ML19317G742

Forwards Info for Study on Control of Heavy Loads Near Spent Fuel. Util Procedures Re Movement of Heavy Loads Over Reactor Core,Spent Fuel Storage Pool & Required Equipment for Safe Shutdown Encl

ML19317G742
Person / Time
Site:	Rancho Seco
Issue date:	07/17/1978
From:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Stello V Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR NUDOCS 8004010572
Download: ML19317G742 (48)

Text

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9/3.f7 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISYRIBUTION FOR INCOMING MATERIAL 50-312 REC: STELLO V ORG: MATTIMOE J J DOCDATE: 07/17/78 NRC SACRAMENTO MUN UTIL DISY DATE RCVD: 07/20/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 40 ADDITIONAL INFO CONCE)MTNG HEAVY LOADS AND SPENT FUEL FOR A STUDY ON " CONTROL OF MEVY LOADS NEAR SPENT FUEL" PLAAT NAME: RANCHO SECO (SMUD)

REVIEWER INITI AL:

XRS DISTRIBUTOR INITIAL: 4{f

• • • • • • • • • • • • • • • • • DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************

GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE A001)

FOR ACTION:

BR CHIEF ORB #4 BC**W/7 ENCL

[._ REG FILE **W/E.NC NRC PDR**W/ ENCL INTERNAL:

I & E'EW/Z"ENCE OELD**LTR ONLY HANAUER**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J.

MCGOUGH**W/ ENCL EXTERNAL:

LPDR'S SACRAMENTO, CA**W/ ENCL REGION V**W/ ENCL TERA **W/ ENCL NSIC**W/ ENCL ACRS CAT D**W/16 ENCL 95NNEN lggg DISTRIBUTION:

LTR 41 ENCL 40 CONTROL NBR:

f(k t

SIZE: 1P+4SP conocc*****************************

THE END

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • Q 800401g & ] p

o g) S.ACRAMENTO MUNICIPAL UTILITY DISTRICT O 6 SMU=

95813; (916) 452-3211 July 17,1978 Director o'f Nuclear Reactor Regulation Attention:

Mr. Victor Stello, Jr., Director Division of Operating Reactors Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No.1

Dear Mr. Stello:

Your letter of May 17, 1978 requested information concerning heavy loads and spent fuel for a study on " Control of Heavy Loads Near Spent Fuel." The attachment to this letter provides the information for each item requested.

Please contact us if you have any additional questions.

Sincerely yours,

.'.b J.' J. Mattimoe Assistant General Manager and Chief Engineer Attachments gg\\.hiyg4g@1;Ei l

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ATTACHMENT

'l.

R' quest:

e Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.

Response

The diagram requested is supplied as Enclosure 1 to this attachment.

2.

Request:

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 i

each object listed, provide its approximate weight and size, a diagram 1

of the movement path utilized (including carrying height) and the frequency of movement.

Response

Fuel, control rods, burnable poison rods, or orifice rods are moved over the fuel transfer canal on almost a continuous basis during refueling.

Once per refueling, an underwater light and a television camera are moved over the reactor core for fuel verification.

Fuel, burnable poison rods, and orifice rods are routinely moved over the spent fuel pool during refueling. Control rod handling tools and source handling tools are moved on a much less frequent basis.

The failed fuel container is the only object of significance which might be moved over the spent fuel pool.

It weighs roughly 2,000 pounds (dry) with a fuel assembly enclosed.

Frequency of movement of the failed fuel container should be much less than once per refueling. Movement path of the failed fuel container is shown on Enclosure 2 of this attachment.

3.

Request:

What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?

Response

The District has not comitted to use a specific cask.

However, it will probably use a cask similar to the General Electric IF-300 which weighs roughly 136,000 pounds fully loaded.

Its diameter is 64" and its length is 198".

4.

Request:

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.

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Attachnunt Pag 2 2

Response

The answer to FSAR Question 5A.43 details the results of the spent fuel cask drop analysis, while the response to Question 9A.32 addresses possible drop distances.

Drop of the missile shields, the upper plenum assembly, and the reactor vessel head are evaluated in the response to Question 9A.45.

5.

Request:

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, punps, etc.) and discuss the feasibility of such an accident affecting this equipment.

Describe the basis for your conclusions.

Response

The reactor building polar crane and the reactor building auxiliary bridge crane are the only lifting devices installed over equipment required for safe shutdown.

They are installed over the reactor vessel head which contains the control rod drives.

Control rod drives are required for plant shutdown. However, the reactor building polar crane and the reactor building auxiliary bridge crane are not used when the plant is in operation and thus they could not feasibly affect safe shutdown of the plant.

6.

Request:

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

Heavy loads moved over the fuel transfer canal include the missile shields, the reactor vessel head, and the reactor plenum.

The missile shields are handled in a manner so as to prevent a drop over the reactor vessel from damaging either the reactor vessel or the reactor vessel head.

The handling method is described in the response to FSAR Question 9A.34.

Missile shields do not normally require movement during any period in which the fuel transfer canal is flooded.

FSAR Questions 9A.34 and 9A.45 discuss the consequences of a reactor vessel head drop. The head will not be lifted more than 3.5 feet and a drop from this height would not cause severance of any cooling water supply lines required for decay heat removal.

During lift of the reactor vessel head, the fuel transfer car.al is not flooded, so possible drainage of the fuel transfer canal need not be considered.

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Attachment Page 3

.FSAR Questions 9A.34 and 9A.45 also discuss the. consequences of a plenum drop. Since the potential impact of a plenum drop-from maximum handling height is considerably less than that of the reactor vessel head, any drop of the plenum will cause less damage to reactor vessel-cooling water connections than a reactor vessel head drop. Since the plenum is handled in a flooded fuel transfer canal, a drop on the seal plate around the reactor vessel could result in drainage of the upper section of the fuel transfer canal. No fuel would be uncovered.

The only heavy load handled.over the spent fuel' pool is the spent fuel i

cask. < As described in the responses to FSAR Questions SA.43, 9A.32, and 9A.33, the detailed analysis of a spent fuel cask-drop shows -little potential for serious leakage.

l 7.

Request:

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.

i

Response

Both the spent fuel cask gantry crane and the reactor building polar crane conform to the standards applicable at the time of their design.

The standards used, the testing required, and the failure modes considered for both types of cranes are described in the response to FSAR Question 9A.33.

This response also shows how the spent fuel cask gantry crane is interlocked to prevent movement over spent fuel' storage locations.

8.

Request:

i Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipmer.t required for the safe shutdown of a plant that-is operating at the time the move occurs.

Response

Pertinent sections of all procedures concerning movement of heavy loads l

over the reactor core, the spent fuel storage pool, or equipment required for safe plant shutdown are included as Enclosures 3 through 8 of this attachment.

Included are the administrative procedure for " Fuel and Component Handling," the operating procedure for '.' Refueling," and the i

maintenance procedures for " Reactor Vessel Closure Head Removal and Replacement," " Reactor Internals Removal and Replacement,". and " Operation of the Reactor Building Polar Crane and the Fuel Transfer Canal Auxiliary Hoist."

In addition to the continuously effective procedures' listed above, a special test procedure is written to control each refueling. A copy of pertinent sections of " Refueling Rancho Seco for Cycle 2" is also included.

1 Attachment

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Pag 2 4

,9.

Request:

Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1, December 1975) regarding Spent Fuel Storage Facility Design Basis.

Res ponse:

A summary of the compliance of Rancho Seco Fuel Storage Facilities with the March 10, 1971 issue of Safety Guide 13, Fuel Storage Facility Design Basis, is provided in response to FSAR Question lA.2.

The December 1975 revision of Safety Guide 13 (now called Regulatory Guide 1.13) changed no regulatory positions which would alter the Rancho Seco status of compliance with the Regulatory Guide.

Enclosures I

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p ENCLOSURE 3 I

A.13' FUEL AND COMPONENT HANDLING 1

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1.0 PURPOSE

.1 Provide procedures to accomplish the following operations:

.1 Transfer and inspection of new fuel from transporter to new fuel storage ^ racks (dry storage). (Section 4.1)............... A.13-6

.2 Transfer new fuel from dry' storage

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to fuel storage pool. (Section 4.2)........ A.13-11

.3 Return of new fuel shipping

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container. (Section 4.3)...................A.13-11

.4 Fuel storage pool bridge checkout

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prior to operation. (Section 4.4)..........A.13-12

.5 Transfer carriage and tran'sfer

,yg carriage tilting mechanism checkout

.j prior to operation. (Section 4. 5}.......... A.13-13

.6 Identification and indexing of fuel assemblies in fuel storage

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pool. (Section 4.6)........................A.13-33

.7 1rcasfer and inspection of control components from transporter to storage. (Section 4.7).....................A.13-33

.8 Shipping of Spent fuel from site

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(LATER) (Section 4.8)......................A.13-33

.9 Relocation of Primary Neutron Source (s) (Enclosure 8.16,

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Se c tion 4. 7)............................... A.13-73

.10 Normal operation. (Section 5.0)............A.13-48

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.11 Equipment shutdown. (Section 6.0).......... A.13-44

.12 Lhading the new fuel shipping container (Section 7.1)....................A.13-46 s,

.13 Unacceptable 6r questionable fuel assembly. (Section 7.2)....................A.13-4E i

.14 Adjustamat of fuel assembly clamps.

