ML20114B834: Difference between revisions

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| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| page count = 6
| page count = 6
| project = TAC:56882
| stage = Other
}}
}}



Latest revision as of 08:16, 23 September 2022

Proposed Tech Specs Re Fire Detection Resulting from Control Room & App R Mods
ML20114B834
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 01/17/1985
From:
GEORGIA POWER CO.
To:
Shared Package
ML20114B832 List:
References
TAC-56882, NUDOCS 8501290536
Download: ML20114B834 (6)


Text

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ENCLOSURE 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO AMEND FIRE-PROTECTION TECHNICAL-SPECIFICATIONS The proposed change to the Technical Specifications (Appendix A to

-0perating License DPR-57) would be incorporated as follows:

Remove Page Insert-Page 3.13-2 3.13-2 e

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TABLE 3.13-1 FIRE DETECTORS MINIMUM OPERABLE-BUILDING NUMBER OF DETECTORS DETECTORS REQUIRED A.1 Control-- Building El .112'-0" 1.1 Station Battery Room 1A 2 1

- 1. 2 Station Battery Room 18 2 1 1.3 " Corridor and Work Area 15 7

,1.4 RPS Vertical Cableway 4 ,

2 f A.2_ Control Building El .130'-0" -

2.1. Switchgear Rooms 11 A,18, _ (1.in each IE, IF, and Transformer Room 8 room or 5) 2.2 Corridor 7 3 2.3 RPS . Vertical . Cableway 2 1 2.'4 East Cableway 15 7 A.3 Control Building El.147'-0" 3.1 Switchgear & MCC Area N.W. Corner 7 3

^ 3.2 Switchgear_& MCC Area N.E. Corner .4 2

-3.3 Cable Spreading Room 50 25 3.4~ LPCI' Inverter Room 9 5 l A'.4 Control Building El .164'-0" 4.1 Control Room' Unit 1 -35 -18 4.2 Control Ro'om Unit 2 15- 8 _

4.3 Peripheral Rooms. 4 (1 in each room or 4);

B.1-Diesel Generator Building 1.1.: _Switchgear Room lE. 4 2 1.2 :Switchgear-Room 1F 4' 2 l'.3- Switchgear Room 1G 4 2 1.4 Battery Room lA_ l 1

'l.S~ Battery, Room 1B 1 1 l.6 Battery Room'1C l' .1 C.l. River Intake Structure Ll.1 Building ~~ Area 11 5-D.l. Reactor _Cuilding El. 130'-0"

~1.1 North Cable Tray Area, .

Remote Shutdown Area, and .

O ' North CRD Area 33. 16 1.2- South Cable' Tray-and South r ,CR0 Area- 35 .'17 -

lD.2 Reactor Building El. 158'-0"

2.lEHVACfRoom 20 10 l

@ 3.13-2

ENCLOSURE 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH-NUCLEAR PLANT UNIT 1 REQUEST TO AMEND FIRE-PROTECTION TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 50.59 the following safety evaluation is provided and documents that the implementation of the proposed Technical Specification change does not constitute an unreviewed safety question:

The proposed change to the Hatch Unit 1 Technical Specifications provides additional restrictions with _ regard to the number of fire detectors and number of minimum operable required fire detectors for the LPCI Inverter Room, Control Room (Unit 1), and the new peripheral rooms. Modifications to the Control Room and peripheral room areas and " Appendix R"-related modifications to the LPCI Inverter Room necessitates amending Technical Specification Table 3.13-1 to reflect the changes resulting from the subject

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modifications. In addition, the number of minimum operable required fire

-detectors for the Control Room (Uitit 2) is being revised in the aforementioned Technical Specification table to reflect plant conditions.

For;these reasons, Georgia Power Company has concluded that the probability of occurrence or consequences of a previousiv analyzed accident or malfunction of equipment important to safety is nA increased, nor has the possibility of a previously unanalyzed accident or malfunction of equipment been created. Margins of plant safety have _not been increased as a result of the proposed change in Enclosu.e 1. Therefore, the proposed changes to the Hatch Unit 1 Technical Specifications does not constitute an unreviewed safety question.

