ML20044B208

Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl

ML20044B208
Person / Time
Site:	Byron
Issue date:	07/11/1990
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
REF-GTECI-A-13, REF-GTECI-A-16, REF-GTECI-A-35, REF-GTECI-AS, REF-GTECI-B-10, REF-GTECI-B-36, REF-GTECI-B-63, REF-GTECI-CO, REF-GTECI-EL, REF-GTECI-PI, REF-GTECI-SU, REF-GTECI-SY, TASK-A-13, TASK-A-16, TASK-A-35, TASK-B-10, TASK-B-36, TASK-B-63, TASK-OR GL-88-03, GL-88-14, GL-88-17, GL-88-3, GL-89-13, GL-90-04, GL-90-4, NUDOCS 9007180113
Download: ML20044B208 (11)

Text

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' Camm:nwealth Edissn ei , '

. g 1400 Opus Place Downers Grove,Illinols 60515 y

July 11. 1990 Dr. Thomas-E. Hurley, Director

Office of Nuclear Reactor Regulation-U.S. Nuclear Regulatory Commission

- Hashington, DC 20S55 Attn: Document Control Desk

Subject:

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

Reference:

(a) Generic letter 90-04

-Request for Information Concerning Status of Implementation of Generic Safety Issues (GSI)

Resolved with Imposition of Requirements or Corrective Actions (b) June 28, 1990 letter from T.J. Kovach to T.E. Hurley

Dear Dr. Murley:

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

-indicated that compilation of the requested informati_on would be completed in less than two weeks from the_ original request date of June 29, 1990. This letter represents 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 to reflect the current status of GSI implementation. The generic letter's guide for updating GSI status was utilized for this process. Accordingly, the Attachment to this letter provides the status of the efforts for Byron Station.

Please direct any questions regarding this rescense to this office.

Respectfully, 9007180iis 90o711 C' Y %&

g - T.K Schuster gDR ADOCK~O5000454 tluclear Licensing Administrator PDC

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Attachment cc: A. Bert Davis-RIII t%

O Resident Inspector-Byron T. Boyce-NRR \

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

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- FACILITY NAME: Evron Nuclear Station DOCKET NO.: 50-454 and 50-455 -

LICENSEE: Commonwealth Edison Comoany- -

ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS 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/A With Pipe Breaks in ths BWR Scram System 41 (B058) BWR Scram Discharge Volume All BWRs N/A Systems.

43 (B107) Reliability of Air Systems All. Plants C NTS #434-104-88-014000 Generic 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 of engineering reviews will be provided by 8/4/90.

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STATUS COPf!ENTS .

- CSIHMPA "to . I ' TITLE APPLICABILYTE a

-FACILITY NAME: - Evron Nucle.ar Station .

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

LICENSEE: . Commonwealth Cdison Comoany ATTACHMENT TO GENERIC LETTER 90--04 RESPONSE STATUS OF LICENSEE' IMPLEMENTATION OF CENERIC SArr u ISSUES

' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcuve. ACTIONS NTS #454-104-89-01300-A01 51 (L913) Improving the Reliability of All Plants I thru A13 Graeric Letter 89-13 Open-Cycle Service Water 1. 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) dated 3/21/90.

The following actions are pending for Generic Letter 89-13. Dates shown below are for Unit 2 and cosmoon. Due dates for Unit 1 are~

approximately 11/15/91.

Action 1.

Intake Structure Inspection Program Action Item Record (AIR)

(454-104-89-01300-A11). Inspection procedure in review process.

Implementation anticipated by end' of September 1990.

Action 2.

Flushing stagnant / infrequently used lines.

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a APDLXCABILITY STATHS- C0fffENTS .

GSI/(MPA No.) TITLE FACILITY NAME:'LEvron Nuclear Station .

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

, LICENSEE: ~ Commonwealth Edison Comoany ATTAcimedi TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArtu ISSJIES

' RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS AIR # Subject 51 (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 lines due end of B2R02 AF Pp SX Suction piping Pending installation of Mod.'due 09/30/90 Action 3.

Heat Exchanger Test / Inspection Program AIR 01300-A-09 Heat Exchanger Inspections Scheduled, to be completed by end of B2R02 - approximately 09/30/90 Action 4.

Ultrasonic inspection of high and low flow locations AIR 01300-A12 Due 09/30/90 Action 5.

Single Active Failure Analysis AIR 01300-A01 Due 09/30/90' srm:1782v:3

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a STATUS CCtM NIS .

GSJ H MPA No.1 TITLE AERLXCABILITY FACILITY.NAME: Byron Nuclear Station .

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

LICENSEE: Commonwealth Edison Comoany ATTACHMENT TO GENERIC LETTER 90-44 RESPONSE STATUS OF LICENSEE IMPLEMENTATION-OF GENERIC SArtir ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREc11vt ACTIONS Item I.D.1 is still'open.

67.3.3'(A017) Improved Accident Monitoring All Plants I Anticipated completion' 12/05/90 Item 1.1 - Post-Trip-Review All Plants C B. Youngblood (NRC) to D. Farrar.

75 (B076) (NLA), 7-11-85. Item'1.1 complete ~

(Program Description and and closed.

Procedure)

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

Capability Item 2.1 - Equipnent All Plants C L. Olshan (NRC) to D. Farrar 75 (3077) (NLA), 1-14-87, Item 2.1 found Classification and Vendor acceptable and closed (references Interface (Reactor Trip System Components) given). EGG-NTA-7212 for Part I,.

EGG-NTA-7447 for Part II.

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

75 (B086) Item 't March 26, 1990. Item 2.2.1 classification for GL 83-28, item closed.

dafety-Rt: ?2 1 Components All Plants awaiting G. Alexander (NLA) to H. Denton 75 (LOO 3) Item 2.2.2 - Vendor (NRC) May 7, 1985. Items 2.1, Interface fcr Safety-Related closure 2.2, 4.5.2, provides. additional Components information.

