ML19344A878
| ML19344A878 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/17/1978 |
| From: | William Cahill CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17150A107 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220447 | |
| Download: ML19344A878 (40) | |
Text
____ _ _
Willirm J. C hill, Jr.
. ce erwwn h
p C:cscii:a:ed Ed: son Comcany of New Y:rk. inc 4 irung Pla:e. New Ycrx. N Y CCC3 Telecncne (212) 4c0 3819 July 17, 1978 Re:
Indian Point Unit No. 2 Docket No. 50-247 Director of Nuclear Reactor Regulation ATIN:
Mr. Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Camission Washington, D. C.
20555
Dear Mr. Stello:
In response to your letter dated May 17, 1978 answers to questions 1 through 8 are provided in the attachnent to this letter. The response to question 9 will be provided to you by August 4, 1^78.
Very truly yours,
/
- / -
/
/
s
/.< !u
. c'n. d s.
i attach.
William J. Cah).ll, Jr.
Vice President S
4 ScomotM7 s
N+ \\,4.
\\
ATTACLENT
- 1. Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved en the refueling floor.
Figures 9.5-1 and 5.1-6 of the Indian Point Unit No.
2 FSAR illustrate the physical relation between the reactor core, the fuel transfer canal. and the spent fuel storage Pool.
Figures 5.1-2 and 5.1-6 of the FSAR show typical laydown areas including the reactor head and upper internals laydown areas.
Heavy loads moved on the refueling ficor for maintenance reasons do not have Predeter=ined laydown areas.
e I
l l
l
2.
Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool.
For each object listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying height) and the frequency of movement.
In addition.to the reactor head (approximately 169 tons including the rig) and the upper internals (approximately 63 tons including the rig) which have to be moved over the
~
reactor each refueling other heavy loads could be moved for maintenance, inservice inspection etc.
Examples of such heavy loads include:
1.
reactor coolant pump mogr_:
weight: 32 tons size:
6' round x 12' long (approx.)
movement: no set path of movement frequency of movement: varies _
2.
inservice inspection tool:
weight: 5 tons size: 14' ro und x 20 ' long (approx.)
movement : no set path of movement frequency of movement: 2 times per outage The only heavy object that would normally be required to be
.o moved over the spent fuel storage pool is a cask.
Technical
'e s Specification 3. 8. A.7 states : "If the spent fuel pit contains g
3 fuel cask sha_ll n_ot,be moved over any
, f.'. t y_
r2 spent fuel, the spent
- c...
g.
'\\ V' region of the spent fuel pi_t until the disk handling system 9
has been reviewed by the Nuclear Regulatory Commission and found to be acceptable."
Therefore, there are no such heavy objects that will be moved over the spent fuel storage podl without first having the required prior review by NRC.
I
3.* What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?
At the present time Con Edison does not og any spent fuel P
c' asks for Indian Point 2, spent fuel.
Con Edison does not have any contracts with vendors to supply casks, at this time.
D L
9 s
y.
j e
4 0
.,n.
e
3 4.
Identify any heavy load or cask drop analyces performed to date for your facility.
Provide a copy of all such analyses not previously submitted to the NRC staff.
Excluding fuel assembly drop analyses, which are not considered heavy load analyses, the following is a list df documents where heavy load or cask drop analyses were previously described to the Commission:
1.
Question 9.6 of the Indian Point Unit No. 2 FSAR.
2.
Letter from Mr. W. J. Cahill, Jr., Con Edison to Mr. George Lear, NRC, dated July 23, 1975.
e b
e j
4 s
e
.m-
5.' Identify any heavy loads that are carried over equipment required for the safe shut down of a plant that is operating at the time the load is moved. Identify what equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc. ) and discuss the feasiblity of such an accident affecting this equipment.
Describe the basis for your conclusions.
Heavy loads are not carried directly over qquipment require d f5r the safe shutdown. of Indian Point 2 when the equipment is operating.
All safety systers are located in the primary auxiliary brilding or below the 95' elevation of the vapor containment building.
Movement of heavy loads on the 95' elevation would not endanger equipmen: used for the safe shutdown of the plant that is operating at the iime the load is moved.
e b
F G
.~. -..
- 6. If heavy loads are required to be carried over the spent fuel stoage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to uncover the spent fuel.
Describe the basis for you conclusions.
Heavy loads are not carried over the spent fuel pool or fuel transfer canal.
See response to question 2.
e O
e'
- 7. Describe any design featureo of your facility which affect the potential for a heavy load handling accident involving spent fuel, e.g., utilization of a single failure-proof crane.
The responses to questions 9.5 and 9.6 of the Indian Point 2 FSAR desribe the use of mechanical stops on the bridge rails and conservative design margins used for the cask related
- handling equipment, respectively, i
?
i 4
O
e 8.-
Provide copies of all procedures currently in sffect at your. facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.
For the reasons presented in responses to Questions 5,6 and 7 Con Edison does not have specific. procedures which address the movement of heavy loads over the reactor core during refueling, the spent fuel pool or the equipment required for the safe shutdown of the unit that is operating at the time the move occurs.
