ML19344A899
| ML19344A899 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/17/1978 |
| From: | Dise D NIAGARA MOHAWK POWER CORP. |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8008220493 | |
| Download: ML19344A899 (100) | |
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A NIAGARA MOHAWK POWER CORPORATION p
NBAGARA MOHAWK 300 ERIE SOULEV ARD WEST SYRACUSE.N Y.13202 July 17, 1978 1
Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Gtello:
- Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 Find enclosed information relative to movement of heavy loads near the spent fuel storage pool or reactor core at Nine Mile Point Unit 1.
This information was requested in your letter of May 17, 1978 to All Licensees of Power Reactors Except those in the Systematic Evaluation Program.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION q -
D. P. Dise Vice President-Engineering i
GJO/szd Enclosure
Question 1 Provide a diagram which illustrates the physical relationship between the reactor core, the fuel transfer canal, the spent fuel storage pool and the setdown, receiving or storage areas for any heavy loads moved on the refueling floor.
Response
The attached Figure 1 illustrates the physical relationship between the reactor core, the fuel transfer canal, and the spent fuel storage pool.
Figure 2 is a cross-sectional view, which shows the placement of the reactor shield plugs.
Figure 3 shows the setdown areas for heavy loads during refueling.
- Setdown, receiving and storage areas for shipping casks are addressed in response to Question 2.
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Question 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.
Response
Figure 3 gives the approximate waight and size of the heavy loads required to be moved over the reactor core during refueling. Procedures require that these loads are not raised more than six inches above the refueling floor.
All heavy loads listed in Figure 3 are removed from above the reactor core to their lay-down area without passing over the spent fuel pool or re-crossing the reactor core. These objects are' planned to be moved on 18-month intervals.
Letters from T. J. Brosnan to J. F. O' Leary dated September 29, 1972 and from P. D. Raymond to D. L. Ziemann dated May 31, 1973 detail the controlled path for cask movement over the spent fuel pool. Casks are restricted to a minimum height of six inches above the refueling floor except as noted in Attachment 4-2.
Crane limit switches assure the travel path and cask height are main-tained. Currently, a cask used to dispose of non-fuel bearing waste is moved approximately once per month. However in the near future, the frequency of this cask movement will drop to approximately five per 18 months. No spent fuel has been moved by casks on the refueling floor.
There is no definitive plan for such movement in the immediate future.
At this time, high density spent fuel racks are being installed at Nine Mile Point Unit 1.
These racks are described in Mr. G. K. Rhode's submittal of December 3, 1976 and subsequent responses to requests for information from l
G. K. Rhode to Mr. George Lear of April 13, 1977, July 27, 1977 and September 29, 1977. By the end of July 1978, all racks in the north half of the spent fuel pool are planned to be installed. The south half of the spent fuel pool will be reracked following the 1980 refueling.
Question 3 What are the dimensions and weights of the spent fuel casks that arc or will be used at your facility?
Response
Currently, Niagara Mohawk is using the 30-ton Vandenburg cask for the disposal of non-fuel bearing waste. This cask has an outside diameter of 50-1/2 inches (shielding cylinder) and the overall length is 133-3/4 inches.
Letters from T. J. Brosnan to J. F. O' Leary of September 29, 1972 and from P. D. Raymond to D. L. Ziemann of May 31, 1973 describe the Cask Drop Protection System installed at Nine Mile Point Unit 1.
Detailed cask drop analyses were performed for 25, 70 and 100 ton casks. In the future, Niagara Mohawk anticipates using casks to ship spent fuel which are within the bounds of these analyses.
Question 4 Identify any heavy load or cask drop analyses performed to date for your facility.
Provide a copy of all such analyses not previously submitted to the NRC staff.
Response
Following is a list of cask drop and heavy load analyses which have been submitted to or issued from the Nuclear Regulatory Commission:
1)
Letter f rom T. J. Brosnan (NMPC) to J. F. O' Leary (AEC), September 29, 1972.
(Attached report: NMP-1 Cask Drop Protection System.)
2)
Letter from P. D. Raymond (NMPC) to D. L. Ziemann (AEC), May 31, 1973.
(Attached report: NMP-1 Cask Drop Protection System.)
3)
Letter from D. J. Skovholt (AEC) to P. D. Raymond (NMPC), August 15, 1973.
(Cask Drop Protection System is acceptable and provides reasonable protection to spent fuel pool.)
4)
Letter from P. D. Raymond (NMPC) to D. J. Skovholt (AEC), July 26, 1973.
(Attached report: Redundant Hoisting System and Crane Movement Controls.)
5)
Letter from G. K. Rhode (NMPC) to K. R. Goller (NRC), December 10, 1975.
(Attached information related to Redundant Hoisting System.)
6)
Letter from G. K. Rhode (NMPC) to George Lear (NRC), March 16, 1977.
(Section III of attached report: Shielded Inspection Platform used for Reactor Vessel Internal Inspection.)
7)
Letter from G. K. Rhode (NMPC) to George Lear (NRC), April 13, 1977.
(Response 12 of attached information: Possible Dropping of a Spent Fuel Rack.)
8)
Letter from G. K. Rhode (1;MPC) to George Lear (:;RC), July 27, 1977.
(Response 3.of attached information: Possible Dropping of the Spent Fuel Rack.)
The following additional cask drop and heavy load analyses have been performed and are attached for your review:
1)
Use of Vandenburg cask in Nine Mile Point Unit 1-Cask Drop Protection System (Attachment 4-1).
2)
Safety Evaluation for Changing Washdown Area and Fuel Handling Procedure
- 16 (Attach: $nts 4-2, 4-3 and 4-4).
Question 5 Identify any heavy loads that are carried over equipment required for the safe shutdown 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 feasibility of such an accident affecting this equipment. Describe the basis for your conclusions.
Response
During plant operations, casks are the only heavy loads that are normally moved.
A study indicates that there is a location along the operating floor where two emergency condenser isolation valves are directly below the cask travel path.
However, a cask drop accident on the refueling floor, which would cause damage to equipment necessary for a safe shutdown, is not realistically feasible.
Protection against such an accident is provided for by a number of in-depth safety features related to cask handling.
As described in attachments to letters dated July 26, 1973 from P. D. Raymond to D. J. Skovholt and dated December 10, 1975 from G. K. Rhode to K. R. Galler, cask movements are horizontally and vertically restricted on the refueling floor. The maximum six inch height above the refueling floor will likely preclude refueling floor breeching, even for the accidental drop of a 100-ton cask. As an added precaution, an energy absorbing pad is attached to the bottom of all casks. This pad further limits energy that is impacted to the refueling floor in the event of a cask drop accident. The energy absorbing pad has been designed such that dropping a 100-ton cask from a height of six inches will impart substantial less energy than is needed for structural failure of the refueling floor.
I Additionally, the July 26, 1973 and December 10, 1975 letters describe the 125-ton redundant hoisting system which is used for all heavy load movements.
This system is designed to preclude cask drop accidents resulting from a single failure in the hoisting system.
There.is a remote possibility that a cask drop down the hatchway could cause The redundant some damage to one of the two sets of containment spray pumps.
125-ton hoisting system provides added assurance that damage to one of the containment spray systems is not feasible, f
I e
Question 6 If heavy loads are required to be carried over the spent fuel storage 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 your conclusions.
Response
During refueling, no heavy loads are carried over the spent fuel pool. However, the spent fuel pool shield plugs must be removed. When these plugs have been raised out of the guide tracks they are moved directly south to avoid the spent fuel pool and the reactor cavity.
Our submittals from G. K. Rhode to Mr. George Lear of Apri2 13, 1977 and July 27, 1977 which are mentioned in the response to Question 4 discuss the consequences of dropping a spent fuel rack during installation.
Casks are the only equipment normally carried over the spent fuel pool.
The Spent Fuel Pool Cask Drop Protection Analyses described in Response 4 discusses the equipment in place to prevent damage to the spent fuel pool in the event of a cask drop accident.
Additionally, letters dated July 26, 1973 from Mr. P. D. Raymond to Mr. D. J.
Skovholt and December 10, 1975 from Mr. G. K. Rhode to Mr. K. R. Go11er describe the recently installed 125-ton double-reeved crane. This crane is designed to preclude the possibility of heavy object drop accidents due to crane failure.
i
Question 7 Describe any design features 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.
Response
A July 27, 1973 letter from Mr. P. D. Raymond to Mr. D. J. Skovholt described the Redundant Hoisting System which has been installed at Nine Mile Point Unit 1.
On December 10, 1975 Mr. G. K. Rhode submitted to Mr. K. R. Goller additional information related to this redundant system.
The spent fuel pool at Nine Mile Point Unit 1 is equipped with a Cask Drop Protection System. This system is described in Response 4.
1 4
Question 8 Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over reactor core during refueling, the spent fuel is storage pool, or equipment required for safe shutdown of a plant that operating at the time the move occurs.
Response
You will find attached the following procedures for the movement of heavy loads on the refueling floor:
PROCEDURE #
TITLE 1)
MP-1.1 Remo*ral of Containment Head 2)
MP-1.2 Removal of Reactor Vessel Head 3)
MP-1.3 Removal of Reactor Vessel Steam Dryer 4)
HP-1.4 Removal of Reactor Vessel Moisture Separator 5)
MP-1.5 Installation of Reactor Vessel Steam Dryer 6)
MP-1.6 Installation of Reactor Vessel Steam Dryer 7)
MP-1.7 Installation of Reactor Vessel Head 8)
MP-1.8 Installation of Containment Head 9)
N1-FHP-16
--Vandenburg Cask Spent Fuel Rack Assemblies 10)
Question 9 Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, Dezember 1975) regarding Spent Fuel Storage Facility Design Basis.
Response
Following is a discussion of each of the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December 1975):
(1)
Regulatory Position The spent fuel storage facility (including its structures and equipment except as noted in Paragraph 6 below) should be designed to Category I seismic requirements.
Niagara Mohawk Compliance The Nine Mile Point Unit 1 spent fuel pool (including its structures and equipment) is designed to Category I seismic requirements.
(See Section VI.B of t!e Nine Mile Point Unit 1 Final Safety Analysis Report.)
(2)
Regulatory Position The facility should be designed (a) to keep tornadic winds and missiles generated by these winds from causing significant loss of watertight integrity of the fuel storage pool and (b) to keep missiles generated by tornadic winds from contacting fuel within the pool.
Niagara Mohawk Compliance Our response to Question 7 of Section I to the Second Supplement to the Final Safety Analysis Report for Nine Mile Point Unit 1 discussed the capability of the plant to withstand tornadic winds. This response detailed the probability of a tornado occurrence for the Nine Mile Foint site area, and describes pressures and/or wind velocity at which functional failure of reactor building structures would occur. Tornadic winds will not cause damage to the spent fuel pool structure.
Regarding torcadic wind generated missiles, Response 4 of Section II of the Second Supplement considers the consequences of a stack failure on the reactor building.
It was considered that it is unlikely that the stack, as a missile, would penetrate the bottom of the spent fuel pool.
Because of the low probability of a tornado occurrence at the Nine Mile F> int site area, the consideration of missiles generated as a result of tornadu.
winds contacting spent fuel in the pool was not included in the design o; the facility.
(3)
Regulatory Position Interlocks should be provided to prevent cranes from passing over stored fuel (or near stored fuel in a manner such that if a crane failed, the load could tip over on stored fuel) when fuel handling is not in progress. During fuel handling _ operations, the interlocks may be bypassed and administrative control used to prevent the crane from carrying loads that are not necessary for fuel handling over the stored fuel or other prohibited areas.
The facility should be designed to minimize the need for bypassing such interlocks.
)
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Response 9 (Continued)
Niagara Mohawk Compliance (To Regulatory Position 3)
During cask movement, the crane is in a control path mode so that casks cannot f all into the spent fuel pool (other than the Cask Drop Protection System).
Interlocks are used on the overhand crane to assure the controlled path is followed. Letters from T. J. Brosnan to J. F. O' Leary of September 29, 1972 and from P. D. Raymond to D. L. Ziemann of May 31, 1973 describe the controlled path near the spent fuel pool.
(4) Regulatory Position A controlled leakage building should enclose the fuel pool.
The building should be equipped with an appropriate ventilation and filtration system to limit the The potential release of radioactive iodine and other radioactive materials.
building need not be designed to withstand extremely high winds, but leakage should be suitably controlled during refueling operations. The design of the ventilation and filtration system should be based on the assumption that the The cladding of all of the fuel rods in one fuel bundle might be breached.
inventory of radioactive materials available for leakage from the building should be based on the assumptions given in Regulatory Guide 1.25, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors" (Safety Guide 25).
Niagara Mohawk Compliance The Reactor Building houses the spent fuel pool. This building is a controlled leakage building based on the assumptions of Regulatory Guide 1.25.
4 (5) Regulatory Position The spent fuel storage facility should have at least one of the following provisions with respect to the handling of heavy loads, including the refueling cask:
a)
Cranes capable of carrying heavy loads should be prevented, preferably.by design rather than by interlocks, from moving into the vicinity of the pool; or b)
Cranes should be designed to provide single-failure-proof handling of heavy loads, so that a single failure will not result in loss of capability of the crane-handling system to perform its safety function; or c)
The fuel pool should be designed to withstand, without leakage that could uncover the fuel, the impact of the heaviest load to be carried by the crane from the maximum height to which it can be lif ted. If this approach is used, design provisions should be made to prevent the crane, when carrying heavy loads, from moving in the
. vicinity of stored fuel.
Response 9 (Continued)
Niagara Mohawk Compliance (To Regulatory Position 5)
It is Niagara Mohawk's position that the reactor building overhead crane meets the criteria of Paragraph b to Regulatory Position 5.
This 125-ton capacity crane is used to handle all heavy loads. Letters trom P. D. Raymond to D. J. Skovholt of July 26, 1973 and from G. K. Rhode to K. R. Goller of December 10, 1975 describe this redundant hoisting system.
(6)
Regulatory Position Drains, permanently connected mechanical or hydraulic systems, and other features that by maloperation or failure could cause loss of coolant that would uncover fuel should not be installed or included in the design. Systems for maintaining water quality and quantity should be designed so that any maloperation or failure of such systems (including failures resulting from the Safe Shutdown Earthquake) will not cause fuel to be uncovered.
These systems need not otherwise meet Category I seismic requirements.
Niagara Mohawk Compliance The spent fuel pool at Nine Mile Point Unit 1 does not have drains or hose connections that by maloperation or failure could cause loss of coolant. The spent fuel pool filtering and cooling system (described in Section X.H of the Nine Mile Point Unit 1 FSAR) is a seismic Category I system, and is provided with siphon breakers to prevent loss of coolant in the event of a line break.
(7)
Regulatory Position Reliable and frequently tested monitor.ing aquipment should be provided to alarm both locally and in a continuously manned location if the water level in the fuel storage pool falls below a predetermined level or if high local-radiation levels are experienced. The high-radiation-level instrumentation should also actuate the filtration system.
Niagara Mohawk Compliance The spent fuel pool at Nine Mile Point Unit 1 is provided with a low level water level alarm on the annunciator panel in the control-room and on the spent fuel pool cooling panel located on elevation 281 of the Reactor Building.
High radiation level instrumentation is in place and is initiated at pre-determined levels in the control room and on the refueling floor.
The spent fuel pool filtration system is actuated by a high radiation alarm.
This instrumentation is tested with a frequency consistent with its historic reliability.
Response 9 (Continued)
(8)
ReguJatory Position A seismic Category I makeup system should be provided to add coolant to the pool. Appropriate redundancy or a backup system for filling the pool from a reliable source, such as a lake, river, or onsite seismic Category I water-storage facility, should be provided. If a backup system is used, it need not be a permanently installed system. The capacity of the makeup systems should be such that water can be supplied at a rate determined by consideration of the leakage rate that would be expected as the result of damage to the fuel storage pool from the dropping of loads, from earthquakes, or from missiles originating in.high winds.
Niagara Mohawk Compliance The condensate transfer system, a seismic Category I system, supplies makeup to the spent fuel pool. The system is capable of supplying 75 gallons per minute. The condensate transfer system is supplied by the condensate storage tanks which have a 400,000 gallen capacity.
Additionally, the fire protection system can be used to provide makeup water.
The fire protection system is capable of providing up to 1000 gallons per minute utilizing two 2 1/2 inch fire hoses without nozzles. The fire protection system is not a Category 1 seismic design. However, redundant full capacity fire pumps take suctions from the seismic Category I intake-discharge tunnel which receives water from Lake Ontario. The fire pumps discharge into a closed loop fire main system such that most single piping failures can be isolated and the system will remain operational.
Makeup water of up to 1075 gallons per minute could be provided by the above makeup systems. This flow capacity is adequate to keep spent fuel covered for water losses resulting from a break in the bottom of the pool of at least 2
10 in,
The design of the spent fuel pool and related structures precludes consideration of significant leakage from the pool as the result of drop accidents or earth-quakes. Potential spent fuel pool damage from missiles resulting from high winds are discussed in Niagara Mohawk's compliance to Regulatory Position 3.
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ATTAC'e!ENT 4-1 M P R ASSOCI ATES. INC.
February 24, 1976 Mr. W.
P., D' Angelo Niagara Mohawk Power Corporation 300 Eric Boulevard, West Syracuse, New York 13202
Subject:
Use of Vandenburgh Cask in Nine Mile Point Unit No.1 - Cask Drop Protection System
Dear Mr. D' Angelo:
The purpose of this letter is to forward the final results of an evaluation performed by MPR of the use of the Vandenburgh cask in the Cask Drop Protection System (CDPS) at Nine Mile Point Unit No. 1.
Preliminary results of the evaluation are contained in our letter to you dated August 8,1975. The final results reported herein do not differ significantly from the preliminary results given in our August 8,1975, letter. The main conclusions of our evaluation are summarized below.
1.
Relative Size of Casks The CDPS was designed for typical 30-ton, 75-ton, and 105-ton spent fuel shipping casks. The Vandenburgh cask (including at-tached base plate) weighs about 35 tons. The diameter of the Van-denburgh cask (~ 50 inches) is about the same as the typical spent fuel casks (~ 36 - 82 inches). However, the length of the Vanden-burgh cask (~ 134 inches) is much shorter than tne typical spent fuel casks (~ 195 - 210 inche s ).
The size of the Vandenburgh cask relative to typical spent fuel casks for which the CDPS was designed is shown in Figure 1.
2.
Hydraulic Performance Results of hydraulic performance analyses for the 35-ton Vanden-burgh cask and a typical 30-ton and 105-ton spent fuel cask are summarized in Table 1.
These results indicate that the maximum hydraulic load on the floor of the spent fuel pool and internal pres-sure inside the CDPS are less for the 35-ton Vandenburgh cask than for the design basis 105-ton spent fuel cask. The maximum impact 114o CONNECTICUT AVENu t. N. W.
WAswiNoToN. D. C. 2oC36 2o2-6s9 232o
M P R ASSOCIATES. INC. February 24, 1976 velocity is greater for the Vandenburgh cask than for the design basis cask. This is. due primarily to the shorter height of the Van-denburgh cask (* 134 inches) compared to the height of the design basis spent fuel cask (~ 200 inches) resulting in a greater possible angle of tilt of the Vandenburgh cask as it drops within the CDPS.
The greater angle of tilt results in a larger flow area around the base plate which results in a greater impact velocity. However, the greater impact velocity of the Vandenburgh cask is not control-ling because the kinetic energy of the lighter Vandenburgh cask at impact is less than the kinetic energy of the heavier design basis cask at impact. Therefore, the hydraulic performance of the Van-denburgh cask in the CDPS is considered acceptable.
3.
Imoact Loads Impact loads on the floor of the spent fuel pool for postulated cask drop accidents are summarized in Table 2 for the 35-ton Vanden-burgh cask and a 30-ton and 105-ton spent fuel cask. In all ca s e s, the impact loads for the 35-ton Vandenburgh cask are less than or equal to the impact loads for the 105-ton design basis cask, and are therefore acceptable.
4.
Stability Durine Acoroach to CDPS r
A 110-inch diameter base plate assembly for the Vandenburgh cask is shown on MPR Drawing 1085-10-01. With this base plate as sem-bly attached, the stability of the Vandenburgh cask during approach to the CDPS will be the same as a spent fuel cask with attached base plate. Therefore, the same interlock controlled approach path to the CDPS shown in Figure 2 that is used for spent fuel casks can also be used for the Vandenburgh cask.
5.
Eccentric Droo Analysis The motion of the Vandenburgh cask following a postulated eccentric drop accident was evaluated. Results of this evaluation indicate that there are two effects which tend to produce greater lateral and angular velocities in the case of the Vandenburgh cask as compared to a spent fuel cask of about the same weight.
