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 R Document Control Branch (Document Control Desk)

SUBJECT:

Forwards response to Generic Ltr 90-04 re closeout of generic safety issues.

D DISTRIBUTXON CODE: A018D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Generic Ltr 90-04 re Status of Licensee Xmplementation of enerxc Saf 8 NOTES:

RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D GIITTER,J. 2 2 INTERNAL: CROCKER, L 9H3 1 1 EC 0 K10D4 1 1 D NUDOCS-ABSTRACT 1 1 EG FI 01 1 1 SCHOLLi R 13E4 1 1 S EXTERNAL: LPDR 1 1 NRC PDR D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR 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.

ol' 9006280322 90062 i PDR ADOCK 05000315 P PDC ti)

Dr. T. E. Murley 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. TITLE APPLICABILITY STATUS* COMMENTS 40 (B065) Safety Concerns Associated All BWRs NA With Pipe Breaks in the BWR Scram System 41 (B058) BWR Scram Discharge Volume All BWRs Systems 43 (B107) Reliability of Air Systems All Plants C (AEP:NRC:1075-2/24/89) NRC C (AEP:NRC:1075A-3/23/89) ACTION 51 (L913) Improving the Reliability All Plants C (AEP:NRC:0553-5/28/81) NRC of Open-Cycle Service Water C (AEP:NRC:1104-1/25/90) ACTION Systems 67.3.3 (A017) Improved Accident Monitoring All Plants C (AEP:NRC:0773-4/15/83) NRC C (AEP:NRC:0773J-2/28/85) ACTION 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)

>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. TITLE APPLICABILITY STATUS* COMMENTS 75** (B076) Item 1.1 - Post-Trip Review All Plants C (AEP:NRC:0838B-3/30/84) NRC (Program Description and ACTION Procedure) 75 (B085) Item 1.2 - Post-Trip Review All Plants C (AEP:NRC:0838S-12/17/86) NRC Data and Information ACTION Capability 75 (B077) Item 2.1 - Equipment All Plants C (AEP:NRC:0838H-4/10/85) SERs Classification and Vendor 3/27/87 Interface (Reactor Trip 4/2/87 System Components) 75 (B086) Item 2.2.1 - Equipment All Plants C (AEP:NRC:0838B-3/30/84) SER Classification for C (AEP:NRC:0838W-12/19/86) 8/13/87 Safety-Related Components 75 (L003) Item 2.2.2 - Vendor All Plants C (AEP:NRC:0838U-1/5/86) NRC Interface for C (AEP:NRC:0838AB-6/16/87) ACTION Safety-Related Components [AEP:NRC:0838AH has been initiated to answer GL 90-03 on the same subject]

75 (B078) Items 3.1.1 & 3.1.2- All Plants C (AEP:NRC:08380-8/20/85) SER Post-Maintenance Testing 6/27/85 (Reactor Trip System Components) 75 (B079) Item 3.1.3 All Plants C (AEP:NRC:08380-8/20/85) SER Post-Maintenance Testing 5/20/86

- Changes to Test Requirements (Reactor Trip System Components) 75 (B087) Items 3.2.1 & 3.2.2 All Plants C (AEP:NRC:0838B-3/30/84) SER Post-Maintenance Testing C (AEP:NRC:0838K-4/12/87) - 4/27/87 (All Other Safety-Related Components)

Attachment to AEP:NRC:1108C Page 3 of 6 GSI MPA No. TITLE APPLICABILITY STATUS* COMMENTS 75 (B088) Item 3.2.3 All Plants C (AEP:NRC:0838H-4/10/85) SER Post-Maintenance Testing C (AEP:NRC:0838P-12/9/85) 5/20/86 Changes to Test Requirements (All Other Safety-Related Components) 75 (B080) Item 4.1 - Reactor Trip All Plants C (AEP:NRC:08380-8/20/85) SER System Reliability 6/27/85 (Vendor-Related Modifications) 75 (B081) Items 4.2.1 & 4.2.2- All PWRs C (AEP:NRC:0838A-11/4/83) SER Reactor Trip System C (AEP:NRC:0838G-3/29/85) 5/23/85 Reliability - Maintenance and Testing (Preventative C (AEP:NRC:0838Q-4/22/86) NRC Maintenance and Surveillance C (AEP:NRC:0838X-5/5/87) ACTION Program for Reactor Trip [ITEMS Breakers) 4.2.3 &

4.2.4]

75 (B082) Item 4.3 - Reactor Trip All W and B&W C (AEP:NRC:0838E-12/21/84 NRC System Reliability - Design Plants ACTION Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor Trip All W and B&W C (AEP:NRC:0895B-'5/10/85) T/S AMEND.