(Section 7.3)..............................A.13-43 A.13-1 Rev. 4 "

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.15 Unacceptable or questionable rod assembly. (Section 7.4)....................A.13-50

.16 Failed fuel detection container operation (LAIER).

Section 7.5)...........A.13-51

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.17 Malfunction of fuel transfer carriage. : (Section 7. 6)................... A.13-52

.,18 Sample forms for receipt 'and inspcetion of nek fuel and new control components.

(Enclosures 8.1-8,5)

A.13 i A.13-61

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.19 Neutron Startup Source Handling.

(Enclosure 8.16)...........................A.13-73 2.0 RE FERENCES

.1 Standard guide specification for customer-provided facilities for receiving, unloading, handling, inspection and storage of Mark B2 fuel assemblies.

B&W Spec. No. 2042.

.2 Mark B2 fuel assembly dimensions for handling and shipping

-,f Dwg. No. 6292 N2.09-1.

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.3 Radiation Control Manual, AP 305.

.4 Standard guide specificaticn for customer-provided facilities for recieving, unloading, handiing, inspection and storage of Mark,B2 core control components.

B&W Spec. No. 2044.

.5 Axial power shaping rod assembly, Bechtel Dwg. No. N4.01-307.

.6 Orifice rod ascembly, Bechtel Dwg. No. N4.01-308.

.7 Control rod asserbly, Bechtel Dwg. No. N4.01-309.

.8 Burnable poison rod assembly, Bechtel Dwg. No. N4.01-306.

3.0 LI! -

AND PRECAUTIONS

.1 New fuel assemblies shall be handled only by suspending vertically from the new fuel handling tool unless secured to a vendor fuel shipping container strongback.

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.2 Puel assemblies may be placed in a vertical standing position if l

bottom and lateral supports are provided which conform to dimensional tolerances which will not allow assembly to deform s

and which provide suitable lateral restraint a'nd guidance at the upper end fitting te m'intain verticality.

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A.13-2 Rev. 4

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3. 0 LIMITS & PRECAUTIONS (Cont'd)

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1

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For restraining the fuel assembly during vertical storage, only.

the permissible clamping surfaces on the upper and lower and fittings shall be used.

.4 The fuel assemblies shall not be removed from the shipping containers unless all of the supporting documentation is available to the inspecting party.

.5 Filter paper is placed in the fuel assembly polyethylene cover to alloy water to drain from the fuel assembly in the event of flooding and subsequent drainage. Do not cover paper in such a manner as to prevent self-draining of a stored fuel assembly.

If the poly cover must be replaced, provide drain holes covered with filter paper (common lab-type) as for original cover.

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.6 Manual handling of fuel assemblies shall be done while wearing -

white, lint-free glovee.

.7 In no case should an attempt be made to load or unload a fuel assembly from the shipping container unless the strongback l1 is locked in the vertical position by both support rods.

.8' Fuel assemblies shall not be left in the strongback in tha vertical position while unattended.

The strongback shall be 1( ?)

lowered to the horizontal or supported from the crane hook to prevent tipping.

.9 Fuel assembly containers shall not be opened or fuel moved l1 unless all doors to the new fuel building are closed, building ventilation is in service, and the inspection area is clean.

.10 In order to keep fuel and storage area clean', 'all personnel

. handling fuel will ssar protective clothing consisting of f

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lint-free coveralls, cotton gloves, shoe covers, and surgeon (f

caps.

l.11 Only one fuel assembly shall be handled at a time, with the '

f remainder of the fuel assemblies located either in the storage

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racks or in a shipping container.

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.12 Personnel handling fuel will, wear. dosimetry _egu.ipment as,,,_

directed by the Radiation Control Group and the applicable Radiation Work Permit.

.13 Do not operate fuel handling equipment with any interlock 1

bypassed or inoperative without responsible supervision.

Whenever possible, *,he manual override capability snould be used instead of the motors for operation with bypasses enabled.

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A.13-3 Rev. 1

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p 3.0 LINITS & PRECAUTIONS (Cont'd) s

.14 Maintain cleanliness standards during fuel and rod assembly handling.

.15 Rod assemblies shall be handled only with the specified tools.

.16 Do not continue to raise or lower a rod assembly following an over-or underload indication without first determining the cause of the condition.

Inspect and evaluate any component subjected to a misaligament or overload condition.

.17 Do not handle irradiated rod assemblies in any manner that could reduce the water' shielding depth below the minimum specified by OPOP B.8.

.18 Except when' transported within a fuel assembly, dummy fuel assembly, or rod assembly shipping container, rod assemblies must be suspended vertically.

Any control component handled in violation of this shall be reinspected and evaluated prior to use (Section 4.7).

.19 Short rod assenblies may.be handled manually provided no loads are imposed or. the pins in other than an axial direction. No load in the axial direction shall be allowed other than the essembly itself plus the rod assembly handling tool with the

.cf, short actuating handle.

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.20 *The rod assembly shipping containers shall not be opened unless all of'the supporting documentation, as listed in the following procedure, is available to the inspecting party.

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.21 A minimum of three alpha swipes shall b'e taken and counted for each new fuel shipping container; two swipes of the container inside surface of 100 cm2 eachs one swipe on each 2

fuel assembly of 100 cm each, acceptable is equal to or less than 2-1/2 times background.

.22 Do not remove a primary, spent or irradiated source from the fuel pool water nor raise the source above a level which produces gamma or neutron radiation levels inconsistant with job time requirements or for which required radiation protection measures are not in effect.

.23 Do not allow new fuel bridge crane cable or sling to become slack when lowering or bottoming source handling tool in any location.

.24 ! Source handling operations should be carried out in the spent fuel pool area only.

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I A.13-4 Rev. 1

(% ',l 3.0 LIMITS & PRECAUTIONS (Cont'd) i

. 25.

Handle' sources with designated handling equipment only.

.26 Store scurce and/or shroud tube assembly only in locations approved for such storage.

.27 This procedure is written for handling a 300 curie or smaller source. Larger sources require a separate procedure.

.28 If a new fuel assembly is dropped:

.1 Personnel evacuate the Spent Fuel Building.

.2 Personnel stay in a group immediately outside the Spent Fuel Building door.

.3 Dispatch one man to nearest telephone to inform the Control Room of the situation.

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.4 Personnel are to remain in one area until Radiation Control personnel have surveyed the area and announced it to be clean.

.5 After it has been confirmed that no radiation problem exists, store the affected assembly away from the remaining fuel.

Cover and seal the assembly if possible.

.29 If a spent fuel assembly is dropped:

.1 Personnel evacuate the Spent */uel Building to the

,f change room if the area radi.ition monitor is not alarmed.

If the area radir.cion monitor is alarming, evacuate to the Warehouse,as per the Emergency Plan.

.2 Inform the Control koom of the situation.

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.3 A Radiation Control team is to survey the area, i

enter the Spent Fuel Building and proc'ure air samples and gaseous activity samples.

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.4 When possible, the assembly should be visually inspected for damage.

.5 When the area is cleared by Radiation Control personnel, place the affected assembly in the Failed Fuel container.

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.30 Do not operate the new fuel bridge crane in such a way that loads are moved over stored fuel assemblies unless absolutely necessary.

.31 Boron concentration of pool water is >1800 ppa.

.32

' All slings used for hoisting and transporting fae.'. assemblies should be tested and inspected using the Department of Labor 1

(OSHA) Rules and Regulations, Part 1910, dated 6/27/75, as a guide.

N A.1.'i-5 Rev. 4-ee

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4.0 FUEL AND COMPONENT HANDLING

.1 Transfer and Inspection of New Fuel From Transporter to New Fuel Storage Racks (Dry Storage).

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Initial Conditions

'.1 New fuel storage cells available.

.2 Tools and material of Enclosure 8.6 available.

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Frocedure

.3 The inspecting requirements Forms No. RS-24 and RS-26 shall be performed in the order listed.

The Forms have spaces to compara manufacturerk versus field-

-checked observations.

The results shall be acknowl-1 edged by vendor and SMUD representatives on Forms N.

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RS-24 and RS-26 at the completion of the inspection.

The report forms RS-24 through RS-27,,shall be numbered in a consistent series starting with the first form of a kind used for a particular NSC contract. Attach-ments shall bear the same serial number as the form of which they are a part.

.4 Inform the Radiation control Group that a new fuel shipment is to be unloaded.

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.5 Position the transporter with the fresh fuel shipping container aboard under the pick-up point of the 1

Turbine Building Gantry Crane.

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.6 Radiation Control Group shall complete a smasc survey l

of the transportar.

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.7 Execute bill of lading. Any comments attached to

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the bill of lading should be noted on Form RS-24 1

or its attachment, Form RS-25.

.8 Execute Form RS-24.* Verify container serial number 1

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with shipping notice.

.9 Fill in information on attachments Form RS-25. At this time, collect all documentation accompanying 1

shipment, with the exception of QC maps which will be inserted in container record receptacle. Record any tripped accelerometers.

.10 Release tie-downs and remove containers from vehicle, y

using a 4-point sling and Turbine Building Gantry Crane or a Fork Lift.

