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MONTHYEARML20085N4931983-10-28028 October 1983
Comments on Three Unresolved Criteria Re NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, Per . Procedure to Estimate Extent of Core Damage Based on Radionuclide Concentrations Will Be Completed by 840601
Project stage: Other
ML20093K1571984-06-0101 June 1984
Issue 1 to Radiological Emergency Response Planning Implementation Procedure RERP-CORE, Core Damage Evaluation
Project stage: Other
ML20090E6421984-07-0202 July 1984
Confirms Installation of post-accident Sampling Sys & Sys Operability as of 840601.Procedure for Obtaining post- Accident Samples of Primary Coolant Is Contained in Health Physics Procedure (HPP)-14, Analytical Instrumentation
Project stage: Other
ML20093K1531984-07-16016 July 1984
Forwards Issue 1 to Radiological Emergency Response Planning Implementing Procedure RERP-CORE, Core Damage Evaluation, to Close NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, Per 840702 Submittal
Project stage: Other
ML20132G5221985-07-0808 July 1985
Forwards Supplemental Safety Evaluation Re Util Response to NUREG-0737,Item II.B.3, Post-Accident Sampling Sys. Eight of Nine Criteria Met.Comments on Resolving NRC Concerns Requested within 60 Days of Ltr Date
Project stage: Approval
IR 05000267/19850231985-09-20020 September 1985
Insp Rept 50-267/85-23 on 850826-30.No Violation or Deviation Noted.Major Areas Inspected:Maint,Operational Safety Verification & Periodic & Special Repts
Project stage: Request
ML20132E2051985-09-20020 September 1985
Requests 60-day Extension for Response to Sser & NRC 850708 Request for Revised Procedure for Estimating Extent of Core Damage Per NUREG-0737,Item II.B.3, Post-Accident Sampling Sys
Project stage: Request
ML20133D8521985-09-30030 September 1985
Provides Update on Util Environ Qualification of post- Accident Monitoring Equipment.Util Unable to File Documentation by 850930.Qualification Will Continue Pending NRC Response on Acceptability of Parameters & Equipment
Project stage: Other
ML20137H6401985-11-25025 November 1985
Advises That Ga Technologies,Inc Has Confirmed That Core Damage Estimate Obtained from Xe-133 Concentration Can Be Independently Confirmed by Use of Kr-88 in Primary Coolant. Procedure RERP-CORE Will Be Revised by 851231
Project stage: Other
ML20140B3021986-01-14014 January 1986
Supplemental Safety Evaluation Supporting Util Addl Info Re Compliance w/NUREG-0737,Item II.B.3, Post-Accident Sampling Sys, (Criterion 2)
Project stage: Approval
ML20140B2891986-01-14014 January 1986
Forwards Supplemental Safety Evaluation on Util Addl Info Re Compliance w/NUREG-0737,Item II.B.3, Post-Accident Sampling Capability. Proposed post-accident Sampling Sys (Criterion 2) Acceptable.Item Resolved
Project stage: Approval
1985-11-25
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_.O P-85328 Regional Administrator Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Attn: Mr. Darwin R. Hunter Docket No. 50-267
SUBJECT:
Post Accident Sampling System
REFERENCE:
(1) NRC Letter dated July 8, 1985 Johnson to Lee (G-85260)
Dear Mr. Hunter:
In a letter dated July 8,1985 (Reference 1) the NRC requested that Public Service Company of Colorado.(PSC) provide comments on resolution of NRC's concerns about the Fort St. Vrain (FSV) Post Accident Sampling System.
NRC indicated that PSC must revise the FSV procedure for estimating the extent of core damage to be consistent with NUREG-0737, Item II.B.3 before this procedure will be acceptable to NRC.
In the Supplemental Safety Evaluation enclosed with Reference 1, NRC stated that the procedure PSC would use to estimate core damage is not acceptable because it is based solely on the Xe-133 concentration in the reactor coolant. PSC is now working with GA Technologies to evaluate the possibility of implementing a backup sampling method based on concentrations of other volatile radionuclides or other gaseous species.
This research is involving more time than originally anticipated.
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. As discussed with Mr. P. Wagner on September 12, 1985, PSC will.need an additional 60 days to complete our research and provide NRC with the information requested in Reference 1.
Should you have any questions concerning this matter, please cont ~act Mr. M.H. Holmes at (303) 571-8409.
Very truly yours, 2m.$odmf YIAL Jack W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:KP:jrp i
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