ML19269D609

Forwards Proposed Amends to Fire Protection Tech Specs Covering Addl Fire Detection Instrumentation & Water Suppression Sys

ML19269D609
Person / Time
Site:	Hatch
Issue date:	05/29/1979
From:	Whitmer C GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7906050274
Download: ML19269D609 (13)

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May 29, 1979 b Geoipia Power Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2 FIRE PROTECTION TECHNICAL SPECIFICATIONS Gentlemen:

Pursuant to 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes amendments to the Plant Match Units 1 and 2 Technical Specifications (Appendix A to the Operating Licenses). The proposed changes are in accordance with your letter dated October 4, 1978, which contained Amendment No. 60 to the Unit 1 Operating License by adding a license condition related to facility modifications for fire protection.

Amendment No. 60 was supported by the Plant Hatch Units 1 and 2 Fire Protection Program Safety Evaluation Report (SER) . Table 1 of the SER itemized the modifications to be completed on both units to improve fire resistance capability. Accordingly, you requested that we modify the Technical Speci-fications on both units to incorporate the limiting conditions for operation and surveillance requirements to reflect these additional fire protection features. Therefore, you will find enclosed proposed changes to the Unit 1 and Unit 2 Technical Specifications that contain the necessary revisions. The proposed changes are specifically related to the additional fire detection instrumentation nd water st ppression systems that will be installed. The schedule for implementation e" these proposed changes to the Technical Speci-fications should coincide wita the schedule for completion of the fire pro-tection modifications as discussed in the SER.

The Plant Review Board and Safety Review Board have reviewed and approved the proposed changes to the Plant Hatch Unit 1 and 2 Technical Specifications and have determined that they do not constitute an unreviewed safety question.

The probability of an accident is not increased nor is the possibility for failures of a type not previously considered introduced, since the proposed changes are based on the modifications which have been approved in the Fire Protection Program. Therefore, margins of safety are not reduced.

79060502Tt 2261 270

Georgia Power d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 May 29, 1979 Page Two Amendment No. 60 to the Unit 1 license contained a statement which pre--

vided for " changes to the Program without prior Commission approval provided that such changes do not result in a decrease in the effectiveness of the Program". The Unit 2 license als.o contains conditions relating to the fire protection program but does not contain a simi.ar provision for modifying the Program. Inasmuch as the document " Evaluation of the Hatch Nuclear Plant Fire Protection Program" applies to both units, we believe it would be appropriate for the Unit 2 license to reflect the same statement which was added to the Unit 1 license by Amendment No. 60 which provides for changes to the Program, under certain conditions, without prior Commission approval.

Therefore, Georgia Power Company hereby requests that the Unit 2 license be amended to include the following statement.

Except for the modifications described in the approved fire protection plan and approved as a result of Commission review of the Hatch Nuclear Plant Fire Protection Program, Georgia Power Company is authorized to make changes to the Program without prior Ccmmission approval provided that such changes do not result in a decrease in the effectiveness of the Program.

The proposed statement would go at the end of item 2.c(d)(b) in the Unit 2 license.

Very truly yours, r, -->

y/

- Chas. F. Whitmer TMM/MRD/mb Enclosures orn to and subscribed,before me this 29th day of May, 1979.

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/ Notary Public, Chi 9pgrg!ctD6Nd/ge My Commission Expires Sept. 29,1981 xc: Mr. Ruble A. Thomas George F. Trowbridge, Esquire 2261 271

ATTACHMENT 1 NRC DOCKET 50-321, 50-366 OPERATING LICENSE DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating Licenses DPR-57 and NPF-5 and have determined that:

a) The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b) The proposed amendment does not contain several complex issues, does not involve ACRS review, or does not require an environmental impact statement; c) The proposed amendment does not involve a complex issue, an environ-mental issue or more than one safety issue; d) The proposed amendment does involve a single issue; namely, the Hatch 1 and the Hatch 2 Technical Specific 6 tion changes for new fire detection and suppression systems protecting safety related areas; and e) The proposed amendment is therefore a Class III amendment.

