Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381

JUN 1 4 1995

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555

Gentlemen:

In the Matter of the Application ofTennessee Valley Authority

Docket Nos. 50-39050-391

WATTS BAR NUCLEAR PLANT (WBN) - STATUS OF SAFETY ISSUES AT WATTS BARUNIT 1 NUCLEAR POWER PLANT - MARCH 1995 - FINAL REPORT

Your letter to 0. D. Kingsley dated February 23, 1995, provided theresults of an NRC review of the status of generic safety issues whichare applicable to WBN. Your letter to 0. D. Kingsley dated May 4,1995, directed TVA to use a final version of the NRC report which wastransmitted informally to TVA on March 29, 1995.

As agreed during our April 28, 1995 meeting, TVA's response to theFebruary 23, 1995 and May 4, 1995, letters is being provided to NRC instages. The first part of the three part response was provided by myMay 19, 1995, letter to you. This letter provides the second part.The final response is targeted for July 14, 1995.

The status for each item is provided in Enclosure 1 as an update to thesummary tables shown in the NRC final report as Tables 4.2, 5.2, 6.2,and 7.2.

9506210279 950614PDR ADOCK 05000390A PDR

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U. S. Nuclear Regulatory CommissionPage 2

JUN 1 4 1995Enclosure 2 provides the rationale for differences between the statusin the summary tables of the final NRC report and the status developedfrom TVA's review of the issues. As requested, completion schedulesare provided for issues with an implementation status of "open."

If you should have any questions, contact E. W. Whitaker at(615) 365-1035.

Sinc ly,

aul R. BaronNuclear Assurance & LicensingManager (Acting)

Enclosurescc (Enclosures):

NRC Resident InspectorWatts Bar Nuclear PlantRt. 2, Box 700Spring City, Tennessee 37381

Mr. P. S. Tam, Senior Project ManagerU.S. Nuclear Regulatory CommissionOne White Flint North11555 Rockville PikeRockville, Maryland 20852

U.S. Nuclear Regulatory CommissionRegion II101 Marietta Street, NW, Suite 2900Atlanta, Georgia 30323

Enclosure 1

Watts Bar Nuclear PlantCompletion Status of Generic Issues

Issue Description NRC Lic TVA Lic NRC TA NRC TVAAction Action Impi Impi Verify Verify

GSI 70 PORV & Block Open Complete Open Complete N/A N/A(B114) Valve Reliability

GSI 75 GL 83-28 Item Complete Complete Open Open Open Open(L003) 2.2.2

Vendor Interfacefor Safety-RelatedComponents .

GSI 75 Post-Trip Review Complete Complete Complete Complete N/A N/A(B076) Program

Description &Procedures

GSI 75 GL 83-28 Item 2.1 Complete Complete Open Open Open Open(B077) Equipment

Classification &Vendor Interfaceon Rx TripSystem Components

GSI 75 GL 83-28 Item Complete Complete Complete Complete Complete Complete(B079) 3.1.3 Post-

MaintenanceTesting - Changesto TestRequirements(Reactor TripSystem)

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Issue Description NRC Lic -TVA Lic NRC TVA NRC TVAAction Action Impi Impi Verify Verify

GSI 75 GL 83-28 Item 4.1 Complete Complete Complete Complete Complete Complete(B080) Reactor Trip

SystemReliability -

Vendor RelatedModifications .

GSI 75 GL 83-28 Item 4.3 Complete Complete Complete Complete N/A N/A(B082) Automatic Shunt

Trip Attachmentl_ Modification

GSI 75 GL 83-28 Item Complete Complete Open Complete Open Complete(B086) 2.2.1

EquipmentClassificationfor Safety-RelatedComponents

GSI-75 GL 83-28 Item Complete Complete Complete Complete Open Complete(B81) 4.2.1 & 4.2.2 RTB

Maintenance andTesting

GSI-75 GL 83-28 Item 1.2 Complete Complete Complete Complete N/A N/A(BO85) Post Trip Review

Data &InformationCapability

GSI-75 GL 83-28 Item Open Complete Open Complete Open Complete(B087) 3.2.1 and 3.2.2

Post-MaintenanceTesting - Changesto TestRequirements(Other SafetyRelatedComponents)

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Issue Description NRC Lic TVA Lic NRC TA NRC . AAction Action Impi Impi Verify Verify

