paid
Project stage: Request
ML20209D0861987-04-21021 April 1987
Revised Application for Amend to License DPR-57,revising Tech Spec Page 3.7-26 to Assign Valve X-211A to Penetration X-210A & Withdrawing Request to Delete Valves E11-F027A & B from Table 3.7-4
Project stage: Request
ML20209D1181987-04-21021 April 1987
Proposed Tech Spec Table 3.7-4 Assigning Valve E11-F028A to Penetration X-211A,restoring Valves E11-F027A & B & Deleting Valves E11-F011B & F026B
Project stage: Other
ML20214T6741987-05-29029 May 1987
Environ Assessment & Finding of No Significant Impact Re Licensee 870304 Application for Amend to Tech Specs,Deleting Certain Valves from Table 3.7-4 That Lists Containment Isolation Valves Subj to Leak Rate Testing,Per 10CFR50
Project stage: Other
ML20214T6401987-06-0101 June 1987
Forwards Environ Assessment & Finding of No Significant Impact Re 870304 Application to Amend License DPR-57 by Revising Tech Specs to Delete Certain Valves from Table 3.7-4
Project stage: Other
ML20214V6631987-06-0505 June 1987
Environ Assessment & Finding of No Significant Impact Re Amend to License DPR-57,revising Tech Specs to Delete Some Valves from Table 3.7-4 That Lists Containment Isolation Valves Subj to Leak Rate Testing Per 10CFR50,App J
Project stage: Other
ML20214V6421987-06-0505 June 1987
Safety Evaluation Supporting Amend 140 to License DPR-57
Project stage: Approval
ML20214V6531987-06-0505 June 1987
Notice of Issuance of Amend 140 to License DPR-57.Amend Modifies Tech Specs to Delete Certain Valves Listed in Table 3.7-4 as Containment Isolation Valves Requiring Leak Tests & Changing Pressure at Which MSIVs Required to Be Tested
Project stage: Approval
ML20214V6391987-06-0505 June 1987
Amend 140 to License DPR-57,modifying Tech Spec Table 3.7-4 to Delete Certain Valves Listed as Containment Isolation Valves Requiring Leak Tests & Changing Pressure at Which MSIVs Required to Be Tested
Project stage: Other
1986-05-14
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Similar Documents at Hatch |
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Georgia Fower Company 333 Piedmont Av:nue Atlanta, Georgia 30308 Telephone 404 526-6526 Mailing Address:
Fbst Office Box 4545 Atlar ta, Georgia 30302 GeorgiaPower L T.Gucwa tre southern e:ttric system Manager Nuclear Safety and Licensing SL-688 2695N May 14,1986
. Director of Nuclear Reactor Regulation A antion: Mr. 9. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 10 CFR 50 APPENDIX J Gentlemen:
Messrs. Rivenbark and Kudrick of the NRC verbally requested additional information in support of our November 16, 1977, submittal regarding changes to the Plant Hatch Unit 1 Containment Leak Rate Test Program.
QUESTION 1:
"How are the TIP shear valves tested?"
RESPONSE 1:
Continuity of the electrical system is continuously monitored via indicating lights.
Shoul d continuity be
- lost, indicating lights illuminate, and an alarm is received in the control room.
The explosive charges are tested and replaced per manufacturer's recommendations.
All four charges are replaced prior to their shelf life expiration date (5 years).
The old charges are fired to assure that they would have performed correctly if they had been actuated while in service.
Prior to replacing the charges in the system, one charge out of the fresh replacement batch is test fired to assure operability.
Based upon the discussions with the NRC, Georgia Power Company will revise the charge testing procedure, as necessary, so that it will be similar to the procedure used for the Standby Liquid Control System explosive charges (Hatch Unit 1 Technical Specifications Sections 3.4/4.4).
1 8605220010 860514 DR ADOCK 05000321 PDR
- O
k Georgia Power n Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 May 14, 1986 Page Two QUESTION 2:
" Describe how the closed systems outside containment are tested to assure that leakage (contaminated water) is minimized."
RESPONSE 2:
The systems (Residual Heat Removal, Core Spray, Reactor Water Cleanup, HPCI, and RCIC) are required to be leakage tested in accordance with Hatch Unit 1 Technical Specifications Section 6.13.
The systems are visually inspected up to the containment isolation valves (except for the HPCI and RCIC system isolation valves which are not accessible during plant operation) when the various system pump functional tests are performed.
If you should have additional questions regarding this matter, please feel free to contact this office at any time.
Sincerely, L. T. Gucwa LTG/mb c: Georgia Power Company Nuclear Regulatory Commission Mr.s. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr.
Senior Resident Inspector fir. H. C. Nix, Jr.
G0-NORMS 2695N 700775
