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 ML20238E9291987-09-0303 September 1987 Responds to 870731 Request for Schedule for Resubmittal of 860815 Response Re CRD Rod Position Indication Instrumentation.Engineering Evaluation Will Be Resubmitted within 120 Days of Proposed Meeting Project stage: Meeting ML20237D2251987-12-15015 December 1987 Summary of 871204 Meeting W/Util Re Licensee Latest Proposals for Licensing Actions Concerning CRD Mechanism Temp Requalification & Position Instrumentation.List of Attendees & Related Info Encl Project stage: Meeting 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 1986-08-22
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] Category:TEST REPORT
MONTHYEARML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML20245L5861989-07-31031 July 1989 CRD Partial Scram Test Results & Max Daily Temp Rept for Jul 1989 ML20246J2041989-05-0808 May 1989 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 51 for Period Ending 890505 ML20235N0611989-02-10010 February 1989 Interim Startup Rept 50 for Fort St Vrain Nuclear Generating Station,881106 - 890204.Informs That Reactor Did Not Operate Above 80% Power ML20154E9291988-08-0808 August 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 48 for Period Ending 880808 ML20196E1591988-05-31031 May 1988 CRD Partial Scram Test Results & Max Daily Temp Rept ML20151D0021988-05-10010 May 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 47 for Period Ending 880510 ML20148G9801988-03-21021 March 1988 CRD Partial Scram Test Results & Max Daily Temp for Feb 1988 ML20148A6391988-02-0909 February 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 46 for Period Ending 880209 ML20196B7961988-01-31031 January 1988 CRD Partial Scram Test Results & Max Daily Temp Rept, 880117-31 ML20148G8301987-12-14014 December 1987 Metallurgical Analysis of Components from Helium Circulator C-2101 ML20237A9681987-12-11011 December 1987 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 45 for Period Ending 871111 ML20235G8571987-08-13013 August 1987 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 44 for Period Ending 870813 ML20236G3021987-07-30030 July 1987 CRD Partial Scram Test Results & Max Daily Temp Rept, 870703-30 ML20207T3391987-02-14014 February 1987 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 42,Rept for Period Ending 870214 ML20207D3361986-12-10010 December 1986 Fort St Vrain Initial Approach to Power (B Series):Interim Rept 41 ML20215K6991986-08-17017 August 1986 Fort St Vrain Initial Approach to Power (B-Series) Interim Rept 40,Rept for Period Ending Aug 1986 ML20204F1161986-07-31031 July 1986 CRD & Orifice Assembly Parameter Trending Test Program ML20207G8871986-07-11011 July 1986 Destructive Exam of Fort St Vrain Fuel Test Element FTE-2 ML20198D0681986-05-14014 May 1986 Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test ML20136D0401985-12-20020 December 1985 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 37,for Period of 850822-1120 ML20137L1141985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-5 S/N:0001 ML20137L0971985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-4 S/N:0004 ML20137L1871985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-4 S/N:0003 ML20137L1631985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-5 S/N:0002 ML20137L1441985-08-26026 August 1985 Test Rept for Singe Channel Analog Isolator P/N:993:34 S/N:0001 ML20135B4741985-08-21021 August 1985 Fort St Vrain Initial Approach to Power (B-Series), 36th Startup Rept for 850522-0821 ML20128F8301985-05-21021 May 1985 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 35,Rept for Period Ending 850521 ML20100E3541985-03-15015 March 1985 Fort St Vrain Initial Approach to Power (B Series), Interim Rept 34 for Period Ending 850220 ML20112H4731985-01-24024 January 1985 NDE of 62 Fuel & Reflector Elements from Fort St Vrain Core Segment 3 ML20101L5031984-12-12012 December 1984 Fort St Vrain Initial Approach to Power (B Series), Interim Rept 33 for Period Ending 841122 ML20098F6581984-08-20020 August 1984 Initial Approach to Power (B-Series) Startup Test Rept, for Period Ending 840820 ML20092K6261984-06-19019 June 1984 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 