ML20072H277
| ML20072H277 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 06/07/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-83-03, IEB-83-3, NUDOCS 8306290388 | |
| Download: ML20072H277 (2) | |
Text
%
TENNESSEE VALLEY AUTHOSITWC PEGION :I CH ATTANOOGA. TENNESSEE 37 400 Chestnut Street Tower II June 7, SkdVN 13 Pil 10 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
OFFICE OF INSPECTION AND EUFORCEMENT BULLETIN 83 SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 50-327 AND 50-328' In response to R. C. DeYoung's letter dated March 10, 1983 concerning IE Bulletin No. 83-03: Check Valve Failures in Raw Water Cooling Systems of Diesel Generators, we are providing the enclosed response. The enclosure addresses items 1, 2, 3, and 4 and completes our response to the Bulletin for the Sequoyah Nuclear Plant.
If you have any questions, please get in touch with K. P. Parr at FTS 858-2688.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, unager Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 8306290388 830607 gDRADOCK 05000327 PDR An Equal Opportunity Employer l
ENCLOSURE
/
RESPONSE TO NRC IE BULLETIN 83-03 Chick Vciva.Fe11ur:0 in Raw Ca@ ling Watcr Systems of' Diesel Generators Sequoyah Nuclear Plant has reviewed its ASME Section XI Pump and Valve Inservice Test (IST) P,rogram and veri f ied that it includes all emergency raw cooling water (ERCU) check valves in the diesel generator cooling water flow path from intake to discharge. The following is a 1ist of valves identified.
ERCW Supply to Diesels ERCW Discharge from Diesels Valve No.
Size Drawinc.b.
Valve L.
l:i ze Drawing No.
1-67-508A 6"
47W845-1 L-6 7-312A H"
47W845-1 2-67-508A 6"
47W845-1 2-67 'il 2A 8"
47W845-1 1-67-508B 6"
47W845-1 1-67-512B 8"
47W845-1 2-67-508B 6"
47W845-1 2-67-512B 8"
47W845-1 1-67-513A*
6" 47W845-1 1-67-517A 8"
47W845-1 2-67-513A*
6" 47W845-1 2-67-517A 8"
47W845-1 1-67-513B*
6" 47W845-1 1-67-517B 8"
47W845-1 2-67-513B*
6" 47W845-1 2-67-517B 8"
47W845-1 ERCW Pump Discharge Valve No.
Size Drawing No,._
67-723A.
24" 47W845-5 67-723B 24" 47W845-5 67-724A 24" 47W845-5 67-724B 24" 47W845-5 6 7-74 3A 24" 47W845-5 67-743B 24" 47W845-5 67-744A 24" 4 7W84 5-5 67-744B 24" 47W845-5
- These four additional ERCW diesel supply check valves are not presently tested in the ASME Section X1 Pump and Valve IST Program.
They are categorized C paccive (r.c testing raqo.i n"l) "alvos since they do not normally supply water
{
to the diesel generator, llowever, since they may dislodge and block flow, I
they have been added in accordance with the requirements of this bulletin.
Verification of the integrity of the ERCW pump discharge check valves is accomplished using surveillance instruction (SI) 45.1, " Essential-Raw
(
Coolant Water Pumps."
This instruction is presently being performed on a l
quarterly basis and uses both a forward f Low and reverse flow test to ensure check valve integrity.
The ERCW supply and discharge check valves in the normal flowpath to the i
diesel generators are stroked fully open at least once per qu:.rter during testing of the diesel >;enerators. To meet the requirements of this bulletin, the ERCW supply and discharge check valves to the diesel generators will be disassembled and visually inspected on a basis of at least once every 24 months.
l l
l 1 l
M
'eJ= :
-re-.,
.m e se L
ENCLOSURE RESPONSE TO NRC IE BULLETIN 83-03 (Continued)
Surveillance instruction (SI) 166.37, " Inspect ion of Dieset Generator ERCU Supply Check Valves," and 81-166. 38, " Inspect ion of Diesel Cencrator ERCW Discharge Valves," will he used to perform this inspection with the initial inspection to be completed prior to startup af ter refueling cycle 1 on unit 2.
Sequoyah Nuclear Plant has Daniels Industries. Incorporated Model 1601-AC check valves installed in the supply and discharge lines to the diesel generator, and the CRCW pump discharge valves are manufactured by Anderson Creenwood (series CVlA). The plant has not experienced any failures on these valves.
4 9
i
-- - 2.-
- - - -