IR 05000335/1994009
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taptember 19. 1994
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MEMORANmlM 10:
Gus C. L41nas, Assistant Director n
for Region !! Reactors j
Division of Reactor Projects I/II, NRR
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Bruce A. Boger, Acting Director
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Division of Reactor Projects, RII
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REQUEST FOR AS31 STANCE IN ADDRESSING ISSUES REGAR J
SUBJECT:
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ST LUCIE UNils 1 AND 2 REFUELING PROCEDURES (T!A 94-023)
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St. Lucie Inspection Report 94-09 contains two items which are unresolved The (Attachment 1) pending Technical Specification (TS) interpretations.
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liransee had dissenting cossnents on these issues, as noted in the inspection report Exit Interview paragraph. The two items are:
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URI 389/94-09 02 Adequacy of a single operator on the refueling bridge
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during core alterations - paragraph 4.a r
This llRT involves interpretation of Unit 2 TS 6.2.2.d which states:
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"All CORE ALTERATIONS shall be observed by a licensed operator and supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limitsd to Fuel Handling who has no other concurrent responsibilities during this operation. The SR0 in charge of fuel handling nomally supervises from the control room and has the flexibility to directly
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fuel pool."
During the St. Lucie Unit ? fuel shuffle. on March I,1994, the licensee had stationed one [ licensed) operator on the refueling bridge to perfons
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refueling operations. This single licensed person. who was in constant
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connunication with the refueling control desk in a control room anner.
was performing actual refueling operations, which included operating the The SR0 in charge of the evolution was located remote bridge and crane.
from the refueling bridge, as is allowed by the TS and discussed in FPL and NRC correspondence ; Attachments 2 and 3).
The inspector questioned staffing adequacy because the operator had
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earlier attempted to grapple a fuel bundle with the crane et incorrect
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coordinates due to a move list error. The single operator had not detected the error by cross check between analog and digital positioning systems. Theinspectorquestionedwhetherthisone(thoughlicensed]
person using the bridge and crane to perform core alterattans est the TS requirement and the NRC's intent regarding a licensed operator observing
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'E G 99-21-1994 06:19Ari FRON u9fM R!! Is TO eUS15042162 P.62
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The licensee's position was that ' observed by a licensed operator *
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refers to the historical practice when nonlicensed persons, perhaps fros
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4 contract service company, actually perfomed the core alterations.
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The licensee believes that ' performing' includes ' observing' when a
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The licenses stated that
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licensed operator perfoms core alterations.
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licenseeandNRCcorrespondence(Attachments 2and3),generatedduring
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the original Unit 2 licensing process, supports their interpretation
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that a licensed operator puforming core alterations constitutes the TS-
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The inspectors reviewed Attachments 2 and 3. and required observer.
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found that they appear to address the location of the SR0 rather than
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the " observing - performing' question.
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in addition to compliance with the TS, the inspectors had the following
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concerns with having only one person on the refueling bridge:
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There was no real-time independent vertftcation of core c
alterattens as they were performed. However, the core load was
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. verified in detail by serial number, orientation, etc. when the
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core shuffle was congleLv.
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From the crane operating station un the bridge, the operator did
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not watch activity in the refueling canal. The operator could
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look down through plexiglass or move a few feet and look over the
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edge of the crane bridge with binoculars, but did not regularly do
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so. Also, there was a IV camera mounted near the bottom of the
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refueling mast, but it was not working. Thus the operator was, in
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a sense, driving 'on instrumente only.'
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Please provide an interpretation (with supporting considerations) of TS i';
6.2.2.d:
Does " core alterations shall be observed by a licensed operator *
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e refer to 11terally directly observing fuel move or does the phrase
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refer more to the process activities and supervision involved?
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Is the TS requirement based upon the assumption that contract or
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maintenance department personnel, requiring licecsed operator 4 >
oversight. perform fuel movement?
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is the TS reautrement based upon the need for real-time
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independent verification of core alterations or fuel movement?
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Does the TS require a second licensed operator, in addition to the
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[ licensed] refueling mar. hine operator. to observe feel movement or
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other core alterations?
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if so, then does the TS require that supervision of core
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o alterations ha performed by an SRO who is separate from the
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observer (i.e., a third person)?
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Adequacy of review and approval of refueling core URI 389/94 09 03,
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alterations (licensee's Tsecomended Move List) - paragraph 4.a 2.
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.This URI invelves interpretation of Unit 2 TS 6.8.1, 6.8.2, and 6.8.3
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TS 6.8.1.a requires procedures reconsnanded by Regulatory Guide
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RG 1.33 recomends precedures for j
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" Preparation for Refueling and Refueling Equipment Operation" and 7j,
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for " Refueling and Core Alterations."
