ML20106E285

From kanterella
Jump to navigation Jump to search

Forwards Corrections to 841019 Response to NRC Request for Addl Info Re Util Request for Schedular Relief from Certain Environ Qualification Requirements
ML20106E285
Person / Time
Site: Hatch 
Issue date: 10/23/1984
From: Gucwa L
GEORGIA POWER CO.
To: Stolz J
Office of Nuclear Reactor Regulation
References
NED-84-559, TAC-55488, TAC-55489, NUDOCS 8410290143
Download: ML20106E285 (3)


Text

Georgia Power Company "4

333 Piedmont Avenue

. Atlanta Georgia 30308 Telephone 404 52&6526 Mahng Address:

Post Offee Box 4545 Attanta, Georgia 30302 Georgia Power L T. Gucwa tv sovraem elatnc system Manager Nuclear Engineereg and Chief Nuclear Engineer NED-84-559 October 23, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Cmmission Washington, D. C.

20555-NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HA'IGI MILEAR PLANT UNIT 1 CORRECPICN OF PREVIOUSLY SUBMITTED IOUIPMENT 00ALIFICATION PROGRAM JUSTIFICATIONS FOR CONTINUED OPERATION Gentlenen:

By letter dated October 19, 1984 (NED-84-550) Georgia Power Cmpany (GFC) responded to your October 12, 1984 request for additional infomation regarding GIC 's requested schedular relief frm certain enviromental qualification reluirements. As part of the response to NRC Itsn No. 4, GPC subnitted a new Justification for Continued Operation (JOO) as part of to that subnittal.

In the instructions included with Enclosure 5, GFC stated that the newly subnitted JCO should be used to replace the previously subnitted JOO on page 46 (of Attachnent 2 to NED-84-508, dated September 26, 1984).

Instead the original page 46 should have renained intact and the new JOO should have been added to Attachnent 2 as page 47.

Enclosed with this subnittal are copies of both JCOs in question. These two JOOs should be added to Attachnent 2 of NED-84-508 as pages 46 and 47.

Any JCOs now in that Attachnent nunbered as page 46 should be discarded.

Note that the new page 47 contains corrections of typographical errors which have been found in the JCD contained in Enclosure 5 to NED-84-550.

Very truly yours, f. T. & m L. T. Gucwa CBS/mb-Enclosures xc:

J. T. Beckhan, Jr.

II. C. Nix, Jr.

~ J. P. O'Reilly (NRC-Region II) 4 3

Senior Resident Inspector j

()

FA MM 0%ML PDR

REV. 1 A'ITACIND7f 2

. E41-C002 (LS-4)

%is limit switch is attached to the HPCI Turbine stop valve and controls the signal which opens the HPCI syste discharge valve as well as activates the turbine regulator r a p generator on HPCI turbine start.

The limit switch is not required for a HEIB in the HPCI rom which is a rupture of -the HPCI stem supply line. No credit is taken for the operation of the HPCI turbine to mitigate the consequences of a HPCI stem line break.

%e limit switch could be subjected to a harsh enviroment due to radiation after a IOCA.

The limit switch is a NAMOD Model D200G-ST-2 and does not have any documented radiation exposure test data.

The manufacturer has provided a list of non-mettallic parts which are used in the subject switch.

Each part has been reviewed to determine its radiation daage threshold value.

'Ibe results of the evaluation have deonstrated that the most susceptible part has a threshold value 5 times higher than the maximm expected total integrated dose in the HPCI rom; therefore, the switch is expected to operate as designed.

Based on the above, continued operation is justified.

46

REV. 2 ATfACIMNr 2

. E41-C002 (SV1)

E41-C002 is the HPCI 'Iurbine and auxiliaries [ including Solenoid Valve E41-C002 (SV1)).

%e HPCI -Turbine could be subjected to a harsh enviroment due to taperature after a HPCI stem line break,, but no credit is taken for the operation of the HPCI 'nirbine following a rupture of its stem supply line.

In the event of a large break IOCA for which the HPCI syste cannot maintain

- RPV level, the HICI 'nirbine may be subjected to high radiation. However, in

- this case the HPCI Syste is not required since the RPV will be depressurized by the break and/or the actuation of the ADS Systs. Adaguate core cooling is then provided by the low pressure EOCS syste s.

In the~ event of a mall break IOCA for which the HPCI can maintain RPV

- level, the core never uncovers and hence core cooling is maintained and the high radiation enviroment is not present.

- %is piece of equipnent has been used during nomal operation in plants similar to Hatch 1 for the past eleven (11) years. To date, no age related catsnon mode failures have been reported.

%ese devices have experienced relatively limited service in Hatch 1 as they have been used during nomal

. operation for only five (5) years. With this limited service this equipnent is not expected to fail before replacm ent.

Based on the above, continued operation is justified.

1 47