The height of the Vandenburgh cask (~ 134 inches) is shorter than a typical 30-ton spent fuel cask (~ 200 inches). The shorter height of the Vandenburgh cask results in a smaller mass moment of inertia and thus, the resistance of the Vandenburgh cask to angular motion due to an eccentrically applied load is less.
F e---
c M P R ASSOCIATES. INC. February 24, 1976 The lifting system for the Vandenburgh cask (i. e., the lifting trunnions on the cask and lifting yoke) appears to be very con-servatively designed. Thus, the maximum eccentric load that can be applied is greater in the case of the Vandenburgh cask than a spent fuel cask of about the same weight. For example, the maximum eccentric load for the 35-ton Vandenburgh cask is estimated to be ~ 5. 6 times the cask weight whereas the maximum eccentric load for a 30-ton spent fuel cask is esti-mated to be ~ 4 times the cask weight.
As a result of these two effects, the angular velocity imparted to the Vandenburgh cask following an eccentric drop accident is calcu-lated to be ~ 8 - 9 times higher than the angular velocity of a spent fuel cask of about the same weight as shown in Figure 3.
The effect of the higher angular velocity for the Vandenburgh cask is that the 110-inch diameter base plate could conceivably catch on the top plate of the CDPS such that the cask could be tipped in a direction towards the spent fuel pool (i. e., the south direction) as shown in Figure 4.
Calculations have been performed to determine the effect on the CDPS of the cask impacting the side of the CDPS as shown in Figure 4.
Results of these calculations are summarized below.
The cask will not topple out of the CDPS since the center of gravity of the cask is well inside the CDPS and the local de-formation at the top of the CDPS is calculated to be less than 10 inches.
The maximum impact load on the floor of the spent fuel pool is calculated to be less than 1200 kips, which was the load for which the floor was analyzed.
The lateral loads on the CDPS are well within the design loads and energy absorption capability of the CDPS lateral support components.
For cases where the base plate does not catch the edge of the top plate following a postulated eccentric drop accident (i. e., the cask drops into the CDPS as intended), the impact loads and energies on the side of the CDPS for the Vandenburgh cask are less than the im-pact loads and energies for the design basis 105-ton cask.
M P R ASSOCIATES. INC. February 24, 1076 Based on the eccentric drop evaluations summarized above, the ex-isting CDPS at.Nine Mile Point is considered satisfactory for eccen-tric drop accid'ents' involving the Vandenburgh cask.
In surnrnary, it is concluded that the existing CDPS at Nine Mile Point Unit I will provide adequate cask dra, protection for the Van-denburgh cask. Please contact us if you have any questions concerning the results of our evaluation.
Sinc e r ely,
}
- /
./t..:/ w k.ke (. J. O d' John W. Johnson Enclosures cc: Mr. G. Gresock i
Mr. E. R. Klein
' Mr. C. V. Mangan j
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d TABLE 1
SUMMARY
- HYDRAULIC adALk' SIS 3 5-Ton 3 0- Ton 105 - Ton p,
Vand'bgh Spent Fuel Spent Fuel 1.
Max. Hydraulic Floor 129 156 357 Load, kips (1. 8 g's)
(2. 6 g's)
(1. 7 g's) 2.
Max. Internal Pressure, 10 12 32 psi 3.
Max. Impact Velocity, it/sec Straight-
.81
.27
.52 Cask Tilted 1.83
.76 1.42 Cask Tilted & Bent Base Plate 2.96 1.91 1.73 4.
Max. KE @ Impact, ft/ kip 9.52 3.40 9.76 a
TABLE 2
SUMMARY
- IMPACT LOADS i
3 5-Ton 30- Ton 105-Ton "E
I" Vand'bgh Spent Fuel Spent Fuel 4
1.
Drop onto Top Plate of CDPS, kips Straight 730 710 1000 Edge of Base Plate 146 309 309 2.
Impact with Bottom of CDPS, kips Straight 980 870 1000 Edge of Base Plate 146 309 309
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Hydraulic, kips 129 156 357 i
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ATTAC&ENT 4-2 O
SAFETY EVALUATION PLAtiT:
Nine Mile Point Unit 1 SYSTEM:
Redundant Hoisting System and Crane Movement Controls MODIFICATI0ft:
Change Washdown Area and Fuel Handling Procedure #16 l
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PREPARED SY:
Gregory J. Gresock DATE Oct.
4, 1977 REVIE'4E0 BY:
Peter E. Francisco DATE Oct.
4, 1977
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DATE / 0,[w'77 APPROVED BY:
/
SORC Review:
in/1-ts-
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SRA3 Approval:
2/3/73
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I I.
Redundant Hoisting Svstem and Crane Movement Controls A.
Present Design The Redundant Hoisting System and Crane Movement Controls and supporting safe _ty_ evaluation is described in a letter to Mr. D. J. SkovEolt, Assistant Director for Operating -
Reactors, Directorate of Licensing, U. S. Atomic Energy Commission dated July 26, 1973.
Briefly, this submiccal detailed the mechanical, electrical and structural features of the redundant hoist, and Egel cask handling
- procedures and crane movement controls, which are in-tended to assure controlled path movement during cask handling operations.
B.
Modification The modification to this system consists of moving the cask washdown tray from its present location to a location adjacent to the west side of the spent fuel pool (see the attached figure).
Fuel Handling Procedure <
(5 Number 16 will be amended to permit the Vandenburg cask to be raised 18 inches above elevation 340'-0 while in the washdown tray.
This evaluation only applies to the Vandenburg cask.
Other casks must be evaluated on a case-by-case basis.
To perform this modification, it will be necessary to plug 1
the two existing drain lines in the washdown tray and to install another drain line which will be aligned with the floor drain between the spent fuel pool and the reactor cavity.
Fuel Handling Procedure Number 16 will be amended to permit the crane operator to switch to Mode 1 when in the washdown tray to allow raising the crane to 18 inches above elevation 340'-0.
Procedure control or crane move-ment control modifications will be necessary to assure compliance with.the 18 inch limit.
However, crane move-ment control is considered the more reliable means of control.
C
f' C.
Analvsis An analysis has been performed which shows that if the Vandenburg cask were dropped straigh: down from 13 to 24 inches above elevation 340'-0" the support structure at the proposed washdown areas is such : hat the floor would not fail structurally.
Since the main consideration in cask handling operations is to maintain operating floor integrity, this mcdification does not adversely affect cask handling operations.
Another item of concern is the possibility of a cask tipping into the spent fuel pool or reactor cavity in the event of a straight or eccentric drop.
Analysis has been performed which concludes that if the cask were dropped from 18 inches it would not tip in' o the fuel pool or the reactor cavity.
II.
Si:e Operation Review Committee and Safety Review and Audit Board Review
('
Neither of the above has reviewed this modification.
III. Comeliance to NRC Standards (10CFR50.59)
A.
The probability of occurrence or the consequences of an acciden: or malfunction of equipment important to safety previously evaluated in the safety analysis report has remained the same, since the movemen: of the cask washdcwn tray and subsequent change in procedures to allow cask raising above the six inch limit will net result in a structural failure of the operating floor.
B.
The possibility for an accident or malfunction of a different type than any evaluated in the safety analysis report has remained the same.
C.
The cargin of safety, as defined in the basis for any technical specification, has remained the same.
There are no tech. specs. which apply to this sys:em.
Based on III A, 3, and C above, this modifica: ion does not constitute an unreviewed safety question.
P D.
No change is required in :he Technical Specificacions incorporated in the license.
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, muaxa 11tmL.00anismotscE h UMOHAWK ATTACH?!ENT !.-3 Syracuse
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o's=ct Septed er16. 1977
,,t. coo,3-N2.1-510 E.F. Treadwell/R.F. Oleck, Jr.
o,,
""r suasset fline Mile Point #1 W.R. D'Angelo to Vandenburgh Cask Handling Reference your letters to E.F. Treadwell dated August 31 and September 1,1977:
We have reviewed the possibility of lifting the subject cask 18 to 24 inches above the 340-0 floor of the' Reactor Building at the locatien requested in your referenced letters (between the Spent Fuel Pool and the Reactor Vessel).
This new position would place the centerline of the cask approximately S'-0 south of column line ft and 3'-0 west of column line 9.
At this approximate location, a straight drop of 18 to 24 inches of the Vandenburgh Cask should not result in structural failure of this floor. Hewever, as we have discussec, the possibility of the " tipping" of the cask should be investigated further by MPR Associates.
It is our considered opinion, however, that the existing cask handling procedure be used since " tipping" of the cask still remains an unreviewed safety question.
Also, we feel that this problem can be better remedied by modifying the method of decontaminating the cask (i.e. spray nozzles built into the wash-down tray).
/
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['[,[c E. F. Treadwell
@dd[,,b.
R. F. Oleck, Jr.
RF0:bc xc: E.R. Klein C.V. Mangan T. Perkins G. Gresock
-R E C EIV E D SEP 1 s 1977 C.
W. 4. 9 Ancus
Amcam 4-s M P R AssoclATES. lNC.
D October 12, 1977 Mr. G. Gresock Niagara Mohawk Power Corporation 300 Erie Boulevard, \\ Vest Syracuse, New York 13202
Subject:
Use of Vandenburgh Cask at Nine Mile Point Unit 1
Dear Mr. Cresock:
In accordance with your letter dated September 26,1977, MPR has performed cask tipping analyses to determine how high the Vandenburgh cask can be raised over the operating floor such that an eccentric drop ac-cident would not cause the cask to tip over when it impacts the floor. An eccentric drop accident is one in which the cask lifting trunnion or lifting yoke is assumed to fail on one side of the cask such that horizontal and angular motion is imparted to the cask as the other stde begins to pick up the load. The analyses were performed for the condition in which the 110-p inch diameter base plate is attached to the bottom of the cask. Based on the 5
results of the cask tipping analyses, it is concluded that the cask lower sur-face can be raised as high as 18 inches above the operating floor with no in-herent chance of tipping ITuowing an eccentric drop accident.
This conclusion is based on approximate but conservative cask tipping analyses. The main elements of these analyses are summarized b elow.
The cask is assumed to be raised a given height above the floor. The lifting trunnion on one side of the cask is assumed to fail. This lets the cask drop straight about 3 inches until the resulting slack in the sys-tem is removed as shown in Figure 1.
After the straight drop of about 3 inches the cable becomes tight.
.A s the cask continues to drop the load in the cable increases in direct pro-portion to the stretch of the cabic. Previous eccentric drop analyses indicate that the maximum force produced in the cable is approximately
- 5. 5 times the weight of the Icaded vandenburgh Cask or about 165 tons.
Since this force is significantly less than the minimum breaking strength of the cable of at least 625 tons, the cable should not break. During this time the vertical velocity of the cask center cf gravity is reduced and p
4 114e CcN %t:Ticur AvtNut. N. W.
WA$HINGTON. o, C. 2co3 6
- o2-6s9 23Co
M PR AssoclATEs. INC.
.2 -
October 12, 1977 l
horizontal and rotational velocity are imparted to the cask. The forces on the cask during this time interval are shown in Figure 2.
. As the cask continues to drop and rotate, the cask's rotation becomes large enough such that the intact cask trunnion moves up an amount suf-
-ficient to eliminate the stretch in tae cable as shown in Figure 3.
At this point, the cable force is removed from the cask.
The cask continues to drop and rotate with constant angular velocity un-til the base plate impacts the floor as shown in Figure 4.
The angle of the cask at impact, the amount of bending of the 1. 5" thick portion of the base plate, and the rotational kinetic energy of the cask at impact are determined. The cask is considered stable if (a) the rotational kinetic i
a energy of the cask at impact is less than the energy absorbed due to l
bending of the base plate, and (b) the cask center of gravity is on the j-stable side of the assumed pivot point, i. e., to the left of the pivot point i
shown in Figure 4.
h.
The assumed initial height of the cask was varied until the maximum height the cask could be raised and still be stable on impact was determined. This height was about 23 inches. To provide reasonable margin, it is recom-j
-f mended that the maximum height the cask lower surface is raised above the operating floor be limited to 18 inches with the 110-inch base plate installed.
It is not recommended that the cask be raised without the base plate in the area adjacent to the spent fuel pool since (1) the base plate provides con-i siderable additional stability to the cask, and (2) if the cask were to drop
]
while lifting it from the base plate, the large holddown blocks on the base plate could provide obstructions which tend to tip the cask.
t It should be noted that the analyses and conclusions discussed above apply only to the Vandenburgh cask. Pleas e contact us if you have any que s tion s.
Sincerely,
[f'
< & L.<. & t G..a 4
- w John W. Johnson l
cc: Mr. W. D' Angelo F
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Syracuse e.svoet 6,u, O 0ctober 12 1977,,uceo, W. R. D'Angelo
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SATJZY E'/ALL'ATION:
Change Mr T. E. Lempges CD P S L'a s h d o.m Chairman, Site Operations Review Ccmmittee Please schedule a SORC review of the a:: ached Safety Evaluation a: your earlies convenience and provide for a response as indicated below.
SORC should be informed that Nuclea: Engineering intends to submi:
the details of this modification :o che NRC.
The CDPS modification was submitted to the NRC prior to (m
installation; therefore, it is appropria:e :ha: the NRC should be aware of this modification to previously des criba ' crane controls.
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SORC has approved this modification.
SORC has not approved :his modification and ccmments are a:: ached.
e STATION MODIFICATICN CCORDINATCR e6 1
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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.1 REMOVAL OF CONTAISIENT HEAD DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3
(.
2/3shJ Maintenance Super
- o[r#d /
[Od-R. B. Abbott
(,
StationSuperintenden[tM 7bh7 (MIPNS)
T. J.
Perkins kM Juhl,,
Chairman of S.O.R.C,,
" ?2if...,
.T. E. Lempges
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ig a Summary of Paces Revision 1, dated February 1977, consists of pages 1 through 6 v
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. _ _ - _ -.. -.. - - = -, -.
NINE MILE POINT NUCLEAR STATION - UNIT NO. 1 MAINTF. NANCE PROCEDURE NO. MP-1.1 REMOVAL OF CONTAINMENT HEAD 1.0 PURPOSE This procedure describes the necessary steps to remove the floor plugs, storage pit shield plugs, spent fuel pool shield plugs, and the containment head.
2.0 PREREOUISITES 2.1 Plant Conditions - The reactor shall be in cold condition and the drywell deinerted and properly ventilated.
C 2.2 System Conditions - Reactor at 0 psig, less than 212 F.
2.5 Mark-Ups - Obtain mark-ups per Section 9 of NMPC Accident Prevention Rules for the following equipment:
(Valves shall be marked up closed.)
2.3.1 Isolation valve down stream of high pressure nitrogen gas storage pressure reducing station.
2.3.2 Bypass around high pressure nitrogen gas storage Pressure reducing station.
r 2.3.3 Nitrogen vapori:ing unit outlet valve located on nitrogen vapori:ing panel.
2.'4 Radiation Work Permit (RKP)
- An RKP shall be obtained per Section IIB of Radiation Protection Procedures for Reactor Building at elevation 340 ft.
The mark-up man shall be the maintenance foreman in charge of the work.
" Work Request" (KR) shall be 1
2.5 Maintenance Request Form obtained and used to document time, material used, labot required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Reactor building overhead crane, 125 T hoist and 25 T hoist, to ensure satisfactory operability per Maintenance Procedure No.
MP21.1, inspection sheet 21.1 A February 1977 MP-1 1 - I w_
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2.6.2 Floor plug shackles and slings per inspection sheet No. 1.1 A 2.6.3 Shield plug lifting rig, slings and shackles per
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inspection sheet No.1.1 B 1
2.6.4 Containment head strongback per inspection sheet No.
1.1C 3.0 TECHNICAL SPECIFICATIONS None Required 4.0 SPECIAL PRECAUTIONS 4.1 Follow requirements as posted for 340 ft level.
4.2 Special care shall be taken to ensure no foreign objects are accidently dropped into the spent fuel pool, reactor cavity or storage pit areas. Supervision to be notified if this should happen.
4.3 Strict adherence to radiation protection instructions that appear on the Radiation Work Permit is essential.
4.4 Immediately upon removal of guard railing sections to facilitate transporting shield
- plugs, provide safety precautions around reactor cavity to safeguard against personnel falling into cavity. Replace guard railing sections as soon as practicable to do so.
s 4.5 Wear hard hats when overhead crane is used to lift equipment.
5.0 SPECIAL TOOLS 5.1 Reactor building overhead crane,125 T and 25 T hoist.
5.2 Containment head strongback assembly.
5.3 Floor plug slings and shackles. (S-1) 5.4 Storage pit shield plug lifting rig, shackles and slings.
(S -
1) 1 5.5 Spent fuel pool shield plug slings and shackles. (S-5) 5.6 Electric impact wrench (1 in. drive) 21/8 in. socket.
February 1977 MP-1.1 2
6.0 REFERI'f.'CES 6.1 N>tPC Drawing 15132, Sheet 10.
6.2 N!!P Radiation Protection Procedures.
6.3 General Electric Servicing Equipment Manual GEK-722.
6.4
.V!P Maintenance Procedure MP-1.8.
7.0 PROCEDURE 7.1 Removal of floor plugs.
7.1.1 Place support pads on floor areas designated for storage of floor plugs.
7.1.2 1.ower 125 T hook and secure floor plug slings to it.
7.1.3 Raise hook and orient it over floor plug number 1.
y 7.1.4 Secure the slings to the four (4) lifting lugs on the floor plug.
7.1.S Remove the necessary sections of guard railing on the north side of the cavity. Check that the south-most sections are not in the secantial position for refueling bridge-clearance, but rather in their circumferential position around cavity.
7.1.6 Raise floor plug number 1 to no more than six (6) inches above the floor and transport it to its proper storage area. See ?O!PC Drawing 15132, Sheet 10.
7.1.7 Set the floor plug down and detach the slings.
7.1.8 Repeat the above procedure with floor plugs number 2, 3, 4, and 5.
7.2 Removal of storage pit shicId plugs.
7.2.1 Secure the storage pit shield plug shackles to the 125 T hook.
1 7.2.2 Raise the hook and orient it over plug number S.
7:2.3 Secure the lifting rig to the four (4) lifting lugs on the plug.
7.2.4 Remove the necessary sections of guard railing on the south side of the cavity.
' February 1977 MP-1.1 3
7.2.5 Raise plug number 8 to no more than six (6) inches above the floor and transport it to the south side of the reactor operating floor. Do not transport plug
. (L over the cavity area.
7.2.6 Set the shield plug down and detach the lifting rig.
7.2.7 Repeat the above procedure with storage pit shield plugs numbers 7 and 6.
7.2.8 After _ setting plug number 6 on the floor, leave the lifting rig attached to the plug.
Unhook one (1) pair of slings from the 125 T hook and place on top of the plug. Detach the other pair of slings from the lifting rig. These slings will be used to remove the spent fuel storage pool shield plugs.
7.3 Removal of spent fuel pool shield plugs.
7.3.1 With the one (1) pair of slings attached to it orient the 25 T auxiliary hook over shield plug number 11.
I 7.3.2 Lower hook and attach slings to the two (2) lifting lugs.
7.3.3 Remove the necessary sections of guard railing at the canal area.
7.3.4 Raise plug number 11 to no more than six (6) inches
(
above the ficor and transport it to its storage area.
See NNPC Drawing 15132 and 'WOTE" in Section 7.2.5 of this procedure for location.
7.3.5
' Set the shield plug down and detach the slings.
7.3.6 Repeat above procedure for plug number 10.
Plug number 9 shall be left in place for shielding purposes until all work in cavity is completed.
7.3.7 Remove slings from 25 T hook.
7.3.8 Replace all sections of guard rail.
February 1977 MP -1.1 - 4 m
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' 7.4 Removal of containment head.
7.4.1 Loosen all containment head hold-down nuts with impact wrench, pivot all hold-down bolts radially
(-
outward.
7.4.2 Lower 125 T hook into head strongback and attach strongback to hook by inserting the three pins into head strongback assembly.
7.4.3 Raise hook to verify strongback is attached to hook.
7.4.4 Raise head strongback from floor to over containment head.
7.4.5 Orient the strongback assembly over containment head and attach anchor shackles to lifting lugs.
7.4.6 Notify Operations and Radiation Protection prior to lifting of head.
7.4.7 Slowly raise containment head. Observe movement at each guide pin. Verify head is lifting level with no binding or restraint.
Maintain clearance of all other equipment.
7.4.8 Raise hea d to a position to clear guard rail around cavity. Move head west and north and position it over ficer plugs numbers 3, 4, and 5.
