ML17254B030
| ML17254B030 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/23/1984 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-83-28, LSO5-84-11-022, LSO5-84-11-22, NUDOCS 8411270377 | |
| Download: ML17254B030 (7) | |
Text
November 23, 1984 Docket No. 50-244 LS05-84-11-022 Mr. Roger Il. Kober, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, Hew York 14649
Dear Mr. Koher:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION -
ITEMS 4.2. 1 and 4.2.2 OF GENERIC LETTER 83-28 Re:
R.
E. Ginna Nuclear Power Plant In conducting our review of your November 4, 1983 response to Items 4.2. 1 and 4.2.2 of Generic Letter 83-28, we have determined that we will need additional information as identified in the enclosure to this letter.
In order to continue our review within a reasonable time frame, your response is requested within 90 days of your receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Please contact us if you have any questions concerning this request.
Sincerely, Original signed by John A. Zwolinski, Chief Operating Reactors Branch ¹5 Division of Licensing DISTRIBUTION oc et NRC PDR Local PDR ORB Reading NSIC JZwnlinski CJamerson PM NRomney OE ELJordan JNGrace ACRS (10)
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Mr. Roger W. Kober November 23, 1984 CC
'Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire Avenue, N.W.
Suite 1100 t<ashington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law
.2 World Trade Center New York, New York 10047 Resident Inspector R.E. Ginna Plant c/o U.S.
- NRC, 1503 Lake Road
- Ontario, New York '4519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Fmpire State Plaza
- Albany, New York 12223 Dr. Thomas E. Murley Regional Administrator Nuclear Regulatory Commission Region I Office 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Jay Dunkleberger Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza,
- Albany, New York 12223 U.
S. Environmental Protection Agency Region II Office ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007
R.E.
GINNA POWER PLANT REQUEST FOR ADDITIONAL INFORMATION GL 83-28, ITEMS 4.2.1 AND 4.
2.2 INTRODUCTION
Rochester Gas and Electric Corporation, the licensee for the R.
E. Ginna Power Plant, submitted their response to Generic Letter 83-28 on November 4, 1983.
The submittal has been reviewed with respect to items 4.2.1 and 4.2.2 of the Generic Letter.
The following,additional information is required to evaluate compliance with these items.
Item 4.2.1 - Periodic Maintenance Program for Reactor Trip Breakers.
1.1 Criteria For Evaluatin Com liance With Item 4.2.1 h
The Ginna Reactor Trip System utilizes Westinghouse DB-50 circuit breakers.
The primary criteria identified for an acceptable maintenance program for this breaker is contained in the Westinghouse Maintenance Program for DB-50 Trip Switchgear The
'RC staff, Equipment Qualification Branch, has reviewed and endorsed the.Westinghouse Maintenance Program for DB-50 Switchgear.
Specifically, the criteria used to evaluate compliance include those items in the Westinghouse program that relate to the safety function of the breaker supplemented by those measures that must be taken to accumulate data for trending.
2.
Letter John E. Maier; Ginna Nuclear Power Plant, to Dennis M.
Crutchfiel'd, NRC, Response to Generic Letter 83-28, November 4, 1983.
I Maintenance Program for DB-50 trip switchgear Revision 0, October 14, 1983.
The licensee's November 4, 1983 submittal indicates that the Ginna Preventative Maintenance Procedure for the'Reactor Trip Switchgear effective October 5, 1983 deviates from the Westinghouse program.
The licensee is required to respond to.the following.
1 1.2 Issues Relatin to Item 4.2, 1 The Ginna Power Plant periodic maintenance program for the reactor trip breaker should include at six month intervals:
1.
Verification of trip bar freedom; 2.
Yerification of operating mechanism alignment and freedom,
~using the procedure identified in the Westinghouse program; 3.
Verification of 33 retaining rings; Verification of arcing and main contacts physical condition, s
using the procedure identified in the Westinghouse program; 5.
Verification of wiring insulation and termination physical condition; 6.
Undervoltage Trip Attachment (UYTA) dropout voltage test and lubrication, using the procedure identified in the Westinghouse program; 7.
Shunt Trip Attachment (STA) operation verification, using the procedure identified in the Westinghouse program; C
- 8. 'nspection of positioning lever condition,'sing the procedure
-identified in the Westinghouse program; 9.
Functional test of the breaker prior to returning it to
- service, using the procedure identified in the Westinghouse
'program.
The licensee should confirm that these nine items are in this Preventative Maintenance Procedure for the Reactor Trip Switchgear or that they will be included.
The licensee should confirm that the following activities are performed every six months or that he will commit to perform them every six months.
l.
Verification of nut and bolt tightness; 2.
Verification of pole bases physical conditions;
~
- 3. 'erification of. insulation link. s physical condition; 4.
Verification of arc chute physical condition; 5.
Verification of breaker cleanliness; Y
6.
Verification of operation of auxiliary switches.
The licensee is to confirm that the periodic maintenance program for the reactor trip breakers includes on a refueling interval basis:
l.
Verification of cell interlocks operation; 2.
Examination of cell interlocks operation; 3.
Measurement of trip force required; using the procedure identified in the Westinghouse program; 4.
Breaker response time to undervoltage trip (this activity is not included in West'inghouse recommendation.)
5.
Functional test'f breaker prior to returning to service, using the I
procedure identified in the Westinghouse program; 3
4
~
~'f they are not included the.licensee should provide a commitment to include these five items.
2.
Item 4.2.2 - Trending of Reactor Trip Breaker Parameters to forecast
~ degradation of operability.
. I Criteria For'.Ewaluatin
-Com liance With Items 4.2.2 Four parameters have been identified as trendable and are included in the criteria for evaluation.
These are (1) undervoltage trip attachment dropout voltage, (2) trip force, (3) breaker response time for underyoltage trip, and (4) breaker insulation resistance.
2.2 Issues Relatin to Item 4.2.2 Tlie licensee submittal states that the trending performance of reactor trip breakers has started with the 1983 refueling outage.
Response
time testing data is being used to establish baseline data to,',determine degradation.
Also Hechanical trending information is being recorded "as found" and "as left."
The licensee did not address the use of the parameters such as undervoltage trip attachment dropout voltage, trip force and breaker insulation resistance for forecasting degradation of the breaker operability.
The licensee should commit to include these three items as trending parameters';
The licensee should provide a discussion to show how the response time test resu'its are being used to determine degradation.
The criteria to be used for evaluation,'cceptance limits, and base line values should be specified.
The licensee stated that "the undervoltage trip coil and the shunt trip coil will be indeyendently tested."
The licensee should provide a more detailed description of this test including whether it is a tripping only or involves othe'r types of testing.