(See Enclosure 8.15)

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A.13-6 Rev.1

4NCLOSURE 4 B.8 REFUELING

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TABLE OF CONTENTS Page Nos.

1.0 Purpose B.8-2 2.0 L, imitations and Precautions B.8-2 thru B.8-7A 3.0 Equipmant Operational Status Checks

.1 Communications Systems B.8-7A

.2 Lighting Systems B.8-7A thru B.8-8

.3 Tra'nsfer Carriages and Upending Mechanise Check Out B.8-8 thru B.8-23

.4 Auxiliary Fuel Handling Bridge Check Out, B.8-24 thru B.8-32A

.5 Main Fuel Handling Bridge Check Out B.8-33 thru B.8-47

.6 Axial Power Shaping Rod Uncoupling B.8-48 thru B.8-53'

.7 h ial Power Shaping Rod Alternate Uncoupling Procedure B.8-53 thru B.8-57a

.8 Torque Tube APSR Uncoupling B.8-57a thru B.8-57d

.9 Coupling Leadscrew to Axial Power Shaping Rod B.8-57d thru B.8-63

.10 Axial Power Shaping Rod' Alternate Coupling Procedure B.8-63 thru B.8-66

.11 Regulating and Safety Rod Leadscrew

, Uncoupling

- B.8-67 thru B.8-70

.12 Regulating and Safety Rod Leadscrew Alternate Uncoupling Procedure B.8-70 thru B.8-74

.13 Couplit.g Regulating or Safety Rod Leadscrew to the Control Rod B.8-74 thru B.8-77

.14 Alternate Coupling Procedure for Regulating, or Safety Rod Leadscrew B.8-78 thru B.8-80

.15 Returning Control Rod Drives to Service B.8-80

.16 Handling Tools Check List 3.8-80 ticu B.8-81 1

.17 Pilling the Fuel Transfer Canal to Refueling Level B.8-81 thru B.8-83 4.0 Refueling B.8-83

.1 Fuel Assembly Handling B.8-83 thru B.8-90

.2-Transfer of a Control Rod B.8-90

.3 Repositioning of Control Rod Assemblies B.8-90 thru B.8-91

.4 Preparation for Power Operation B.8-92 5.0 Enclosures B.8-93 thru B.8-100 3

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B.8-1 Rev. 3

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.UCSM'o'vides dett.iled steps for refueling equipment check out.

.2 Provides limits and precautions for refueling operations.

.3 Provides guides for plant systems status during refueling.

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.4 Provides detailed steps for coupling and uncoupling Control Rod Drive mechanisms.

.5-Provides guides for filling fuel transfer canal.

. 6-Provides detailed steps for Control Rod exchanging.

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Pr'ovides detailed steps for' fuel removal and replacement.

2.0

$IITATIONSANDPRECAUTIONS

.1 A radiation work permit is required for all evolutions involving el o

operation.of fueling eqtiipment.

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.2 On all mechanisms operated over the reactor, canal, or pool,

'I all small tools and,"other items must be secured by a safety line.

.3 All safety glasses uorn by personnel shall have a restraining strap attached.

.4 All film badges and pocket dosimeters shall be taped securely to prevent falling from pockets.

.5 Area radiation monitors shall. be fully functional and in service.

.6 Portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect individuals shall be readily accessible in the event an area monitor b2comes unserviceable.

.7 Core suberitical neutron flux shall be continuously monitored by at least two neutron flux monitors, each with a continuous indication available, whenever core geometry is being changed.

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When core geometry is not being changed, at least one neutron flux monitor shall be in service.

.8' At least one d,. cay heat removal pump and cooler shall be operable.

49 During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shc11 be maintained at not less than that required for refueling shutdown.

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.10 Direct communications between the control room and the refueling

' personnel in the reactor building shall exist whenever changes in core geometry are taking place.

.11 ~ During the handling of irradiated fuel in the reactor building, at least one door on the personnel and emergency hatches shall be closed.

The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.

.12 Isolation valves in lines containing automatic containnent isolation valves shall be operable, or at least one shall be closed.

.13 When two irradiated fuel assemblies are being handled simultaneously within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times.

Irradiated fuel assemblies may be handled with the auxiliary hoist provided i

no other irradiated fuel assembly is being handled in the fuel transfer canal.

.14 During the installation or removal ~of a fuel element or a control rod if count rate increases by a factor of 10 on any two source i

range instruments concentrated boric acid shall be immediately i

injected to reduce the count level and further movement shall stop until an evaluation has been made.

.1j The reactor building purge system, including thw radiation monitors R-15001A and R-15001B shall be tested and verified to-be operable immediately prior to refueling operations.

.16 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

.17 No heavy loads will be handled over irradiated fuel when it is stored in the spent fuel pool, except during fuel handling operations.

.18 The refueling canal shall be maintained below 140*F when fuel handling operations are being conducted.

.19 only persons authorized by the Shift Supervisor shall be allowed entry into the fuel handling areas during refueling.

i

.20 At the commencement and completion of each evolution, the control room shall be notified and the control room operator will record the evolution.

.21 Prior to the commencement of this procedure, an inspection shall be made to insure that all loose or foreign material has bee-removed from the fuel han'dling areas.

.h l

.22 A tool and equipment accountability log shall be established

(

prior to the reactor vessel head removal and all material brought into and removed from the refueling area shall be l

logged accordingly.

See AP.35.

l3 f

.B.8-3 Rev. 3

~~ ------- ~'~

'~ -~' ~ ~' ~ ~

~ ~ ~ ~

o r

Dl '

.23 Refueling bridges shall not be operated with any interlock V

' bypassed unless approval has been g' ranted by the on-duty Shift Supervisor.

Af ter bypassing an interlock, the key'shall be returned to the Shift Supervisor.

.24 All refueling bridge interlocks that are bypassed shall be immediately recorded by the control room gperator.

.25 Prior to shift change of the refueling operators, all interlocks that.were bypassed shall be placed in the normal position and reported to the control room to be recorded.

.26 All incore monitor assemblies hva been withdrawn in accordance M.30.

2

.27 Any system which might decrease the boron concentration by causing dilution will be either isolated or its operation monitored.

.28 Prior to fuel handling, verify tilat the water level in the fuel transfer canal is not varying by conducting water level measurements of the transfer canal and spent fuel pool.

Water level shall be maintained between 38'3" and 38'9".

.29 Prior to insertion of'a fuel assembly into the reactor two Qf

~;

• people shall check that.the fuel assembly contains the correct 1

CRA, ORA, APSRA, BPRA, as the case may be.

.30 During the actual fuel loading, no. fuel assembly will be disengaged from the handling device until an equilibrium count rate has been established on all indicating channels.

If count increases by a factor of 2, allow 5 min. for stabilization.

Then recount.

.31 Followin3 fuel assembly insertion, tw'o persons shc11 independently verify that the fuel assembly identification and core position are correct and the fueling Atatus boards shall be updated.

.32 Any manipulation involving irradiated or radioactive components shall be conducted in a manner providing maximum water and/or mechanical shielding compatible with desired o'perations.

.33 Before any fuel assem5 ly or contitol assembly is lowered, a visual check shall be made for proper location and that no i

obstructions are in the way.

.34 Periodic checks shall be made during fueling operations to verify that fueling bridge interlocks are operable.

,35 Construction or maintenen'ce on the reactor coolant system shall be suspended while fueling operations are in progress.

B.8-4 : Rev. 2

(....

,1-i*

j

.36 During fuel handling or control component handling, if a sudden increase or decrease in load is observed, the operation shall i

be.immediately stopped. and an evaluation made prior to any further movement.

.37 A core status display shall be maintained in the control room, spent fuel building and containment building throughout fuel or control component handling.

l

.38 Spent fuel pool and fuel transfer canal levels should be such that a minimum of 9 f t. of water, is maintained over the active fuel lini of the spent fuel assemblies.-

.39 If an unexpected increase or decrease in count rate occurs on one or more neutron flux monitors, loading will be suspended until the reason has been determined and evaluated.

4

.40 All recorded neutron levels will be the average of. three successive stable counts.

If the count rate is greater than 100 eps, the count will be for 10 seconds.

If the count rate is less than 10 cys, the count will be for 100 seconds. A stable count is within:

i2

/.counti + count 2 + count 3 3

)

.41 The transfer canal water shall be s' mpled for boron concentration a

every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during refueling operations.

.42 I

Reactivity additions shall not be made until the effects of preceding additions have been evaluated and until the core response from subsequent addition has been estimated.

.43 Plots of reciprocal neutron multiplication as 'a function of the parameter identifying reactivity change shall be maintained.

independently by at least two persons.

Each person shall use data from two or more neutron detectors.

Fuel loading will be suspended until the reason has been determined and evaluated, if the next fuel assembly loaded will constitute as much as 1/3 of the additional fuel which the loading curves predict is necessary for criticality.

.44 If fuel loading is interrupted for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, it may be necessary to renormalize the inverse multiplication plot. New plots will be on the same chart in use before operations were interrupted.

.45 If fuel 1dading operations have been delayed more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify the operability of the neutron monitoring systems by running a chi square distribution.

If chi square is not in specificationa, renormalized plot.