7.4.9 Place flange protectors on floor plugs and slowly lower the head onto them. Verify head is secure.
7.4.10 Remove head strongback from head by detaching anchor shackles from lifting lugs.
1 7.4.11 Remove head strongback from 125 T hook by pulling the three pins from the head strongback assembly and store in a proper location.
8.0 IN-PROGRESS INSPECTION During removal of floor plugs, shield plugs and containment head make a general inspection of plugs, head, and hold-down bolts.
If any defects are found, note them on the WR and inform the 1
maintenance supervisor as soon as possibic.
9.0 TESTING None Required.
February 1977 MP-1.1 - 5 e
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10.0 RETURN TO N0le1AL i
10.1' Replacement of the containment head is prescribed in maintenance procedure MP-1.8.
10.2 No mark-ups shall be c1 cared at this time.
I 10.3 Return the RIT.
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10.4 Complete, sign, and return hR form.
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February 1977 MP-1.1 - 6 f
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N!!!I. !!!!.li l'01::T !;t!Cf.I'A!! ;TATION - IJt!!T f;0. 1 Reactor I uilding Crane Overhaul test and inspection.hect for n
I>c r i ei.f i i-i n s n, e t i,,,,
Date
__ Equipment Piccc No.
_ System l!21.1A Check I.ist Tester's Name Unsat/ Sat Brid.c Structure 1.
2.
Trolley Structure 3'.
Bolting - Rivets 4.
Shcaves - Drums S.
Gears, Pins, Rollers 6.
Brakes 7,
Wheels 8.
Cranc flooks J
9.
Ropes 10, Lir.iit Switches k
11.
Controls - Contacts 12.
Lubrication 13.
I'liri"R Attach Magnetic Particle inspection for hooks to this Inspection Sheet.
Remarks:
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JII;I. !!!!.1: l*(ll:"! 1:llCI.1".A!! !;TATI()l: - Il!;1T l 0 1 Overhaul tent and inspect. inn sheet for Rc: ctor Cavity I'lut:s Slin;'s 'ar;! Shackles Date liqitipment l'iccc l'o.
Syste:a
- 1.lA Chect I.ist Tenter's ?!anic Unnat/ Sat t
1.
Top Cable Ring (2) 2.
Top : cek Splice (4) 3.
SliUE (4) 4.
Top Turnbuckle Pin (4)
Turr. buckle (4) 5.
Botten Turnbuckle Pin (4) 6.
Botter Shackle (4) 7.
8.
9.
10.
11.
12.
13.
Rccarks:
- !!
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"I ATI0:: - lit !T !.O. 1 Storanc Arca Sliichi Overhaul ter.t and ing ection r.heet for Plugs I.iftinn !!in
's Date Equipr:ent Piece No.
System n 1. p>
j Cheel; I.ist Tester'r.?!ane Unsat/ Sat Top Cabic Ring (2)
.1.
2, Top ' tech. Splice (4) 3.
Sling (4) 4.
Top Turnbuckle Pin (4) 5.
Turnbuckle (4) 6.
Bottc= Turnbuckle Pin (4) 7.
Botton Shack!c (4) 8.
Liftiti; Trc e (1) i
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9.
10.
11.
12.
13.
Remarks:
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- !!!!:l; :ll!.li l'ul::T ;;tK:ll31t ';TATIO:: - II:;1T i:0. I Over!.aul test und in pection sheet for
!!rywell llead I.i f t i ne, P.i t
.g Date Iquipment Piccc No.
System
- 1.1C 4
Chech I.ist Tester's Name Unsat/ Sat Strongback Assembly (1) 3, 2.
Shackles (9) 3.
Eyebcit + Pin flug end) (3) 4.
Pins - (hcod end)
(3) 5.
6.
7.
S.
9.
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10.
11.
12.
13.
l Remarks:
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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION
'JNIT NO. 1 MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.2 RDf0 VAL OF REACTOR VESSEL HEAD DATE AND INITIALS APPROVAL BY NAME REVISION I REVISION 2 REVISION 3 2l.? S/ 7')
Maintenance Super 'so
.. [
/2/3[,b k
R. B. Abbott
'U g
Station Superintendent 3g (NMPNS)
[M T. J. Perkins
[/V ChairmanofS.O.R.C<k.<
e
. fs'.y,.. /
T. E. Lempges
/
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/
i Summary of Patres Revision 1, dated February 1977, consists of pages 1 through 6.
a i
NINE MILE POINT NUCLEAR STATION - UNIT NO. 1 MAINTENANCE PROCEDURE NO. MP-1.2
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REMOVAL OF REACTOR VESSEL !! FAD 1.0 PURPOSE This procedure describes the necessary steps to remove the reactor vessel head.
2.0 PREREQUISITES 2.1 Plant Conditions - The reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
2.2 System Conditions Reactor at 0 psig, temperature 212 F, containment head removed.
2.3 Mark-ups - Obtain mark-ups per Section 9 of NMPC Accident Prevention Rules on following equipment:
(valves shall be marked up closed and breakers de-energi:ed, racked out, and marked up.)
2.3.1 Head vent:
a.
BV 37-01 Motor Breaker PB155 b.
BV 37-02 Motor Breaker PB155 c.
BV 37-06 Motor Breaker PB155 2.3.2 Head spray:
a.
BV 34-01 Motor Breaker 2.3.3 CRD valves:
a.
301-8A b.
301-8B An RWP shall be obtained per 2.4 Radiation Work Permit (RWP)
Section IIB of Radiation Protection Procedures for Reactor Building at elevation 340 ft and reactor cavity. The mark-up man will be the maintenance foreman in charge of the work.
" Work Request" (WR) shall be 1
2.5 Maintenance Request Form obtained and used to document time, materici used, labor required, and date job is performed.
February 1977 MP-1.2 - 1
2.6 Pre-Inspections 2.6.1 Reactor building overhead crane 125,.25 and 1/2 T hoists per maintenance procedure No.
MP. 21.1
(
Inspection Sheet 21.1A.
2.6.2 Vessel head insulation lifting rig per Inspection Sheet No. 1.2A.
2.6.3 Stud tensioners and stud tensioner lifting rig assembly per Inspection Sheet No.1.23.
2.6.4 Head lifting assembly per Inspection Sheet No. 1.2C.
1 2.6.5 Vessel head slings, shackles and turnbuckle assembly per Inspection Sheet No. 1.2D.
3.0 TECHNICAL SPECIFICATIONS None Required 4.0 SPECIAL PRECAUTIONS 4.1. Follow requirements as posted for 340 ft level.
4.2 Special care shall be taken to ensure that no foreign objects are accidently dropped in the spent fuel pool, reactor cavity or storage pit areas.
Supervision to be notified if this should happen.
4.3 Strict adherence to radiation protection instructions that appear on the RKP is essential.
4.4 Radiation Protection must be notified whenever a change in radiation, contamination, or airborne contamination is at all possible.
4.5 Wear hard hats when overhead crane is used to lift equipment.
5.0 SPECIAL TOOLS 5.1 Reactor building overhead crane 125 T, 25 T and 1/2 T hoists j
5.2 Head insulation lifting rig 5.3 Stud tensioners and stud tensioner lifting rig 5.4 Head vent fan assembly 1
S.5 Nut and washer rack
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February 1977 MP-1. 2 - 2
1 5.6 licad strongback lifting assembly 5.7 Vessel head slings, shackles and turnbuckles assembly 5.8 Head stud rack
6.0 REFERENCES
6.1 NMPC Drawing 15132, Sheet 10 6.2 General Electric Servicing Equipment Manual GEK-722 6.3 Biach Industries Inc., " Instruction and Maintenance.'tanual for 1,680,000 lb. Tensioner Model d:-5039."
6.4 NMPC Accident Prevention Rules 6.5 NMP Radiation Protection Procedures 7.0 PROCEDURE 7.1 Unbolt flanges of the three (3) instrument lines to the vessel head: head vent, head spray, and wide range level control.
I Caution:
a.
Radiation Protection to be notified and present at time of opening of flange joint.
b.
Control Room is to be notified that you are removing the, pipe on the wide range control.
,t 7.2 Unbolt the above instrument line flanges at ventilation openings to drywell and remove pipes from cavity with 25 T hoist.
See NMPC Drawing 15132, Sheet 10, and note below.
7.3 Install blanks on the three (3) head flanges.
1 Caution:
Blank flange on the ' Vide level control" is not to be
" SEALED."
(Level indicator has to breathe with the atmosphere.) Use flat washer between flange faces.
7.4 Unbolt all ventilation ducts and remove them from the cavity.
See NMPC Drawing 15132, Sheet 10, for their storage locations on El. 340 ft.
7.5 Place grating sections over ventilation openings to drywell.
7.6 Prior to removal of head insulation " carousel," Instrumentation and Control shall remove all thermocouples installed on safety valves and vessel head.
This may be done at any time after removal of containment head.
February 1977 MP-1.2 - 3 r
7.7 Attach vessel head insulation lifting rig to 25 T hook, orient I
the rig over insulation and attach Icgs.
Raise insulation slowly and check for any binding or hang-ups.
When free of reactor head, lift insulation out of cavity and locate it on
's top of floor plugs numbers 1 and 2 in northeast corner of operating floor.
7.8 Prepare the stud tensioner and lifting rig assembly according to Section I,
" Pre-Operating
" Instructions,"
of Siach Industrics Inc.,
" Instruction and Maintenance Manual for 1,680,000 lb. Tensioner, Model #2-5039."
7.9 Using the 25 T auxiliary hoist, follow the procedure written in the Biach Industries Inc.,
" Instruction and Maintenance Manual,"Section II, Operating Instructions, and Section III, Programming, Parts 3.1 and 3.5.
Nuts shall be loosened using a 2-pass program.
NOTE:
Prior to the Sacond pass, Operations must be notified to reduce vessel water level to below the vessel flange.
7.10 Raise stud tensioner rig out of cavity and place in designated storage area.
7.11 Install head vent fan assembly to head vent flange and purge i
vessel head of radioactive gases.
7.12 Lower nut and washer racks into cavity, remove nuts and washers
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from studs and place in racks.
Lift leaded racks out of cavity and stack against north wall operating floor.
7.13 Install stud thread protectors on all studs except No.1 and No.32.
Install guide pins on No.1 and No.32.
7.14 Lower 125 T hook into vessel head strongback and attach strongback to hook by inserting the three pins into the head I
strongback assembly.
7.15 Raise strongback from floor and attach slings to strongback.
7.16 Orient the lifting assembly over vessel head, and attach slings 1
to the lifting lugs with the anchor shackles.
7.17 Slowly apply load to head lifting rig. Verify head is raising evenly and level. Maintain cicarance between studs and stud openings in head.
NOTE:
When ready to lift head, contact Radiation Protection to survey and monitor for increased radiation and airborne conditions.
Radiation Protection will February 1977 MP-1.2 - 4 M
dicate when vessel head has been adequately purged and may be lifted out of cavity. When lifting head has been authori:ed, remove the purging apparatus out k
of the cavity.
7.18 Raise vessel head slowly until clear of studs and guide pins.
this time.
NOTE:
A11' personnel shall leave the cavity at 7.19 Continue to raise head out of cavity and transport it to the vessel head pedestal.
1 7.20 Slowly lower head onto pedestal.
1 7.21 Remove lifting assembly from head by detaching archor shackles from lifting lugs.
7.22 Remove head strongback from 125 T hook by pulling the three y
in a proper pins from the head strongback assembly and store location.
7.23 Attach polyethylene sheeting to underside of head to contain contamination.
7.24 Vessel head guide pins on studs No.1 and No. 32 may be removed at this time and stud protectors placed on these studs.
7.25 Lower the head stud rack into the cavity, remove the four (4) east ve:sel head studs (Nos.15-18), place in rack, and remove See
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rack out of cavity and place in designated storage area.
2-1 General Elcetric Servicing Equipment Manual GEK 22, pages through 2-3, for description and diagram of head stud rack.
7.26 Reno <e the four (4) or five (5) east drywell head hold-down bolts.
7.27 Remove the east drywell head guide pin.
8.0 IN-PROGRESS IN3PECTION 8.1 While performing maintenance procedure, make a general inspection of instrument lines and flanges, ventilation piping, I
head insulation, head nuts, studs and washers, vessel flange and vessel head.
If any defects are found, document them on the WR and inform the Maintenance Supervisor as soon as possible.
9.0.T.E. STING None Required February 1977 MP-1.2 - 5
.10.0 RE'nJRN TO NOR4\\L 10.1 Replacement of the Reactor Vessel Head is prescribed in Maintenance Procedure StP-1.7.
.10.2 No Mark-ups shall be cleared at this time.
10.3 Return the RWP.
10.4 Complete, sign, and return the WR form.
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' February 1977
. MP-1. 2
, 6 m
E NIN!i MII.li POINT Nt!CLIL\\R STATION - UNIT NO.1 Overhaul test and inspection sheet for Reactor Building Crane Perin lie insnectinn Date Equipment Piccc No.
System
- 21.1A Check List Tester's Name Unsat/ Sat 1.
Bridge Structure 2.
Trolley Structure 3',
Bolting - Rivets 4.
Sh' eaves - Drums S.
Gears, Pins, Rollers 6.
Brakes 7.
Wheels 8.
Crane Hooks 9.
Ropes
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10.
Limit Switches 11.
Controls - Contacts 12.
Lubrication 13.
Wiring Remarks:
Attach Magnetic Particle inspection for hooks to this Insuection Sheet.
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illfil; !111.11 l'Oi!.T !:l!CI.I'.All STATIO*: - I!!!!T ::0. 1 Overhaul tc:.t and inspection sheet for itx. IIcad Innulation I.if tin;; Itir.
Date Equipment l'iccc ?Jo.
System
- 1.2A Cheek I.ist Tester's Name Unsat/ Sat 1.
Top Ring (1) 2.
Mech. Splice Top (3)
Cabic (3) 3.
! tech. Splice Bottom (3) 4.
Turnbuckles (3) 5.
H ks (3) 6.
7.
8.
9.
10.
11.
12, 13.
itemarks:
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15I!;l. !!!!.l. l'Oi!il t;ilr!!.l.Al'. f.TA'l lo:: - In:lT ;o. 1 Tensioner I.iftinn itin Overhaul ter.t and inr.pection sheet for.
t l'1.2B Date Equipment Piccc No.
System Check 1.ist Tester's Name Unsat/ Sat Top Ring-(1) 1.
Top !!ech. - Splice (4) 2.
Cabic (4) 3'..
B tto: '!cch. Splice (4) 4.
5.
Bottom Pin (4) 1 t
6.
Eye Bolt (4) 7.
Frame (1) 8.
Tensioner Support-Cables (4)
(4) 9.
!cch. Splico 10.
!!coks (4) 11.
Stud Tensioners (5) 12.
13.
Remarks:
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Nlt:I: !!!!.l. l'Oi!.T ?:llCl.l:A1: ;TATIO!: - II:!!T ;0 1
Overhaul ter.t an<1 insp<etion sheet for Itcactor ife:nl Liftinn Asser bly C
Date 1(luipment Piccc No.
Synten
- 1.2C and 1.2D 4
Chech 1.ist Tester's Name Unsat/ Sat l:
1, Lifting Assc=bly Pins (1)
Head Bolts G ?uts (3) l 2.
3.
Shack!cs (3) i 4.
3 Mech. Splices (3) 5.
Slings (3) 6.
Lower !!ech. Splices (3) 7.
Top Turn Buckle Bolts (3)
Turnbuckles (3) 8.
L wer Turnbuckle Bolts (3) 9.
i c-(
10.
11.
12.
13.
Remarks:
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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION --UNIT NO. 1 MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.3 REMOVAL OF REACTOR VESSEL STEAM DRYER DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3
(
Maintenance Super
/
/ y((
- Jh/?([.
R. B. Abbott bl7 /-77 f
Station Superintendent [MEp (NMPSS) f/
T. J. Perkins 7f /
Chairman of S.O.R.C
/
T. E. Lempges '/h
^ I d innt 62 <[i +. t
//
Summarv of Pages Revision 1, dated February 1977, consists of pages 1 and 3.
i i
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NINE MILE POINT NUCLEAR STATION - UNIT NO. 1 MAINTENANCE PROCEDURE NO. MP-1.3 k
RD10 VAL OF REACTOR VESSEL STEAM DRYER 1.0 PURPOSE This procedure describes the necessary steps to remove the steam dryer from the reactor vessel.
2.
PREREOUISITES 2.1 Plant Conditions - The reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
Reactor level slightly below the flange 2.2 System conditions joint, vessel head removed.
All mark-ups obtained for removal of vessel head 2.3 Mark-ups (see Maintenance Procedure 1.2) shall be retained.
An RWP shall be obtained per 2.4 Radiation Work Permit (RWP)
Section IIB of Radiation Protection Procedures for reacter building at elevation 340 ft anc reactor cavity. The mark-up man will be the maintenance foreman in charge of the work.
" Work Request" (WR) shall be
~
2.5 Maintenance Request Form
('
obtained and used to document time, material used, labor 1
required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Steam dryer hold-down-tool per Inspection Sheet No.
1.3A 2.6.2 Steam dryer lifting apparatus per Inspection Sheet No. 1.3B 2.6.3 Reactor building overhead crane, 125 T hoist per Maintenance Procedure No. 21.1 Inspection Sheet No.
21.1A 3.0 TECllNICAL SPECIFICATIONS None Required 4.0 SPECIAL PRECAUTIONS 4.1 Follow requirements as posted for 340 ft level.
MP-1.3 - 1 February 1977 i
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4.2 Special care shall be taken to ensure that no foreign objects are accidentally dropped in the spent fuci pool, reactor cavity or storage pit areas.
Supervision to be notified if this k.-
should happen.
4.3 Strict adherence to radiation protection instructions that appear on the RWP is essential.
4.4 Radiation Protection must be notified whenever a change in radiation, contamination, or airborne conditions is at all possible.
5.0 SPECIAL TOOLS 5.1 Steam dryer hold-down tool 5.2 One (1) section of actuating pole 5.3 Steam dryer lifting apparatus 5.4 Reactor Building everhead crane, 125 T hoist 5.5 Water sprinklers and hose 5.6 Underwater lights
6.0 REFERENCES
6.1 General Electric Servicing Equipment Manual GEK-722 6.2 Nine Mile Point Radiation Protection Procedures 7.0 PROCEDURE 7.1 Position the stean dryer laydown ring pad in the west end of the storage pit equidistant to the north, south and west walls of the pit.
7.2 Connect the steam dryer hold-down tool to one section of actuating pole.
See General Electric Servicing Equipment Manual GEK-722, pages 2-29 through 2-32, for description of these tools and their use.
7.3 Unlock each of the four (4) steam dryer hold-downs with the hold-down tool.
7.4 Attach steam dryer lifting slings to 125 T hook. Orient the lifting frame over the dryer and attach each of the four (4) lifting devices to the four (4) lugs on the dryer. See General Electric Servicing Equipment Manual GEK-722, pages 2-13 and 2-14, for instructions and diagram.
(
April 1974 MP-1.3 2
hoses and sprinklers, connected to condensate transfer Prepare 7.S supply, around storage pit area to keep dryer wet as soon as it is moved to storage pit.
(
7.6 Notify Radiation Protection and Operations prior to lifting dryer.
7.7 Raise dryer slowly and verify it is lifting evenly with no it into binding. Raise until cicar of head studs and transport storage pit.
personal shall leave reactor cavity area if radiation NOTE:
All level increases.
7.8 Slowly let dryer down onto ring pad.
7.9 Disconnect lifting rig from dryer.
on condensate transfer supply to sprinkler system and 7.10 Turn adjust sprinklers to afford maximum possible wetting of dryer.
Sprinklers must be kept on until storage pit is flooded for moisture separator storage.
8.0 IN-PROGRESS INSPECTION l
8.1 Make a general inspection of the steam dryer for cracks and i
weld failures. Note such defects on the KR and inform the Maintenance Supervisor as soon as possible.
9.0 TESTING None Required 10.0 RETURN TO NOR'!AL of the reactor vessel steam dryer is prescribed in 10.1 Replacement Maintenance Procedure MP-1,6 10.2 No mark-ups shall be cicared at this time 10.3 Return the RWP 10.4 Complete, sign, and return WR form
(
February 1977 MP-1.3 - 3
,-~
I NINI; 1111.1: l'Ol!.T t;t:(;1.1:Al: !;TATluN - ll!'IT ;;0. 1 l
1 Overhaul test anti inr.pection r,heet for Steam l>ryer linf atchine, Total 13r.l:9512-C1
- I 3^
Date liquip:nent Piccc No.
System Checi: List Tester's Na ::e Unr.at/ Sat 1.