GSI 75 GL 83-28 Item Complete Complete Complete Complete Complete Complete(B088) 3.2.3 Post-

MaintenanceTesting - Changesto TestRequirements(Other SafetyRelatedComponents)

GSI 94 Additional Low Open Complete Open Complete N/A N/A(B115) Temperature

OverpressureProtection

II.G.1 Power Supplies Complete Complete Open Complete Open Completefor PressurizerRelief Valves,Block Valves, &Level Indicators

II.K.2.13 Thermal Complete Complete N/A N/A N/A N/AMechanical Report

II.K.3.1 PORV Isolation Complete Complete N/A N/A N/A N/ASystem

II.K.3.2 Report on Safety Complete Complete Complete Complete N/A N/AEffect of a PORVIsolation System

MPA B031 Deep Draft Pump Open Complete Open Complete Open CompleteDeficiencies

MPA B110 Motor Operated Open Complete Open Open Open OpenValve Testing andSurveillance

MPA X809 Thimble Tube Open Open Open Open N/A N/AThinning inWestinghouseReactors

USI A-01 Water Hammer Open Complete Open Open N/A N/A

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Issue Description NRC Lic TVA Lic NRC TVA NRC TVAAction Action Impl Impi Verify Verify

USI A-11 Reactor Vessel Open Complete Open Complete N/A N/AMaterialToughness

USI A-36 Control of Heavy Complete Complete Open Open N/A N/ALoads Near SpentFuel

USI A-44 Station Blackout Complete Complete Open Open Open Open

USI A-45 Shutdown Decay Complete Open Open Open N/A N/AHeat RemovalRequirements _

USI A-49 Pressurized Open Complete Open Complete N/A N/A(A021) Thermal Shock I I I II___

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Enclosure 2

Watts Bar Nuclear Plant Generic IssuesBasis for TVA Status

Issue Number Description Basis / Rationale/Comments

GSI 70 (B1 14) PORV & Block Valve NRC accepted TVA's response to this issue in a January 9, 1991 letter. TheReliability remaining TAC item (76742) was kept to ensure proper implementation in the

Technical Specifications (TS). Licensing action is considered complete based onWBN TS being developed in accordance with the NRC standard technicalspecification program (STS). The STS program supersedes or incorporates earlierTS requirements and WBN TS will be approved under STS.

Implementation is complete based on completion of NCO9 100110001 which revisedappropriate procedures to include manufacturers recommendations.

GSI 75 (L003) GL 83-28 Item 2.2.2 Implementation of the Vendor Interface portion of this issue is open pending theVendor Interface for Safety- completion of the Vendor Interface CAP to be completed by Fuel Load.Related Components

Implementation of the NPRDS is an existing commitment (NCO840202003) withcompletion due by Commercial Operation.

GSI 75 (B076) Post-Trip Review Program TVA agrees with the NRC assessment that this item is complete.Description & Procedures

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Issue Number Description Basis / Rationale/Comments

GSI 75 (B077) GL 83-28 Item 2.1 Implementation of the Q-list portion of this issue was completed within the contextEquipment Classification & of the Q-list CAP and documented in NRC IRs 90-08, 91-08, 91-29, 91-31, 93-20,Vendor Interface on Rx Trip 93-68, and 94-27.System Components

Implementation of the Vendor Interface portion of this issue is open pending thecompletion of the Vendor Interface CAP to be completed by Fuel Load.

Implementation of the NPRDS program is an existing commitment(NCO840202003) with completion due by Commercial Operation.

GSI 75 (B079) GL 83-28 Item 3.1.3 Post- TVA agrees with the assessment that testing requirements have been evaluated forMaintenance Testing - adverse impacts on Reactor Trip System components as required by the genericChanges to Test letter. The basis for this conclusion is the November 7, 1983, TVA letter to NRC.Requirements (Reactor. TripSystem) WBN technical specifications are being developed in accordance with the NRC

standard technical specification program STS. The STS program supersedes orincorporates earlier TS requirements and WBN TS will be approved under STS.As such, there should be no TS requirements which could degrade reactor tripsystem components.

The appropriateness of procedures and specifications was verified by NRC in IR94-73.

