Letter Sequence Other |
|---|
|
Results
Other: AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal, AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility, AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules, AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas, AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks, AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818, ML20117C275, ML20117C283, ML20203G517, ML20205D440, ML20205E845, ML20205E852, ML20205T067, ML20209G129, ML20212N039
|
MONTHYEARML20117C2831985-05-0606 May 1985 Licensing Rept,High-Density Spent Fuel Racks Project stage: Other ML20117C2611985-05-0606 May 1985 Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Request ML20117C2751985-05-0606 May 1985 Proposed Tech Specs Allowing Replacement of Current low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks to Provide Increased Storage Capacity Project stage: Other AECM-85-0143, Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid1985-05-0606 May 1985 Forwards Application for Amend to License NPF-29,changing Tech Specs to Allow Replacement of low-density Aluminum Spent Fuel Racks w/high-density Spent Fuel Racks. Licensing Rept,High-Density Spent Fuel Racks, Encl.Fee Paid Project stage: Request ML20129F9581985-07-0505 July 1985 Forwards Request for Addl Info Re High Density Spent Fuel Racks in Upper Containment Pool & in Spent Fuel Storage Pool.Response Due by 850715 Project stage: RAI ML20133A1781985-07-26026 July 1985 Forwards Request for Addl Info Re Application to Amend License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & Spent Fuel Storage Pool.Info Requested by 850815 Project stage: RAI AECM-85-0229, Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress1985-07-29029 July 1985 Responds to 850705 Request for Addl Info Re Structural Analyses Presented in 850506 Application for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Direct Stress Below Liner Matl Ultimate Stress Project stage: Request ML20136H1801985-08-0909 August 1985 Forwards Request for Addl Info Re 850506 Request for Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks in Upper Containment Pool & in Spent Storage Pool.Info Requested by 850826 Project stage: RAI AECM-85-0252, Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl1985-08-15015 August 1985 Responds to NRC 850705 Request for Addl Info Re Structural Analyses Presented in Application for Amend to License NPF-29,authorizing Installation of High Density Spent Fuel Racks.Info Re Numerical Solution of Dynamic Analyses Encl Project stage: Request AECM-85-0272, Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis1985-08-30030 August 1985 Forwards Response to NRC 850726 Request for Addl Info Re Amend to License NPF-29,allowing Installation of High Density Spent Fuel Racks.Tech Spec Section 4.5 Changed to Conform to Ref Design Used in Analysis Project stage: Request ML20209G1291985-09-0606 September 1985 Evaluation of Spent Fuel Racks Structural Analysis,Grand Gulf Nuclear Station Unit 1, Technical Evaluation Rept Project stage: Other AECM-85-0297, Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility1985-09-11011 September 1985 Forwards Correction to Table 1 of 850815 Final Response to NRC Question Re Dynamic Analysis of High Density Spent Fuel Racks Proposed for Installation at Facility Project stage: Other AECM-85-0289, Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal1985-09-12012 September 1985 Forwards Revised Proposed Tech Spec Change Concerning Spent Fuel Pool & Upper Containment Pool Storage Capacity After Installation of High Density Spent Fuel Racks,Per 850506 Submittal Project stage: Other AECM-85-0352, Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules1985-11-0101 November 1985 Forwards Clarification of Use of Stress Criteria for High Density Spent Fuel Racks,In Response to NRC Request.Stress Criteria Differences Between OT Position Paper & NUREG-0800 Amount to Same Limits for Rack Modules Project stage: Other AECM-85-0410, Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks1985-12-18018 December 1985 Forwards Response to NRC Request to Determine & Submit Occupational Exposures Associated W/Operation W/High Density Spent Fuel Racks,Per 850506 Application for Amend to License NPF-29,allowing Installation of Racks Project stage: Request AECM-86-0077, Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas1986-03-14014 March 1986 Forwards Revised Spent Fuel Loading Pattern Developed to Maintain Dose Rate Contribution from Spent Fuel in Auxiliary Bldg Spent Fuel Pool Area Below 2.5 Mrems/H for Routinely Accessible Areas Project stage: Other AECM-86-0011, Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks1986-03-15015 March 1986 Responds to 850809 Request for Addl Info Re 850506 Application for Amend to License NPF-29,allowing for Installation of High Density Spent Fuel Racks Project stage: Request AECM-86-0176, Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl1986-06-0505 June 1986 Application for Amend to License