IR 05000412/1987052

Insp Rept 50-412/87-52 on 870713-17.No Violations Noted. Major Areas Inspected:Startup Test Program review,post-core Hot Functional Test Witnessing & Test Result Review

ML20236P327
Person / Time
Site:	Beaver Valley
Issue date:	08/06/1987
From:	Eselgroth P, Wen P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236P269	List: IR 05000412/1987052 ML20236P265
References
50-412-87-52, NUDOCS 8708120298
Download: ML20236P327 (4)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-52 Docket N License N NPF-64 Licensee: Duquesne Light Company P.O. Box 4 Shippingport, P Facility Name: Beaver Valley Unit No. 2 Inspection At: Shippingport, Pennsylvania Inspection Conducted: July 13-17, 1987 Inspectors *

F-s-87 P. Wen,ReacgrEngineer,DRS date Approved by: M F-4-F7 Pet'erEs~elgrp, Chief,TPS,OB,DRS date Inspection Summary: Inspection on July 13-17, 1987 (Inspection Report Number 50-412/87-52)

Areas Inspected: Startup Test Program review, post-core hot functional test witnessing and test result revie Results: No violations were identifie '

Note: For acronyms, not identified, refer to NUREG-0544, " Handbook of Acronyms and Initialisms."

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8708120298 B70007 PDR ADOCK 05000412 G PDR I-._ _ _ _ _ _ _ _ _ _ _ _ _ . - - - - - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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Details 1.0 Persons Contacted Duquesne Light Company

• J. Godleski, Senior Test Engineer R. Huston, Reactor Engineer

• T McGourty, Principal Engineer J. Miller, Senior QA Specialist

• T. Zyra, Director Site Test and Plant Performance U.S. Nuclear Regulatory Commission

• J. Beall, Senior Resident Inspector L. Prividy, Resident Inspector The inspector also contacted other administrative and technical licensee personnel during the course of the inspectio " Denotes those present at the exit meeting held on July 17, 198 .0 Post-Core Hot Functional Testing 2.1 Startup Test Program During this inspection period, the unit changed operational modes from Cold Shutdown (Mode 5) to Hot Standby (Mode 3) for post-core hot functional and pre-critical testing. Mode 4 (RCS average coolant temperature >200 F, but <350 F) was entered on 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> July 15, 1987. On July 17, 1987, the unit entered Mode 3 (RCS average coolant temperature >350 F).

As documented in the NRC Inspection Reoort 50-412/87-48, Section 2, a problem with high pressure drop across the diesel generator lube oil strainer was identified during the pre-operational test and the most recent plant operating surveillance test (OST). The licensee's diesel generator originally had two half-capacity strainers with no isolation valve provided in between. This lube oil strainer installation does not permit strainer element cleaning with the engine operating. The licensee corrected this problem by installing a duplex lube oil strainer system. The post modification tests were conducted per OST 2.36.1 (2EGS-GS2-1) and 2.36.2 (2EGS-EG2-2) on July 8, and 14, 1987, respectivel Tests were properly completed and satisfactory, and emergency diesel generators were declared operable prior to the plant's heat up to Mode Due to the delay in the Mode 5 activities, the actual test of the licensee's initial startup test (IST) program has just started. At the end of this inspection period, the IST program had completed the

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following tests: 'IST 2 018.02, " Control Rod Drive Mechanism Timing Test," Section A in Mode 5-test condition, IST-2.01'B 03," Control Rod Drop Time Measurement Test,." Sections A and B in Mode'5 test condition, and D.0-2.03.01, "Incore Thermocouple and RTD Cross Calibration," at TAVE 250 F test plateau. In addition, IST;

-2.03.01, "Incore Movable Detector System Chest Test," was completed in the previous inspection period and was reported in the NRC inspection report 50-412/87-48, Section .2 -Test Results Review

.Those test results as identified above were reviewed by.the inspector to verify that:

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test changes were approved and. implemented in accordance with administrative procedures; changes did not. impact the basic objectives of the test;

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test deficiencies and exceptions were properly identified, ,

resolved, and resolution accepted;

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the cognizant engineering group had evaluated the test results and signified that testing demonstrated design conditions were met; and,

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test results compared satisfactorily with established acceptance criteria or were properly resolve ,

Discussion The test results from P0-2 03.01, "Incore Thermocouple and RTD Cross Calibration," performed at Tave 250 F test plateau indicated that 6 out of 24 RTD's had bad readings. Among them, 2 RTD's TE4328 and ,

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TE432D) from Loop 3 supplied inputs to the Reactor Protection Syste The bad reading consisted of the isothermal correction check; in that, each RTD's reading was compared with the RCS average tempera-tur Six RTD"s readings were found exceeding the procedure established acceptance criterion of 1.2 F. This information was transmitted from the test group to the operations group verbally at the plant morning meeting on July 16, 1987,- and again using formal l memorandum on July' 17, 1987. This problem will be continuously l, evaluated at different test plateaus with higher RCS average temperature I Findings i No unacceptable conditions were identifie >

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! 3.0 Independent Calculations / Verifications j i

The inspector independently reviewed several visicorder traces of IST-2.018.03, " Control Rod Drop Time Measurement Test," and verified that )j the drop times had been interpreted correctly from these selected trace J All 48 control rod's drop times under cold no-flow, and cold full-flow were consistently fall within the two-sigma limit and less than the seconds acceptance criteri No unacceptable conditions were identifie .0 QA/QC Interface The licensee QA Surveillance Group continuously provided test coverage for the IST program. The inspector noted that witness points in the master copy of the completed IST tests were initialed by QA surveillance

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Group persor.nel. QA activities in the startup testing area were properly

! ' documented in the QA surveillance report No unacceptable conditions were identifie i 5.0 Exit Meeting An exit meeting was held on July 17, 1987 to discuss the inspection scope and findings, as detailed in this report (see paragraph 1J for ' ~

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attendees).

At no time during this inspection was written material provided to the licensee. Based on the NRC Region I review of this report and discussions held with the licensee representatives at the exit, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction l

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