ML20058H795
| ML20058H795 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/03/1993 |
| From: | Rainey G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CCN#9314163, NUDOCS 9312130226 | |
| Download: ML20058H795 (2) | |
Text
CCNf9314163 l
e pg
~.m PIIIIADELPIIIA ELECTRIC COMPANY PI:ACH 110TRW AlDMIC POWI R STATION it. D. I. Ikax 208 s U _. __ jh Delta. Pennsylvania 17.414 nu u sunuu-m, nmin omu s u mu (717) 456-7014 December 3, 1993 US Nuclear Regulatory Commission Attn:
Document Control Desk Washington DC 20555
Dear Sir:
Subject:
Peach Bottom Atomic Power Station Units 2 &3 1
Pesponse to Combined Inspection Report 93-18/18 In the cover letter of the subject inspection report, you requested a schedule for upgrading the operational cycle monitoring program.
Please find attached a schedule that addresses this upgrade as well as the issues discussed in Section 3.1 of the subject inspection report. Completion of this program should allow closure of unresolved item, UNR 90-14-02.
If you have any questions or require any additional information, please do not hesitate to contact us.
j Sincerely,
,$^^
w a iney ';
m jyG R. Ra Vice Presiden RKS: bah Attachment cc:
R. A.
Burricelli, Public Service Electric & Gas W.
P.
Dornsife, Commonwealth of Pennsylvania W. L. Schmidt, Senior Resident Inspector, US NRC T. T. Martin Administrator, Region I, US NRC R.
I. McLean, State of Maryland 11.
C.
Schwemm, Atlantic Electric C.
D. Schaefer, DelMarVa Power 090013 A/ { l n
9312130226'931203 PDR-ADOCK 05000277 O
PDR l
o Response to Inspection Report 93-18/18 Operational Cycle Monitoring Program Upgrade Schedule 1.
Revise the routine test procedure that maintains a cumulative
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record of Reactor Pressure Vessel temperature and pressure cycles to include additional events and new
" maximum allowable" occurrences.
This revision will be completed by December 15, 1993.
2.
Develop a concise and consistent methodology for counting of' cycles.
This methodology will be completed by March 31, 1994.
3.
Determine the past data that is required and initiate retrieval of this data from the archive storag:
facility.
I Tnia action will be completed by April 30, 1994, 4.
Perform a preliminary review to verify the adeqLey of the methodology developed for counting of cycles and the content of the routine test procedure.
Additionally, ensure that there is sufficient data obtained from the archives to effectively count cycles and determine the number of cycles expended.
Based on the review of this preliminary. data, additional records may need' to be retrieved or procedures and methodologies may require revision.
This preliminary review will be completed by May 31, 1994.
5.
Review and evaluate the data obtained to determine the total l.
number of cyclic transients. This action will be completed by December 31, 1994.
6.
Prepare a table of the cycles expended to date and compare with each transient listed in the Updated Final Safety Analysis Report, Table 4.2.4.
Evaluate the percentage of total component life that has been expended.
This evaluation will be completed by December 31, 1994.
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