IR 05000373/1988020

Insp Rept 50-373/88-20 on 880718-27.No Violations or Deviations Noted.Major Areas Inspected:Action on Previous Findings,Calibr of Nuclear Instrumentation Sys & Shutdown Margin & Reactivity Anomaly Surveillances

ML20151U893
Person / Time
Site:	LaSalle
Issue date:	08/11/1988
From:	Phillips M, Wetzel B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20151U866	List: IR 05000373/1988020 ML20151U862
References
50-373-88-20, NUDOCS 8808190291
Download: ML20151U893 (13)

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U.S. NUCLEAR REGULATORY C0t1 MISSION

REGION III

Report No. 50-373/88020(DRS) Docket No. 50-373 License No. NPF-11 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: LaSalle County Station, Unit 1 Inspection At: LaSalle Site, Marseilles, Illinois Inspection Conducted: July 18 through 27, 1988 ! Inspector: tze // 98 Dat6 Approved By: nt .P lips, Chief f////// .' Operatio.1a1 Programs Section Date Inspection Summary Inspection on July 17 through 27, 1988 (Report No. 50-373/88020(DRS)) A_reas Inspected: Routine, unannounced safety inspection of licensee action en previous inspection findings (92701), calibration of nuclear instrumentation systems (61705), shutdown margin and reactivity anomaly surveillances (61707), 4 core thermal power evaluation (61706), core power distribution limits (61702), and control rod performance testing (72700).

Results: No violations or deviations were identified.

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DETAILS 1. Persons Contacted

    * J. Diederich, Station Manager
    *J. W. Geiseker, Technical Staff Supervisor
    *W. R. Huntington, Services Superintendent
    *D. E. Jones, NRC, Project Inspector
    *P. F. Manning, Assistant Superintendent, Technical Services E. A. McVey, Assistant Lead Nuclear Engineer
    *J. A. Miller, Lead Nuclear Engineer
    *D. R. Reif, Regulatory Assurance The inspector also interviewed other licensee personnel during the course of the inspection including members of the operations and technical staf * Denotes persons attending the exit meeting of July 27, 198 . Licensee Action on Previous Inspection Findings (92701) (Closed) Open Item (373/86036-01(DRS)): During Unit 1, Cycle 2 startup testing, procedure LOP-RD-04, "Control Rod Drive Timing,"

Revision 2, was performed using the incorrect data sheet thereby precluding strict adherence to the procedure. The correct data sheet could not be found at the start of the test; therefore, Attachment C of LOS-AA-W1 was modified and used to document the tes Procedure LOP-RD-04 was replaced by surveillance LOS-RD-SRS,

    "Control Rod Drive Timing." The change from an operating procedure to a surveillance placed stricter controls on test performance, documentation and record retention requirement '

LOS-RD-SR5, 9evision 2 was performed satisfactorily during Unit 1, Cycle 3 startup testing between June 25 and July 1, '1988. The surveillance was adhered to and documented properly on the appropriate data sheets. The inspector has no further concerns in this area, (Cloted) Violation (373/88010-01(DRS)): During defueling activities two Intermediate Range Monitors (IRMs) on the same trip system were declared inoperable which is one more than allowed by Technical Specification 3.3.1. However, 'D' IRM was probably never technically inoperable because it passed both a functional test and an instrument calibration without any edjustments made to the IRM. The main concern with this incident was that of procedural and administrative errors that resulted in a Mode change without the required instrumentation opsrable and, more importantly, operating personnel not aware that they were in noncompliance with Technical Specifications (TS) for eight day , - . - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _ . _ _ _ - _ _

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The licensee performed the following immediate corrective actions i prior-to commencing defueling operations:

    (1) Core alterations were suspended and a half scram was initiated     I which satisfied the action statements required by TS 3. {

    (2) A functional surveillance was performed on all nuclear instrumentation which indicated that all IRMs were operabl (3) All outstanding entries in the degraded Equipment Log (DEL)     ;

were reviewed and determined to be acceptable for refueling '

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operation (4) All TS requirements for Mode 5 as well as requirements which are applicable to all Modes were verifie The insper. tor verified that the licensee completed and implemented the following corrective actions taken to avoid further violation-t (1) The following revisions were made to Procedure, LAP-220-4, I

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       "Degraded Equipment Log," Revision 3, to improve the documentation and tracking of safety related degraded and  i inoperable equipment:     <
       * A requirement was added to place red tags on all safety related/TS equipment located in the control room that i !

inoperabl '

       * Attachment 8 of LAP-220-4 was revised to require documentation of changes in equipment status and the date and time red tags were placed on inoperable equipmen * Attachment F was reformatted to clearly indicate the  ,

status of equipmen * A new Attachment I, "Degraded Equipment Change History," , was developed to clearly track status changes of equipment and provide reliable information to the operating staff - concerning the status of equipmen i ,

       * -The Operating Engineer's weekly DEL review was expanded to l         allow other off-shift personnel, who were not responsible  !

for maintaining the log, to review the DEL for compliance with TS requirement .

