ML20063F307
| ML20063F307 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/20/1982 |
| From: | Swartz E COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| REF-SSINS-6820 4816N, IEB-80-06, IEB-80-6, NUDOCS 8208310212 | |
| Download: ML20063F307 (5) | |
Text
'O AH?A N Commonw; lth Edison ongffrst, Nabonal Plaza Chicago, libnois 7 7 Address Reply to Post Office Box 767 gj Chicago. lHinois 60690 Augus t 20, 1982 Mr. Jame s G.
Keppler, Regional Adminis trator Directorate o f Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Dresden Station Units 2 and 3 IE Bulletin 80-06 ESF Reset Control Final Response NRC Docket No. 50-237/249 Re ferences (a):
D. L.
Peoples letter to J.
G.
Keppler dated Jun e 10, 1980 (b):
R.F.
Janecek letter to T.
A.
Ippolito dated Ma rch 20, 1981 (c):
D.
M. Crutchfield letter to L.
O. De1 George dated Ma rch 29, 1982
Dear Mr. Keppler:
Re ferences (a) and (b) provided the response to the subject Bulletin for our Dresden Station.
Subsequently, Reference (c) provided the Commonwealth Edison Company with the NRC S ta ff Sa fety Evaluation Report concluding that our response satisfied the concerns o f the subject bulletin.
l Re ference (c) indicated that "a post implementation review of the installation and testing of the proposed modifications will be carried out by the NRC to confirm the satisfactory completion of this topic".
The Attachment to this letter is provided to document the actions we have taken and is considered to be the final response to IE Bulletin 80-06 concerning Dresden Station.
To the best o f my knowledge and belief, the s tatements contained in the Attachment are true and correct.
In some respects these statements are not based on my personal knowledge, but upon irformation furnished by other Commonwealth Edison employees.
Su ch information has been reviewed in accordance with Company practice I
and I believe it to be reliable.
//E
'I 8208310212 820820 PDR ADOCK 05000237 AU6 2 4 1932 l
G PDR
. Please address any questions that you or your staf f may have concerning this matter to this of fice.
Very truly yours, Douglas Swa rk E.
tOclea r Licensing Adminis trator Attachment cc:
NHC Of fice o f Inspection and En forcement Division of Reactor Operations Washington, DC 20555 J. D.
Hegner - ORB 2 P.
W. O'Connor - ORB 5 RIII Inspector - Dresden 4816N
COMMONWEALTH EDISON COMPANY ORESDEN STATION UNITS 2 and 3 l
FINAL RESPONSE TO IE BULLETIN 80-06
" Engineered Sa fety Features Reset Controls" l
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The Engineered Safety Feature systems that were found to be in conflict with IE Bulletin 80-06 at Dresden Station Units 2 and 3 were modified to satisfy the requirements o f IE Bulletin 80-06.
The systems that were modified are as follows:
1.
HPCI System Revised HPCI drain-valves 2301-64, 65, 29, and 30 to remain closed, valve 2301-28 remain open and auxiliary oil pump to continue running upon reset of actuation signal.
Documentation of the design and preoperational tests are provided per Modification M12-2(3)-80-50.
The functional test of modification on Unit 2 was performed April 29, 1981.
Special Procedure 82-4-41 was used for Unit 3 preoperational test on April 21, 1982.
2.
Isolation Condenser Modified the isolation control switches and Group V isolation circuitry o f valves 1301-1, 2, and 4 to remain closed upon reset o f actuation signal.
The information relating to design and tests are provided per Modification M12 - 2( 3 ) -8 0 -33.
The functional test of the Unit 2 modification was performed April 27, 1981, and Uni t 3 functional test on December 23, 1980.
3.
PCIS Modified Groups 1 and 2 circuitry so all valves remain closed when isolation is reset.
DOS-1600-7 Revision 6 was i
performed April 21, 1982 for Unit 3 and all valves operated l
as required.
Unit 2 modification is incomplete due to unavailability of control material and is scheduled to be completed in the next outage.
The available information is provided per Modification M12-2(3)-79-52.
4.
TIP Revised the TIP drive system circuitry to satisfy IE Bulletin 80-06 and 79-08 requirements.
The modification ensures that TIP's will continue to withdraw even a f ter Group I isolation signal.
Information is provided per Modi fication M12-2(3)-80-51.
The functional tests were performed April 19, 1982 fo r Uni t 3 and Ma y 11,1982 for Uni t 2.
The testing of the modifications listed above was done af ter installation and specifically demonstrated the equipment will not reposition from its emergency position with initial signal reset.
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' The following ACAD valves were tested by means of Special Procedure 82-4-49:
2599-1A, 18, 2A, 28, 3A, 3B, 4A, 48, 5A, and 58.
It was verified that the ACAD valve operation was not consistent with IE Bulletin 80-06 in that if any isolation was not reset and the injection valves 2599-1A, 18, 2 A, 2B, 3A, and 38 are originally in an open position, they would reopen without direct action of an operator as the drywell pressure fell.
Howeve r, the ACAD system is designed for post-LOC A use and the system is j
activated by the operator and watched continually by the operator during system operation.
Also, as can be seen on Piping and Instrument Diagram M-7C7, these valves are normally in a closed position and would not ce a f fected by such an isolation reset scenario.
l The Containment Atmospheric Monitoring (CAM) valves 24-9 9-1 A, 1B, 2A, 28, 3 A, 38, 4A and 4B were also found to be o f 4
similar design, although they are not part o f any isolation group.
These valves are normally closed except under post-LOCA condition.
It is our belief that an IE Bulletin 80-06 modification is not needed for these valves.
Most of the modifications and testing was done during the 1981 and 1982 refueling outages.
The incomplete modification on the Unit 2 PCIS is scheduled for completion during the next Unit 2 refueling outage.
The preoperational test on PCIS will be performed by DOS 1600-7 a f ter the completion o f Modification M12-2-79-52, as was done on Unit 3.
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