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Results
Other: 05000312/LER-1985-001, :on 850124,operations Personnel Found Hydrogen Monitor Sys Containment Isolation Valves Open.Caused by Tagging Inconsistency.Cover Panels added.Post-accident Sampling Sys Operation Procedure Revised, 05000312/LER-1986-020, Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-20, ML17341B657, ML20002B642, ML20023B820, ML20024A705, ML20137X776, ML20137X795, ML20151Y962, ML20203P855, ML20215C433, ML20215J722, ML20215L385, ML20215L569, ML20235P297
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MONTHYEARIR 05000312/19800131980-07-0202 July 1980 IE Insp Rept 50-312/80-13 on 800505-09.No Noncompliance Noted.Major Areas Inspected:Document Control Program,Onsite Review Committee Operations,Reactor Operator Requalification Program & IE Bulletin 79-27 Followup Project stage: Request ML20002B6421980-12-15015 December 1980 Forwards Commitments for Implementation of Items in NUREG-0737, Clarification of TMI Action Plan Requirements Project stage: Other ML17341B6571982-02-16016 February 1982 Forwards List of Procedures & Basis Used to Determine Whether or Not Radiological Effects Are Anticipated Re post-accident Analysis of Reactor Coolant Samples Project stage: Other ML20023B8201983-05-0202 May 1983 Forwards Resolution of Open Items Re NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, Per 830215 Evaluation & 830314 Telcon.No Significant Radiation Effects Anticipated Project stage: Other ML20024A7051983-06-17017 June 1983 Clarifies Info Provided in Re NUREG-0737,Item II.B.3 Post-Accident Sampling Sys (Pass), Per 830526 Request.Equipment Ordered to Allow Powering of Analyzer & Solenoid Valves from Reliable Source within 3 H Project stage: Other ML20137X7951985-11-22022 November 1985 Notice of Deviation from Insp on 850923-27 & 1007-15 Project stage: Other ML20137X7761985-11-22022 November 1985 Notice of Violation from Insp on 850923-27 & 1007-15 Project stage: Other ML20151Y9621986-02-0606 February 1986 Forwards post-accident Sampling Sys (PASS) Design Changes Implemented to Correct Capability Deficiencies.Pass Still Meets Requirements of NUREG-0737,Item II.B.3.Clarification of PASS Design Also Encl,Per 860127 Discussions Project stage: Other ML20141N8801986-03-13013 March 1986 Forwards Addl Info Re Changes to Facility post-accident Sampling Sys,Per 860218 Meeting W/Nrc & 860220 Telcon.Data Re Induced Gamma Radiation & Accuracy of Portions of Sys Affected by Mods Will Be Provided When Available Project stage: Meeting ML20155F3891986-04-11011 April 1986 Documents Commitment Made at 860218 Meeting W/Nrc to Demonstrate Operability of post-accident Sampling Sys Prior to Startup.Scope & Schedule for Test Will Be Provided in Time for NRC Comments to Be Considered Project stage: Meeting ML20203P8551986-04-30030 April 1986 Forwards Summary of Test for Chloride & Boron Analysis Employing Appropriately Diluted Test Matrix of post-accident Sampling Sys Equipment,Per 860313 Commitment.Addl Mods to Improve Sys Reliability & Maintainability Also Encl Project stage: Other 05000312/LER-1985-001, :on 850124,operations Personnel Found Hydrogen Monitor Sys Containment Isolation Valves Open.Caused by Tagging Inconsistency.Cover Panels added.Post-accident Sampling Sys Operation Procedure Revised1987-01-22022 January 1987
- on 850124,operations Personnel Found Hydrogen Monitor Sys Containment Isolation Valves Open.Caused by Tagging Inconsistency.Cover Panels added.Post-accident Sampling Sys Operation Procedure Revised
