IR 05000498/1989028

Insp Repts 50-498/89-28 & 50-499/89-28 on 890731-0804.No Violations or Deviations Noted.Major Areas Inspected:Power Plateau Testing for Unit 1,Cycle 1,including Power Temp Coefficient of Reactivity & Control Rod Worth Measurements

ML20246A346
Person / Time
Site:	South Texas
Issue date:	08/11/1989
From:	Ray Azua, Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20246A330	List: IR 05000498/1989028 ML20246A327
References
50-498-89-28, 50-499-89-28, NUDOCS 8908220439
Download: ML20246A346 (6)

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f,; Y APPENDIX U.S. NUCLEAR REGULATORY COMMISSIO >

REGION IV

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NRCLInspection' Report: 50-498/89-2 Operating Licenses: NPF-76 50-499/89-28- NPF-8 ~ Dockets: 150-498-50-499

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Licensee: ' Houston. Lighting & Power Company (HL&P) .

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Houston,- Texas 77001 i-Facility Name: .-South Texas Project (STP), Units 1 and 2

' . Inspection At: STP, Bay City, Texas cInspection Conducted: July 31 through August 4, 1989 J

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T. O. McKer0sn, Reactor Inspector, Test I!#[f7

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Date Programs Section, Division of Reactor Safety

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ke k et.- f////t'9 R. V. Azua, Reictor Inspector, Test Programs Date Section, Division of Reactor Safety

'Approvid: W#[#f W..C. Seidle,. Chief, Test Programs Section Date Division of. Reactor Safet ~ Inspection Summary Inspection Conducted July 31 through August 4,1989 (Report 50-498/89-28)

Areas Inspected: . Routine, unannounced inspection of the licensee's power plateau testing for Unit 1, Cycle 1 which included p:.wer coefficient of reactivity, end of' cycle moderator temperature coefficient, control rod worth measurements, core thermal power calculations, and followup to a previous

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l-2 Results: Within the areas inspected, no violations or deviations were identified. The licensee has sufficiently satisfied the testing requirements for the power ascension progra Inspection Conducted July 31 through August 4, 1989 (Report 50-499/89-28)

Areas Inspected: Routine, unannounced inspection of the licensee's power plateau testing for Unit 2, Cycle I which included power coefficient of reactivity, load swing testing, core thermal power calculations, and core flux distribution mappin Results: Within the areas inspected, no violatier.s or deviations were identified. The licensee has sufficiently satisfied the testing requirements

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,t . DETAILS

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" g Persons Contacted .

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~4' 4 m,. . , HL&P ,

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7 (*L .Kinsey,; Plant Manager . .

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• Si Lr Rosen..Vice: President', Nuclear Engineering & Construction

• M.,A.lBarnett,LicensingManager .

. .. + r*W.MJ.; Jump, Maintenance Manager 3 A, "

• W.' L. Mutz, Operations Strategic Planning Manager

.*G.'L. Parkey, Manager,' Integrated Planning & Scheduling

• D.=A.:Leazar,; Reactor. Support. Manager

• D. E Bohner, Quality: Engineering Manager 1 *' ,*Mb R.!Wisenburg, Plant Supe _rintendent .

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? *C. B. Thiele,iReactor Performance' Supervisor

- *C. A..Ayala, Licensing' Supervisory Engineer

• T."J. Jordan., Manager, Plant Engineering

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• A. K. Khosla, Senior Licensing Engineer #

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TJ. Morris, Reactor. Performance Engineer

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NRC'

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'* E. Bess,' Senior Resident Inspector, Unit 1 L*J. I. Tapia, Senior Resident Inspector, Unit 2

• D. M. Hunnicutt, Senior Project Engineer, Region IV c

• Denotes. those present during:the exit interview held on August 4,198 . 1Followu'p to' Previous' Inspection Finding ~-(92701)

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4(Closed)Openitem 8844-01: Leakage reduction program development for

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primary coolant sources outside the containment. This open item involved

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the followup review of.the licensee's proceduralized leakage. reduction

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During.the. followup inspection, the inspector reviewed the licensee's 4 - : actions to develop a formalized leakage reduction program. The licensee has' implemented the leakage reduction program through the operations plant

<. surveillance ' procedures (OPSP-11) program and the reactor coolant system (RCS)

pressure. boundary inspection for boric acid leaks by issuance of general Procedure OPGP03-ZE-0003, Revision 0, dated August 1, 1988. The procedures x, .under the 0 PSP-11 program include those systems listed under Technical

" Specification .(TS) 6.8.3 and others which could act as radioactive materials effluent paths under accident conditions. The adequacy of specific procedures under the OPSP-11 program will be reviewed during-future local

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leak' rate' tests and RCS leakage determination inspections. This item is

