ML20085H081

Monthly Operating Rept for June 1967 for Saxton Nuclear Experimental Corp

ML20085H081
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Site:	Saxton File:GPU Nuclear icon.png
Issue date:	06/30/1967
From:	SAXTON NUCLEAR EXPERIMENTAL CORP.
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SAXTON UUCLEAR EXPERIMENTAL CORPOPlTigi operations Report for June 1967

1. GMmi. L At the beginning of this report period preparations were being made to remove the reactor vessel head to investigate the malfunction of control rod No. 5 and/or its drive mechanism. On June 2nd the reactor vessel head was removed and stored on the operating floor.

On June 5th it was shown by making an inverse count rate plot that the boron concentration, 2037 pp::, in the storage well was adequate tc hold the reactor suberitical for the control rod configuration - Nos.1, 3, 4, 6 and 2 fully withdrawn and Nc. 5 fully inserted.

On June 7th a lifting force was applied to the top of control rod No. 5 The force was applied with a manually operated gear hoist which was suspended from a stationary support erecued over the storage well. The ccatrol rod became free when a force of 162 pounds was applied with the hoisi.. This force was in addition to that applied to the control rod with the drive mechanism. Once the control rod was free to move it was raised to 40 inches and then lowered to cero inches with the hoist.

Mille the weight of the control rod was on the hoist the drive rod bundle was raised to 9 inches and then lowered to zero inches with the drive mechanism. These operations gave evidence that the obstruction which had blocked the movament of the control rod had been dislodged.

While, control rod No. 5 was still attacned to the hoist, ali rix control l

rods were positioned at approximately 8 inches from the bottom. Control rod No. 5

[ and No. 2 were then wit) drawn to 40 inchee. An inverse count rate plot made during the rod movements ahowea the reactor to be suberitical with the two highest worth rods fully withdrawn. This procedure verified that the shutdown reactivity requirement for the removal of any two control rods from the core was met.

In the days that followed a special ma:Lntcaance .1truction was carried out l to inspect control rod No. 5 and adaace.nt fuel assemblies with the underwater l periscope for mechanical defects, and to verify the proper operation of the drive mechanism.

The upper core barrel with instrument frame was removed from the reactor vessel on June 9th and was placed on its storage platform in the storage well.

The three fuel assemblies occupying core positions It-3, D-4 and C-4 l adjacent to control rod No. 5 were removed from the core on June 13th. Each assemb3y l

was inspe:ted with the underwLter periscope and then placed in the fuel storage rack. No defects were found.

On June 14th control rod No. 3 was carefully lifted from the reactor vessel and was transferred to the underwster periscope for inspection. The rod was found to

be nomal in all respects except for a vertica) line of gouges on one side of one blade l

of the solid stainless stcel top adapter of the absorber section. The uppermost and longest of the gouges was estimated to be 1/8" wide, 1/16" deep and 3/8" long.

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$NEC Operation 3 Report for Jun e 1967 . . . _ . . . #2 It was detenmined, that when the control rod was in its fully inserted position in the reactor vessel, the gouged area on the adapter wau at the same general level as the upper control rod guide block which is mounted on the underside of the upper core support plate. Upon completion of the underwater inspection the cor. trol rod was placed in the fuel storage rack.

The drive mechanima for control rod No. 5 was exercised on June 16th.

The drive rod was raised and lewered in inercoents of 10 inches over its full range of travel 40 inches. The performance of the drive mechanism was normal.

Tne fuel aosenbly occupying cor cosition C-3, adjacent to control rod No. 5, was removed frcet the reactor vessel and inspected with the underwcter periscope on June 16th. No defects were observed. The fuel assembly was placed in the storage rack.

An Inspection Engineer for the Materials Testing laboratory of Pittsburgh, Pa. was on the site on June 21st. All 36 reactor vessel head studs were ultrasonically inspected. Uine of the same studs were magnetic particle inspected. All 36 nuts for the he.d stuan were altrasonically inspected. The hook for the 20 ton rotary crane and the hook for the refueling crane in the containment vessel were magnetic narticle inspe cted. All items inspected were found to be free of cracks and discontinuities of the types th&t can be located by the inspection methods used.

On June 22nd the water in the storage well was lowered to grating level.

The plugs over the two reactor vessel material surveillance specimens capsules were recoved and with the aid of special lighting it was observed that the capsules were still ia the retaining baskets mounted on the thermal shield.

