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Category:ANNUAL OPERATING REPORT
MONTHYEARML20207A6981998-12-31031 December 1998 Reactor Operations Annual Rept for 980101-1231, for Univ of Missouri Research Reactor Facility.With ML20203L0531997-12-31031 December 1997 Reactor Operations Annual Rept,970101-1231, for Univ of Missouri Research Reactor Facility ML20210R2701997-07-31031 July 1997 Univ of Missouri Research Reactor Operations Monthly Summary,July 1997 ML20138Q6601996-12-31031 December 1996 Reactor Operations Annual Rept for 1996 ML20100M7821995-12-31031 December 1995 Univ of Mo Research Reactor Reactor Operations Annual Rept Jan-Dec 1995 ML20101F5381995-12-31031 December 1995 Revised Pages III-1 & VII-1 to 1995 Operations Annual Rept ML20080M4281994-12-31031 December 1994 Univ of Mo Research Reactor Operations Annual Rept,Jan-Dec 1994 ML20063M2041993-12-31031 December 1993 Operations Semiannual Rept Jul-Dec 1993 ML20059M4791993-12-31031 December 1993 Research Reactor,Univ of Missouri - Columbia,1992 Annual Rept ML20056G0741993-06-30030 June 1993 Univ of Missouri Research Reactor Operations Annual Rept 1992-1993, Covering Period Jul 1992 - June 1993 ML20114C6751992-06-30030 June 1992 University of Missouri Research Reactor Facility Operations Annual Rept,1991-1992 ML20082L4171991-06-30030 June 1991 Univ of Mi Research Reactor Operations Annual Rept Jul 1990 - June 1991 ML20059C5051990-06-30030 June 1990 Univ of Missouri Research Reactor Operations Annual Rept, Jul 1989 - June 1990 ML20246B1991989-06-30030 June 1989 University of Missouri Research Reactor Operations Annual Rept,Jul 1988 - June 1989 ML20151Q9221988-12-31031 December 1988 Univ of Missouri Research Reactor Operations Annual Rept 1987-1988 ML20237K5721987-06-30030 June 1987 Operations Annual Rept 1986-1987 ML20209E5431986-08-31031 August 1986 Reactor Operations Annual Rept,Aug 1986 ML20212L9251986-06-30030 June 1986 Univ of Missouri Research Reactor Annual Rept,Jul 1985 - June 1986 ML20134M9291985-06-30030 June 1985 Univ of Missouri Research Reactor Annual Rept,1984-85 ML20097F4771984-12-31031 December 1984 Univ of Missouri Research Reactor Annual Rept 1983-1984 ML20096C5621984-06-30030 June 1984 Annual Rept 1983-84, for Jul 1983 - June 1984 ML20084D2991984-03-31031 March 1984 Progress Rept for Univ of Missouri - Rolla Nuclear Reactor Facility,Apr 1983 - Mar 1984 ML20080D3211983-08-31031 August 1983 Annual Rept,Jul 1982 - June 1983 ML20076C6691983-08-19019 August 1983 Univ of Missouri Research Reactor Facility,Reactor Operations Annual Rept,Jul 1982 - June 1983 ML20065B8051983-02-16016 February 1983 Annual Rept,Jul 1981 - June 1982 ML20063F8881982-08-31031 August 1982 Reactor Operations Annual Rept,Jul 1981-June 1982 ML19254B4121979-08-31031 August 1979 Annual Operating Rept for Jul 1978-June 1979 ML20062H3171978-06-30030 June 1978 Univ of Mo Research Reactor (MURR) Annual Rept, Jul 1977 - June 1978 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212D4471999-09-20020 September 1999 Safety Evaluation Supporting Amend 31 to License R-103 ML20211B1671999-07-13013 July 1999 Special Rept on 990614 Re Test of Scram Set Point of Two of Five Low Primary Coolant Flow Safety Sys Channels.Caused by Trip Set Points Being Too Close to TS Limits.Compliance Procedure 23 Will Be Revised ML20206A9681999-04-21021 April 1999 Revised Page 4 to MURR QA Plan ML20202G9051998-12-31031 December 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Dec 1998 ML20207A6981998-12-31031 December 1998 Reactor Operations Annual Rept for 980101-1231, for Univ of Missouri Research Reactor Facility.With ML20202G9171998-11-30030 November 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Nov 1998 ML20202G9271998-10-31031 October 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Oct 1998 ML20154M3301998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Univ of Missouri Research Reactor ML20154M3401998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Univ of Missouri Research Reactor ML20236Y5941998-08-0606 August 1998 Special Rept:On 980706,operator Noted That One Sample Listed as Inches Long on Loading Sheet,Only 2 Inches Long.Errors Constitute Observed Inadequacy in Implementation of Administrative & Procedural Control.Procedures Revised ML20154M3431998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Univ of Missouri Research Reactor ML20236S1711998-07-15015 July 1998 Ro:On 980615,large & Rapid down-shift on Three Different Meter Indications from One Ni Drawer Was Discovered.Caused by Failed Preamplifier in Wide Range Amplifier Subject Ni Drawer.Replaced Cabling,Detector & Preamplifier ML20154M3651998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Univ of Missouri Research Reactor ML20154M3731998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Univ of Missouri Research Reactor ML20154M3841998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Univ of Missouri Research Reactor ML20246P9931998-03-31031 