ML20101F538

Revised Pages III-1 & VII-1 to 1995 Operations Annual Rept

ML20101F538
Person / Time
Site:	University of Missouri-Columbia
Issue date:	12/31/1995
From:	MISSOURI, UNIV. OF, COLUMBIA, MO
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ML20101F516	List: ML20101F512 ML20101F538
References
NUDOCS 9603260045
Download: ML20101F538 (4)

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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."

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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

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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