Sections of a procedure which i
pertains to the lifting of the reactor head and internals is provided for your information.
e 4
IP-W J
n i
) 4 p]j(;: j; p ;Ekg. J A t
'3.6 REFUELING
,,., 4 '
a
_Applicabilig Applies to ope rat f r.g limi t a t. i on s duringarefueling operations.
Obicetive To ensure that no incident could occur during refueling operations that would,advercely affect public henith and
~-
safety.
Specif $ c:1 i on During refueling operations, the following conditions shall be
- r. a t. iu f i e d :
1.
The equipnent door and at leant one door in cach perr.onnel air loch shall be properly clog.cd.
In ac' di ti on, et least one isointion valve shall be operebJe or loc.hed cloced in cach 1[ne penetrating the containnent and
~
which provider. a direct p a t.h fron contninuent ed atmosphere to the outside.*
2.
Radiation levels in the c on t aine.cu t and spent fuel storage areas r, hall be nonitored c on t.in-concly.
~
3.
The core s'uberitical neutron flux shall bc continuously moniLored by the tuo cource range monitorr, each.vich continuous visual indiention in the con f.rol room 1
l and one with audibic indicatTon in the 1
(
cont aininen t' availabic whencver core geometry
\\
is being changed.
When corn pcometry is not being changed, at least one cource range neutron l
1 flux monitor shall be in service-e M5
~,
y k lbl
- f
=
4.
'At 1 cast one residual heat removal pump and heat e # " ' ['
l q'k !I.
i J.
exchanger shall be operabic.
i.g,3 gM.
1 N
19 5.
'During reactor vesca1 head' comoval and while
,p tq >n loading and' unloading fuel from the reactor, T,yg bh all b c_<t 40
- F and the mininum boron concen-tration suffic'icnt to maintain the reactor
.suberi tical by at 'le ns t 10% 6h / k..
The reonired boron concentration shall be verified by chemical
,1 analysis daily.
6.
' Direct coumunication between the control loom and the l
retoeling cavity manipulator cranc chall be availabic whenever changes in core ncometry are taking,placc.
da_rb^-~Ochfd
(
A 7.
If the spent fuel pit contains spent fuel uwp d.s [d 6% em d_A et "d&*q, the ent Yd fr.el ensk shall not be moved over any rer, ion of the spent fuel pit until the eaek handling system has 11 I
been reviewed by the Nuclear Regulatory Co:: mission and found to be acceptable.
8.
fhe containment vent and purge cystem, in clu d'in g the radiation mon'$ tors which initiate -isolation, shall be tested and verified to be operabic immediately prior
.us~e d d a M +i 4 /jI[AfiCUb d t.cm edd
, to u fueling erarations.
}
9.
No movement of fuel in the reactor shall be made until
(
the reactor has been nuheritical for at least ninety
{ ll hours.
In the event that more than 'o n e region of 16 M nrC n,
' e:
m fuel (72 assemblics or less) is to be disetarted from 11 the reactor,those assenblics in excess of one region s
shall not be discharged before a continuous' interval of 400 ho'urs has elapsed after shutdown.
k
- 10. The min $ mum water level above the top of the core shall be at least 23 feet whenevc r movement of spent fuel is being made.
i
11. A d e a d-lo a d t e s t shall be s u c c e s s"f ully performed on the fuel storage refueling building crane before fuel noveuent begins.
The load assur. red by the refueling cranc for t h i s
,t e s t. must be equal to or greater than the maxinun Joad to be as s ur.e d t
by the refueling cranc during the refueling op e r at ion.
A throuhh visual inspec'tfon of the refueling crane shall be pade after the dead load J
test and prior to fuel h er.d 3.in g.
12.
The fuel-handling building charcoal filtration systen nust be opernting whenever spent fuel r.ovement is being made unicss the spent, fuel has had a. continuous
{11
~ 35-day decay period.
./. l..,-
- 13. A licensed senior reactor operator shall be at the site and designated in charge of the operation whenever changes in core geonetry are taking place.
/
(
~
197 5 3,s 3 og 16
g.
II a n :- of Ihe npecIfled l iri t t I n g con d l t J.in:
for r e f u e.i i n g i n not ric t., ref ueling shall cear c until the spe ci fie d limits are met, and no operations which may increase the reactivity of the core shall be made, basis
'f h e equip:ent and genera 3 procedures to be utilized during iciucling are discursed in the FSAR.
Detailed instructions, the ab ov e-s pe c'i f i e d precautions, and the design of the fuel-hendling e c; u i pme n t incorporating built-in interlocks and safety f eat urcs, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety.
Whenever changes r.r e not being made in core geometry, one flux monitor is sufficient. This permits maintenance of the instrumentation.
C on t i n u ouf, monitoring of radiation levcis (2 above) and neutron flux provides immediate indication of an, unsafe condition.
The residual heat pump is used to maintain a uniform boron concentration.