.46 l

No fuel, control rod inter'nals or..otl),ex assembly shall be l

handled with other than ppecified tools.

• B.8-5 9

,y-.

<--,4

,y.,

w.

e o.

. =.

r 7 s c

).

i

.47 Do not place any fuel assembly, control or internals component or other such item in any location not specifically designed '

to receive that assembly.

.48 Handling speeds and manual operations shall be conducted in a manner to prevent impacting any objects and to avoid excessive deceleration loading.

Specifically:

d

• 1 Maximum lowering speed within one foot of an object shall not be greater than 6 feet / minute.

.2 Maximum lateral speed within f,1ve feet of any object shall be not greater than 2 feet / minute.

.49 Fuel assemblies shall.be suspended in a vertical position.

unless secured to a stronaback.

.50 Long rod assemblies shall be' suspended in a vertical handling i

position unless inserted in a fuel assembly, a rod shipping container or a rod handling container.

.51 The following limits apply when manually handling shcre rod 7

r assembly:

.)

.1 No loads are imposed on the pins in other than an axial direction.

.2 No load in the axial direction shall be allowed other than the weight of the assembly itself plus.the weight of the rod assembly handling tool with the short actuating handle.

.52 All refueling equipment shall be checked or tested before fuel loading starts in accordance with the applicable sections -

of this procedure.

.53 Fuel bridge operation shall be done only by persons who are fully qualified 'and auth'orized to do this work, or by other individuals only when they are under the direct supervision of such qualified and authorized persons.

.54 No equipment containing glass shall be allowed in the fuel handling areas unless it is in an enclosure of a non-breakable type.

.55 Any water added to the refueling canal shall be of primary water quality and at least 1800 ppab.

.56 If any of the above limits and preen.utions can not be satisfied,

~

fueling operations shall be stopped and the shife supervisor

's_)}

i immediately notified.. ' Fueling operation ghall not continue until an evaluation of the problem has been completed.

r B.84

-- u.~

\\;

~~

'.57 Hourly readings'of neutron flux shall be recorded continuously

• in addition to those required for refueling operations.

Allhuelelementsandcomponentsshallhavebeeninspectedin

.58 accordance with 0F A.13, prior to being transferred to the containment building.

.59 Prior to fuel movement the reactorthead shall be installed on the head storage stand and the upper plenum shall be stored in the fuel transfer canal.

'3

.60 Refueling' operations shall not be conducted unless the minimum personnel requirements are met in accordance with Enclosure 5.5.

.61 If a new fuel assembly is dropped:

.1 Personnel evacuate the reactor building.

.2 Personnel stay in a group immediately outside the reactorm building main personnel

• hatch.

.3 Dispatch one man to nearest telephone to inform the Con?.rol j

Room of the situation.

.4 Personnel are to remain 15 one area until health physics f

personnel have surveyed the area and announced it to be clean.

g

.5 When health physics confirms that no radiation problem exists, store the affected assembly away from the remaining b

fuel.

I

'1

!l t

If a spent or irradiated fuel assembly is dropped:

s

.1 Personnel evacuate the Reactor building to the Auxiliary building change room.

.2 Inform the Control Room of the situation.

.3 A radiation control team is to survey the area, take remote Reactor building air and gaseous activity samples.

.4 Re-entry into the containment building shall not be allowed until a full evaluation has been made and approval, g

by the Plant Superintendent has been granted.

.5 When possible, the assembly should be visually inspected j

for damage.

t B.8-7 Rev. 3 '

l

(

r,.

e

.6 When the area is cleared by Health physics personnal, transfer the affected assembly to the Spent Fuel Pool and place it in the failed fuel container.

.52

. Any changes to this procedure shall be in accordance with AP.2.

1

.63 Stop logs in Spent Fuel Storage Pool between tilting devices, and Spent Fuel Pool must be in place before draining or filling the Fuel Transfer Canal.

3.0 EQU1PMENT OPERATIONAL STATUS CHECKS

.1 Communications Systems.

Initial Conditions

.1 Communications and television systems have'been energized by the instrument department.

Procedure

.' 2 control room operator will ve.rify visual communication with all areas of refueling operations by use of pan

-fh and tilt devices of the television camera.

-JV

.3 Voice communications will be verified by actual trans-mission in both directions between refueling areas and Control room.

2 Lighting Systems Initial Conditions,

.1 Lighting has been energized for approximately ten minutes.

NOTE:

Do not energize water cooled lightingnunless it is fully submerged in water and fully vented.

B. 8-7A Rev. 1 i

y1 e

G G

4 e

,r 3.0 LINiTATIONS AND PRECAUTIONS (ccutinu:d)

.2 No operation requiring a specific Reactor Coolant System or Ranctor Vessel water level shall be comenced without verifying that the required level exists and can be maintained.

r

.3 During handling and servicing operations do not strike the Reactor Vessel or the vesse.1 head with any object or allow the head to strike any object in a manner which will cause a visible deformation of the metal surface.

.4 Prior to maintenance or repair operations Health Physics controls must be established before any component which has been exposed to the Reactor Coolant System,is opened or removed.

.5 Handling of the Reactor Vessel head seal 02 rings shall be such that the 0-rings are not deformed to an extent greater than that imposed for the shipment of new 0-rings.

.6 Adhere strictly to procedures set forth in Refs.' 2.9, 2.10, 2.11, 6

and 2.12.

.7 The Reactor Coolant System must be greater than 1800 PPM Boron prior to closure head removal.

4.0 SPECIAL TOOLS / EQUIP.'ENT h

.1 Tools and equipment as per Refs. 2.1, 2.6, 2.7, and'2.8.

[

6 5.0 TESTING / ACCEPTANCE CRITERIA

.1 None 6.0 PROCEDURE INITIAL

.1 Initial Conditions

.l

.1 Clearance obtained;. Work' Request No.

.2 Missile shiciding slabs removed from above the Reactor Vessel.

r

.3 Insulation storage racks are in the canal near 6

the Reactor Vessel head.

h H.1-2 Rev. 6

\\

l

. 430 PR0CEDURE (c= tis.I Y !

-INITIAL

.4 Remove the clamps holding the segments of the thermal insulation together.

Using a stud hoist, lift each segment high enough to clear adjacent segments and transfer it to the storage rack, Remove and store the insulation until it is to i

i be,. installed.

.5 Transfer the stud tensioners and stud handling equipment to the Reactor Vessel head area.

.6 Delete.

.7 commence uncoupling all 69 control rod drive mechanisms in accordance with Ref. 2.'4.

.8 Delete.

.9 Clean the closure head area.

Remove all parts and tools from the head flange.

.10 Install the canal seal plate in accordance with Ref. 2.2.

.11 At least one set of Reactor Vessel closure 0-rings in

', ~

place on ring platform of head storage stand cleaned and prepared to install.

.12 AP.35 Tools and Equipment Control, in use.

.13 Reactor Coolant System water level drained to 4 inches + 2 below the Reactor Vessel flange, or to maintenance level if Reactor Coolant Pump Seal work is to be performed.

.2 Head Removal and Storage

.1 Detension and remove studs from the Reactor vessel head flange in accordance with Ref. 2.1.

.2 Verify all 69 control rod drive mechanisms have been uncoupled per Ref. 2.4.

.3 Prepare the head and internals handling fixture and the head lifting pendants for head removal.

See Raf. 2.3 for assembly procedure.

NOTE The Reactor Ve'ssel head lifting pendants should be numbered and matched to a particular lug on the head and a position on the head an'd internals handling fixture.

The pendant turnbuckles should be set to (continued)

M.1-3 Rev. 7 ll>

I'

~

6.0 PROCEDURE (continued)

_ INITIAL give a iciel lift of the Keactor Vessel

, head, locked in place with lock nuts, and scribed upon initial installation of the Reactor Vessel head, this will facilitate a 1cvel lift in subsequent head removal

^

and replacement operations.

If hydraset load positioners are used, the pendants will have to be alterad to accommodate the hydraset.

4' Using the Auxiliary Hoist. transfer each pendant to the head service structure.

.6 - Open the pendant access doors on the walkway at the top of the service structure. Assure that each pendant is suspended over its matching head lifting lug. Manually guide cach pendant through the walk-

~

vay access doors. Match the pendant eyes with the head lifting lugs..

~

.6' Pin each pendant to its head lifting lug and support g

the pendants upper ends.

Inspect each pendant and its fixtures to assure that all fittings are secured

" ~ ~ ~

and locked.

.5 Inspect the entire head and service structure to p

verify that all connections between the head and the building have been broken and cleared.

Assure that there are no obstructions in the required path from

~

the Reactor Vessel to the storage stand.

.8 ' Position the head and internals handling fixture over 7

the head service structure and match and pin the pendants to the handling fixtur,e turnbuckles..

.9 After all of the me'chanical preparations have been l7 checked, place at least two radiation monitors, remote or hand-held, at the canal floor on either side of the closure' head.

Contamination on the underside of the head may result in unpredictable radiation levels.

Notify all personnel in the Reactor Building that the Reactor Vessel closure head is being removed.

B

~

M.1-4 Rev. G k

6.0 FROCEDURE (continued)

_ INITIAL J

.10 Hoist the head from the Reactor Vessel in accordance with Refs. 2.10 and 2.11.

