ML19250A192

Informs Util That NRC Does Not Concur W/Safety Evaluation Re Penetration R626 Experiment.Nrc Prepared to Meet W/Util Re Concerns

ML19250A192
Person / Time
Site:	Crane
Issue date:	09/05/1979
From:	Jay Collins NRC - NRC THREE MILE ISLAND TASK FORCE
To:	Norrell M GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 7910220055
Download: ML19250A192 (1)

Text

{{#Wiki_filter:r -- - o v'. r * ~ ~ 7 D,. n.('.'? ' 'I Dl'Il g wH NU ' y',;* s a September 5, 1979 ~ HDORANDUM FOR: M. F. Morrell, CPU Engineering FRO _M: J. T. Collins, Deputy Director TMI-Support

SUBJECT:

NEC COMMEN23 ON TMI-2 PERETRATION R626 E1FERDENT - SAFETY EVALUATION REPORT N x In responsa to your request of August 21, 1979 ve have reviewed the subject dommant and our commants are attaehed. The NRC does not concur in the Safety Evaluation Report as written. We are prepared to meet with you at your convenience to resolve our conserns. g I, l ? .c

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1 t ,,. t. ],[- J ',}' C y . ; y .J..k. Collins, Deputy Director m, t. 3, '., j.. ' '.TMI-Support s .;.. m c ? g., , :.p, ; -,._.;;. >y gg g[ggglg s. ~ ~. ' - s R. C. Aran 1A, Met-Ed. ,.cc p'iscribution: J. G. Barbein, Mat-Ed -,' -Centr'al' Files J. Lea NRR Rdg. File { l W. Raymond TMI/SEP r/f g g QO g TMI Site r/f D U cc w/o encl ' PSB/TMI r/f i R. Yo11mme l R. Corsti ~ I I I ~ a L 860 102 l i OFFICE > E-2 Jupport I ( SURNAME > JT ins ;j b DATE > /79 NRC Form 318A (4-79) NRCM 02040

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e IV inserted through the penetration. The gas is f,irst drawn through a particulate filter and then through a series of charcoal filters designed to trap various species of iodine. The filtered air sample is drawn through tygon tubing to the glove box wall. From the glove box vall through the gas stu:ple panel, the gas sample is drawn through stainless steel tubing which will have been pressure tested for leakage. Af ter having been drawn through the sample. ~ ~, panel, the gas will then be puc: ped back into the glove box where it can be purged back into the containment. All the sampling operations are performed in those portions of the syste.a that will be subatmospheric to eliminate the chances for out-leakage. As a further precaution, the samp1*e p el will be located near the glove box tent exhaust fan in the event that gases were to escape. Priar to breaching any portion of the sample system, the tubing will be purged into the conta.inment, by a self-contained supply of inert gas. .g Two basic types of sa:nples will be taken. The first will be to evaluate the ritium content by bubbling gases through a bottle of demineralized wat 'Ihe second sample is to be drawn with a hypodermic needle through a rubber sepetzn seal and transferred to an evacuated bottle for evaluation c4 the noble gases. .N yg; K;JA n //d .N o d M M & ) ~ i t ,,, co.,, a c u u n - ) / 4 L n /.Jc : / 6..; A @ D,,, ~ ,t.4,y 7 c.,,,- ~g ~ ~ a a. \\ ( d'h. N.'i 860 'i.1, ~ G

J. ga Fr4 4%3 Inter-Office Memorandum Oa:e e gus t i'r, 19 7v "T. -Y ar b d ~ a..t &.% 4 Sub;ec TM1-2 Penetration Ro26 txpa iment f3 Distributic.) Location T?il-2 ~ The att:ched s,ifety evalua tion re. cort is farwirded for yottr use in rev iewi ng' t.:le p rocedores' associa tv. w i th t.'m r.ubject ta st n %,4 M.P. MorrelI cc; R4 Jir.nn[d,RiiCT) G. Co. I i n's t JJCE;En, K f'. Wi ison (w/o ' + e s 9gg h ~ s ~ ~ 860 '1.7 GPU %rwce Corocration is e subsdary of General Pubic Urifiries Corcaration

e s TMI-II CONTAINMEITT SURVEILL4NCE SAFETY EVALUATION REPORT By ~ T. A. Brandsberg Fluid and Ifec.hanical Systems k6 l'I[ Approved By: Special Products resign GPU Contract No. B&W Contract No. Prepared for: General Public Utilities By MBCOCK & WILCO.T Power Generation Group Nuclear Power Generation Division P. O. Box 1260 Lynchburg, Virginia 24505 k ~ o$$"4 860 !!7 e

TMI-II CONTAINMENT SURVEIIL\\NCE SAFEIT EVALUATION REPORT 1. Abstract

2., Introduction / Background 3.