The chutdoun margin indicated in P a r t.
5 will keep the core subcritical, even if all control rods were withdrawn from the c o r e.,
During refueling, the reaccer refueling
(
S cavity is fil3cd with app.oximately 300,000 gallons of 1
wha t e r frou the refueling water' storage tank with a boron con cent rat ion of 2000 ppm.
The minimum boron concentratici of this water.at 1615 ppm boron is sufficient to maintain the react or suberitical by at 1 cast 10% Ak/k in the cold
(.
.chutdowr. vith all rods inserted, and vi,11 also naintain the core suberitical even i!'no control rods were inserted into 1.c '*i c.:.c n e T.u.
341 3.6-4
Con R4 son Indian Point Station Maintenance Procedure For Refuelino, Ins _erj ce Reactor Disassembiy And Reassembly; j
Title:
Inspection And/Or Extraordinarv Maintenance J
2-CM-2.4 Identification Number: _
Head & Internals Reactor RVI Ccmponent 2.4 Sub-System System
^ Number o
I!A 7b j
Date:
1 Revision Number:
l
/
~
191 1
__ of Page Number J
S l9fy,* $fS Prepared By J. Ouirk/W. Monti l
~gg,gg dA/(.K j
(October 1977) oA Engineer:(4/ A'<; L V#4 f-S 7/4yg fec77cm/
!{
A/
v N ld W N TAf U
Revieved By:
II0 N f &,
'W 3
4/f/~/Wf 0/ N $ML a te : N.(1.hudC."Of-7g SNSC Review Has swa t/Pfen NFSC Review /Date:
Not Required
/
[ N &~~jZ )Y k Y '
,/'##'_
Approved By:
H, MWR No. 2N5 t
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 2
OF 191 A.
PURPOSE-To provide a detailed procedure for the removal and replacement of the Reactor head, Reactor internals, and associated hardware in preparation for and return-ing from' refueling operations, inservice inspection (s) and/or extraordinary maintenance operations.
NOTE Before proceeding with work review sections B to D thoroughly.
)
0 e
-)
PROCEDURE UO.
2-CM-2.4 REVISION 1
PAGE 3
_ OF 191
)
l B.
PREREQUISITES Appendix B and Appendix D respectively contain con-1.0 sumable material and special tool lists; the respons-ible General Maintenance Supervisor should assure the availability of this material and these tools well in advance of actual need.
Prior to beginning the actual work an MWR shall be 2.0 obtained from the Operations sub-section and the number recorded on the face of this procedure (see S AO-10 4).
In order to proceed with work there is a need to
~
3.0 obtain Work Permits, Radiation Work Permits and a Primary Pressure Soundary PerniEI~~The acquisition of these permits is the Maintenanct beperviscr's These permits shou,d be returned responsibility.
to the issuing authority as soon as their need is no longer valid.
The General Maintenance Supervisor should kcep, as part of this procedure's use, a catalog of open and closed permits.
(See SAO-105 i
and procedure QA-10.)
4.
e 4
)
e
. PROCEDURE NO.
2-CM-2.4 REVISION 1
1Mdg o _ er ns C.
PRECAUTIONS
)
1.0 RADIOLOGICAL _
several steps in this procedure the Reactor Coolant l.1 At will be opened to containment atmosphere.
System (RCS)
Be aware of possible presence of radiogas, contaminated Where surfaces liquid and particulate contamination.
or areas exposed to the RCS are opened, radiation stream-ing may be experienced.
Exposed contaminated surfaces Beta fields will generate both gamma and beta fields.
can cause exposure to the skin of the whole body and to the lens of the eye unless these areas are protectdd.
In certain cases high contact field readings will req-uire the individual to wear wrist badges or finger rings.
These items will be specified by H.P. and specified on the RWP when required.
Observe radiological precautions indicated in this procedure and required by the Radiation Work Permits (RNP).
Use care in the disposal of any contaminated or radio-1.2 active material.
All material removed for disposal must be properly wrapped in plastic and approved by Health Physics prior to being removed from the job site.
l3 Any materials or parts stored for reuse must be care-fully wrapped, and marked to identify them to prevent inadvertent disposal.
1.4 All personnel involved in the job shall be instructed in the radiologi. cal protection requirements, and be familiar with the radiological rules and guidelines in effect at the plant site.
1.5 All individuals should be thoroughly familiar with their job functions when working in high radiation areas in order that the ALARA concept of ccllective dose (man-rem) to all personnel and to the individual be kept as low as reasonably achievable.
2.0 SYSTEM INTEGRITY 2.1 Any opening to the RCS must be sealed with plastic and yellow tape when work is not in progress or a person assigned to monitor the opening to prevent foreign mater-ial from entering system.
2.2 When it is possible for a tool to fall into the open RCS if inadvertently dropped, it must be secured with a line.
The QA Engineer will determine when such precautions are necessary.
2.3 The Operations, Maintenance and QA Engineers will jointly j) determine the extent of the clean area surrounding an open-ing in the RCS.