GSI 75 (B080) GL 83-28 Item 4.1 Reactor TVA agrees with the assessment that the modifications have been completed. TheTrip System Reliability - modification was verified by NRC in IR 94-73.Vendor RelatedModifications

GSI-75 (B081) GL 83-28 Item 4.2.1 & Verification was completed in IR 94-73.4.2.2 RTB Maintenance andTesting

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Issue Number Description Basis / Rationale/Comments

GSI 75 (B082) GL 83-28 Item 4.3 TVA agrees with the assessment that the modifications have been completed. TheAutomatic Shunt Trip modifications were complete with the closure of NCO850404211 and were verifiedAttachment Modification by NRC in IR 94-73.

GSI-75 (B085) GL 83-28 Item 1.2 Post Trip TVA agrees with the NRC assessment. As documented in IR 94-73, the plant andReview Data & Information procedures provide the necessary information for reactor trip evaluations.Capability

GSI 75 (B086) GL 83-28 Item 2.2.1 Licensing action is complete based on an NRC letters and safety evaluations of theEquipment Classification for Q-list Corrective Action Program dated September 11, 1989, January 23, 1991,Safety-Related Components and March 17, 1994.

Implementation of the Q-list portion of GL 83-28 is complete based on completionof the Q-list CAP as documented in TVA letter dated January 28, 1994.

NRC verification is documented in NRC IRs 90-08, 91-08, 91-29, 91-31, 93-20,93-68, and in 94-27 which concluded the CAP implementation was complete.

GSI-75 (B087) GL 83-28 Item 3.2.1 and Licensing action for this item was completed originally by inspection report IR 86-3.2.2 Post-Maintenance 04. SSER 5 reflected this closure by citing the inspection report. As noted in theTesting - Changes to Test NRC report, TVA modified its position by letter dated November 1, 1993.Requirements (Other Safety Regional inspectors again reviewed site procedures in IR 94-73. This completesRelated Components) the Licensing Action.

Implementation is complete based on issuance of procedures to ensure inclusion ofpost-maintenance test requirements in appropriate site procedures.

NRC verification is documented in IR 94-73.

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Issue Number Description IBasis / Rationale/Comments

GSI 75 (B088) GL 83-28 Item 3.2.3 Post- TVA agrees with the assessment that testing requirements have been evaluated forMaintenance Testing - adverse impacts on safety-related components as required by the generic letter.Changes to TestRequirements (Other Safety WBN TS are being developed in accordance with the NRC standard technicalRelated Components) specification program STS. The STS program supersedes or incorporates earlier

TS requirements and WBN TS will be approved under STS. As such, there shouldbe no TS requirements which could degrade safety related components.

l_ The appropriateness of procedures was verified by NRC in IR 94-73.

GSI 94 (B1 15) Additional Low Temperature Licensing action is considered complete based on WBN TS being developed inOverpressure Protection accordance with the NRC standard technical specification program STS. The STS

program supersedes or incorporates earlier TS requirements and WBN TS will beapproved under STS.

Implementation is considered complete with the completion of operating proceduresas referenced in IR 93-203. The system is described in FSAR section 5.2.2.4.The weakness reported in the NRC Final Report on Safety Issues pertains to theresolution of GSI 70.

Implementation issues associated with technical specification requirements areaddressed in WBN technical specifications which are being developed inaccordance with the NRC standard technical specification program (STS). The STSprogram supersedes or incorporates earlier TS requirements and WBN TS will beapproved under STS.

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Issue Number Description Basis / Rationale/Comments

II.G. 1 Power Supplies for Implementation is considered complete based on completion of the recommendedPressurizer Relief Valves, modifications. The configuration is reflected in the System Description for theBlock Valves, & Level Reactor Coolant System .Indicators

Verification of the modifications was completed in IR 85-25 and confirmed in IR91-04.

II.K.2. 13 Thermal Mechanical Report TVA agrees with NRC assessment that the issue is resolved and no TVA action isrequired unless NRC review of WOG generic resolution identifies required actionsand NRC notifies TVA.

II.K.3. 1 PORV Isolation System TVA agrees that this issue is complete based on Westinghouse generic analysiswhich demonstrated that adequate protection was provided by the existing PORVisolation system as modified after TMI.

II.K.3.2 Report on Safety Effect of a TVA agrees that this issue is complete based on Westinghouse generic analysisPORV Isolation System which demonstrated that adequate protection was provided by the existing PORV

isolation system as modified after TMI.

