ML15112B017

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Amends 98,98 & 95 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Condition 3.E & Tech Specs Re Facility Fire Protection Mods
ML15112B017
Person / Time
Site: Oconee  
Issue date: 06/09/1981
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Duke Power Co
Shared Package
ML15112B018 List:
References
DPR-38-A-098, DPR-47-A-098, DPR-55-A-095 NUDOCS 8106180211
Download: ML15112B017 (19)
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Text

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8REG&

UNITED STATES NUCLEAR REGULATORY COMMISSION j.

WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.. 50-269 OCONEE NUCLEAR STATION, UNIT 0O.

1 AMENDMENT TO FACILITY OPERATING.LICENSE Amendment No.

98 License No. DPR-38

1.

The Nuclear Regulatory Commission (the Comimission) has found that:

-A. The applications for amendment by Duke Power Company (the licensee) dated March 18 and May 15, 1981, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health andsafety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes to, License Conditions 3.B and 3.E. and to the Technical Specifications as indicated in the attachment to this license amendment. Paraqraphs 3.B. and 3.E. of Facility Operating License No. nPR-38 are hereby amcnded to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

18 6 8

\\

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3. E. Fire Protection The licensee is authorized to proceed with and is required to complete the modifications identifiedin Table 3.1 of the NRC's Fire Protection Safety Evaluation Report on the Oconee Nuclear Station dated August 11, 1978, and as subsequently amended.

The modifications shall be completed on the schedule specified in Table 3.1, except for Item 3.1.14, "Dedicated Safety Shutdown Facility", which shall be completed 30 months after NRC approval of design.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION J n F. Stolz, Chi perating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 9, 1901

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO 5 0-270 OCONEE NUCLEAR STATION, UNIT N0.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-47

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The applications for amendment by Duke Power Company (the licensee) dated March 18 and May 15, 1981, comply' with the standards and.requirements of

-the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized bythis amendment can be conducted without endangering the health-and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's reaulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes to License Conditions 3.B and 3.E. and to the Technical Specifications as indicated in the attachment to this license amendment. Paraqraphs 3.8. and 3.E. of Facility Operating License No. DPR-47 are hereby amcnded to read as follows:
3. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

-2

3. E. Fire Protection The licensee is authorized to proceed with and is required to complete the modifications identified in Table 3.1 of the NRC's Fire Protection Safety Evaluation Report on the Oconee Nuclear Station dated August 11, 1978, and as subsequently amended.

The modifications shall be completed on the schedule specified in Table 3.1, except for Item 3.1.14, "Dedicated Safety Shutdown Facility", which shall be completed 30 months after NRC approval of design..

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION YJo n F. Stolz, Chi erating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 9, 1901

REo1 UNITED STATES 0

NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.. 50 207 OCONEE NUCLEAR STATION, UNIT 10. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-55

1. The Nuclear Regulatory Commission (the Coimmission) has found that:

A.

The applications for amendment by Duke Power Company (the licensee) dated March 18 and May 15, 1981, comply with the standards and requirements of the Atomic Energy Act of 1954,. as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;.

B. The. facility will operate in conformity with the applications, the pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.

2. Accordingly, the license is amended by changes te License Conditions 3.B and 3.E. and to the Technical Specifications as indicated in the attachment to this license amendment. Paraqraphs 3.8. and 3.E. of Facility Operating License No. DPR-55 are hereby amended to read as fo lows:

3B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised.through Amendment No. 95,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.E. Fire Protection The licensee is authorized to proceed with and is required to complete the modifications identified in Table 3.1 of the NRC's Fire Protection Safety Evaluation Report on the Oconee Nuclear Station dated August 11, 1978, and as subsequently amended. The modifications shall be completed on the schedule specified in Table 3.1, except for Item 3.1.14, "Dedicated Safety Shutdown Facility", which shall be completed 30 months after NRC approval of design.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chief erating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June I, 1931

ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 9 TO DPR-38 AMENDMENT NO.

98 TO DPR-47 AMENDMENT NO.

95 TO DPR-55 DOCKETS NOS.

50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.

Remove Pages Insert Pages vi vi 3.17-1 3.17-1 3.17-2 3.17-2 3.17-3 3.17-3 3.1 7-4 3.17-4 3.17-5 3.17-5 3.17-6

3.

17-7 3.17-8 3.1 7-9 4.19-1 4.19-1 4.19-2 4.19-2

LIST OF:TABLES Table No.

