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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
[Table View] |
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| ML20093K153 |
| Person / Time |
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| Site: |
Fort Saint Vrain  |
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| Issue date: |
07/16/1984 |
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| From: |
Warembourg D
PUBLIC SERVICE CO. OF COLORADO |
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| To: |
Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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| Shared Package |
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| ML20093K156 |
List: |
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| References |
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| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM P-84216, TAC-44443, NUDOCS 8407300466 |
| Download: ML20093K153 (2) |
|
Text
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public Service Company Cf Ccacudn>
gbl 16805 WCR 19 1/2, Platteville, Colorado 80651 C
July 16, 1984 Fort St. Vrain Unit #1 P-84216 g
?'f-}\\ll U W (2 %
Mr. E. H. Johnson, Chief J/!
Reactor Project Branch 1
(
R 23m U.,S. Nuclear Regulatory Commission j
S 611 Ryan Plaza Drive, Suite 1000 i------
Arlington, Texas 76011
SUBJECT:
Post Accidnat Sampling System Implatnentation REF:
- 1) P-84192, D. W. Warembourg to E. P. Johnson, dated July 2, 1984
Dear Mr. Johnson:
It has been brought to my attention that Reference 1 did not contain all of the information that is necessary in order for you to close NUREG-0737, Item II.B.3,
" Post Accident Sampling System".
In addition to the modifications made to our sampling system and i
procedure, a new RERP Implementing Procedure, RERP-CORE, " Core Damage Evaluation," was developed in order to give us a mechanism to evaluate core damage based on radionuclide information and other core parameters.
Issue 1 of RERP-CORE was effective June 1, 1984.
Mr. James Montgomery of your office is on controlled distribution for this procedure. As a courtesy, a copy of Issue 1 of RERP-CORE has been attached.
We feel that the modification to the post-accident sample collection system, the concomitant change to our sampling procedure, and the development of RERP-CORE combine to address your areas of concern 1
OOOkh OO PDR I l
s
-z-with respect to Item II.B.3, and request that you close this item.
If you have any further questions, please contact Mr. Ted Borst of my staff at (303) 571-7436, Extension 203.
Very truly yours, 4
$ 7Y Wenc Don W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW/dic Attachment cc: Borst T
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