When working within this area CA -
Procedure 410 must be followed.
PROCEDURE NO.
2-CM-2.4 REiISION 1
PAGE 5
OF 191 3
w 3.0 QUALITY ASSURANCE - GENERAL PRECAUTIONS 3.1 Notify Q.C. prior to the start of work.
3.2 Full inventory control and equipment accountability is to be maintained in accordance with QA Procedure 110.
3.3 When working near the open RCS all personnel shall wear protective clothing with wrist =- ankles, front fly, and pockets taped closed; eyeg--
.11 be taped to the head or adequately tied to prevent dropping.
3.4 There shall be no other work undertaken in the area (grinding, machining, welding, etc.) which could endanger the clean area or cause foreign material to enter the primary system.
3.5 Calibrated tools and/or instruments are to be used for all specified measurements.
3.6 Nylon line will be used.- Manilla rope is not accept-
)
able in the Class A cleanliness boundary.
4.0 SAFETY 4.1 Observe standard safety precautions.
Remember that anti-C garments - which are very necessary - make task efforts more tedious and thus might suggest unsafe short cuts.
Do not be convinced without thorough review.
)
i
~.
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 6
_ OF 191 _
D.
GENERAL INSTRUCTIONS 1.0 Maintain the check Off List (COL), section G through-out this procedure.
Steps marked (*) require entry on the COL, any step requiring sign-off or data entry are so marked.
2.0 Use of Travelers Further amplification of any instruction required in the body of this procedure such as the removal of a stuck stud or alignment bushing will be provided in the form of a traveler ammended to this procedure, Such These will not be considered a procedure change.
travelers will be prepared and approved by Maintenance for hold Engineer Sub-Section, and reviewed by Q.A.
points prior to use.
3.0 Secuence of Steps The number sequence of steps indicated in this proced-ure need not be followed except where specifically in61cated in the procedure or as indicated below.
9 Steps 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18' 19, 20, and 21 must be done in order.
Changes to this procedure not covered by 2 or 3 above, 4.0 must be in accordance with Maintenance Engineer Sub-Section Administrative Directives (AD-4).
E CAUTION Temporary procedure changes must be reviewed by SUSC within seven days.
Because there is potential for movement of core compon-5.0 ents (fuel or RCC's) during head and upper internals removal, constant communication between personnel on 95' elevation containment and the CCR must be maintained as specified in this procedure.
e i
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 7
OF 191 E.
REFERENCES - Copies are available from the Indian Point Central Files Controller.
1.
. Westinghouse Refueling Procedure F-2, from Plant Manual.
2.
Combustion Engineering Instruction Manual Number 17765, Reactor Vessel.
3.
Stud Tensioner Instruction Book, Westinghouse Order i 54-F-66181-B, Biach Industries Order No. 725.
4.
Reactor Vessel Insulation Book, Westinght.use Order i 54-F-70611D-MlC369.
5.
Westinghouse Instruction F-7.6, Internals Lif ting Rig, PSE/PNJ-FHSTIR.
6.
Unit No. 2 System Description No. 17, Fuel and Core Component Handling.
7.
SAO-105, Work Permits.
8.
QA Procedure No.10, Cleanliness Control.
s
^)
9.
Stearns-Roger Instruction Book B32920, Fuel Transfer System.
10.
Royal Industries, Part. Length Control Rod Drive Manual No. 106.
11.
Unit No. 2 System Description No. 2, Reactor Vessel and Internals.
12.
Unit No. 2 System Description No. 14, Incore Instrument-ation.
13.
Whiting Corporation, Polar Crane Manual for Crane Serial No. 9548 (UE&C F.P. 9321-1289).
14.
HPP 2.1 - Radiation Work Permits.
i
PRdCEDURE NO.
2-CM-2.4 TIVISIO14 1
PAGE 8
OF 191 F.
DETAILED PROCEDURE INTRODUCTION This procedure is composed of twenty-five (25)
I.
independent sections and one sign-off section, the Check Off List (COL).
Work Permits, Radiation Work Permits and the II.
Primary Pressure Boundary Permit can be sought on the basis of each section.
This does not mean that cne permit set will suffice for each section but rather you can discuss total permit need for each section independently.
WARNING III. No water, regardless of purpose, shall be used or sprayed on elevation 69' of the reactor cavity
}
until the Presray Seal is installed and pressur-ized.
If this is not done and water is introduced at elevation 69' you will destroy the Nuclear Instrumentation.
E o
PROCEDURE NO.
2-CM-2.4_ REVISION 1
PAGE 42 OF 191 I
11.0 Reactor Head Removal _ (Refer to Figures 25, 28 and 29) 11.1 Prerequisites 11.1.1 Insure "O" ring gaskets for head are available.
See Section 11 of Appendix B.
11.1.2 P.G.M. crane maintenance personnel available in V.C. when lift is made.
11.1.3 Three (3) precision levels.
11.1.4 Primary Pressure Boundary Permit (see Section E, Reference 8).
11.2 Precautions
- 11.2.1 Do not proceed until part length CRD shaf ts have Been unlatched.
