ML20096H012
| ML20096H012 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/05/1984 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| EF2-72769, NUDOCS 8409110231 | |
| Download: ML20096H012 (9) | |
Text
7 Cayne H. Jens eENtons Detrol [
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September 5, 1984 EF2-72769 Director of Nuclear. Reactor Regulation Attention:
.Mr.
B. J. Youngblood, Chief
' Licensing Branch No.1 Division of. Licensing U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Youngblood:
' Reference (1):
Fermi 2 NRC Docket No. 50-341
-(2):
Detroit Edison to NRC Letter, " Submittal of Revision 2 of Report on Inservice Testing of Pumps and Valves", EF2-65368, Oct. 4, 1983
Subject:
Inservice Testing of Pumps and Valves Reference (2) submitted Revision 2 to the Fermi 2 Report on Inservice Testing of Pumps and Valves.
The letter also contained responses to open items pending from the May 17-18
' meeting'between' Detroit Edison and your staff's conJultants
.from-EG & G, Idaho.
Attached to this letter are the resolutions to the remaining open items pending from
-Reference (2).
In addition,'. based on conversations with Mr. Bob Kirkwood of the Mechanical Engineering Branch, Detroit Edison commits to make the following modifications to its Inservice Testing
. Program for Pumps and Valves (Reference 2):
1.
Relief Request PR Diesel Fuel Oil Transfer Pump This relief request will be deleted.
Detroit Edison will provide for quarterly measurement of reference values as required by Article IWP of Section XI of the Code.
0 B409110231 840905 gg i
PDR ADOCK 05000 P
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Mr. B.J. Youngblood September 5, 1984
- EF2-72769 Page 2 2.:
Relief Request VR All Solenoid Operated Valves
.This relief request will be changed to indicate that
'two seconds instead of'five seconds will be used to define short stroke' times.
It.is our understanding that,this is. consistent with the NRC position on this
~
subject..
3.
Relief Request -VR Control Rod Drive This relief ~ request will be deleted and replaced with new relief requests VR-43 and VR-44 (see item B.2 in the attachment).
4.
Relief Request VR Combustible Gas Control
'This relief request will be deleted.
5.
Relief Request VR Nuclear Boiler As with item 2 above, this-relief request will be changed to indicate that 2 seconds.versus 5 seconds will~be used as the limiting time to demonstrate r
adequate' valve operability.
Your concurrence with the above modifications should close all remaining open items relative to the Fermi 2 Inservice Test Program for Pumps and Valves.
After your concurrence, Revision 3 to the Program will be issued to account for the above changes and other minor revisions due to design and program evolution.
Detroit ' Edison remains concerned, however, that until full implementation of this program is achieved under operating conditions, all' deficiencies associated with its implemen-tation may not have been identified.
Therefore, Edison reserves the right to request from the Commission those program revisions that may be authorized by the Commission's regulations.
Mr. B. J.-Youngblood September 5, 1984
-EF2-72769
'Page 3 If-you should have any further questions, please contact Mr. O.! Keener Earle at-(313) 586-4211.
Sincerely,
\\&
cc s - Mr.
P. M.-Byron
- Mr. M. D. Lynch
- Mr.
R. Kirkwood*
USNRC, Document Control Desk
- Washington, D.C.-
20555
- With attachments I
... - ~....
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Mr.LB..J..Youngblood 9
September.'5, 1984 EF2-72769'
' Page:4 bcc: F. E..Agosti*
L.nP.1 Bregni' W. F. Colbert*
O. - :K., Earle-W. R. Holland R. S.-Lenart*
E. Lusis P. A. Marquardt T. D.. Phillips*-
.B.
J.
Sheffel*
'A. A..Shoudy
<H. Tauber G. M. Trahey A. E. Wegele Approval Control
- O. K.~Earle (Bethesda Office)*
M. S.'Rager*
24th Floor Reading Room NRR Chron File *
- With Attachments
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Attacha nt 1
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. Responses < to :IST Program Open Items
- From-DECO Letter EF2-65368, Oct. 4', 1983 J'
iA i ' Responses ' to' Open Items ' from Attachment' A to EF2-65368
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1.
' :Feedwater System-1 Open Item:
The installed excess flow check valves V13-2392 and V13-2393lare in the.IST program,-
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'but do not appear as' excess flow check valves on 6M721-2023, Revision N.
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Response
The current revision of'6M721-2023 shows
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V13-2392 and V13-2393 as excess flow check
-valve s.
2.
61721-2145-66 Traversing In-Core Probe System Open Item:
_The check valve C51-J009 does not appear on
- Revision A of-61721-2145-66.-_ Exactly what-
~
' drawinr, _C51-J009 will. appear on has yet to be decided.
F
,s JResponse:
Drswing 61721-2837-6 has the best view of the TIP System and will be used in place of 61721-2145-66. 61721-2837-6 will be changed 3R to include the check valve.-
3.
6M721-2081 Control Rod Drive Hydraulic System
.Open Item:
' Valve C11-144Lat coordinate A-B should be valve C11-114, as shown in the IST program.?
Response
The curront revision of-6M721-2081 shows C11-114.
4.
