*

..z .

' Camm:nwealth Edissn-' -

ei , . g 1400 Opus Place'

Downers Grove,Illinols 60515

y

July 11. 1990

Dr. Thomas-E. Hurley, DirectorOffice of Nuclear Reactor Regulation-:

U.S. Nuclear Regulatory Commission- Hashington, DC 20S55

Attn: Document Control Desk

Subject: . Byron Station Units 1 and 2Response to Generic Letter 90-04HRC Docket _Has. 50-454 and_50-12

Reference: (a) Generic letter 90-04-Request for Information ConcerningStatus of Implementation ofGeneric Safety Issues (GSI)Resolved with Imposition ofRequirements or Corrective Actions

(b) June 28, 1990 letter from T.J. Kovachto T.E. Hurley

Dear Dr. Murley:

' Generic Letter 90-04 was issued as a part of the NRC's continuing effortto establish and maintain an accurate and validated implementation status for allsignificant staff imposed regulatory requirements or corrective actions. Animportant aspect of this effort is to ensure that the licensee and the NRC agree onthe status of GSI resolution implementation at each facility. Reference (b)

-indicated that compilation of the requested informati_on would be completed in lessthan two weeks from the_ original request date of June 29, 1990. This letterrepresents the Commonwealth Edison (Edison) response to Generic Letter 90-04, for

; Byron Station.

Byron Station has reviewed the guidance provided in the Generic Letter.The attached GSI table (Enclosure 1 from the. generic letter) has been updated toreflect the current status of GSI implementation. The generic letter's guide forupdating GSI status was utilized for this process. Accordingly, the Attachment tothis letter provides the status of the efforts for Byron Station.

Please direct any questions regarding this rescense to this office.

Respectfully,

C' Y %&, . , .

9007180iis 90o711 g - T.K SchustergDR ADOCK~O5000454 tluclear Licensing Administrator

PDC

/scl:1056-2 '

t%AttachmentOcc: A. Bert Davis-RIII

Resident Inspector-ByronT. Boyce-NRR \

_._ _ . . _ . . _ _ . . . . . . . .

~ -:.

- 7 ,_

~'

-=

.. . m

^ 'GSI/(MPA No.) ' TITLE APPLICABILITY STATUS - C0ffENTS -

.e ;

=. _. '. . . .

.

- FACILITY NAME: Evron Nuclear Station.

.

'

DOCKET NO.: 50-454 and 50-455 - ' .LICENSEE: Commonwealth Edison Comoany- -

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF CENERIC SAFETY ISSUES

RESOLVED WITH' IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS

GSI/(MPA No.) TITLE ' APPLICABILITY STATUS C0ffENTS

60 (B065) Safety Concerns Associated All BWRs N/AWith Pipe Breaks in ths BWRScram System

41 (B058) BWR Scram Discharge Volume All BWRs N/ASystems.

43 (B107) Reliability of Air Systems All. Plants C NTS #434-104-88-014000Generic Letter 88-14 1. Letter from M. Richter (NLA).(SOER 88-1) to NRC-dated 2/16/89.. ..

~

2. Letter from D. R. Muller (NRC).to H. E. Bliss (NLA) dated..

4/11/89..3 . The supplemental: response

providing the results ofengineering reviews will beprovided by 8/4/90.

-

srm:1782v:1

.. +. - z. -

__ ______ _ . .

_ _-

, . . . . , . . . . . . . .

- CSIHMPA "to . I ' TITLE APPLICABILYTE STATUS COPf!ENTS .

.a

-FACILITY NAME: - Evron Nucle.ar Station .

~ DOCKET NO.: 50-454 and 53-455 --

LICENSEE: . Commonwealth Cdison Comoany

ATTACHMENT TO GENERIC LETTER 90--04 RESPONSESTATUS OF LICENSEE' IMPLEMENTATION OF CENERIC SArr u ISSUES

' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcuve. ACTIONS

51 (L913) Improving the Reliability of All Plants I NTS #454-104-89-01300-A01thru A13

Graeric Letter 89-13 Open-Cycle Service Water1. Letter from M. Richter to NRC

Systens dated 1/29f90, CECO Response

to Generic Letter 89-13.2. Letter from P. Shemanski (NRC)

to T. Kovach (NLA) dated3/21/90.

The following actions are pendingfor Generic Letter 89-13. Dates

shown below are for Unit 2 andcosmoon. Due dates for Unit 1 are~approximately 11/15/91.