Verify this f act with the Oper-ations Watch Supervisor.
11.2.2 As head is being lifted constant communication shall be maintained with the CCR Cperator in case j
an RCC comes with the reactor head.
o 11.3 Procedure Steps 31.3.1 Remove all tools and equipment from pit, do not proceed unless step 10.3.6 has been signed off by the Quality control Inspector.
- 11.3.2 Prepare reactor head pad on 95' elevation to receive the head by placing plastic cn floor to contain any water, then place two (2) new reactor vessel clos-ure 0-rings around closure head storage pad.
CAUTION Visually inspect new gaskets.
Insure that they are free of dents, scratches, and pealing or flaking of coating.
O e
e
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 43 _ OF 191 11.3.3 Before proceeding you must verify the following:
A.
From Operations Watch Supervisor - that the Part Length Rods are unlatched.
This should have been accomplished shortly after step 3.3.7 was completed.
B.
That steps 1.3.1 and 1.3.2 have been completed AND signed off on the Check Off List.
- 11.3.4 Attach the reactor head lifting rig to the crane and in turn to the reactor head.
On the reactor head flance mark stud hole 12 as "I7",
stuc hole 28 as "28", and stud hole 44 as "44".
This will TaclTitate proper orientatTon7 hen the reactor head is to be reinstalled.
Insure the alignment pins are correspondingly marked and boldly with Nissan low chloride marker.
NOTE The reactor head and its lifting frame weight 169 tons.
- 11.3.5 Notify the CCR Operator you are about to lift the Reactor Head.
Lift head approximately 1" (by eye),
and check for levelness with the three precision i
levels installed 120 degrees apart.
If not, set head back down and adjust head lifting device - sling assembly.
Repeat this operation until head is level to within 0.003" per foot to the flange mating surface, o
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 44 OF 191 i
- 11.3.6 Notifv Cr9 that reactor head will now be moved un
^
two feeE 61gher.
Lift head two feet (cTeck for le-Iness during lift), insure reactor head does*
~
. t oind on alignment pins.
- 11.3.7 Continue raising head to about 170" above flange.
Maintain communication with CCR.
Make continuous visual inspection of full and part length rods to assure rods are not moving up with reactor head.
- 11.3.8 Lift reactor head out of pit and place it on the storage pad on 95' elevation.
- 11.3.9 Have Operations inflate pres-ray seal if not al-ready done as part of step 10.3.2d.
Notify Oper-ations that step 11.3.8 is complete so that full length CRDM's may be unlatched.
Hold at this coint until these items are completed.
- 11.3.10 Operations can now flood the reactor cavity.
e i
e
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 45 0F 191 3
WARNING The :mxt part of this procedure involves movement of the reactor's upper internals.
These internals weight about 130,000 pounds and are moved under water.
Clearances are very tight and require precis-ion actions.
CARE is the key word in your dealing with them.
You shall review this next section totally cefore you act and in particular tne drawings associated with this section.
You must, to be successful, also review it with
~
There is no recovery from your men.
damaged upper internals.
CARE.
PROCEDURS NO.
2-CM-2.4 REVISION 1
PAGE 46 OF 191 12.0 Removal of Upper Internals from Reactor Vessel (See Figures 26, 28, 30, 31, 32, and 33) 12.1 Prerequisites 12.1.1 For safe horizontal movement of the upper internals it is necessary that the water be sufficiently clear, so that the Maintenance Supervisor in charge of lift-ing the upper internals can clearly see tne reactor vessel flange with the water level at the normal refueling height of about 93.5'.
12.1.2 One 50' metal tape measure and brass plum bob.
Verification of completion of Section 1.4 of this 12.1.3 procedure.
12.1.4 PGM Crane and Elevator group on hand when lift is started.
12.2 Precautions 12.2.1 This move and that of section F16 of this procedure 8
are the most critical.
Work must be done in a careful and precise manner, paying close attention to this procedure.
There shall be no rush work in an attempt to meet schedule requirements during this phase.
12.2.2 It is necessary for the upper flange of the internals I
package to clear water by approximately 2 feet.
There will be considerable radiation streaming from this exposed portion.
H.P. must be on hand to monitor radiation.
Personnel within view of the refueling poo.' must be limited to only those essential per-sonnel for this operation as determined by the Maintenance Supervisor in charge.
4 LJ
PROCEDURE NO.
2-CM-2.4_ REVISION 1
PAGE 47
_ OF 191 Communication with the CCR shall be maintained 12.2.3 during this phase until the package is landed on the storage stand.
When working near or over the refueling canal, 12.2.4 all tools or equipment which could fall into the refueling canal must be secured by lanyards.
12.3 Procedure Steos Refer to Figure 26 for an elevation view of the 12.3.1 reactor vessel storage stand and internals trans-This figure shows reference heights port path.
necessary to assure clearance between the intern-als, storage stand, and reactor vessel.