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TS 6.5.1.b requires procedures for " Refueling Operations."
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TS 6.8.2 requires that each of those procedures, and changes
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J thereto, shall be reviewed by the FRG and approved by the Plant
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General Manager prior to implementation.
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TS 6.8.3 allows temporary changes to those procedures provided:
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The intent of the procedure is not altered.
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The change is approved by two members of the plant
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J management staff, at least une of whom holds a Senfer
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Reactor Operator's license on the unit affected.
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j The change is documented, reviewed by the FRG, an. approved
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by the plant General Manager within 14 days of
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implementation.
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Thelicensee'sReconeendedMoveList(Attachment 4)wasthedocument
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It was developed
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that detailed the fuel assembly and CEA move sequence.
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.during the core load development process and it identified, in order,
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each fuel assembly and CEA to be moved, the location from which it was
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to be moved, and the location to which it was to be moved. It not only
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addressed moves within the reactor vessel, but also moves between the fuel pool and reactor vessel, and moves within the fuel pool. It was
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3200090, Refueling Operations, watch also
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. invoked by Test Procedure described steps necessary to deviate from (change] the list (see
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However, the Recommended Move List itself was not part
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of the test procedure and was not reviewed by the FRG or approved by the
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G Plant General Manager. Instead, it was approved by the Reactor J?
Engineering Supervisor. Deviations from the Recommended Move List were
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. approved by the reactor engineer on shift and the refueling coordinator
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During past refueling outages, many fuel or CEA movement sequence
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changes [as many as.90] have occurred due to equipment problems.
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Mistorically, the escasmanded Move List had been cart of a procedure but
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The licensee de-
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tired operatnrs, and wasted radiation exposure.
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proceduralized it to cope with these problems.
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f-99-21-1994 06120R1 FROM USt#C G11 DRP TO 83015642182 P.04
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The licensee now considers the Recommended Move List to be a non-
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procedure and therefore not subject to the TS 6.8.2 requirements for
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. ' review and approval of procedures and also not subject to the TS 6.8.2
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The and TS 6.8.3 requirements for processing changes to procedures.
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Itcensee stated that, since the Recomended Hove List's preparation,
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use, and modification were directed by a FRG-reviewed procedure, a FRG
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i review should not be required for the list itself. Subsequently, the
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. licenses stated that a telephone review with other Combustion J
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Engineering plants found that the licensee's position was comon in the
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industry.
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The inspectors had the following concerns with the licensee's practice
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of handling the Recomended Hove List as a non-procedure:
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The Recommended Move List was an important document. It was used
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by reactor engineers and operators for performing safety-related
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activities. Errors in it could potentially lead to unsafe
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conditions of fuel arrangement. However, the licensee was
requiring less review and approval for the Reconsnended Move List
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than for a safety-related procedure.
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The retention of a record of the Recomended Move List could be of
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significant value in determining the cause of an accident or
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45.2.9 - 1979 Section 2.2.1.
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malfunction, as described in ANSI
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However, the licensee often issued a new Recocnended Move List and
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discarded the old one with no formal review and no record
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retention.
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Please determine if the Recomended Move List is considered to be a
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l 6.8.1. 6.8.2, and 6.8.3.
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procedure, subject to the requirements of TS
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in a refueling outage on October 31, 1994.
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/SE. Lucie Unit 1 is scheduled to b e able to respond to this request by that f
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Plea'sa let me know if you will not
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If you have any questions concerning this request, please contact time.
K. Landis (404/331-5509) orR.Schin(404/331-5561).
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Docket No. 335 DPR-57
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Attachments:
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Applicable portions of
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IR50-335,389/94-09
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Ltr. from FPL to NRC
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dtd. Sept. 22, 1981,
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regarding SRO Refueling
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Supervisor
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Attachmentscont'd:
(Seepage 5)
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Attachments cont'd:
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Ltr. from NRC to FPL
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dtd. Sept. 30, 1981,
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regarding Refueling SRO
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Reconnended Move List
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5.. Appitcable portions of
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Test Procedure 3200090,
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Refueling Operations
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j J. Norris, NRR
' T. Johnson, Turkey Point SRI i
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Si Elrod, St. Lucie SRI
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K. Lindis, RII
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l R Cooper, RII j
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E Greenman, RIII
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_8. Beach, RIV
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K. Perkins. WCF0
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5. Ytas, TSS, RII
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- For Previous Concurrence See Attached
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..'lencts cont'd:
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'.dtd. sept. 30, 1981, e..
.rega ing Refueling SR0 P
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4. ' Rec ided Move List
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5. /Applica e portions of
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Test Proc re 3200090,
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REGION II==
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MTN:'. Drs R. E. Uhrig, Vice 3.1
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' President, Acyanced Systems
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Thank you for your letter of September 22. 1981 which confities your d't
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. conversation with Mr. H. C. Dance of our staff.