System Reliability - Tech Plants C (AEP:NRC:0895E-6/20/85) Ul ¹86 Spec Changes (Automatic U2 ¹72 Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B091) Item 4.4 - Reactor Trip All B&W Plants NA System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

Attachment to AEP:NRC:1108C Page 4 of 6 GSI MPA No. TITLE APPLICABILITY STATUS* COMMENTS 75 (B092) Item 4.5.1 - Reactor Trip All Plants C (AEP:NRC:0838A-11/4/83) SER System Reliability- C (AEP:NRC:0838D-10/24/85) 6/27/85 Diverse Trip Features C (AEP:NRC:0838Q-8/20/85) NRC (System Functional Testing) C (AEP:NRC:0838V-11/7/86) IEIR C (AEP:NRC:0838Z-6/25/87) 50-316/316; C (AEP:NRC:0838AA-10/28/87) 89032, C (AEP:NRC:0838AD-12/18/87 89032 C (AEP:NRC:0838AE-3/22/88)

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

[THESE SUBMITTALS ALSO CLOSE OUR RESPONSIBLITY UNDER 10CFR50.62, ISSUED ON THE SAME SUBJECT]

75 (B093) Items 4.5.2 & 4.5.3 All Plants C (AEP:NRC:0838A-11/4/83) SERs Reactor Trip System C (AEP:NRC:0838H-4/10/85) 3/3/87 Reliability - Test 8/16/89 Alternatives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for Dealing All BWRs NA with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of Auxiliary All PWRs C (AEP:NRC:1047-5/31/88) SERs Feedwater Pumps 2/17/88 7/6/88 99 (L817) RCS/RHR Suction Line Valve All PWRs C (AEP:NRC:1033-11/20/87) SER Interlock on PWRs C (AEP:NRC:1033A-10/21/87) 5/21/90 C (AEP:NRC:1033B-1/9/89) 124 Auxiliary Feedwater System AN0-1&2, Rancho NA Reliability Seco, Prairie Island 1&2, Crystal River-3 Ft. Calhoun

Attachment to AEP:NRC:1108C Page 5 of 6 GSI MPA No. TITLE APPLICABILITY STATUS* COMMENTS A-13 (B017) Snubber Operability All Plants AEP Ltrs. 3/22 & 8/7/77 T/S AMEND Assurance - Hydraulic C (AEP:NRC:0504-11/11/81) Ul¹20-8/5/77 Snubbers C (AEP:NRC:0931-8/19/86)

Ul¹104 U2¹91 4/13/87 A-13 (B022) Snubber Operability All Plants NA-No Mechanical Snubbers in Assurance - Mechanical Safety-Related Systems Snubbers A-16 (D012) Steam Effects on BWR Core Oyster Creek NA Spray Distribution & NMP-1 A-35 (B023) Adequacy of Offsite Power All Plants AEP Ltr. 6/22/77 T/S AMENDS Systems C (AEP:NRC:0268-12/17/79) Ul¹39-7/25/80 C (AEP:NRC:0313-2/22/80) U2-7/10/80 C (AEP:NRC:0268B-5/28/80 SER C (AEP:NRC:0591-1/22/82) 9/10/80 C (AEP:NRC:1063-11/29/88) 6/1/81 T/S AMENDS Ul¹76 U2¹57 11/22/83 B-10 Behavior of BWR Mark III All BWR Mark III NA Containments Plants B-36 Develop Design, Testing and All Plants with NA Maintenance Criteria for OL Applications Atmosphere Cleanup System After 4/1/80 Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems

Attachment to AEP:NRC:1108C Page 6 of 6 GSI MPA No. TITLE APPLICABILITY STATUS* COMMENTS B-63 (B045) Isolation of Low Pressure All Plants C (AEP:NRC:0560-2/23/80) T/S UN-Systems Connected to the NUMBERED Reactor Coolant System ORDER DATED Pressure Boundary 4/20/81