ML20101L557
| ML20101L557 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/27/1984 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, ULNRC-1002, NUDOCS 8501020270 | |
| Download: ML20101L557 (5) | |
Text
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1901 Grotiot Street St Louis December 27, 1984 Donald F.Schnell Vice Pres %$ent Mr. Harold R. Denton,' Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
ULNRC-1002 DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 GENERIC LETTER 83-28
References:
1.
ULNRC-829 dated 5-21-84, same subject 2.
ULNRC-.763 dated 3-12-84, same subject 3.
ULNRC-687 dated 11-18-83, same subject 4.
Youngblood to Schnell letter dated 7-18-84, Review of Design for Automatic Shunt Trip for Scram Breakers - Callaway Plant, Unit 1 Reference one transmitted Union Electric's approved implementation schedule associated with the provisions of Generic Letter 83-28.
The attachment provides additional information regarding those Staff positions not completely addressed.
Given the information in the attachment and in references one through i
three, the remaining actions to be implemented are those associated with the non-NSSS vendor interface program (item 2.2).
This program will be fully implemented by September 1985.
Very truly yours,
[a-et Donald F.
chnell t3 GGY/lw
Attachment:
Generic Letter 83-28 Responses f
$[1 8501020270 841227 7
PDR ADOCK 05000483 P
PDR h
Mailing Address: RO Box 149, St Louis MO 63166
STATE OF MISSOURI )
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SS CITY OF SY. LOUIS )
Robe r t J. Schukai, of lawful age, being first duly sworn upon oath says that he is General Manager-Engineering (Nuclear) for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has exocuted the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true anU correct to the best of his knowledge, information and belief.
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By Rober J.'
chukai Genera nager-Engineering Nuclear SUBSCRIBED and svorn to before me this vf 7 day of Jara/4/, 198 h bki' p yf e
BARBARA J. PFAFT NOTARY PUBUC. STATE OF MISS0'JRI MY COMMISSION EXPIRES APH L 22,1525 ST. LOUIS COUNTY
- - ~ - _ _ - _. _ - _..
i cc:
Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.
Washing ton, D.C.
20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 John H. Neisler Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 William Forney Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission
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Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR$1 Steedman, Missouri 65077 Jan Stevens Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop P-316 7920 Norfolk Avenue Bethe:da, MD 20014 l
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L Generic Letter 83-28 Responses 1.1 Our Reactor Trip Review Program, as discussed in references one and two, has been fully:
implemented.
1.2 The computer systems providing post-trip review data are in place and functional.
Refer to our discussion given in reference two.
2.1 The Callaway Q-List and NSSS vendor (Westinghouse) interface programs have been fully implemented.
Refer to our discussion given in reference three.
2.2
'Our non-NSSS vendor interface program will follow the recordnendations of the NUTAC report, " Vendor Equipment Technical Information Program," issued in March 1984.
This program will be fully imple-mented by Sept' ember 1985.
Refer to our discussions given in references two and three 4
which address the balance of item 2.2.
3.1/3.2 Administrative procedures are in place.which ensure that post-maintenance testing is performed as required and that appropriate guidance is included in maintenance procedures.
Refer to our, discussions given in references one and three.
4.1 Modified Undervoltage Trip Attachments (UVTA's) have been installed on all reactor trip (main) and bypass breakers.
4.2.1 The Westinghouse Owner's G'oup (WOG) compilation r
of maintenance information for the reactor trip switchgear was issued on October 18, 1984.
This l
information has been incorporated into Preventive Maintenance Procedure MSE-SB-OSG01.
This maintenance program now includes periodic veri-fication of UVTA drop-out voltage, Shunt Trip Attachment (STA) operal'lity under degraded voltage conditions (70 VDC vs. 125 VDC design),
and UVTA trip force (i.e., available force) and breaker load (i.e., required force).
Refer to our discussion given in reference one.
4.2.2 The following parameters affecting operation of the reactor trip switchgear and measured period-ically per the surveillance procedure di.scussed uader item 4.2.1 are trended to forecast degradation of operability:
w-3 L
f (a) insulation resistance (b) contact clearancee (c)
UVTA drop-out voltage (d)
UVTA' trip force and breaker load (e) automatic shunt trip response time.
The responsible maintenance engineer reviews completed surveillances and accumulates pertinent data.
This data is trended to ensure that values of the above parameters are within acceptable bounds for operation.
Pre-determined action levels are set to ensure that operation remains within these bounds.- If trending indicates equipment degradation, additional attention will be focused on the component in question.
This attention may manifest itself in decreased surveillance intervals, supplemental maintenance, or component r,eplacement, dependent on the nature and severity of the degradation.
4.2.3/4.2.4 The WOG life. cycle and qualification test programs have been completed.
The results of these programs are applicable to Callaway and document the seismic qualification of our UVTA's and STA's.
Consistent with the results of these programs, the service life for the UVTA's is 1250 operations.
This life has been included in surveillance procedure MSE-SB-QS001 discussed under item 4.2.1.
No service life was assigned to the STA's.
STA replacement is required only if the degraded voltage test discussed under item 4.2.1 results in unsatisfactory performance (i.e., if the breaker does not trip).
No other qualification contin-gencies resulted from the WOG programs.
4.3 The automatic shunt trip panel, qualified shunt trip coils, and safety-related STA's have been installed and are functional.
Seismic qualifi-cation of the STA has been successfully completed as discussed above.
Technical Specification changes per reference four have been initiated and l
will be submitted under. separate cover.
No changes are required to ensure manual reactor l
trip switch testing as this is already covered by Technical Specification 4.3.1.1-1.
This manual trip TADOT is performed prior to restart following each refueling outage.
Refer to our automatic shunt trip design discussion give in reference two and the Staff's evaluation given in reference four.
4.4 This item is not applicable to Callaway.
4.5 Refer to the discussions under item 4.3 above and those given in references two and three.
s.
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