Page 2.3-1A Reactor Protective System Trip Setting Limits - Unit 1 2.3-11 2.3-1B Reactor Protective System Trip Setting Limits -

Unit 2 2.3-12 2.3-1C Reactor Protective System Trip Setting Limits - Unit 3 2.3-13 3.5.1-1 Instruments Operating Conditions 3..5-4 3.5-1 Quadrant Power Tilt Limits 3.5-14 3.17-1 Fire Protection & Detection Systems 3.17-5 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Test Frequency 4.1-9 4.1-3 Minimu:; Sampling Frequency 4.1-10 4.2-1 Oconee Nuclear Station Capsule Assembly Withdrawal Schedule 4.2-3 at Crystal River Unit No. 3 4.11-1 Oconee Environmental Radioactivity Monitoring Program 4.11-3 4.11-2 Offsite Radiological Monitoring Program 4.11-4 4.11-3 Analytical Sensitivities 4.11-5 4.17-1 Steam Generator Tube Inspection 4.17-6 4.18-1 Safety Related Shock Suppressors (Snubbers) 4.18-3 6.1-1 Minimum Operating Shift Requirements with Fuel in Three 6.1-6 Reactor Vessels 6.6-1 Report of Radioactive Effluents.

6.

6-8 Amendments Nos. 98, 98 & 95 Vi

3.17 FIRE PROTECTION AND DETECTION SYSTEMS Aoplicability This specification applies to the operability of fire protection and detection systems when equipment protected by those systems is required to be operable.

Objective To assure the operability of fire protection and detection systems which pro tect systems and equipment required for safe shutdown.

Soecification 3.17.1 The minimum fire detection instrumentation for each fire detection zone shown in Table 3.17-1 shall be operable. The fire detection instruments located within the containment are not required to be operable during the performance of Type A Containment Leakage Rate Tests.

When this specification is determined not to be met, appropriate action shall be taken consisting of one or more of the following:

1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a fire watch patrol shall be established to in spect an accessible zone with the inoperable instrumentation at least once per hour.
2. The inoperable instrumentation shall be restored to operable status within 14 days or a report shall be submitted to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrumentation to operable status.

Continued operation of the affected unit is permitted provided that this condition is met. Operation under this specification is not considered to be in a degraded mode and thus is not reportable under Technical Specification 6.6.2.1.b (2).

3.17.2 The Fire Suppression Water System shall be operable. This system shall consist of '2 High Pressure Servien Water (HPSW) pumps with a design capacity of 6000 gpm each and automatic initiation logic, and the associated piping and valves supplying water to the sprinkler systems and fire hose stations.

The KPSW pumps shall.be aligned to the high pressure fire header. When this specification.is determined not to be met, appropriate action shall be taken con sisting of the following:

1. The inoperable equipment shall be restored to operable sta tus within 7 days or a report shall be submitted to the. Commis sion within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

Continued operation of the.affected.unit is permitted provided that this condition is met. Operation under this specification is not considered to be in a degraded mode and thus is not reportable under Technical Specification 6.6.2.1.b (2).

3.17-1 Amendments Nos.

9F, 98 & 95

2. With do Fire Suppression Water System operable, in lieu of the above, the following action shall be taken.
a. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a backup Fire Suppression Water System shall be established. If a backup Fire Suppression Water System cannot be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place the reactor in Hot Standby within the next twelve (12) hours and in cold shutdown within the following forty-eight (48) hours.
b. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the Commission shall be notified by tele phone, and in writing no later than the first working day following the event.
c. Within 14 days of the event, a report shall be submitted to the Commission outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

3.17.3 The sprinkler and spray systems in safety related areas listed in Table 3.17-1 shall be operable. If a system is determined to be inoperable, the following corrective action shall be taken.

1. A continuous fire watch with backup fire suppression equipment shall be established in the area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2. The sprinkler or spray system shall be restored to operable status within 14 days or a report shall be submitted to the Commission within the next 30 days outlining the cause of in operability and the plans for restoring the system to operable status.

Continued operation of the affected unit.is permitted provided that this condition is met. Operation under this speci fication is not considered to be a degraded mode and thus is not reportable under Technical Specification 6.6.2.1.b (2).

3.17.4 The automatic CO2 system provided for the generators at the Keowee Hydro Station shall be operable. If the system is determined to be inoperable the following corrective action shall be taken:

1. A continuous fire.watch with backup fire suppression equipment shall be established in the area withir, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2. The COZ system shall be restored to operable status with in 14 days or a report shall be submitted to the Commission within the next 30 days outlining the cause of inoperability and the plans for restoring the system to operable status. Con tinued operation of the affected reactor unit is permitted provided that this condition is met. Operation under this speci fication is not considered to be in a degraded mode and thus is not reportable under Technical specification 6.6.2.1.b.(2).