Action 1.Intake Structure InspectionProgram Action Item Record (AIR)(454-104-89-01300-A11). Inspectionprocedure in review process.Implementation anticipated by end'of September 1990.Action 2.Flushing stagnant / infrequentlyused lines.

srm:1782v:2

'' I ||

a,

GSI/(MPA No.) TITLE APDLXCABILITY STATHS- C0fffENTS .

.

FACILITY NAME:'LEvron Nuclear Station .

DOCKET NO.: '5'0-454 and 50-455 -

, LICENSEE: ~ Commonwealth Edison Comoany

ATTAcimedi TO GENERIC LETTER 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArtu ISSJIES

' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS

AIR # Subject51 (L913) continued

01300-A02 AF Pp Miniflow Recire.due end of B2R02

01300-A03 DG Jkt Wtr Train X-tie-lines due end of B2R02-

01300-A04 Unit 0 CC Ex Flush

01300-A06 SX to FP X-tie linesdue end of B2R02

AF Pp SX Suction pipingPending installation ofMod.'due 09/30/90

Action 3.Heat Exchanger Test / InspectionProgramAIR 01300-A-09Heat Exchanger InspectionsScheduled, to be completed by endof B2R02 - approximately 09/30/90

Action 4.Ultrasonic inspection of high andlow flow locationsAIR 01300-A12 Due 09/30/90

Action 5.Single Active Failure AnalysisAIR 01300-A01 Due 09/30/90'

srm:1782v:3

., ,

, _ - - _

,a ui n '

..- .; .

GSJ H MPA No.1 TITLE AERLXCABILITY STATUS CCtM NIS .

*.

FACILITY.NAME: Byron Nuclear Station .

-DOCKET NO.: - 50-454 and 50-455' -

LICENSEE: Commonwealth Edison Comoany

ATTACHMENT TO GENERIC LETTER 90-44 RESPONSESTATUS OF LICENSEE IMPLEMENTATION-OF GENERIC SArtir ISSUES

RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREc11vt ACTIONS

67.3.3'(A017) Improved Accident Monitoring All Plants I Item I.D.1 is still'open.Anticipated completion' 12/05/90

75 (B076) Item 1.1 - Post-Trip-Review All Plants C B. Youngblood (NRC) to D. Farrar.(NLA), 7-11-85. Item'1.1 complete ~(Program Description and and closed.Procedure)

75 (3085) Ites 1.2 - Post-Trip Review All Plants C V. Noonan (NRC) to D. Farrar (NLA)May 5, 1986. Item 1.2 SER.. Item

Daca and Information Closed.Capability

75 (3077) Item 2.1 - Equipnent All Plants C L. Olshan (NRC) to D. Farrar(NLA), 1-14-87, Item 2.1 found

Classification and Vendor acceptable and closed (referencesInterface (Reactor Trip given). EGG-NTA-7212 for Part I,.System Components) EGG-NTA-7447 for Part II.

S. Sands (NRC) to T. Kovach (NLA)'75 (B086) Item 't 2.1 - Equipment All Plants C

March 26, 1990. Item 2.2.1classification for GL 83-28, item closed.dafety-Rt: ?2 1 Components

75 (LOO 3) Item 2.2.2 - Vendor All Plants awaiting G. Alexander (NLA) to H. Dentonclosure (NRC) May 7, 1985. Items 2.1,

Interface fcr Safety-Related 2.2, 4.5.2, provides. additionalComponents information.

srm:1782v:4.

"' . __ d

...~

-_

iGfSZ/(MPA No. TITLE APPLICABILITY SJATUS COPMENTS f"2

; , ;.

-FACILITY NAME: Byron Nuclear Station- _

DOCKET NO.: 50-454 and 50-455 *

: LICENSEE: Commonwealth Edison Comcany

' ATTACHMENT-TO GENERIC Ltntx 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES

ACTIONSBESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREL ~nvE

All Plants C B. Youngblood (NRC) to D..Farrar75 (B078) Items 3.1.1 & 3.1.2 , '(NLA), 9-26-85. Items.3.1.1-Post-Maintenance Testing

3.1.2, 3.2.1, 3.2.2, 4.1, and.(Reactor Trip System 4.5.1 complete andcomponents )

closed.