We concur with your intent
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to require' the "Refuelihg SA0" to supervise from the control room with the r.'
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freedom to move quickly to all refueling areas.
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We approef ate your cooperation with us.
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Division of Resident and-
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Reactor Project Inspection
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cc:. C. M. Wethy. Plant 4anager
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Nat Weems. QA Const Tction Manager
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ST. LUCIE PLANT
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PREOPEpuLTIONAL TEST PROCEDURE NO. 3200080. F'LEYl3 ION 5
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BEFUELING OPERATION i
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APPENDDCE
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RECOMMENDED MOVE UST
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i EXAMPLE DATA 8HEET
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j 99-21-1994 es conn rnors ustsec Ril DRP TO B3015e42182 P.20
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ST. LUCIE Pl. ANT
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. PREOPERATIONAL TEST PROCEDURE NO. 3200090. REVISION 6
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REFUEUNG OPERAT10N j
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)hTAfLED PROCEDURE _:
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.12.1 The Operations Supervisor has reviewed the status of at CORE TJ -
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ALTERATIONS, related systems as well as the overall plant status, and
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l authertzes the commencement of fuel movement.
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Verined by Date
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Operanone Supervisor
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' 12.2 All required personnet are on stadon.
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l Vertfled by Date
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12.3 AR fuel and insert moves will be directed fmm the Refueling Control Center in
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the following manner.
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The Recommended Move Ust will be used as a move sequencing guide, f
to refueling.
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Deviations in the Recommended Move Ust sequence are permoed and
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aternate locations may be utihsd as temporary locanons provided the
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fosowing are cheerved:
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l A. Sources, or fuel assemb5es meeting the minimum humup
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requiremente of 9.8.1 RX-A10, RX-Y10 (PSL 1) or RX410, RX.Y12
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(PSL 2) If required, wit be located in before any other fuel moves
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are permkeest
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i-B. Movement of an assembly is in accordance with the Fuel Assembly i
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j Storage Table (F.A.S.T.).
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C. Vertfy that the mast orientation is correct to support the new move.
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D. Verify that as a result of sets.tii an assemtdy, no other assemb5es
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l E. Vertty that inserting an aseemtdy into a new location in the core and
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usy..w"ng it would not cause k to be a free standing essembly.
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i n-F. Vertfy that moving an assembly into a spent fuel Rack does not
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violate spent fuel pool region requirements or funnel requiremente.
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t Attachment 5
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W2M Wd2 60' G-9W j;
h..,,w,g;;r,Get U1
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,et-21-1994 esistiart snori ustsc RIt cap to e3etse4 ate 2 p.21
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Page .0 of $2
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St. LUCIE PLANT
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PREOPERATIONAL TEST PROCEDURE NO. 3200090. REVISION 6
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REFUELING OPERATION i
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12.0 DETAILED PROCEDURE: (continued)
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i 12.3 (continued)
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(continued)
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l G. Any deviadon is approved by the Reactor Engineer on shift and the
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Refueang Coordinator (8RO).
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H. If the deviation does affect the FRG approved Pinal Core Loading
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Pattom, reactivity conservatism shall be ensured and FRG
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re approval obtained prior to core vertfication.
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3.
The Refueling Control Center wiR Inform the station conduceng the move i
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is to be moved and changes in Refueling Machine mast orientation if
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rup&ud.
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The station perbeming the move wfR acknowledge the directions issued
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by the Refue8ng Control Center prior to any mogwnent. For the a-
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operator's convenience a Fuel Movement Log simlar to that provided in.,;
this procedure will be provided for recording the Instructions transmitted
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by the Refuehog Control Center.
. 12.4 Refueling Control Centar-Operating Personnel hosponabRitles
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Coordinate the movement of at fuel and core components. Refer to
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Appendices C and D for Insert and CEA transfer guidance.
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2.
Receive notification of core component movement and acknowledge
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such notl6 cation by core scprient serial number (s), offginadng
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location present location, core coordinates, and orientation of the
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Refueling Machine mast.
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3.
Vertfy Bridge and Trotoy coordinates (hoist position upon (noortion of a
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fuel sseembly) stated by Refueung Machine Operator are vand for the
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core coordinates in the refueGng sequence for the amvfees step,
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record on the Fuel Movement Log.
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Track completion of each transfer by filDng out the Fuel Movement Log.
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The Fuel Movement Log will then be used by Reactor Engineering to
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complete Appendix B, the final fuel transfer. sequence at the conciunion
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of the fuel move, then update the Fuel Status Magnet Board.
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