IR 05000275/1986025

Insp Rept 50-275/86-25 on 860825-29.No Violations Noted. Major Areas Inspected:Preparation for Refueling Activities

ML20206T943
Person / Time
Site:	Diablo Canyon
Issue date:	09/17/1986
From:	Mendonca M, Pereira D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20206T940	List: IR 05000275/1986025 ML20206T935
References
50-275-86-25, NUDOCS 8610070246
Download: ML20206T943 (5)

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U. S. NUCLEAR REGULATORY COMMISSION

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-Report No.. 50-275/86-25'- *

Docket.No. 50-275~

License No. DPR-80 Licensee: Pa'cific Gas.and Electric Company 77 Beale Street ,

Room 1451 San Francisco, California 94106 Facility Name: Diablo Canyon Unit 1 Inspection at: Diablo Canyon Site, San Luis Obispo County, California Inspection Con uct d: A ust -29, 1986 Inspector: sv ~ &gd4 / / d

. B. Per ira, roject Inspector Date Signed Approved by: L 424// tytts / [

?!. M. Mendonca, Chief Date Signed Reactor Projects Section 1 Summary:

Inspection from August 25 through August 29, 1986 (Report No. 50-275/86-25)

Areas Inspected: Routine inspection of preparation for refueling activities of Unit The inspection module used as guidance was " Preparation for Refueling" (60705).

8610070246 860917 PDR ADOCK 05000275 G PDR

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L DETAILS'

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'l . ' Persons Cont acted-

• R. C. Thornberry, Plant Manager'

• P. G. Sarafian, Reactor Engineer

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• J.~ M. Gisclon, Assistant Plant Manager, Technical-Services

• J.'Hubble, Supervisor of Security

- *J. DeMartini,' Senior Personnel Representative

• D. S. Taggart, Director, Quality Support,. Quality Assurance C. L. Eldridge, Quality Control Manager

• R. L.' Ewing,. Shift Foreman, Operation D.' B.LMiklush Maintenance Manager

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R..Johnston, Nuclear Regulatory Compliance Plant Representative

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• W. G. Crockett, Instrumentation and Control Maintenance Manager

- *D. Vosburg, Engineering Manager

• K. Doss, Onsite Review Group

• K. A. Levitt, Material Services Manager

• J. Molden,' Operations Training Supervisor

• L.' F. Womack, Operations Manager

• J. Townsend, Assistant Plant Manager

• T. L. Grebel, Regulatory Compliance Supervisor

-*M. J. Angus, Work Planning Manager The inspector interviewed several other licensee employees including shift supervisors, reactor and auxiliary operator * Denotes those attending the exit interview . Preparation for. Refueling This inspection.was to determine the acceptability of the selected portions of licensee procedures for the conduct'of refueling operations;

,the a'dministrative requirements for . control- of refueling operations and pl, ant conditions during refueling, and the implementation of controls for

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the above.two items., - '

The inspector reviewed licensee approved-procedures for the following

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three areas: Receipt, inspection, and storage of new fue Fuel handling, transfer, and core verification.

' Inspection of fuel to be reused.

Procedure No. OP-B-8A, Revision 4,' dated 5/14/86, " Handling-and Storage

, of New Fuel' Assemblies," provides methods for removal of new fuel l . assemblies from shipping containers, handling and inspection of shipping i containers, and movement of fuel assemblies from the shipping containers to new fuel storage locations. Operating Procedure (0P) No. B-8C,

Revision 2, dated 6/14/85, " Inspection of New Fuel," provided for fuel ( inspection in conjunction with fuel receipt. The procedure directed that L new fuel assemblies will be moved directly from the new fuel shipping

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containers in the receiving areas to the new fuel. inspection' area. At

.this area, the fuel-assemblies are to be visually-inspected for shipping

~ damage and fabrication defects. In addition, the fuel is drag tested in a new . fuel storage vault with the drag test jib crane hoist centered directly above. The fuel-inspections check for cleanliness, brazings, clad defects, rod misalignment, stains of any kind, and weld discolorations. Procedure No. - 0P-B-8C provides prerequisites, precautions and guidelines for drag load limits, fuel inspection, and fuel storage are The procedures for fuel handling, transfer, and-core verification had not been approved at the date of this inspection. Procedure No. OP-B-8D S-1,

" Core Unloading Sequence", had been rewritten for fuel assembly removal from the cores of Units 1 and 2. Each fuel assembly or insert move was identified by step number and the location from which and to which it is moved. The applicable precautions to prevent accidental criticality,