16M721-2083 Residual Heat Removal System, Division II j
Open Item:
Valve,V13-7688 has been installed, however, it' does not appear in Revision M of 6M721-2083.. Valve V13-7688 is on-a 1" bypass line around the containment isolation Valve E11-F0505 (V8-2164). Valve V13-7688 allows the pressure to'be equalized,across E11-F0508 so that this testable check valve can be-exercised during cold shutdown.
Open Item:'
Valve V8-3874 has also been installed and is 4
not shown on Revision M of 6M721-2083. This, y
~
valve is on a 3/4" bypass line around the' containment isolation' valve E11-F608
'(V8-3407). This bypass line allows heated water trapped inside the RHR shutdown cooling
~
. suction line to be relieved into the reactor 2-vessel.
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s Pege 2 of 5
' Responses to IST Program Open Items Frgy DECO Letter EF2-65368, Oct. 4, 1983 A.
Responses to Open Items from Attachment A to EF2-65368 (Cont'd)
Response
Valves V13-7688 and V8-3874 are shown on the -
current revision of 6M721-2083.
'5.-
6M721-2084' Residual Heat Removal System, Division I.
-Open Item:.
Valve V13-7687 has' been installed but does not appear on Revision P of 6M721-2084.
Valve V13-7687 is on a 1" bypass line around the containment' isolation valve Ell-F050A
-(V8-2163). Valve V13-7687 allows the pres-sure to be equalized across Ell-F050A so that this testable check valve can be exercised during cold shutdown.
Response
The current revision oi 6M721-2084 shows
.V13-7687.
6.
6M721-5449, control Rod Drive' Hydraulic System - Part 2 Open Item:
Relief Valve Cll-F012 (V22-2027) originally was located on F&ID 6M721-2081, Revsion 1..
s It should appear with the scram discharge.
volume on 6M721-5449, however, Cll-F012 is not shown on Revision 0 of 6M721-5449.
Response
Valve Cll-F012 has been deleted from the' system. This valve will be deleted from the IST program.
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Attschment 1 Psga 3 of 5 Responses to IST: Program Open Items-
' From DECO Letter EF2-65368, ' Oct. 4, 1983
.B.
Responses to'Open Items from' Attachment B to EF2-65368 1.
H.1 Core Spray (6M721-2034).
Open Item:
Detroit Edison is investigating the removal of the valve internals from check valvec E21-F017B (V8-3181) which are-lines that lead
~
' from relief valves to the suppression pool, since these' valves do not perform a safety related function..Because there is a high probability that the valve internals will be removed..these check valves along with Relief Request.VR-19 have been deleted from the program. If removal of-_the valve internals is not possible, valves E21-F017A and E21-F017B will be put back into the' program and appropriate testing procedures will be developed.
Reponse:
The check valves leading from the relief
. valves to the suppression pool do not perform a safety related function and the valve internals. have been removed. Therefore,
.these valves will not be included in the program.
2.
M.1 Control Rod Drive Hydraulic System (6h721-2081)-
.Open Item:
An appropriate testing method and frequency for C11-115 and C11-138 will ' be submitted in
-October, 1983.
Response
The attached new relief requests (VR-43 and VR-44) present technically sound methods for' testing C11-115 and C11-138. - These relief
.requeste replace VR-12.
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Attachmsnt 1 Pzga 4 of 5 Relief Request VR-43 SYSTEM:
Control Rod Drive COMPONENT:
- C11-115 (Typical of = 185 valves)
CATECORY:
C FUNCTION:
For a scram to occur, C11-115 must close to prevent back flow into the charging water header.
TEST REQUIREMENT:
Exercise check valve in the close direction every three months (CT-1).
BASIS FOR RELIEF: 1 During normal operation, the drive water pumps
-supply drive water and cooling water to the control rods. In order to test C11-115 in the close position,.the drive water pumps must be shut
?down, thus interrupting the supply of cooling water to the control rods. Interruption of cooling water would cause excessive temperature in the control rods.
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ALTERNATE TESTING: The check valve will be exercised once every 18 months during the_CRD accumulator system integrity test. ' Normal water level in the accumulator verifies that the check valve opens properly.
E-Page 5 of 5 Relief Request VR-44 SYSTEM:
Control Rod Drive COMPONENT:
C11-138 (Typical of 185 valves)
CATEGORY:
C FUNCTION:
For a scram to occur, C11-138, must close to prevent back flow into the cooling water header.
TEST REQUIREMENT:
Exercise check valve in the close position every three months (CT-1).
BASIS FOR RELIEF:
Due to system configuration, direct verification that the check valve closes is not practical.
Indirect verification of valve closure is provided each time a control rod is moved.
If C11-138 fails to close properly, the rod will fail to insert because drive water at a pressure between 90 psi and 260 psi above reactor pressure will flow into the cooling water header which operates at approximately 20 psi above reactor pressure.
ALTERNATE TESTING: When the reactor is in either Operation Condition 1 or 2 and the thermal power is above the preset power level of the rod worth minimizer and the rod sequence control system, all operable and withdrawn control rods will be moved at least one notch once per seven days per Technical Specification paragraph 4.1.3.1.2.
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