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t ENCLOSURE 3 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO AMEND FIRE PROTECTION TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment and has determined that its adoption would not involve a significant hazard. The basis for this determination is as follows:

a. PROPOSED CHANGE Add to Technical Specification Table 3.13-1, " Fire Detectors", a new item (Item A.3, 3.4) pertaining to the LPCI Inverter Room and which specifies the number of fire detectors and the number of minimum operable fire detectors required for that area.

BASIS The fire detectors added to the LPCI Inverter Room are part of on-going

" Appendix R" modifications. The changing of Technical Specification Table 3.13-1 to reflect this modification in the LPCI Inverter Room constitutes an additional restriction not presently included in the Technical Specifications. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR.

This change does not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR.- The margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the

" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

b. PROPOSED CHANGE Change Item A.4, 4.1 in Technical Specification Table 3.13-1 to reflect an increased number of fire detectors and increased number of minimum operable fire detectors required for the Unit 1 Control Room.

BASIS

- As a result of the removal of a wall separating the Unit 1 Control Room and the then existing peripheral rooms during control room modifications, the area formerly occupied by the peripheral roon's is now included in the ~ Unit 1 Control Room area. and is used for ATTS panels.

Fire detectors' installed in the former peripheral room:; area were included in the expanded Unit 1 Control Room area, as appropriate. The changing of Technical Specification Table 3.13-1 to reflect the control room modifications resulting in an increased number of fire detectors

. s ENCLOSURE 3 (Continued)

NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO AMEND FIRE PROTECTION TECHNICAL SPECIFICATIONS BASIS (Continued) and increased number of minimum operable detectors required for the Unit 1 Control Room constitute an additional restriction not presently included in the Technical Specifications for that particular area. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR. The margin of safety as defined in the basis for

- any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

c. PROPOSED CHANGE Change Item A.4, 4.2 in Technical Specification Table 3.13-1 to reflect plant conditions regarding the number of minimum operable fire detectors required for the Control Room (Unit 2).

' BASIS Changes in the number of minimum operable fire detectors required for the Control Room (Unit 2) . require revision of the aforementioned Technical Specifications table to reflect plant conditions.

Consequently, the increase in the minimum number of required fire detectors constitutes an additional restriction not previously included in the Technical Specifications. This change does not affect the probability or consequences of an accident 'or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR. The margin-of safety as defined in the basis of any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the . change is consistent with Item (ii) of the "Exarrples of Amendments that are Considered Not Likely to Involve Significant Hazards-Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

d. PROPOSED CHANGE Change Item A.4, 4.3 in Technical Specification Table 3.13-1 to reflect the -number of fire detectors and number of minimum operable fire the new peripheral rooms resulting from detectors' required for modificationstotheUnit1ControlRopm.

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  • ENCLOSURE 3 (Continued)

NRC DOCKET 50-321 OPERATING LICENSE DPR-57

-EDWIN I. HATCH NUCLEAR PLANT UNIT 1

. REQUEST TO-AMEND FIRE PROTECTION TECHNICAL' SPECIFICATIONS BASIS As a result of control room modifications, the existing peripheral rooms were eliminated by removal of a wall separating them from the Unit 1 Control Room, and that area used for placement of ATTS panels. New peripheral rooms were constructed requiring that fire detection be

. installed. The changing of Technical Specification Table 3.13-1 to reflect the fire detection requirements for the new peripheral rooms constitutes an additional restriction not previously included 'in the

-Technical Specifications. This change does not affect the probability or. consequences of an accident or malfunction analyzed in the FSAR.

This changes doe not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR. The margin of safety as defined in the basis of any Technical Specification

-is not affected. The effect of this change is therefore within the-acceptance criteria'and the change is consistent with Item (ii) of the

" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of-the Federal Register.

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