75 (B079) Items 3.1.3 - Post All Plants C B. Youngblood (NRC) to D. Farrar(NLA), 11-5-85. Items 3.1.3 andMaintenance Testing-Changes. 3.2.3 complete and closed.to Test Requirements

(Reactor Trip SystemComponents)

75 (B087) Items 3.2.1 & 3.2.2 All Plants C B. Youngblood (NRC) to D. Farrar-(NLA),-9-26-85. Items 3.1.1,

Post-Maintenance Testing3.1.2, 3.2.1, 3.2.2, 4.1, and(All Other Safety-Related4.5.1 complete and closed.

Components)

75 (B088) Item 3.2.3 All Plants C B. Youngblood (NRC) to D. Farrar(NLA), 11-5-85. Items 3.1.3 and

Post-Maintenance. 3.2.3 complete and closed.Testing-Changes to TestRequirements (All OtherSafety-Related Components)

75 (B080) Item 4.1 - Reactor Trip All Plants C B. Youngblood GiRC) to li. Farrar(NLA), 9-26-85. Items 3.1.1,

System Reliability 3.1.2,-3.2.1, 3.2.2, 4.1, ano(Vendor-Related 4.5.1 complete and closed.Modifications)

sen:1782v:5

I

-' ^

, . , , , . . . . . . . . . . . . . . . _ .

,,

.

.- - .

,,

-;

- .GSJ/(MPA No.) . TITLE ~ APPZ.YCABIIITY- STATUS COPMENTS - j_

*

.

: FACILITY NAME: Byron Nuclear Station ,.

: DOCKET NO. : 50-454 and 50-455 *

LLICENSEE: Commonwealth Edison Comoany-

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE-STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArtu ISSUES

RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECT 1vt ACTIONS

75 (B081) -Items 4.2.1 & 4.2.2 All PWRs C V. Noonan (NRC) to D. Farrar (NLA) ..April 28, 1986. SER for Items

Reactor Trip System4.2.1 and 4.2.2. Items closed.Reliability-Maintenance and

Testing (PreventativeMaintenance and SurveillanceProgram for Reactor TripBreakers)

-

75 (B082) Item 4.3 - Reactor Trip- All W and conditionally B. Youngblood (NRC) to D. FarrarSystem Reliability - Design B&W Plants-- approved (NLA), 3-13-85. Item 4.3, auto

shunt trip modification approvedModifications (Automatic on 4 conditions.- Awaiting finalActuation of Shunt TripAttachment for Westinghouse approval and closeout,and B&W Plants)

75 (B090) Item 4.3 - Reactor Trip All W & B&W C L. Olshan (NRC) to T. KovachSystem Reliability - Tech Plants May 22, 1989. Technical

Specification amendment and SER.Spec Changes (Automatic Closed Generic Letter 85-09 andActuation of Shunt Trip82-33. Item 4.3.Attachment for Westinghouse

and B&W Plants)

75 (B091) Item 4.4 - Reactor Trip All B&W N/A

System Reliability Plants

(Improvements in Maintenanceand Test Procedures for B&WPlants)

srm:1782v:6

.

- - - -

. . ~ _-.m.

-~

~

.

GSY/(MFA NoN' TITLE APPLIC BILITY ! STATUS C0tetENTS ...

'

FACILITY NAME: Byron Nuclear' StationJ DOCKET NO.: 50-454 and 50-455 .-

. LICENSEE: Commonwealth EdisonLComcany -

ATT CHMENT TO GENERIC LEntx 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES

RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ~ ACTIONS

75 (B092) Item 4.5.1 - Reactor Trip -All Plants C .B. Youngblood (NRC) to D. Farrar.System Reliability-Diverse -(NLA) 9-26-85. Items'3.3.1,Trip Features (System '3.1.2, 3.2.1, 3.2.2, 4.1 and 4.5.1Functional Testing) complete and closed.

75 (B093) Items 4.5.2 & 4.5.3 'All Plants C L. Olshan-(NRC) to D..Farrar (NLA)Reactor Trip System January 23, 1987. SER for ItemReliability - Test- 4.52. Item closed.Alternatives and Intervals L. Olshan (NRC) to T. Kovach (NLA)(System Functional Testing) June 16, 1989. Item 4.5.3 closed

per contractor report,' Idaho-National Engineering EGG-NTA-8341,March, 1989.

86 (B084) Long Range Plan for Dealing All BWRs N/Awith Stress CorrosionCracking in BWR Piping

93 (B098) Steam Binding of Auxiliary .All PWRs C 1. Letter from L. Olshan toGeneric Letter 88-3 Feedwater Pumps H. E. Bliss dated 7/19/88NTS //454-104-88-00300 accepting corporate response.

srm:1782v:7

_ . _ . _ _ _ , _ _ _ _ _ _ _ _ _ _ - . _ _ ____ __ _ _ ~ _ _ __ . __

.. -

'

gi ii ,; , , . . . . , . . . . .

