ML17328A296

Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues

ML17328A296
Person / Time
Site:	Cook
Issue date:	06/25/1990
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR AEP:NRC:1108C, GL-83-28, GL-90-03, GL-90-04, GL-90-3, GL-90-4, NUDOCS 9006280322
Download: ML17328A296 (10)

Text

ACCELERATED DISIBUTION DEMONS~ION SYSTEM REGULATORY INFORMATION DXSTRXBUTION SYSTEM (RIDS)ACCESSION NBR:9006280322 DOC.DATE: 90/06/25 NOTARIZED:

NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana&05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana S 05000316 AUTH.NAME AUTHOR AFFXLIATXON ALEXICH,M.P.

Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)R

SUBJECT:

Forwards response to Generic Ltr 90-04 re closeout of generic safety issues.DISTRIBUTXON CODE: A018D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Generic Ltr 90-04 re Status of Licensee Xmplementation of NOTES: D enerxc Saf 8 RECIPIENT ID CODE/NAME PD3-1 LA GIITTER,J.

COPIES LTTR ENCL 1 1 2 2 RECIPXENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1 1 D INTERNAL: CROCKER, L 9H3 NUDOCS-ABSTRACT SCHOLLi R 13E4 EXTERNAL: LPDR 1 1 1 1 1 1 1 1 EC EG FI NRC PDR 0 K10D4 01 1 1 1 1 D S D NOTE TO ALL"RIDS" RECIPIENTS:

D PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 11 Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 AEP:NRC:1108C Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 GENERIC SAFETY ISSUES RESPONSE TO GENERIC LETTER 90-04 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: T.E.Murley June 25, 1990

Dear Dr.Murley:

This letter is in response to Generic Letter (GL)90-04 regarding close-out of generic safety issues.We support your concern and desire to close long-standing generic safety issues.Attachment 1 to this letter is a copy of Enclosure 1 to GL 90-04 with our responses identified in the"STATUS" column.We have used the"COMMENTS" column to identify the safety evaluation report (SER)or license amendment that, to our understanding, indicates that the issue is closed.Comments with"NRC ACTION" annotated means that, to our knowledge, we have not received a response to our latest submittals on that safety issue.The AEP:NRC: submittal numbers and dates reflected in the"STATUS" column are provided for reference and to the best of our knowledge reflect the complete list of submittals on a given topic.We have responded to each issue noted in the enclosure to GL 90-04 except for the most recent generic letter (GL 90-03), which is an iteration of Item 2.2 of GL 83-28.Our response, which will slightly modify our original position, will be submitted in the near future.9006280322 90062 i PDR ADOCK 05000315 P PDC ol'ti)

Dr.T.E.Murley-2-This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M..Ale ich Vice President cc: D.H.Williams, Jr.A.A.Blind-Bridgman J.P.Padgett NFEM Section Chief A.B.Davis-Region III NRC Resident Inspector-Bridgman Attachment to AEP:NRC:1108C Page 1 of 6 FACILITY NAME: COOK NUCLEAR PLANT Ul AND U2 DOCKET NO.: 50-315 and 50-316 LICENSEE: DPR-58 and DPR-74 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF RE UIREMENTS OR CORRECTIVE ACTIONS (Information is identical for Units 1 and 2 except as noted with Amendment No.)GSI MPA No.40 (B065)41 (B058)TITLE Safety Concerns Associated With Pipe Breaks in the BWR Scram System BWR Scram Discharge Volume Systems APPLICABILITY All BWRs All BWRs STATUS*NA COMMENTS 43 (B107)51 (L913)67.3.3 (A017)Reliability of Air Systems All Plants Improving the Reliability All Plants of Open-Cycle Service Water Systems Improved Accident Monitoring All Plants C (AEP:NRC:1075-2/24/89)

C (AEP:NRC:1075A-3/23/89)

C (AEP:NRC:0553-5/28/81)

C (AEP:NRC:1104-1/25/90)

C (AEP:NRC:0773-4/15/83)

C (AEP:NRC:0773J-2/28/85)

C (AEP:NRC:07730-10/15/85)

C (AEP:NRC:0773P-10/1/85)

C (AEP:NRC:0773S-6/29/87)

C (AEP:NRC:0773AB-10/15/88)

C (AEP:NRC:0773AC-6/20/88)

C (AEP:NRC:0773AG-10/16/89)

NRC ACTION NRC ACTION NRC ACTION>Please follow attached guidance for completing this column.*<The 16 items listed for GSI 75 all relate to actions derived from the generic implications of Salem ATWS events.Item numbers correspond to Generic Letter 83-28 action item numbers.

Attachment to AEP:NRC:1108C Page 2 of 6 GSI MPA No.75**(B076)75 (B085)TITLE Item 1.1-Post-Trip Review (Program Description and Procedure)

Item 1.2-Post-Trip Review Data and Information Capability APPLICABILITY All Plants All Plants STATUS*COMMENTS C (AEP:NRC:0838B-3/30/84)

NRC ACTION C (AEP:NRC:0838S-12/17/86)

NRC ACTION 75 (B077)Item 2.1-Equipment Classification and Vendor Interface (Reactor Trip System Components)

All Plants C (AEP:NRC:0838H-4/10/85)

SERs 3/27/87 4/2/87 75 (B086)75 (L003)75 (B078)75 (B079)75 (B087)Item 2.2.1-Equipment Classification for Safety-Related Components Item 2.2.2-Vendor Interface for Safety-Related Components Items 3.1.1&3.1.2-Post-Maintenance Testing (Reactor Trip System Components)

Item 3.1.3 Post-Maintenance Testing-Changes to Test Requirements (Reactor Trip System Components)