3.17-2 Amendments Nos.

92, 90 & 95

3.17.5 The fire hose stations listed in Table 3.17-1 shall be operable or the following action shall be taken:

1. If a fire hose station listed in Table 3.17-1.is inoperable, an additional equivalent capacity fire hose of length sufficient to reach the unprotected area shall be provided at an operable hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2. If the inoperable fire hose station cannot be restored to operable status within 14 days, continued operation of the affected unit is permitted provided that within the next 30 days a report is submitted to the Commission outlining the cause of the inoperability, actions taken, and the plans for restoring the system to operable status.

Operation under this specifica tion is not considered to be a degraded mode and is not report able under Technical Specification 6.6.2.1.b(2).

3.17.6 All fire barrier penetrations (including cable penetration barriers, fire doors, fire dampers) protecting safety related areas.shall be operable.

If a fire barrier protecting a safety-related area is determined to be inoperable, the operability status of the fire detection instru mentation for the affected safety related area(s) shall be determined within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and the following action shall be taken:

1. If the fire detection instrumentation for the affected area(s) is operable, a fire watch patrol shall be established to inspect the area at least once per hour.
2. If the fire detection instrumentation is inoperable, a contin uous fire watch shall be established within the next hour on at least one side of the affected penetration fire barrier. The non-functional fire barrier penetration(s) shall be restored to functional status within 7 days.
3. If the non-functional fire barrier penetration(s) cannot be re stored to functional status within., days, continued operation of the affected unit is permitted provided that within the next 30 days, a report is submitted to~the-Commission outlining the cause of the inoperability and the plans for restoring the sys tem to operable status.

Operation under this specification is not considered to be a degraded mode and is not reportable under Technical Specification 6.6.2.1.b(2).

Bases Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equip ment and is an integral element in the overall facility fire protection program.

3.17-3 Amendments Nos. 98, 98 & 95

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

The operability of the fire suppression systems ensures that adequate fire sup pression capability is.

available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system spray and/or sprinklers, fire hose stations, and penetration fire barriers. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be. taken since this system provides.the major fire suppression capability of the plant.. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the nuclear plant.

The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when a barrier is not functional, a fire watch patrol will be required to inspect the affected area frequently as a precaution in addition to the fire detection instrumentation in the area.

If fire detec tion instrumentation.in the area is not operable, a continuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

3.17-4 Amendments Nos. 93,.9 & 95

TABLE 3.17-1 A.

Fire Detection Instrumentation REACTOR CONTAINMENT DETECTORS ELEV UNIT EOUIPMENT/LOCATION PROTECTED PROVIDD/OPERABLE 796, 850 1

Reactor Bldg Penetrations 2 Strings (1 String (8 Detectors)/

4 Deteor 845 1

Reactor -Coolant Pumps 2 Strings 1 String 8 Detectors 4 Detectors) 830 1

Reactor Bldg Cooling Units 2 Strings 1 String (6 Detectors J/3 Detectors 796 2

Reactor Bldg Penetrations 2 Strings 1 String Detectors 4 Dececto-s) 796 2

Reactor Coolant Pumps 2 Strings 1 String

\\8 Detectors,J4 Detectors) 796 2

Reactor Bldg Cooling Units 2 Strings 1 String (6 Detectors //3 Detectors) 796 3

Reactor 3ldg Penetrations 2 Strings I String (8 Detectors/

\\4 Detectors 796 3

Reactor Coolant Pumps 2 Strings 1 String (8 Detectors/

\\4 Detectors) 796 3

Reactor Bldg Cooling Units 2 Strings 1 String (6 Detector s/

Detectors BLOCKHOUSE 796 1-2 Switchgear Bit,.B2T 2/1 796 1-2 CT-4 Transformer 2/1 796 3

Switchgear 3Blt, 3B2T 271 4160 VOLT SWITCHGEAR 796 1

4160V Switchgear (1TC,

ITD, 2/1 1TE) 796 2

4160V Switchgear (2TC,

2TD, 2/1 ITE) 796 3

4160V Switchgear (3TC,

3TD, 2/1 3TE)

MIERGENCY FEED WATER PUMP TURBINE 771 1

EFWP Turbine 1/1 771 2

EFWP Turbine 1/1 3.17-5 Amendments Nos.