Project stage: Other ML20235P2971987-03-13013 March 1987 Rev 3 to Procedure AP.56, Core Damage Assessment Project stage: Other ML20215J7221987-05-0404 May 1987 Submits Addl Info Re Mods to post-accident Sampling Sys in Effort to Improve Sys Reliability & Provide Alternate Analyses for Boron,Chlorides & Reactor Bldg Atmosphere Radioisotopes.Criterion 10 of NUREG-0737 Satisfied Project stage: Other ML20215L5691987-05-0404 May 1987 Forwards,For info,bi-weekly Update of Working Copy Status Rept of 870427 post-accident Sampling Sys Mods Project stage: Other ML20215C4331987-06-0202 June 1987 Forwards Biweekly Update of Working Copy Status Rept of PASS Mods .Work Request Initiated to Repair Leak on Output of Filter F-496 (Er 131281) & Mgt Safety Review Committee Review Completed on 870526 Project stage: Other ML20215L3851987-06-16016 June 1987 Forwards 870608 Biweekly Update of Working Copy Status Rept of post-accidental Sampling Sys Mods,For Info Project stage: Other 05000312/LER-1986-020, Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-201987-07-0606 July 1987 Forwards Rev 3 to Procedure AP.56, Core Damage Assessment, for Inclusion in NRC Review of post-accident Sampling Sys. Procedure Revised to Correct Discrepancy Noted in LER 86-20 Project stage: Other 1986-03-13
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f APPENDIX B NOTICE OF DEVIATION Sacramento Municipal Utility District License No. DPR-54 P. O. Box 15830 Docket No. 50-312 Sacramento, California 95813 As a result of the inspection during the period of September 23-27, 1985, October 7-15, 1985, and from telephone discussions held on October 18, 21, 22, 23, and 24, 1985,- and in accordance with the NRC Enforcement Policy, 10 CFR Part 2, Appendix C, the following deviations were identified:
A.
In your letter RJR 83-512 of June 17, 1983 you stated:
"The District will commit to provide refresher training involving use of the PASS equipment for a sufficient number of designated equipment users to insure the availability of trained personnel to support post-accident sampling requirements. The frequency of such testing / training will be every six months 25%."
Contrary to the above, training and/or refresher training of users involving the use of the PASS equipment has not been provided since April 1984.
This is a deviation.
B.
In your letter RJR-84-343 of August 30, 1984 you stated:
...The District will submit a schedule by October 26, 1984, for either an in-house design and fabrication or the procurement of vendor supplied shields to be at the Rancho Seco site."
Contrary to the above, as of the time of this inspection, on September 27, 1985, a schedule for either procurement or designing and fabrication of the shields had not been made or determined.
This is a deviation.
C.
In your letter RJR-84-343 of August 30, 1984 you stated in Section III(i):
'"...All three of the above procedures will be reworked to address the recovery of the particulate and iodine media for transport to the analysis station under normal and accident conditions of low and high activity, respectively. The District proposes the proper completion of the three procedures by October 12, 1984."
Contrary to the above, as of the date of this inspection, September 27, 1985, procedures AP.305-24, " Reactor Building Air and Stack Samples,"
AP.305-26, ~" Auxiliary Building Air and Stack Samples" and AP.305-29, "Radwaste Service Area Vent Samples" do not address the recovery of particulate and iodine media for transport to the analysis station under accident conditions.of high activity.
This is a deviation.
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D.
In your letter RJR 84-343 of August 30, 1984, you stated in Section II(f),
"...At any rate, the district should be able to complete this research and development process and finish the installation of remote adjustment capability by September 28, 1984."
Contrary to.the above, as of September 27, 1985, the installation of the remote: adjustment capability had not started.
This is a deviation.
Please submit to this office within thirty days of the date of this notice a written statement or explanation regarding the above items,. describing corrective steps taken, the results achieved (or corrective steps that are planned), and the date when corrective action will be completed.
W. S A) / / A '
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Dated JW[ss A. Scaraso,' Director Division of Radiation Safety and Safeguards s_
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