Unlatching Tool (1) 2.
Actuating Pole (1) 3.
~4.
5.
6.
7.
8.
9.
('
10.
r 11.
12.
13.
Remarks:
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151!11: :lli.l. Pul:TI' f;llCl.I' Alt STATION - IlNIT !!O. 1
\\
-Overhaul test and inspection sheet for Steam tiryer T. Ffoistort-Sepa rn to r i
Sliny,s and I:quipinent 700lmpolvi l Date liquipment Piccc No.
System 1.3n 1
4 Chech List Tester's Name Unsat/ Sat i
1.
Top Cable Rin9s (7)
Top Cable. tech. Snlice (4) s 2.
3',
Cabic (4) l 4,
Dottom.*4cch. Splice (4) 5.
Lifting Pins (4) 6.
Upper Guide (4) 7.
Rack 6 Pinion (4)
Lower Guide (4) 8.
L (4)
BAE 9.
10.
Frame (1)
. s 11.
12.
13.
I Remarks:
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Hit:1. f.tll.l; Poli.T i;t!Cl.l Alt !;TATlo:: - litilT 240 1 Iteactor Ilullilinn Crane Overhaul test and in:;pection sheet for l'e r i t ali c I ti.n c t i n.v.
Date Equipment Piccc No.
_ _ _ System
- 21.1A Chech Iist Tester's ?!ame Unsat/ Sat 1.
liridge Structure l
2.
Trolicy Structure 3',
Bolting - Rivets 4.
Shcaves - Drums 5.
Gears, Pins, Rollers 6.
Brakes 7.
IVheels 8.
Cranc Ilocks 9.
Ropes 10.
1.imit Switches f
11.
Controls - Contacts 12.
Lubrication 9
13.
Ifirin,q i
Attach Magnetic Particle inspection for hooks to this Inspection Sheet.
Remarks:
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NIAGARA 3!CILWK POWER CORPORATIO!:
NINE ?!ILE POINT NUCLEAR STATION - C' IT NO. I MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.4 REMOVAL OF REACTOR VESSEL 310ISTURE SEPAPATOR -
DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISIO. 2 REVISIO.' I
(
.ph s/77 Maintenance Supervisor kdc
[2Ob e
R. B. Abbott
/CN StationSeperintenden[t [
N3[7[
(t3!PNS) d y)
T. J. Perkins Chairman of S.O.R.C.
f.
T. E. Lempges
{($
fe na.785 I.'s.u.o j
Summary of Paces and S.
Revision 1, dated February 1977, consists of pages 1
NINE MILE POINT NUCLEAR STATION - UNIT NO. 1
(
MAINTENANCE PROCEDURE NO MP-1.4 REMOVAL OF REACTOR VESSEL MOISn!RE SEPARATOR 1.0 PURPOSE This procedure describes the final steps to prepare the reactor cavity for flooding, to remove the reactor vessel moisture separator, and to remove canal gates for refueling.
2.0 PREREQUISITES 2.1 Plant Conditions - The reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
Reactor level slightly below the flange 2.2 System Conditions joint, steam dryer removed.
All mark-ups obtained for removal of vessel head 2.3 Mark-ups (see Maintenance Procedure No.1.2) shall be retained.
An RWP shall be obtained per 2.4 Radiation Work Permit (RWP)
Section IIB of Radiation Protection Procedures for Reactor Euilding at elevation 340 rt anc reactor cavity. Th,e mark-up man will be the maintenance foreman in charge of the work.
(
"Nork Request" (WR) shall be 1
2.5 Maintenance Request Form obtained and used to document time, material used, labor.
required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Reactor building overhead crane per Maintenance Procedure No. 21.1 Inspection Sheet No. 21.1A 2.6.2 Shroud head bolt wrench per Inspection Sheet No.1.4A 2.6.3 Moisture separator lifting apparatus per Inspection 1
Sheet No. 1.3B 1
3.0 TECi1NICAL SPECIFICATIONS None Required
-(_
Mp-1.4 - 1 February 1977 m
4.0 SPl!CIAL PRI:CAttrIONS 4.1 Follow requirements, as posted for 340 ft level.
4.2 Special care shall be taken to ensure that-no foreign objects are accidentally dropped in the spent fuci pool, reactor cavity, or storage pit areas. Supervisien to be notified if this should happen.
4.3 Strict-adherence to radiation protection instructions that appear on the RWP is essential.
1 4.4 Radiation Protection must be notified whenever a change in radiation, contamination, or airborne conditions is at all possible.
5.0 SPECIAL TOOLS 5.1 Reactor building overhead crane, 125 T, 25 T and 1/2 T hoists.
5.2 Shroud head bolt wrench.
5.3 Steam line plug installation tool.
5.4 Actuating pole and J hook or L hooks.
4 5.5 Fuel pool shield plug slings and shackles.
5.6 Moisture separator lifting apparatus.
5.7 Fuel pool canal gate slings and shackles.
5.8 Under water lights.
6.0 REFERENCES
6.1 General Electric Servicing Equipment Manual GEK-722 6.2 General Electric Servicing Equipment Manual GEK-33101A 6.3 NMPC Drawing 15132, Sheet 10.
6.4 NMPC Drawing 15194 6.5 NMP Radiation Protection Procedures 7.0 PROCEDURE 7.1 Unlocking moisture separator
(,
MP.1.4 - 2 April 1974
sm 7.1.1 Loosen and unlock moisture separator holddown bolts (shroud hold-down bolts) using the shroud head bolt wrench.
(
a.
Lower wrench over bolt to be loosened. Rotate inner wrench handle to engage the belt, locating tab with locator socket.
Push down and hold outer wrench to disengage the
- retainer, and rotate vrench handle counterclockwise until the nut comes in contact with the stop.
Note:
Should problems arise in loosening, hold down bolts, contact supervision immediately for assistance.
c.
The bolt locating tab indicates the position of the T bar. The locating tab pointing toward the center of the vessel indicates T bar in unlocked position.
1.
See General Electric Servicing Equipment "anual GEK-722, pages 2-15 and 2-16.
7.1.2 Visually check that all hold-down bolts are unlocked and remove bolt wrench frem cavity.
7.2 Preparing cavity for flooding 7.2.1 Install main steam line plugs per General Electric Servicing Equipment Manual GEK-33101A.
7.2.2 Install blanks on ventilation ducts on cavity wall.
7.2.3 Remove plugs from cavity drain lines. Notify station shift supervisor.
7.2.4 Remove grating sections on cavity floor from cavity and install cover plates
(" silver dollars")
on ventilation openings to drywell.
Check that each plate has two (2) gaskets securely cemented to its underside.
Bolt down covers and air test each one for leakage with 5 psig service air.
7.2.5 Inspect reactor cavity and remove all tools and equipment to operating floor.
7.2.6 Remove spent fuel pool shield plug No. 9 with 25 T hook and place in designated storage area.
i
)
(_
MP-1.4 - 3 April 1974 r
7.2.7 Remove polyethicne wrapping from Portabic Radiation Shicid. Using the 125 T hook, lift the shield and transport to the spent fuci pool cavity canal and lower into place.
7.3 Removing moisture separator 7.3.1 Attach separator lifting frame slings to 125 T hook.
Orient the lifting frame over the separator and attach each of the four (4) lifting devices to the four (4) lugs on the separator. See General Electric Servicing Equipment Manual GEK-722, pages 2-13 and 2-14, for instructions and diagrams.
7.3.2 Notify Radiation Protection and Operations that moisture separator is ready to be lifted.
7.3.3 Slowly raise moisture separator approximately two (2) feet and verify it is lifting evenly with no binding.
7.3.4 Continue to raise separator as Operations raises water level, maintaining approximately two (2) feet of water above separator.
7.3.5 Raise separator until clear of head studs and storage pit ledge and transport to storage pit.
7.3.6 Slowly lower separator onto the four (4) support pedestals, making sure the four (4) support less on the separator maten un witn tne pedestals.
7.3.7 Detach ' slings from 125 T hook and tie off to the railing around storage pit.
7.3.8 Operations shall continue to raise water level to normal level in cavity and storage pit.
7.4 Removing fuel pool canal gates 7.4.1
-Remove large gate first. Attach two (2) slings to 25 T hook. Center hook over large gate and attach slings to gate lifting lugs.
7.4.2 Loosen hold-down jack. Turn screws counterclockwise to break seal. Remove jacks when seal is broken.
7.4.3 Slowly raise gate until free of pins, and move to storage rack in fuci pool.
Set gate on rack and remove slings.
(
MP-1.4 - 4 April 1974 7
- _ ~ - _
7.4.4 Repeat above procedure for small gate.
7.4.5 Sec NMPC Drawing 15104 for gate assembly and details.
8.0 IN-PROGRESS I.NSPECTION 8.1 Make a' general inspection of moisture separator for cracks and weld failures. Note any defects on the WR and inform 1
the Maintenance Supervisor as soon as possible.
9.0 TESTING None Required 10.0 RETURN TO NORMAL 10.1 Replacement of reactor vessel moisture separator is prescribed in Maintenance Procedure MP-1.5 l
10.2 No mark-ups shall be cleared at this ti=c 10.3 Return the RWP.
j 10.4 Complete, sign, and return WR form g
(.
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MP-1.4 - 5 February 1977
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I:lt:l; Mt 1.I'. l'ill:.T f:tX:1.I. Alt iTNIIuti - UtilT too. I Overhaul test aint inr.pection sheet for llenctor fluildinn Crane l'a risuf i c f n. i e c t i nin Date I:quipment Piece No.
System if21.1A Chech I.ist Tester's Name tinsat/ Sat i
1.
Brid;te Structure 2.
Trolley Structure 3'.
Bolting - Rivets 4.
Sheaves - Drums 5.
Gears, Pins, Rollers 6.
13 rakes 7.
l'ihecis 8.
Crane flocks 9.
Ropes 10.
Lit::it Switches
[,
Controls - Contacts 11.
12.
Lubrication 13.
h'i ring Attach Magnetic Particle inspection for hooks to this Insnectien Sheet.
Remarks:
1 I
7 e
NINE Mll,1! I'0 INT NilCLI: Alt STATION - lJNIT NO. 1 Overhaul test and inspection sheet for Shroud licad Bolt Wrench Date __
Equipment Piccc No.
System 11.JA t
Check List Tester's Name Unsat/ Sat 1.
External. Ext. Rod (1) 2.
Internal Ext. Rod (1) i 3.
4.
s.
6.
7.
8.
9.
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10.
11.
12.
13.
Remarks:
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NI:51: lIll.I: l'0 INT !11N:1.lAR !;TATION - II:;lT l'O.1 Overhat:1 test and itit.pection slicct for St easii Dryer ti Sfoistiere Senar: tn Slings and l'.<ptipw nt 70f.1:Minil'Tl
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Date 1:quipment Piccc No.
System 1.3n Chech 1.ist Tester's ':ame Unsat/ Sat 1.
Top Cabic Rin.:s (2) 2.
Top Cable Mcch. Snlice (4) 3',
Cable (4) 4.
Bottom Mech. Splice (4) 5.
Lifting Pins (4) 6.
Upper Guide (4) 7, Rack ~G Pinion (4) l Lower Guide (4) 8.
1 BAR (4) p, Frame (1)
(.
10.
11.
12.
13.
Remarks:
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.7 NIAGARA M0ll\\WK POWER CORPORATICN NINE MILE POINT NUCLEAR STATION - UNIT NO. 1 MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.S INSTALLATION OF REACTOR VESSEL MOISTURE SEPARATOR DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3 37/H/7'l Maintenance Supervisom,
([
R. B. Abbott
[dd [Ld, 6 C,.
[/hdb
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Station Superintendent 3[3['I/
(!31PNS)
T. J. Perkins b fO f/pd Chaiman of S.O.R.C.
I [O
/'
T. E. Lempges
[
+f Sumary of Paces Revision 1, dated February 1977, consists of paces 1, 6, and 7.
s L
NINE ?-IILE POINT NUCLI2it STATION - UNIT NO.1 MAINTENANCE Pit 0CEDURE MP-1.5
(
INSTALLATION OF REACTOR VESSEL MOISTURE SEPARATOR 1.0 PURPOSE This procedure describes the necessary steps to install the canal gates and the reactor vessel moisture separator.
2.0 PREREQUISITES 2.1 Plant Conditions - the reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
moisture separator positioned in storage 2.2 System Conditions pit, cavity and storage pit flooded.
all mark-ups obtained for removal of vessel head 2.3 Mark-ups (see Maintenance Procedure 1.2) shall be in effect.
An RKP shall be obtained per 2.4 Radiation Work Permit (RWP)
Section IIB of Radiation Protection Procedures for Reactor Building at elevation 340 ft, and the reactor cavity. The mark-up man shall be the maintenance foreman in charge of the work.
(
2.5 Maintenance Request Form
" Work Request" (WR) shall be 1
\\
obtaincd and used to document time, material used, labor required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Reactor Building overhead crane per Maintenance Procedure No. 21.1 Inspection Sheet No. 21.1A 2.6.2 Shroud head bolt wrench per Inspection Sheet No. 1.4A 2.6.3 Moisture separator lifting apparatus per Inspection Sheet No. 1.3B 3.0 TECHNICAL SPECIFICATIONS None Required-4.0 SPECIAL PRECAUTIONS 4.1 Follow requirements as posted for 340 ft. level.
MP-1.5 - 1 February 1977 wm
4.2 Special care shall be taken to ensure that no foreign objects are accidentally dropped in the spent fuel pool, reactor cavity, or sterage pit areas. Supervision to be notified if this should happen.
4.3 Strict adherence to radiation protection instructions that appear on the RWP is essential.
4.4 Radiation Protection must be notified whenever a change in radiation, contamination, or airborne conditions is at all possible.
5.0 SPECIAL TOOLS 5.1 Reactor Building overhead crane 125 T, 25 T and 1/2 T hoists.
5.2 Shroud head bolt wrench.
5.3 Steam line plug installation tool.
5.4 Actuating pole and J hook or L hook.
5.5 Fuel pool shield plug slings and shackles.
5.6 Moisture separator lifting apparatus.
5.7 Fuel pool canal gate sli gs and shackles.
5.8 Condensate transfer hoses.
5.9 Liqua-Blaster.
5.10 Torque wrench.
5.11 Underwater Lights
6.0 REFERENCES
6.1 General Electric Servicing Equipment Manual GEK-722.
6.2 General Electric Servicing Equipment Manual GEK-33101A.
6.3 NMPC Drawing 15132, Sheet 10.
6.4-NMPC Drawing 15194.
6.5 NMP Radiation Protection Procedures 7.0 PROCEDURE 7.1 Installing Fuci Pool Canal Gates MP-1.5 2
April 1974
7.1.1 Install small gate first. Attach 2 slings to 25 T hook. Center hook over small gate in spent fuci pool storage rack and attach slings to gate lifting lugs.
7.1.2 Lift gate, transport to canal, and install in its proper slot.
7.1.3 Install hold-down jack and tighten screws (turning clockwise) to seal the gate.
7.1.4 Remove the slings from the gate lifting lugs.
7.1.5 Repeat above procedure for installation of large gate.
7.1.6 See NMPC Drawing 15194 for gate assembly and details.
7.2 Installing Moisture Separator 7.2.1 1he moisture separator lifting apparatus should have remained attached to the separator from the separator removal procedure.
NOTE:
Check moisture separator hold-down bolts for proper orientation. The tab should be pointed towards the center of the coisture separator.
7.2.2 Attach the moisture separator lifting rig to the 125 T hpok.
7.2.3 Notify Operations and Radiation Protection of intent to lower the moisture separator into the reactor.
7.2.4 Raise separator to a height that will clear the storage pit ledge and transport it to a position over the reactor cavity.
Align moisture separator to guide pins in the reactor.
7.2.5 As Operations begins draining water from the cavity-storage pit area, the following functions shall be performed:
a.
Lower the moisture separator, maintaining approximately 2 ft of water above top of separator.
Caution: Do not allow crane hook to enter water in cavity b.
Commence washing down cavity and storage pit walls with the Liqua-Blaster and condensate transfer water.
i MP-1.5 - 3 April 1974 l
Caution: Do not point no::le towards personnel As the steam dryer is bared, turn the sprinkling
(
c.
system (installed at time of dryer removal) on to keep the dryer wet until it is installed.
7.2.6 Continue lowering separator until it is positioned in the reactor.
7.2.7' Continue decontamination efforts until the bulk of crud has been washed off the cavity walls and floor.
Contamination level should be below approximately 10,000 cpm /ft.
7.2.8 Radiation Protection shall monitor radiation and contamination conditions in the cavity and inform maintenance when personnel may enter cavity.
7.2.9 Place access ladder on storage pit ledge and secure to guard railing with rope.
7.2.10 Check moisture separator is in position and detach the four (4) lifting devices from the moisture separator.
See General Electric Servicing Equipment Manual GEK-722, pages 2-13 and 2-14 for instructions and diagrams.
7.2.11 Raise the lifting apparatus out of the cavity and
(
place on operating floor or install on steam dryer.
7.2.12 Detach the slings from the 125 T hook.
7.3 Removal of Portable Radiation Shield 7.3.1 Thoroughly wash down shield with condensate transfer water.
7.3.2 Attach appropriate slings to the 25 T hook and lower hook over shield. Shackle the slings to the lifting lugs of the radiation shield.
7.3.3 Lift the shield out of the cavity and place on the operating floor in its proper storage area.
Detach slings from shield.
7.3.4 Wrap the shield in polyethylene to contain contamination.
7.4 Decontaminating Reactor Cavity MP -1. 5 4
April 1974
7.4.1 Thoroughly decontaminate the reactor cacity using the Liqua-Blaster and condensate transfer water supply.
7.4.2-Radiation Protection shall provide frecuent monitoring of radiation conditions. The results of the radiation surveys shall determine when sufficient decontamination is accomplished.
7.5 Installing Fuel Pool Shield Plug 7.5.1 Attach the fuel pool shield plug slings to the I5 T hook.
7.5.2 Lower hook over shield plug No.9 and shackle slings to lifting lugs.
7.5.3 Lift shield plug, transfer to canal area and slowly lower into position.
7.5.4 Detach slings frca plug and crane.
-7.6 Miscellaneous 7.6.1 Blanks on cavity wall ventilation openings may be removed at this time.
7.6.2 The vessel head studs may be prepared at this time, a.'
Secure the head stud rack, centaining the 4 i
studs removed following the removal of the vessel head, with the 25 T hook and lower into cavity.
b.
Install the stud handling device and stud wrench in the top of stud No.15 and install the stud in its proper hole in the vessel flange.
c.
Tighten firmly with the stud wrench.
d.
Repeat the above procedure for studs Nos.16, 17 and 18.
i e.
Remove the stud protectors from the remaining studs.
f.
Thoroughly wire brush each stud and lubricate with Cranc 'Utread Compound No.425, "Never See:"
nickel based compound, or equivalent.
MP-1.5 - 5 April 1974 i
t J
g.
Install the two guide pins on studs No.1 and No.32 and stud thread protectors on the remaining studs.
h.
Remove the head stud rack from the cavity.
7.6.3 The main steam line plugs shall be removed prior to installation of the vessel steam dryer.
Follow the procedure written in General Electric Servicing Equipment Manual GEK-33101A.
7.7 Locking Moisture Separator 7.7.1 Lock the moisture separator hold-down bolts using the shroud head bolt wrench as follows:
a.
Lower wrench over bolt to be locked. Rotate inner wrench handle to engage the bolt, locating tab with locator socket.
b.
Rotate wrench handle clockwise, tightening the nut.
c.
Continue to rotate until the locator handle turns 90 indicating the tee-bar at the bottom of 0
the bolt is in the locked position.
d.
Tighten the nut to approximately 40 ft-lb torque.
'e.
Lift the bolt wrench off of the bolt and visually check that the locating tab is tangent to the vessel circumference, i.e., in the locked position.
f.
Repeat above procedure fer all hold-down bolts.
7.7.2 Upon completion of moisture separator locking procedure, the maintenance foreman in charge of the work shall visually check and verify that each hold-down bolt is in the locked position. lie shall state this verification on the WR and initial it.
Notify Station Shift Supervisor.
8.0 IN-PROGRESS INSPECTION 8.1 No specific inspection is required.
liowever, normal maintenance observations may result in discovery of possible 1
abnormalitics or defects. These shall be documented on the NR covering the work and brought to the attention of the Maintenance Supervisor.
February 1977 MP-1.S - 6 I
9.0 TESTING None Required.
10.0 RETURN TO NOR'tAL 10.1 No mark-ups shall be cleared at this time 10.2 Return the RKP 10.3 Complete, sign, and return hR form 1
StP-1.5 7
February 1977 i
NINI. :-111.I' l'Oltil til!(*l.1: Alt.TN110!1 - II JIT NO. 1 Overhaul test and in::pection.chect for Renctor liuiltlinn Cranc l'< ri<ni1.