Make a final inspection of the upper internals
- 12.3.2 lifting rig and the manipulator bridge crane.
Insure that they are free of loose particles of dirt or tools, etc., that could fall into the vessel.
- 12.3.3 At least two (2) hours prior to anticipated lift-turn on the Dillon ing of the internals lifting rig, Load Cell indicator and allow it to warm up.
Obtain reference dimension of upper internals pack-
- 12.3.4 age in vessel for use as a guide in reassembly as follows:
a)
Mark a reference location on the manipulator crane from which to drop the measuring tape and plum bob.
Record this position for re-assembly.
CAUTION Attach a lanyard to the tape measure.
Insure that plum bob is securely fastened to the tape measure.
o PROCEDURE NO.
2-CM-2.4_ REVISION 1
PAGE 48 OF 191 b)
Have Operations position the manipulator crane over the upper internals such that the plum bob can be positioned on the upper internals.
Have manipulator operator record the manipulator coordinates of this position and record them on the COL.
c.)
Lower the tape measure until the plum bob rests on the upper internals.
Record the tape reading on the COL.
d)
Retrieve the tape measure.
Use care handling, since it is wet with radioactive water.
Place in plastic bag before removal from manipulator.
e)
Move manipulator from core area.
STOP Do not start unless you intend to remain in Containment until I
the end of step 12.3.5h.
The following work cannot be lef t in mid-stream.
- 12.3.5 Latch the upper internals as follows:
a)
Lifting Rig Description (Refer to Figures 30, 31 and 32)
The internals lifting rig is a structural frame device to handle the upper and lower reactor vessel internal packages.
The rig consists of a sling assembly, spreader as-sembly, leg assembly, support r'.ng, protect-ive ring, and a mechanism handling tool.
The rig is suspended from the main crane hook and is remotely attached to the internal pack-ages by the use of a mechanism handling tool.
This tool it, operated from the platform on the manipulator crane.
b PROCEDURE NO.
2-CM-2.4 REVISIOH 1
PAGE 49 OF 191 7
For initial rough alignment and guidance when over the reactor vessel and upper internals storage stands, the rig uses three long guide studs.
For final fine alignment and guidance, the rig uses the four reactor vessel alignment keys and similar keys on the upper internals storage stand.
The brackets at the bottom of the rig which guide on these alignment pins must be manually moved when switching from handling the upper internals to handling the.ower in-ternals assembly.
The brackets must be bolted in the lower set of holes to handle the upper internals and in the uoper set of holes to handle the lower internals.
A protective ring assembly, that protects the reactor vessel mating surface during the refuel-ing operations, is supplied with the rig.
The ring is placed on the reactor vessel after the vessel head is removed and remains in place until the refueling operations are complete and the vessel head is to be re-installed.
The mechanism handling tool is used to connect and disconnect the protective ring and the rig.
For
, storage, the ring remains attached to the rig,
- b)
Install the Dillon Load Cell sensor assembly to the main crane hook by inserting the pin through the two side plates and the hole provided in the hook.
After the attachment is ccmplete, suspend the' assembly from the hook and visually inspect each component.
Insure that the adapters and Dillon Load Cell sensor are free uo pivot about the pin connection.
Attach a guide line to each side of the sister hook for the purpose of rotating the hook assembly.
At no time shall a twisting moment to rotate the hook be induced through the internals lif ting rig.
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 50 OF lol c)
Lawer the load cell assembly positioning the adaptar between the two top lugs of the in-ternals lifting rig.
Insert the connecting pin by use of the pull rod assembly which is attached to one of the top lugs.
When the connecting pin extends through the adaptar to approximately 1/8 inch beyond the other lug, Move tighten the pull rod assembly lock nut.
the manipulator crane east _to a position beyond the reactor vessel to allow access for removal of the internals package.
Insure that the four alignment pin brackets are bolted and pinned in the lower set of holes on the rig.
- d)
Slowly raise the internals lifting rig, when it is unseated record the Dillon Load Cell reading on the COL.
Then proceed to the re-actor vessel area.
Using the guide lines that are attached to the sister hook, orient the rig with respect to the reactor vessel guide studs, then lower the assembly until it has seated on the upper internals package.
(See Figures 26, 28, 30, 31, and 32.)
e)
, Locate the manipulator crane platform near the center of the internals lifting rig and disconnect the load cell assembly with the pull rod assembly.
Remove the load cell as-sembly from the immediate area.
- f)
Attach the mechanism handling tool to the hoist on the manipulator crane, then proceed to the attachment point.
Disconnect the pro-tective ring assembly with the mechanism hand-ling tool, and thread the torque tube assembly into the internal package.
This is accomplished by placing the adaptar on the end of the tool over the adaptars on the protective ring and torque tube mechanisms and then rotating the handwheel on the top of the tool.
Repeat the procedure for each of the three attach-ment locations.
(Approximately:
at 150 hand-wheel, 8 turns.)- During the locating movements of the manipulator crane, (at 1450 and 2500 handwheel 1-2 turns) insure that the mechanism handling tool and the manipulator mast are clear of obstructions.
