ML17328A978
| ML17328A978 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/28/1991 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1054A, IEB-89-002, IEB-89-2, NUDOCS 9104020028 | |
| Download: ML17328A978 (6) | |
Text
ACCELERATED/DISTRIBUTION 'DEMOITI'ATION SYSTEM
'EGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)
ACCESSION NBR:9104020028 DOC.DATE: 91/03/28 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 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATXON
~
I MURLEY,T. E.
Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC Bulletin 89-002. re Anchor-Darling swing check valves supplied w/internal retaining block studs of ASTM Spec A193,Grade B6,Type 410 stainless steel. Summary of insps of bolts/studs removed from subj valves encl.
DISTRIBUTION CODE:
IE32D
,COPIES RECEIVED:LTR ENCL I
SIZE:
NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T.
INTERNAL: AEOD/DOA NRR/DET/ECMB9H NRR/DOEA/OEAB11 NRR/DREP/PEPB9D NRR/EMCB/HERMAN NRRJ+
~B12
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GN3~. fEE 01 EXTERNAL: NRC PDR COPXES LTTR ENCL 1
0 1
1 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 RECIPXENT XD CODE/NAME PD3-1 PD AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DOEA/OGCB11 NRR/DST 8E2 NRR/MCLELLANI T NRR/ROOD,H RES/DSIR/EIB NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1.
1 1
1 1
1 1"
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,"
ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 20.
Indiana Michi~
Power Company One Summit Square
.P.O. Box 60 Fort Wayne, IN 46801 219 425 2111 INDlANA NlCHlGAN POWER AEP:NRC:1054A Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
RESPONSE
TO NRC BULLETIN NO. 89-02 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn: T.
E. Murley March 28, 1991
Dear Dr.- Murley:
In NRC Bulletin No. 89-02 dated July 19,
- 1989, the NRC requested licensees to disassemble and inspect all safety-related Anchor Darling Model S350W swing check valves supplied with internal retaining block studs of ASTM'Specification A193, Grade B6, Type 410 stainless steel.
Also, the design of safety-related check valves manufactured by companies other than Anchor Darling were to be reviewed to determine if similar designs and material selection had been used and, if so, to similarly inspect such valves.
These inspections by disassembly were to be performed at the next refueling outage or scheduled outage" of four weeks or longer beginning 90 days after the receipt of the bulletin (July 21, 1989 for Cook Nuclear Plane).
This action has been completed and we are hereby responding to NRC Bulletin 89-02.
We had previously submitted' voluntary report, (letter AEP:NRC:1054 dated October 28, 1988) concerning our initial findings of degradation of A193, Grade B6, Type 410 stainless steel retaining block studs in Anchor Darling Model S350W swing check valves installed in the emergency core cooling system in both units.
Briefly, the report stated that studs in 4 of the 12 Unit 1 check valves and 10 of the 12 Unit 2 check valves had been replaced with the new A193, Grade B8, Type 304 stainless steel stud material, in accordance with the manufacturer's recommendation.
Replacement of the studs in the remaining 10 Anchor Darling swing check valves tha't had 410 stainless steel studs was completed after receipt of metallurgical evaluations by Westinghouse and prior to the issuance of NRC Bulletin 89-02.
. 20402002S 910 2 F'DR ADOCK 05000w15 P'Fl>
Dr. T.
E. Murley AEP:NRC:1054A In complianc'e with the requirements of the bulletin, a data base was developed for the 502 safety-related check valves at Cook Nuclear Plant.
The original design and materials of these valves were also reviewed.
Forty-seven of the valves were determined'to have contained Type 410 stainless steel stud/bolt material.
These were the 24 Anchor Darling Model S350W valves.and 23 valves of similar design by other manufacturers, i.e.,
1 Crane-Aloyco, 20 Velan and 2
A&M valves.
As stated earlier, the bolting material replacement on the 24 Anchor Darling (12 in'ach unit) was completed prior to the receipt of NRC Bulletin 89-02.