,-

,

SSJ HMPA Wo.)- XITLE -APPLICABILITY STATUS C0ff!ENTS - - . . -.

. .;

, FACILITY NAME: 'Evron Nuclear Station- L

DOCKET NO.: 5'0-454 and 50-455 -

LICENSEE: Commonwealth Edison Comoany

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArt.li ISSUES

RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcnvt. ACTIOrd

99 (L817) RCS/RHR Suction Line Valve All PWRs I 1. Letter from R. A. Chrzanowski'(NLA) to T.E. Murley dated

Generic Letter 88-17 Interlock on PWRs 12/30/88.NTS #454-104-88-01700

2. Letter from R. A. Chrzanowski(NLA) to T. E. Murley dated

-1/31/89.

3. Letter from R. A. Chrzanowskito T. E. Murley providing CECO

. response to the Generic Letter| 88-17 Programmed Enhancementsp dated 2/6/89.i-

4. ' Letter from T. E. Murley:to R.

A. Chrzanowski dated 11/1/89..

5. Letter from P. Shamanski to-T. Kovach dated 1/17/90.

6. Technical Specification changerequest in Letter fromT. Schuster (NLA) to.T. E. Murley dated 1/31/90.Changes for removal of RHRAutoclosure Interlock, allow

the operation of one safetyinjection pump in Mode 5,removal of RHR flowrate inMode 6. Amendment expected8/1/90.

srm:1782v:8

- - := - ; '_--

-e

EIHMPA No.) TITLE APPLICAEILITY STATUS COtTtENTS .

..

FACILITY NMIE: Byron Nuclear StationEOCKET NO.: .50-454Jand 50-455 ,

LICENSEE: Commonwealth Edison Company *

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSESTATUS OF LICENSEE IMPLEMENTATION OF GENEP.IC SAFETY ISSUES

RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS

99 (L817) continu=1 Corresponding Modifications toremove the autoclosure interlockare:

M6-2-89-024 and M6-1-89-024,anticipated completion forUnit 2, end of'B2R02.Anticipated completion forUnit 1, end of BIR04.

124 Auxiliary Feedwater System All PWRs N/AReliability ANO-l&2,

Rancho Seco,. Prairie

Island 1&2,CrystalRiver-3Ft. Calhoun

A-13 (B017) ' Snubber Operability..

All Plants NC Tech Spec 3/4.7.8 incorporatesAssurance Hydraulic Snubbers this item.

A-13 (B022) Snubber Operability All Plants NC Plant design and Tech Spec 3/4.7.8Assurance Mechanical Snubbers incorporates this item.

A-16 (D012) Steam Effects on BWR Core Oyster-Creek N/ASpray Distribution & NMP-1

srm:1782v:9

.- .= . - - . ___ _ __ _ _ _ _ = _ _ . _. - _, .-

~ '. -

*''

... .Y ' Y. . .. .

.*- - .

. y.

,

GSIHMPA No.i~ TITLE APPLICABILITY. STATUS: C0ft1ENTS 7,

'F4CILITY NAME: Byron Nuclear' Station '

DOCKET NO.: -50-454 and 50-455-' *

LICENSEE: Commonwealth Edison Comnany

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSESTATUS OF LICENSEE' IMPLEMENTATION OF GENERIC SArt.u ISSUES

~ RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECT 1ve. ACTIONS-

A-35 (B023) Adequacy of Offsite Power All Plants NC ' Plant design incorporates thisitem. Reference SER and UFSAR.

Systems

B-10 Behavior of-BWR Mark III All BWR N/A

Containments Mark'IIIPlants

B-36 Develop Design, Testing and All Plants NC Plant design incorporates this-

Maintenance Criteria for with OL item, reference SER and UFSAR.

Atmosphere Cleanup-System ' ApplicationsAir Filtration and After 4/1/80Adsorption Units forEngineered Saftey FeaturesSystems and for NormalVentilation Systems.

B-63 (B045) Isolation of Low Pressure All Plants NC Plant design and Tech Spec 3/4.4.6incorporates this item.Systems Connected to the

Reactor Coolant SystemPressure Boundary-

i

srm:1782v:10.

t __