The head should be level witihin 1/8 inch as it is lif ted. The alignment studs will provide guidance.

Raise the head to clear the d

guide studs (approximately 3.5 feet).

Upon clearing the guide studs, move the head east and away from the open Reactor Vessel.

Once clear of the Reactor Vesrel tra'nsfer the head to the head storage stand.

• j

' There is one inch of diametrical clearance between the inside vertical surface of the head and the storage stand gussets and two inches.of lead-in on the gussets.

Verify visually that the head and stand are concentric then lower the head to rest on the stand.

.1%

Verify that the head is level on the stand.

Install

)

support stands to support cables.

Slack the hoist and unpin the pendants from the head and internals handling fixture.

Holst the fixture straight up away

~

from the head.

.11 Survey head and storage stand and wash down where f

necessary to remove dirt or radioactive contamination.

q Radiation levels may necessitate filling the storage

~~

f V

stand with water.

.12 Clean stud holes and install stud hole seal plugs

{

per Ref. 2.1.

.3 Head Placement i

t

'.1 Loosen 0-ring retaining clips on underside of closure head flange.

Slide clips toward center of head to i

free 0-ring.

Cut and remove both seal 0-rings.

[

Inspect scaling surface on underside of the head i*

flange.

Refs. 2.5'and 2.8 apply.

.2 Remove protective covering from replacement 0-rings and inspect 0-rings.

Lift inner 0-ring and while holding it against. the sealing surface slide clips into perforations in the 0-ring.

Tighten retaining clips.

Repeat installation for outer 0-ring.

CAUTION The head seal 0-rings must be handled with extreme care and the 0-rings and scaling surfaces thoroughly inspected prior to installation.

l H.1-5 Rev. 1 L

g,

.6.0 PROCEDURE (c ntinund)

6. C.

PEOCEIUi.1 (contittued".-

INITIAL g.,

v...

ki)

.3 Prepare and attach head and internals handling fixture

~

.50 and. head: lifting pendants: ast per. Sectiour 6.2;r steps i

4,$.3.through4.2..S...-.

ine o.toq wiou -

se a c~. s.

virh n

~.a-, :r n AF er a li:te:- 'ane ebenr*n; Stu:7

.4 Spove;-stud hole:. plugs and clean, inspect and-lubricate prud. holes. per.Ref. 2;1e_

ru.. - c LL t t.t

p. a. : m:. :.. :.= ;m. zu..:. a.

• t-

-L

~:;

.5 Assure that the-alignment studs are-installed.asn

l specified... Inspect the Reactor Vessel and closure head.o ring-sealing surfaces.. Clean and dress the r

surfaces in accordance with Ref. 2.8.

Announce that the. Reactor Ves.sel closure head is being moved and hoist the-head off:the. storage stand.

Hove the head over.the.. east.end.df the refueling canal and lower it l

to approximately 3.5 feet above the canal floor.

Move the head over the Reactor Vessel and align holes No.

. U.

15-and No.-45 with the: alignment studs.5 Inch the-1 head.-down until'.the alignment studs.penetrat,e the 8

atud; holes.in the_ closure. head. flange...

. hstdlin; fin:::.

c.: ;

nt :;.nr I nt;; - U: rC

.6 Continue lowering the closure head to within a foot i

of the Reactor Ve el flange.

Measure the closure i

. Li head 4 flange to. Reactor. Vessel flange distance at-i four or-more opposite. points - to. verify that the..

s closure-head is level with. respect to.the. Reactor Yessel. flange.within 1/8 inch.

Clean the 0-ring

-s grooves.

Inch the head down until the head lift-

.1:

ing: pendants;a.re slack---

re-h=:.

(

CAUTION

.:a:.. a:.:: : - -

Do not stop lowering or job during

.1 Leeve-.the lowering interval af ter verify-h:a:

'_.ing th'c. head level.

r :,.

. r:.

. ;; :. :a :

.7 Detach and remove the pendants and handling fixture.

~

Remove the. alignment. studs as specified in Ref. 2.1.

.8 Install and tension the studs as specified in

{

Ref. 2.1.

.4 Preparation for Operation l

.1 Reinstall the head thermal insulation (Reverse Section 6.1, Secp 6.1.5,).

t'

.2 Remov the canal seal in accordance with Ref. 2.2.

}[3) p...

M.1-6 Rev. J L

. (]

.6.C

..... *

• L'.~.1** tf e ;

14.

.a v...

6.0 PROCEDURE (continued)

INITIAL h em

t..,.

.3

..C.o..upl.e..th.e..c.o.n. trol. rod...d.ri.ves and connect electrical

. M...d.s a.n..d.c.o.ol.i.nB. Nter lines in accordance with Ref. 2.4.

Vent coutrol rod drive mechanism housings 6

.. t

. phil.e. f.illing. _the. Reactor Coo.Lant System.

See

.Jt.e.f

2. 4....,.......

..e.

r..........

w.-..............

7.0 ENCLOSURES

. >. s...

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• Rev. 6.

• H.~1-7 l

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Rev. 5 ENCLOSURE 6

.M.2 REACTOR INTERNALS REMOVAL AND REPLACEMENT 1.0 PURPOSE

. l.

To o'utline system prerequisites and mechanical procedures required for removal and replacement of the plenum assembly and the core support assembly.

.2 To describe the ascembly and preparation of the closure head and internals handling fixture.

2.0 REFERENCES

.1 Internals General Arrangement, Bechtel Dwg. No. N3.02-1-0.

.2 Plenum Assembly, Bechtel Dwg. No. N3.02-6-0.

.3 Core Support Assembly, Bechtel Dwg. No. N3.02-2-1.

.4 Head and Internals Handling Fixture Assembly, Bechtel Dwg. No.

N3.01-47-2.

.5 Internals Handling Adapter, Pendants, and Spreader Ring Arrangement, Bechtel Dwg. No. N3.03-46-0.

.6 Internals Indexing Fixture, Bechtel Dwg. No. N3,.01-71-0.

.7 Internals Storage Stand Assembly, Bechtel Dwg. No. N3.03-43-0.

.d Internals Handling Extension, Bechtel Dwg. No. N3.03-6-2.

.9 Reactor Vessel Instruction Manual, V-200.

.10 AP.35, Tools and Equipment Control.

5

.11 Radiation Control Manual and Procedure.

.12 H.26, Surveillance -and Radiation Specimen Handling.

.13 Process Standards, AP.107, " Fuel Handling Cranes."

.14 Technical Specifications, Section 3.10.

.15 FSAR, Appendix 9, Page '9A-40.

.16 USNRC Regulatory Guide i.10'4, Feb. 1976.

r M.2-1 Rev. 5 i

f, :,'

')

3. 0, LIMITATIONS / PRECAUTIONS O,

Do not exceed ten percent overload when hoisting any internals

.1 component.

.2 Do not exceed ten percent underload when lowering any internals component prior to the component seating in its proper location.

NOTE Weights of intere c.s and handling equipment are:

DRY WET Plenum Assembly......................

110,000 lb's.

96,000 lbs.

2 Core Support Assembly................

225,000 lbs.

197,000 lbs.

Head and Internals Handling F'ixture Assembly.............................

12,000 lbs.

Internals Handling Adapter, Pendants, and Spreader Ring....................

3,000 lbs.

Internals Indexing Fixture...........

12,000 lbs.

Internals Storage Stand Assembly.....

8,200 lbs.

Internals Handling Adapter (Pendant)

)

Assembly.............................

850 lbs. each Internals Indexing Fixture Penclants..

48 lbs. each

.3 Reduce lowering speed to one ft./ min. or less during final six inches of travel.

.1 Hoisting speed and bridge and trolley travel speed sh'all be limited to 5 ft./ min. hoist, 40 ft./ min. bridge, and 2

30 ft./ min. trolley while handling critical loads.

.4 Match marks are established during the test program for mating parts in the assembly of internals handling equipment.

Check,

these marks to insure proper alignment and configuration.

.5 No lift of the reactor internals assemblies shall be performed unless the lifting equipment including cranes, cables, and fittings have been inspected as specified in SP-201.05, Inspection of the Reactor Building Polar Crane and Turbine Building Gantry Crane.

l

.6 The maximum lif t of any internals assemblics must not exceed 3'6" above the reactor vessel flange, at which time horizontal movement must be made to clear the reactor vessel flange.

When the indexing 2

fixture is installed on the reactor vessel flange the maximum lift will be approximately 7,' above the react.or vessel flange.

O V

N.2-2 Rev. 2

p., :

3 4

~

4. 0 SPECIAL TOOLS. AND.. EQUIPMENT

.1 Equipment.,ig acc.or. dan.c,e. wi.th. Refs. 2.4 through 2.8.

u.

u..--..

a.. e..

.. s.........

co=::cc...

5.0 T. ESTING AND.. ACCEPTAN.CE..CR. I.TERI A....

1-.:..

ur

.s

-w.s.

. Y.....-..m.

P rfrm"hl'i'ghk'en't' ah'd cbnfiksifatioh checks in accordance with

.1' o

Ref. 2.9.

s..,..

U 6.0 PROCEDURE INITIAL

.1' NEpEraYi$i[ahd'lbspic'tibh'.bf' hahilling and indexing fixtures.

i

. CIC 0;pp* '...55L"._;...........