98, j3 & 95

TABLE 3.17-1 (cont'd)

DETECTORS ELEV UNIT EQUIPMNT/LOCATION PROTECTED PROVIDED/OPERABLE 771 3

EFWP Turbine 1/1 CABLE ROOM 609 1

Cable Room 6/4 809 2

Cable Room 6/4 809 3

Cable Room 7/4 PUMP ROOMS 758 1

Between LPI Pumps 1A&lC 1/1 758 1-2 Between LPI Pumps 13&23 1/1 758 2

Between LPI Pumps 2A&2C 1/1 758 3

LPI 3A Pump 1/1 758 3

Betw-een LPI Pumps 3B&3C 1/1 758 1

Between HPI Pumps 1A&iB 1/1 758 1-2 Between HPI Pumps 1C&2C 1/1 758 2

Between HPI Pumps 2A&2B 1/1 758 3

HPI Pump 3C 1/1 758 3

Between HPI Pump 3A&3B 1/1 PENETRATION ROOMS 822 1

East Penetration Room 3/2 809 1

Above MCC's (lU,

1XI, lXJ) 3/2 822 2

East Penetration Room 3/2 809 2

Above KC's (2R, 2XI, 2XJ) 3/2 822 3

East Penetration Room 5/3 822 1

West Penetration Room 3/2 822 1

West Penetration Room 3/2 822 3

West Penetration Room 3/2 CONTROL ROOMS 822 1-2 Control Room Area (Includes 9/6 Computer Room, I&E Shop, Baily Cabinet) 3.17-6 Amendments Nos. 93, 93 & 95

TABLE 3.17-1 (cont'd)

DETECTORS ELEV UNIT EOUIPMENT/LOCATION PROTECTED PROVIDED/OPERABLE 822 3

Control Room Area (Includes 7/4 Computer Room, Electrical Shop, Bailey Cabinet)

CABLE SHAFT 822 1

Unit 1 Cable Shaft 1/1 822 2

Unit 2 Cable Shaft 1/1 822 3

Unit 3 Cable Shaft 1/1 833 3

Cable Shaft 5th Floor 1/1 BATTERY ROOM 809 3

Control Battery Room 2/1 KEOVEE HYDRO STATION 700 Control Room 4/2 688 Battery Room 4/2 700 Mechanical Equipment Gallery 3/2 700 Main Lube Oil Storage Room 1/1 701 Generator #1 6/4 701 Generator #2 6/4 710 Operating Floor 6/4 B.

Sorinkler And Sorav Systems SPRINKER SYSTEMS Turbine Driven Emergency FDW Pump Units 1, 2,and 3 Transformers CT-1 CT-2 CT-3 CT-4 CT-5 A3.17-7 Amendments Nos.- 9V, 9A Z. 95.

TABLE 3.17-1 (cont'd)

SPRINKLER SYSTEMS Cable Room Units 1, 2, and 3 Equipment Room Units 1, 2, and 3 Cable Shaft (3rd Level)

Units 1, 2, and 3 Cable Shaft (4th & 5th Level)

Units 1, 2, and 3 EMULSIFIRE/SPRAY SYSTEMS Keowee Hydro Station Main Lube Oil Storage Room Main Transformer C. Fire Hose Stations Location No.

Valve No.

Area or Component Protected 3-D-28 1HPSW-194 1&2 Blockhouse, 1&2 3rd Floor Switchgear AX-34 1hPSW-437

  1. 1 Cable Spread Room AX-35 IHPSW-436
  1. 1 Cable Spread Room AX-33 2HPSW-436
  1. 2 Cable Spread Room AX-32 2HPSW-437
  1. 2 Cable Spread Room AX-30 3EPSW-436
  1. 3 Cable Spread Room AX-31 3BPSW-437
  1. 3 Cable Spread Room 5-M-31 2HPSW-304 1&2 Control Room, 1&2 Emergency Shutdown Panels TOH-3 3HPSW-338 2 Control Room, #3 Emergency Shutdown Panel 1-J-28 2HPSW-242
  1. 1 First Floor Motor Control Centers, HPSW Pumps, 1&2 LPSW Pumps 1-J-43 3HPSW-345
  1. 3 1st Floor Motor Control Centers 1-B-19 1HPSW-163
  1. 1 EFWP 1-D-39 2HPSW-246
  1. 2 EFWP 1-D-53 3HPSW-336 43 ETWP AX-23 1HPSW-438
  1. 1 Equipment Room AX-24 1HPSW-439
  1. 1 Equipment Room AX-25 2HPSW-438
  1. 2 Equipment Room AX-26 2HPSW-439
  1. 2 Equipment Room AX-27

