ML20004C788
| ML20004C788 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/27/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-81-443-000 10CFR-050.55E, PT21-81-443-000, SQRD-50-328-81, NUDOCS 8106050256 | |
| Download: ML20004C788 (3) | |
Text
l
^
"r e E33 EE ' s t e_EY.i t '--
- e..--2
.c : _
r-;z- >
,7 400 Chestnut Street Tower II h
3' May 27, 1981 SQ 50-328/81-17 m \\ &!
s f gf f
9\\
Mr. James P. O'Reilly, Director Office of Ins tien and Enforcement Q
U.S. Nuolear R 1 story Commission k,j JUj 0 4193Y %
Region II - Suite 100 u.s, D J @ aaer 101 Marietta Street Atlanta, Georgia 30 3
//
Dear Mr. O'Reilly 4
4 SEQUOYAH NUCLEAR PLANT UNIT 2 - EXCESSIVE PRESSURE DROPS ACROSS TE ERCW STRAINERS - SQRD-50-328/81 THIRD IlffERIM REPORT The subject deficiency was initially mported to NRC-0IE Inspector R
W.
Wright en January 28, 1981, in accordance with 10 CFR 50.55(e) as NCR SQN Mi:3 8006R1. Interia m ports were submitted en February 27 and April 27, 1981. Enclosed is our third interim mport. The enclosed mport provides justification for operation of unit 2 before final resolution of this NCR. We expect to submit our next report by August 24, 1981. We consider 10 CFR 21 applicable to this deficiency.
If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
l Very truly yours, TENNESSEE VALLET AIFTHORITT L. M. Mills, Manager Nuclear Regulation and Safety Enclosure
/
oo: Mr. Victor Stello, Director (Enclosure)V Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 5 11 6
6'(
8106050$$(p S
g -89 re g*-we-ywyw-m--m-y-e*+
--wgr-s-g ypww.y-7.+m-e=N a"-a--Tw = --me ns wen-NWWww w ' de9'e m v w wh
- r e-Ne--*--s-m-w me rew w w dar a wev e ees W * * *ar-m*-uWe w+>wwwer'%~Ne*+-e4 mm m
w n
2 ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 EXCESSIVE PRESSURE DROPS ACROSS THE ERCW STRAINERS SQRD-50-328/81 10 CFR 50.55(e)
THIRD INTERIM REPORT Description of Deficiency During preoperational testing at Sequoyah unit 1, it was discovered that pressure drops in excess of that designed for existed across the ERCW strainers.
S. P. Kinney Engineering in Carne'gie, Pennsylvania, supplied these strainers and predicted their pressure drop. The actual pressure drop, however, was much -larger than the stated value.
As a result, reduced flow rates could occur due to increased system resistance. The total system pressure drop for unit '1 has been determined to be acceptable; however, the acceptability of two-unit operation was not established.
Safety Implications The ERCW System is designed to supply a continuous flow of cooling water to various heat loads in systems and components necessary for l
plant safety. As a result of the excessive pressure drops across the l
strainers, flow rates less than the values claimed in the plant safety analysis could have resulted, which could have adversely affected the safety of the plant.
Interim Progress TVA has completed the preoperational flow balance test on the ERCW system, and the test results indicate that the system will perform satisfactorily as discussed in NCR SQNSWP8107, without replacing the strainers. TVA is continuing to evaluate the system to determine what modifications should be implemented to better enhance system performance, and has not yet decided if the strainers will be replaced.
l l
l
(
O 3
TENNESSEE VALLEY AUTHCR!TY cmc *rsccor r. r s s z t :.m 400 Chestnut Street Tower II p, 0 O c)
May 26, 1981 HTRD-50-518. -519, -520, -521/81-03 p \\ QI,4 s PBRD-50-553, -554/81-03.._
WA 8(X\\1')f S
.2.'Y*,1 Mr. J nes P. O'Reilly, Director Office of Inspection and Enforcement 5
JU 0 4 1981 > @
U.S. Nuclear Regulatory Cocriission ua,Mdua m R
~~
80*s*No's
,ff Region II - Suite 3100 b
101 Marietta Street Atlanta, Georgia 30303 g
Dear Ma. O'Reilly:
HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS - SGTS DESIGN DEFICIENCY -
HTRD-50-518, -519, -520, -521/81 PERD-50-553, -554/81-03 i
The subject deficiency was initially reported to NRC-OIE, Region II Inspector, McKenzie Thomas on December 12, 1980, as NCR's HTNANE3 8004 i
and PBNNEB 8004 The first interim report was submitted on January 9, 1981. In ecmplianer with paragraph 50.55(e) of 10 CFR Part 50, this letter constitutes the second interim report on the subject deficiency.
l TVA and GE/C. F. Braun are awaiting a proposed corrective action from CTI-Nuclear to provide adequate water drainage. The corrective action will be reviewed by TVA and at that time will be forwarded to GE for approval. We anticipate that the corrective act.ons will be reviewed and the results forwarded to you in the form of a final report by September 30, 1981.
We consider 10 CFR Part 21 applicable to this nonconfermance. TVA l
anticipates transmitting another interim report or final report if pessible, on or before September 30, 1981. If you have any questions, please call Jim Deser at FTS 857-2014 Very truly yours, l
TENNESSEE VALLEY AUTHORITY l
L. M. Mills, Manager Nuclear Regulation and Safety Mr. Victor Stello, Director l
cc:
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 gfli s*
h=/ 7
- - -