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considered close y

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4 Startup Testing (72700)-

' Isothermal and Moderator Temperature Coefficient Determinations (IP61708],

This portion of the inspection involved the review of moderator temperature coefficient (MTC) determination at end of life conditions for Unit 1. The inspectors reviewed the licensee's Procedure OPSP10-ZG-0004, Revision 2, " Determination 'of Moderator Temperature Coefficient at Power, dated November 6,1988. This review was performed to verify the frequency in which MTC was determined and that it met the requirements set forth in the licensee's TS. The inspectors also ensured that the MTC calculations were correct and within the limits established in the licensee's T5 and correlated closely to predicted values provided by the vendo Control Rod Worth Measurements (61710)

The inspectors reviewed the control rod worth measurements for Unit 1 Cycle 1, at beginning of life (BOL). The inspectors found the test results evaluation consistent with those findings previousl addressed in NRC Inspection Report 50-498/88-24 The inspectors had no further questions regarding this startup tes Within this portion of the inspection, no violations or deviations were identifie . . Power Level Plateau Data Review - Unit I and Unit 2 (72600. 72608, 72616, 72624)

During this portion of the inspection, the inspectors reviewed the Unit I and Unit 2 test results evaluations for various~ tests not previously reviewed under the power plateau program'(i.e., 30 percent, 50 percent, 75 percent, 100 percent). The inspectors reviewed the station procedures, results, evaluations,'and associated documents tabulated in the attachmen The inspectors reviewed the listed documents to verify that the tests were completed and the results were within the stated TS acceptance criteri The procedures, where appropriate, satisfied-the commitments set forth in STP, Units 1 and 2, final safety analysis report (FSAR). Furthermore, the licensee had performed core and plant surveys to assure safe operation during power ascension. The inspectors reviewed core flux distributions, core thermal power calculations, and thermodynamics data collections to verify that test results were consistent with predicted values and that no significant anomalies were identified. The licensee sufficiently reviewed the test results and formally evaluated authorized continuation to the next higher power platea During the review, the inspectors observed that the licensee had incorpo-rated an additional data sheet to page 44 of Procedure 2 PEPO 4-ZY-0015 -

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. 30 percent -yet had not accounted for the additional cata sheet by pagination s,t or attachment of an errata ' sheet to the front of the document. . The inspectors

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1. , ' 'noted that Procedure.2 PEPO 4-ZA-0003, Revision 0 does not address the

- administrative controls necessary to* incorporate revised data sheets-into-n! ' the test results.during the' review processe cThe inspectors discussed the

. potential _for. lost data sheets with the' reactor performance' supervisor.~;The

. licensee. committed to incorporating sufficient' administrative controls to -

correct:similar, recurrent conditions _in future startup; tests. This concern-shall remainian open item pending. review during a future inspection

• ~(498/8928-01; 499/8928 01) .

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.< Within the scope of this inspection, no violations or deviations were

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W' t Exit Interview ,

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The inspectors conducted an exit ir.terview on August:4, 1989, at which

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time the-inspectors summarized their findings and scope of the inspectio Vx, . The' licensee did not identify, as proprietary, any of..the information-provided to, or: reviewed by, the' inspectors.'

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' ATTACHMENT s 9; . : ,

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l'- 2 PEPO 4-ZY-0017, Revision-1, " Power Coefficient Determination - Initial

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7Startup Test Results - 30%," dated May 23, 1.989

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& -( .* 2 PEPO 4-ZY-0017 Revision 1. " Power Coefficient Determination"- 75% Power i! . Test-Results," dated June 7, 1989

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' :. 2 PEPO 4-ZY-0017f Revision 1 " Power Coefficient Determination - 90% Powe , Test:Results," dated June 14, 1989

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"*' _2 PEPO 4-ZY-0011,: Revision 0, " Load Swing Test.- 30%," dated May 16, 1989

,, , 2 PEPO 4-ZY-0011, Revision 0. " Load Swing Test ~ 50%,". dated May.28, 1989

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• 2 PEP 02-ZG-0010. Revision 3.. " Calorimetric Calculations," cated July 6, l}

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2 PEPO 4-ZY-0011', Revision 0, " Load Swing Test - 75%," dated June 7, 1989 L

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2 PEP 04-ZY-0011.. Revision 0, " Load' Swing Test .100%," dated June 18, 1989

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1. ' 2 PEPO 4-ZA-0003, Revision 0, " Documentation of' Initial Startup Test

" Rescits," dated October 6, 1988 4-2 PEPO 4-ZY-0030, " Initial. Synchronization and 30% Power Test " dated

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• 2 PEP 04-ZY-0020, Revision 0, "At Power Calibration of Steam and F.W. Flow Instrumentation.- Initial Startup Test Result at 30% Pow:m - dated May 19, y '1989

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• 2 PEP 04-ZY-0030,'" Flux Distribution Map - THX-00-5-30RIL," dated May 22, 1989 l

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• 2 PEPO 4-ZA-0001, Revision 0, " Initial Startup Test Sequence Completion Summary - 30%", dated May 23, 1989  !

• - IPEP04-ZY-0017,'Pevision 3. " Power Coefficient Determinations," dated

' July 6, 1988

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