ML20005F329
| ML20005F329 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/03/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-89-002, IEB-89-2, NUDOCS 9001160185 | |
| Download: ML20005F329 (4) | |
Text
T ver icy Power sot 60n p ;
snippinoport. rA nonaos CL*lE"L o,n c
January 3, 1990 V
U. S. Nuclear Reguletory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 and No. 2 i
BV-1 Docket No. 50-334, License No. DPR-66 l
BV-2 Docket No. 50-412, License No. NPF-73 NRC Bulletin 89-02 Gentlemen:
Attached is our response to NRC Bulletin 89-02
" Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Interval Prelcaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves ofL Similar Design".
This provides the status of actions taken to meet the requirements of the Bulletin.
If you have any questions concerning this response, please contact my office.
Very truly yours, 64
. D. Sieber Vice President Nuclear Group cc:
Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Mr. R. Saunders (VEPCO) 1 9001160185 900103 PDR ADOCK 05000334 I (
0 PDC
~
t.
,$L u
COMMONWEALTH OF PENNSYLVANIA) l
)
ss:
COUNTY OF BEAVER
)
i
-r Afb f
on this O
day of Il A'RA4/2#
, 1990, before me, y llMM.
1M, 4 -,
a Notary Public n and for said t
Commonwealth and County, personally appeared J. D. Sieber, who being duly sworn, deposed, and said that (1) he is Vice' President - !!uclear of Duquestir, Light, (2) he is duly authorized to execute and file the forego),n Oubmittal on behalf of said Company, and (3) the statements
- set iedt; in the Submittal are true and correct to the best of his
.i knowledge, information and belief.
lUl 0 /'/h ?
rY Nata @ Seal Trn 2ek Notry Pubic y%y A Ba:yConmyse EEbro,Ociter Cotn 9tes Aug.16, ID93 j
Mornbur, PemsyMnia Ah d hw
1
'e DUQUESNE LIGHT COMPANY Nuclear Group Beaver Valley Power Station Units 1 & 2
~*
ATTACHMENT 1
Reolv to NRC Bulletin 89-02 l
Item I.A i
All licensees of operating reactors are requested to disassemble and inspect all safety-related Anchor Darling Model S350W swing check valves supplied with internal retaining block studs of ASTM 1
specification A193 Grade B6 Type 410 SS.
Licensees should review the design of other safety-related check valves to determine if similar designs and material selection to the Anchor Darling model S350W are used.
If so, such valves should be similarly inspected.
The inspection by disassembly should be performed as follows:
1.
If any of the internal bolting is to be reused, it should be inspected for cracks using surface inspection techniques (penetrant or magnetic particle).
Cracked bolting should be replaced and a
failure analysis performed including chemical analysis to confirm material type.
2.
If all suspect bolting is to be replaced with bolting of material and hardness specified in I.A.3, surface inspection and failure analysis of the old bolting may not be needed unless an unexpected failure mechanism is evident.
3.
Reused and new bolting should be hardness tested for a maximum Rockwell hardness value of Rc26.
Any internal preloaded bolting that does-not meet the hardness requirements should be replaced by bolts of the same material with a maximum Rockwell hardness of Rc26 or by an alternate material approved by the valve manufacturer.
Resoonse We have reviewed the design of all safety-related check valves at Beaver Valley Units 1 and 2 to identify any Anchor Darling Model S350W check valves and other check valves with internal preloaded components of Type 410 stainless steel.
Based on this
- review, we have identified six (6) Anchor Darling Model S350W check valves installed in the Beaver Valley Ur.it 1 (BV-1) safety injection system (ISI-48 through 1SI-53).
No other safety-related check valves were found with internal preloaded components of Type 410 stainless steel.
Y
l Att chment Reply to NRC Bulletin 89-02 1
+
Pate 2
+
i-I We have replaced the internal retaining block studs on all six of the above valves.
The material type of the new studs is ASTM-A564 Type 630-1100.
This replacement naterial was selected by and procured from the valve manufacturer (Anchor Darling).
Since this material is different from the original material (Type 410 stainless steel) the hardness testing requirement of Item I.A.3 is not applicable.
None of the old retaining block studs were found with visible cracking.
Since i
they were all replaced with new material, and no unexpected failure mechanism was found, no additional surface inspection or failure analysis was performed on the old studs as required by Item I.A.2.
This completes all actions required by NRC Bulletin 89-02 for Beaver Valley Units 1 and 2.