Basic Methods & Equipment 4. Detail Safety Considerations and Equipment Evaluation 5. Conclusions 6. Figures.

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Penetration Details in 2, 3. 4. Boring Equipment

5.. Secon'dary Boundary 6.

Purge Air System Diagram 7. Cas Sample Panel 8. Cas Sample System Diagram %c\\sY o gbc 860

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g. ABSTRACT Babcock & Wilcox, working in conjunction with General Public Utilities (GPU), is developing methods, equipment, and procedures for gaining access ~ to the 'DiI-2 containment for remote surveillance. It is intended that the direct measurement of conditions and inspections of equipment withirt the containment building will allow focusing of actions required for plant repair and recovery programs. This report discusses the methods and equipment to be used and evaluates how the equipment and design procedures have b'een developed and tested to meet the environmental requirements. 860 '!5 S e O O t ~ g e o h e

B INTRODUCTION /BACKCROUND As a result of the March 28, 1979, loss of feed water transient at the Three-Hile Island-2 Reactor, the containment building vas contaminated with ~ significant amounts of radioactive materials and gases. As one of the activities needed to recover the use of the reactor containment building, Babcock & Wilcox is developing-the nethods, equipc:ent, and procedures,to insert surveillance equipment through a containment penetration. ~ - It is anticipated that the surveillance equipme,nt would a1 low a detailed , study of: 1. The radioactivity levels and sources, 2. The potential effectiveness of proposed decontamination techniques, and 3. The physical condition of some of the equipment in the containment. This report describes the methods to be used for the first containment surveillance program and just how these methods will ensure safe use of this equipment. 860 '1e e h .e t ~ m k o O

9 METHODS AND EQUIPMENT It is proposed that the containment surveillance program utilize THI-2 Reactor Containment Building Penetration No. R-626 as shown in Figures 1, 2, & 3. This penetration consists of a 12" O.D. pipe with a 1" thick wall which presently is scaled inside and out with blind flanges. With suitable precautions (as will be discussed in Section 4) the outside blind _ flange.will be. removed and machinery s inserted into the interior blind flange and a 9" hole cut through into the containment atmosphere. Through this hole it is intended to insert various pieces of equipment such as tele lsion cameras, lights, and instrumentation for analysis of radioactivity levels and' sources. Samples of the gases and surface contamination will be taken, and the shielding effectiveness of various, garments that might be worn into the containment will b'e evaluated. The various pieces of equipment will be inserted and withdrawn using long-reach rods which will be manipulated from the glove box shom in Figure 4 and/or from the fuel storage building. ~ ~ To provide long-term isolation of the containme6t environment, two' gate = valves with elastomer sealing surfaces are to be installed in place of the outside blind flange. From the containment up. to, and including these valves, the system is designed to withstand the stresses associated with deadweight, seismic, and thermal loads. Siesmic loads on the secondary containment components were evaluated to ascertain their effect on the penetration piping and valves. ~he supports and connections of the secondary containment are desiged to preclude excess loads being transmitted to the penetration. 860 '17 Y e

=. I DETAIL SAFETY CONSIDERATIONS = AND EQUIPMENT EVALUATION The equipment and procedures to be used for the surveillance program has two main objectives. These objectives are to mainnin the integrity of the containment isolation boundary and to minimize the radiation exposure to the individuals working on or near the surveillance equipment. To demonstrate how these objectives are. met, each stage of the surveillance program will be discussed along with the specific precautions that are unique to each stage.. There are several safety aspects that will be considered throughout this program which will be discussed first. GENERAL SAFETY PRECAUTIONS During the surveillance program operations. the release of radioactive materials and gases that are airborne in the containment will be virtually eliminated by procedures and equipment that will at all times maintain at least one leak-tight barrier between the containment building interior..and - the external environment. That leak-tight barrier will vary during the operations as discussed further on in this section. According to all procedures that involve direct RB access through the penetration, one prerequisite will be 'that the containment atmosphere be main. tained at a subatmosp c condition. This will ensure no flow of airborne radioactivity out of the contain=ent boundary components. Local containment pressu're monitoring equipment will provide the surveillance operators with a direct. indication of pressure. Although the requirement for negative pressure may be extreme and perhaps unnecessary for a well sealed pressure boundary, it does provide significant added confidence, and cargin for error. Again, according to all procedures that involve direct RB access through 860 '18