March 1998 Monthly Operating Rept Summary for Mar 1998 for Univ of Missouri Research Reactor ML20246Q0231998-02-28028 February 1998 Monthly Operating Rept Summary for Feb 1998 for Univ of Missouri Research Reactor ML20203H4271998-02-26026 February 1998 Safety Evaluation Supporting Amend 30 to License R-103 ML20246Q0201998-01-31031 January 1998 Monthly Operating Rept Summary for Jan 1998 for Univ of Missouri Research Reactor ML20198K9441998-01-0808 January 1998 Special Rept:On 971209,reactor Shutdown by High Power Scram Initiated by Wide Range Monitor of Nuclear Instrument Sys. Caused by Unanticipated Positive Reactivity Insertion. Reflector Sample Opened & Inspected ML20203L0531997-12-31031 December 1997 Reactor Operations Annual Rept,970101-1231, for Univ of Missouri Research Reactor Facility ML20202H4091997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Univ of Mo Research Reactor ML20197D2751997-12-15015 December 1997 Ro:On 971026 & 1106,slight Elevation of Fission Products Were Detected in Primary Coolant Water Analyses.Caused by Slight Fabrication Flaw in Element MO-460.Surveillance of Bwx Technologies Fabrication Techniques Will Be Increased ML20202H3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Univ of Mo Research Reactor ML20202J1151997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Univ of Missouri Research Reactor ML20202J1201997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Univ of Missouri Research Reactor ML20211B2871997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Univ of Missouri Research Reactor ML20210R2701997-07-31031 July 1997 Univ of Missouri Research Reactor Operations Monthly Summary,July 1997 ML20196G8891997-07-15015 July 1997 Special Rept:On 970616,scram Setpoint for Low Flow Scram for Heat Exchanger 503A Leg Was 25 Gpm Below TS Limit.Caused by Drifting of Setpoint of Vutronik Monitor Switch DPS-928A. Adjusted Trip Setting & Retested Trip Setting ML20149L3761997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Univ of Mo Research Reactor ML20141H6451997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Univ of Mo Research Reactor ML20141H6581997-04-30030 April 1997 Monthly Operating Rept for April 1997 for Univ of Missouri ML20141H6691997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Univ of Missouri ML20136D7211997-03-0606 March 1997 Safety Evaluation Supporting Amend 29 to License R-103 ML20141H7421997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for University of Missouri Research Reactor ML20141H6421997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Univ of Mo Research Reactor ML20141H7001996-12-31031 December 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for Dec 1996 ML20138Q6601996-12-31031 December 1996 Reactor Operations Annual Rept for 1996 ML20141H7221996-10-31031 October 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for Oct 1996 ML20116E2621996-07-30030 July 1996 Ro:On 960701,emergency Generator Shutdown on High Coolant Temp.Caused by Sheared Water Pump Shaft.Replaced Defective Pump ML20141H6781996-06-30030 June 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for June 1996 ML20149L3721996-05-31031 May 1996 Monthly Operating Rept for May 1996 for Univ of Mo Research Reactor ML20117L1091996-05-13013 May 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Apr 1996 ML20117L1001996-03-31031 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Mar 1996 ML20117L0951996-03-13013 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Feb 1996 ML20117L0841996-03-0606 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Jan 1996 ML20100J3991996-02-22022 February 1996 Ro:On 960123,reactor Was Shut Down by Manual Scram When Console Operator Determined That Regulating Blade Was Inoperable.Caused by Seized Bearing on Gearbox Input Shaft. Bearing Replaced ML20097J4391996-01-26026 January 1996 Special Rept:On 951227,reactor Shutdown Occurred Due to Reactor in Operation W/Regulating Blade in Degraded Condition.Replaced Dowel Pin ML20101F5381995-12-31031 December 1995 Revised Pages III-1 & VII-1 to 1995 Operations Annual Rept ML20100M7821995-12-31031 December 1995 Univ of Mo Research Reactor Reactor Operations Annual Rept Jan-Dec 1995 1999-09-20
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. - SECTION IH REVISIONS TO THE HAZARDS
SUMMARY
REPORT 1 January 1995 through 31 December 1995 During the past year, Reactor Operations staff has made a concerted effort to update and make corrections to the Hazards Summary Report. These changes were reviewed by licensed staff and by members of the Safety Subcommittee and have been determined not to involve a change in Technical Specifications or an unreviewed safety question as defined in 100FR50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1,1965)
Original HSR, page 3 6, Section 3.2.6, paragraph 1, sentence 1:
Delete 'The pneumatic tube system components entering the reactor containment consist of nine lines, . ."