\\3HPSW-438

  1. 3 Equipment Room AX-28 3HPSW-439
  1. 3 Equipment Room AX-13 1HPSW-448 1&2 HPI Pumps, 1&2 LPI Pumps AX-14 1HPSW-449 3 HPI Pumps, 3 LPI Pumps 1-J-47 3HPSW-349 3 LPSW Pumps AX-36 IHPSW-445
  1. 1 West Penetration Room AX-45 1HPSW-444
  1. 1 East Penetration Room AX-42 2HPSW-444
  1. 2 East Penetration Room AX-43 2HPSW-445
  1. 2 West Penetration Room AX-29 3HPSW-444
  1. 3 East Penetration Room AX-44 3HPSW-445
  1. 3 West Penetration Room Amendments tros.

98, 98 & 95 3.17-8

TABLE 3.17-1 (cont'd)

C.

Fire Hose Stations Location No.

Valve No.

Area or Component Protected 3-J-28 2KPSW-241 1&2 3rd Floor Switchgear 3-M-43 3HPSW-339 3 3rd Floor Switchgear, 600V Load Center AX-22 1HPSW-440 I Battery Room AX-20 2HPSW-440 2 Battery Room AX-18 3HPSW-440 3 Battery Room Keowee Hydro Station Operating Deck (NW)

NA Operating Floor Operating Deck (NE) NA Operating Floor Operating Deck (SW) NA Operating Floor Operating Deck (SE) NA Operating Floor Control Room NA Control Room Mechanical Equip ment Gallery NA Mechanical Equipment Gallery 3.17-9 Amendments Nos. 98, 98 & 95

4.19 FIRE PROTECTION AND DETECTION SYSTEM Applicability This specification applies to fire protection and detection systems which protect systems and equipment required for safe shutdown.

Objective To verify the operability of fire protection and detection systems.

Specification 4.19.1 Fire Detection Systems

a. Each of the fire detection. instruments listed in Table 3.17-1 shall be tested for operability at least once per 6 months by performance of a Channel Functional Test, except as noted in part b.
b. The testing interval for detectors specified in Table 3.17-1 which are inaccessible during power operation may be extended until such time as the detectors become accessible for a mini mum of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The testing interval shall not extend past a refueling outage.

4.19.2 The Fire Suppression Water System shall be documented operable as follows:

a. Monthly
1. A functional test of the high pressure service water pump and associated automatic valve shall be performed.
2. Proper alignment of valves shall be verified.
3. A visual inspection of the fire hose stations listed in Table 3.17-1 shall be performed.
b. Annually
1. Each high pressure service water pump shall be tested to verify flow of 3000 gpm.
2. The sprinkler systems listed in Table 3.17-1 which pro tect safety-related systems shall be functionally tested, except in the cable spreading rooms, equipment rooms, and cable shafts.
3. The sprinkler system spray headers and nozzles, listed in Table 3.17-1, which protect safety-related systems, shall be inspected.

4.19-1 Amendments Nos. 98, 98 & 95

4. The fire hose stations shall receive a maintenance inspection to include removal and reracking of the hoses and inspection of coupling gaskets.
c. Refueling
1. A visual inspection of each nozzle's spray area will be conducted to verify the spray pattern is not obstructed.
d. At least once per 3 years:
1. A system flow test shall be performed on the fire suppres sion water system in accordance with Chapter 5,Section II of the Fire Protection Handbook, 14th Edition, NFPA.
2. The fire hose station valve listed in Table 3.17-1 shall be partial-stroke tested.
3. Each. fire hose shall be subjected to a hydrostatic test at a pressure at least 50 psig greater than the maximum pres sure at the station.

4.19.3 The high pressure COZ System for the generators at the Keowee Hydro Station shall be demonstrated operable as follows:

a. Monthly
1. Each valve in the flow path will be verified to be in its correct position.
b. Semiannually
1. The CO2 storage tank weight shall be verified to be at least 90% of the full charge weight.
c. Refueling
1. The system shall be verified to actuate manually and auto matically, upon receipt of a simulated action signal.
2. A flow test will be performed through headers and nozzles to assure no blockage.

4.19.4 Penetration fire barriers which protect safety-related equipment shall be verified functional by visual inspection at a refueling frequency and prior to declaring a penetration fire barrier functional following repairs or maintenance.

Amendments Nos. 98, 98 & 95 4.19-2

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