1,,:.,ci1,,i,
!) ate Equip:nent Piccc No.
Systen
- 21.1A Check I.irt Tester's Maric Unsat/ Sat l
1.
Bridge Structure 2.
Trolicy Structure 3'.
Bolting. - Rivets 4.
Sheaves - Dru:ns S.
Gears, Pins, Rollers i
6.
Brakes i
7.
hhecis i
-l 8.
Cranc Ilocks 9.
Ropes 10.
Linit Switches 11.
Centrols - Contacts 12.
Lubri cation 13.
h' iring Remarks:
- Attach Magnetic Particle inspection for hooks to this Inspection Sheet.
i 4
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N!!!!' !!!!.l. l'Olt.T ;;tiCl.l;ilt f.TN! 10!! - II ;lT ;O. 1 Overhaul test anti in:;pect ion slicet for S t < am l'rys r I; Floi ;tu re- ';e n:e r:ito r Sling:. anil 1:<pii iment 7061:T.Hil'T 1 i
Date Equipment Piecc No.
System
- 1. w Chec1.1.ist Ter.ter's Name Unsat/ Sat 1.
Top Cable Itines (2) 2.
Top Cable Stech. Splice (4) 3'.
Cable (4) 4.
Bottom blech. Splico (4) 5.
Lifting Pins (4) 6.
Upper Cuide (4) 7.
Rack'S Pinion (4)
Lower Guide (4) 8.
i 9,
BAR (4)
{
10.
Frame (1) 11.
i l
12.
I 13.
't Remarks:
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1 Overhaul test and inr.pection sheet for Shrtual !!c:id liot t 1
a tirene h Date Equipment Piccc No.
System
- 1.1A l
Chech List Tor,ter's Nanc Unsat/ Sat 1.
External fixt. Itod (1) 2.
Internal Ext. Rod (1) 3.
~4.
4 5.
6.
7.
8.
9.
t.
10.
11.
12.
3 e
13.
1 Remarks:
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NIAGARA *10llWK PoliER CORPORATION _
NINE MILE POINT NUCLEAR STATION - UNIT NO. 1 MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.6 INSTALLATION OF REACTOR VESSEL STEAM DRYER DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3 r
- stah, Maintenance Supe
((((f[
[OGL R. B. Abbott Station Superintendent N
7
(.9tP :S) k k.
6 )4 T. J. Perkins 7
Chairman of S.O.R.C.
T. E. Lempges
] [g Gy,g
/.!nta Summary of Paces Revision 1, dated February 1977, consists of pages 1 and 3.
s
NITE ".!!.!! l'Ol!.T NUCLEAlt S':. ATION - IINIT
.0, 1
MA!!ril'. NANCE PROCEDURE f tP-1.6 INS 1 ALLATION OF REACTOR VESSEL STr\\*? DRYER 1.0 PURPOSE 1his procedure describes the necessary steps to install the steam dryer into the reactor vessel.
2.0 PREREQUISITES
^
2.1 Plant Conditions - The reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
l 2.2 System conditions - Moisture separator installed, steam dryer located in storage pit.
All mark-up s obtained for removal of vessel head 2.3 Mark-ups (see Maintenance Procedurc 1.2) shall be in effect.
An RKP shall be obtained per 2.4 Radiation Work Permit (RKP)
Section IIB of Radiation Protection Procedures for reactor at elevation 340 fc and reactor cavity. The mark-up building man shall be the maintenance foreman in charge of the work.
" Work Request" (NR) shall be 2.5
-laintenance Request Corm I
\\
obtained and used ta document time, material used, labor required and date job was performed.
2.6 Pre-inspec'.lons 2.6.1 Reactor Building overhead crane per Maintenance Procedure No. 21.1 Inspection Sheet No. 21.1A 2.6.2 Steam dryer hold down tool per Inspection Sheet No.
1.3A.
1 2.6.3 Moisture separator lifting apparatus per Inspection Sheet No. 1.3B 3.0 TEC!!NICAL SPECIFICATIONS None Required 4.0 SPECIAL PRECAUTIONS 4.1 Follow requirements as posted for 340 ft icycl.
i MP-1.6 - 1 February 1977-
4.2 Special carc shall be taken to ensure that no foreign objects are accidentally dropped in the spent fuel pool, reactor
(
cavity, or storage pit areas. Supervision to be notified if this should happen.
4.3 Strict adherence to radiation protcetion instructions that appear on the REP is essential.
4.4 Radiation Protection must be notified whencycr a change in radiation, contamination or airborne conditiens is at all possible.
5.0 SPECIAL TOOLS 5.1 Steam drycr hold-down tool.
5.2 One section of actuating pole.
5.3 Steam dryer lifting apparatus.
5.4 Reactor building overhead crane 125T hoist.
5.5 Underwater lights.
6.0 REFERENCES
6.1 General Elcetric Servicing Equipnent.ifanual GEK-722 6'. 2 NMP Radiation Protection Procedures 7.0 PROCEDURE 7.1 Attach steam dryer lifting slings to 125 ton hook. Orient the lifting frame over the dryer and attach each of the 4 lifting devices to the four lugs of the dryer. See General Electric Servicing Equipment Manual GEK-722, pages 2-13 and 2-14 for
~
instructions and diagram.
7.2 Check each dryer hold-down assembly and verify that the pointer bar is pointing toward center of dryer (unlocked position).
7.3 Turn off sprinkling system.
7.4 Notify Operations and Radiation Protection of imminent dryer installation.
7.5 Raise dryer high enough to cicar the storage pit ledge and transfer to cavity. Orientate dryer to align with guide pins in the Reactor.
MP-1.6 - 2 April 1974
7.6 When in position over ver. sci, slowly lower into place. Check for proper installation.
(
7.7 Dotach lifting rig from dryer, remove it from cavity and place in its storage area on El. 340 ft.
7.8 Connect the dryer hold-down tool to one section of actuating pole. See General Elcetric Servicing Manual GEK-722, pages 2-29 thru 2-32 for description of these tools.
7.9 Lock the 4 dryer hold-down assemblics with the hold-down tool.
on the hold-dewn When in the locked position the pointer bar assembly is in a position parallel to the reactor vessel wall.
7.10 The naintenance foreman in charge of the work shall visually check that each hold-down assembly is in the locked position.
I He shall state this verification on the hR and initial it.
I Notify station shift supervisor.
8.0 IN-PROGRESS INSPECTION i
S.1 Any abnormalities or defects discovered through normal maintenance observations shall be documented on the hR and I
brought to the attention of the Maintenance Supervisor.
9.0 TESTING None required.
10.0 RETURN TO NOR'!AL 10.1 No mark-ups shall be cleared at this time.
10.2 Return the RNP 1
10.3 Complete, sign and return WR form.
(
MP-l.6 - 3 February 1977 I'
Nit:1. !!!!.l; l'Ollir NIN:1.!: Alt STATION - !! NIT NO. 1 Overhaul test and inc.pection slicet for Reactor !!uildinn Cranc lacrinili e in.:n, et i..,
.(
Date Equipment P3ccc No.
_ System
- 21.!A Check I.ist Tester's Name Unsat/ Sat i
1, liridge Structure S
2.
Trolley Structure I.
Bolti':g - Rivets
.g,
Shcaves - Drums 5.
Gears, Pins, Rollers 6.
Brakes 7.
Wheels i
8.
Cranc flooks 9.
Ropes 10.
Limit Switches s
11.
Controls - Contacts 12.
Lubrication 13.
1liring i
Remarks:
Attach Magnetic Particle inspection for hooks to this Inspection Sheet.
9
. -. ~.
NINI! !!!I.li PolNT WilC1.1:AR STATION - IINIT NO.1 Overhaul test and inspection sheet for Steam Dryer Unistching Tool 135D0542-C1
- 1.3A Date Equipment Piccc No.
System 1
i Check I,ist Tester's Name Unsat/ Fat 1.
Unlatching Tool (1) 2.
Actuating Pole (1) 3.
i 4.
1 5.
I 6.
7.
8.
9.
1 10.
i 11.
12.
13.
i Remarks:
l 1
4'
!;I:ll'. !!!l.1 l't)I!.'T WilCl.l.AIt !;TATI() - II:'IT !;0. 1 I
Overhaul test and inr.ps et ion sheet for St cans lirver T, Ni sture L m r::*or
(;
Slinns anel I:< psi iiwnt 70(.I'P,tioti l l
Date 1: quip::ent Piece No.
System 1.3R 4 '
Chech I.ist Tester 's Nime, Unsat/ Fat 1.
Top Cable Rinc.s (2)
Top Cabic.1cch. Snlice (4) 5 2.
3',
Cabic (4)
I 4.
Bottom 5!cch. Splice (4) 5.
Lifting Pins (4) 6.
Upper Cuide (4) t 4
7.
Rack f, Pinion (4)
Lower Guide (4) 8.
DAR (4) 9.
b 10.
Frame (1) 11.
12.
13.
Remarks:
M b
I
(
NIAGARA MOR\\WK POWER CORPORATICN NINE MILE POINT NUCLEAR STATION - UNIT NO.1 i
MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.7 INSTALLATION OF REACTOR VESSEL HEAD DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3 N.
.)l0 $/ 77 Maintenance Supervis R. B.' Abbott
(([c
[tY(b Station Superintendent
$g (RIPNS)
T. J.
Perkins
[
I//
/
ChairmanofS.O.R.C.[i4f' T/ /,..,
T. E. Lempges T
Summary of Paces Revision 1, dated February 1977, consists of pages 1, 2, 4, 5, 6 6.
I i
nm w
NINil MILE POINT NUCLEAR STATION - UNIT NO.1 MAINTLNANCE PROCEDURE MP-1.7 k
INSTALLATION OF REACTOR VESSEL llEAD 1.0 PURPOSE This procedure describes the necessary steps to install the reactor vessel head.
2.0 ' PREREQUISITES 2.1 Plant Conditions - the reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
steam dryer installed, vessel head 2.2 System Conditions positioned on pedestal.
mark-ups obtained for removal of vessel head shall 2.3 Mark-ups be in force. See Maintenance Procedure MP-1.2.
An RNP shall be obtained per 2.4 Radiation Work Permit (RWP)
Section IIB of Radiation Protection Procedures for Reactor Building at elevation 340 ft and reactor cavity. The mark-up man shall be the maintenance foreman in charge of the work.
2.S Maintenance Request Form -
" Work Request" (NR) shall be l1 obtained and used to document time, material used, labor
(
required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Reactor building overhead crane 125, 25, 1/2 T hoists per maintenance procedure No.
AP-21.1, Inspection Sheet 21.1A.
2.6.2 Vessel head insulation lifting rig per Inspection Sheet No. 1.2A.
2.6.3 Stud tensioners and stud tensioner lifting rig assembly per Inspection Sheet No. 1.2B.
1 2.6.4 Head lifting assembly per Inspection Sheet No. 1.2C.
2.6.S Vessel head slings, shackles, and turnbuckle assembly per Inspection Sheet No. 1.2D.
l February 1977 MP-1.7 - 1
'M
3.0 TECl!NICAI. SPECIFICATIONS Nonc Rcquired
(
4.0 SPECIAL PRECAUTIONS 4.1 Follow requirements as posted for 340 ft level.
4.2 Special care shall be taken to ensure that no foreign objects are accidentally dropped in the spent fuel pool, reactor cavity or storage pit areas.
Notify Supervision if this should happen.
4.3 Strict adherence to radiation protection instructions that appear on the RWP is essential.
4.4 Radiation Protection must be notified whenever a change in radiation, contamination, or airborne conditions is at all possible.
5.0 SPECIAL TOOLS 5.1 Reactor building overhead crane 125 T, 25 T and 1/2 T hoists.
5.2 ' Head insulation lifting rig.
9.3 Stud tensioners and stud tensioner lifting rig.
5.4 Vessel flange heating blanket.
1 5.5 Head strongback lifting assembly.
'5.6 Head slings, shackles and turnbuckles assembly.
5.7 Nut and washer rack.
5.8 Head stud rack.
5.9 0-Ring retainer punch.
5.10 0-Ring retainer pliers, 5.11 Nut and bushing lifting device.
6.0 REFERENCES
6.1 General Electric Servicing Equipment Manual GEK-722.
6.2 Biach Industries, Inc., Instruction and Maintenance Manual for 1,680,000 lb Tensioner Model #2-5039.
February 1977 MP-1.7 - 2
6.3 General Electric " Ope rating instructions for Reactor Vessel Flange llcating Blanket" Manual.
(
6.4 Combustion Engineering, Inc.,
Book No. 164, " Niagara Mohawk Reactor Vessel Instruction Manual".
6.5 NMPC Accident Prevention Rules.
6.6 NMP. Radiation Protection Proceudres' 7.0 PROCEDURE 7.1 Installation of 0-Rings on Vessel I! cad 7.1.1 Remove old 0-rings by removing retainer rings, detaching retainer clips and dropping 0-rings frem grooves.
7.1.2 Position the new 0-rings beneath the head.
NOTE: During hpndling, the 0-rings must be protected at all times from scratching or excessive springing.
7.1.3 With the 0-ring retainer pins in their respective
- holes, install either of the 0-rings in its respective groove in the mating surface of the head.
7.1.4 The 0-ring is secured by means of the retainer clips.
Insert the tongue of a retainer clip in the 31ot on
-(
the' I.D.
of the 0-ring and engage the clip over the retainer pin with the retainer punch.
Install a retainer ring onto_the retainer pin over the tongue of the retainer clip.
NOTE: To ensure that the 0-ring retainer will resume its original shape after installation, do not spread the retainer any wider than is necessary to engage it over the 0-ring retainer pin.
7.1.5 Repeat the above procedure for the remaining 0-ring.
7.2 The vessel head studs should have been c1 caned and lubricated after installation of the moisture separator.
The two guide pins should have been installed on studs #1 and #32, and thread protectors installed on the remaining studs.
See Maintenance Procedure MP-1.5, Section 7.6, for this requirement.
7.3 Clean all surfaces of the vessel head and reactor vessel flange.
August 1974 MP-1.7 - 3
-7.4 Installation of Ver. sci !! cad
'7.4.1 Lower 125-T hook into vessel head strongback and 1-
. attach strongback to hook by inserting the three pins I
into the head strongback assembly.
I 7.4.2 Raise strongback from floor and attach slings to j
strongback.
7.4.3 Orient the lifting assembly over vessel head and i
attach slings to the lifting lugs with the anchor shackles.
7.4.4 Slowly apply load to lifting rig and lift head off pedestal. Clean the mating surface.of the vessel head of all foreign matter.
7.4.5 Level the head so that the top of the flange is level within.002 in./ft across its diameter.
1 7.-4.6 Notify operations of imminent head installation.
7.4.7 Transport the head over to the vessel and position it such that the mating surface of the head is parallel to. the face of the vessel flange, and the stud guide pin holes in the head are in line with the guide pins.
7.4.8 Lower the head until the mating surfaces of the head and vessel come into-centact.
1 7.4.9 Remove lifting assembly from head by detaching anchor shackles from lifting lugs.
~
7.4.10 Remove head strongback from 125 T hook by pulling the i
three pins from the head strengback assembly and store in a proper location.
7.4.11-Remove the guide pins and all stud thread protectors and remove from the cavity, i.
7.4.12 Lower the nut and washer racks into the cavity.
7.4.13~
Install the appropriate pair of beveled washers on each stud. Check that the female bevel is over the male bevel, and that the washer numbers correspond to the stud numbers.
7.4.13 Install the appropriate nuts on the like-numbered studs.
f '
l l
l
7.4.14 Tighten all nuts with a nut runner to a maximum 100 ft/lb torque.
7.4.15 Remove all nut and washer racks from the cavity and l
return them to their storage area on El. 340 ft.
7.5 Installation of Vessel Flange Heating Blanket 7.5.1 Request operations to raise the water level in the-vessel to the flange.
7.5.2 Install the heating blanket according to the General Electric " Operating Instructions for Reactor Vessel Flange Heating Blanket" manual.
J NOTE:
Maintain flange temperature above 100 F.
7.6 Stud Tensioning 7.6.1 Prepare _ the stud tensioner and lifting rig assembly I
according to Section I, " Pre-Operating Instructions,"
of Biach Industries, Inc.,
Instruction and Maintenance Manual for 1,680,000 lb Tensioner, Model
- 2-5039. The 25 T hoist shall be used for suspending the tensioner rig.
y 7.6.2 Clean out holes in head bolts.
(Be sure there is not any dirt in them.)
(
7.6.3 Standardize indicator on standardi:ation block secure measuring rod.
7.6.4 Secure a complete set of head bolt elongation readings, (Bolts have been tightened to 100 foot pounds torque and are heated above 100 F) and attach to the WR.
7.6.5 Tighten the nuts according to the Biach Industries, Inc., Instruction and Maintenance Manual,Section II,
" Operating Instructions,"
and Section
- III,
" Programming."
7.7 When stud tensioning is complete, remove stud tensioner assembly from the cavity area. Detach the tensioners from the lifting rig, disassemble hoses, and place all equipment in cheir storage areas on El. 340 ft.
NOTE:
Have operations raise water Icvel above vessel flange joint.
4 i
February 1977 MP-1.7 - 5 t
the flange heating blanket and place in 7.8 Dismantle and remove its storage area.
7.9 Misec11ancous 7.9.1 Using the 25 T crano and appropriate slings, install the head insulation ring (" carousel") onto_the vessel head.
7.9.2 Install the three (3) instrument lines to the vessel head: head vent, head spray, and.yarway level control.
7.9.3 Remove ver.tilation opening covers (" silver dollars")
and set on El. 340 ft.
7.9.4 Install the ventilation stacks to the drywell.
7.9.S Instrumentation and Control shall install thermocouples and accompanying lines to the vessel head and safety valves.
NOTE: Installation of safety valves shall have been accomplished either when the vessel head was positioned on the pedestals or after it has been installed on the vessel flange.
See Maintenance Procedure MP-1.13.
8.0 IN-PROGRESS INSPECTION
(
8.1 While performing the maintenance procedure, make a general inspection of instrument lines and flanges, ventilation piping, head insulation, head studs, nuts and washers, vessel flange and head. Any defects shall be noted on the WR and relayed to
^
the Maintenance Supervisor immediately.
9.0 TESTING None Required 10.0 RETURN TO NORMAL 10.1 Clear mark-ups 10.2 Return the RWP 10.3 Complete, sign, and return NR form
'I February 1977 MP-1.7 - 6 I
F
= _ _ _
Hlfili IllI.l; l'Ol!.T MtfCI.121: ';*lW11iRi - II::IT I;O. 1 lleactor P.uili!inr. Crane
. 0verhaul ter.t and in::pection sheet for l'e r i niil i c I n me.ct inin
. \\
Equip:. cnt Piccc No.
System
- 21.1A I'
Date 1
4 A
Cheel: I.ist Tester's Name Unsat/ Sat 1.
11 ridge Structure 2.
Trolley Structure 3'.
Bolting - Rivets 4.
Sheaves - Drums Gears, Pins, Rollers 5.
6.
Brr.kes 7.
h' heels S.
Cranc Ilooks 9.
Ropes i
- 10.. Limit Switches 1
t
(
~%g 11.
Controls Contacts j
12.
Lubrication
.l 13.
h' iring Attach >!agnetic Particle inspection for hooks to this Inspection Sheet.
Remarks:
1 i
4
's i
4 1
n i
j
MINI; 111.11 l'ol:Tr t:llCI.1: Alt *.TATitul - II::IT t'O.
1 l
Overhaul test and inr.pection sheet for itx. Ilead Insulation
('
Li f tin;; Itig Date Equipment Isicco No.
System
- 1.2A Check I.ir.t Tester's Name Unsat/ Sat 1.
Top Iting (1) 2.
Mech. Splice Top (3)
Cable (3) 3.
2 tech. Splice Bottom (3) 4.
Turnbuckles (3) 5.
Hooks (3) 6.
7.
8.
9.
(, '
10.
11.
12.
13.
]
Remarks:
l l
I s
4
=
W 9*
-e-,
e-
,,---m-----,
,,-ru..-y.,.-
N1:;L !!!1.L l'ol.T :;ilt:I.1 AIt :;T/J: Io:; - ti::1 i :.o. 1 i
Tenr.ioner I.ifting Rig Overhaul ter.t and innpection sheet for i
.(.
- 1 20 Date Equipment Piece No.