2 :erntar ern:: _ NOTE -

an:..

nee:

.rc

~Aram ~

-- ~ The follbking' prhparatioh and inspection In:crr. proc ~edure,:. (Section 6.1.1 through Section anc i.: 6.1.5),..must. be. carried. out. each refueling.

i ; #" _..

r......_

.1

' Head"and'Inte'rhals'handlihg' fixture, see Ref. 2.4.

.In c::.4-. I: r_;s 5 :::i -:

=.0 1.-

a,.: --- 1.. This. fixture will. be submerged in the pool

.. :p". "'--- "-Whter'and mQst be ^ thoroughly cleaned before 2

"' -. 'use'.

Cleaning complete.

O' intern:13 incex:np ?;- tr >.-e: a.c.

1

.2 Remove any rust and apply a light film of

'a.n:h.cr rl'NE0 LUBE!' to bearing holes, j

c L' L;. -....::'..

.3 Inspect for any evidence of cracking or

~.:::. y,ielding. '

e

.1.-

7-L NOTE i

.

::t : :rA: :rt The head and internals handling a:.. _- --..:. fixture and the internals handl-

- m si rt? -r C Ling adapter are used to remove 2

the plenum assembly and the core

4. - :. :u :_

rsupport-assembly.

v:.. :

.2.

The internals handling extension, See Ref. 2.8 shall

l be cleaned and inspected in accordance with Steps 6.1.1.1 through 6.1.1.3 prior to each use.

.3.-

Internals handling adapter, pendants, and spreader ring, see Ref. 2.5.

a--

f: :

.1 Clean all component parts of assembly as in

. Step 6.1.1.1.

()

, pl. 2-3 lRev. 2 r

.p,

<3 t

6.0 PROCEDURE (continued)

INITIAL

.2 Check latches for freedom of action.

.3 Verify that components are assembled in proper configuration for lifting plenum or core support 2

assembly in accordance with Ref. 2.5.

Assure that all fasteners are properly secured.

)

.4 Do not adjust or loosen turn-buckles during assembly of fixture, see Section 3.5.

.5 visually inspect for evidence of wear or damage.

.4 Internals indexing fixture, see Ref. 2.6.

.1 Check all manual latching devices for freedom

,of action.

. '2' Clean internal and external suriaces as in

~

Section 6.1.1.

.3 Check guide, keys for evidence of galling.

Stone surface lightly to restore finish if required.

Do not remove Lase metal.

O

.4 verify that guide stud 1atches are secured in the open position.

l

.5 Assure that all fasteners are properly secured.

.6 Assure that locking bars are 'in the open position.

.7 Do not adjust or 1oosen turn-buckles.

NOTE The internals indexing fixture forms an extension of the reactor vesse1 internals keys to orient the internals for removal from and insertion into the vessel.

.5 The internals storage stand, see Ref. 2.7, shall be 2

c1eaned prior to filling the canal.

.2 Initial Conditions

.1 Work Request No.

K2-4 Rev. 2

~

p.e 6.0 PROCEDURE.(conti ued)

~

INITIAL

.2 AP.35, Tools and Equipment Control, in effect, Ref.

5 2.10.

'3 Reactor Vessel closure head removed from vessel.

.4 Inspect the reactor vessel flange and clean surface if necessary.

.5 Both fuel handling bridges are parked clear of the core at the end of refueling, canal.

.6 Fuel transfer canal flooded to the level as designated by the Shift Supervisor. Only the deep end is flooded 5

if the plenum is to be removed " dry".

NOTE Internals indexing fixture may be installed and handling fixture attached to plenum assembly prior to flooding the canal unless radiation levels prohibit direct attachment of fixtures to internals. This procedure is based on remote attachment of fixtures.

(h

.7 Internals storage. stand prepared for use.

If core support assembly is to be stored on stand, spot-stand for alignment of core support assembly guide blocks into openings provided and level to.006"/FT.

5 Arrange for TV or other optical assistance for guiding the core support assembly into the stand and remove the upender necessary for use of the stand.

.8 Indexing fixture installed on Reactor Vessel flange and latched to guide studs.

The indexing fixture 5

is not required to be installed for removal of the core support assembly.

3 Removal of the Plenum Assembly

.1 Attached head and internals handling fixture to polar crane main hook using the internals handling exten,

sion, Ref. 2.8, as a connecting link.

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6.0 PROCEDURE (continued)

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INITIAL

.2 Attach internals handling adapters and pendants to the ir. board holes in pads of head and internals handling-fixture as shown on Ref. 2.4.

Latches must be closed with shims installed.

NOTE Attach the adapter and pendant handling at the west end of the wall bracket first, the middle one second, etc.

The pendants are match-marked and must be installed'on their corresponding pads of the handling fixture.

.3 Attach spreader ring assembly.

The spreader ring must be oriented in position for the plenum lifi.

NOTE The spreader ring is not required to be 5

attached if the plenum is to be lifted

" dry".

.4 Lower the internals handling adapters, pendants, and

>g spreader ring assembly (if used) into the end of the 5

~ V fuel transfer canal to within approximately seven feet of the canal floor.

See NOTE of Step _ 6.3.3, l

.5 Position the handling assembly and spreader ring (if used) over the reactor vessel with the "W" axis of handling fixture oriented with the "W" 5

axis of the indexing fixture.

See NOTE'of Step 6.3.3.

.6 Lower internals handling assembly to engage and latch on plenum assembly lifting lugs. Verify engage-5 ment.

.7 Hoist the plenum assembly clear of the reactor vessel and' indexing fixture.

Observe Limitations / Precautions of this procedure.

NOTE The maximum list required before the plenum assembly is moved laterally to the storage area is approximately 18 feet.

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M.2-6 Rev. 5

6.0, PROCEDURE (continued)

]

INITIAL

.8 Place the pleaum on the internals storage stand in the deep end of the Fuel Transfer Canal or S.E.

corner of challow end..

.9 Unlock the latch boxes and hoist'the internals handl-ing assembly to the 60' elevation storage area for 5

attachment of indexing fixture lifting pendants.

.10 Remove the indexing fixture and store on the 60' elevation.

.4 Removal of Core Support Assembly

.1 Initial Conditions

.1 Conditions the same as in Section 6.2.1 through 6.2.8.

.2 Core completely defueled.

.3 Delete.

5

.4 Plenum relocated in east end of refueling canal, b

.1 Reinstall plenum in' reactor vessel.

.2 Move fuel handling bridges to the west end of refueling canal.

.3 Remove plenum and place 'on floor of the east end of refueling canal.'

NOTE Move fuel handling bridges to east end of refueling canal with caution.

.5 Both fuel hand' ling bridges parked clear of the core and internals storage stand at the east end of the refueling canal.

.6 Clear space provided in deep end of fuel transfer canal for storage of core support assembly (180 inch min. dia,).

.7 Internals storage stand placed in deep end of canal.

M.2-7 Rev. 5

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c 6.0 PROCEDURE (continued)

INITIAL

.2 Attach head and internals handling fixture to the polar crane main hook using the internals handling extension as connecting link.

~

.3 Attach the internals handling adapter and pendants to the head and internals handling fixture.

Attach to inboard holes (5-1/2 inch dia.) on handling fixture.

See Refs. 2.4 and 2.5.

U

.4 Assemble the internals handling adapter, pendants, and spreader ring assembly in the proper configuration for core support assembly removal.

Remove the shims from the pendant and latch assemblies in accordance with Refs. 2.4 and 2.5.

.5 Attach indexing fixture lifting pendants to the out-board holes (3 inch dia.) on the head and internals 5

handling fixture if the indexing fixture ia being used.

l

.6 Open pendant locking. bars on the indexing fixture (if 5

used).

.7 Hoist and position the handling fixture over the

-s reactor vessel.

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.8 Lower the handling fixture to engage the spreader ring on the indexing fixture keys if the indexing fixture 5

is being used. The indexing fixture pendants will ride over tha lifting pendant pads while lowering,

~

.9 Lower the handling fixture until assembly comes to rest and latch on the core support lifting lugs.

.10 Hoist the core support assembly until upper flange is approximately flush with top of indexing fixture.

Stop hoist.

(This step may be omitted if the index-ing fixture is not to be used.)

NOTE Total weight of reactor internals and lifting fixtures is approximately 107 tons.

Lift required before lateral movement is approximately 32 feet.

.11 Using long-handled tool and working from the auxiliary l

fuel handling bridge, rotate guide stud latches on indexing fixture to the open position.- Close locking 5

l, bars on indexing fixture lif ting pendants.

(This-i

._ step may be'omitted if the indexing fixture is not to be used.)

H.2-8 Rev. 5

..I 6.0 PROCEDURE.(continued)

INITIAL

.12 Hoist core support assembly and indexing fixture (if 5

used) clear of reactor vessel.

CAUTION During this operation the area should be cleared of.all excess personnel. Area radiation level should be continuously monitored.

Approximately seven feet of the assembly will be exposed during transfer to the internals storage stand.

s

.13 Move the assembly into position over the internals storage stand.

Lower until core support assembly comes to rest on the stand. Use TV or other optical 5

assistance for guiding the core support assembly on to the stand.

.14 Release internals handling adapt'er latches.