Tne water level was raised to six feet above the reactor vessel flange and from the vant ' ta point of a scaffold crected over the 2 eactor vessel the visible areas of the lower 'upport plate were inspected for abnonaalities and foreign material.

None were seen, ae bottou guide block for control rod No. 5 was viewed with a borescope. No detects were observed.

Also on June 22nd .five new single plutonium enriched fuel rods were received from the Westinghouse Fuel Fabrication facility at Cheswick, Pa.

On June 23rd the upper core support plate and the accessible eurfaces of the upper guide block for control rod No. 5 were inspected with a borescope. Some scoring vas visible on the vsrtical edge of the guide block that was directly opposite to the gouged area on the centrol rod adapter when the control rod was fully inserted -ia the core. The gouges on the control rod adapter and the scoring seen on the upper guide block were evidence enough to conclude tnat the immobilization of control rod No. 5 was causea by a small piece of hard material, origin and present location unknown, falling into the narrov opening between the upper core support plate and the control rod adapter and becoming wedged between the adapter and the upper guide block. No significant damage was done in freeing the control rod.

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L Aeration; Henort for Jur e_ . %? _# . , ' , . , #3 The four 9x9 fuel assemblies (C-3, C-4, D-4 and D-3) and control rod No. 5 were removed from the storage rack and returned to the reactor vessel on June 26th.

The compcnents were transferred in the reverse sequence of that in which they were removed from the core. Control rod No. 5 was installed in its slot with an orientation tnat differed 180 from that which it fonnerly had.

Centrol rod Na. 2 was removed from the reactor vessel and was inspected with the underwater periscope. Some heavy rubbing marks were seen on the cladding of twc rods in the upper follower section and what appasred to be a defect in the cladding was observed on one rod in the lower section of the follower. The control rod was returned to the reactor vessel.

The last four days of the month were devoted primarily to the inspection of all 9 of the rar.ovable fuel rods in the plutonium portion of the core. Five of these rods were inspected with the underwater periscope and then placed in the fuel storage rack _ The remaining four rods were inspected with the underwater periscope, three were measured with a profilometer and all were returned to new locations in the core. The five new fuel rods that were rectived on June 22nd were inserted in the vacant core positions.

On Jane 30th control rods Nos.1, 3 and 6 were renoved from the reactor vessel, inspect ed with the periscope and then returned to the reactor vessel. No abnormalaties were seen on thcae control rods.

2 EXPERIMa'TAL PRCGRAM Al!. nine of the 9x9 renovable zircaloy clad fuel rods in the plutonium portien of the core were removed for inspection. Five of the fuel rods (serial Nos. ,

f03-15-1; 503-15-33 503-15-4, 503-15-7 and 503-16-1) four having pelletized fuel and one having v:bracory compacted fuul were placed in the fuel storage rack. The remaining four roda (serial Nos. 503-15-.2, 503-15-5, 503-15-6 and 503-16-2) three having pelleticed fuel and one having vipac fuel were returned to new locations in l the core. F:ve new rode (serial Nos. 503-15-8, 503-15-9, 503-16-3, 503-16-4 and i

503-16-5) two having pelletized fuel and three having vipac fuel were installed in the va:t r t Jocat2ons.

No wear or fretting aside from normal contact marks were noted on any of l

the removable rods except 503-15-7. On this rod clad wear in the order of 0.0005 l

inch deep was found at the top grid support location and at the bottom grid support i locatien, manor _ fretting in the order of 0.001 inch deep was noted. These conditions l were nc, considered to be a problem.

The four 9x9 fuel assemblies in core locations B-3 (#503-2-3), D-4

(#503-12-1), C-3 (#503-12-3) and D-3 (#503-13 -1) were inspected with the underwater periscope for crud deposition. In general, the appearance of the fuel assemblies was good. The corrosion product deposition, where found, varied with location from a light spotty distribution to a fairly uniform pattern. Tne deposit thickness is estimated at varying between 0 and 3 mils. The heaviest deposit ' occurs only along relatively amall regions.