NPF-29,changing Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks,In Response to NRC Concerns from Review of Util .Affirmation & Justification for Change Encl Project stage: Request ML20205T3631986-06-0505 June 1986 Proposed Changes to Tech Specs 3/4.7.9.1 & 5.6.3 Re Installation of High Density Spent Fuel Racks Project stage: Request ML20205T0671986-06-0909 June 1986 Revised Tech Spec Page 5-6 Re High Density Spent Fuel Racks Project stage: Other AECM-86-0179, Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks1986-06-0909 June 1986 Forwards Revised Tech Spec Page 5-6 Inadvertently Omitted from 860605 Submittal Re High Density Spent Fuel Racks Project stage: Other ML20203G5171986-07-14014 July 1986 Notice of Consideration of Issuance of Amend to License NPR-29 & Proposed NSHC Determination & Opportunity for Hearing to Revise Tech Spec Section 5.6, Fuel Storage, Allowing Increased Upper Containment Pool Capacity Project stage: Other AECM-86-0229, Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 8608181986-07-25025 July 1986 Forwards Responses to NRC Concerns Re Spent Fuel Decay Heat Capability & Associated Operating Procedures,Per 860716 Telcon.Requests That OL Amend for High Density Racks Be Granted on 860818 Project stage: Other ML20205D4401986-07-28028 July 1986 Notice of Violation from Insp on 860613-0714 Project stage: Other ML20205E8521986-08-12012 August 1986 Notice of Availability of Environ Assessment & Finding of No Significant Impact Re Application for Amend to License NPF-29,revising Tech Specs to Authorize Spent Fuel Pool Expansion Project stage: Other ML20205E8451986-08-12012 August 1986 Environ Assessment Re Mod of Spent Fuel Storage Racks at Plant Project stage: Other ML20212N0561986-08-18018 August 1986 Safety Evaluation Supporting Issuance of Amend 17 to License NPF-29 Project stage: Approval ML20212N0391986-08-18018 August 1986 Amend 17 to License NPF-29,revising Tech Spec Section 5.6, Fuel Storage to Allow Increased Upper Containment Pool Capacity & Increased Spent Fuel Storage Pool Capacity Project stage: Other ML17219A2551986-12-0505 December 1986 Safety Evaluation Re Util Fire Protection Deviation Requests from App a to Branch Technical Position Asb 9.5-1 & App R to 10CFR50.Listed Deviations Granted.Deviation Re Lack of Fire Rated Barrier Denied Project stage: Approval 1985-09-12
[Table View] |
Text
..
ENCLOSURE 1 NOTICE OF VIOLATION Mississippi Power and Light Company Docket No. 50-416 Grand Gulf Nuclear Station License No. NPF-29 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 13 -
July 14, 1986, a violation of NRC requirements was identified.
The violation involved procedural adequacy and adherence.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:
Technical Specification 6.8.1 requires that the applicable procedures recommended in Appendix A of Regulatory Guide 1.33 be established, implemented and maintained. Appendix A of Regulatory Guide 1.33 states that safety-related procedures and drawings should include instructions for the operation of control room heating and ventilation systems and instructions for the bypass of safety functions and jumper control. Drawing M-0049, Control Room HVAC System, and Administrative Procedure ( AP) 01-S-06-03, Control of Temporary Alterations, implement this requirement.
AP 01-S-06-3 requires the shift superintendent or designee to issue jumpers as required, make required entries in the jumper log and requires the operations assistant to sign the temporary alteration form following complete restoration of the temporary alteration. Drawing M-0049 specifies chlorine detector isolation valves 251F079 and Z51F080 be secured in the locked open position.
Contrary to the above:
1.
Surveillance procedure 06-IC-SZ51-SA-0001 was inadequate in that it did not specify that the chlorine detector isolation valves Z51F079 and Z51F080 be locked in the open position, as required by Drawing M-0049.
On June 30, 1936, the valves were fcund open but not locked open.
2.
On July 3, 1986, the following errors were noted in the temporary alteration forms and/cr jumper log:
a.
The jumper log did not list approximately twenty jumpers associ-ated with temporary alteration 85-0005.
b.
The jumper log stated jumper J247 was installed under temporary alteration 86-0023 instead of temporary alteration 86-0020.
c.
The cperations assistant's signature was entered on temporary alteration 86-0017 prior to tre restoration of the alteration.
8608190039 860728
{DR ADOCK 05000416 PDR
Mississippi Power and Light Company 2
Docket No. 50-416 Grand Gulf Nuclear Station License No. NPF-29 This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Mississippi Power and Light Company is hereby required to submit to this Of fice within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken' and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
FOR THE NUCLEA REGULATORY COMMISSION
/
/
/-
y be Roger D. Wa) r, Director Division of eactor Projects Dated at Atlanta,lyGeorgia this 28 day of Ju 1986.
1
.__