the penetration, one prerequisite is to maintain a small (*1SCFM) positive flow of air into the containment when.he isolation gate valves are opened. 'This positive inflow will tend to discourage the migratian of airborne radioactivity into the penetration gipe and the secondary boundary components. It has been calculated that a total of 120 hours of ISCFM air flow would not cause the RB to increase by note than 0.05 psi. It is anticipated that no more than about 25 hours of .~ operation with this purge will be required to complete the vork outlined herein. ,In addition, prior to opening, and af ter shutting the containment gate valve s, the secondary boundary atmosphere will be, purged back into the _ penetra-tion pipe, thus ensuring that small amounts of airborne radioactivity which does

• leave the containment will not be released during transfer of equipment in and out of the secondary pressure boundary.

PHASE I-HOLE DRILLI?K; During the first phase of the surveillance program the inner seal plate of the penetration is to be cut through with a. 9" trepan cutter as shown in figure 4. Prior to starting this cutting operation, a positive air pressure ~ will be maintained on the penetration to ensure immediate flow of air into the containment when the seal plate is first breached. This purging air flow is to be maintained.at all times until the cutter is withdrawn back into the top hat, the gate valve closed, and the valve seal integrity verified. Prior to the removal of the blind flange outside of the containment building, the t penetration pipe will be inspected for-internal contamination through the s removal of the pipe' plug in the face o*f the exterior blind flange. Following i confirmation that this area is devoid of harmful amounts of radiation, then the blind flange'will be removed and a twelve inch (12") gate valve installed. This gate valve will become the primary boundary for the containment. Both this valve, and another to be mounted later this pipe will have an elastomer seal for the valve seat to ensure tightness. Prior to the use of these valves, they will be tested to ,'. (%j ensure their integrity under pressure and modified as i 'g. {,needed to ensure leak tightness. MO '10

d l 'Ihe equipment to be used to drive a hole through the blind flange locate ~ h seal is inside the containment building is designed such that a leak tig t The equipment shown figuratively in provided during the whole operation. Figure 4 maintains a seal by use of a top hat arrangement attached to the gate The' boring bar being driven by the air motor valve on the penetration pipe. ring operations ~ # aft seal outside of this top hat is provided with han the a=bient so that uill be perfonned with the containment pressure less t any leakage past the seal will be into the containment. The boring bar air motor will have the. air discharge port ducted to a h d of point outside of the area of potential contanination to avoid t e sprea contamirtation products. the cutting tool will be Following the completion of the borinh operation, ~ d and scaled. withdrawn into the top hat to allow the gate valve to be close the area will be enclosed in a plastic tent During the drilling operations, inside the top to insure that the small amount of gases whi'ch may u w. m e hat will not be released to the environment. The procedures for the hole cutting operations are provided with specific Tn._m conditions and con-contingency plans for various abnormal conditions. tingencies as follows: withdraw boring Failure to maintain the containment subatnospheric: 1. equipment and seal penetration. open and close. gate valve Failure to meet leak rate acceptance criteria: with a positive flow of air into the containment acrossthe valve to 2. blow chips from the valve seat. loosen cutter by Failure to maintain cutting action due to binding:if cutter continues to bind in th G h3 reversing the air motor drive; hc (withdraw cutter and seal penetration. ?' e the cutting bar can be forcefully Difficulty in withdrawing boring bar: force the bar will separate at 4,. withdrawn knowing that with sufficientThese joints are splined to allow withdra one of the joints. Following the removal of the the shearing of the joint retaining pin.the gate valve can be closed to bar segment, d to cut The hole cutting operations will be virtually identical to those use The procedures were developed from the water sampling hole at Penetration 401. 860 '29