.15 Using the internals handling fixture, hoist the index-ing fixture (if used) and internals handling adapter, 5

pendants, and sprecder ring to convenient stor_ age g

area,

.16 Fuel transfer canal water level may now be lowered to permit access to the reactor vessel interior. Temporary shielding may be required since draining the canal to floor level will expose about 14 feet of the core support assembly.

'.5 Replacement of Core Support Assembly

.1 Initial Conditions

~

.1 Core support assembly in place on internals storage stand.

.2 Prepare handling equipment in accordance with Section 6.1 of this procedure.

.3 All work / inspection operation on reactor vessel

.and core support assembly completed,

.4 Head and internals handling fixture and internals handling adapter and pendants assembled for lift-l ing the core support-assembly as described in l

Section 6.4, Steps 6.4.2 through 6.4.4 of this procedure.

M.2-9 Rev. 5

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6.0, PROCEDURE'(continued) 4 s

_ INITIAL

.5 Pick the indexing fixture in proper configuration I

for handling the core support assembly, i

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.6 Fuel transfer canal flooded.:o refueling level.

i

.7 Plenum and fuel handling b.tdges located in east 1

end of refueling canal.

,f

.2 Align internals handling assembly with core support assembly and lower until internals handling adapters come to rest and latch on~ lifting lugs'.

.3 Hoist assembly clear of storage stand.

Observe 5

" CAUTION" in Step 6.4.12 of this procedure..

.4 Position assembly over reactor vessel and orient with vessel axis and guide studs.

• 5 Lower assembly until core support assembly enters the f

reactor vessel.

.6 Continue lowering core. support assembly into reactor vessel until the assembly is in place.

3

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.7 Using long-handled tori disengage-lifting pendant

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1atches on internals handling pendants.

.8 Hoist lifting equipment and indexing fixture clear of the reactor vessel.

' NOTE Indexing fixture lif ting pendants must be guided into their sockets using long-handled tool.

.9 Replace the upender removed in Step 6.2.7.

5

~

.6 Replacement of Plenum Assembly

.1 Initial Conditions

.1 Core support assembly in place in reactor vessel.

.2 Fuel handling operations completed.

.2 Attach head and internals handling fixture to the polar crane and pick and install the indexing fixture on the g

reactor vessel.

W H.2-10, Rev. 5 L.

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6.0 PROCEDURE (continued)

INITIAL

.3 Holst the internals handling assembly clear of the indexing fixture.

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NOTE Indexing fixture lifting pendants must be guided clear of lifting pads.

.4 Position the internals handling fixture assembly over the plenum with the "W" axes aligned, 9

.5 Lower the internals handling assembly to engage and latch on the plenum lifting lugs.

.6 Hoist the plenum and position the plenum over the indexing fixture and vessel with the "W" axes and keyways aligned.

.7 Lower the plenum while guiding the indexing fixture lifting pendants out and away from their mating Sockets.

.8 Lower the plenum to rest and release the latch boxes,

.9 Rotate the guide stud latches on the.*dexing fixture and secure them in the open position.

.10 Boist the internals handling assembly while guiding the indexing fixture lifting pendants back into their mating sockets.

.11 Move the pendant locking bars to the closed position.

.12 Remove the indexing fixture and transfer it to the 60' elevation storag.e area.

.7 Delete.

5 7.0 ENCLOSURES e

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RWC:cci 4-21-76 ENCLOSURE 7 M.31 OPERATION OF THE REACTOR BUILDING POLAR CRANE AND THE FUEL TRANSFER CANAL AUXILIARY HOIST 1.0 PURPOSE To identify and outline Polar Crane and Auxiliary Hoist movement over and into the Fuel Transfer Canal to perform and assist maintenance functions requiring movement of material and equip-ment over, into and out of the Fuel Transfer Canal.

2.0 REFERENCES

.1 Rancho Seco Unit 1 Technical Specifications, Section 3.11, Reactor Building Polar Crane and Auxiliary Hoist.

.2 Maintenance Procedures M.1, M.2, M.3, M.7, M.8, M.10, M.12 and M.26.

l

.3 USNRC Regulatory Guide,l.104, February 1976.

3.0 LIMITATIONS AND PRECAUTIONS lh

.1 ' The Fuel Transfer Canal will be delineated by readily visible yellow and black striped markers. The Reactor Vessel will be delineated by readily visible red markers.

(See Enclosure 7.1)

Hoisting speed and brid e and trolley travel speed shall be F

.2 limited to 5 ft./ min. hoist, 40 ft./ min. bridge, and 30 ft./ min.

trolley while handling Reactor Vessel components.

~

The Polar Crane hooks or FTC Auxiliary Hoist shall not be

.3 operated over the Fuel Transfer Canal when any fuel assembly is being moved IAW Ref,. 2.1.

into or out of the

.4 This procedure does not pertain to movement Such Reactor Vessel area as delineated by the red markers.

equipment movements are contained in separate procedures.

~

All Crane Operators and ground signal men shall be aware of the

.5 l

restricted areas and their significance.

l All rigging and handling fixtures shall be visually inspected

.6 and approved for use by the Foreman in charge of the maintenance function prior to any movement over or into the Fuel Transfer Canal.

i

c 4.0 SPECIAL TOOLS AND EQUIPMENT lI

.1 All slings, shackles, fixtures, etc. shall be stainless steel i

or painted and cleaned before and after use under water in the FTC.

.2 All shackle pins must be equipped with a retaining lanyard.

5.0 ACCEPTANCE CRITERIA

.1 Any tooling, equipment,. shielding, support fixture, etc. deemed necessary and approved by the Foreman in charge of the maintenance function'to support, prepare,_or perform the maintenance function, may be transported into the FTC only in accordance with this procedure.

.2 The " red" restricted zone shall be adhered to at all times after the removal of the Reactor Vessel missile shields.

No movements will be allowed over the red zone within the scope of this proce-dure.

(See Enclosure 7.1) 6.0 PROCEDURE

.1 All involved Foremen, Crane Operators and ground men will be knowledgeable of this procedure.

k

.2 All tooling or equipment sha'll be transported to the FTC and lowered to the height to clear any obstructions already placed in the FTC and then moved laterally to the location of use.

.3, When using the Polar Crane Auxiliary Hook, the bridge must be rotated to keep the Main Hook away from the center of the Reactor Vessel core.

7.0 ENCLOSURES

.1 Diagram of Fuel Transfer Canal Zone Markings.

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MOVEMENTS IN Ti!IS AREA ARE

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DDW: jim 8-18-77 ENCLOSURE 8 STP-211 REFUCLINC RANCHO SECO FOR CYCLE 2, 1.0 PURPOSE

.1 To provide the procedure for refueling the Rancho Seco Unit 1 Reactor.

2.0 REFERENCES

.1 OPOP B.8, Refueling.

.2 Rancho Seco Unit 1 Technical Specification 6.8.1.b.

.3 Maintenance Cleanliness. Control, M-114.

.4 Tools and Equipment Control, AP-35.

• .5

,' AP.16, Control and Accountability of Special Nuclear Materials.

.6 B&W Operating Specification OS 1502-02, Refueling Shuffle Sequence for Rancho Seco Cycle 2.

3.0 PREREQUISITES, NOTE:

Estimated Time Required:

10 days, each with two 10-hour shifts and assuming all equipment operable.

~

l

.1 Spent fuel pool is filled to, refueling level, %38 ft., and that its Boron concentration is >1800 ppmB.

)

.2 Incore SPND assemblies withdrawn to refueling position prior to movement of corresponding' fuel assembly.

NOTE:

-.12 identifies three Incore Thermocouples to be left in service to accommodate modification of the Decay Heat System.

Prior to removing those identified fuel assemblics, verify that their SPND's have been removed.

An STP Log entry is l

sufficient to recotd compliance.

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STP-211-1

.\\

q 3.0, PREREQUISITES (Continued)

.3 "Special attention has been given.to Out-Of-Core / Fuel Transfer Canal seal pintos to insure they are leaktight when the canal is flooded.

.4 Both Fuci Transfer Tube bolted flanges have been removed.

.5 The fuel transfer canal deep end drain flanges are in place and tight.

.6 Verify that the Fuel Transfer Canal drain " flapper" (under grating in SW corner) is securely connected to its lifting cable.

.7 The Fuel Transfer Canal is ficoded to refueling level and >1800 ppmB.

.8 The RV plenum assembly has been removed and is parked at the west end of FTC.

.9 Decay Heat Removal System in opera, tion per SOP A.8, Section 4.8.

.10 Verify that a current I-109 check of the RPS Channels NI-1 and

'NI-2 has been done and that the source range nuclear instruments are in cervice.

.11 I-606, Reactor Building Purge / Radiation Monitoring System Intef-lock Test has been completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of beginning fuel movement.

.12 The reactor has been suberitical fo'r at east 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

.13 Orifice rod assemblics identified in Enclosure 8.7 as those to

, be loaded into rod handling containers for transfer to the core during refueling are in place in the inspection area of the SF Building.

.14 New fuel locations in SF Pool have'been verified per Enclosure 8.13A/B by two separate individuals.

4.0 TEST AND SPECIAL EQUIPMENT

.1 Plant source range nuclear instrumentation with Scager-Timers attached to at least one channel, two desired for X test.

