ML20202B534

Amend 98 to License DPR-40,revising Sections 2 & 3 of Tech Specs to Incorporate Operability & Surveillance Requirements for New Fire Suppression Equipment in Compressor Room

ML20202B534
Person / Time
Site:	Fort Calhoun
Issue date:	07/01/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20202B517	List: ML20202B512 ML20202B534 ML20202B541
References
TAC-61237, NUDOCS 8607100325
Download: ML20202B534 (6)

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[ o,, UNITED STATES E o NUCLEAR REGULATORY COMMISSION

E WASHINGTON. D. C. 20555 o t

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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING L-ICtNSE Amendment No.98 License No. OPR-40

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

A. The application for amendment by the Omaha Public Power District (the licensee) dated April 9, 1986 complies 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 application, the provisions 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 satisfied.

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8607100325 860701 PDR P ADOCK 05000285 PDR

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this i

license amendment, and paragraph 3.8. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

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

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

FOR THE NUCLEAR REGULATORY COMMISSION ihhdA 0Av

• e Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical i Specifications Date of Issuance: July 1, 1986 i

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. gg FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating

the area of change.

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4 Remove Pages Insert Pages 2-91 2-91 i 3-81 3-81 i

3-83 3-83 i ,

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2.0 LIMITIf4G C0t4DITI0t45 FOR OPERATION 2.19 Fire Protection System (Continued)

(3) The provisions set forth in Section 2.19(2) do not apply to time periods during which Containment Integrated Leak Rate Tests are being performed.

(4) Fire suppression water system shall be operable, except during system testing, jockey pump maintenance or training (not to exceed 7 consecutive days) with both fire pumps, each with a minimum capacity of 1800 gpm, with their discharge aligned to the fire suppression header and automatic initiation logic for each fire pump.

a. With less than the above required equipment:

(i) restore the inoperable equipment to operable status within 7 days.

(ii) if equipment is not restored to operable status within 7 days, prepare and submit a report to the Nuclear Regulatory Commission, pursuant to Section 5.9.3. i of the Technical Specifications, within the next 30 days, outlining the plans and procedures to be used to provide for the loss of the system and the cause of the malfunction.

b. With no fire suppression water system operable:

(i) establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(ii) notify the Nuclear Regulatory Commission, pursuant to Section 5.9.2.a of the Technical Specifications, outlining the cause of the malfunction, the actions taken, and the plans and schedule for restoring the system to operable status.

(iii) If (i) above cannot be fulfilled, place reactor in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following thirty (30) hours.

(5) The sprinkler system in the Diesel Generator Rooms, the sprinklers above the steam driven auxiliary feedwater pump, the sprinkler / spray nozzle system in the compressor room, and the deluge system in the personnel corridor between fire areas 6 and 20 shall be operable except during system testing. If inoperable:

a. Within one hour establish a continuous fire watch with backup fire extinguishing equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol, i

i Amendment tio. /E,EJ,98 2-91 4

3.0 SURVEILLANCE REQUIREMENTS 3.15 Fire Protection System (Continued)

3. Verify that each fire pump starts automatically on low fire system pressure to maintain the fire suppression water system pressure >100 psig.

e. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association using a clean water source.

f. At least once per year by visually inspecting the strainer on the discharge side of the fire pumps to verify operability.

(3) The sprinkler system in the Diesel Generator Rooms, the sprinklers above the steam driven auxiliary feedwater pump, the sprinkler / spray nozzle system in the compressor room, and the deluge system in the personnel corridor between fire areas 6 and 20 shall be demonstrated to be oprable:

a. At least once per 18 months

1. By visual inspection of the spray / sprinkler headers to verify their integrity.

2. By visual inspection of each spray / sprinkler nozzle to verify no blockage and no obstruction of the spray area.

3. By performing a system functional test which includes simulated automatic actuation of the system and verifies that all automatic valves actuate to their correct position.

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

, head spray / sprinkler nozzle is unobstructed.

(4) Each fire hose station designated in Table 2-8 shall be verified to be operable:

a. At least once per month by visual inspection of the station to assure all equipment is available and the system pressure (as determined at the jockey pump pressure gauge) is within limits,

b. At least once per 18 months by removing the hose for inspection and reracking and replacing any degraded gaskets in the couplings.

c. At least once per 3 years by:

1. Partially opening the hose station valves to verify valve operability and no blockage.

Amendment No. 40, D ,98 3-d1

3.0 SURVEILLANCE REQUIREMENTS 3.15 Fire Protection System (Continued) l

b. At least once every 6 months by verifying each halon storage tank pressure and weight or level.

c. At least once every 18 months by:

1. Verifying the system, including associated ventilation dampers (if applicable), is actuated by a simulated test signal. Manual and automatic test signals will be alternated every 18 months.

2. Visual inspection of spray headers to verify integrity.

3. Visual inspection of all nozzles to ensure no blockage.

d. At least once every three years by performing an air flow test through each header and nozzle to assure no blockage.

(9) Battery powered smoke detectors in control room cabinets and consoles shall be demonstrated OPERABLE by performance of an operational test performed using a built-in test device at least semi-annually.

Basis The fire protection system provides a means for detecting, alarming, and extinguishing plant fires. The system is divided into the fire detection subsystem and fire extinguishing subsystem.

The fire detection subsystem is an instrumentation system which alarms control room operators of a fire, indicating fire location on a panel in the control room, and providing local indication from the detector in the affected zone.

The fire extinguishing system includes the sprinklers which protect the Diesel Generator Rooms. Also included are the hose stations which protect the immediate vicinity outside the entire plant, hose cabinets inside the intake structure, and other miscellaneous equipment.

Maintaining the operability of the fire protection system under various operating conditions is eesential to insure the integrity f various nuclear safety-related plant systems and equipment. The above surveil-lance measures aid in accomplishing this objective.

Specification 3.15(2)f provides a surveillance program that insures that silt and other material in the river water will not prevent the delivery of water to areas protected by fire water suppression systems.

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Amendment No. 40,$3,gg 3-83

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