IR 05000271/1990009

Insp Rept 50-271/90-09 on 900703-0812.Violations Noted.Major Areas Inspected:Plant Operations,Radiological Control, Maint/Surveillance,Emergency Preparedness,Security & Safety Assessment/Quality Verification

ML20059N143
Person / Time
Site:	Vermont Yankee
Issue date:	09/27/1990
From:	Rogge J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20059N137	List: IR 05000271/1990009 ML20059N135 ML20059N142
References
50-271-90-09, 50-271-90-9, NUDOCS 9010100149
Download: ML20059N143 (35)

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l l U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /90-09'

Docket N License No'. DPR-28 .

I Licensee: Vermont Yankee Nuclear Power Corporation l RD 5, Box 169 Brattleboro, Vermont 05301

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Facility: Vermont Yankee Nuclear Power Station t

Inspection At: Vernon, Vermont

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Inspection Conducted: July 3 - August 12, 1990

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Inspectors: Harold Eichenholz, Senior Resident Inspector Thomas G. Hiltz, Resident Inspector

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Approved by: w 76 Q36n~ F. Rogge, Chief, Rgj' dt6/ Projects Section 3A

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Inspection Summary: Inspection on July 3 - August 12, 1990 l Areas Ins'pected: Resident safety inspection of the following areas: plant operations, radiological controls, maintenance / surveillance, emergency preparedness, security, engineering / technical support,.and safety l assessment / quality verification.

Results: . Inspection results are summarized in the attached Executive Summar r L

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9010100149 900928 PDR 'l Q ADOCK 05000271 v PDC

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EXECUTIVE SUMMARY VERMONT YANKEE INSPECTION REPORT f -271/90-09 JULY 3 - AUGUST 12, 1990 *

Plant Operations * '

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Power operation continued throughout the inspection period. Two schedule power. reductions were completed to perform a rod pattern er. change and a rod pattern adjustment. One violation regarding' the failure to prepare 10 CFR 50.59 safety evaluations and to. conduct required reviews prior to, implementing changes to plant systems was identified. An. engineered safety system walkdown -

on the Core Spray system was completed. As. a result of this walkdown, an unresolved item was identified involving the administrative and operational controls implemented to ensure safety-related valve operability. Several o'

examples were noted where the as-found status of the Core Spray system did not agree with the most recent revision to the FSA Radiological Control t Routine review of radiological protection practices indicated that the radiation protection program was effective. An unresolved: item concerning controls over irradiated fuel movement above the biological shield-was close '

Maintenance and Surveillance An excellent questioning attitude towards perceived equipment deficiencies was demonstrated by I&C department personnel. New fuel inspection and channeling activities were well controlled. Inservice vibration measurement testing of ;

the service water pumps was observed and determined to'be. acceptable. The level of knowledge of the maintenance personnel performing the maintenance was a strength. An unresolved item regarding the failure of valve RHR-38B was

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closed. Maintenance activities associated with "/" EDG (emergency diesel generator) resolved engine load balancing optimization problems. Inspection ,

of the monthly surveillance on the "B" EDG identified a, procedural weakness for resolving acceptance criteria discrepancies. Unfamiliarity.with infrequently used procedural steps and expected equipment responses was noted during the calibration of rod block monitor channel "B." +

Emergency Preparedness ,

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A partial participation emergency exercise was' conducted. The NRC incident response team and the Region I site team were activated and participated in the

' exercise. Details of the NRC inspection in this area are contained in NRC s inspection report 50-271/90-0 .

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Executive Summary 2 Security

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Compersatory measures to support equipment repairs of a _ security system backup ,

power supply were appropriate. A follow-on item to assess.the corrective maintenance program for ways to improve the timeliness of repairs remains ope Engineering and Technical Support ,

The engineering controls designed to prevent inadvertent introduction of .

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nitrogen in the service air system were determined to be adequate .The response to industrial safety concerns involving the use.of reactor building access door passive seals during activities involving the transfer of new fuel into.the

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reactor building reflected a good level of technical support to plant operation Safety Assessment / Quality Verification Acceptable safety oversight performance of the Plant Operations Review Committee was noted in their review of continued plant operations without' the reactor building railroad access door's temporary passive seal. However, timely ;

. resolution of longstanding conecrns involving the postulated loss of instrument '

air to the pneuma;ic seals on .ne reactor building railroad access door would -

have prevented the potential conflict with personnel safety while unloading and inspecting new fuel. Concerns were identified due to PORC corrective actions associated with a long overdue safety evaluation involving a change to the 1 valve lineup of the core spray syste ,

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1990 Outage Milestones 89 - 90 OTG J F M A M J - J A S O N D J .F M A M J J A EB O N DU PREPARATION  ;

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1990 Outage Afilestones 89 . . 90 J F M A M J J A S O N D J F M AM J __J A B O N O.: -4 PROCUREMENT

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COMPLETE REORDERS .

MSPR PREP / REVIEW / APPROVAL M RECEIVE P.O. CONFORMATION CONTRACTS REVIEWED / GENERATED /IN PLACE MJ ._

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