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SNEC Operations Report for June 1967 . . . . . , , #4 The high pressure nitrogen compressor for the supercritical technology test loop was relocated from the containment vessel to the auxiliary equi;nent room of the control and auxiliary building,  ;

3. OPERATIONAL TWPS The radiation monitoring system circuits were tested on June 13th.

On June 27th and 28th control rod No. 5 was raised to 40 inenes (full out position) with the drive mechanism and dropped a total of 5 times. The shortest tine recorded for a drop was 815 milliseconds and the longest was 846 milliseconds. The drops were made with the reactor in a cold, no-flow candition, A temporary guide block substituted for the guide block on the upper core support plate. The drop times recortled compared favorab(v with previous data taken for the same reactor conditions.

L. MAINTENANCE The principal items or mechanical maintenance for the month included rixnoving the reactor vessel head; rigging a rianually operated gear hoast and freeing control rod No. 5: removing the upper core barrel from the reactor vessel and placing it on a storage ple.tform; cleaning the thirty-six reactor head studs, acorn nuts and w shers; preparing the reactor vessel head for painting; processing four drums of evaporator

! bottoms: painting the internal surf aces of the magnetic clutch for the variable

( frequency motor generator set with three coats of epoxy paint; repairing a universal l joint on the contairment vessel rotary crane; replacing the seats an fifteen conference room chairs; painting the reactor head bolt can; replacing the ca' con vanes $n the air pump for the northeast site particulate monitor, RIC-8; and Landling fuel, control rods and other core components.

l The major items of electrical and instrumentation maintenance for the month included cleaning contacts on relays in the control circuits for the refueling crane; replacing the "zero" potentiometer in nuclear instrumentation source ran log micrea= meter; replacing the G-M tube in the area radiatien monitor (ge channel A labitron) located in the chenistry laooratory; assembling a borescope for use in the reactor vessel; installing a new gear train in the nuclear instrumentation start-up range recorder; pressurizing the underwater periscope for use in inspecting fuel in the storage well; replacing a circuit breaker in the sewage plant distribution panel; repairing the fast start-up rate alarm; repairing the scaler and audible alarm for the portable neutron dcLecting enannel used in fuel handhng operations; replacing the transmitter in the paging phone for the.operatirc, area in the containment vessel; replacing a decade unit in the G-M scaler in the count room; measuring the voltages on the cathodic protection system for burf ed pipes and tanke; repairing the voltmeter used in the control room for calibrati% melear instrumentation; repheing the bulba in two underwater refueling lights; and repairing the alpha acaler in the count room.

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SNEC Operations Report for y,tne 1967 . . , . . . . #5 l

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l The main coolant systs was in a cold shutdown condition and open to the i storace well throughout this report period. The boron concentration of the water in the storage well was 2050 p,:m. The shutdown enoling system was operated as necessary to remove core residual heat. A swmary of ths analyses taken from the shutdown cooling system during the month is given in the following table; Shutdem Cool 1,2tg,,, System Minimum  !!axinum pH at 25 C 5.13 6.08 Conductivity, umhos 7 55 17 3 Iioren, pps 1087 2060 Chlorides, p.m 0.015 0,02 Gross Deta-Gamma (15 Min. Degassod) uc/cc 0.0026 0.172 Tritiun. ue/ce 0.012 0.013 7 PJsDIATION AND WASTE _D.ISPOSAL Padiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiatien readings were taken; location Radiation Reading l

,0&A kildiqg Waste Drum (baling machine) 20.0 mrem /hr beta-gama Charging Pump (contact with chamber) 18.0 mrem /hr beta-gama Sample Room (door of cample panel) 2.0 mrea/nr beta-ga. ma Cnemical lab Hot Sink (l" from drain) 3.0 mrem /hr beta-gamma

!NDF Evaporator (under bottom) 35 mrc:t/hr beta-gamma Evaporator (contact outside upper level) < 1 crern/hr beta-gama D:2 Storage Area (at HRA fence) 5 0 mrem /hr beta-gamma C.v.

i Primary .r.cpartment (general upper level) 38 mrem /hr beta-gamma Primary Ccmpr.rtment t ecntact M.C. pump volute) 230 mren/hr beta-gamma Primary Cenpartment (S.G. bottom) 80 mrem /hrbeta-gamma Primary Compartment (pressurieer bottom) 80 mrsm/hr beta-gamma Primary Compartment (general lower level) 15 mrez/hr beta ga:=r.a Prima y Ccepartment (Regen. HI) 120 mren/hr beta-g -