t I Recocmendations those actually used for the water sample hole cutting operations. from these operations were incorporated. One dif ference to be noted between the procedures used on the R401 penetra-tion and the R626 penetration is the pressure to which the penetration pipe and isolation valves are tested. The design pressure.for the electrical connector spool piece is Epsig based on the connector manufacturer's recoceenda-tions. However, this pressure has been found to be more than sufficient considering the sources of energy available._to heat.,the. containment atmosphere and cause pressure build up., ~ This is confirmed each time the RB coolers are put 'into operation. Although } the heat removal capability of one RB cooler loop is several times greater than the decay heat production in the TMI-II core (as of August, 1979), it can only draw down the RB pressure less than Ipsi. From this it is obvious that the total core decay heat would cause an RB pressure increase of much less than Ipsi, even if thab heat uere totally transferred to the RB atmosphere (rather '5 % than through thhaten valls anu rigf the containment structure). PHASE II - SECONDARY BOUNDARY INSTAL 1ATION Following the hole drilling operations and the cleanup of the area, work will begin for installation of the secondary pressure. boundary components. These installation activities are to 'be. performed with the isolation gate valve closed so that they do not pose an environmental or radiological risk. To prevent the - accumulation of possible~ trace amounts of radioactive leakage, the tent air exhaust will remain functional. The pressure boundary equipment is designed and tested to ensure the capability to remain leak tight at pressures up to 2 psig. The major components i clude the following as shown in figure 5: 860 '21 e e

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z i FN 17 - glove box PN 42 - 12" gate valves - electrical connector spool piece ~ PN 43 PN 46 - mounting flange PN 7 - extension pipe PN 1 - extension pipecover Also, part of the surveillance system -components are valves, regulators, t atmosphere. and tubing to be used for purging the secondary boundary componen d Most of these components and the surveillance tools were assembled an ~ ~ ble with the. tested prior to shipment to the site and found to be - compati i ities. operations described in the procedure for the surveillance act v two 12" . To further enhance the usefulness of the glove box equipment, Between them is provided gate valves are provided for penetration sealing. V camera equipment a spool piece with the electrical connector needed for the T With this arrangement, one or th_e and the permanent radiation monitor. h h this-other valve may be closed to maintain the containment boundary w et er, equipment is inserted or withdrawn. d The secondary component _s have been evaluated to determine what loa /^5 Table 1 shows th( results of these will be applied to the containment pipe. i acceptability based calculations and demonstrates a significant margin o Ro%l f' is on allowable loads provided by the piping designer, Burns ~ the' weight of. the .~ 7-:- The calculations and tabu 1ated results assume that ~ / [ fact, the work plat-glove box is supported by the penetration piping when 1 the RB penetration pipe Despite this conservatisn, form is designed to hold it. is f ar f rom overloaded. * ~ PHASE III - CONTAI!MElfr SURVEILLANCE - Following the installation of the secondary pressure boundary compcnents for TV, communications, and and the completion of the exterior connections 860 '2? \\

i Prior to the radiation monitors, the surveillance activities, will commence. opening of the containment isolation valve!(s), the pressure boundary cocponents will be tested to confirm Icak tightness. The surveillance activity sequence of events will be as follows: Glove box radiation survey $md penetration pipe cleanup. 1. Insertion of TV camera and video survey. 2. 3. Containment radiation survey. ' 4. Containment air sample. 5. Containment surf ace swipe samples. 6. Containment relative humidity survey. 7. Installation of permanent radiation monitor. The secondary boundary will be breached to install and/or remove equipment prior to Step 1, above, and between Steps 1 & 2 and 2 & 3 and af ter Step 7. During these periods, the containment boundary is maintained by the 12" gate valve. By minimizing the number of times that equipment is moved in and/or out of the secondary containment, the chances of inadvertantly spreading radioactive contamination from the glove box will be minimized. As a further precaution, both of the areas around the glove box and the extension pipe cover will be surrounded by a work tent. The tent around the glove box shall be provided with an exhaust fan that is ducted to a suitable air filter system. By procedure, anytime the extension pipe cover is to ba removed, the glovebox viewport will also be opened to draw air through the extension pipe, from the fuel handling building, and through the exhaust This precaution will discourage the migration of contamination out system. of the extension pipe into the fuel handling building. The' procedures for the surveillance activities include consideration of Thes e various abnormal op.erating conditions which might be encountered. 860 '27

