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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 O PublicService o.
Company of Colorado P.O. Box 840 Denver, CO 80201 -0840 (303) 571-7511 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 l
l September 30, 1985 Fort St. Vrain Unit No. 1 P-85347 A M @ M 0 W [F> %
Regional Administrator Region IV I
OCT - 21985 l!
U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 j
Arlington, Texas 76011 ATTN: Mr. Dorwin Hunter Docket No. 50-267
SUBJECT:
Environmental Qualification of Post Accident Monitoring Equipment
REFERENCE:
(1) PSC Letter dated February 28, 1985 Warembourg to Johnson (P-85065)
(2) PSC Letter dated March 28, 1985 Warembourg to Johnson (P-85112)
(3) PSC Letter dated September 24, 1985 Walker to Chilk (P-85334)
Dear Mr. Hunter:
The purpose of this letter is to provide an update on PSC's efforts to qualify Fort St. Vrain's (FSV) Post Accident Monitoring (PAM) equipment as identified in Reference 1.
By letter dated March 28, 1985 (Reference 2) PSC committed to a date of September 30, 1985 as the date by which all documentation of the qualification of FSV's Regulatory Guide 1.97 Category I and II equipment would be in place in our Environmental Qualification (EQ) files.
However, our EQ files are being totally reformatted, as described in Reference 3.
Therefore, PSC will be unable to have the qualification documentation for the FSV PAM equipment in our files by September 30, 6
1985. The auditable EQ files for this equipment will be implemented i
on the same schedule as the files for the FSV equipment required for 6
forced circulation cooling.
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DR ADOCK 050 7
o no
_2 PSC intends to continue to qualify the equipment identified in Reference 1 pending a response from NRC on the acceptability of the FSV PAM parameters and equipment.
If there are any questions on this matter, please contact Mr. M.'H.
Holmes at-(303) 571-8409.
Very truly yours, to tv yYwJnw D. W. Warembourg, Manger Nuclear Engineering Division DWW/SM:km i
- w..