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2 iGfSZ/(MPA No.

" TITLE APPLICABILITY SJATUS COPMENTS f

-FACILITY NAME: Byron Nuclear Station- _

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

LICENSEE: Commonwealth Edison Comcany

' ATTACHMENT-TO GENERIC Ltntx 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES ACTIONS BESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREL ~nvE All Plants C B. Youngblood (NRC) to D..Farrar 75 (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 and components )

closed.

All Plants C B. Youngblood (NRC) to D. Farrar 75 (B079) Items 3.1.3 - Post (NLA), 11-5-85. Items 3.1.3 and Maintenance Testing-Changes.

to Test Requirements 3.2.3 complete and closed.

(Reactor Trip System Components)

C B. Youngblood (NRC) to D. Farrar 75 (B087) Items 3.2.1 & 3.2.2 All Plants

-(NLA),-9-26-85. Items 3.1.1, Post-Maintenance Testing 3.1.2, 3.2.1, 3.2.2, 4.1, and (All Other Safety-Related 4.5.1 complete and closed.

Components)

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

Testing-Changes to Test Requirements (All Other Safety-Related Components)

Item 4.1 - Reactor Trip All Plants C B. Youngblood GiRC) to li. Farrar 75 (B080) (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

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COPMENTS - j TITLE ~ APPZ.YCABIIITY- STATUS

- .GSJ/(MPA No.) . *

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

-Items 4.2.1 & 4.2.2 All PWRs C V. Noonan (NRC) to D. Farrar (NLA) ..

75 (B081) April 28, 1986. SER for Items Reactor Trip System 4.2.1 and 4.2.2. Items closed.

Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) -

Item 4.3 - Reactor Trip- All W and conditionally B. Youngblood (NRC) to D. Farrar 75 (B082) B&W Plants-- approved (NLA), 3-13-85. Item 4.3, auto System Reliability - Design shunt trip modification approved Modifications (Automatic on 4 conditions.- Awaiting final Actuation of Shunt Trip Attachment for Westinghouse approval and closeout, and B&W Plants)

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

Spec Changes (Automatic Actuation of Shunt Trip Closed Generic Letter 85-09 and Attachment for Westinghouse 82-33. Item 4.3.

and B&W Plants)

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

System Reliability Plants (Improvements in Maintenance and Test Procedures for B&W Plants) srm:1782v:6

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

FACILITY NAME: Byron Nuclear' Station J

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

. LICENSEE: Commonwealth EdisonLComcany -

ATT CHMENT TO GENERIC LEntx 90-04 RESPONSE STATUS 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 4.5.1 Functional 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 Item Reliability - 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/A with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of Auxiliary .All PWRs C 1. Letter from L. Olshan to Generic Letter 88-3 Feedwater Pumps H. E. Bliss dated 7/19/88 NTS //454-104-88-00300 accepting corporate response.

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-APPLICABILITY STATUS C0ff!ENTS --..-

SSJ HMPA Wo.)- XITLE .

, FACILITY NAME: 'Evron Nuclear Station- L DOCKET NO.: 5'0-454 and 50-455 -

LICENSEE: Commonwealth Edison Comoany ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SArt.li ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORREcnvt. ACTIOrd All PWRs I 1. Letter from R. A. Chrzanowski' 99 (L817) RCS/RHR Suction Line Valve (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. Chrzanowski to T. E. Murley providing CECO

. response to the Generic Letter l 88-17 Programmed Enhancements p 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 change request in Letter from T. Schuster (NLA) to

.T. E. Murley dated 1/31/90.

Changes for removal of RHR Autoclosure Interlock, allow the operation of one safety injection pump in Mode 5, removal of RHR flowrate in Mode 6. Amendment expected 8/1/90.

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-e EIHMPA No.) TITLE APPLICAEILITY STATUS COtTtENTS .

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

LICENSEE: Commonwealth Edison Company ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE IMPLEMENTATION OF GENEP.IC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS 99 (L817) continu=1 Corresponding Modifications to remove the autoclosure interlock are:

M6-2-89-024 and M6-1-89-024, anticipated completion for Unit 2, end of'B2R02.

Anticipated completion for Unit 1, end of BIR04.

124 Auxiliary Feedwater System All PWRs N/A Reliability ANO-l&2, Rancho Seco,

. Prairie Island 1&2, Crystal River-3 Ft. Calhoun A-13 (B017) ' Snubber Operability. .

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

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

A-16 (D012) Steam Effects on BWR Core Oyster-Creek N/A Spray Distribution & NMP-1 srm:1782v:9

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

'F4CILITY NAME: Byron Nuclear' Station

• 454 and 50-455-DOCKET NO.:

LICENSEE: Commonwealth Edison Comnany ATTACHMENT TO GENERIC LETTER 90-04 RESPONSE STATUS OF LICENSEE' IMPLEMENTATION OF GENERIC SArt.u ISSUES

~ RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECT 1ve. ACTIONS-All Plants NC ' Plant design incorporates this A-35 (B023) Adequacy of Offsite Power item. Reference SER and UFSAR.

Systems Behavior of-BWR Mark III All BWR N/A B-10 Mark'III Containments Plants All Plants NC Plant design incorporates this B-36 Develop Design, Testing and item, reference SER and UFSAR.

Maintenance Criteria for with OL Atmosphere Cleanup-System ' Applications Air Filtration and After 4/1/80 Adsorption Units for Engineered Saftey Features Systems and for Normal Ventilation Systems.

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

Systems Connected to the Reactor Coolant System Pressure Boundary-i srm:1782v:10.

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