IR 05000412/1987040

Safety Insp Rept 50-412/87-40 on 870511-15.No Violations Noted.Major Areas Inspected:Startup Test Procedures Review, Qa/Qc Interfaces & Licensee Actions on Previous Insp Findings

ML20215E520
Person / Time
Site:	Beaver Valley
Issue date:	06/10/1987
From:	Florek D, Wen P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215E517	List: IR 05000412/1987040 ML20215E514
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM 50-412-87-40, NUDOCS 8706220011
Download: ML20215E520 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-40 i

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Docket N License No. CPR-105 Licensee: Duquesne Light Company '

P.O. Box 4 Shippingport, Pennsylvania 15077 1 Facility Name: Beaver Valley Unit No. 2 Inspection At: Shippingport, Pennsylvania Inspection Conducted: May 11-15, 1987

{,3 Inspector: ./ M(n k P. Wen,' Reactor Engineer, DRS (daye l Approved by: r d2/? / b/

D. J'. Florek, ~ Acting Chief, TPS i date Operations Branch, DRS Inspection Summary: Inspection on May 11-15, 1987 (Inspection Report No. 50-412/87-40)

Areas Inspected: Routine unannounced inspection by one regional inspector of the startup program and startup test procedures review, QA/QC interfaces and licensee actions on previous inspection finding Results: No violations were identifie NOTE: For acronyms not defined refer to NUREG 0544, " Handbook of Acronyms and Initialisms".

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DETAILS 1.0 Persons Contacted Duquesne Light Company ':

• D. Claridge, Compliance Engineer J. Dusenberry, QA Surveillance

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

• 0. Hunkele, Director QA Operations

• J. Johns, Supervisor QA Surveillance T. McGourty, Principal Engineer

• L. Rabenau, Lead Compliance Engineer

• C. Schultz, Principle Engineer

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

• J. Beall', Senior Resident Inspector The inspector also contacted other administrative and technical licensee personnel during the course of the inspectio * Denotes those present at exit meeting held on May 15, 198 .0 Startup Test Program 2.1 Test Program Review The licensee's Initial Startup Test Phase of the Startup Test Program covers tFe initial fuel loading through operation at rated power and warranty demonstrations. The administration of the startup program, procedure.1 controls, test personnel responsibilities, and inter-relationships of the various organizations were described in the Startup Manual Chapter 3.5 (Unit 2 Site Testing and Plant Performance Group) and associated administrative procedures TPP-12.1 through 12.4. These have been reviewed and approved by the Onsite Safety Committee (OSC) and plant managemen NRC has conducted Startup Test preparation inspections as documented in Inspection Reports 50-412/87-27, 87-31 and 87-3 Based on the review of the test program and test procedures through these ;

inspections, and discussion with licensee representatives, the inspector concluded that the licensee's startup test program is consistent with FSAR Chapter 14 (Initial Test Program) and Regulatory Guide '1.68 commitment The licensee's overall startup test program s tatu s., procedures, organization and staffing level are adequat ,

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2.2 Test Procedure Review The inspector reviewed the 8 test procedures listed in Attachment A for the attributes identified in inspection report 50-412/87-31 Section The test procedures satisfied the attributes except as noted below- i

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(1) IST-2.04.03 (Verification of Plant Performance Following a Turbine Trip Coincident with a Loss of Offsite Power at' Load)

The current acceptance criteria were too general and lacked specific instructions to determine acceptabilit After discussion with the licensee cognizant engineer, the procedure will be revised to provide more clear guidance for the determination of the test acceptability specifically, by (i) l clarifying the emergency diesel generator auto start require-ment, (ii) providing more specific guidance for the system !

response acceptance criteria, and (iii) clarifying the turbine driven auxiliary feedwater pump performance acceptabilit This procedure will again be reviewed in a subsequent inspectio .0 QA/QC Interface with the Startup Test Program The site QA/QC organization, program and surveillance plan to support the upcoming startup test coverage were examined in the previous NRC inspec-tions. During this inspection period, the inspector held discussions with the site QA surveillance supervisor and a cognizant-QA engineer to monitor QA/QC's progress on these activities. The inspector noted that QA had participated in the test procedure review and Startup Manual approval proces Through discussion and examination of a sample surveillance plan, the inspector concluded that QA/QC is actively involved in the Startup Test Progra .0 Licensee Action on Previous Inspection Findings (Closed) Unresolved Items (50-412/00-00-22): TMI Action Item II.E. Auxiliary Feedwater (AFW) System Automatic Initiation and Flow Indicatio l This item specifies various requirements with respect to the timely J initiation of the auxiliary feedwater syste The NRR staff has reviewed !

the Beaver Valley Unit 2 design and concluded that this design satisfies {

the requirements of NUREG 0737, Item II.E.1.2. (Safety Evaluation Report Related to the Operation of Beaver Valley Unit 2, NUREG-1057). During this inspection the inspector verified that the initiation signals and l circuits are testable and that the test requirements are included in the i final draft of Technical Specifications. The associated surveillance test procedures are described in Operating Surveillance Test Procedures 2.2 through 2.24.7 and have been approved. The inspector also verified that the AFW system is provided with safety grade, emergency powered, flow I

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indicators on each of the three AFW discharge lines to the steam !

generators. These flow indicators are displayed on the Main Control Board and the Emergency Shutdown Panel. Based on this information, this item is close .0 Exit Meeting >

An exit meeting was held on May 15, 1987, to discuss the inspection scope and findings, as detailed in this report (see paragraph 1.0 for attendees). At no time was written material given 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 th's report does not contain information subject to 10 CFR 2.790 restrictions i

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ATTACHMENT A Startup Test Procedures Reviewed

-- IST-2.01A.02 Startup Adjustments to the Reactor Coolant System, Revision IST-2.01A.07 Automatic Reactor Control, Revision ,

-- IST-2.02.04 Power Coefficient Measurement, Revision IST-2.04.03 Verification of Plant Performance Following a Turbine Trip Coincident with a Loss of Offsite Power at Load, Revision IST-2.04.0S Large Load Reduction Test for Turbine Runback, Revision IST-2.06.03 RTD Bypass Loop Flow Verification, Revision IST-2.07.02 Failed Fuel Detection System Test, Revision IST-2.21A.02 Plant Performance Following MSIV Closure at Power, Revision ;

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