ML17255A569: Difference between revisions
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| issue date = 12/21/1983 | | issue date = 12/21/1983 | ||
| title = Forwards Rev 4 to Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990,per IE Bulletin 83-03.Rev Incorporates Leakage Requirements for Svc Water Pump Discharge Check Valves 4601-4 | | title = Forwards Rev 4 to Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990,per IE Bulletin 83-03.Rev Incorporates Leakage Requirements for Svc Water Pump Discharge Check Valves 4601-4 | ||
| author name = | | author name = Maier J | ||
| author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | ||
| addressee name = | | addressee name = Crutchfield D | ||
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000244 | | docket = 05000244 | ||
Revision as of 03:50, 19 June 2019
| ML17255A569 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 12/21/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17255A570 | List: |
| References | |
| REF-SSINS-6820 IEB-83-03, IEB-83-3, NUDOCS 8312280350 | |
| Download: ML17255A569 (6) | |
Text
.a REGULATQRQNFORMATION DISTRIBUTION S'EM (RIBS)ACCESSION NBR;8312280350 DOC~DATEf 83/12/21 NOTARIZED:
NO DOCKET FACIL:50 204 Robert Emmet Ginna Nuclear Plantg Uni;t ig Rochester G 05000244 AUTH'AME AUTHOR AFFILIATION MAIER J,E~Rochester Gas 8 Electric Corp+RBCIP~NAME RECIPIENT AFFILIATION CRUTCHFIELDgD
~Operating Reactors Branch 5
SUBJECT:
Forwards Rev 0 to inservice pump 8 valve testing, program for Jan 1981 Dec 1990iper IE" Bulletin 83 03.Rev incorporates leakage requirements for svc water pump discharge check valves 0601 I/DISTRIBUTION CODE!A007 COPI S ECEIVEDiLTR-ENCL SIZEG//TITLE:.OR Submittal:
Inservice'nspection/Testing NOTES:NRR/DL/SEP icy'5000204 RECIPIENT ID CODE/NAME NRR ORB5 BC 01 COPIES LTTR ENCL 7 7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNALG ELD/HDSO NRR/DE/MTEB 10 RGN1 1 0.NRR/D MEB 15 1 1 IL 04 1 1 EXT'ERNALs ACRS NRC PDR NTIS NOTES!16 02 10 10 1 1 1 LPDR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 26
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ROCHESTER GAS AND ELECTRIC CORPORATION
~89 EAST AVENUE, ROCHESTER, N.Y.14649 JOHN E, MAIER Vice Presktent TELEPHONE AREA cDDE Tle 546-2700 December 21I 1983 Director of Nuclear Reactor Regulation Attention:
Mr.Dennis M.Crutchfieldi Chief Operating Reactor Branch Number 5 U.S.Nuclear Regulatory Commission Washington>
D.C.20555
Subject:
Xnservice Pump and Valve Testing Program R.E.Ginna Nucleax Power Plant Docket Number 50-244
Dear Mr.Crutchfield:
I Enclosed is Revision 4 to." ,the Ginna Station Quality Assurance Manuals Appendix CI which describes the Inservice Pump and Valve Testing Program for January 1, 1981 through December 31I 1990 testing period.-This revision fux ther revises and supexcedes Revisions 3 and 3AI submitted on December 21, 1982 and June 20I 1983.The changes are largely editorial and a ttempt to eliminate any remaining inconsistencies with the surveillance requirements of Technical Specifications.
En response to NRC XSE Bulletin 83-03I this revision also incorporates leakage requirements for the service water pump discharge check valves 4601, 4602, 4603 and 4604.Although margin lines identify only location of Revision 4 changes, the submittal contains all pages of the current Pump and Valve Testing Program.To be consistent wi th NRC XGE Bulletin 83-03 commitmentsr this revision will be implemented on January 1I 1984 having been reviewed and approved by PORC and NSARB.The Rev i'sion 3 I 3A and 4 submi t ta 1 s and related Technical Specification changes respond to all remaining NRC questions raised in your letter of May 26, 1981 regarding our Pump and Valve Program>and provide a basis for final program approval.These submittals include one additional request for relief which was inadvextantly omitted from previous submittals.
Xn upgrading the accumulator check valves from Category C to Category A to.address the boundary valve leakage concerns, Note-28 clarified the valve stroking conditions.
These conditions include partial stroke testing after refueling and cold shutdownsr and after Q ggi22i.8gi228035, QSQQQ244'DR AOOCK poR'P 041 1'll li't n lt It i l s~~~NL';Dennis N;Crutcgield December 21<1983 Page 2 maintenance>
repair and replacement>
which is a departure from ASME code that necessitates Commission concurrence in accordance with lOCFR Part 50, Section 50.55a~paragraph(s)
.Very truly yours, John E.Maier>Enclosure
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