31 for Period Ending 840522 ML20084R2711984-05-10010 May 1984 Moisture Monitor Injection Tests in Compliance W/Fort St Vrain Tech Spec Limiting Condition for Operation 4.9.2 ML20087M8931984-02-22022 February 1984 Initial Approach to Power Tests (B-Series), Interim Rept 30 for Period Ending 840222 ML20083P5551983-12-16016 December 1983 Test Rept:Thermal Properties of Facility Fuel Element 1-2415 ML20083B4981983-11-22022 November 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), for 830923-1122 ML20083P5351983-09-23023 September 1983 Test Rept:Tensile Properties of Facility Fuel Element 1-2415 ML20080J2381983-08-22022 August 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 28 for Period 830623-0822 ML20024B0411983-05-22022 May 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Startup Rept 27 for 830223-0522 ML20073J1811983-04-0808 April 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 26 for Period Ending 830222 ML20076H3961983-04-0404 April 1983 Visual Exam Results of Segment 2,Fort St Vrain Fuel Elements 1-2415,1-0172,2-2693,1-0108 & 5-0801 ML20073S3251983-02-22022 February 1983 Initial Approach to Power Tests (B-Series), Interim Rept 26 for Period Ending 830222 ML20028E7291983-01-11011 January 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 25 for 820923-1222 ML20023E0531982-10-21021 October 1982 Results of Pgx Graphite Surveillance,Fort St Vrain. ML20066A3811982-10-0707 October 1982 Initial Approach to Power Tests, Interim Rept 24 for Period Ending 820822 ML20064M7411982-09-20020 September 1982 Test Rept:Nondestructive Exam of Fsv Fuel Test Element FTE-1 ML20055B9861982-07-22022 July 1982 Initial Approach to Power Tests (B-Series),Interim Rept 23 for Period Ending 820522 A16764, Radiochemical Analysis of First Plateout Probe from Fort St Vrain High-Temp Gas-Cooled Reactor1982-06-30030 June 1982 Radiochemical Analysis of First Plateout Probe from Fort St Vrain High-Temp Gas-Cooled Reactor 1992-09-01
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l P-87273 ;
Attachment 1 I l
CONTROL R00 DRIVE PARTIAL SCRAM l TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT l
REPORT PERIOD- !
JULY 3, 1987 - JULY 30, 1987 t
l I
i Prephred by: eI 6 sew /
' R. L. ' Burrows !
Senior Plant Engineer I Approved by:
F . 'J
_ lx Novacheli )
lechnical/ Administrative l Services Manager ;
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l Public S?rvice Company of Colorado Fort St. Vrain Unit No. 1
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870B040199 870730 PDR ADOCK 05003267 :
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P-87273 l Attachment i 1 page 3 j l
I I. ABSTRACT j i
This report summarizes the partial scram test results af.d the j maximum ti8ily temperature of those control rods with motor I temperatures above 215 degrees Fahrenheit. It is prepared to !
satisfy the Fort St. Vrain Interim Technical Specification l Surveillance Requirement 4.1.1.A.1.a. The time period covered by j this report is July 3,1987 through July 30, 1987.
I II. BACKGROUND I Because proper operatien of the Control Rod Drive Mechanism .
(CRDM) is critical for safe operation of the reactor, a series of )
qualification tests were conducted over a one year time span to j demonstrate $ts capability. The motor temperature during these I tests varied between 200 degrees Fahrenheit and 230 degrees i Fahrenheit, and averaged 215 degrees Fahrenheit. A total of 130,000 jog cycles plus 1600 scrams was icgged during the final design testing, which is many times that enected over the normal life of a CRDM. The operating temperature of the CRDM is' limited by the trotor insulation which is rated for 272 degrees Fahrenheit ,
I to account for motor temperature rise, frictional torque j l
increase, and winding life expectancy. ^
1
- In order to monitor CRDM temperatures, Resistance Temperature l Devices (RTD's) are mounted on the closure piate, orifice valve motor plate, and CRDM motor as shewn on Figure 1. All CRDM's installed in the reactor are equipped with RTD's. Three recorders locatad in the control room record each of these temperat-ures for all 37 CRDM's. CRDM motor temperatures are alarmed at 212 degrees Fahrenheit and 247 degrees Fahrenheit.