Reolace with: 'The pneumatic tube system components entering the reactor containment consist of eight lines, . .
Original HSR, page 3 5, Section 3.2.7, paragraph one, sentence 3:
Delete- "This 16 inch pipe has a 12 inch collar . . . ."
Reolace with: "This 16 inch pipe has a 12 inch long collar . . . ."
Original HSR, page 3 7, Section 3.2.8, paragraph one, sentences 3 through end of section:
(This revision also replaces 1968 revision.)
Delete Sentence 3 through end of section.
Reolace with:
" Located within the containment building on the fifth level in the mechanical equipment space (Figure 3.3)is an emergency air compressor. This emergency air compressor normally
" rides" on the main air supply line until there is a drop of pressure in the main air line to less than 85 psi. At that time the srnali emergency air compressor comes on and a check valve closes ofrall of the compressed air system external to the containment building. This emergency air compressor, under these circumstances, carries the air requirements within the f containment building. The compressed air supplied by one or the other of these two separate systems is maintained in accumulator tanks located on the compressor and goes from these tanks by means of a piping system to a pressure reducing and regulation system to provide the i motive force for the inflated gaskets, l This system is equipped with check valves and automatic starters such that if there is a failure or loss of compressed air from the main unit, the emergency air system will come on and carry the inflatable gaskets and any other air controlled devices associated with the reactor.
( The emergency air compressor is also connected to the emergency diesel generator in the event of electrical power failure."
l 9603260045 960321 El PDR ADOCK 05000106 R pop
l Original HSR, page 3 9, Section 3.3, paragraph 2, sentence 1: , ,
Delete 'The containment system integrity is compromised only during reactor shutdown and i only then . . . ."
Renlace with: "The containment system integrity is compromised only when the reactor is secured and only then . . . ."
Original HSR, page 311, Figure 3.1; 19901991 Annual Report Revision: )
4 Reolace with: Updated Figure 3.1-Basement Level (MURR Dwg # 2269, Sheet 1 of 3, dated 10/25/93)
Original HSR, page 312, Figure 3.2; 1990-1991 Annual Report Revision:
Reolace with: Updated Figure 3.2--Grade Level Plan (MURR Dwg #2269, Sheet 2 of 3, dated l 10/25/93)
Original HSR, page 313, Figure 3.3:
Reolace with: Updated Figure 3.3--Third, Fourth and Fifth Level Plan (MURR Dwg #2269, Sheet 3 of 3, dated 10/25/93)
- Original HSR, page 314, Figure 3.4
Reolace with: Updated Figure 3.4-North and East Elevations (dated 1/3/95)
Original HSR, page 315, Figure 3.5:
- Reolace with
- Updated Figure 3.5--South and West Elevations (dated 1/3/95)
Original HSR, page 318, Figure 3.8; 197172 Annual Report Revision:
Reolace with: Updated Figure 3.8-Cooling Tower Building at Grade Plan (1/3/95) l Original HSR, page 41, 'Section 4.1, paragraph 2, sentence 1:
Delete- "The fueled region is an annulus of a right circular cylinder with a nominalinner .
radius of 2.77 inches and an outer radius of 5.81 inches." l l
} Reolace with: 'The fueled region is an annulus of a right circular cylinder with a nominal inner radius of 2.67 inches and an outer radius of 5.88 inches."