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    (2) Procedure, LOP-AA-03, "Reactor Mode Change," Revision 2, has     i been revised to incorporate a checklist which identifies all  ,

the requirements necessary to enter Mode 5 (Refueling) from  !

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Mode 4 (Cold Shutdown), including the requirement to have 3 IRMs per trip system operabl I (3) The event was reviewed with members of the operating' staff.

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The inspector has no further concerns in this are . Calibration of Nuclear Instrumentation Systems (61705)  !

The inspector reviewed the following completed procedures concerning nuclear instrumentation systems, and verified adherence to the procedures and compliance with TS requirement .

 * LTP-1600-22, "SRM Performance Check " Revision 6, performed June 2 through 7, 198 * LTP-1600-23, "Intermediate Range Monitor Performance Check,"

Revision 5, performed July 5-6, 198 ,

 * LIS-NR-102, "Unit 1 Intermediate Range Monitor Rod Block and Reactor i

Scram Calibration," Revision 1, performed May 21 through 23, 198 * LIS-NR-302, "Unit 1 Intermediate Range Monitor Rod Block and Reactor Scram Functional Test," Revision 5, performed July 2,198 ! * LTP-1600-6, "TIP System Calibration," Revision 4, completed July 16, f 198 ;

 * LAP-100-29, "Whole Core LPRM Calibration," Revision 5, performed i July 13 through 15, 198 ,

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 * LTP-1600-8, "Nuclear Engineer's Method for APRM Calibration,"

Revision 2, performed July 6 and July 13, 198 No violations or deviations were identified, l , f ' Shutdown Margin and Reactivity Anomaly Surveillances (61707) i l The inspector reviewed completed surveillances and confirmed that shutdown margin and reactivity anomaly calculations complied with TS and were consistent with cycle specific data supplied by G2neral Electric Company. The following documents were utilized during the review:

* "Cycle Management Report and Prestartup Cycle Operation Plan for

LaSalle Unit 1, Cycle 3," dated May 13, 198 * LTS-1100-14. "Shutdown Margin Subcrif ! cal Demonstration,"

Revision 1 completed July 4, 198 t '

 * LTS-1100-1, "Shutdown Margin Test," Revision 6, performed July 4, l
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198 * LTS-1100-2, "Checking for Reactivity Anomalies," Revision 10, I completed July 4, 198 [

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 ' Core Thermal Power-Evaluation (61706)

The inspector revi wed (TP-1600-10, "Calculating Core Thermal Power," Revision 6, and several samples of the completed Attachment A, "Heat Balance Calculat.on Sheet," performed at various power level Attachment A is a worksheet used by the nuclear engineers to perform a hand heat balance when the process ccmputer is inoperable or to verify the process computer calculation The inspector identified one concern with the procedure. Steps 6 and 7 of the worksh?et require the engineer to record the current of the rceirculation pumps when they are operating at high speed only. A constant is used for the recirculation pumps energy when they are operating in low speed. However, some of the engineers were recording the current in low speed and inserting that into the heat balance calculation which could create a sma'il error in the resultant core thermal power. The inspector noted that in the two cases where this error was made on the worksheet the resultant core thermal power was not used to calibrate the Average Power Rangs Monitors or verify the computer code, but was for information onl "he licensee responded to the inspector's concern by revising the

  %DiKsheet to Clarify Steps 6 and 7, to prevent errors in recording the
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pump currents. The worksheet will also be reprinted because some of the ! Steps were not very legibl The procedure revision adequately resolved the inspector's concer No violations or deviations were identifie . Core Power Distribution Limits (61702) The inspector reviewed one week's sample of LTS-1200-4, "Nuclear Engineer's Daily Surveillance," Revision 7, completed for July 13 i through 20, 1988 and verified that power distribution limits were in

compliance with TS Section 3/4.2. The inspector also reviewed

' LAP-100-29, "Unit 1 Shiftly Surveillance," Revision 2, perfo med on July 15, 1988. The inspector verified that the thermal limits recorded i: on the procedure were consistent with those output by the process . ' computer and complied with TS limits. No violations or deviations were identified.