System 4
l Check i.ist Tester's Name Unsat/ Sat Top Rinc, (1)
I 3,
Top 11cch. Splice (4) 2,
\\
l 3',
Cabic (4)
Bottom !!ech. Splice (4) 4.
5.
Bottom Pin (4) 6.
Eye Bolt (4) j 7.
Frame (1)
\\
8.
Tensicne Support Cabler (4) 4 (4) 9.
5:ech. Splico 10.
Hcoks (4)
Stud Tensioners (5) 11, 12.
13.
Remarks:
4
\\...
1 e
Hl!:l; !!!I.1: l'Olf;T Sl!CI.l! Alt !;TATION - (INIT !;0. I Overhaul tent and inspection chect for Iteactor lle:al Liftinn A ;scrbly Date
!!quipment l'icce No.
System
- 1.2C and 1.2D Check 1.ist Tester's Name Unsat/ Sat Lifting Assembly Pins (1) 1.
Ilead Bolts G Nuts (3) 2.
3; Shackles (3) 4.
3 F!cch. Splices (3)
S.
Slings (3) 6.
Lcteer.Slech. Splices (3) 7.
Top Turn Buckle Bolts -(3)
Turnbuckles (3) 8.
L teer Turnbuckle Bolts (3) 9.
(,
10.
f 11.
l i
12.
13.
Il Remarks:
1
}
i f
I
.. _. _..,,. _, +..,,,.,..,, -,.,.,,.,, _..,,,
,,__,.,,.7,w.,s,.
(
NIAGARA MOHAh'K POWER CORPORATIO':
NINE MILE POINT NUCLEAR STATION MAINTENANCE PROCEDURES PROCEDURE NO. MP-1.8 INSTALLATION OF CONTAI.'0!EhT HEAD DATE AND INITIALS APPROVAL BY NAME REVISION 1 REVISION 2 REVISION 3 C
.ph sh, f k0D B
bo t
/
0 0
Station Superintendept 3[3[g (FCIPNS) p f 78/[
T. J.
Perkins J/(! hI Chairman of S.O.R.C.
./
T. E. Lempges
'ry _.y
- /{'
..,v Summarv of Paces Revision 1, dated *ctruary 1977, consists of pages 1 through 5.
(
NINE MILE POINT NUCLEAR STATION - U"IT NO. 1 MAINTENANCE PROCEDURE NO. MP-1.8
(
INSTALI.ATION OF CO.'.TAINMENT HEAD 1.0 PURPOSE This procedure describes the necessary steps to install the containment head, spent fuel pool shield plugs, storage pit shield plugs and floor plugs.
2.0 PREREQUISITES 2.1 Plant Conditions - The reactor shall be in the cold condition and the drywell deinerted and properly ventilated.
2.2 System Conditions - Reactor at 0 psig, less than 212 F.
2.3 Mark-ups - None required.
2.4 Radiation Work Permit (RKP)
- An RWP shall be obtained per Section IIB of Radiation Protection Procedures for reactor building at elevation 340 ft.
The mark-up man shall be the maintenance foreman in charge of the work.
2.5 Maintenance Request Form - " Work Request" (NR) shall be 1
obtained and used to document time, material used, labor required, and date job is performed.
2.6 Pre-Inspections 2.6.1 Reactor builidng overhead crane, 125 T and 25 T hoists to ensure satisfactory operability per Maintenance Procedure No. 21.1A.
2.6.2 Floor plug shackles and slings per Inspection SheetNo. 1.1A.
1 2.6.3 Shield plug lifting rig, slings and shackles per Inspection Sheet No. 1.1B.
2.6.4 Containment ~ head strongback per Inspection Sheet No.
1.1C.
3.0 TECHNICAL SPECIFICATIONS None Required February 1977 MP-1.8 - 1
\\~
l
4.0 SPECIAL PRECAln IONS 4.1 Follow requirements as posted for 340 ft icvel.
4.2 Special care shall be taken to ensure no foreign obj ects are accidently dropped into the spent fuci pool, reactor cavity or storage pit areas. Notify supervision if this should happen.
4.3 Strict adherence to radiation protection instructions that appear on the RWP is essential.
4.4 Immediately upon removal of guard railing sections to facilitate transporting shield
- plugs, provide safety precautions around reactor cavity to safeguard against personnel falling into cavity. Replace guard railing sections as soon as practicable to do so.
5.0 SPECIAL TOOLS 5.1 Reactor building overhead crane, 125 T and 25 T hoists 5.2 Containment head strongback assembly.
5.3 Floor plug slings and shackles 1
5.4 Storage pit shield plug lifting rig, shackles and slings 5.5 Spent fuel pool shield plug slings and shackles 5.6 Impact wrench'(1 in. drive) 2 1/8 in. socket 5.7 Air line and pressure regulator and gage 5.8 Torque Wrench (calibrated)
6.0 REFERENCES
6.1 NMPC Drawing 15132, Sheet 10 6.2 NMP Radiation Protection Procedures 6.3 General Electric Servicing Equipment Manual GEK-722 f
6'4 NMP Maintenance Procedure MP-1.1 6IS NMP Maintenance Protedure MP-1.6 1
6.6 -ISP-IC-24.2
(
February 1977 MP-1.8 - 2
7.0 PROCI:1)til:I!
7.1 Installation of Containment IIcad f
\\
7.1.1 Check that all containment head hold-down bolts are pivoted radially outward and the guide pin ts installed.
Check containment head gasket.
Renew if required - clean flange.
7.1.2 Lower 125 T hook into head strongback and attach strongback to hooks by inserting the three pins into the head strongback assembly.
1 7.1.3 Raise hook to verify strongback is attached to hook.
7.1.4 Raise head strongback from floor to over containment head.
7.1.5 Orient strongback assembly over containment head and:
attach shackles to the lifting lugs.
7.1.6 Notify Operations of imminent installation cf
-containment head.
7.1.7 Lift containment head off floor plugs and clea:
1 flange. Then transfer to cavity.
7.1.8 Slowly lower head onto containment flange, observing movement at each guide pin.
Verify that head is lowering evenly.
7.1.9 Remove the anchor shackles from the head lift points, lift head strongback out of the cavity and transport 1
it to its storage area. Detach strongback from thA 125 T hook by pulling the three pins from the hebsd strongback assembly.
7.1.10 Rotate all hold-down bolts inward into position. at the containment head.
7.1.11
" Square off" the head by tightening the north, sour 4 J
east and west hold-down bolts with the impact wrenei.
7.1.12 Continue to tighten the remaining hold-down botts until complete. The maintenance foreman in charge of the work shall visually check all hold-down bolts cal verify they have all been tightened. He shall then document this on the WR.
7.2 Installation of Spent Fuci Pool Shield Plugs l-February 1977 otP-1.8 - 3 w=-=
7.2.1 If the reactor has been disassembled to the extent for refueling purposes, shield plug No.
9 should already have been installed prior to installation of the steam dryer, per Maintenance Procedure MP-1.5.
7.2.2 Attach one (1) pair of shield plug slings to the 25 T y
auxiliary hook and orient over shield plug No. 10.
7.2.3 Attach the slings to the two shield plug lifting lugs with the appropriate shackles.
7.2.4 Remove the necessary sections of guard railing at the canal area.
7.2.5 Raise plug No.10 to no more than six (6) in above the floor and transport it to the canal.
7.2.6 Slowly lower the plug into place in the canal and detach the slings from the plug lifting lugs.
7.2.7 Repeat the above procedure for plug No. 11.
7.2.8 Detach the slings from the 25 T hook.
7.3 Installation of Storage Pit Shield Plugs 7.3.1 The storage pit shield plug lifting rig with one (1) pair of slings should have rer.ained attached to shield plug No.
6 during removal procedure e(-
(Maintenance Procedure MP-1.1).
7.3.2 Attach to the 125 T hook the pair of slings used to transport the fuel pool shield plugs.
7.3.3 Orient the 125 T hook over storage pit shield plug i
No. 6 and attach the pair of slings (attached to the plug) to the hook.
7.3.4 Remove the necessary sections of guard railing on the south side of the cavity.
7.3.5 Raise plug No.
6 to no more than six (6) in. above the floor and transport to the storage pit-cavity area.
7.3.6 Slowly lower the plug into place and detach the lifting rig'from the plug.
7.3.7 Repeat the above procedure for shield plugs No. 7 and No. 8.
February 1977 MP-1.8 - 4
7.3.8 Trans fer slings to their proper storage area on El.
361 ft (See MIPC Drawing 15132, Sheet 10) and detach from hook.
7.4. Installation of Floor Plugs 7.4.1 Attach the floor plug slings to the 125 T hook.
7.4.2 Center the hook over shield plug No. 5 and attach the slings to the plug lifting lugs with the proper shackles.
7.4.3 Remove.the necessary sections of guard railing around the cavity.
7.4.4 Raise the plug to no more than six (6) in, above the floor and transport to cavity area.
7.4.5 Slowly lower the plug into place (See MfPC Drawing 15132, Sheet 10, for location) and detach slings frca plug.
7.4.6 Repeat the above procedure for floor plug "os. 4, 3, 2 and 1.
7.4.7 Transfer slings to their proper storage area on El.
361 ft (See MtPC Drawing 15132, Sheet 10) and detach from hook.
7.4.8 Replace all sections of guard railing that were removed for this procedure.
8.0 IN-PROGRESS INSPECTION 8.1 Inspect the gasket seating surfaces of the drywell head flange 1
joint, section 7.1.7 of this procedure.
NOTE:
Complete Overhaul Test and Inspection Sheet and attach to
'y WR form when job is completed.
9.0 TESTING-9.1 Request Instrument and Control to pressure test the containment head manhole cover and the drywell head flange joint per ISP-IC-24.2.
10.0 RETURN TO NOR.ifAL
~10.1 Return the RWP 10.2 Complete, sign, and return NR form
-l February 1977 pp.1.8 - 5
' Nll;!. Illi.I' pol'.T !U!Cl.l: Alt ';TATit>N - IlNIT NO. 1 Overhaul test and inr.pection sheet for Itenctor Ituildin;: Cranc l'e r i neli e I n a.,.c t i..n -
'Date Equipment Piccc No.
. System
- 21.IA Cheet f.ist Tester's Name Unsat/ Sat 1.
Bridge Structurc l
2.
Trolley Structure 3'.
Bolting - Rivets 4.
Shcaves - Drums
~
l S.
Gears, Pins, Rollers 6.
Brakes 7.
tihecis 8.
Cranc !!ocks 9.
Ropes 10.
Limit Suitches
{;
11.
Controls - Contacts l
12, ' Lubrication 13.
tviring 1
Renarks:
Attach >!agnetic Particle inspection for hooks to this Inspection Sheet.
i l
l 1
1 I
)
k.
i i
NINI !ill.li l'0!!.T NilCLIA!! STATION - IJNIT NO.1 i
1
' Overhaul test and inspection sheet for Reactor Cavity Plugs Slings and Shackles Date Equipment Piece No.
System
- 1.1A i
Check List Tester's Name Unsat/ Sat 1.
Top Cable Ring (2) 2.
Top Neck Splice (4) 3'.
Sling (4) 4.
Top Turnbuckle Pin (4)
Turnbuckle (4) 5.
Botton Turnbuckle Pin (4) 6.
Bottom Shackle
-(4) 7.
' 8.
9.
~
~
10.
11.
j 12.
13.
I Remarks:
I.
1
~
NIN!! Mll.li l'Oli.T NilCl.1: Alt STATION '- lit;lT NO.1 St rag Area Shield Overhaul test and inspection sheet for
- h Plugs' Lifting Rig Date
~ Equipment Picce No.
System a!.!o Check List Tester's Name Unsat/ Sat Top Cable Ring (2) 1.
2.
Top Mech. Splice (4) 3.
Sling (4) 4.
Top Turnbuckle Pin (4)-
S.
Turnbuckle (4) 6.
Bottom Turnbuckle Pin (4) 7.
Bottro Shackle (4) 8.
Liftin Frame (1) 9.
(
10.
11.
12.
13.
Remarks:
i i
t s
1 l
)
NIMl; fill.1: POINT NilCl.1: Alt STATION - UNIT NO. I Overhaul test and inspection sheet for Drywell Ilead j
(
1.ifting Rig l
Date Equipment Piccc No.
System
- 1.1C Check List Tester's Name Unsat/ Sat 3,
Strongback Assembly (1) 2.
Shackles (9) i 3.
Eyebolt + Pin (lug end) (3) 4.
Pins - (hood end)
(3)
S.
6.
7.
8.
9.
(
10.
i 11.
12, 13.
Remarks:
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N1-FHP-16 8-2S-76 NINE MILE POINT NUCLEAR STATION UNIT #1 FUEL HANDLING PROCEDURE NO. N1-FHP-16 VANDENBERG CASK DATES AND INITIALS APPROVALS BY NAME SIGNATURE REVISION 0 REVISION 1 REVISION 2 Y
f7) 1 % ! $.bI General Superintendent
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~/M sf 7'd n'- V'"'f'?'
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Chairman of S.O.R.C.
F T. E. Lempges Ip/ql75 Tl?!!M Station Superintendent T. J. Perkins
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Maintenance Supervisor
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k;kdt hL R. B. Abbott Reactor Analyst Supervisor,
WF f Pages
['4 T. J. Dente gb-
/7-f 76 tummary o Revisitn 1, dated 15 August 1977, consists of pages 1 through 12 and Checklists 1 through S and Figures 1 through 3.
NIAGARA MOHAWK POWER CORPORATION i
N1-FHP-16 8/IS/77 Page 1 16.0 TITLE:
NINE SIILE POINT NUCLEAR STATION UNIT #1 FUEL HANDLING PROCEDURE NO. N1-FHP-16 VANDENBERG CASK 16.1 PURPOSE:
The purpose of this procedure is to describe the manner in which the Vandenberg. Cask will be-handled and filled with non special nuclear material.
16.2 REFERENCES
(a) ATCOR Inc. Cask Handling Procedures for Vandenberg Cask.
(b) Cask Drop Protection System Operating Requirements-
.and Technical Manual >FR-433 Rev. 2.
(c) Railroad Door Operating Procedure No. N1-FHP-2B.
(d) JAFNPP-NMP Nuclear Station Radiation Protection Procedures.
16.3 PREREQUISITES:
(a) All access controls and security measures must be in effect. A Radiological Survey of the cask surface should be obtained as a record of receiving contamination 1
level.
(b) Functional tests for all necessary plant equipment must be conpleted.
(c) ~ Personnel must be properly trained in the operation of equipment to be used.
(d) All radiological controls and procedures must be in j
effect during all Vandenberg cask operations 5 preparations.
)
(e) ' Crane inspection must be up to date per Preventative Maintenance action N1-PM-V1.
(f) Crane and link must be test loaded prior to first shipment (empty cask:may be used for test load).
(g)- Ensure that restricted path for handling cask over Reactor Building El. 340' operating floor has been tested prior to initial use of cask.
(h) The sunshade 6 steel framework must be removed.
1 i
N1-FitP-16 8/1S/7-Page 2 16.3.1 FUNCTIONAL CONTROLS:
All requirements as set forth in the.FHP No. 11 Functional Control Procedure must be satisfied.
16.3.2 SPECIAL EQUIPMENT:
(a) Vandenberg Cask (b) Crusher-shear Device (c) Cask Liner (d)
Inner Liner (e)
Inner Liner Table (f)~ Cutting Sleeve (g) Cutting Sleeve Table (h) Filter Pump and Filter 16.4 DIVISION OF RESPONSIBILITIES:
(a) All movements of radioactive naterials into the cask liner and cask handling operations will be done by Niagara Mohawk employees.
(b) Cask decontamination and radiation protection will be done by Niagara Mohawk pggjoyees.
.wK (c)
It is the responsibility of the ATCOR to assure proper decontamination of the empty cask prior to NMPC receipt.
(d) All required check-off lists to be co$pleted by Niagara Mohawk employees.
(e) Niagara Mohawk Power Corporation will be responsible for all crane operations. ATCOR personnel will coordinate with NNPC personnel-on the movement of equipment by the crane.
16.S PROCEDURE l
16.S.1-RECEIPT Or CASK TRAILER i
(a) Spot trailer on driveway to the reactor building extension.
(b)
Inspect the trailer, cask and cradle for damage.
(c) Remove sunshade 6 steel framwork.
1 (d)
Rad.-Prot. Survey Cask 6 Trainier, l
16.5.2.
NOVING CASK TRAILER FROM DRIVEWAY INTO AIR LOCK (a) Obtain cask handling check-off list.
(b)
Enter-track bay within reactor building through man door D-132.
I
N1-FHP-16 8/15/77 Page 3 16.5.2 MOVING CASK TRAILER FROM DRIVEWAY-INTO AIR LOCK (Cont.)
(c) Check rail door D-39 that it is closed and sealed properly.
(d) Check light adjacent to man door D 45 to assure that man door D-196 is closed and sealed (green light).
Enter air lock through man door D-45.
Close D-45 and make sure green light is on.
(e) Enter track bay extension through man door D-197.
Close man door D-197 and check green light on.
(f) Rail door D-198 can now be opened. Rail door D-39 is interlocked with D-198.
Green-lights on operating panel will indicate that rail door D-39 is closed and sealed.
Operate D-198 according to Nine Mile Point Standing Order No. 7 and N1-FHP-2B.
(g) Place portable threshold cover (s) over door seal at sill of door D-198 such that vehicle tires will ride on the threshold coverts) over the door seals.
(h) Move the cask aboard the trailer, into track bay extension far enough so that rail door D-19S can be closed.
(i) Close rail door D-198 and lock. Make sure green light is on.
(j) Open rail door D-39.
(k) Move the cask aboard the trailer into position under crane.
16.5.3 PREPARATION FOR CASK REMOVAL (a) Remove impact absorbers on the two lifting trunions.
1 (b) Remove two hold-down straps (wt. 485 lbs.)
(i)
Remove the sixteen 1 1/4" x 5" long bolts that secure the hold-down to the cradle.
(ii)
Attach an eyebolt to the hold-down straps.
-(iii) With crane, lift the hold down straps off the shield and set them on floor.
(iv)
Remove the 4" trunnions from the locker beneath the trailer and bolt them to the cask.
(c) Remove dirt-dust and other contaminates picked up during transportation, with water.
If additional scrubbing and washing is necessary, it shall be done in the washdown tray on elev. 340'-0.
Caution: Do not use detergents in water that will be discharged to the waste collector tank. Do not clean cask in track bay without Rad. Prot. approval.
1
N1-FHP-16 8/15/77 Page 4 16.5.3 PREPARATION FOR CASK REMOVAL (Cont.)
(d) Complete receiving inspection for possible damage in transit.
16.5.4 PREPARATIONS REQUIRED ON EL. 340'-0 OPERATING FLOOR OF REACTOR BUILDING PRIOR TO TRANSFER OF THE CASK (a) Using reactor building crane, move base plate and energy absorbing pad assembly from storage to the Point No. lA location at south side of the equipment hatch (Rx Bldg.
340'-0).
Orient the base plate assembly properly (lifting lug #12 must line up with cask flange cutout) and assure that the energy absorbing pad is properly clamped to the base plate. By attaching and securing the four wing bolts on the energy absorbing pad to the base plate assembly.
(b) Prepare base plate assembly to receive cask.
(1) Loosen cap screws on the 12 base plate lifting lugs locking pin retainers.
(2) Turn retainers to the unlocked position.
(3) Remove the 12 base plate lifting lugs locking pins from the base plate' assembly.
(4) Pull the 12 base plate lifting lugs into the base plate assembly.
(c) Using the reactor building crane move wash down tray from storage to its proper location on Rx Building 340'-0 El. (point No. 2A).
16.5.5 ERECTING CASK WITHOUT TILTING MECilANISM (a) Place the two 1 1/4" stainless steel wire rope slings around the cask and attach them to the crane 125 ton hook.
(b) Lift the cask in the hori ontal position and lower it onto wood blocks and chock it so it will not roll.
(May be necessary to move trailer).
(c) Remove wire rope slings.
]
(d) Remove cask impact absorbers and store in track bay.
(e)
Install lifting link to 125 ton hook of reactor building crane by. inserting pin through holes in link plate and hook.
(f) Attach the lifting yoke to the lifting link with pin.
~
N1-Flip-10 8/15/77 Page 5 16.5.5 ERECTING CASK WITHOUT TILTING MECHANISM (Cont.)
(g) Move crane with lifting link and lifting yoke to the centerline of rails and centerline of hatch.
(h) Switch crane control into Mode 42.
This switch is in the crane pendant controls.
Remove key from pendant control to ensure Mcde 42 is retained during cask handling work.
(i)
Lower lifting yoke to' cask and attach lifting yoke to upper trunnions and a wire rope sling to lower trunnions.