Items 3.2.1&3.2.2 Post-Maintenance Testing (All Other Safety-Related Components)

All Plants All Plants All Plants All Plants All Plants C (AEP:NRC:0838B-3/30/84)

SER C (AEP:NRC:0838W-12/19/86) 8/13/87 C (AEP:NRC:0838U-1/5/86)

NRC C (AEP:NRC:0838AB-6/16/87)

ACTION[AEP:NRC:0838AH has been initiated to answer GL 90-03 on the same subject]C (AEP:NRC:08380-8/20/85)

SER 6/27/85 C (AEP:NRC:08380-8/20/85)

SER 5/20/86 C (AEP:NRC:0838B-3/30/84)

SER C (AEP:NRC:0838K-4/12/87)

-4/27/87 Attachment to AEP:NRC:1108C Page 3 of 6 GSI MPA No.75 (B088)75 (B080)75 (B081)TITLE Item 3.2.3 Post-Maintenance Testing Changes to Test Requirements (All Other Safety-Related Components)

Item 4.1-Reactor Trip System Reliability (Vendor-Related Modifications)

Items 4.2.1&4.2.2-Reactor Trip System Reliability

-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)APPLICABILITY All Plants All Plants All PWRs STATUS*C (AEP:NRC:0838H-4/10/85)

C (AEP:NRC:0838P-12/9/85)

C (AEP:NRC:08380-8/20/85)

C (AEP:NRC:0838A-11/4/83)

C (AEP:NRC:0838G-3/29/85)

C (AEP:NRC:0838Q-4/22/86)

C (AEP:NRC:0838X-5/5/87)

COMMENTS SER 5/20/86 SER 6/27/85 SER 5/23/85 NRC ACTION[ITEMS 4.2.3&4.2.4]75 (B082)Item 4.3-Reactor Trip System Reliability

-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)All W and B&W Plants C (AEP:NRC:0838E-12/21/84 NRC ACTION 75 (B090)75 (B091)Item 4.3-Reactor Trip System Reliability

-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)Item 4.4-Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)All W and B&W Plants All B&W Plants C (AEP:NRC:0895B-'5/10/85)

C (AEP:NRC:0895E-6/20/85)

NA T/S AMEND.Ul¹86 U2¹72 Attachment to AEP:NRC:1108C Page 4 of 6 GSI MPA No.75 (B092)TITLE Item 4.5.1-Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)APPLICABILITY All Plants STATUS*C (AEP:NRC:0838A-11/4/83)

C (AEP:NRC:0838D-10/24/85)

C (AEP:NRC:0838Q-8/20/85)

C (AEP:NRC:0838V-11/7/86)

C (AEP:NRC:0838Z-6/25/87)

C (AEP:NRC:0838AA-10/28/87)

C (AEP:NRC:0838AD-12/18/87 C (AEP:NRC:0838AE-3/22/88)

C (AEP:NRC:0838AF-5/2/88)

COMMENTS SER 6/27/85 NRC IEIR 50-316/316; 89032, 89032[THESE SUBMITTALS ALSO CLOSE OUR RESPONSIBLITY UNDER 10CFR50.62, ISSUED ON THE SAME SUBJECT]75 (B093)86 (B084)93 (B098)Items 4.5.2&4.5.3 Reactor Trip System Reliability

-Test Alternatives and Intervals (System Functional Testing)Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps All Plants All BWRs All PWRs C (AEP:NRC:0838A-11/4/83)

C (AEP:NRC:0838H-4/10/85)

NA C (AEP:NRC:1047-5/31/88)

SERs 3/3/87 8/16/89 SERs 2/17/88 7/6/88 99 (L817)RCS/RHR Suction Line Valve All PWRs Interlock on PWRs C (AEP:NRC:1033-11/20/87)

C (AEP:NRC:1033A-10/21/87)

C (AEP:NRC:1033B-1/9/89)

SER 5/21/90 124 Auxiliary Feedwater System Reliability AN0-1&2, Rancho NA Seco, Prairie Island 1&2, Crystal River-3 Ft.Calhoun Attachment to AEP:NRC:1108C Page 5 of 6 GSI MPA No.A-13 (B017)A-13 (B022)TITLE Snubber Operability Assurance-Hydraulic Snubbers Snubber Operability Assurance-Mechanical Snubbers APPLICABILITY All Plants All Plants STATUS*AEP Ltrs.3/22&8/7/77 C (AEP:NRC:0504-11/11/81)

C (AEP:NRC:0931-8/19/86)

NA-No Mechanical Snubbers in Safety-Related Systems COMMENTS T/S AMEND Ul¹20-8/5/77 Ul¹104 U2¹91 4/13/87 A-16 (D012)A-35 (B023)Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems Oyster Creek&NMP-1 All Plants NA AEP Ltr.6/22/77 C (AEP:NRC:0268-12/17/79)

C (AEP:NRC:0313-2/22/80)

C (AEP:NRC:0268B-5/28/80 C (AEP:NRC:0591-1/22/82)

C (AEP:NRC:1063-11/29/88)

T/S AMENDS Ul¹39-7/25/80 U2-7/10/80 SER 9/10/80 6/1/81 T/S AMENDS Ul¹76 U2¹57 11/22/83 B-10 Behavior of BWR Mark III Containments All BWR Mark III NA Plants B-36 Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems All Plants with NA OL Applications After 4/1/80

Attachment to AEP:NRC:1108C Page 6 of 6 GSI MPA No.B-63 (B045)TITLE Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary APPLICABILITY All Plants STATUS*C (AEP:NRC:0560-2/23/80)

COMMENTS T/S UN-NUMBERED ORDER DATED 4/20/81