2261 272

ATTACHMENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS The proposed changes to the Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Remove Page Insert Page 3.13-2 3.13-2 3.13-5 3.13-5 3.13-6 3.13-6 2261 273

TABLE 3.13-1 FIRE DETECTORS MINIMUM OPERABLE BUILDIfiG fiUMBER OF DETECTORS DETECTORS REQUIRED A.1 Control Building El. 112'-0" 1.1 Station Battery Room lA 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 A.2 Control Building El.130'-0" 2.1 Switchgear Roons lA, 1B, (1 in each lE, IF, and Tran-fonner 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 l A.4 Control Building El. 164'-0" 4.1 Control Room Unit 1 21 10 4.2 Control Room Unit 2 15 7 4.3 Peripheral Rooms 10 5 l B.1 Diesel Generator Building 1.1 Switchgear Room lE 4 2 1.2 Switchgear Room 1F 4 2 1.3 Switchgear Room 1G 4 2 1.4 Battery Room l A 1 1 1.5 Battery Room 1B 1 1 1.6 Battery Room 1C 1 1 C.1 River Intake Structure 1.1 Building Area 11 5 D.1 Reactor Building El. 130'-0" 1.1 tiorth Cable Tray Area, Remote Shutdown Area, and North CRD Area 33 16 1.2 South Cable Tray and South CRD Area 35 17 D.2 Reactor Building El. 158'-0" 2.1 HVAC Room 20 10 Amendment No. 50 3.13-2 2261 274

3/4.13 FIRE PROTECTION SYSTEMS 3/4.13.3 SPRAY AND/0R SPRIflKLER SYSTEM _S.

LIMITING CONDITI0 tis FOR OPERATION 3.13.3 The following spray and/or sprinkler systems located in the following areas shall be OPERABLE:

'a. Turbine Lube Oil Storage

b. Turbine Lube Oil Reservoir

c. RCIC Room

d. HPCI Room

e. Recirculation Pump Motor Generator Room

f. East Cableway

g. Cable Spreading Room

h. RPS Vertical Cableway

i. Control Building Corridor (El.130')

j. Intake Structure

k. Reactor Building HVAC Room

. APPLICABILITY: At all times when equipment in the area is required to be 6PERABLE.

ACTI0ti:

a. With a spray and/or sprinkler system inoperable establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s), within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provided radiation levels permit personnel access.

b. Restore the system to OPERABLE status within 14 days or pre-pare and submit a Special Report to the Commission within the next 30 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.

2261 275 Amendment flo. 50 3.13-5

3/4.13 FIRE PROTECTION SYSTEMS 3/4.13.3 SPRAY AND/0R SPRINKLER SYSTEMS SURVEILLANCE REQUIREMENTS 4.13.3 The spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

a. At least once per 12 months by D rforming a system functional test which includes simulated automatic actuation of the system and verify that the automatic sprinkler valves in the flow path actuate to their correct position. Deluge system valves will be checked for auto actuation but will not be tripped through a complete cycle.

b. At least once per 18 months:

1. By inspection of spray headers to verify their integrity.

2. By inspection of each nozzle to verify no blockage.

c. At least once per 3 years by performing an air flow test through each spray / sprinkler header and verifying each open head spray /

sprinkler nozzle is unobstructed.

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3.13-6

ATTACHMENT 3 flRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIll I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHAflGES TO TECHNICAL SPECIFICATIONS Remove Page Insert Page 3/4 3-59 3/4 3-59 3/4 3-59a 3/4 3-60 3/4 3-60 3/4 7-25 3/4 7-25 3/4 7-26 3/4 7-26 2261 277 V

IflSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING C0flDITION FOR OPERATION 3.3.6.8 As a minimum, the fire detection instrumentation for each area shown in Table 3.3.6.8-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that area is required to be OPERABLE.