Issue Number JDescription Basis / Rationale/Comments

MPA B031 Deep Draft Pump Licensing action is complete based on a review and closure by Regional inspectorsDeficiencies (BL 79-15) in IR 94-45.

Implementation is complete based on incorporation of ASME vibration limits asdiscussed in TVA's letter dated January 24, 1995. Preventive maintenance andmonitoring programs are described in FSAR sections 3.9.2 & .3 and in siteprocedures. As agreed during the April 28, 1995 meeting with NRC, completionof the required actions is considered to complete the issue. Subsequently identifiedproblems are handled separately through the corrective action program and do notreopen the issue.

Verification was conducted in IR 94-45 which closed the bulletin and IR 95-05which concluded that WBN had implemented an adequate ASME Section XI ISTprogram.

MPA B110 MOV Testing and Licensing action is considered complete based on specific closure statements made'Surveillance in an NRC letter dated September 14, 1990, which closed MPA B110.

Implementation remains open pending completion of several program elementswhich are scheduled for completion by August 31, 1995.

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Issue Number J Description Basis / Rationale/Comments

MPA X809 Thimble Tube Thinning in Licensing action is open pending NRC documentation of their review of TVA'sWestinghouse Reactors March 11, 1994, response to the bulletin. Bulletin 88-09 requires the completion

of inspections at the first refueling outage. This is consistent with the scope ofinspections which must be performed during a refueling outage. SER Supplement 6rephrases the requirement to "before the first refueling outage". The schedule inBL 88-09 is considered the controlling schedule for the inspections.

Implementation requires a confirmation letter from TVA documenting that aninspection program has been established and an inspection of the tubes has beenperformed after the first cycle of operation. TVA previously committed to submita letter 30 days after the completion of tube inspections which will be conductedduring the first refueling outage.

USI A-01 Water Hammer The final NRC report references the generic closure based on incorporation ofguidance into the Standard Review Plan. Branch Technical Position ASB wasimplemented in 1984 (after the WBN SER) to address water hammer, but it isapplicable only to plants receiving a construction permit after 1984. Watts Barreceived a CP prior to 1984 and as such BTP ASB 10.2 is not applicable. The1982 SER is still valid.

Implementation is open pending completion of dynamic effects piping vibrationtests which require full system temperatures and flows. These tests are conductedduring power ascension and power operations as described in FSAR section 14.2.

l_ Therefore, this item is scheduled for completion after Fuel Load.

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Issue Number Description Basis / Rationale/Comments ]USI A-il Reactor Vessel Material USI A-il was resolved by NUREG 744. NUREG 0744 RI. (GL 82-26) provided

Toughness additional guidance on meeting 10 CFR 50, Appendix G, but allows alternativemethods to demonstrate adequacy of reactor pressure vessels. SSER supplement 14documents the NRC acceptance of WBN methods of compliance with Appendix G.Therefore, the Licensing action is considered closed.

,_ __ Implementation is considered complete based on NRC approval in SSER 14.

USI A-36 Control of Heavy Loads Implementation is open pending completion of commitments which are required toNear Spent Fuel be complete by the first refueling outage.

USI A-44 Station Blackout Implementation requires completion of modifications to provide compressed gascontrol of the TDAFW pump line valves which TVA committed to complete byfuel load. The modifications and associated procedures are scheduled forcompletion by July 10, 1995.

USI A-45 Shutdown Decay Heat The Licensing action for this item should be open. Generic Letter 88-20 subsumedRemoval Requirements USI A-45 and GL 88-20 requires a IPEEE analysis. TVA previously has

committed to submit the IPEEE analysis within 120 days following the end of theUnit 1 Cycle 1 outage. The NRC accepted that schedule by letter dated March 4,1994.

Similarly the implementation of A-45 remains open pending completion of theIPEEE.

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|Issue Number Description Basis / Rationale/Comments

USI A-49 (A021) Pressurized Thermal Shock Licensing action is considered complete since SSER 14 concluded Watts Barcomplied with Appendix G without exemptions.

Implementation is considered complete based on NRC acceptance in SSER 11 ofTVA submittals required by 10 CFR 50.61. The NRC final report on WBNgeneric safety issues, notes that the WBN response to Generic Letter 89-12 is

___ _ Iadequate.