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 51 OF 191 h
g)- When the rig-internals attachment is complete and the protective ring assembly is discon-nected, locate the manipulator crane platform near the center o' the rig and connect the load cell assembly as previously outlined.
Remove the manipulator crane from the area in-suring that the path to the upper internals storage stand is clear.
- h)
Insure that the crane is directly over the center position, then permanently bench mark the crane rail with reference to the crana?
position.
For future use record the location of this bench mark.
STOP Do not stalt unless you intend to remain in Containment until the end of step 12.3.6h.
The following work cannot be left
)
in mid-stream.
- 12.3.6 Raise and transport as follows:
a)
Using critical lift control, begin taking a strain with the polar crane.
Observe the Dillon Load Cell indicator for abnormal var-iation full load should be about 130,000 pounds when full load is obtained raise about 2 inches and check for any abnormal indicat-ion such as binding or shifting.
Record the actual full load on the COL,.
j b)
If no abnormal conditions are found, continue J
to raise slowly until a point is reached where the levelness of the lift may be determined.
At this point stop, insure levelness.
Monitor the load cell for any deviations from full load.
If at any time the load exceeds the expected load by 10% or more, S T O P.
If at any point
-)
e re-
,s
PROCEDURE No.
2-CM-2.4 REVISION 1
PAGE 52 OF 191 h
abnormal indications are found the package is to be lowered to rest in the reactor and the Maintenance Engineer notified.
If move-ment in either direction, up or down seems abnormal, stop and notify the Maintenance Engineer.
From the point that the lift is is landed the crane begun until the package _,ded.
must not be left unatten Observe precaution 12.2.2.
c)
When the Maintenance Supervisor has assured himself that no abnormal indications are present he may direct more rapid up crane movement.
Raise the upper internals package so that the upper plate is sufficiently above 95' elevation for the guide bushing to clear the water surface.
(See, Figure 26.)
~
NOTE j
Photographs are available in machinery history file showing position of internals package out of water to meet the requirements of this step.
WARNING At no time shall a twisting moment to rotate the hook be induced through the internals lifting rig.
Use the guide lines.
d)
Rotate the load 180 degrees and slowly trans-port the upper internals package to the stor-age stand.
e)
Align the guide bushings with the alignment pins, and lower to within several inches of the stand.
(See Figure 26.)
,/
f
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 53 OF 191 f)
Using critical lift speed, lower ento the IP.and.
Observe the Dillon Load Cell indi-cator as the load is being relieved.
Be alert to any shiftino or binding durini-lowering or resting.
g)
Once the internals are seated on the stand disconnect the crane from the internals lifting package.
The Dillon Load Cell sensor may remain or be removed.
h)
Inform CCR that this phase is complete.
Clean up the area, remove and store all tools; 12.3.7 proceed to Section 14, Preparation for Reasser.bly of Reactor Head and Upper Internals.
m 4
a
PRQCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 60 OF 191 WARNING The next part of this procedure involves movement of the reactor's upper internals.
These internals weigh about 130,000 pounds and are moved under water.
Clearances are very tight and require precision actions.
CARE is the key word in j
your dealing with them.
You shall review this next section totally before you act and in carticular the drawings associated with this section.
You must, to be successful, also review it with your men.
There is no recovery from damaged upper internals.
CARE.
s S
9 e
m
g
~
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 61 OF 191
)
16.0 Reassembly of Upper Internals in Reactor Vessel (See Figures 26, 28, 30, 31, 32, and 33) 16.1 Prerecuisites l
16.1.1 For safe horizontal movement of the upper intern-als, it is necessary that the water be suffic-iently clear so that the Maintenance Supervisor I
in charge of lifting the upper internals can clearly see the reactor vessel flange.
With the water level at the normal refueling height (about 93.5').
16.1.2 One 50' metal tape measure and brasc n,tHm bob from 12.1.2.
(Tape must be caliaratSd.)
16.1.3 PGM Crane and Elevator group on site when lift is started.
16.2 Precautions 16.2.1 This lift and the lift section 15 of this pro-cedure are the most critical.
Work must be done in a careful and precise manner, paying close attention to this procedure.
There shall be no rush work in an attempt to meet schedule require-ments durina this phase.
16.2.2 It is necessary for the upper flange of the internals package to clear the water by approx-imately 2 feet.
There will be considerable rad-iation streaming from this exposed portion.
H.P.
must be on hand to monitor radiation.
Personnel within view of the refueling pool must be limited to only those essential personnel for this oper-ation as determined by the Maintenance and Watch Supervisors.
16.2.3 When working near or over the refueling canal, all tools or equipment which could fall into the refueling canal must be secured by lanyards.
4 Y
^
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 62 OF 191 16.3 Procedure
- 16.3.1 Connect the crane to the internals lifting pack-The Dillon Load Cell sensor must be recon-age.
nected if removed.
