ML20249C809

Amend 20 to License NPF-38,changing TS as Indicated in Attachment to License Amend & Paragraph 2.C(2)

ML20249C809
Person / Time
Site:	Waterford
Issue date:	07/21/1987
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20249C787	List: ML20249C786 ML20249C790 ML20249C800 ML20249C802 ML20249C809 ML20249C813
References
NUDOCS 9807010225
Download: ML20249C809 (6)

Text

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/ o g UNITED STATES

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NUCLEAR REGULATORY COMMISSION a WASHINGTON, D. C. 20555

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i LOUISIANA POWER AND LIGHT COMPANY

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DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-38

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

A. The application for amendment by Louisiana Power and Light Company (the licensee) dated January 13, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations l set forth in 10 CFR Chapter I;

! B. The facility will operate in conformity with the application, l the pro' visions of the Act, and the rules and regulations of the Commission; C.

i There is reasonable assurance (i) that the activities authorized by thit amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i D. The issuance of this amendment will not be inimical to the l common defense and security or to the health and safety of the l' public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable j requirements have been satisfied.

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9807010225 980629 DR ADOCK 05

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

l NPF-38 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION

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Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 21,1987 1

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1 ATTACHMENT TO LICENSE AMENDMENT NO. 20 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications l with tre attached pages. The revised pages are identified by Amendment l number and contain vertical lines indicating the areas of change. The i corresponding overleaf pages are also provided to maintain document  !

completeness.

i Remove Insert l 3/4 3-48a B 3/4 3-3 8 3/4 3-3 8 3/4 3-3a B 3/4 3-3a J

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INSTRUMENTATION-CHEMICAL DETECTION SYSTEMS BROAD RANGE GAS DETECTION LIMITING CONDITION FOR OPERATION i

3.3.3.7.3 Two' independent broad-range gas detection systems shall be operable I with their alarm / trip setpoints' adjusted to actuate at the lowest achievable' '

'IDLH gas concentration level of detectable toxic gases providing reliable l

operation. 3' APPLICABILITY: All MODES.

ACTION:

a. With one broad range gas detection system inoperable, restcre the-inoperable detection system to.0PERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room l ventilation system in the recirculation mode of operation.

b. With no broad range gas detection system OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room ventilation l l system in the recirculation mode of operation.

c. The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS I

l 4,3.3.7.3 Ea: broad range gas detection system shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL

, FUNCTIONAL TEST at least once per 31 days and a channel calibration at least l -once per 7 days. Calibration will consist of the introduction of a standard gas and adjusting the' instrument sensitivity based on the calibration gas relationship of the standard gas to the calibrating gas.

L WATERFORD - UNIT 3 3/4 3-48a AMENDMENT NO. 20

INSTRUMENTATION BASES 3/4.3.3.6 ACCIDENT HONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." Table 3.3-10 includes Regulatory Guide 1.97 Category I key variables. The remaining Category I variables are included in their respective specifications.

The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the Core Exit Thermocouple (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post THI-2 Action Plan.

The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to existence of, and recovery from ICC. Additionally, they aid in tracking reactor coolant inventory. These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37. These are not recuired by the accident analysis, nor to bring the plant to Cold Shutdown.

In the event more than four sensors in a Reactor Vessel Levol channel are inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and reactor vessel head are removed. It is not feasible to repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core. If only one channel is inoperable, it should be restored to OPERABLE status in a refueling outage as soon as reasonably possible. If both channels are inoperable, at least one channel shall be restored to OPERABLE status in the nearest refueling outage.

3/4.3.3.7 CHEMICAL DETECTION SYSTEMS The chemical detection systems are the ammonia, chlorine, and broad range toxic gas detection systems.

The OPERABILITY of the chemical detection systems ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chemical release.

The chemical detection systems provide prompt detection of toxic gas re-leases which could pose an actual threat to safety of the nuclear power plant or significantly hamper site personnel in performance of duties necessary for the safe operation of the plant.

The broad range toxic gas detection system operates on the principle of gas photoionization, and therefore, the system is sensitive to a broad range of gases. The system is therefore sensitive to both atmospheric and chemical composition normal fluctuations affecting the Waterford 3 site. The setpoint WATERFORD - UNIT 3 B 3/4 3-3 AMENDMENT N0. J#, 20

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' I INSTRUMENTATION BASES for the system is thus based on testing and operating experience, and the set-point is set at the lowest achievable IDLH gas concentration providing reliable operation and the optimum detection of toxic gases. The setpoint is therefore subject to change wherein necessitated by o'erating experience such as a result of changes in the Waterford 3 area chemicai atmospheric profile. The setpoint is established and controlled by procedure. ,

3/4.3.3.8 FIRE DETECTION INSTRUMENTATION l

OPERABILITY of the fire detection instrumentation ensures that adequate 4 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 detaction of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

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.

l 3/4.3.3.9 LOOSE-PART DETECTION INSTRUMENTATION  !

The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability.is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and Surveillance Requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection l l

Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

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WATERFORD - UNIT 3 B 3/4 3-3a AMENDMENT NO. U , 20