.2 Two channels of computer trend recorder, trending NI-1 and NI-2,

-Log cps.

If not available, use Scaler-Timers.

.3 Binoculars, float'abic.

STP-211-2 D

q:

q 4.0 TEST AND SPECIAL EQUIPMENT (Continued)

.4 View box, desirable.

.5 Fuel Accountability boards are to be in-place in the Reactor Building, Spent Fucl Building, and Control Room.

.6 A manual CRA handling tool for irradiated assemblies is desirable in the Fuel Transfer Canal. Sec~ Enclosure 8.14 for its operation.

.7 A. programmable eniculator for X2 testing is desirable.

5.0 LIMITS AND PRECAUTIONS NOTE:

The Limits and Precautions presented in this STP are those directly applicable to the refueling of the reactor.

Limits and Precautions listed.in other procedures, particularly A.13 and B.8, are to be used only to the extent that they. affect use of governed equipment.

This STP supercedes all other procedures relative to refueling,

.1 Observe 'all reasonable precautions to prevent the unnecessary.

contamination of equipment or radiation exposure to personnel.

.2 The water in,the Reactor Coolant System and Decay Heat Removal System shall be borated to a minimum uniform concentration of 1800 ppmB.

.3 Core suberitien1 neutron flux shall be continuously monitored by at least two neutron flux monitors, each with continuous indication available, whenever core geometry is being changed.

When core. geometry is not being changed, at least one neutron flux monitor shall be in service.

The two chanacic shall indicate at least two (2) counts per second attributable to neutrons.

.5 If at any point in fuel handling, an unexpected increase in count rate occurs, the operation will be suspended pending

.5 evaluation by the responsible Rancho Seco Sanior Licensed Operator and by assigned Shift Nuclear Engineer.

Operations will not be resumed without' specific authorization by the responsible Senio,r Licensed Operator.

STP-211-3 f.

~

5.0 i. LIMITS AND PRECAUTIONS (Continued)

.5a containment evacuation will be performed if'either of the source.

range detectors show an increase by a fai: tor of. ten or more due to's single reactivity change..

.5b Boron injection will be initiated if the count rate on either of the two responding channels increases by a factor >5 due_to reactivity change or if the boron concentration decreases below 1800 ppmB.

l NOTE:

This procedure removes, replaces, and/or shuffles all but one fuel assembly and control rod.

At most, two fuel assem-blies are required to be out of the core at a time, thus the effect on oirerall core reactivity and suberitical multi-I plication will noti be apparent to the l

out-of-core neutron detectors'. Therefore l

1/M_ plots are not meaningful', and are not required.

2 l

i x tests are donc daily only to show statistically that the nuclear instru-

~

mentation is seeing random neutrons, not other systematic noise.

=-

.6 In the event of an interruption in ' fuel handling, countrate monitoring shall be continuous until the Shift Nuclear Engineer and Senior l Licensed Operator on duty agree it is no longer necessary.

4

.7 Once each day whe'n fuel handling is in progress, the FTC/RCS Boron Concentration shall be determined.

Minimum acceptable concentra. tion is 1800 ppmB.

.8 If doing-1/M plots, a new baseline will be established for inverse count rate any time a detector or neutron source is repositioned.

.9 Isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be in a safety features position.

.10 Radiation levcis in the Reactor Building refueling arcas are monitored by R15026 and R15027.

Radiation' levels in the spent fuel storage area are monitored by R15028.

If'any of these instruments become inoperable, portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect I

l individuals ' involved i'n fueling operation, shall be used until l

the installed instrumentation is returned to service.

j.

j; STP-211-4 l

l

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5.0 LIMITS AND PRECAUTIONS (Continued)

.11 Any foreign object that could be dropped into the Reactor Vessel, Fuel Transfer Canal, or Spent Fuel Poo,1 must be secured to a safety line.

.12 All TLD badges, pocket dosimeters, etc., shall be taped securely to prevent falling from pockets per M.3.

.13 Use the methods of AP.16 to insure the accountability of all fuel assemblics.

Change-in core location assignments require prior approval of the PRC and Plant Superintendent.

.14 Maintain voice combunications between the Control Room and the upender stations in the Spent Fuel Building and the Reactor Building while fuel is being moved between buildings or in the FTC.

Fuel activities only in the SFB'do not require continuous voice communications.

.15 During the handling of irradiated fuel in the Reactor B' ilding u

at least one door on the personnel and emergency hatches shall be closed.

The equipment hatch cover shall* be 'in place with a minimum of four bolts securing the cover to the sealing surfaces.

.16 At least one path for Concentrated Boric Acid addition to the Primary System must be operable.

.17 At any time if the Responsible Senior Licensed Operator feels that continu.ed operation will involve undue risk to personnel, or equip-ment, or will compromise the Technical Specifications and/or Licence Provisions, operations will be stopped.

.18 All fuel assemblies will be orientated in the reactor grid with the identification plate in the East direction, W-axis, since the Z-axis is North. See Enclosure 8.5.

.19 A Nuclear Engincor will evaluate the shutdown margin at the end of each work day and at the end of core loading.

This shall be recorded in the STP Procedure Log..

.20 If a fuel assembly is dropped in either the Reactor or Spent ' Fuel Building:

.1 Personnel evacuate to the Auxiliary Building change room.

.2 Inform the Control Room of the situation.

.3 A radiation control team is to survey the area, take air and gaseous activity samples.

.4 Re-entry into the affected area shall not be allowed until a full evaluation has been made and approval by the Plant' Superintendent has been, granted.

S 7-211-5 s

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v 5.0'

• LIMITS AND PRECAUTIONS (Continued)

.5 When the area is cleared by Heal,th, Physics personnel, inspect the fuel assembly and determine its disposition, i.e.

continued use, repair, or storage.

If necessary, place into a failed fuel container to limit the spread of contam-ination.

.21 If a fuel ele, ment or core component is damaged, or suspected of damage, it shall be inspected by the plant nuclear engineer to determine suitability for use.

.22 Do not operate fuel handling equipment with any interlock bypassed or inoperative without approval by the Shift Supervisor.

Whenever possible, the manual override capability should be used instead of motors for operation with bypasses enabled..

.23 Maintain a minimum of 9. feet of water over the ' top of active fuel region in a fuel assembly.

.24 A minimum of :10 positions shall be filled on each crew accomplishing

~this procedure.

See Enclosure 8.1.

.25 Maximum duty hours for any individual is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in a 24-hour

~

period.,

.T6 Personnel access in the Reactor Building.shall be as shown on Enclosure'8.2.

.27 If fuel grapple down light is ON and Z-Z tape does not indicate withiin 5 inches of grapple tube down in core position, immediately suspend insertion or removal of fuel assembly and evaluate.

.28 Visually verify that the fuel handling mast,by Z-Z tape position, is in the full up position prior to moving bridge or trolley (main, auxiliary.and SF).

NOTE:

Fuel assemblies have been damaged at some nuclear plants by failure to adhere to this precaution.

.29 The Reactor Building polar crane hoists shall not be operated over the fuel transfer canal when any fuel assembif is being moved.

.30 The auxiliary hoist shall not be operated over the fuel transfer canal when any fuel assembly is being moved.

.31 All operations in the fuel handling areas shall be in accordance with Reference 2.3 with regard to maintaining cleanliness.

.32 All operations in the fuel handling areas shall be in accordance with Reference 2.4 with regard to inspection and control of tools and equipnent.

~

STP'211-6 O

~

PRECAUTIONS (Continued) aen two irradiated fuel assemblics are being handled simultaneously within the fuel transfer canni, a minimum of 10 feet siparation shall be maintained between the assemblies at all times.

.33a Irradiated fuel assemblies may be handled with t'he auxiliary bridge crane provided no other irradiated fuel assembly is being handled in the fuel transfer canal.

.34 If any of 'the specified limiting conditions for fuel handling are not met, movement of fuel in the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.

.35 Do not handle irradiated rod assemblics in any manner that could reduce the water shielding depth below the minimum of 9 feet.

.36 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

.37 The refueling canal shall be maintained below 140*F' when fuel handling operations are being conducted.

.38 No fuel, control rod, or other core assembly shall be handled with other than specified tools.

19 Do not place any fuel assembly, control or internals component, or other such item, in any location not specifically designed to receive that assembly.

.40 The following limits apply when manually handling short rod (ORA) assembly:

.1 No loads ar6 imposed on the pins in other than an axial direction.

.2 No load in the axial direction shall be allowed other than the weight of the anacmbly itself plus the weight of the rod assembly handling tool with the shor.t actuating handle.

.41 Refueling operations shdll not he conducted unless the minimum personnel requirements are mot in accordance with Enclosure 8.1.

.42 Stop log in Spent Fuel Pool between upenders and Spent Fuel Pool must be in place before draining or filling the Fuel Transfer Canal, i.e., while the RB Transfer Tube blank flanges are off and the FTC is not filled.

.43 Shif t supervisor permission nust be obtained prior to raising the new fuel cicvator.

.44 Uhen placing an orifice rod in the control rod handling container by hand,llealth Physics should monitor the container because it may be highly contaminated after handling exposed BPR's.

STP-231-7

_