(j) With yoke on 125 ton crane hook and sling on 25 ton crane hook, lift cask hori:ontal, 4 feet clear of wood ' blocks.
(k) With 25. ton crane hook holding this level, raise yoke end until cask is vertical.
(1)
Lower cask in vertical position on wood blocks and remove lower sling.
4 16.5.6 TRANSPORT OF CASK WITHIN REACTOR BUILDING (a) Maintain crane on north-south centerline of equipment hatch while raising cask.
l (b) Operate crane on restricted path only with control in mode #2.
j Caution:
e Make certain that yoke hooks are properly engaged
)
to the trunnions on the cask and verify that the enclosure sections are fully open.
Note:
The cask liner may be installed while cask is in track bay or after cask has been inserted into fuel pool. This will depend on conditions at time of cask arrival.
16.5.7-LOADING LINER INTO CASK IN TRACK BAY i
(a) Remove the eight 1 1/2" bolts and nuts and the four tapered lead-in bolts from the cask bottom plate.
Open cask. drain line and drain any accumulated moisture, 1
close drain.
(b) With the lifting yoke attached to the crane and the upper trunnions, raise the-cask bell section clear of the bottom plate and set it aside on wooden blocks.
While bell section is being removed, check' cask interior for radiation fields.
' Inspect "0" rings on bottom plate.
Replace "0" rings if they are damaged.
a
<e
NI-FilP-16 8/15/77 Page 6 16.5.7 LOADING LINER INTO CASK IN TRACK -BAY (Cont.)
(c) Remove the cover from the liner and inspect the drain screen to insure it is open.
Then with the 25 ton hook on crane, set uncovered liner on the bottom plate. Two
-guide points are used to center the liner on the bottom plate. Disengage crane.
(d) Place the cask bell section back on the bottom plate.
With the four tapered lead-in bolts, fasten the bell section to the bottom plate. Tighten the bolts firmly but do not torque down.
16.5.S MOVING CASK (a) Raise cask 6", stop and check holding brakes.
(b)
Raise cask until upper limit switch stops vertical movement.
Caution:
South railing around equipment hatch must be removed.
(c) Move cask south to base plate location. Align indicators on trolley and bridge so that the centerline of cask matches centerline of base plata (point no. l A).
1 (1) Open cask drain line.
(d) Lower cask on to base plate. Orient cutout in cask lifting flanges with lug #12 on base plate assembly.
Lower cask until it contacts base plate.
Do not have any unnecessary slack in crane cables.
Caution: Replace south railing around equipment hatch.
(e) Attach base plate assembly and energy absorbing pad to cask.
(1) Push the 12 lifting lugs into the cask lifting flanges.
(2) Line up locking holes in base plate assembly and lifting lugs.
(3)
Install the 12 locking pins in matching holes on base plate assembly and lifting lugs.
(4) Turn retainers to the locked position.
(5) Tighten the cap screws on the 12 base plate assembly locking pins retainers.
(f) Raise cask with base plate and energy pad until upper limit switch stops vertical motion. Move along restricted, path until ensk in on centerline of wash down tray (point no. 2A).
(g)
Lower cask into.washdown tray to bear on energy absorbing pad. Disengage lifting yoke from cask.
2d-illiP-10 8/15/77 Page ~
16.5.8
~ 50VING CASK (Cont.)
(h)
Place scaffolding around cask, if necessary, 1
Note:
If it is necessary to remove contaminates with detergents, it shall be done at this time.
All cleaning shall be done in accordance with procedures established at reactor site.
Caution:
Do not use detergents in water that will be discharged to the waste collector tank.
16.5.10 CASK LOADING (a)
Remove scaffolding from around cask, if erected.
1 (b) With the lifting yoke attached to crane and upper trunnions, raise cask, base plate and energy absorbing pad enough to clear east edge of the washdown tray.
Move cask east on centerline of restricted path to point #3.
Lower cask to bear on floor with no slack in cables.
Disengage energy absorbing pad and raise c * -* of the energy absorbing pad.
aan:
(1) Do not operate crusher-shear device while the cask is being moved in or out of dash pot.
(2) Before moving cask, close and lock gate on cask drop protection system and remove railings.
(See Special Procedure #1)
(c) Move cask on centerline of restricted path. At each point of direction change, use movable and stationary indicators on crane to align cask. Move cask over fuel pool, index crane and lower cask to bottom of cask drop protection hydraulic cylinder.
(1) Using the remote tool unthread the 4 tapered lead-in bolts from the bottom plate.
(Number of turns to be determined).
Caution:
All personnel who must walk out onto the cask drop protection system top plate shall wear a l
safety belt.
(e)
(1) Raise bell section clear of pool.
Caution: Monitor the bell section as it approaches the surface of the pool and emerges.
(2) Rinse bell section over pool.
4 N1-FHP-16 S/15/77 Page S 16.5.10 CASK LOADING (Cont.)
(3) Follow restricted path with bell section and place down in washdown tray.
(4) Disconnect yoke from cask.
(f)
If liner has not been installed in track bay remove cover from cask liner. Then with the 25 ton hook on crane, lower cask liner onto bottom plate in pool.
Disengage crane.
(g)
Install railing on cask drop protection system.
Caution: All personnel who must walk out onto the cask drop protection system top plate shall wear a safety belt.
(h) Open gate on cask drop protection system.
(See Specisi Procedure #1).
(i)
Load cask liner with waste materials.
(1)
Place crusher / shearer device over liner.
(2) Commence packaging flow channels 4 poison curtains using a random dispersal method that will afford the greatest practical amount of self shielding.
(3) Package waste materials until the liner is full.
(j) Fasten nylon lines to the liner cover and lower cover into pool. Position cover on liner, secure cover bolts with extension tool. Remove nylon lines.
I (k) Engage yoke and crane to bell section in washdown tray and raise bell section free of the washdown tray. Move east on centerline of restricted path to point #3.
(1) Close and lock gate on cask drop protection system.
Remove _ railings (ree Special Procedure #1).
(m) Move bell section on centerline of restricted path to cask drop protection hydraulic cylinder.
Position cask bell section in exact location as when it was removed from the bottom plate.
Lower bell section into pool and after ensuring that the guide pins on the bottom plate are in alignment with the holes in the bell section flange, rest the bell section on the bottom plate.
(n) Secure the bottom plate to the cask with the 4 tapered lead-in bolts using the special remote tool.
N1-FHP-16 8/15/77 Page 9 16.5.10 CASK LOADING (Cont.)
(o)
Lift the cask from the pool so that the drain valve clears the pool surface.
Caution: Monitor the cask, as it approaches the surface of the pool and emerges, in accordance with radiation protection procedures.
If radiation streaming exists during lift, stop lift and lower cask back into pool until streaming ceases.
Ascertain the cause of streaming and correct.
(p) After drain clears the pool surface, stop lift. Hose down cask with clean water and allow cask water to drain into 1
pool. This will require the cask to remain suspended over the pool for about 45 minutes.
i (q) Follow centerline of restricted path to point #3 and reinstall the energy absorbing pad. Nove cask and energy absorbing pad to washdown tray.
(r)
Lower cask into washdown tray to bear on the energy absorbing pad. Secure the bottom plate with S-1 1/2" bolts.
1 (s) Place scaffolding around cask, if necessary replace all railings around cask drop protection system and open gate of cask drop hydraulic cylinder.
(t) Decontaminate the outside of the cask and lifting yoke.
Caution: Do not use detergents in water that will be discharged to the waste collector tank.
(u)
Install vent and drain plugs.
16.5.11 LOWERING CASK WIT 1100T TILTING MECilANISM (a)
Remove scaffolding from around cask, if erected.
1 (b) Ensure that wood blocks are properly positioned in reactor building track bay.
(c) With the lifting yoke attached to crane and upper trunnions, raise cask, base plate and energy absorbing pad enough to clear the west edge of the washdown tray.
Move cask west on centerline of restricted path to bar,e plate unloading location (Point No. lA).
(d). Lower cask, base plate and energy absorbing pad to bear on floor (no slack in crane cables).
d 9% EWM
- N1-FHP-16 S/15/77 Page 10 16.5.11 LOADING CASK WIT 110UT TILTING MECllANISM (Cont.)
(e) Remove lifting lugs that hold base plate to cask.
Refer to Section 16.5.4b for procedure.
Caution: South railing around equipment hatch must be removed.
(Elev. 340 '-0")
(f) Raise cask until upper limit switch stops vertical motion.
(g) Move cask on restricted path to the centerline of rails and centerline of hatch.
Place plastic on Rx. Bldg.
I track bay floor.
(h)
Lower cask onto wooden blocks in reactor building track bay.
(i) Attach 1 1/4" wire rope sling to lower trunnion and to 25 ton crane hook, Caution: Replace south railing around equipment hatch (elev. 340'-0")
(j) Lift cask with yoke until cask bottom is at least 4' clear of floor.
(k) Take up slack with 25 ton crane hook.
(1)
Lower upper end of cask with yoke until cask is hori: ental.
(m) Lower hori: ental cask to rest on wood blocks, remove yoke from upper trunnions, remove yoke and link from cable.
(n)
Install cask impact absorbers.
(o) Using the two 1 1/4" stainless steel slings, raise cask with crane 125 ton hook.
(p) Ensure that cask trailer is properly positioned to receive cask, then position cask over cradle on truck.
(q)
Lower entire cask in horizontal position onto cradle-on the trailcr bed.
(r) Remove the lower trunnions and place them in the equipment box.
(s) Tie the cask down to the cradle using 32 bolts and 1
two tie-down rings.
(t) Check closures and hold-downs on cask.
(u) Ascertain that the radiation level coming from the loaded cask is below the acceptable maximum limit per Radiation
' Protection Procedure.
y
+- - -
P
N1.FHP-16 8/15/77 Page 11 16.5.11 LOADING CASK WITHOUT TILTING MECHANISM (Cont.)
(v) Prepare shipping forms and bill of lading per Radiation Protection Procedure.
(w) Placard truck and label cask for shipment per Radiation 1
Protection Procedure.
(x) Check the tractor and trailer tires and equipment for wear and damage.
^
16.6 SHIPMENT FROM REACTOR SITE
'(a) - Move tractor and cask trailer into reactor building extension.
(b) Close railroad door D-39 and seal tight.
(c) Open rail door D-198 in accordance with procedure N1-FHP-2B and Nin: Mile Point Standing Order No. 7.
(d) Place portable threshold coverts) over door seal at sill of door D-198 such that vehicle tires will ride on the threshold cover (s) over the door seals.
(e) Move tractor and cask trailer out of reactor building extension and close rail door D-198.
(f) Reinstall sunshade and steel framework.
1 SPECIAL PROCEDURE #1 1.
Opening Gate on Cask Drop Protection System (a)
Install railing on cask drop protection system.
(b) Engage ratchet type wrench on jacking hex head at south
. side of gate.
(1 1/2" across flats of hex head.) Rotate tool counter clockwise until latch pins are fully dis-engaged.
(Approx. 21 turns are required). Normal operating torque is less than 20 ft. - Ibs.
(c) Engage wrench onto hex head of hinge pin ; north side of gate).
It is'1 1/S" across flats of hex head. Normal operating torque is less than 150 ft-lbs.
Max design torque is 300 ft-lbs (see note).
Rotate wrench counter cleckwise until gate is opened far enough to engage gate locking pin.
Note: Shear pins are provided in latch lacking hex and gate hinge pins to prevent damage in case interference or binding is present which results in the need for excessive torque to operate latch cr gate.
If a shear pin fails during operation of latch or gate, the cause should be determined and eliminated prior to replace-ment of shear pin for continued operation.
~
N1-FHP-16 8/15/77 Page 12 2.
Closing Gate on Cask Drop Protection System (a)
Install railing on cask drop protection system.
(b) Engage wrench onto hex head of hinge pin, located at north end-of gate. Remove gate lock pin.
It may be necessary to' apply torque in counterclockwise direction 3
to the gate to unload the gate lock pin.
(c) Rotate wrench clockwise until gate.is fully closed and against mechanical stop.
Latch pins should be properly aligned with gate. Hold gate against stop, if necessary, while inserting latch pins as described below.
(d) Engage ratchet type wrench onto jacking hex head located above latch at south end of gate.
1 (e) Rotate tool clockwise until latch is fully engaged.
(f) Remove tools from cask drop protection system.
Note: Shear pins are provided in latch jacking hex and gate hinge pins to prevent damage in case interference or binding is present which results in the need for excessive torque to operate latch or-gate.
If a shear pin fails during operation of latch or gate, the cause should be determined and eliminated prior to replacement of shear pin for continued operation.
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N1-FHP-16 Checklist 8/15/77 Page 1 J
N1-FHP-16 CHECKLIST NINE MILE POINT NUCLEAR STATION UNIT 'l FUEL HANDLING PROCEDURE Paragraph Completion Reference Checklist Date and Initials 16.3(b)
Verify all functional tests of all necessary plant equipment was completed.
/
i-16.3(e)
Verify that main reactor building crane inspection is up to date (N1-PM-V1)
/
- 16. 3(f)
Verify crane and link load tested.
/
16.3(g)
Verify that restricted path on reactor building elev. 340'-0" operating floor was tested.
/
16.5.1(a)
Verify cask trailer and tractor is oriented correctly on reactor building extension driveway.
/
)
16.5.1(b)
Verify that trailer, cask and cradle was 1
inspected for damage.
/
16.5.1(c)
Sunshade removed.
/
i 1
l 16.5.1(d)
Rad. Prot. Survey completed.
/
I 16.5.2(c)
Verify rail door D-39 is closed and sealed properly.
/
16.5.2(d)
Verify green light adjacent to can door D-45.is on te assure man door D-196 is closed and sealed.
/
-16.5.2(e)
Verify man door D-197 is closed and green light is on.
/
- 16. 5. 2 (f)
Verify green lights on operating panel indicate door D-39 is closed and sealed.
/
i 16.5.2(g)
Verify portable threshold coverts) are t-placed over D-198 door seal sill.
/
16.5.2(h)
Verify that cask trailer is oriented-correctly in track bay extension.
/
4 J
=.4~
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,.-.r-
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N1-FifP-16 Checklist 8/15/77 Page 2 Paragraph Comple* ion Reference Checklist Date and In. 4.als 16.5.2(1)
Verify rail door D-198 closed and locked and green light lit.
/
16.5.2(j)
Rail door D-39 open.
/
16.5.2(k)
Verify that cask trailer is properly oriented under Reactor Building Crane
/
/
1 16.5.3(a)
Impact absorbers removed.
16.5.3(b)
Hold down straps removed
/
16.5.3(d)
Verify that cask has not been damaged in transit
/
16.5.4(a)
Verify that base plate and energy absorbing pad assembly are clamped and properly oriented.
/
16.5.4(c)
Verify that washdown tray has been properly placed.
/
- 16. 5.~ 5 (b)
Verify cask is properly chocked
/
16.5.5(d)
Verify cask impact absorbers removed
/
16.5.5(e)
Verify lifting link pin installed.
/
16.5.5(h)
Verify crane control switched to Mode
- 2
/
16.5.5(1)
Cask removed from trailer 6 set in vertical position.
/
16.5.7(a)
Verify all bolts removed from bottom 1
plate and cask drained.
/
16.5.7(b)
"0" Rings inspected.
/
16.5.7(c)
Verify that liner is properly seated with~ cover removed 6 drain screen open.
/
16.5.7(d)
- Verify bell section bolted firmly
/
'16.5.8(a)
Verify that crane holding brakes are tested.
/
16.5.S(c.1).
Cask drain open.
/
1 i
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..p.s
N1-FHP-16 Checklist 8/15/77 Page 3 Paragraph Completion Reference Checklist Date and Initials 16.5.8(e)
Verify that base plate and energy absorbing pad are properly attached to cask.
/
16.5.8(g)
Verify that cask has been lowered into center of washdown tray and lifting yoke disengaged.
/
16.5.10(a)
Verify scaffolding removed from around cask.
/
16.5.10(b)
Verify energy absorbing pad disengaged and gate locked on cask drop protection system.
/
- 16. 5.10 (c)
Cask lowered into cask drop protection hydraulic cylinder.
/
16.5.10(d)
Verify that the 4 tapered lead in bolts are unthreaded.
/
16.5.10(e)
Verify bell scetion removed, and stored in washdown tray.
/
- 16. 5.10 (f)
Verify cark liner installed properly.
/
16.5.10(g)
Verify railing reinstalled on cask drop prctection system.
/
16.5.10(h)
Verify gate opened
/
- 16. 5.10 (j )
Verify cask liner cover bolted.
/
16.5.10(1)
Verify cask drop protection system gate closed 6 locked
/
16.T 10(m)
Verify bell section resting on bottom plate.
/
- 16. 5.10 (n)
Verify bottom plate secured to bell section.
/
16.5.10(o)
Verify cask is being monitored during lift.
/
16.5.10(p)
Verify cask that cask was drained.
/
1 16.5.10(q)
Verify energy absorbing pad installed.
/
i
N1-FHP-16 Checklist 8/15/77 Page 4 Paragraph Completion Reference Checklist Date and Initials 16.5.10(r)
Verify that bottom plate bolts are secured.
/
1 16.5.10(s)
Verify all railings replaced and gate opened on cask drop hydraulic cylinder
/
16.5.10(t)
Verify cask decontaminated
/
16.5.10(u) 7erify that vent 5 Drain are plugged.
/
16.5.11(b)
Verify reactor building track bay ready to receive cask.
/
16.5.11(e)
Verify that base plate has been removed from cask.
/
16.5.11(h)
Verify that cask is chocked properly on wooden blocks and all railings replaced.
/
16.5.11(i)
Verify cask hooked to both crane hooks.
/
16.5.11(1)
Verify cask is lifted to hori:ontal position.
/
16.5.11(m)
Verify cask resting on wood blocks and yoke and link removed from crane
/
16.5.11(n)
Verify cask impact absorbers installed
/
16.5.11(o)
Verify cask lifted
/
16.5.11(p)
Verify that cask trailer is properly positioned to receive cask.
/
16.5.11(q)
Verify that cask is properly seated in trailer cradle.
/
- 16. 5.11 (r)
Verify that lower trunnions have been removed 4 stored.
/
16.5.11(s)
Verify that cask is properly tied down.
/
16.5.11(t)
Verify all closures 5 hold downs are safety checked.
/
1
t N1-FHP-16 Checklist 8/15/77 Page 5
~ Paragraph Completion Reference Checklist Date and Initial u
16.5.11(u)
Verify radiation. level below maximum limit.
/
1 16.5.11(v)
Verify shipping forms and bill of l
lading properly prepared.
/
16.5.11(w)
Verify shipping labels posted.
/
16.5.11(x)
Verify that tractor and trailer inspected for wear 6 damage.
/
16.6(a)
Verify that tractor and cask trailer l
moved to reactor building extension.
/
o 16.6(b)
Verify rail door D-39 is closed and sealed properly with green light lit.
/
i.
16.6(c)
Verify man door D-197 is closed and green is on.
Verify rail door D-198 opened in accordance with procedure.
/-
16.6(d)
Verify door D-198 sill seals protected
/
'16.6(e)
Verify that tractor and cask have been moved out of reactor building
. extension and rail door D-198 closed.
/
- 16. 6( f")
Reinstalled sunshade 5' steel framework.
/
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NINE MILE POINT NUCLEAR STATION INSTALLATION PROCEDURE FOR SPENT FUEL RACK ASSEMBLIES DATE AND INITIALS APPROVALS SIGNATURES REVISION 0 REVISION 1 REVISION 2 Station Superintendent 7
7p NMPNS T. J. Perkins
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General Superintendent j f 2/4/27 f
Nuclear Generation mpge w
~sv Summary of Pages NIAGARA.'.10llWK POWER CORPORATION
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W.iCitTER ASSOCI ATES. INC.
5100 CENTRE AVENUE Pf t700UMGH r'C *I N G y LV A NI A IS232 (412) G21 2 566 wacramicaL cesicg y,gLg,,,,,gc,
- ,,,,,,,,,t INSTALLATION PROCEDURE FOR SPENT FUEL RACK ASSEMBLIES PREPARED FOR NIAGARA MOHAWK FCWER CORPORATICN SYRACUSE, NEW YORK cepcember 23, 1977 NMP-T-107
)
Revision 1, January 12, 1978 l
NOTE:
Work this Precedure in conjunction with Niagara Mohawk Power Corp. Specification No. CO-51 C-264.