The Dillon Load Cell indi-cator recuires 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> warm up prior to its use.
STOP Do not start unicss you intend not to leave Containment until the end of step 16.3.7.
The following work cannot be left in mid-stream.
16.3.2 Using critical lift speed, raise the package off the stand.
Observe the Dillon Load Cell indi-cator as the load is being increased.
The load should be the same as when it was removed, see the COL.
Be alert to any shifting or binding during movement.
- 16.3.3 Raise sufficiently high to clear the reactor alignment pins.
Observe precaution 16.2.2.
(See Figure 26.)
CAUTION At no time shall a twisting moment to rotate the hook be induced through the internals lifting rig.
Use the guide lines.
- 16.3.4 Rotate package 1800, and carefully transport to position over the reactor vessel.
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 63 OF 191 6,
- 16.3.5 Align bushings (lifting rig) to alignment pins (in the Reactor Vessel) and lower package to within six (6) inches of landing.
This should be determined using the tape and plum bob over from the manipulator.
Use care when lowering to ascure acainst binding or shifting.
Constantly monitc; the load cell.
If a 10% cnange is ooserved, S T O
!.' and notify the Maintenance Engineer.
The cell should read about 130,000 pounds.
(See COL for exact load at removal.)
- 16.3.6 When the six (6) inch point is reached use the critical lift control to lower the final six (6) inches.
Observe the Dillon Load Cell indicator as the load is seated.
(See Figure 26.)
Remove all load from the crane.
- 16.3.7 When the upper internals package has been seated, have Operations reposition manipulator bridge to coordinate with what was recorded in 12.3.4b.
Drop plum bob and tape (tape must be secured by lanyard).
Insure that plum bob is secure on the tape.
Record height above internals, this must agree with the value recorded in step 12.3.4b, if not, notify the Maintenance Engineer.
Record reading on COL.
Reel up tape and place in plastic bag.
Store until next refueling.
Log storage position.,
- 16.3.8 Using mechanism handling tool, unlatch rig and re-connect protective ring.
Remove manipulator from Over Core.
WARNING T e torque tubes are spring loaded, use caution in unlatching.
~
PROCEDURE NO.
2-CM-2.4_ REVISION 1
PAGE 64 OF 191 4
l
- 16.3.9 Using critical lift speed raise up upper internals
' ~
lifting rig, the weight must be the same as that recorded in step 12.3.5d on the COL, and place on the upper internals storage stand.
Record weight on the COL.
16.3.10 Disconnect the lifting rig from the crane; remove and store the Dillon Load Cell sensor and indicator outside the VC where the Maintenance Engineer directs.
- 16.3.11 Notify Operations that the full length CRDM's can be re-latched and the pit can be drained.
The reactor cavity can be cleaned before proceeding to next part of procedure but is not mandatory at this time.
CAUTION The Pres-ray seal must remain inflated during reactor cavity cleaning.
O
/
PROCEDURE NO.
2-CM-2.4 REVISION _1__
PAGC 65
_ OF 191 j
h 17.0 Reactor Head Replacement (See Figures 25, 28 and 29) 17.1 Prerecuisites 17.1.1 Verification of completion of step 14.2 above.
17.1.2 PGM Crane and Elevator group shall inspect the Polar Crane prior to lift.
Crane and Elevator personnel shall be on site until lift is complete.
17.2 Precautions 17.2.1 Until the head is landed, there will be a high radiation field coming from the open reactor vessel.
17.3 Procedure Steps
- 17.3.1 Attach the head lifting device upper sling as-sembly to the Polar Crane.
Inspect the head lifting device, and remove any loose objects or dirt.
Mark stud holes 12, 28, and 44 with
)
yellow tape if not done as required earlier.
STOP Do not start unless you intend not to leave Containment until the end of step 17.3.4.
The following work cannot be left in mid-stream.
- 17.3.2 Attach the sling assembly to the Reactor Vessel head lifting eyes.
Lift the reactor vessel closure head off the storage stand about six (6) inches.
Check levelness per step 11.3.5 above.
(Refer to Figures 25, 28 and 29.)
l
PROCEDURE NO.
2-CM-2.4 REVISION 1
PAGE 66 OF 191
{.
- 17.3.3 Raise the reactor head off its stand and move it in position over the reactor vessel.
Align bolt holes 12, 28, and 44 in vessel head with the corresponding alignment pins and siculy lower the vesse.1 closure head.
(Verify that descent is even.)
At about 170" off the flange check drive shaf t to sleeve alignment.
(See Figure 25.)
- 17.?.4 Continue to slowly lower the head to about one (1) foot above the vessel and clean the reactor QC.nspector, Watch Super-mating surfaces.
T visor, and Maintenance Supervisor shall make joint inspection for cleanliness prior to close up.
Lower head until it is seated on the reacter vessel.
(See Figure 25.)
17.3.5 Remove the head lifting rig from the reactor vessel head and store it in the head storage stand.
17.3.6 Remove the lifting rig from the Polar Crane.
s e
4 1
I
.