l Control Rod Performance Testing (727900) ! The inspectot reviewed the following surveillances used for startup testing of the control rod drives and verified that the data was properly  ;

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2 recorded and results were acceptable:

  * LTP-700-2, "Control Rod Friction and Settle Testing," Revision 3, i

performed June 8 through 11, 198 * LOS-RD-SR5, "Control Rod Drive Timing," Revision 2, performed ! June 25 through July 1, 198 , I i l '

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       * LTS-1100-3, "Control Rod Following and LPRM Operability Verification," R; vision 4, performed July 6 through 12, 198 * LOS-RD-SR1, "Control Rod Drive Mechanical Coupling Verification,"

Revision 3, performed May 27 through 29, 198 * LTS-1100-4, "Scram Insertion Times," Revision 9, completed July 8, 1988.

' The inspector identified one concern with LTS-1100- Step C.3 read, in part, "The Rod Scram Sequence should be consistent with current operating recommendations and written such that successive rods are separated radially by at least two control cells." After plotting the scram sequence on a core map it was evident that successive rods were not separated radially by at least two control cells, as stipulated in the procedur However, the sequence was consistent with Procedure LTP-1600-2, "Guidelines for Control Rod Sequence Development," Revision 7 and coincided with the predicted rod pattern at the time of the scram ) timing. The rod sequencing was also written to maintain power greater ' than 20% (to avoid Rod Drop Accident concerns) and less than 25% (to avoid thermal limit concerns). The licensee revised LTS-1100-4 Step to reflect the way rod scram sequences currently are being written, which adaquately resolved the inspector's concern.

' No violations or deviations were identifie . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on July 27, 1988, and summarized the scope and findings of the inspection. The inspector also discussed the likely informational content of the inspection report with regard to , documents or processes reviewed by the inspector during the inspection.

! The licensee acknowledged statements made by the inspector and stated that no material reviewed by the inspector was considered proprietary.

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INSPECTOR'S REPORT (Continuation) __ I -

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RP 05168

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.\ , SALP FUNCTICHAL AREA ASSESSMENT AND PRELTHlRARY INSPECTOR EVALUATION FORM

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pacility: _ /, a dh //c', Inspection Report No.: 56 -373 /96C /S L FUNCTIONAL AREAS I / l _] l II l ITI I IV v Dev lunitlRatinal l P uNT OFERITlbHS l l l l l , l l l l- - 1 l l l l 1 l l l l RADIOLCGICAL CONTROLS l l l l l l l l l_ l l l l 1 ll l l l 0l l MIWlERANCE  ! l l l l l l l l Pl l- 1 I I I ~~ l l l EIl W3')i ~ f TORVEI_LMNCE- l l l H l I l I h

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* Functional areas for Construction and Operations CRITERIA FOR DETERMINING CATEGORY RATING Management Involvement in Assuring Qualit . Approach to Resolution of Technical Issues from a Safety Standpoin . Resoonsiveness to NRC Initiative Enf',rcement Histor . Operational and Construction Event . Staffing (including stanagement).

RATING KEY: (For Categories 2 - Declining and 3, provide narrative basis for conclusion) g *. Category I Category 2 - Declining Ca egory 2 Category 3 -[ii s fcrin iS inc.o nia ten t- ed, % %t l l Inspector (s) concerns adequately addressed oE SAL 9

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March 3, 1986

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5tatus Code __________________________________________________ S __________________________________________________ FUstCTf0stAL AREA gm TYPE Coor 1 OPERATt045 gpg ,,, AC3 - Asseostos. EarWIR. OC ORD - ORDERS TO LICEftSEE RAD - CHEM ,,,, p,, acc - AttcCAfson orn - orn(R MAINTCNANCE ,,L 3 ,, SOL - BULLET 88I P?O - 10 CfR PART 20 se . SunytetLANCE g g CAL P78 - to CFR PART 7, (McRcw mte

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APP. c sEC. u=R - u=RESOtyco aTcMs . orm - oets attn won - weironawg Attachment I to RP 1201

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SSE - io CFR 50.55t.) :TEMs ' Revised 12/04/87 i

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