CRDM motor temperatures 2.re monitored at least onue per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that they are less than 250 degrees Fahrenheit, which is a limiting condition for operation. If one or more CRDM motor temperature (s) is found to be greater than 215 degrees Fahrenheit during the daily surveillance, the motor temperature of all CRDM's exceeding 215 degrees Fahrenheit is recorded and a partial
. scram test is performed on the CRDM with the highest motor temperature once per 24 houes. These surveillance ensure that l
CRDM motor temperatures exceeding 215 degrees Fahrenheit do not degrade the CRDM's reliability to perform its design function when required.
P-87273 Attachment 1 l Page 2 III.
SUMMARY
OF RESULTS CRDM motor temperatures exceeded 215 degrees Fahrenheit for two intervals during this report period. The first interval was from July 3, 1987 through July 11, 1987. The second ,
interval was from July 17, 1987 through July 21, 1987. Since j the daily scram surveillance is performed only when CRDM motor !
temperatures exceed 215 degrees Fahrenheit, data is presented l for these two intervals only. l 1
The partial scram test results and maximum daily temperature ;
of those CRDM's with motor temperatures above 215 degrees !
Fahrenheit are presented on Table 1. The pertinent parameters presented are: reactor region involved, control rod position, maximum daily motor teinperature, extrapolated scram times j (surveillance value and Back EMF calculated val ue') and ;
starting acceleration. The control rod position is presented because of its relationship to available starting torque which affects the starting acceleration and extrapolated scram time calculated by surveillance. The surveillance extrapolated scram time is affected by control rod position because it is calculated using distance travelled versus time. Since the acceleration is slovar at lower contrcl rod positions, a ;
longer period of time is required to reach steady state speed. '
This longer acceleration period results in a decrease in I
distance travelled over a given period of time, and thereby indicating a longer extrapolated scram time. The extrapolated scram time calculated by the Back EMF program applies a correction factor to provide a projected full length scram time. Therefore, the surveillance scram times can only be compared for trends if the control rod position is approximately the same. The Back EMF calculated scram time is mote readily trended since the value should be independent of control rod position.
The starting acceleration values presente:1 represent those calculated by the Back EMF program. These values reflect the CRDM's freedom of rotation to accelerate to steady state soeed and therefore are considered to be valuable performance I
indicators. Two values are presented: The actual-acceleration measured during a scram from the indicated control rod position, and the projected acceleration, if the control rods were at the full out position (greater than 188 inches). If the control rod position is greater than 188 inches, no data is presented for a projected starting i acceleration since the actual and projected are the same. As indicated with scram times, the projected starting acceleration is more readily trended since the value should be independent of control rod position.
. .j l
i s
I P-87273 Attachment 1-Page 3 !
i IV. CONCi.USIONS The performance of CRDM's with motor temperatures in excess of 215 degrees Fahrenheit did not show any significant trends or .,
degradation during this report period. Therefore, it is '
{
concluded that CRDM motor temperatures exceeding 215 degrees Fahrenheit did nct degrade the CRDM's reliability to perform ,
its design function when required, i i
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OPubiicservice-16805 WCR 19 1/2, Platteville, Colorado 80651.
July.30, 1987 Fort St. Vrain Unit No. 1 P-87273 U.S. Nuclear Regulatory. Commission ATTN: Document Control Desk Washington, D.C. 20555 Attention: Mr. Jose A. Calvo Director, Project Directorate IV Docket No. 50-267
SUBJECT:
CONTROL R0D DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT
Dear Mr. Calvo:
The Fort St. Vrain Interim Technical Specifications (Surveillance Requirements, Section 4.1.1.A.1.a) require that a report be provided to the NRC at least once every 31 days when one or more Control Rod Drive (CRD) motor temperature (s) exceeds 215 degrees Fahrenheit. A report on the partial scram test' results and the maximum daily temperature of those CRD's with motor temperatures above 215 degrees Fahrenheit is included as Attachment 1 for your review.
We hope you will find this submittal responsive to your concerns. If you have any questions or comments, please contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely, 0.0. UAWw.
R. O. Williams Vice President Nuclear Operations R0W:RLB/bj Attachment cc: Regional Administrator, Region IV Attention: Mr. J. E. Gagliardo, Chief Reactor Projects Branch cc: Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain l.
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