4 Original HSR, page 4 2, Section 4.2, paragraph 2, sentence 2:
Delete: "The overall radial dimension of an assembly is 3.28 inches."
Reolace with: " The overall radial dimension of an assembly is 3.21 inches (as determined from radial length from inside ofinner roller to outside of outer roller)."
Original HSR, page 4 2, Section 4.2, paragraph 3,last sentence:
Delete "The radius to the innermost plate is 2.77 inches and to the outermost plate is 5.76 inches."
Reclace with: "The nominal radius to the innermost plate is 2.77 inches and to the outermost plate is 5.76 inches."
III-2 4
l
[.: _ _
SECTION VII REACTOR PHYSICS ACTIVITIES 1 January 1995 through 31 December 1995
- 1. Fuel Utilization: During the period 1 January 1995 through 31 December 1995, the following elements reached feasible burn-up and were retired:
{
[ Serial Number Final Core Date Last Used MWD MO-377 95 9 03-06-95 125.58 MO-379 95-9 03-06-95 125.58
[ MO-382 95-23 06-05-95 112.67 MO-384 95-23 06 05-95 112.67 MO-385 95-24 06-19-95 119.02
[ MO-386 95-18 05-01-95 121.57 MO 387 95-24 06-19-95 119.02 MO-388 95-18 05-01-95 121.57
{ MO-389 95-24 06-19 95 112.75 MO 390 95-20 05-15-95 123.47
[ MO-391 95-24 06-19-95 112.75 L MO-392 95-20 05-15-95 123.47 MO-393 95-52 12-04-95 123.26 MO-394 95 12 03-27-95 129.62
[ MO-395 95-52 12-04-95 123.26 MO 396 95-12 03-27-95 129.62 MO-397 95-39 09 27-95 122.15
( MO-398 95-53 12-11 95 118.75 MO-399 95-39 09-27-95 122.15 MO-400 95-53 12-11-95 118.75
( MO-402 MO.404 95-32 95-32 08-07-9~; 117.97 08 07 95 117.97 MO-405 95-42 10-09-95 116.85 MO-407 95-42 10-09-95 116.85 Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with four new elements or fewer as conditions dictate. A core designation consists of eight fuel elements of which only the initial critical fuel element serial numbers are listed in the following table of elements in service 31 December 1995. To increase operating
[ efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.
[
VII-1 L
~'
l ,
l Fabrication Initial Core Initial Serial Number Core Number Load Number Ooeratine Date MO-422 68 95-1 01-03 95 MO-424 69 95 1 01-03-95 MO-425 69 95-4 01-23-95 MO-426 69 95 9 02-27 95 MO-427 69 95-4 01-23-95 MO-428 69 95 9 02-27-95 MO-429 69 95-14 04-03-95 MO-430 69 95-20 05-20-95 MO-431 70 95 14 04-03 95 l
.MO-432 70 95-20 05-20 95 MO-433 70 95-22 05-22-95 MO-434 70 95 24 06-06-95 MO-435 70 95-22 05 22-95 MO-436 70 95 24 06-06-95 MO-437 70 95 30 07-17 95 MO-438 70 95-32 07-31-95 MO-439 71 95 30 07-17 95 MO-440 71 95-32 07 31-95 MO441 71 95 39 09-18 95 MO-442 71 95 42 10-02 95 l
MO-443 71 95-39 09 18 95 MO-444 71 95 42 10-02-95 MO-445 71 95-46 10-30 95 MO-446 71 95-52 11-27 95 MO-447 72 95-46 10-30-95 MO-448 72 95 52 11-27-95
- 2. Fuel Shipments: Thirty-two spent fuel elements were shipped from MURR to Savannah River Site, Aiken, South Carolina. The identification numbers of i these elements are:
MO-321 M O-357 MO-365 MO-373 MO-322 MO-358 MO-366 MO-374 MO-347 MO 359 MO-367 MO-375 MO-349 MO 360 MO-368 MO-376 MO-352 M O-361 MO-369 MO 378 MO-354 MO-362 MO-370 MO380 MO 355 MO 363 MO 371 MO-381 MO-356 MO-364 MO-372 MO-383 VII 2