Primary Compartment (Non Regen. RX) L2 arem/hr beta-ga::ca Auxiliary Equipment Ccept. (S.C.H.I.) 12 mrem /hr beta-ganz Aun11ary Equipaent Compt. (D.T. top) 12 mrem /hr beta-gamma Auxiliary Equipnent Ccapt. (D.T. bottom) 170 mrem /hr beta-gamma Auxiliary Equip::ent Compt. (general lower level) 9 mram/hr beta-gn=ma Reactor Deck (head removed) 1000 mrem /hr beta-ga=a Reactor Deck (waist level) 200 mrem /hr beta-gama

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SNEC Operations Report for June 1967 . , , . . . . #6 Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, t0ols, equipaent and C.V. during shutdown. The clean areas were within the " Clean Area" limits. Tne controlled area was generally within the " Clean Area" limits. The controlled area was cleaned frequently to keep and/or to return it l to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimize ,

the amount of smearable contamination. The following contamination levels were observed: l

_ location Contamination Readinn CM Ibilding Charging Pump Chamber 3L800 d/m/ smear beta-gamma Charging Pump Chamber < 10 d/m/ smear alpha Charging Room Floor 995 d/m/amear beta-gamma Sample Room Sink 171000 d/m/ smear beta-gamma Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor 886 d/m/ smear beta-gama Chenical lab Hot Sink 7520 d/m/cmear beta-gamma Chemical '.e.b Pot Sink < 10 d/m/ smear alpha

.R,hT Pump Room F1cor 653 d/m/ smear beta-gamma Shipping Roa:n Floor 448 d/m/ smear beta-gama h2.:.

l Operating Deck 2860 c/m/ smear beta-ga::r.a Opera'.ing Deck < 10 d/m/ smear alpha Prim ry Compartment (grating) 5960 d/m/ smear beta-gamma l

Primary Compartment (grating) 4 10 d/m/ smear beta-gamma I

Liquid and gaseous effluents from the SNEC site for the month of June 1967 l

were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Iast Twelve Months Tritium 0.206537 4.800909 22 790027 liquid 0.001946 0.016132 0.023 45-Air, Xe 0.000000 11.053901 80.146183

-Air, I-132. 0.000000 0.000850 0.10615' Air, H.F.P. 0.000000 0.110539 0.80146 4

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. June 1967 . . 0 .. . #7 Five (5) barrels of waste were drummed for temporary storage. No drums were shipped from the site.

Radiation exposure for all SNEC personnel as measurea by film badges for thi month of May 1967 were a maximma of 680 mran with an average of 53.2 mram.

Radiation exposure for all visiting personnel as measured by film badges for the month of May 1967 were a maximum of 900

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1 SAXTCN NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS MONTH JUNE YEAR 1967 1

NUOLF).R UNIT MONTH YEAR TO DATE TILES CRITICAL NO. 0 0 493 HOURS CRITICAL HRS. 0 754 70 19,617.65 TD:ES SCRAMMED (MANUAL) NO. 0 1 292 O TD:ES .SCPJJ2J2 (INADVERTANT) NO. 0 0 31 THEICiAL PG IR GDIERATION WH 0 17,665 02 357,749.89 AVERAGE BPNUP (PuRegien) WD/XTU 0 1,441.94 12,1B3.74 CO:ITROL RC'. POSITIONS AT DID OF HONTH AT B2UILIBRIUM POWER OP O Et PAIN C001 ANT BCRON 20L4 PPH RODS OUT - INCHES NO. 1 0 NO. 2 0 NO. 3 0 NO. 4 0 NO. 5 0 NO. 6 0 E!:CC'mICAL UNIT HONTH YEAR TO DATE l GP.0:S GE:ERATION WH q 3,367 60,842.00 ST .TIO:t SERVICE WH 89.34 733.48 11,452.67 STATION SERVICE  % -

21.78 18.82 AVG. PUJ;T EFFICIDICY - WH(e)/WH(t)  % 0 19.06 17.01 AVG. GDiERATION PJNNING ( 0 HRS) W 0 4,462.85 3,398.53 PIA!!T ICAD FACTOR -

(i.VG. GOI. FOR MONTHNAX. IDAD)  % 0 17 07 29 33 AUXTLTAP.Y STEMt SUPPLY - NUCLEAR STF./M SUPPLIED ET REACTOR HRS. O 754.50 16,244.75 WDF EVAPORATOR OPERATION HRS. 115 1,009.67 4,925.25

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