/
CC::TE::TS PART a - Spent Fuel Rack Replacement Plan PART B - Instructions For Installation of ::c.t Spen: Fuel Rack Assemblies e
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:D-T-107
/
2' A TC A SPCNT PUCL RACI: REPLACEMCMT PLA:*
1.0 SCOPE 1.1 This Plan provides the order and sequence by which the existing racks shall be removed by the Owner, and the new P.ack Assemblies and Seismic Supports shall be installed by the Installer.
The sequence and order by which the existing spent fuel assemblies shall be relocated by the owner during progress of the replacement work is also included in the Plan.
Detailed installation instructions are contained in Part B.
2.0 REFERENCES
2.1 PART B Of Installation Procedure No. NMP-T-107.
2.2 Figure 1 of Installation Precedure No. MMP-T-107.
2.3 WAI Drawings:
115 Plan Arrangement In Spent Fuel Pool, Rack Assemblies and Rack Assembly Bases.
2.4 NMP Drawings:
C '5131-C, Sheet No. 12 - Equipm=rt Lor-t'r
~~- t tr'
" - ~
- Pool, Reactor Head Cavity, and Storage Pit.
Spent Fuel Pool Bundles Identifications After 1977 Refuel Outage.
(Received October 5, 1977).
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g3. 0 COMPONENT IDENTIFICATIOM.(Refer to_Picurc 1j For the purposc of identifying -specific c::isting rack Iccations, new Rach Assembly and Scismic Support locations in Parts A and 3 of this Installation Procedure, the following letter and number designations are assigned.
These designations are shown on Figure 1, and are based on Niagara Mohawk Power Corporation Plan
" Spent Fuel Pool Bundles Identifications After 1977 Refuel Outage" and on WAI Drawing Nos. 115-l'and 115-28.
3.1 Designation of' existing rack locations:
Existing rack locations are designated by broken lines and are identified by number / letter combinations, e.g.,
"3-MN." derived as follows:
East-West rows of racks are indicated by circled numbers, e.g., "([)"
North-South rows of racks are indicated by pairs of letters, e.g.,
"MN," arranged alphabetically from West to East.
An existinc rack location designated as "3-MN" indicates that it is located in East-Westrow"@"andNorth-Southrow"MN".
Control rod rack locations in the Northwest corner of the pool are designated in the same manner.
Four special rack locations at the East end of the pool are similarly designated, except that only the directional letters NS and NE are used in combination.with the row numbers.
Acircledplus,({), indica:es that the existing rack contains spent fuel.
Acircledminus,({},.
indicates that the axisting rack contains no fuel.
3.2 Designation of new Rack Assembly and Seismic Support Locations:
New Rach Assembly and Scismic Support locations are designated by solid lines and arc identified by letter / number combinations, e.g.,
"W7,"'and "S4," derived as follows:
East-West rows of Rack Assemblies are indicated by letters, e.g.,
"W" North-South rows of Rack Assemblies are indicated'by numbers, e.g.,
"7".
A new Rach Assembly location designated "W7" indicates that it is located in' East-West' row "W" and North-South row "7".
Seismic 1 Support locations are designated by "S" followed by a number arranged progressively around the-perimotor of the array of Rack Assembli'es, e.g.,
"S4".
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/,/4.0 GENERAL RCOUIRC"CNTS 4.1 Monitoring of the environmental working conditions in the spen fuel pool area during the installation activities shall be performed by the owner's Ilealth-Physics Department.
4.2 Prior to the work of removing existing racks and installing the new Rack Assemblies and Seismic Supports, the Morth portion of the spent fuel pool shall have been cleared by the Owner of all control rods, control rod racks, channels and channel racks, debris and miscellaneous equipment not related to or required for storage of spent fuel.
When the existing racks are removed and prior to installation of new equipment, the floor of the pool shall be cleaned by the Owner to remove small debris and accumulated fine particles.
4.3 The Owner shall dispose of existing racks, safety curtains, rack covers, and debris removed frem the pool.
The Owner'shall temporarily store control red racks and channel racks until completion of the installation of the new Rack Assemblies.
.4.4 A12 new equipment shall enter the pool frem the North side.
4.5 The 0*.iner shall temporarily relocate existing fuel assemblies, as called for in the following sequence, so that equipment will never be transported over any stored spent fuel assemblics.
4.6 Seismic Class I capability of any new Rack Assembly in which spent fuel assemblies are temporarily stored must be maintained during installation of the remaining new Rack Assemblics and Seismic Supports.
When each new Rack Assembly is installed, it shall be temporarily restrained until the next adjacent Rack Assembly is installed.
Existing racks which have been relocated for temporary spent fuel storage shall be secured in place by means of existing swing bolts.
-a r'4. 7 Prior to transferir.J -.ent Cu.1 ao:;emolius into a new Rach Assembly, the Owner shall perfor.T an insertion and withdrawal test of a random selection of ten ;cr:ent (10 '. ) of the fuel boxes in the Rack Assembly by means of a simulated fuel assembly.
4.8 The sequence of activities contained in Section 5.0 is based upon presently availacle information.
However, if problems should arise due to unanticipated local conditions, deviations from this sequence may be initiated, provided they are mutually agreed upon by the Owner and the Installer.
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0
, 5.0 SCOUT::C2 0" ACTIVITICS inafor to rigurc 1)
V s.
5.1.1 The owner shall remove -cight -(:),c:: sting control rod rac.;2 fr--
the following locc.tions:
3-CD 3-KL 3-EF 4-KL 3-GII
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"L, 3-IJ 5-MN 5.1.2 The owner shall transfer five (5) existing racks from the follcwing rack locations to five (5) of the former control red rack loca'.icns vacated in Section 5.1.1:
5-OP 3-CD 5-QR 3-EF From 5-ST To 3-GEl 5-UV 3-IJ' 4-ST 3-KL
~
NOTE:
This relocation of racks will permit temporary storage of spent fuel away from the installation work area in the Northeast corner of the pool.
5.1.3 The Owner shall transfer ninety-seven (97) spent fuel assemblies (total contents) from the existing racks at the following five (5) locations to the five (5) racks which were relocated in Section 5.1.2:
'6-NS
._3-CD_.
7-WE 3-EP From 8-WE To 3-G:i 9-WC 3-IJ 3-ST 3-KL ees Mem
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.I 5.1. -.
The Cwner snail remove twelve (12) existing racks from tne fc11cwing rack locations:
3-ST 4-UV 7-UC o
3-UV 4-WX 8-WC 3-WX 4-YZ 9-NC 3-Y2 6-NS Cast Wall Channel Rack with supports 5.1.5 The Installer shall install Seismic Supports at the folicwing seven (7) locations:
S4 S8 SS S9 56 S10 S7 5.1.6 The Installer shall install new Rack Assembliet, at the following two (2) locations:
Order Location 1
W9 2
X9 5.1.7 The Installer shall install temporary seismic restraints between the West side of new Rack Assemblies at locations N9 and X9 and t.y.e nearest existing swing bolt locations.
5.1.8 The Owner shall perform an insertion and. withdrawal test of a random selection of ten percent ( 10 'i ) of the fuel boxes in cach of the Rack Assemblics, listed in Section 5.1.6, by means of a simulated fuel assembly.
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5.1.9 The Cwner shall trans fer two ht'n-2 red-t.ic t'zo (212) s p o r. : fuul a s rt b s (total in North portion of pool) frcm the existing racks at the following locations to the newl Rack Assemblies at locations
'.79 and X? :
a'3-CD 3-OP 3-EF 3-QR
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Frc=
3-m!
4 -!.:
To a9 3-IJ 4-OP 3-KL 4-QR 3-MN 5.1.10 The Owner shall remove all the remaining racks in the North portion of the pool, consisting of existing racks at the following c :.c. c +1-P)~
locations:
- 7. u:.. ' =
3-CD 3-KL 4-MN 3-EF 3-MM 4-OP 3-GH 3-OP 4-QR 3-IJ 3-QR
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5.1.11 The Installer shall install Seismic Supports at the following eleven (11) locations:
S1 S11 S15 S2 S12 SIG S3 S13 S17 S14 S18 5.1.12 The Installer sha$.1 install new Rack Assemblics at the following si:: (G) locations:
Order Location Order Location 1
N7 4
X5 2
X7 5
X3 3
W5 6
51 3.1.13 The Owner shall perform an insertion and uithdrawal test of a random selection of tan percent (10') of the fuel boxes in each df the Rack Assemblics, listed in Section 5.1.12, by cans ?f a simulated fuel assemoly.
This test shall be performed prict to transfering fuel assemblics into the Rack Assemblies.
, c... - ~, g :
PART 3 INSTRUCTIONS FOR INSTALLATIO:: OF NEW SPCNT FUCL RACK ASSCMBLIES 1.0 SCOPE 1.1 These instructions cover the work required to install the new Rack Assemblies and Seismic Supports in the spent fuel pool.
The order and sequence by which the new equipment shall be installed is contained in Part A.
2.0 REFERENCES
2.1 Part A of Installation Procedure No. NMP-T-107.
2.2 Figure 1 of Installation Procedure No. NMP-T-107.
Figure 2 of Instal ation Procedure No. NMP-T-107, 2.3 NMP-T-95, Packaging, Storage Prior to Shipping, Handling, Shipping, And On-Site Storage of Spent Fuel Rack Assemblies.
2.4 WAI Drawings:
~
115-1 113-23 115-35 115-3 115-25 115-36 1.15.;
115-27 1;3-33 115-5 115-28 115-40 115-8 115-30 115-41 115-9 (Sheet 1) 115-31 115-42 115-9 (Shoot 2) 115-34 115-44 115-21
r-3.0 mI::TC::ANCC or SCIS: TIC CLASS I CAPACILITY 3.1 Scismic Class I capability of any new Rach Assembly in..:i ch spent fuel is temporarily stored must be maintained during installation of the remaining ncw Rack Isssemblies and Seismic Supports.
Analysis has shown that temporary seismic restraint is needed for Rack Assemblies W9 and X9 prior to transfering existing spent fuel assemblies into these two Rack Assemblies.
(Refer to Part A, Section 5.1. 7) ep e
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4.0 PREPARATIONS 4.1 Prior to installation of any now Rack Assemblics ancfor Seismic Supports, the clearing and cleaning work described in Part A, Section 4.2, shall haze been completed for the area of the pecl where the installation work is to be performed.
4.2 Pricr to installation, the Rack Assemoly for a scheduled loca: en (Refer to Part A, Section 5.0) shall be determined by checking the identification number on its shipping cover with the designation of its location on Figure 1 and WAI Drawing No. 115-1.
4.3 The tarpaulin shipping cover shall be completely removed from the Rack As'embly, exposing the Lifting Spreader and four base s
corners.
4.4 The Rack Assembly shall be lifted horizontally from the truck bed and temporarily stored in the reactor building, in the horizontal position, in accordance with the procedure described in Section 7.3.2 and Figure 1 (llorizontal Lift) of NMP-T-95.
Local on-site transport, if required, shall be performed with the Rack Assembly on a truck; not while suspended on a portable crane.
4.5 The Rack Assembly shall be withdrawn from temporary storage as required and lifted in its horizontal position to the floor at Elevation 340'-0", in accordance with Section 7.3.2 and Figure 1 (llorizontal Lif t) of NMP-T-95, for inspection and preparation for installation.
4.6 The Lifting Spreader, which is attached to the top end of the Rack Assembly and was not covered by the polyethylene sheet, shall be wiped clean.
The polyethylene cover may be removed at this time to enabic convenient inspection of the Rack Assembly in the horizontal position, or the cover may be removed after the Rack Assembly has been upended to its vertical position.
All thread protection blocks and materials at the base corners shall be removed alona with the main cover.
After removal of the cover,
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condition of the Rack Assembly until it,is lowered into the pcol.
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. r *. u The Rack Assembly shall be inspected for damage, and cleaned of any dirt or foreign matter picked up during shipping and handling.
4.7 The Rack Assembly shall be upended frem t.3 horizontal to the vertical position in accordance with the procedure described in Section 7.3.3 and Figure 2 (Uponding) cf NMP-T-95.
Steel plates should be located on the floor under the two Uponding Shoes.
Plates or blocks of matched thickness should be pre-placed at locations on the floor, so that the other two corners of the base will be resting on these blocks on the floor when the Rack Assembly is in a vertical position.
After the Rack Assembly has been upended to the vertical position, the Upending Brace, between the Lifting Spreader and the base corner, shall be removed.
(Refer to NMP-T-95, Fig. 2) 4.3 A separate bc: of loose parts, containing four jack screws with base plates, is provided for each new Rack Assembly and is marked with the same identification, e.g.,
W9.
These parts shall be inspected for damage and cleaned of any foreign matter, e.g, packing materials.
Special care shall be e::ercised during handling and any subsequent temporar'; storage prior to installation
.o prevent damage to the jack screw threads.
4.9 The Rack Assembly shall be lifted vertically in accordance with the proceduro described in Section 7.3.1 and Figure 1 (Vertical Lift) of NMP-T-95, to a height convenient for working at the corners of the base.
The Uponding Shocs shall be removed from the two base corners.
IIcavy cribbing shall be built up under three of the four 6" corner posts of thn base.
Cribbina is net permitted as a support against the underside of the horizontal pipes of the base frame, nor as a support against the underside of the final support pliecs.
4.10 With the Rach Assembly suspended by the crane and supported at three corners of the base, the appropriate 1; designated jack screw shall be incerted in the unsupported corner.
Refer to rigure 2 for correct orientation of jack screws for each Rack Assembly.
Care should be exercised in guiding the jack screw to avoid damaging the threads.
After the jack screw has been inserted
-.L' *.O and turned to appro::imately three full threads of engagement, further adjustment may be performed by means of the tool previded for this purpose.
This tool is incerted down throush the water box frem the top of the Rack Assembly and engages the upper end of the jack screw.
The extension of the Rack Assembly jack screw may be pre-adjusted to suit "as built" conditiens prior to installation in accordance with Section 5.5.
Heavy cribbing shall be built up under the jack screw and base plate.
4.11 With the Rack Assembly still suspended by the crane remcVe the original cribbing from under a second 6" corner post of the base, and install the second jack screw as described in Section 4.10.
Build up heavy cribbing under the jack screw and base plate.
Repeat these operations until all four jack screvs are in place.
4.12 The Rack Assemlby is now ready for transport by the building crane to the spent fuel pool for installation.
4.13 The boxes containing the Seismic Supports are marked with Seismic Support location designations, e.g.,
"S4".
The boxes shall be unpacked and the equipment inspected for damage in accordance with the sequence of installation contained in Part A.
Care shall be exercised during handling and interim storage (e. g.,
between shif ts) to preserve the cleaned condition.
e l
a 5.0 INSTALLATION 5.1 The new Rack Assemblics and Seismic Supports shall be installed in accordance eith the sequence of activities described in Part A, Section 5.0.
5.2 New Rack Assemblies and Seismic Supports shall not be lifted or transported over any spent fuel assemblies stored in the pool.
5.3 The Seismic Supports shall be set on the pool floor at the locations indicated by dimensions shown on NAI Drawing No. 115-1 as modified by "as built" conditions.
Seismic Supports at locations S2, 53, S4, SS, S6, S7, S3, and S16 (Types J, K,
L, and M on NAI Drawing No. 115-21) are equipped with adjustable jack screws to aid in alignment with the Rack Assembly bases.
The entension of the Seismic Support j a :: scrs.s may be pre-adjusted to suit "as built" conditions prior to installatien.
5.4 Guide lines shall be attached to the Rack Assembly to enable guiding it during lowering into the spent fuel pool.
This guidance is necessary to assure protection against da.nage to the pool walls and will facilitate positioning the Rack Assembly to its correct location and directional orientation in accordance with WAI Drawing No. 115-1.
5.5 With the Rack Assembly suspended in the vertical position above the floor the four jack screws shall be adjusted to a preliminary setting so thct the Rack Assembly will be uniformly suppo"ted in a level position by all four jack screws.
It is suggested that the preliminary setting be such that the bottoms of the 6" round jack screw base plates are 11 1/2" below the bottoms of the fuel support plates.
Similarly, it is suggested that the bottoms of the 4" square jack screw base plates be set at 10" below the bottoms of the fuel support pi ttes.
Final adjustment and leveling shall be performed after the Rack Assembly has been located in its final position on the pcol floor.
(See Secticn 3.9)
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3.2
.._... :..e guice linas manned at the floor (Clevation 340'-0")
and the Rack Assembly securely attached to the crano hook, and suspended in a reasonably level position, the Rack Assembly shall be carefully lowered toward its correct position on the floor of the pool.
As the Rack Assembly appr: aches the pool floor, special attention shall be given to its lateral positiening relative to the previously installed Seismic Supports.
The final position of the Rack Assembly shall be at the locations indicated by dimensions shown on WAI Drawing No. 115-1 as modified by-"as built" conditions.
The corner base plates of all Rack Assemblies shall rest directly on the pool floor, except those corner base 4
plates located at Seismic Support locations S9, S10, Sll, S12, S13, S14, and Sld, which shall rest directly on the Seismic Supports.
5.7 Special care shall be exercised during installation of Rack Assembly W9 to prevent interference with the existing fuel preparation machine on the East wall of the pool.
The East side of the Rack Assembly shall be kept approximately 3'-0" from the East wall during lowering into the pool.
The Rack Assembly shall be lowered to a minimum elevation above the pool floor at which the jcck screw base plates will clear the top of the existing clevises, which extend 3 1/4" above the pool floor.
The maximum elevation above the pool floor to which the Rack Assembly shall be lowered shall be that at which the bottoms of the fuel support plates are 16" above the pool floor.
This will permit the base frame pipe at the East. side of the Rach Assar.bly to paas partially under the lower stop plate of tho' fuel preparation machine to the correct latcral location of the Rack Assembly.
With the Rack Assembli suspended 16" above the pool floor, and with the jack screws adjusted to clear the clevises at this elevation (Refer to Section 5.5), the Rack Assembly shall be moved toward the East wall of the pool to its final lateral loc.ation, and. lowered to rest on the pool floor.
L__
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' 5. 8.- Special care _ shall be exercised during installation of Rack Assembly X9 to prevent interterence with the existing fuel preparation machine on the Cast wall of the pool.
In addition to all the precautions and instructions contained in Section 5.7 special attention should be directed to the jack screw base plate (square) at.the Southwest corner of the Rack Assembly.
This jack scrow base plate will rest on Seismic Support 59, and the Rack Assembly shall be lowered to a minimum elevation which will 5
permit.the jack screw base plate to clear the Seismic Support, the sides of which extend approximately 3 3/4" above the pool floor.
(Refer to Section 5.5)
~ After the Rack Assembly has been set on the pool floor in its 5.9-correct lateral location,-the jack screws shall be adjusted to
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assure that the Rack Assembly is resting solidly at all four corners and is level.
Adjustment of the jack screws is accomplished by inserting the extension t6ol down through the apprcpriate water boxes and engaging the slots at the tops of the jack screws.
The final levelness and verticality of the installed Rack Assembly may be verified by any of several methods or combinations
- hereof, e.g.,
by placing a precise level across the tops of the fuel boxes, or by suspending a plumb bob along the sides of the Rack Assembly.
Verticality is considered acceptable, if a side of the Rack Assembly is plumb within 0.15" of the true veritcal over its total height.
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5.10 When Ehe lateral positioning, setting, and final leveling have been completed, the Lifting Spreader shall be detached from the Rach Assembly and removed frcm the pool.
The Lifting Spreader is detached _from the Rack Assembly by removing the three 1" bolts, located in the lugs marked "A",
by means of an extension tool capable of unscrowing the bolts and capturing them for removal from the pool.
The Lifting Spreader can then be lifted from the pool by means of the crane.
1 5.11 All of the ab5ve opera tions in the pool may be performcd ay the use of _ remote handling tools and/or the assistance of divers.
.i 6.0. TESTIMG Prior to transfering spent-fuel assemblics into a newly installed Rack Assembly,-the Owner shall. perform an insertion and withdrawal
. test of a random selection of ten percent (101) of the fuel bo::es in the' Rack Assembly by means of a simulated fuel assembly.
7.0- CLEAN-UP AND INSPECTION After completion of the installation of all Rack. Assemblies and Seismic Supports,'all permanent equipment temporarily removed from the pool and its surrounding area shall be restored to normal-locations and conditions.
All temporary equipment and tools shall l
be removed from the area.
A general inspection and check shall be performed to assure completion of the entire rack replacement work.
8.0 - DCCUME::TS AND RECORDS,
Upon completion of his responsibilities for the scope of the spent fuel rack replacement, the Installer shall provide a Certificate of Compliance certifying that he has met all the requirements.
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r (Installation Procedure !!o. MMP-T-107)
ORIE::T.'.TIO:1 OF JACK SCREMS ON RACK ASSE::BLIES NW
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