ML20236G861

Amend 86 to License DPR-54,revising Tech Specs 3.1.6, Leakage & 3.8, Fuel Loading & Refueling Re Requirements for Monitoring Airborne Radioactivity Inside Containment

ML20236G861
Person / Time
Site:	Rancho Seco
Issue date:	10/23/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236G854	List: ML20236G851 ML20236G861 ML20236G879
References
NUDOCS 8711030323
Download: ML20236G861 (6)

Text

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![s  % UNITED STATES NUCLEAR REGULATORY COMMISSION

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SACRAMENTO MUNICIPAL UTILITY DISTRICT +

DOCKET NO. 50-312

, RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 '

License No. DPR-54 1

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

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A. The application for amendment by Sacramento Municipal Utility '<

l. District (the licensee) dated February 20, 1987, as supplemented June 2, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the i

provisions of the Act, and the 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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, 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licerst amendment, and paragraph 2.C.(2) of Facility Operating License No. DPF-54 is hereby amended to read as follows:

(2) Technical Specifications

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The Technical Specifications contained in Appendices a A and B, as revised, through Amendment No. 86, are hereby incorporated irq the license. The licensee shall operate'the facility in neardance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMhfiSSION N. <.

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.,fst'd f Georgeht Knighton, irector 1

( Project Directorate V Divisior/, of ' Reactor Projects - III, c/ IV, % and Special Projects

Attachment:

Changes to the Technical '

Specifications Date of Issuance: October 23, 1987 i

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October 23, 1987' i

ATTACHMENT TO LICENSE AMENDMENT NO. '86 FACILITY OPERATING LICENSE NO. OPR-54 l DOCKET N0. 50-312 .

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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified >y Amendment number and contain vertical lines indicating the area of change.

I Remove Insert 3-13a

• 3-14 3-14 3-14a 3-14a 1 3-45 3-45 i

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• The text of this page now appears on Page 3-14 and has not changed.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation ;

i Bases (continued)

When the source of leakage has been identified, the situation can be )

evaluated to determine if operation can safely continue. This evaluation will be performed by the Operating Staff and will be documented in writing and approved by the Superintendent. Under these conditions, an allowable reactor coolant system leakage rate of 10 gpm has been established. This explained leakage rate of 10 gpm is also well within the capacity of one high pressure injection pump and makeup would be available even under the loss of off-site power condition.

If leakage is to the Reactor Building it may be identified by one or more of the following methods:

A. Sump Levels - All Reactor Building leakage is collected in the Reactor Building sumps. These sumps drain by gravity into a 120 gallon Reactor Building drain accumulation tank. The drain accumulation tank is used to measure the drain flow with level indicators at 20 gallons and 120 gallons. The tank is dumped into the East decay heat removal pump room sump. The frequency of dumping the accumulation tank and time interval between levels are recorded in the Control Room and are direct measures of the flow rate. Depending on the level at which the tank is dumped, the time to confirm a 1 gpm leak is between 40 minutes and 120 minutes.

Frequency of oraration of the East DHR pump room sump pumps is recorded in the antrol room to provide verifica' tion of proper operation of the Ructor Building drain accumulation tank.

Since the Reactor Building drain system collects drainage from all components in the Reactor Building, a change in drain flow does not necessarily indicate a reactor coolant system leak. One method available for determining if the additional drain flow is reactor coolant is to collect drainage in the drain accumulation tank, draw a sample from the tank, and analyze the sample for boric acid concentration and radioactivity.

B. Radioactivity - Changes in the reactor coolant leakage rate in the Reactor Building may cause changes in the control room indication of the Reactor Building atmosphere particulate radioactivity.

The response time for the radiation monitor to detect a given leak rate is dependent on the coolant activity level, building equilibrium level, and the detector sensitivity. The radiation detection monitor's particulate channel has the ability to detect a small unidentified leak of approximately 1 gpm in approximately one hour. This is a qualitative leak detection method and the actual leakage rate can be determined from the other detection systems.

Amendment No.13,86 3-14

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS )

Limiting Conditions for Operation V

C. -Reactor Coolant Inventory - Total reactor coolant system leakage i rate is periodically determined by comparing indications of reactor I power, coolant temperature, pressurizer water level and makeup tank level over a time interval. All of these indications are recorded. .

Since the pressurizer level is maintained essentially constant by  !

the pressurizer level controller, any coolant leakage is replaced by I coolant from the makeup tank resulting in a tank level decrease.

TN makeup tank capacity is 31 gallons per inch of height and each graduation on the level recorder represents 1 inch of tank height. 1 This inventory monitoring method is capable of detecting changes on {

the order of 31 gallons. A 1 gpm leak would therefore be detectable '

within approximately one-half hour.

As described above, in addition to direct observation, the means of detecting reactor coolant leakage are based on two different.

principles, i.e., activity and sump level and reactor coolant i inventory measurements. Two systems of different principles provide, therefore, diversified ways of detecting leakage to the reactor building.

The upper limit of 30 gpm is based on the contingency of a complete loss of plant power. A 30 gpm loss of water in conjunction with a complete loss of plant power and subsequent cooldown of the reactor coolant system by the turbine bypass system (set at 1,040 psia) and steam driven emergency feedwater pump would require more than 60 minutes to empty the pressurizer from the combined effect of system leakage and contraction. This will be ample time to restore electrical power to the plant and makeup flow to the reactor coolant system.

The plant is expected to be operated in a manner such that the secondary coolant will be normally maintained within those. chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is consistently not maintained within these chemistry limits, over some period of time localized corrosion could occur and might result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 1 GPM). Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 1 GPM can be detected by monitoring the secondary coolant. Leakage in excess of this limit will require plant shutdown during which the leaking tubes will be located and plugged.

Amendment No. m 86 3-14a

l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l Limiting Conditions for Operation 3.8.8 When two irradiated fuel assemblies are being handled simultaneously within the fuel transfer canal, a minimum of 10 feet separation shall L

' be maintained between the assemblies at all times. Irradiated fuel assemblies may be handled with the auxiliary bridge crane provided no other irradiated fuel assembly is being handled in the fuel transfer canal.

3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.

3.8.10 The Reactor Building purge system, including the reactor building stack radiation fronitor, shall be tested and verified to be operable immediately prior to refueling operations.

3.8.11 Irradiated fuel shall not be removed from the reactor until the unit has been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.8.12 No loads will be handled over irradiated fuel stored in the spent fuel pool, except the fuel assemblies themselves. A dead weight load test at the rated load will be performed on the Fuel Storage Building handling bridge prior to each refueling.

Bases Detailed written procedures will be available for use by refueling personnel. These procedures, the above specifications, and the design of the fuel handling equipment, as described in subsection 9.7 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur during tne refueling operations that would result in a hazard to public health and safety. If no change is being made in ccre geometry, one flux monitor is sufficient. This pen 111ts maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux j provides irnmediate indication of an unsafe condition. j pump is used tc maintain a uniform boron concentration.{he decay heat removal The refueling {

boron concentration indicated in Specification 3.8.4 will be maintainea to ensure that the more restrictive of the following reactivity conditions is {

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1. Either a keff of 0.95 or less with all control rods removed from the core.

2. A boron concentration of 11800 ppm.

The actual calculated boron concentration for item (1) above is 1974 ppm boron. Specification 3.8.5 allows the control room operator to inform the i Reactor Building personnel of any impending unsafe condition detected f rom l the main control board indicators during fuel movement. '

The specification requiring testing Reactor' Building purge termination is to verify that these components will function as required should a fuel her.dling '

accident occur that results in the release of significant fission products.

Amendment No. 79, /J, 89, 86 3-45