i abnormal conditions and the contingency plans are as follows: i Procedure would identify methods 1. Leakage during pressure testing: to be used to identify and seal leakage paths. Large radiation increase during tool withdrawal: Stop tool withdrawal 2. until HP can evaluate acceptable increases in radiation and plan accordingly. Withdraw tools Failure to control containment pressure subatmospheric: 3. and close a 12" gate valve. Re-evaluate the need for subatmospheric containment based on experiences to that t ime. Withdraw hand f rom damaged glove and inspect .o4. Damage to glove that hand for contamination. Cover glove port and continue if possible. 5. Inability to withdraw tool (s): Examine with TV or with the mirror - If this doesn't provide enough information for in the glove box. If withdrawal, push tool in,to penetr. tion and close gate valve. a through with a saw necessary, disassemble reach rod section or cut if needed. Put on airmasks, 6. Increasing Airborne Activity in the glove box tent: withdraw tools, close a 12" gate valve and exit the work tent. Con-tact HP to detect the source of activity. The e uipment to be used for the surveillance program has been assembled and ' n f/ t b ' O( demonstrated to f unction as expected during mock-up tests perforced at B&W's { The operators have also demonstrated their capability to funct. on Research Center. d' in a glove box with a negative pressures similar to those which have been ( observed within the TMI-II containment. Prior to shipment to the site, all the pressure boundary components will have been tested to their respective design pressure, ie.,15psig for the spool piece and the two valves, and 2 psig for the glove box and extension pipe. -With the exception of the containment gas sample, all the surveillance work will be performed within the confines of the previously described glove 'Since the gas sampling procedure will bring a small amount of the contain-box. ment. atmosphere outside of the pressure boundary, it is warranted to describe these activities in further detail. The gas sample panel, shown pictorally in Figure 8 is provided with a vacuum pump to draw gas samples from the containment through the sample tubing e ~ 860 '2^

Inserted through the penetration. The gas is f,irst drawn through a particulate filter and then through a series of charcoal filters designed to trap various species of iodine. The filtered air sample is drawn through tygon tubing to the glove box vall. From the glove box wall through the gas sample panel, the gas sample is drawn through stainless steel tubing which will have been ~~ pressure tested for leakage. Af ter having been drawn through the sample panel, the gas will then be pumped back into the glove box where it can be purged back into the containment. 1 Ai.1 the sampling operations are performed in those portions of the system that will be subatmospheric to eliminate the chances for out-leakage. As a further precaution, the samp1*e p el will be located near the glove box tent exhaust fan in the event that gases were to escape. Prior, to breaching any portion of the sa=ple system, the tubing will be purged i' to the co n tainment, n ' ~ by a self-contained supply of inert gas. Two basic types of samples will be taken. The first will be to evaluate the tritium content by bubbling gases through a bottle of demineralized water. 'The second sample is to be drawn with a hypodermic needle through a rubber septum seal and transferred to an evacuated bottle for evaluation of the noble gases. ~860 '25 O = ~ 4 e

~ 6. CONCLUSIONS _ The preceding sections have diccussed the equipment and methods by the TMI-II containment be initially surveyed. which it is proposed that It has been demonstrated that these procedures and equipment will reduce personnel exposure to low levels and will maintain the containment integrity to ensure no danger of environmental impact. 860 '2' g 4 e 4 Se t e e O e e e e e- = S 9 e e-e= d

i TABLE 1 RB PDErPATICN PIPE Ir. ADS Cbgenent

Weight of

.CG Distance Ftm2nt. Icad . J.

Cc:ponent Fran wall

~".'(Fti--Ibl ... (Ibs) ._...(inchesi,... '. '. 1. Ist Gate valve 300 13S. 337.5 ~ 2. Spool Piece <100 17 141.7 ~ 3. 2nd-Gate Valve 300-20h s, 512.5 4. Mountirg Flange 50 25 104.2 } 5. Glove Bax 200 38 633.3 6. Men & BIuiprent 500 ' 38 1583.3 Total Dead Weight 1450 3313 Ft-Ib ~ . Seismic. (2) 7957 Ft-Ib Dead Weight +- 3480 A11cw ble 28,000 .10,600 Ft-Ib (1) of Glove Box wight is supported by the extension pipe

12) Assmmirq a rigid bcdy arrl using the peak spectra amlerations of 2.0 g's horizontal ard 1.33 g's vertical total mcment load was nultiplied by 41.332 + 2.04 = 2.40 Because of the ruh glove box smin, there will be no appreciable Note:

themal loads. y ~ 860 '27 O h q =.

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t:

l =^'; of R-I x a 1 l F 9 l t [ l A q1 r ; ] h ., i. g,, i . 1 1 gl JD @x .L. 1-O M M l \\\\ 3 I I g r Gr \\ g l d l l l 4 ~ k l g I ~ 1 ? 8 3 -a l I e g q i i &r ' -b L, , 860 '37 .}}