Letter Sequence Request |
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Results
Other: ML20079Q405, ML20079Q414, ML20082F335, ML20093C080, ML20099J326, ML20099J334, ML20137L067, ML20137L073, ML20137N914, ML20141N187, ML20141N189, ML20203P944
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MONTHYEARML20079Q4141983-09-30030 September 1983 Safety Parameter Display Sys Program Plan, in Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737 Project stage: Other ML20082F3351983-11-0404 November 1983 Requests Info Re NRC Schedule for Preimplementation Review of Safety Parameter Display Sys.Nrc Review Needed to Enable Further Implementation of NUREG-0737,Suppl 1 Requirements Per Generic Ltr 82-33 Project stage: Other ML20079Q4051984-01-20020 January 1984 Forwards Safety Parameter Display Sys Program Plan & Responds to NRC Re Control Room Design Review in-progress Audit.Audit Proposed to Take Place During Wk of 840312 Project stage: Other ML20137L0731984-08-31031 August 1984 Rev 0 to Procedure EIP-24, Test Procedure for Performance & Isolation Testing of 1E Analog & Digital Isolators Project stage: Other ML20093C0801984-09-19019 September 1984 Informs That Safety Parameter Display Sys (SPDS) SAR Will Be Submitted by 841114.Preimplementation Audit Results Received 4 Months Later than Expected.Schedule for Submittal of SPDS Info Requested in NRC Will Be Provided Project stage: Other ML20099J3161984-11-13013 November 1984 Forwards Response to NRC 840914 Request for Addl Info Re SPDS Sar,Rev 0 to SAR, Fort St Vrain SPDS & Revised SPDS Program Plan Project stage: Request ML20099J3341984-11-13013 November 1984 Revised SPDS Program Plan Project stage: Other ML20099J3261984-11-15015 November 1984 Rev 0 to Fort St Vrain SPDS Sar Project stage: Other ML20141N1891984-12-0707 December 1984 Rev 2 to Procedure EIP-30, Isolator Circuit Differential High Voltage Fault Test Procedure Project stage: Other ML20107C1021985-01-31031 January 1985 Responds to 850131 Request for Addl Info Re SPDS Isolators. Description of Measures Taken to Protect Safety Sys from Electrical Interference Generated by SPDS Will Be Provided by Aug 1985 Project stage: Request ML20137L0671985-08-0101 August 1985 Rev 0 to Procedure PSCC-1-EIP-24, Test Procedure for Qualification of Fort St Vrain Electrical Isolation Sys for Public Svc Co of Co Project stage: Other ML20137L0561985-08-26026 August 1985 Forwards PSCC-1-EIP-24, Test Procedure for Qualification of Fort St Vrain Electrical Isolation Sys... & Rev 0 to EIP-24, Test Procedure for Performance & Isolation Testing..., Per NRC Request for SPDS Review Project stage: Request ML20137N9141985-09-0505 September 1985 Forwards Test Plan Used in Testing SPDS Isolation Equipment from Interference & Provides Action Taken Re Info Needed for NRC Review Project stage: Other ML20141N1871986-02-19019 February 1986 Forwards Response to 860103,14 & 15 Requests for Addl Info Re SPDS Project stage: Other ML20203P9441986-04-29029 April 1986 Clarifies to NRC Re Spds.Forwards Rev 2 to Procedure EIP-30, Isolator Circuit Differential High Voltage Fault Test Procedure Project stage: Other 1984-08-31
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Text
1.,
PublicService
.no s.,
Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 August 25, 1985
,s Fort St. Vrain 1
SEP - 31985 unit No. 1 P-85300 Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 Attn: Mr. Dorwin Hunter Docket No. 50-267
SUBJECT:
Safety Parameter Display System Safety Analysis Report
REFERENCES:
- 1) NRC Letter Johnson to Lee dated 9/14/84 (G-84355)
- 2) PSC Letter Warembourg to Johnson dated 7/19/84 (P-84372)
- 3) PSC Letter Warembourg to Johnson dated 11/13/84 (P-84487)
Dear Mr. Hunter:
Attached please find test plan and preliminary test report for Safety Parameter Display System isolation (SPDS). This letter also provides the action taken in regard to the information needed for staff review discussed in Reference 3, Item 7.C. and 7.D.
NRC requested "With regard to isolation devices between the SPDS and n
safety systems, provide the following information:"
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e
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..1 Item 7.C.
For each type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable fcr its application (s). This description should include the test configuration and how the maximum credible faults were applied to the devices.
ITEM 7.D.
Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e. open and short circuits).
Item 7.C.
is addressed by Attachments 1 and 2 to this letter.
Item 7.D. is addressed by Attachments 3 thru 7.
If you have any questions regarding this matter, please call Mr.
M.
H.
Holmes at(303) 571-8509.
Very truly yours, 0JY.fYw d wy D. W. Warembourg, Mandtjer Nuclear Engineering Division DWW/DW:pa Attachments cc: Mr. E. H. Johnson