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fuel damage, and to assure fuel accountability were addresse Procedure No. OP B-8D S-2, " Core Loading Sequence," had be'en rewritten for fuel assembly and incore detector loading for.the cores of Units 1 and The procedure provided prerequisites, precautions and limitations to be addressed during core loadin Procedure No. OP B-8D S-3, " Insert Shuffle Sequence (Spent Fuel Pool),"

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provided guidelines and_ sequence steps for five specific sections of insert shuffle. Precautions to prevent fuel damage and to insure fuel

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,, accountability were provide Procedure No. OP B-8F, entitled " Fuel Bundle Visual Examinations in the

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Spent Fuel Pool" provides the instructions and guidelines for performing .

visual inspections of fuel bundles in the spent fuel pool. This _

procedure performs visual inspections on fuel bundles which are brought

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to the designated fuel rack inspection station in Region 1 of the spent-t* fuel pool. The fuel bundles are lowered, raised, and/or rotated'and

<t visually inspected pe.r the direction of the Test Directo '

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. Training personnel were using the latest procedure revisions, approved or

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unapproved, for training plans and lessons, and so training would not be impacte .

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The inspector reviewed the licensee's administrative requirements for control of refueling operations. Procedure No. OP B-8D, Revision 8,-

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dated 6/6/86, entitled " Refueling Prerequisites" ensures the following activities:

[ ~ Readiness of equipment and associated systems to ensure a safe and expeditious refueling operatio . Verification of equipment status and plant conditions prior to and during refueling to ensure planned conditions are being maintaine . Verification of valve lineup to ensure that the boron concentration and volume in the RCS is maintained during refuelin : m 7u7q ui a- 4- 'c, c. - v,, pg

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Identify those' activities which must be ~ current prior to andcduring'-

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core-alteration % -

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[ .This procedure provides' core unloading, core loadingIprerequisites, a'nd-f ,' . (the refueling' valve checklists. Periodic verification of items req'uired ;m

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for refueling is accomplished:using' Surveillance Test Procedure'(STP)

I-1A, B, C and D procedures.. These procedures provide'the' check on

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verification'that.the refueling technical specifications are met and continually checke The licensee appears to have established the following procedural-items: Definition of lines of supervision, Shift manning requirement The requirements for training and qualification of key personne Communication and QA/QC requirement Radiation monitoring and radiological control requirement Requirements for equipment checkout, dry runs of critical

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operations, and-fuel handlin Casualty procedure Requirements for work stoppage, delays, and hold The inspector reviewed several issued administrative, and operating procedures which verified the'above listed procedural item The inspector _ reviewed the administrative controls for establishing and monitoring control of plant conditions during refuelin The requirements for shutdown margin and reactivity monitoring are detailed in STP R-12,:and STP I-1A,;respectively. Surveillance Test Procedure (STP) R-12, Revision 8, dated 6/6/86 entitled " Boron Concentration during Refueling" provides-for the responsibilities, frequencies, samples,-and analysis of Boron concentrations from the reactor coolant system and any filled sections of the refueling cana .

After the boron samples are taken, theresults and sample times are

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reported to Operations.

i Surveillance Test Procedure (STP) I-1A, Revision 13, dated 12/18/85, entitled " Routine Shift Checks Required by Licenses" provides for the reactivity monitoring, radiation monitoring, reactor vessel water level

^? control,.and decay heat removal. Surveillance Test Procedure I-1C, '

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_ Revision 15, dated 5/22/86, entitled " Routine Weekly Checks" provides-for

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l6 a containment integrity verification. This containment integrity.

l .. verification provides assurance that the . equipment door is closed and '

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f held in place by'a minimum of 4 bolts, a minimum of one door in each ' =

' airlock is closed, and containment isolation valves are close , , ,

. STP's I-1A, I-1B, I-1C provide the required shift, routine daily checks', ,

,i : and routine weekly checks, respectively, as required by the Technical ijj  ;

Specifications during refueling (Section 3/4.9).  ;

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!5 ae The, reviewed, administrative and operating procedures provide controls is for monitoring the shutdown margin, reactivity, and radiation. .In

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addition,reactorvesselwater-levelcSatrol,decayheatremoval,and

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containment integrity requirements are specified and documente The inspector reviewed the licensee'.s implementation of-controls. Th ' inspector reviewed the licensee's fuel receipt and inspection records for the. upcoming Unit-1 fuel load. These records were performed in

'accordance with the operating procedures OP-B-8C, and OP B-8A as discussed previously in this repor No violations or deviations were identifie . Exit An exit meeting was held with the licensee's representatives identified in paragraph 1 on August 29, 1986, wherein the inspector surnarized the scope and findings of the inspection as described in this_repcrt.

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