Letter Sequence Other |
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Results
Other: ML20137N628, ML20138L801, ML20138Q922, ML20148Q761, ML20151P101, ML20154A545, ML20154A550, ML20196B796, ML20198D059, ML20198D068, ML20206P200, ML20212B732, ML20236G302
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MONTHYEARML20138L8011985-12-12012 December 1985
Discusses NRC 851115 Request Re Status of Licensing Issues, Util 851105 Clarification Re Schedule of CRD Mechanism Assembly Environ Qualification Testing & Util Re Tech Spec Upgrade Program Review Schedule
Project stage: Other
ML20138Q9221985-12-19019 December 1985
Informs of Inability to Meet 851230 Completion Date of High temp,300 F,Crd Mechanism Test & Preliminary Evaluation,Due to Difficulties,Including Orifice Valve on Mechanism.Final Rept Will Be Submitted by 860331
Project stage: Other
ML20151P1011985-12-27027 December 1985
Discusses long-term Action Re CRD Mechanism Position Indication Proposed by NRC Preliminary Rept Restart & Continued Operation of Fort St Vrain Nuclear Generating Station, Per
Project stage: Other
ML20137N6281986-01-30030 January 1986
Provides Preliminary Evaluation Test Results of High Temp, 300 F Test of CRD Mechanism Assembly,Per .Test Completed on 860122.Assembly Performed Required Operations of Scram & Drive Motor W/O Incident
Project stage: Other
ML20198D0681986-05-14014 May 1986
Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test
Project stage: Other
ML20198D0591986-05-16016 May 1986
Forwards 908813, Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test. No Failure of Assembly Component Experienced
Project stage: Other
ML20206P2001986-08-22022 August 1986
Ack Receipt of Transmitting Rept Entitled, Parameter Trending Test Program. Data from Rept Will Be Incorporated Into Listed Ongoing Licensing Actions
Project stage: Other
ML20212B7321986-11-30030 November 1986
Evaluation of Proposed CRD & Orifice Assembly 300 F Temp Limits,Fort St Vrain Nuclear Generating Station
Project stage: Other
ML20236G3021987-07-30030 July 1987
CRD Partial Scram Test Results & Max Daily Temp Rept, 870703-30
Project stage: Other
ML20196B7961988-01-31031 January 1988
CRD Partial Scram Test Results & Max Daily Temp Rept, 880117-31
Project stage: Other
ML20148Q7611988-04-0707 April 1988
Provides Proposed Plan for Requalification of CRD Mechanisms for Elevated Temps.Items for Consideration in Temp Requalification Plan for CRD Mechanisms Listed
Project stage: Other
ML20154A5501988-04-28028 April 1988
Temp Prediction for CRD Mechanism Motors
Project stage: Other
ML20154A5451988-04-28028 April 1988
Integrated Sys Study of CRD Mechanism Rod Position Instrumentation
Project stage: Other
ML20154A5381988-05-0606 May 1988
Forwards Rev B to EE-12-0013, Integrated Sys Study of CRD Mechanism Rod Position Instrumentation & Temp Prediction for CRD Mechanism Motors, Per 871204 Meeting
Project stage: Meeting
1986-05-16
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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 May 16, 1986 Fort St. Vrain Unit No. 1 P-86374 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
CRDM Assembly
REFERENCES:
- 1) PSC Letter, Lee to Johnson, dated January 30, 1985 (P-85032)
- 2) PSC Letter, Warembourg to Butcher, dated November 5, 1985 (P-85380)
- 3) PSC Letter, Brey to Berkow, dated December 12, 1985 (P-85463)
- 4) PSC Letter, Warembourg to Berkow, dated December 19, 1985 (P-85478)
- 5) PSC Letter, Warembourg 8605230125 060516 to Berkow, dated PDR ADOCK 0500 7
January 30, 1986 P
(P-86071)
Dear Mr. Berkow:
PSC has committed to perform a high temperature (300 degrees Fahrenheit) test of a CRDM assembly, and to advise the NRC of the results of those tests (References 1 and 2). The NRC was advised of the preliminary results of the test in Reference 5.
d l], -
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P-86374 Page 2 May 16, 1986 This letter fulfills our commitment to submit a final test report (copy attached) on the 300 degree Fahrenheit high temperature test on a CRDM assembly.
The actual testing was completed on January 22, 1986, and as indicated in our preliminary report, the CRDM assembly performed the required operation of scram, operation of the CRD drive motor, and operation of the orifice valve drive motor, without incident.
The position indication switches and potentiometers were monitored and functioned throughout the test. No failure of any CRDM assembly component was experienced.
If you have any questions concerning this subject, please contact Mr.
M.H. Holmes at (303) 480-6960.
Very truly yours, b /Y /YM u &
D. W. Waremboug, M eager Nuclear Engineering Division DWW/JRR:jmt Attachment i
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