A summary of inspection results and actions taken on the remaining 23 valves (11 in Unit 1 and 12 in Unit 2) is provided in the attached table.
All of these studs were also replaced with acceptable ASTM A193, Grade B8, Type 304 stainless steel studs during the 1990 refueling outages for Units 1
and 2.
We believe that the actions indicated above satisfy the requirements of NRC Bulletin 89-02.
We therefore consider this letter to complete our response to NRC Bulletin 89-02.
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, A
M. P. Alexich Vice President ldp Attachment cc:
D; H. Williams, Jr.
A. A. Blind J.
R. Padgett G. Charnoff A. B. Davis - Region III NRC Resident Inspector
- Bridgman NFEM Section Chief
Attachment 'to AEP:NRC:1054A Summary of Inspections of Check Valves '
Attachment to AEP:NRC:1054A Page 1
Summary of Inspections of Type 410 Stainless Steel Bolts/Studs Removed from Safet -Related Check Valves Unit 1 Valve 1-CS-523-1 Manufacturer Velan Inspection Method None Remarks (1)
Bolt/stud inadvertently
$iscarded after decontamination 1-CS-523-2 Velan None Bolt/stud inadvertently fiscarded after decontamination 1-CS-523-3 Velan None Bolt/stud inadvertently Pscarded after decontamination 1-CS-523-4 1-DF-108-C 1-DF-109-C 1-DF-114-A 1-DF-115-A 1-FV-153 Velan Velan Velan Velan Velan Velan None VT-1 VT-1 VT-1 VT-1 VT-1 Bolt/stud inadvertentl(2)iscarded after decontamination Acceptable (3)
Acceptable (3)
Acceptable (3)
Acceptable (3)
Acceptable.
It was not establislg) that the studs were Type 410 1-FW-160 Velan VT-1 Acceptable, It was not establislg) that the studs were Type 410 1-SI-148 Notes Crane-Aloyco None Bolt/stud inadvertentlygliscarded after decontamination (1)
All Type 410 stainless steel bolt/stud material from the above -11 valves.was discarded.
(2)
Check valve disassembly visual examination reports, filed as part of the ISI program, indicated no adverse conditions observed.
(3)
No indications of degradation were found during inspections, although some studs were damaged upon removal.
i~send VT - Visual examination
Attachment to AEP:NRC:1054A'age 2
Unit 2 Summary of Inspections of Type 410 Stainless Steel Bolts/Studs Removed from Safet -Related Check Valves (Continued) e Valve Inspection'anufacturer Method Remarks(
2-CS-523-1 Velan UT, Visual Acceptable, threads damage(.
inadvertently upon removal 2-CS-523-2 2-CS-523-3 2-CS-523-4 2-DF-114-C 2-DF-115-C 2-DF-108-A 2-DF-109-A 2-FW-153 Velan Velan Velan Velan Velan Velan Velan Velan None UT UT, Visual VT VT VT-1, PT VT-l,'T VT Bolt/stud inadvertently )iscarded after decontamination Acceptable (4)
Acceptable Acceptable (4)
Acceptable (4)
Acceptable (4)
Acceptable (4)
Acceptable.
It was not esca'gjshed that the studs were Type 410 2-FP-160 Velan VT-1 Acceptable.
It was not estab)shed that the studs were Type 410 2-CS-321 None Bolt/stud inadvertent)g discarded after decontamination 2-CS-321 (spare)
None Inspect)jy waived; valve never in service Notes (1)
All Type 410 stainless steel bolt/stud material from the above 12 valves was discarded.
(2)
Bolt was found to be 1/8" short.
(3)
Check valve disassembly visual examination reports, filed as part of the ISI program, indicated no adverse conditions observed.
(4)
No indications of degradation were found during inspection, although some studs were damaged upon removal.
~ie end VT - Visual Examination UT - Ultrasonic Testing PT - Dye Penetrant