ML17249A288
| ML17249A288 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/15/1979 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17249A289 | List: |
| References | |
| TASK-05-11.A, TASK-5-11.A, TASK-RR NUDOCS 7911230282 | |
| Download: ML17249A288 (6) | |
Text
I REGULATORY INFORMATION DISTRIBUTION SYSTEM (BIDS) 1 I'CCE.SERIO(gNBR;7911230282 C ~ DATE: 79/11/15 NOTARIZE 4
NO DOCKET FAC2C';A 244 Robert= Emmet Ginna Aucleai Plantr Unit li Rochester G
05000244 AOTH ~ AAME. 'UTHOR AFFILIATION)
WHItEgL';
Rochester Gas "L Electr)c Corp>
'ECAP;NAME
'RECIPIENT AFFILIATION ZIP'A'NNiD.L.,
Operating"Reac'tor's Branch 2
SUBJECTS Forwards App C to QA Manual re revised
)nserv<ce pump 8
valve tesH ng program fot May 19T9 Dec 19BOt DISTRIBUTION CODE':
A001'S COPIES RECEIVED:LTR ~ ENCL", Zg SIZE:~
z z:~+~~
TIl'lE: gener el
- 0) st r )Gute on for af tet Issuance of Oper at fng"C) c N>>ES:~~
~ ~(lglg~a C..
oCm4p~
RECIPIENT COPIES RECIPIENT COPIES ID'CODE/NAME'TTH"ENCL ID CQDE/NAME L'TTA "ENCL ACTlONt 05 BC >~g M~
7 7
INTERNAL
~L 12 18K'5 CORK>> PERF BR ie AEAC 8FTY SA 20 EEB 22 BAINKMAN OELD EXTERNALS 03 LPDR
?3 ACRS 1
1 2.
2 i
1 i
i ii 0
1 1
16 16 02 NRC PDR 14 TA/EDO i7 EAGR BR i9 PLANT SYS BR 2i KFL"f TRY SYS EPB<<OOR 04 NSIC 1
1 i
i i
ii i
ii 1
1
~/
Ya TOTAL'UMBER OF COPI'KS REQUIRKD'TTR ~
ENCL
I' il fl L
l il P
(SIII //)I))I)I)I
//g
/////
///
ZuI////I
//////////
I///////////
ROCHESTER GAS AND ELECTRIC CORPORATION
)
. I4(t
\\>>>> ~ 0>> I > <<0
~(
toa)(
X(
R".'(At(
ALI')
o 89 EAST AVENUE, ROCHESTER, N.Y, 14649 LEON D. WHITE. JR.
VICE PRESIDENT TEI.EPHONE AREA CODE TId 546-2700 November 15, 1979 Director of Nuclear Reactor Regulation Attention:
Dennis L. Ziemann, Chief Operating Reactors Branch N2 U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Inservice Pump and Valve Testing Program R.
E. Ginna Nuclear Power Plant Unit Nl Docket No.
50-244
Dear Mr. Ziemann:
In accordance with the requirements of 10CFR Part 50, Section 50.55a, paragraph (g),
we have enclosed Revision 1 of the Ginna Station Inservice Pump and Valve Testing Program for the May 1, 1979 through December 31, 1980 period, "Appendix C to the Ginna Station Quality Assurance Manual."
This revision incorporates the changes discussed with members of your staff over the past months in addition to incorpo-rating the remaining locked valves (Category E) that appear in the Administrative Procedure for the control of locked valves.
This revision also includes pumps and valves associated with the recently completed Standby Auxiliary Feedwater System.
Valves 851 A and B have been removed from the program (Cate<<>>
gory B of revision 0) due to a review of their operational function.
These valves are located in the containment emergency sump and are in suction line to the RHR pumps.
They are required to be open to perform their function during the recirculation phase of a loss of coolant accident.
Originally; the valves were installed to provide a redundant means of isolating that portion of the suction line, however, this capability is not required by the plant safety analysis.
Since the valves must be open to perform their safety function, and since there is no safety reason for being able to close Y~,p
V I4
ROCHESTER GAS AND ELECTRIC CORP.
DATE November 15, 1979 To Dennis L. Ziemann SHEET NO.
the valves in responding to an accident, the two valves have been removed from Category B and will be de-energized during normal operation to prevent inadvertent closure.
The valves would be closed during refueling shutdown to permit testing of the RHR system and as such will be excluded from the valve program based on the IWV-1300 exclusion criteria for valves which are utilized for operating convenience.
All changes to the program, other than editorial, are highlighted with vertical lines in the right margin next to each change.
Valves 1812 A and B have also been removed from the program (Category C of revision 0) due to a review of their oper-ational function.
These normally closed check valves help to isolate the Residual Heat Removal System from the Reactor Coolant Drain Tank system whenever RHR pumps are in operation.
Consistent with IWV-3520, the listing of Category C check valves include only those valves which are required to change position to fulfilltheir safety function.
Enclosed are forty (40) copies of this letter and the attach-ments.
Sincerely, AEC:dma Enclosures
0