ACTION:

With one or more of the above required fire detection instruments inoperable:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,. establish a fire watch patrol to inspect the area (s) with the inoperable instrument (s) at least once per hour,* and

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.9.1, prepare and submit a Special Report to the Commis-tion pursuant to Specification 6.9.2 within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

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• This ACTION is not applicable for fire detection instrumentation located inside the primary containment. The surveillance required by Specification 4.3.6.8.4 shall be performed.

It!STRUMEtiTATION FIRE DETECTION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS 4.3.6.8.1 Each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUtlCTIONAL TEST. All portions of a channel inside the primary containment may be excluded from the CHANNEL FUNCTIONAL TEST. For such instruments, a complete CHANNEL FUNCTIONAL TEST shall be performed at each scheduled outage greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during which entry is made into the primary containment, if not performed within the pre-vious 6 months.

4.3.6.8.2 The circuitry supervision associated with the detector alarms shall be demonstrated operable at least once per 62 days for all NFPA Code 72D Class B supervised circuits.

4.3.6.8.3 The primary containment temperature in the drywell shall be checked at least once per hour for any abnormal indications whenever fire detection instrumentation in that area is declared inoperable.

2261 279 HATCH - UNIT 2 3/4 3-59a

TABLE 3.3.6.8-1 FIRE DETECTION INSTRUMENTATION MINIMUM OPERABLE AREA NUMBER OF DETECTORS DETECTORS Control Building, E. 112'-0" Station Battery Room 2A 2 1 Station Battery Room 2B 2 1 Corridor and Work Area 9 4 Control Building, El. 130'-0" Switchgear Rooms, 2A, 2B, 5 1 per room 2C, 2D and Transformer Room Corridor 6 3 RPS Vertical Cableway 2 1 East Cableway 14 7 Diesel Generator Building Switchgear Room 2E 4 2 Switchgear Room 2F 4 2 Switchgear Room 2G 4 2 Battery Room 2A 1 1 Battery Room 2C 1 1 Reactor Building, El .130'-0" North Cable Tray Area, Remote Shutdown Area, and North CR0 Area 38 19 South Cable Tray Area and South CRD Area 35 17 Reactor Building , El .158'-0" HVAC Room 23 11 Drywell Recirculation Pump A Area 1 1 Recirculation Pump B Area 1 1 Div. 1 Control & Power Cable Tray Area 1 1 Div. 2 Control & Power Cable Tray Area 1 1 Div. 1 CRD Cable Tray Area l 1 Div. 2 CRD Cable Tray Area 1 1 2261 280 HATCH - UNIT 2 3/4 3-60

PLANT SYSTEMS SPRINKLER SYSTEMS LIMITING CONDITION FOR CPERATION 3.7.6.2 The following sprinkler systems shall be OPERABLE:

Turbine lube oil storage

• Turbine lube oil reservoir RCIC room HPCI room West cableway East cableway Recirculation pump motor generator room Cable spreading room RPS vertical cableway Control Building Corridor (El. 130')

Drywell (recirculation punps)

Reactor Building HVAC room APPLICABILITY: Whenever equipment in the sprinkler protected areas is required to be OPERABLE.

ACTION:

a. With one or more of the above required sprinkler systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provided radia- l tion levels permit personnel access; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

2261 281 HATCH - UNIT 2 3/4 7-25

PLANT SYSTEMS SPRINKLER SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.6.2 Each of the above required sprinkler systems shall be demonstrated OPERABLE:

a. At least once per 12 months by performing a system functional test which includes simulated automatic autuation of the system and verify that the automatic sprinkler valves in the flow path actuato to their correct positions. Deluge system valves will be checked for auto actuation but will not be tripped through a complete cycle.

b. At least once per 18 months:

1. By inspection of the spray headers to verify their integrity, and

2. By inspection of each deluge nozzle to verify no blockage.

c. At least once per 3 years by performing an air flow test through each open head sprinkler header and verifying each open head sprinkler nozzle is unobstructed.

2261 282 HATCH - UNIT 2 3/4 7-26

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